radioactive waste management profiles · regulates radioactive waste, the laws and regulations that...

Radioactive Waste Management Profiles a Compilation of Data from the

Net Enabled Waste Management Database (NEWMDB)

No . 4*

INTERNATIONAL ATOMIC ENERGY AGENCY

November 2002

*Previous publications in this series contained reports on data collected and managed by the IAEA in its Waste Management Database (WMDB), which was superseded by the NEWMDB in 2001.

EDITORIAL NOTE

Staff of the IAEA prepared this report based on data submitted by IAEA Member States to the Agency’s Net Enabled Waste Management Database (July 2001 to March 2002). The accuracy and completeness of the information in this report is directly related to the quality of the information provided by authorized representatives from Member States.

Throughout the text, names of Member States are retained as they were when the text was compiled.

The use of particular designations of countries or territories does not imply any judgment by the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries.

The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA.

Table of Contents

Note: Click on a row in the following list to view the identified PDF file

or click on one of the bookmarks in the list to the left Contacting the IAEA................................................................................... CONTACT.PDF

Foreword .................................................................................................. FOREWORD.PDF

Introduction ..................................................................................... INTRODUCTION.PDF

Overview Reports ................................................................................... OVERVIEWS.PDF Indicator of Sustainable Development for Radioactive Waste Management Consolidated Radioactive Waste Inventory Status and Trends in Radioactive Waste Management The Joint Convention and the NEWMDB Scorecard for National Systems for Radioactive Waste Management

Guide to Reading Profile Reports..................................................................... GUIDE.PDF

Country Waste Profile Reports.................................................................. PROFILES.PDF

Glossary...................................................................................................... GLOSSARY.PDF

CONTACTING THE IAEA For information about the NEWMDB or to obtain copies of NEWMDB reports, please use the following contacts: Internet:

http://www-newmdb.iaea.org/ (Homepage) e-mail:

[email protected] (NEWMDB Programme Officer) facsimile (FAX):

NEWMDB Programme Officer Division of Nuclear Fuel Cycle and Waste Technology International Atomic Energy Agency +43 1 2600 7

mail:

NEWMDB Programme Officer Division of Nuclear Fuel Cycle and Waste Technology International Atomic Energy Agency Wagramerstrasse 5, P.O. Box 100 A-1400, Vienna, Austria

http://www-newmdb.iaea.org/

mailto:[email protected]

FOREWORD

The Agency’s Net Enabled Waste Management Database (NEWMDB) is an Internet-based[1] database to collect information about radioactive waste management activities and waste inventories in Agency Member States. The NEWMDB’s On Line Help[2] provides extensive detail about the purpose, scope and limitations, and use of the NEWMDB.

The NEWMDB was developed to succeed the Waste Management Database (WMDB), which was used to collect information from Agency Member States during the 1990’s. The last WMDB data collection cycle was started in 1997/98 and concluded in late 1999. The last WMDB report was issued in mid-2000.

A comprehensive review of the WMDB was undertaken in mid-1999. Based on feedback from Member State representatives, consultants and Agency staff members, it was concluded that:

• data collection and dissemination for the WMDB was not timely, • the WMDB questionnaire lacked clear and concise guidance, • respondents had difficulty reporting on their radioactive waste management

programmes and inventories according to the Agency’s proposed waste classification scheme,

• the information in the WMDB reports was not easy to evaluate or use, and • the WMDB could not support a key Agency objective to compile a comprehensive,

international radioactive waste inventory.

In short, the WMDB did not meet the needs of its customers.

In addition to the WMDB review, the following transpired since the WMDB was developed and implemented:

• radical changes have occurred in information management, notably the Internet, • the Joint Convention on the Safety of Spent Fuel Management and on the Safety of

Radioactive Waste Management (the Joint Convention) came into force June 2001. The Joint Convention is the first legally binding, international instrument specifically related to spent fuel and radioactive waste management and it contains specific requirements for the exchange of information between Contracting Parties.

• Agenda 21 was issued from the UN Conference on Environment and Development, held in Rio de Janeiro in June 1992. Chapter 40 of Agenda 21 calls for the development of indicators for sustainable development (ISD). As a follow up, the Agency was assigned the responsibility to develop ISD for radioactive waste management (ISD-RW), in accordance with Chapter 22 of Agenda 21 and the UN wide indicators development work programme. The Agency developed a single ISD-RW in September 2001, which was later refined in February 2002.

1 http://www-newmdb.iaea.org/start.asp 2 http://www-newmdb.iaea.org/help.asp

IAEA/WMDB/4 (2002) Page FW-1

http://www-newmdb.iaea.org/start.asp

http://www-newmdb.iaea.org/help.asp

The principal objectives for developing the NEWMDB were to: • support the routine reporting of status and trends in radioactive waste management

based, to the greatest extent practicable, on quantitative data rather than anecdotal information,

• assess the development and implementation of national systems for radioactive waste management,

• support the ISD-RW and the compilation of a comprehensive, international radioactive waste inventory based on a unified waste classification scheme, and

• conform, to the greatest extent practicable, with the reporting requirements of the Joint Convention.

In October 2000, the Agency issued a Note Verbale asking each of its Member States to nominate a single point of contact, known as a Country Co-ordinator (CC), who would interact directly with the NEWMDB’s Programme Officer (PO) during data collection cycles. A total of 51 Member States appointed a CC for the first data collection cycle, which was held July 6, 2001 to March 15, 2002.

The NEWMDB Administrator grants database access to CCs, who can, in turn, designate and register other users, Report Co-ordinators (RCs) and Waste Experts (WEs), to assist with NEWMDB submissions.

The NEWMDB was implemented as a series of components that requires registered users to input and approve information in a step-wise process as follows (see Figure 1):

Step 1: CCs input their contact information and they register RCs and WEs to assist with data submission (optional). CCs use the waste class matrix tool to identify all waste classification schemes used in their country and to compare these schemes with the Agency’s proposed waste classification scheme. Figure 2 shows one of the two waste class matrices created by the CC for the USA for the NEWMDB’s first data collection cycle. The matrix shows the relationship between the “USDOE” waste classification scheme and the Agency’s proposed waste class scheme (LILW-SL, LILW-LL and HLW waste classes). CCs were requested to provide supporting documentation (see the Comments and Attachments “links” in Figure 2) to indicate whether or not a waste classification scheme is required by law or regulation and to describe how the percentages in the matrix were derived. The matrix tool provides support for the Joint Convention requirement that “For each Contracting Party the report shall also address its... ...criteria used to define and categorize radioactive waste”. The issue of waste classification is discussed at greater length in the Introduction. CCs are unable to proceed to Step 2 until waste class matrices are approved by them and by the NEWMDB Administrator (currently this is the NEWMDB’s PO). Step 1 proved to be a major stumbling block for many CCs in the first data collection cycle.


Step 1

usersmatrices

Step 2

structuregen info

CC Admin CC Admin

Step 3

“wastedata”

APPROVALS APPROVALS

Figure 1: Steps in the NEWMDB Data Input Process

Figure 2: The Waste Class Matrix for the USA’s Department of Energy

Step 2: CCs customize how information about radioactive waste management programmes and inventories will be reported to the NEWMDB. This feature was added because a number of respondents to the 1997/98 WMDB questionnaire stated that they found it difficult to “fit” their information into the WMDB’s rigid structure. With the NEWMDB, CCs define the number of Reporting Groups and within each Reporting Group they identify the waste management sites and waste management facilities (processing, storage, disposal and dedicated spent/disused sealed radioactive source (SRS) management facilities). For facilities, CCs indicate attributes such as type, capacity, percent filled, etc. Step 2 includes the “General Information” component where CCs identify who regulates radioactive waste, the laws and regulations that are relevant to radioactive waste management, significant milestones in radioactive waste management in their countries, and radioactive waste management policies. CCs answer up to 80 policy related questions (some questions are conditional “if” questions, where “Yes” answers require additional questions to be answered). Figure 3 illustrates some policy questions.

Step 3: The “Waste Data” component of the NEWMDB is used by CCs (and those they designate to assist them) to identify waste treatment and conditioning methods (see Figure 4), to specify the inventory of radioactive waste for each waste class at each waste management site (see Figure 5) and to specify inventories of spent/disused SRS in dedicated SRS management facilities (see Figure 6).


Figure 3: Example NEWMDB Policy Questions

Figure 4: Example of Waste Processing (Treatment / Conditioning) Data


Figure 5: Example Radioactive Waste Inventory Data

Figure 6: Example Spent/Disused Sealed Radioactive Source Inventory Data


During the first data collection cycle, only about 40% of Member States appointed CCs and only 20 full submissions and 2 partial submissions were received. However, even with the low level of participation and the small number of submissions, the results of the first data collection indicated that the NEWMDB successfully achieved the objectives identified previously. Briefly, the results of the first data collection cycle have shown that the NEWMDB:

• could be used to collect information from Member States annually – this addresses a major problem with the WMDB (“data collection and dissemination… …not timely”),

• provides extensive guidance to users, which addresses another WMDB fault (“lacked clear concise guidance”),

• demonstrated that the data needed to compute an indicator of sustainable development for radioactive waste management are available at the national level, see Overview Reports: Indicator of Sustainable Development for Radioactive Waste Management

• can support the compilation of a comprehensive, international radioactive waste inventory based on a unified waste classification scheme, see Overview Reports: Consolidated Radioactive Waste Inventory

• supports the routine reporting of status and trends in radioactive waste management based on quantitative data rather than anecdotal information, see Overview Reports: Status and Trends in Radioactive Waste Management

• can support reporting requirements for the Joint Convention, and see Overview Reports: The Joint Convention and the NEWMDB

• can be used to assess the development and implementation of national systems for radioactive waste management. see Overview Reports: Scorecard for National Systems for Radioactive Waste Management.

Readers may notice some repetition of text in the various Overview Reports. This repetition is intentional – it allows the reports to be essentially self-standing.

This report, “Radioactive Waste Management Profiles No. 4”, includes a summary and a compilation of waste management data provided by Agency Member States from July 2001 to March 2002 using the NEWMDB’s Internet-based, on line interface. The “country waste profiles” reports that are compiled within the Profiles report No. 4 contain the information submitted by individual Member States during the data collection cycle. See Guide to Reading Profile Reports and Country Waste Profile Reports.

Publication of this NEWMDB Profiles Report is made possible by the participation of Member States. The efforts of the Resident Missions to the Agency in Vienna and other governmental organizations in Member States who co-ordinated the submission of the data are greatly appreciated.

This report was compiled by the following Agency staff members:

Greg W. Csullog Iouri Pozdniakov Department of Nuclear Energy Department of Management Waste Technology Section Business Solutions Section


INTRODUCTION

The evolution of radioactive waste management is, fundamentally, no different than the evolution of waste management in other industrial sectors, such as the chemical industry. Like waste management in other sectors, radioactive waste management was not a high priority in the early days of nuclear research and development. Now it is often viewed as a critical factor that helped decide the direction of the nuclear industry in some Member States and it could help decide the direction of the nuclear industry in others.

Over the last one to two decades, the evolution of radioactive waste management has focused on the development and implementation of technological solutions to problems. From the mid-1990s onward, there has been an ever increasing focus on non-technical aspects of radioactive waste management [1]. Of note, radioactive waste managers are increasingly interested in informing their stakeholders (one definition of a stakeholder is anyone who declares him/herself to have a vested interest in radioactive waste management).

In 1998, the European Commission (EC) conducted a survey to determine the interest, knowledge and feelings of European citizens about radioactive waste and its management [2]. The survey asked questions in five areas:

• how well do people think they were informed about radioactive waste, • what is their level of knowledge about radioactive waste management, • what is the public’s views on different aspects of radioactive waste management, • what are the opinions related to geologic disposal of high level and long-lived

radioactive waste, and • which generation, present or future, should be responsible for decisions on waste

disposal and what is the possible role for the European Union in this area.

How well informed does the average European citizen think he/she is informed about radioactive waste? The answer, not very well. How much do European citizens actually know about radioactive waste? The answer, not a lot [3].

A recent report by the Union of the Electricity Industry (Eurelectric), entitled “Nuclear Power Plant’s Radwaste in Perspective”, provided an overview of the management of radioactive waste from nuclear power in 14 European countries [4]. The report stated:

“…The basic problem concerning radwaste from nuclear power plants seems to be mostly a political one, which originates from the lack of public support in some countries. This area must certainly be improved and better and honest communication is strongly recommended to obtain public acceptance… … Public information should be reinforced to improve the public perception and political support.”

The Agency attaches a high importance to the dissemination of information that can assist its Member States with the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support the nuclear fuel cycle and nuclear applications. Article VIII of the Statute of the Agency, entitled “Exchange of Information”, states:

“A. Each member should make available such information as would, in the judgment of the member, be helpful to the Agency.

IAEA/WMDB/4 (2002) Page Intro-1

B. Each member shall make available to the Agency all scientific information developed as a result of assistance extended by the Agency pursuant to Article XI.

C. The Agency shall assemble and make available in an accessible form the information made available to it under paragraphs A and B of this article. It shall take positive steps to encourage the exchange among its members of information relating to the nature and peaceful uses of atomic energy and shall serve as an intermediary among its members for this purpose.”

The Agency’s Medium Term Strategy [5] states: “The challenge for the Agency in the medium term is threefold: • to understand how the needs and interests of Member States are changing so

as to be able to respond by focusing on the appropriate nuclear technologies; • to contribute to the objective assessment of the use of nuclear technologies and

to assist Member States in the safe application of those technologies that continue to have a comparative advantage;

• to play a catalytic role in the international effort to maintain and increase knowledge, understanding and expertise in the nuclear field, particularly through the collection and dissemination of scientific information and the transfer of technology.”

The above indicates the keen interest that nuclear power providers, the EC and the Agency have in the dissemination of information to the public and other stakeholders. In addition, it indicates the importance of timely and reliable information to support Agency activities that serve the needs of its Member States.

The NEWMDB is the Agency’s principal mechanism for the collection and dissemination of information about waste management programmes and activities in its Member States. The dissemination of information is carried out both inside and outside of the Agency.

The Role of the NEWMDB in the Collection and Dissemination of Radioactive Waste Management Information

Internal Dissemination of Information

The Agency’s Country Files System (CFS) is an internal co-ordinated information tool that allows Agency staff to retrieve information from in-house databases and other information sources on a country-by-country basis. Use of the Country File System is restricted to Agency staff. The current (5th) version of the CFS contains the following (in addition to other information):

• Fact sheets, geographic, demographic and economic information; • Energy and economic data; • Addresses for a wide variety of organizations; • Country organization infrastructure and Nuclear Power Profile; • Nuclear Facilities overview; • Nuclear Power Plants, Research Reactors and Nuclear Fuel Cycle facilities; • Uranium Deposits;


• Radioactive Waste Inventories; • Index of Travel Reports; and • Technical Co-operation Projects, plans and Research Contract data.

Data displayed by the CFS are obtained directly from the latest versions of the following databases (in addition to other sources of information).

• Energy and Economic Data Bank - EEDB • Power Reactor Information System - PRIS • Research Reactor Database - RRDB • Research Contracts System - RCS • Technical Cooperation Management System - TCMS • Safety Country Profile Database - SACOP • Nuclear Fuel Cycle Information System - NFCIS • Uranium Deposits - UDEPO • Radioactive Waste Inventories - WMDB (Waste Management Database)

Note, at the time of writing of this report, the NEWMDB database had not yet been linked to the CFS. This is due to the fact that the scope and content of the NEWMDB is substantially different than that of the WMDB and new interface routines have to be developed. In the future, the CFS will have links to both the WMDB and NEWMDB data.

The CFS contains a disclaimer that states “We make no claims for the accuracy of the data in this site” because much of the information is based on data collected from Member States. The NEWMDB has been engineered to allow traceability of information back to national level reports and, as such, over time verification and validation should make this information trustworthy. This is a critical factor - if Agency staff are to use information linked to the CFS to support decision making, this information must not only be timely, it must be accurate and trustworthy. To achieve this aim, the full and effective co-operation of Member States is required during NEWMDB data collection cycles.

External Dissemination of Information

The Indicator of Sustainable Development for Radioactive Waste Management: One of the objectives for developing the NEWMDB was to provide support for an indicator of sustainable development for radioactive waste management (ISD-RW). The first data collection cycle with the NEWMDB has shown that it can be used to collect and compile some of the same nationally-based information that would be needed by countries to compute the ISD-RW. Details of the NEWMDB in the context of the ISD-RW are provided in Overview Reports: Indicator of Sustainable Development for Radioactive Waste Management.

Consolidated Radioactive Waste Inventory: One of the fundamental features of the NEWMDB is that it allows Member States to report their waste inventories according to the waste classification scheme(s) used in their own countries. However, the NEWMDB requires Member States to describe how their waste classification scheme(s) compare with the one proposed by the Agency in 1994 [6]. Member States use the NEWMDB’s waste class matrix tool to make this comparison. This topic is discussed in detail under the subheading entitled “The Classification of Radioactive Waste”


Member States participating in submitting information to the NEWMDB were asked to appoint a single point-of-contact, called a Country Co-ordinator, to interact directly with the NEWMDB’s Programme Officer. Country Co-ordinators are responsible for completing the waste class matrix on behalf of their country.

Figures 1 and 2 show the two waste class matrices created by the Country Co-ordinator for the United States of America for the NEWMDB’s first data collection cycle. The matrices show the relationship between two waste class schemes used in the USA and the Agency’s proposed waste class scheme (LILW-SL, LILW-LL and HLW waste classes). Country Co-ordinators were requested to provide supporting documentation (see the Comments and Attachments “links” in the figures) to indicate whether or not a waste classification scheme is required by law or regulation and to describe how the percentages in the matrix were derived.

Figure 1: Waste Class Matrix for the USA’s Department of Energy Waste

Figure 2: Waste Class Matrix for the USA’s Commercial Waste

Once the waste class matrix (or matrices) is created, Member States report their waste inventories to the NEWMDB according to their own waste classes, not according to the Agency’s waste classes. For example, the USA reported its radioactive waste inventories according to classes A, B, C, etc, not according to LILW-SL, etc.


The NEWMDB’s matrices allow the Agency to transpose Member States’ waste inventories according to the Agency’s waste classes in order to compile a radioactive waste inventory according to a single waste classification scheme. Details of the inventory compilation are provide in Overview Reports: Consolidated Radioactive Waste Inventory.

Status and Trends Report Series: In 2001, to support of the Agency’s information strategy, the first volume in a new series of reports entitled “Radioactive Waste Management Status and Trends” was issued [1]. The first volume states the following:

“Previously, reports on status and trends in radioactive waste management had been issued as part of the Agency’s Yearbook, which was last published in 1997. These reports contained mainly anecdotal information that was assembled by Agency staff in the course of regular programme activities. As such, the structure and content of status and trends reports changed from year-to-year. In addition, the reports did not rely principally on quantitative data to support their assessments of status and trends. The structure of the current report was derived with the intent of developing a formal framework for the assembly of information in radioactive waste management. The objectives were:

1. to identify subject areas deemed to be of interest to Member States and the Agency, 2. to report the status of and trends in radioactive waste management according to these subject areas, and 3. to base this reporting, to the greatest extent practicable, on quantitative data.

Objectives 1 and 2 have been met by the current report. However, currently, quantitative data are not available at a sufficient level to achieve objective 3.”

One of the principal objectives for developing the NEWMDB was to achieve objective 3. The status and trends report series is actually a subset of the NEWMDB report series. Volume 2 of the status and trends report, published September 2002, has already benefited from information collected during the NEWMDB’s first data collection cycle. However, as indicated in the Foreword, the level of participation by Member States in the first cycle was quite low. To achieve objective 3, full and effective co-operation of Member States is required during future NEWMDB data collection cycles. Additional discussion is given in Overview Reports: Status and Trends in Radioactive Waste Management.

The NEWMDB and the Joint Convention: One of the objectives for developing the NEWMDB was to conform, to the greatest extent practicable, with the reporting requirements of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) [7]. Contracting Parties to the Joint Convention are required to “establish… …guidelines regarding the form and structure of the national reports to be submitted pursuant to Article 32”, where Article 32, “Reporting”, states:

“1. In accordance with the provisions of Article 30, each Contracting Party shall submit a national report to each review meeting of Contracting Parties. This report shall address the measures taken to implement each of the obligations of the Convention. For each Contracting Party the report shall also address its: i. spent fuel management policy; ii. spent fuel management practices; iii. radioactive waste management policy;


iv. radioactive waste management practices; v. criteria used to define and categorize radioactive waste.

2. This report shall also include: i. a list of the spent fuel management facilities subject to this Convention,

their location, main purpose and essential features; ii. an inventory of spent fuel that is subject to this Convention and that is being

held in storage and of that which has been disposed of. This inventory shall contain a description of the material and, if available, give information on its mass and its total activity;

iii. a list of the radioactive waste management facilities subject to this Convention, their location, main purpose and essential features;

iv. an inventory of radioactive waste that is subject to this Convention that: a. is being held in storage at radioactive waste management and nuclear

fuel cycle facilities; b. has been disposed of; or c. has resulted from past practices This inventory shall contain a description of the material and other

appropriate information available, such as volume or mass, activity and specific radionuclides;

v. a list of nuclear facilities in the process of being decommissioned and the status of decommissioning activities at those facilities.

The use of an international database, like the NEWMDB, to collect the full scope of information required under Joint Convention reporting requirements is currently not feasible. Member States would have to expend a great deal of effort to provide the full scope of information to the NEWMDB and in many cases they may not be able (or may be unwilling) to report this information within the requirements of NEWMDB data collection cycles. The objective set out was “to conform, to the greatest extent practicable, with the reporting requirements of the Joint Convention”. The extent of this conformance is described in detail in Tables VI and VII in Reference [8].

The first data collection cycle has shown that the NEWMDB can be used to collect some of the information required for Contracting Party reports under the Joint Convention. As such, Member States that are Contracting Parties and also participate in NEWMDB data collection cycles could attach NEWMDB reports to their Contracting Party reports to minimize the costs and efforts for reporting.

A major reason for seeking conformance with the Joint Convention is that the availability of Contracting Party reports is a decision that will be made by the Contracting Parties themselves. If the decisions are made that (a) the reports will not be publicly available and (b) reporting will only be done under the Joint Convention and not to the NEWMDB, much of the information that would be publicly available via the NEWMDB would disappear from the public domain. This would be contrary to recent activities to improve the availability of waste management information.

Scorecard for National Systems for Radioactive Waste Management: Article 18, “Implementing Measures”, of the Joint Convention states:


“Each Contracting Party shall take, within the framework of its national law, the legislative, regulatory and administrative measures and other steps necessary for implementing its obligations under this Convention.”

Article 19, “Legislative and Regulatory Framework”, of the Joint Convention states: “1. Each Contracting Party shall establish and maintain a legislative and regulatory framework to govern the safety of spent fuel and radioactive waste management. 2. This legislative and regulatory framework shall provide for (i) the establishment of applicable national safety requirements and regulations for radiation safety.”

The Agency Safety Fundamentals document “The Principles of Radioactive Waste Management” [9], which is cited in the Preamble of the Joint Convention, states:

“The timely creation of an effective national legal and associated organizational structure provides the basis for appropriate management of radioactive waste”.

The implementation of national systems for radioactive waste management has, historically, been different in each Member State. While some mechanisms exist to document national activities [10] to [12], previously there had been no formal, systematic mechanism to assess international progress in establishing national systems for radioactive waste management. This is not meant to imply, in any way, that significant progress has not been made in the implementation of national waste management systems in many Member States. Of note, major progress has taken place in Central and Eastern Europe in recent years [13].

This issue has been addressed by the NEWMDB, which provides a mechanism to report this progress in a concise manner that would be easy to digest by policy and decision makers. The “General Information” component of the NEWMDB is used by Member States to identify who regulates their radioactive wastes, the laws and regulations that are relevant to radioactive waste management, significant milestones in radioactive waste management in their countries, and radioactive waste management policies. Member States answer up to 80 policy related questions (some questions are conditional “if” questions, where “Yes” answers require additional questions to be answered). Simple “point-and-click” actions are required to answer the policy questions. The results can be readily compiled into a scorecard to assess the status of and the progress towards the implementation of national systems for radioactive waste management in Agency Member States. Details of the scorecard are given in Overview Reports: Scorecard for National Systems for Radioactive Waste Management.

Harmonization of National and International Waste Management Information: Recently, Agency Member States that have implemented information systems in support of nationally-based activities in radioactive waste management have begun to focus efforts on the harmonization of the various information systems that have been implemented. This will facilitate the collection and management of information by their national bodies. However, many Agency Member States either do not have waste management related information systems or they have not begun to deal with multiple, incompatible information systems. Additionally, overall Member States have paid little attention to the exchange of information at the international level.

A recent paper presented at an Agency sponsored conference [14] describes the Agency’s efforts to improve and harmonize international reporting in the area of radioactive waste management, to provide technical guidance on developing and implementing nationally-based information systems and to develop software tools for use by developing Member States. The objective of the


Agency’s efforts is to ensure that its Member States consider factors such as the reporting information to international organizations, the exchange of information between organizations within their country, the exchange of information between countries (for example, in support of international repositories) and the passing of information to future societies after repository closure.

The harmonization of information at the national level will facilitate the collection of data for the NEWMDB. It will also help ensure that the NEWMDB information that is distributed internally and externally to the Agency is traceable and verifiable.

The NEWMDB and Information about Spent/Disused Sealed Radioactive Sources (SRS): Two recent events have re-focused attention on the need for the safe management of spent/disused SRS. First, Article 28.1 of the Joint Convention states that each “Contracting Party shall, in the framework of its national law, take the appropriate steps to ensure that the possession, re-manufacturing or disposal of disused sealed sources takes place in a safe manner.” Second, the Agency has recently developed, and is currently implementing "The Action Plan for the Safety of Radiation Sources and the Security of Radioactive Materials" [15]. Safety means measures intended to minimize the likelihood of accidents with radioactive sources and, should such an accident occur, to mitigate its consequences. Security means measures to prevent unauthorized access to, and loss, theft and unauthorized transfer of radioactive sources.

The above events are in addition to the Agency's on-going activities in support of the management of spent/disused SRS, which have been ongoing since the late 1980's. These activities have focused on two areas - the provision of technical guidance and direct, technical assistance to Member States.

The various measures and activities that have been or are being implemented are to deal with the fact that spent/disused sources, if not properly managed, can fall out of regulatory control, which can lead to serious injuries and deaths. As such, it is important that Member States have mechanisms in place to ensure that spent/disused sources are either recycled/reused or transferred to secure waste management facilities in a timely manner after becoming, or after being declared, spent and/or disused.

The NEWMDB is used to collect several types of information about the management of spent/disused SRS, namely:

• the location and types of dedicated spent/disused SRS facilities for SRS declared to be or managed as radioactive waste (Note: the term “dedicated” is defined in the NEWMDB’s on line glossary),

• Member State policies towards spent/disused SRS management, and • inventories of spent/disused SRS in dedicated spent/disused SRS facilities.

The NEWMDB is the only publicly available, international source of information about the management and inventories of spent/disused SRS when these sources are declared to be or are managed as radioactive waste and categorized according to the Agency’s newly published source categorization scheme [16]. Due to the low participation rate in the first NEWMDB data collection cycle, the amount of information about these SRS is limited. The full and effective co-operation of Member States is required during future NEWMDB data collection cycles to ensure that more data become available.


The Classification of Radioactive Waste

In 1994, the Agency published a Safety Guide entitled “Classification of Radioactive Waste” [6]. This guide stated:

“To simplify their [radioactive wastes] management, a number of schemes have evolved for classifying radioactive wastes according to their physical. chemical and radiological properties of significance to the facilities managing this waste. These schemes have led to a variety of terminologies, differing from country to country and even between facilities in the same country. This situation makes it difficult for those concerned to communicate with one another regarding waste management practices, causing problems in comparing data published in the scientific literature, and causes confusion among members of the public trying to understand waste management programmes and practices of their countries and of other Member States…

…The objective of this Safety Guide is to recommend a method for deriving a classification system and to suggest a general system for classifying radioactive waste that will facilitate communication and information exchange among Member States, and eliminate some of the ambiguity that now exists in classification schemes for radioactive wastes.

Furthermore, this Safety Guide is to specify boundaries in a general system for classifying radioactive waste, especially in the assignment of boundaries to radioactive waste classes. It describes how to deal with a classification system, points out approaches for further quantification and discusses methods by which boundaries can be derived.”

The following focuses on the issues denoted by the bold italicized text, it discusses progress made towards the implementation of a general system for waste classification and it discusses the waste class matrix feature of the NEWMDB, which was implemented for Agency Member States (a) to identify the waste classification schemes they use and (b) to compare these schemes with the Agency’s proposed general waste classification scheme.

A recent assessment of the Agency’s proposed general waste classification scheme indicated that the scheme is not rigorous and not completely defined [8]. This assessment was confirmed at a recent meeting of the Waste Safety Standards Committee (WASSC). The report for the 11th WASSC stated [17]:

“WASSC recognises the need for a review of the current safety guide, in order to: • take more account of predisposal waste management considerations • address the inclusion of other waste types • introduce an international definition of radioactive waste

However, it is felt that the review should not start before the ongoing/planned collection of data from Member States. Further consideration should then be given to the matter in the framework of the Joint Convention and of the need for harmonisation of classification schemes in that context.”

The “ongoing/planned collection of data from Member States” referred to the first data collection cycle of the NEWMDB.


Table 1 summarizes the recent assessment of the Agency’s proposed general waste classification scheme.

Table 1: Summary of the Assessment of the Agency’s Proposed General Waste Classification Scheme Exempt Waste (EW) Typical Characteristics

activity levels at or below clearance levels (see Note 1) Possible disposal Options no radiological restrictions

Low and Intermediate Level Waste (LILW)

Typical Characteristics activity levels above clearance levels thermal power below about 2kW/m3 (see Note 2)

Short Lived (LILW-SL) Typical Characteristics restricted Long Lived radionuclide concentrations (see Note 3) Possible Disposal Options near surface or geological disposal facility

Long Lived (LILW-LL) Typical Characteristics long lived radionuclide concentrations exceeding limitations for LILW-SL (see Note 3) Possible Disposal Options geological disposal facility

High Level Waste (HLW)

Typical Characteristics long lived radionuclide concentrations exceeding limitations for short lived waste thermal power above about 2kW/m3 Possible Disposal Options geological disposal facility

Note 1: There is no internationally agreed definition for clearance levels Note 2: There is no international consensus on this thermal power level Note 3: Safety Guide 111-G-1.1 only provides guidance for restricting the concentrations of alpha emitting radionuclides - no explicit guidance is provided for other long lived radionuclides The proposed scheme defines the LILW class by exclusion - it is neither clearance nor HLW. However, currently there are no internationally agreed definitions of either clearance or HLW, as such these boundary conditions are ambiguous. Additionally, the proposed scheme divides LILW into the LILW-SL and LILW-LL classes but only provides general guidance on the level of alpha emitting nuclides. The Safety Guide states “The boundary between short lived and long lived waste cannot be specified in a universal manner”, indicating that the boundary between the LILW-SL and LILW-LL classes is also ambiguous. Furthermore, recent discussions between the NEWMDB’s Programme Officer and official contact points in Member States has indicated that the Safety Guide’s discussion of “methods by which boundaries can be derived” is inadequate or could not be understood. The Safety Guide objective to “eliminate some of the ambiguity that now exists in classification schemes for radioactive wastes.” may have been partially achieved, however it is clear that a great deal of ambiguity regarding the classification of radioactive waste still exists in Agency Member States.

Since the Agency Safety Guide on the classification of waste was issued in 1994, several assessments have been made of the multitude of waste classification schemes used world wide [1], [4], [13], [18] . All of these assessments indicated that some form of harmonization of waste classification is needed. In 1999, the European Commission issued a recommendation that stated “the [EU] Member States and their nuclear industry adopt a common classification system for national and international communication purposes as well as to facilitate information management in this field” [19]. The EC recommendation further states:

“… that this classification system should be used for providing information concerning solid radioactive waste to the public, the national and international institutions and the non-governmental organisations. It would not replace technical criteria where required for specific safety considerations such as licensing of facilities or other operations;


that this classification system could be used by Member States. During the period to 1 January 2002 it could be used in parallel with existing national systems;… … The use by all countries of the international IAEA classification of radioactive waste packages is a suitable base to develop a common classification system for the Member States of the European Union. Definition of a reference classification system may provide useful guidance for specific countries in developing their own management strategies, whilst at the same time facilitating general and commercial communications. Concerning safety, however, while such a reference classification system may be useful for generic and basic considerations, it cannot replace specific safety assessments performed for specific management purposes, including the selection of disposal routes….”

The EC recommendation is based on the Agency’s 1994 Safety Guide but includes modifications to the Agency’s the proposed general classification scheme. For example the EC recommendation states, “For instance the IAEA recommended limit of heat generation in LILW radioactive waste (2 kW/m3), was not retained. The experts could not find any foundation for such a value and commonly accepted that this value is only related to site-specific safety analysis.”

One key point is that the recommended common EC classification system should “be used for providing information concerning solid radioactive waste to the public, the national and international institutions and the non-governmental organisations” but it would not replace existing waste classification schemes that support waste management operations and activities, notably disposal assessments. Another key point is that the recommended EC classification system only serves as a “suitable base to develop a common classification system for the Member States of the European Union”. However, this EC statement must be viewed in the context that the Agency’s proposed general classification scheme is not rigorous and not complete. The same is true for the EC’s recommended common classification system since its waste classes are also defined by either ambiguous boundary conditions or boundary conditions for which there is no international consensus.

A major question arises. How could EU Member States “convert” waste management information based upon nationally-based waste classification schemes into information reported according to the EC’s common classification system if the boundary conditions for the EC’s waste classes are ambiguous and in the context of the EC statement that “In addition the borderlines between the [national] categories are not always easily quantifiable and hence can vary widely from one country to another.”?

Recent discussions between the NEWMDB’s Programme Officer and official contact points in Member States indicated that some Agency Member States have recently adopted or are planning to adopt the Agency’s proposed waste classification scheme in support of waste management programmes and activities. The adoption of the Agency’s proposed general classification scheme may not only be premature, it may be inappropriate if it is to serve as the fundamental basis for radioactive waste management. The EC statement that its recommended common classification system “would not replace technical criteria where required for specific safety considerations such as licensing of facilities or other operations” is a clear recognition of the limitations of the Agency’s proposed general classification scheme as the basis for supporting radioactive waste management operations. The EC has clearly indicated that until an effective common classification system is developed, its recommendations should be limited to


providing information “to the public, the national and international institutions and the non-governmental organisations”.

An additional point to consider is that the Agency’s proposed scheme, upon which the EC recommendation is based, is principally a disposal based waste classification scheme. As such, it does not adequately address pre-disposal radioactive waste management (handling, processing, storage) that can require quite complex classifications such as fissile/non-fissile waste, waste requiring/not requiring safeguards, package stackability, compressibility, durability in storage, etc. In other words, the Agency’s proposed waste classification scheme does not fully address “technical criteria where required for specific safety considerations such as licensing of facilities or other operations”.

Obviously there is an international dilemma. While organizations like the EC want to see radioactive waste reported according to a common classification system, how could this be implemented given the fact that both its recommended common system and the Agency’s proposed general scheme are not rigorous and not completely defined and, nationally, there is a great deal of uncertainty about waste classification in general? A possible solution is described next.

The recent assessment of the Agency’s proposed general waste classification scheme indicated that the scheme “could serve as a good foundation” for developing a rigorous and complete scheme. This fact was also recognized by the EC. However, the development of a rigorous and complete common waste classification scheme could be well into the future. How, then, could Agency Member States report their radioactive waste inventories to the NEWMDB in such a way that the Agency could compile a comprehensive, radioactive waste inventory according to a common classification scheme?

The NEWMDB’s waste class matrix tool was implemented to address this issue. Using the waste class matrix, an Agency Member State’s single point of contact, known as a Country Co-ordinator, is responsible for identifying the various waste classification schemes used in his/her country and for comparing these schemes with the Agency’s proposed general classification scheme. Country Co-ordinators were requested to provide supporting documentation to indicate whether or not a waste classification scheme is required by law or regulation and to describe how the comparison between their schemes and the Agency’s proposed scheme was performed.

Once the identification and comparison of waste classification schemes was completed, Member States reported their radioactive waste inventories to the NEWMDB according to their own, nationally-based waste classes. The advantages of this approach are:

• The reporting of wastes according to nationally-based waste classes avoids the requirement for Country Co-ordinators to first “convert” nationally-based information into a common classification scheme. The intention was to have Member States report information that could be traced back to nationally-based reports. Converted information reported at the international level is not readily traceable back to unconverted information reported at the national level. This factor is very important to the successful reporting of nationally-based information at the international level. Without traceability, confidence cannot be established for the international information. In addition, use of the waste class matrix was a major stumbling block for many Country Co-ordinators. A number of Country Co-ordinators indicated that they had difficulty using the matrix because (a) they did not have any formally recognized waste classification


scheme(s) in their country, (b) the schemes they did have were not quantitatively based or were based upon parameters such as the origin of waste and radiation field strength measurements, which could not be readily compared with the Agency’s proposed classification scheme, and/or (c) they had difficulty with the inherent ambiguities of the Agency’s proposed waste classification scheme.

• The waste class matrix information is used after Member States report their wastes according to their own waste classes to convert national waste inventories into a first order approximation of an international waste inventory according to the common scheme. NOTE: individual Member State waste inventories are not reported according to the Agency’s common classification scheme. Only a “rolled up” inventory, the total inventory of wastes from all Member States that reported to the NEWMDB, is reported. Please see Overview Reports: Consolidated Radioactive Waste Inventory. This approach allows the international community time to develop a comprehensive, common classification scheme and allows Member States time to develop and implement effective, operational waste classification schemes. Until these are implemented, Member States can report traceable waste inventory data to the NEWMDB. Over time, the first order approximation of an international waste inventory according to a common classification scheme can progress to a reasonably accurate representation of the inventory of radioactive waste in Agency Member States.

Figures 1 and 2, presented previously in the INTRODUCTION, illustrate waste class matrices prepared by the Country Co-ordinator for the USA during the NEWMDB’s first data collection cycle. Supporting documentation indicated that the comparison of waste classification schemes was based upon detailed waste characterization data that had been compiled. The provision of supporting documentation by Country Co-ordinators is in conformance with a requirement of the Joint Convention, which states that “For each Contracting Party the report shall also address its... ...criteria used to define and categorize radioactive waste”.

On February 14, 2002, the Agency issued a Note Verbale to its Member States requesting that Member States that currently do not have a Country Co-ordinator to appoint one. The Note Verbale also requested that Member States that did not make a submission to the NEWMDB during the first data collection cycle (July 2001 to March 2002) do so during the second cycle (July 2002 to January 2003). The second data collection cycle is expected to result in additional Country Co-ordinators having problems with the identification of waste classification schemes in their countries and for comparing these schemes with the Agency’s proposed schemes. This will help identify additional countries that require international guidance on the issue of waste classification.

The results of the first NEMWDB data collection cycle indicate that the proposed WASSC review of the Agency’s proposed general waste classification scheme should be undertaken in a timely manner.

At time of writing, the Waste Technology Section in the Division of Nuclear Fuel Cycle and Waste Technology at the Agency had plans to introduce the development of a new technical document to address “operational waste classification” starting in fiscal year 2004. The intention is to undertake a comprehensive examination of waste segregation practices in Member States and to assess why these practices were implemented. From this assessment, an operational waste classification scheme can be prepared for the life cycle management of radioactive waste. An


operational waste classification scheme would provide valuable input for the development of a higher level, common waste classification scheme.

References

[1] “Radioactive Waste Management Status and Trends - an overview of international status and trends in radioactive waste management”, International Atomic Energy Agency report IAEA/WMDB/ST/1 CD ROM, September 2001.

[2] “Europeans and Radioactive Waste”, Eurobarometer 50.0, Directorate-General XI of the European Commission, Eurobarometer home page, http://europa.eu.int/comm/dg10/epo/eb.html.

[3] Derek M. Taylor and Simon Webster, "Public Opinion on Radioactive Waste Management in the European Union", (European Commission, DG-Environment), International Topical Meeting on Radioactive Waste Management: Commitment to the Future Environment (ENS Topseal '99) 10-14 October 1999, Antwerp, Belgium.

[4] “Nuclear Power Plants’ Radwaste in Perspective”, a report by the Union of the Electricity Union (EURELECTRIC, a union of UNIPEDE and EURELECTRIC), Report Number 2001-2110-0008, December 2001.

[5] The IAEA’s Medium Term Strategy, http://www.iaea.org/worldatom/Documents/mts.pdf

[6] “Classification of Radioactive Wastes”, International Atomic Energy Agency Safety Guide, Safety Series 111-G-1.1, IAEA, Vienna, 1994.

[7] “Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management”, International Atomic Energy Agency Information Circular INFCIRC/456, 24 December 1997.

[8] G.W. Csullog, I. Pozdniakov, U. Shah, V. Kostitsin, M.J. Bell, “The International Atomic Energy Agency’s Net-Enabled Waste Management Database”, Waste Management 2001 Symposium, Tucson, Arizona, USA, February 2001.

[9] “The Principles of Radioactive Waste Management”, International Atomic Energy Agency Safety Fundamentals, Safety Series 111-F, IAEA, Vienna, 1995.

[10] “International Waste Management: A Compendium of Programs and Standards”, prepared by Golder Associates Incorporated, published by WM Symposia Incorporated, February 1997.

[11] “Nuclear Waste Bulletin - Update on Waste Management Policies and Programmes”, No 13, Organization of Economic Co-operation and Development/Nuclear Energy Agency, Paris, 1998 December.

[12] Internet home page of the Radioactive Waste Management Committee of the Nuclear Energy Agency, http://www.nea.fr/html/rwm/.

[13] “Radioactive Waste Management Profiles - Compilation of Data from the Waste Management Database, No. 3”, International Atomic Energy Agency Report IAEA/WMDB/3, Vienna, April 2000.

[14] G.W. Csullog, W.E. Falck, and S.T.W. Miaw, “The IAEA Perspective on International and National Radioactive Waste Management Information Systems”, Proceedings of the “International Symposium on the Management of Radioactive Waste from Non-Power


http://www.iaea.org/worldatom/Documents/mts.pdf

Applications - Sharing the Experience”, Malta, November 2001, IAEA publication in press.

[15] International Atomic Energy Agency General Conference Resolution GC(45)/RES/10, September 2001.

[16] “Categorization of Radiation Sources”, International Atomic Energy Agency Technical Document, IAEA-TECDOC-1191, IAEA, Vienna, December 2000 (corrected March 2001).

[17] Report of the 11th Waste Safety Standards Committee (WASSC) meeting, April 4-6, 2001. (http://www.iaea.org/ns/committees/wassc/documents/reports/wasscreport11.pdf)


[19] Commission Recommendation of 15 September 1999 on a classification system for solid radioactive waste (SEC(1999) 1302 final), Official Journal of the European Communities, L265 Volume 42, 13 October 1999.


OVERVIEW REPORTS

This section of the “Radioactive Waste Management Profiles, Number 4” contains overview reports that provide assessments of the achievements and shortcomings of the NEWMDB during the first data collection cycle (July 2001 to March 2002). The individual overview reports are contained in separate files that are linked to this file (OVERVIEW.pdf). To access individual overview reports, please click on the links in the following table.

Readers may notice some repetition of text in the various Overview Reports. This repetition is intentional – it allows the reports to be essentially self-standing.

File Name Report Description ISD-RW.pdf Indicator of Sustainable Development for Radioactive Waste Management

This report describes the relationship between an Indicator of Sustainable Development for Radioactive Waste Management (ISD-RW) and the data submitted by IAEA Member States to the NEWMDB.

INV.pdf Consolidated Radioactive Waste Inventory This report describes the IAEA’s efforts to compile an international inventory of radioactive waste according to a common classification scheme.

S&T.pdf Status and Trends in Radioactive Waste Management This report describes the role of the NEWMDB in the provision of quantitative data in support of an IAEA report series entitled “Radioactive Waste Management Status and Trends”

JC.pdf The Joint Convention and the NEWMDB This report describes the scope of the NEWMDB in relation to the reporting requirements of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management.

NATSYS.pdf Scorecard for National Systems for Radioactive Waste Management This report describes the role of the NEWMDB in assessing the development and implementation of national systems for radioactive waste management.

IAEA/WMDB/4 (2002) Page OV-1

OVERVIEW REPORT: Indicator of Sustainable Development for Radioactive Waste Management

BACKGROUND

As a follow up to the United Nation’s (UN) Conference on Environment and Development in 1992 [1], the UN’s Department of Economic and Social Affairs (DESA) invited the IAEA to develop one or more indicators of sustainable development (ISD) for the management of radioactive waste (RW). Responsibility for this task was given to the IAEA’s Division of Nuclear Fuel Cycle and Waste Technology (NEFW) within the Department of Nuclear Energy.

Indicators were required to cover radioactive waste from both Nuclear Power and Nuclear Applications activities. Following guidance from UN-DESA on scope and methodology, a series of workshops and consultancies resulted in the development of a family of indicators. As of 1999, the IAEA had proposed a set of nine ISD-RW. However, in late 1999 DESA, the UN agency responsible for indicators, began a process to consolidate the various ISD that had been developed and, to varying degrees, subjected to country testing. The result was that experts chosen by DESA selected a single ISD-RW to remain in the DESA list of indicators (“Indicators of Sustainable Development: Guidelines and Methodologies”, UN, New York, 2001).

This selected ISD-RW was reviewed by the IAEA’s experts in two consultants’ meetings held September 2001 and February 2002. The experts concluded that an alternative ISD-RW was required since the ISD-RW selected by DESA:

• does not derive or use a baseline against which progress can be judged, • does not acknowledge waste that is under management control, • makes no distinction between wastes from different activities (e.g. Fuel Cycle,

medical use etc.), • makes no attempt to discriminate between the relative hazards of waste types

(e.g. low-level waste (LLW) and high-level waste (HLW)), • uses a metric (volume) that is dominated by low risk waste (LLW), • appears to penalize the Fuel Cycle nations even if they manage their wastes in

a sustainable manner (since the only metric is volume), • has no clear definition of an end point (when is sustainability reached?), • fails to distinguish between wastes with and without a defined disposition, and • uses an unproven supposition that the volume of waste is linked to

environmental impact and human health.

As a consequence of the consultancies, a new ISD-RW was developed and is described next.

THE INDICATOR OF SUSTAINABLE DEVELOPMENT FOR RADIOACTIVE WASTE MANAGEMENT

The ISD-RW developed by NEFW: • recognizes the shortcomings of a purely volume based approach for an

indicator, • is a single, dimensionless indicator that includes a consideration of waste

volumes in its derivation, and

IAEA/WMDB/4 (2002) Page ISD-1

• provides a measure of both the current status of radioactive waste management at any point in time and the progress made over time towards the sustainability of radioactive waste management. This measure can be at the national level for a country or it can be at sectoral levels, such as nuclear applications (e.g., medical and industrial applications).

Sustainability is the point at which the amount of radioactive waste awaiting disposal is not increasing, the waste is in the final form required for disposal and it is being safely stored. Note, since currently there is an international debate about whether or not disposal is the endpoint for waste management (some have proposed alternatives such as indefinite storage), the use of the term disposal in the context of the ISD-RW implies any internationally acknowledged alternative to disposal.

The ISD-RW only considers managed waste, it does not consider the intentional release of radioactivity into the environment (the “dilute and disperse” option). The ISD-RW does not require countries to base reporting of the indicator on (1) historic waste (except as a recognized component of a backlog of waste), (2) contaminated sites or (3) NORM(1) waste; however, these waste may be factored in on a voluntary basis.

The ISD-RW is based upon two factors that are applied to each of the waste classes used and reported by a country. Each factor has 4 states that indicate progress by way of milestones. The use of these two factors results in the ISD-RW being expressed as a dimensionless number between 0 and 100 with 0 being the least sustainable condition and 100 being the most sustainable condition.

FORM FACTOR indicates the suitability of waste for storage or its endpoint

Factor Value Description F1 0 waste not established as acceptable or known not to be acceptable for storage F2 10 capability exists to process waste for storage F3 25 capability exists to process waste for endpoint condition F4 50 inventory of waste not in its endpoint condition is not increasing

ENDPOINT FACTOR indicates the status of waste relative to its endpoint

Factor Value Description E1 0 no planned endpoint established E2 10 design and site approved E3 25 facility operational E4 50 inventory of waste not placed into its endpoint is not increasing

Note: Factors F4 and E4 indicate a capacity to manage waste as opposed to a capability to manage

The two factors are to be applied to each of the waste classes that are used and reported by a country. By way of example only, the ISD-RW limiting conditions that follow assume that a country uses three waste classes (LILW-SL, LILW-LL and HLW). Note: it is not necessary to define LILW-SL, etc. since the ISD-RW allows countries to report according to their own waste classes, which are too numerous and diverse to define herein. It is only necessary to realize that nationally-based waste classes are used.

(1) Naturally Occurring Radioactive Material


Limiting Condition - Least Sustainable Condition Waste Class

Form Factor

Endpoint Factor

Sum of Factors

LILW-SL 0 0 0 LILW-LL 0 0 0 HLW 0 0 0

Note: While the indicator is most useful when it is calculated and reported for each waste class used within a country, it is possible to derive a single, consolidated indicator based upon the average for each waste class. The use of an average value should be used with caution since it might lead to a meaningless, misleading or unwanted result.

Limiting Condition - Most Sustainable Condition

Waste Class

Form Factor

Endpoint Factor

Sum of Factors

LILW-SL 50 50 100 LILW-LL 50 50 100 HLW 50 50 100

The two factors were derived to reflect the management of waste and to cover the major activities of waste processing coupled with the final endpoint of the waste. The factors are presented as independent but are linked. For example, the capability of processing of waste to a form suitable for its endpoint requires a knowledge of the endpoint (but not necessarily the full achievement of factor E2). The factors are described next:

F1: Acceptability for storage can be achieved by regulatory acceptance or conformance with international guidance (for example, IAEA guidance). Possible reasons for failing to achieve acceptance include:

• absence of a regulator or failure to satisfy the regulator, • no mechanism to assess or present the justification for storage, and • no assessment carried out

F2: The capability to prepare waste for storage implies that the waste can be put into a form that can be demonstrated to satisfy, as a minimum, international guidance for the storage of waste. Examples include:

• tanks that are acceptable for liquid waste, • the containerization of loose waste, • treatment to stabilize waste, and • conditioning

This state implies the availability of a suitable facility to store the waste.

F3: The capability to prepare waste for the endpoint implies that (a) an endpoint has been identified and (b) that the waste form meets endpoint acceptance criteria. This state also implies that the waste form can be stored in an acceptable facility and this facility has a sufficient design life to contain the waste until consigned to its endpoint. In some cases, the F3 state will be identical to the F2 state; however, the state will be supported by additional evidence that the waste will meet the endpoint criteria (as a minimum to international guidelines).

F4: This state requires that the inventory of waste that is not suitable for its endpoint is not increasing, which requires a knowledge of both the rate of waste


generation and the rate that it is put into its endpoint condition. If waste is generated in a form that is not suitable for its endpoint condition, processing facilities must be available and processing it to a form suitable for its endpoint at a rate equal to or greater than the rate of its arising.

E1: This state implies that there are no plans for an endpoint for the waste or that the plans are insufficiently well formulated to give confidence that an endpoint can be achieved on a defined time scale. An example might be that disposal is the endpoint but neither a facility design nor a site has been approved (e.g., accepted by the regulator).

E2: In this state, a major hurdle has been overcome. A site and a facility design have been approved thereby overcoming one of the major impediments to putting waste into its endpoint.

E3: In this state, the endpoint facility has been licensed and its operability demonstrated. It does not imply that it is fully operational or receiving waste, only that it is possible to put waste into its endpoint.

E4: This state requires that the inventory of waste waiting to be put into its endpoint is not increasing, which requires a knowledge of both the rate of waste generation and the rate that it is put into its endpoint. This state indicates that progress is being made to reduce the inventory of wastes not in its the endpoint. An understanding of the volume changes related to processing is also required to determine this state.

The following is a theoretical example of calculating the ISD-RW for each waste class reported by a country. The example assumes the following conditions exist in a country:

• the country uses the waste classes GCC, HLW, LLW, TRU, and SF, • the amount of LLW and TRU that is unsuitable for disposal is not increasing

and the amount of waste waiting for disposal is not increasing, • the capability exists to put GCC into a safe storage condition, details of a

disposal facility have not been established, • the capability exists to put HLW into its endpoint condition, details of a

disposal facility have not been established, • SF is in a safe storage condition, details of disposal facility have not been

established.

Waste Class Form Factor Endpoint Factor Sum of Factors LLW 50 50 100 TRU 50 50 100 GCC 10 0 10 HLW 25 0 25 SF 10 0 10

Note, for some waste, like SF, if the waste, as generated, is in a form suitable for storage, a country would use Form Factor F2 (since processing is not required, a value equivalent to having the necessary processing is used). A similar approach is used for waste that, as generated, is suitable for disposal.

The following provides guidance for calculating the ISD-RW. The guidance is based upon an IAEA consultants’ meeting held September 2002.


GUIDANCE FOR CALCULATING THE ISD-RW

To calculate the ISD-RW, the first step is to identify the various classes of radioactive waste that are managed in a county [2],[3],[4]. Next, the ISD-RW is calculated for each waste class. This process can lead to misleading or unwanted results if the waste classification scheme(s) used by a country: • is not “endpoint” based

As stated previously, “Sustainability is the point at which the amount of radioactive waste awaiting disposal is not increasing, the waste is in the final form required for disposal and it is being safely stored”. The ISD-RW was developed to reflect sustainability and, therefore, is best applied to waste classes that are “endpoint” based. For example, one country uses the following waste classes, which are endpoint based: LLW-A, LLW-B, LLW-C (surface / near surface disposal) LLW-GCC (not suitable for surface / near surface disposal) HLW (geological disposal) This waste classification scheme is suitable for calculating the ISD-RW. However, schemes that are based on, for example, handling waste (using radiation field and contamination levels) may not be suitable for calculating the ISD-RW. Countries should not re-classify wastes simply to be able to calculate the ISD-RW if they determine that calculations with their existing waste classes lead to misleading or unwanted results. Instead, these countries should undertake a review of their waste classification scheme(s) in the context of its applicability to the full life cycle management of waste. If after this review countries adopt a revised waste classification scheme, the ISD-RW can be recalculated for the new classes.

• does not adequately separate waste into suitable classes The classification scheme shown above is a good example of separating wastes into a sufficient number of classes to facilitate the effective, long-term management of wastes. However, some countries may have waste classes that could lead to unwanted results when calculating the ISD-RW. For example, suppose that LLW-A, LLW-B, LLW-C and LLW-GCC were rolled into a single waste class called LLW. Calculating the ISD-RW could “penalize” the country for grouping waste unsuitable for surface disposal into the same class as waste suitable for surface disposal. When calculating the ISD-RW, it is not possible to “break out” a sub-set of waste from a class, therefore, the ISD-RW calculation for LLW would have to be based upon the management of the GCC component (“worst case”) and would not properly reflect the country’s sustainability for the management of A, B and C waste. As stated above, countries should not re-classify wastes simply to be able to calculate the ISD-RW.

To assist with calculating the ISD-RW, two flowcharts were developed in the September 2002 consultancy on the ISD-RW, see Figure 1 and Figure 2. For each decision node in the flowcharts, explanations are given in Table I. As stated earlier, disposal in the flowcharts and table implies any internationally acceptable “endpoint” that is an alternative to disposal.


THE NEWMDB IN THE CONTEXT OF THE ISD-RW

One of the reasons the International Atomic Energy Agency (IAEA) developed its Net Enabled Waste Management Database (NEWMDB) [3] to [8] was to provide support for the ISD-RW. The NEWMDB is an international database, however, per UN guidance, all indicators are required to satisfy the following:

• national in scale and scope, • relevant to assessing progress towards sustainable development, • understandable, that is to say, clear, simple and unambiguous, • realizable within the capacities of national Governments, • conceptually well founded, • open-ended and adaptable to future development, • dependent on data that are readily available or available at a reasonable cost benefit

ratio, and • adequately documented, of known quality and updated at regular intervals.

To ensure that any indicator that was developed would be useful to and could be used by countries, the UN had activities on capacity building and training (1995-1999) and country testing (1996-1999). Since the ISD-RW was only developed in late 2001 and finalized in early 2002, it was not part of any capacity building, training or country testing activities. This issue was recognized during the development of the NEWMDB.

If it could be demonstrated that the NEWMDB could be used to collect and compile the same nationally-based data that would be required to compute an ISD-RW, then the use of the NEWMDB could be considered as the capacity building, training and country testing activities applied to other indicators.

The first data collection cycle with the NEWMDB was conducted from July 2001 to March 2002. A review of the information collected was carried out in the context of the ISD-RW during the consultancy held in September 2002. The conclusions and recommendations of the consultants were:

• The NEWMDB does not have all the information to compute the ISD-RW. However, countries that prepare NEWMDB submissions should be able to calculate the ISD-RW based on those submissions plus supplemental information that is likely to be available (such as qualitative information that is needed to answer the guidance questions).

• An ISD-RW questionnaire, based on the guidance in this document, should be added to the NEWMDB to provide an effective way of compiling the information needed to compute the ISD-RW.

• Since the ISD-RW is computed for each waste class used by a country, understanding and use of both the NEWMDB and the ISD-RW should be harmonized by way of achieving international consensus on radioactive waste classification.

The indicator was subjected to testing in September 2002 by consultants from four IAEA Member States. The consultants found the ISD-RW acceptable but did not like the guidance that had been developed by the IAEA. New guidance for computing the ISD-RW was developed and is described in this document.


SUMMARY

The ISD-RW described in this document was developed after UN activities on capacity building, training and country testing in support of indicators of sustainable development. The IAEA’s NEWMDB, which was developed from late 1999 to early 2001 and used from July 2001 to March 2002 to collect radioactive waste management information from IAEA Member States, has been used to collect and compile some of the nationally-based information that would be needed by countries to compute the ISD-RW.

A conclusion from the September 2002 consultancy was that countries that prepare NEWMDB submissions should be able to calculate the ISD-RW based on those submissions plus supplemental information that is likely to be available (such as qualitative information that is needed to answer the guidance questions).

A further conclusion was that capacity building for using the ISD-RW is still required, notably in the context of waste classification.


Start

Are you safely storing your

waste?

No

Does the capability for

processing waste for

storage exist (~99%)?

No


processing WUD for

disposal exist (~99%)?

Does WUDnot exist and estimated that it

will not appear in the future?

Yes

WUD not increasing?

Stop

NoF=F4=50

Stop

Yes

Stop

Stop

Yes

F=F1=0

Yes F=F2=10

F=F3=25

Yes

No No

No in this case also implies “do not know” if a safety assessment was not performed for waste storageWUD = radioactive waste unsuitable for disposal

Start

Are you safely storing your

waste?

No


processing waste for

storage exist (~99%)?

No


processing WUD for

disposal exist (~99%)?

Does WUDnot exist and estimated that it

will not appear in the future?

Yes

WUD not increasing?

Stop

NoF=F4=50

Stop

Yes

Stop

Stop

Yes

F=F1=0

Yes F=F2=10

F=F3=25

Yes

No No

No in this case also implies “do not know” if a safety assessment was not performed for waste storageWUD = radioactive waste unsuitable for disposal

*

** is it

***

*

** is it

***

Figure 1: Guidance for Calculating the Form Factor (Flowchart 1) Page ISD-8

Start

Has the disposal site been approved & does

the design of the disposal facility exist?

Is the disposal facility

operational?

Are both WND and WID not increa ng?

Stop

Stop

StopE=E4=50Stop

No

No

Yes

Yes

Yes

No

E=E1=0

E=E2=10

E=E3=25

WND = radioactive waste not in disposalWID = radioactive waste improperly disposed

Start




operational?


Stop

Stop

StopE=E4=50Stop

No

No

Yes

Yes

Yes

No

E=E1=0

E=E2=10

E=E3=25

Start




operational?


Stop

Stop

StopE=E4=50Stop

No

No

Yes

Yes

Yes

No

E=E1=0

E=E2=10

E=E3=25

WND = radioactive waste not in disposalWID = radioactive waste improperly disposed

***

si

***

***

si

***

si

***

Figure 2: Guidance for Calculating the Endpoint Factor (Flowchart 2) Page ISD-9

Table I. Information necessary to compute indicator and availability of information in the NEWMDB

Questions from flowcharts 1 and 2 Explanation of the questions

1. Are you safely storing your waste? To get a “Yes” answer, the answers to all the following questions must be “Yes”:

Question: Did you perform an assessment of existing and future waste regarding safe storage*?

* Safe Storage: Waste is safely stored if, for the conditions and time of storage, packages remain retrievable (without package degradation that would cause significant health, safety or environmental impacts).

Question: Did the assessment show that existing waste is safely stored?

Question: Did the assessment show that existing waste will continue to be safely stored under the conditions and time of storage?

Question: Did the assessment show that future waste will be safely stored?

2. Does the capability of processing waste to a form suitable for storage exist (~ 99% of the waste)?

Note: 99% is a guide – it indicates that the capability exists for most waste.

Note: for waste that is suitable for storage as generated (it does not need to be processed), a Yes answer applies.

To get a “Yes” answer, the answers to all the following questions must be “Yes”:

Question: Are the technology and know-how for processing all waste* to forms suitable for storage available?

* All waste means 99% of volumes and activities of all existing and future waste unsuitable for storage (see the column to the left).

Question: Are financial and human resources available?

Question: Are the necessary processing facilities licensed for operation?

3. Does waste unsuitable for disposal (WUD) not exist and is it estimated that WUD will not appear in the future?


Question: Did you perform an assessment regarding the safe disposal condition of the waste existing in storage and of waste already disposed?

Page ISD-10

Questions from flowcharts 1 and 2 Explanation of the questions Note: For waste in storage, it must be in a form suitable for the intended repository until the time of retrieval from storage and emplacement into the repository. For waste disposed, it must have been in a form suitable for disposal at the time of its emplacement in the repository.

Question: Did the assessment of existing waste show that all this waste is in a suitable condition for disposal?

Note: An assessment might indicate that some waste had been improperly disposed (WID = waste improperly disposed) in currently operated or previously operated repositories if disposal practices do not meet present day standards.

Question: Did you perform an assessment regarding the safe disposal condition of future waste?

Question: Did the assessment indicate that all the future waste would be suitable for disposal?

4. Does the capability for processing WUD to forms suitable for disposal exist (~ 99% of the waste)?

Note: 99% is a guide – it indicates that the capability exists for most waste.

Note: for waste that is suitable for disposal as generated (it does not need to be processed), a Yes answer applies.


Question: Are the technology and know-how for processing all WUD* to forms suitable for disposal available?

*All WUD means 99% of volumes and activities of all existing and future waste unsuitable for disposal (see the column to the left)

Question: Are financial and human resources available?

Question: Are the necessary processing facilities licensed for operation?

5. Is the volume of WUD not increasing?


Question: Have you compared the existing volumes of WUD with past volumes of WUD? Question: Does the result of the assessment show that no increase has occurred? Question: Have you compared the existing volumes of WUD with predicted future volumes of WUD? Question: Does the result of the assessment show that no increase is expected to occur in the near future, e.g. in the next 2 to 5 years?

Page ISD-11

Questions from flowcharts 1 and 2 Explanation of the questions

6. Has the disposal site(s) been approved and does the design of disposal facility(ies) exist?


Question: Has the disposal site(s) been approved by the regulatory authority?

Question: Has the design of the disposal facility(ies) been completed?

Question: Has the application for construction approval been submitted to the regulatory authority?

7. Is the disposal facility(ies) operational?

To get a “Yes” answer, the answer to the following question must be “Yes”:

Question: Has the facility been approved for operation by the regulatory authority?

8. Are WND* and WID** not increasing?

*WND: Radioactive waste not in disposal **WID : Radioactive waste improperly disposed


Question: Have you compared the existing volumes of WND and WID with past volumes of WND and WID?

Question: Does the result of the assessment show that no increase has occurred?

Question: Have you compared the existing volumes of WND and WID with predicted future volumes of WND and WID?

Question: Does the result of the assessment show that no increase is expected to occur in the near future, e.g. in the next 2 to 5 years?

Page ISD-12

REFERENCES

[1] “Report of the United Nations Conference on Environment and Development”, United Nations General Assembly Report A/CONF.151/26, 28 September 1992.


[3] G.W. Csullog, H. Selling, R. Holmes and J.C. Benitez, “The Net Enabled Waste Management Database in the Context of an Indicator of Sustainable Development for Radioactive Waste Management”, International Conference on Issues and Trends in Radioactive Waste Management, Vienna, Austria, December 9-13, 2002.

[4] G.W. Csullog, A. Petö, D. Tonkay and R. Burcl, “The Net Enabled Waste Management Database in the Context of Radioactive Waste Classification”, International Conference on Issues and Trends in Radioactive Waste Management, Vienna, Austria, December 9-13, 2002.

[5] G.W. Csullog, I. Pozdniakov, G. Petison, V. Kostitsin, U. Shah, M.J. Bell, “The IAEA’s Net Enabled Waste Management Database: Overview and Current Status” , International Conference on Issues and Trends in Radioactive Waste Management, Vienna, Austria, December 9-13, 2002.


[7] G.W. Csullog, W.E. Falck, and S.T.W. Miaw, “The IAEA Perspective on International and National Radioactive Waste Management Information Systems”, Proceedings of the “International Symposium on the Management of Radioactive Waste from Non-Power Applications - Sharing the Experience”, Malta, November 2001, IAEA (in preparation).

[8] common home page for the WMDB and NEWMDB http://www-newmdb.iaea.org/start.asp

Page ISD-13

OVERVIEW REPORT: Consolidated Radioactive Waste Inventory

Currently there is no single, publicly available source of information about worldwide quantities of radioactive waste. The first issue of the new Agency report series entitled “Radioactive Waste Management Status and Trends” [1] indicated that the Agency decided to implement a suite of information systems related to quantities of radioactive waste in its Member States. One of those systems is the Net Enabled Waste Management Database (NEWMDB).

One of the fundamental features of the NEWMDB is that it allows Member States to report their waste inventories according to the waste classification scheme(s) used in their own countries. However, the NEWMDB requires Member States to describe how their waste classification scheme(s) compare with the one proposed by the Agency [2]. Member States use the NEWMDB’s waste class matrix tool to make this comparison.

Member States participating in submitting information to the NEWMDB were asked to appoint a single point-of-contact, called a Country Co-ordinator, to interact directly with the NEWMDB’s Programme Officer. Country Co-ordinators are responsible for completing the waste class matrix on behalf of their country.

The NEWMDB’s matrices allow the Agency to transpose Member States’ waste inventories according to the Agency’s waste classes in order to compile a radioactive waste inventory using a single waste classification scheme.

For a number of years, the Agency has had an objective to compile a comprehensive radioactive waste inventory in its Member States. However, the results of a May 2002 consultants’ meeting at Agency headquarters indicated that the compilation of a comprehensive inventory is, for the foreseeable future, extremely difficult, if not impossible, to achieve. The consultancy reported the following:

1. Currently, there is no single source of radioactive waste inventory data from all countries using radioactive material. The Agency has the broadest membership of these countries, and therefore, it is in the best position to compile an international radioactive waste inventory. A consolidated inventory of radioactive waste in Agency Member States would represent the vast majority of radioactive waste around the world.

2. National infrastructures for radioactive waste management differ between Member States, e.g. some may have very mature regulatory processes, while others are just starting to put an infrastructure in place. Because of these differences, compiling nationally-based information into a common information system is difficult. Therefore the Agency is taking the following approach: • Agency staff have concluded that radioactive waste encompasses such a

broad area, that it is very difficult to develop a single data source approach, • The Agency has developed the NEWMDB to compile some of this diverse

information from Member States and to translate waste inventory information according to a common waste classification scheme, and

• Existing information is found in multiple sources both at the Agency and in Member States. Some of these sources of information, and others to be developed, are needed to complement the NEWMDB to report a more complete radioactive waste inventory.

IAEA/WMDB/4 Page INV-1

3. The initial implementation of the NEWMDB did not lead to compilation of a comprehensive inventory due to two distinct reasons: (1) limited participation by Member States, and (2) the scope of the NEWMDB’s data collection. Limited Participation: Collecting radioactive waste management data and submitting it to the NEWMDB as requested by the Agency is done on a goodwill basis. A total of 51 out of about 130 Member States nominated Country Coordinators for the NEWMDB’s first data collection cycle (about 40% of Agency Member States). Of the 51 Member States with Country Coordinators, 19 (at time of writing this had increased to 20) made full submissions and 2 made partial submissions (about 15% of Agency Member States). There was a variety of reasons for the limited participation of Member States with Country Coordinators that included, among others, a lack of technical knowledge, poor Internet access, the priority assigned by the Member State, and other issues preventing submittal. Full and effective cooperation by Member States is required during future data collection cycles to support the compilation of a consolidate inventory.

Scope of Data Collection The intended scope of the NEWMDB was to have Agency Member States report radioactive waste stored or disposed in waste management facilities according to their own national waste classification scheme(s). In recognition of the differences in understanding of definitions for radioactive waste management terms in Member States (e.g., storage, “interim” storage, etc), the following guidance was provided: • Waste in the midst of processing or in “interim” storage (as defined in the

NEWMDB’s glossary) was not to be reported, e.g., typically 1 year or less, because of the added burden on waste reporting this could cause. This waste is likely to represent a small fraction of a country’s radioactive waste inventory. The exception was HLW in “interim” storage at reprocessing facilities.

• Spent nuclear fuel was not to be reported because some Member States do not consider spent nuclear fuel as waste and some Member States do not want to report spent nuclear fuel inventories publicly no matter what its status. However, most, if not all, countries are willing to have their spent fuel inventories reported when consolidated with other fuel in publicly available summary reports.

• In situ waste was not to be reported, e.g., bulk-contaminated facilities/equipment and abandoned/contaminated sites because of differences in classification (in some countries it is not waste) and difficulties in estimating quantities.

• Exempt/clearance waste was not to be reported because it no longer meets the definition of radioactive waste. In addition, inventories of waste being held in delay/decay storage until they become clearance waste was not to be reported.

• Technology-Enhanced Naturally Occurring Radioactive Material (TE-NORM) was not to be reported because there is no international consensus


on whether this material is radioactive waste. This also includes Naturally Occurring Radioactive Material (NORM).

• Uranium mine and mill tailings (UMMT) were not to be reported because the large volume of these low concentration wastes could mask the other radioactive waste and due to difficulties in estimating quantities of UMMT wastes.

• Intentional discharges, e.g., water or air emissions, to the environment were not to be reported because they do not meet the definition of waste in a waste management facility.

• Special fissionable materials, e.g., plutonium, were not to be reported because they may be considered a resource and not waste.

4. Exceptions and variations to the scope of the NEWMDB occurred based on differences in interpretation of NEWMDB guidance for submissions. These differences, noted below, impact upon the compilation of the inventory and need to be addressed in future data collection cycles: • At least one Member State did not report the inventory for some of the

waste classes defined in its waste matrix, even though the information was available. For example, France has a waste class with very low concentrations (1-100 Bq/g) of radionuclides. France did not want to assimilate this waste into the Agency’s LILW-SL category, so the inventory of this waste class was excluded from the data submission (the inventory was, however, included as a comment in NEWMDB submission). The waste results from D&D type activities and will be disposed in a dedicated, “VLLW” disposal facility.

• Because of the waste classification matrix, at least one Member State did not know how to interpret how a particular waste fit into the Agency waste classification scheme, so it did not report the waste. This highlights the problem with the classification of waste - different countries have different interpretations of how to use the matrix and the Agency waste classification scheme is not complete and not rigorous. This issue needs to be addressed to resolve problems experienced by Member States.

• France did not report HLW and LILW-LL resulting from reprocessing of foreign spent nuclear fuel in their NEWMDB submittal. The waste is stored in France’s reprocessing facility awaiting return to the country of origin. NEWMDB guidance was to report all HLW at processing facilities, not just the domestic portion. This approach is different from the one used by the EC in its waste inventory survey. The issue needs to be resolved (for both HLW and LILW-LL).

• The NEWMDB requirement was to report spent/disused sealed radioactive sources (SRS) in dedicated SRS management facilities, as dedicated is defined in the NEWMDB’s glossary. For the initial submittal, there were different interpretations of the reporting requirements. Ireland interpreted the guidance that a factory or hospital could be the site and a storage area within the site as a facility, and therefore SRS stored there would be reported to the NEWMDB. The USA reported disused sealed sources collected and stored in a government facility pending disposal, and not at factories or hospitals throughout the country. France did not provide


information on disused sealed sources pending verification of their inventory and categorization according to the Agency’s new categorization scheme. There are differences in understanding and interpretation of guidance by some Member States on how to report SRS in the NEWMDB which needs to be addressed in the future. The NEWMDB Programme Officer reported that this area was the most problematic area and required significant attention.

• For disposal facilities, the NEWMDB contains the following two options for selection: Sea dumping (sea bed disposal) Sea dumping (deep sea disposal) Even though sea disposal is not practiced, Member States were to report waste that had been disposed (however, this guidance was not provided in the NEWMDB on line Help). No submission included information on inventories from sea dumping, which is understandable.

• Countries may not report waste volumes consistently (some countries use actual package volumes, some may use the volume of the waste excluding container or overpack, some may report displacement volume in storage/disposal, etc). This issue should be raised in the inventory report and dealt with over time to ensure consistency in reporting.

5. Based on the current scope of the NEWMDB, the following observations were made: • The Agency maintains databases for power and research reactor spent

nuclear fuel and publishes summary reports. The Agency should consider adding a “waste flag” for spent nuclear fuel declared as waste. The fuel databases could then be used by the Agency to compile a consolidated inventory of spent nuclear fuel declared as waste to report summary statistics. A separate module added to the NEWMDB for compilation of spent nuclear fuel declared as waste by some Member States is not recommended. Internal experience at the Agency has found that collecting spent nuclear fuel data in a separate NEWMDB module is not likely to be successful.

• The NEWMDB does not cover UMMT sites or in situ “wastes” at radioactively contaminated sites. The Agency has a project called the Directory of Radioactively Contaminated Sites (DRCS) for collecting various data on contaminated sites, with plans to use the same data structure for UMMT sites. The DRCS is under development and will provide geographical and other information on contaminated sites throughout the world. The DRCS will not contain the type or level of information that would be needed to develop a radioactive waste inventory for contaminated sites or for UMMT sites, since it is extremely difficult to estimate these in situ inventories or residues at UMMT sites, whether or not these residues are considered to be wastes. As such, currently there is no consolidated source of information about wastes at UMMT sites or at radioactively contaminated sites.

• The NEWMDB does not cover discharges to the environment, since the scope of the NEWMDB is waste within waste management facilities


(confine and contain option and not dilute and disperse option). The Agency has begun a discharge/release data collection initiative within its Safety Programme by asking Member States for country contacts. This programme is the recommended data collection point on discharges and release information. It has the potential to estimate the world wide inventory of radionuclides released into the environment, which would complement the information on confine and contain wastes.

• In the immediate future, the only information source that could supplement NEWMDB data in support of a the consolidated radioactive waste inventory would be spent nuclear fuel databases with a “waste flag”.

• In addition to providing the Agency with consolidated information on radioactive waste inventories, there are benefits to Member States from participating in NEWMDB data collection cycles. Developing a national inventory of radioactive waste is a difficult task. This difficulty is not always fully appreciated within a Member State. The NEWMDB project provides an opportunity for Member States, who may or may not have national waste inventory reporting requirements, to share lessons learned, discuss common issues and definitions, and to understand the nuances in developing national inventories.

• While many Agency Member States do not report to international organizations other than the Agency, some Agency Member States, e.g. those that are in the EU or members of the OECD, have additional international radioactive waste reporting requirements. The information in the NEWMDB could be used to satisfy some of the national reporting requirements called for in section II.2(b) of the “Guidelines Regarding the Form and Structure of National Reports” for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention). NEWMDB reports could also satisfy other radioactive waste management information requests, e.g. the European Commission, which would avoid duplication of efforts. Country Coordinators for the NEWMDB could be encouraged to interact with those individuals in their own country who are preparing reports for the Joint Convention and other international organizations to inform them of the information and reports available in the NEWMDB.

6. Even with a low participation rate, the results of the first cycle indicated that: • The NEWMDB is a suitable tool for the compilation of a international

radioactive waste inventory according to a unified waste classification scheme, within the limitations described above, and

• Many Member States do not have waste classification schemes at all or they have schemes that are not quantitative and/or not disposal based. As a result, many of the 51 Country Co-ordinators had difficulty specifying how their countries classified their wastes and/or in comparing their waste classification schemes with the Agency’s proposed waste classification scheme. This is an issue that needs to be addressed if the Agency is to successfully prepare a consolidated inventory of radioactive waste in its Member States.


Another limitation for preparing a consolidate radioactive waste inventory report is that not all Member States can report waste inventories as of the same reporting date. Please refer to the following from the NEWMDB’s on line help:

http://www-newmdb.iaea.org/showhelp.asp?Topic=2-1-4

As such, for initial NEWMDB data collection cycles, the consolidated inventory will not be based on all Member States reporting inventories as of the same date.

The Agency issued a Note Verbale to its Member State Missions on February 14, 2002 announcing the poor response to the first data collection cycle and requesting that more Member States appoint Country Co-ordinators and complete submissions during the second data collection cycle, scheduled for July 2002 to January 2003.

The following presents the first consolidated radioactive waste inventory for Agency Member States that prepared submissions to the NEWMDB in the first data collection cycle. At the time of writing, 20 full and 2 partial database submissions had been made. However, one submission was not approved for publication and, therefore, the inventory data from this submission is not included in the first consolidated inventory.

Lastly, the first consolidated inventory is presented subject to all the limitations and caveats discussed previously. As such, it should be interpreted solely as an indicator of what the Agency can prepare for dissemination if it obtains the full and effective co-operation of its Member



States and when consistent, traceable radioactive waste information is submitted to the NEWMDB by Agency Member States.

The First Consolidated Radioactive Waste Inventory

Methodology

1. Agency Member States define the waste classification schemes used in their countries and they compare these schemes with the Agency’s proposed common classification scheme. This is accomplished using the NEWMDB’s waste class matrix tool; see the example that follows:

2. Member States report radioactive waste inventories according to their own waste classes, see the example that follows:

3. The Agency transposes the inventories that were reported according to Member State waste classes into inventories reported according to the Agency’s common waste classes. The following example is based on the two previous images.


Class C LLW volume = 4223 m3 Class C LLW = 75% LILW-SL and 25% LILW-LL (according to matrix) therefore, Class C LLW is “equivalent” to 3167.25 m3 LILW-SL and 1055.75 m3 LILW-LL The above is repeated for all radioactive waste inventories reported to the NEWMDB NOTE: This conversion should be taken as a first order approximation due to ambiguities inherent in the Agency’s common classification scheme. NOTE: With the transposition process, the Agency will not report individual inventories that have been transposed. Instead, all transposed inventories are “rolled up” into totals. See Table I.

4. Member States report their inventories of spent/disused sealed radioactive sources (SRS) that are in dedicated SRS management facilities, where dedicated is defined as follows in the NEWMDB’s on line glossary: dedicated: used in the NEWMDB to indicate a facility for managing sealed radioactive sources (SRS) within the following scope: (1) encompasses all SRS, not just disused or spent SRS (2) the only wastes processed, stored or disposed by the facility are disused and/or spent SRS declared to be waste or the facility has a programme to track the location and characteristics of all SRS in the facility The intent of the definition is to help ensure that Member States can report the inventory of SRS at waste management sites, which may be difficult or impossible to do for facilities at sites in which not all SRS are tracked individually. See the example that follows:


5. The Agency reports the total of the SRS. See Table II. Please also refer to the “Guide to Reading Member State “Country Waste Profile” Reports”, which is included as part of this fourth Radioactive Waste Management Profiles report.


Note: The information in the following tables is subject to all the limitations and caveats discussed previously. As such, it should be interpreted solely as an indicator of what the Agency can prepare for dissemination if it obtains the full and effective co-operation of its Member States and when consistent, traceable radioactive waste information is submitted to the NEWMDB by Agency Member States.

Table I: First Consolidated Radioactive Waste Inventory (volume of waste in m3)

STORAGE DISPOSAL CLASS unprocessed processed unprocessed processed LILW_SL 331428 99526 9609586 1207704 LILW_LL 186631 46942 11123 8317 HLW 360143 2225

Table II: First Consolidated SRS Inventory (numbers of sources)

HALF LIFE RANGE # of category I sources # of category II sources # of category III sources < 30 years 13094 9322 1940 > 30 years 17061 2947

Table III: List of Countries whose Information is Included in Tables I and II Country Number of Operating Nuclear

Power Plants SRS Information Included

(Yes/No) Argentina 2 No (see note below) Belarus 0 Yes Chile 0 Yes Cuba 0 Yes Ecuador 0 No Finland 4 No France 59 No Germany 19 No Greece 0 No Hungary 4 Yes Islamic Republic of Iran 0 Yes Kuwait 0 Yes Peru 0 Yes Romania 1 No Slovak Republic 6 No Spain 9 No Tunisia 0 Yes Turkey 0 Yes Ukraine 13 No United States of America 104 Yes

Note: Argentina provided SRS information to the NEWMDB as part of its submission. This information was provided as a database “attachment” – it was not entered into the database via SRS data entry screens. The information could not be processed for inclusion in Table II.


References




OVERVIEW REPORT: Status and Trends in Radioactive Waste Management

In 2001, the Agency published the first issue of a new report series entitled, “Radioactive Waste Management Status and Trends” [1]. The first issue contained the following text:

“…the Agency attaches a high importance to the dissemination of information that can assist Member States with the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support the nuclear fuel cycle and nuclear applications.

This status and trends report has been issued in support of the Agency’s strategy. It also represents the start of a process to improve the reporting of status and trends in radioactive waste management.

Previously, reports on status and trends in radioactive waste management had been issued as part of the Agency’s Yearbook, which was last published in 1997. These reports contained mainly anecdotal information that was assembled by Agency staff in the course of regular programme activities. As such, the structure and content of status and trends reports changed from year-to-year. In addition, the reports did not rely principally on quantitative data to support their assessments of status and trends.

The structure of the current report was derived with the intent of developing a formal framework for the assembly of information in radioactive waste management. The objectives were:

1. to identify subject areas deemed to be of interest to Member States and the Agency,

2. to report the status of and trends in radioactive waste management according to these subject areas, and

3. to base this reporting, to the greatest extent practicable, on quantitative data.

Objectives 1 and 2 have been met by the current report. However, currently, quantitative data are not available at a sufficient level to achieve objective 3. This issue is addressed in Section 10…”

Section 10 in the first issue of the status and trends report focused on the role of the NEWMDB in support of objective 3.

At the time the first issue of the status and trends report was published, the first data collection cycle with the NEWMDB was underway. Since that time, the first data collection cycle concluded (it took place from July 2001 to March 2002) and the second issue of the status and trends report was issued [2].

The second issue of the status and trends report benefited to some extent from the data submitted by Member States to the NEWMDB. But, due to the low number of submissions (20 full, 2 partial), the statement “currently, quantitative data are not available at a sufficient level to achieve objective 3” is still quite applicable. However, progress was made towards achieving objective 3.

IAEA/WMDB/4 Page S&T-1

The results of the first data collection cycle for the NEWMDB indicate that:

• The NEWMDB can be used to collect and disseminate information about the implementation of national systems for radioactive waste management in a concise manner that would be easy to digest by policy and decision makers. However, with the low response rate for the first data collection cycle, too few data were collected to draw broad conclusions. The results obtained were not rigorously assessed because a “lessons learned” process is required to clarify some of the questions and responses. The results are presented in subsection 11.1 of the second issue of the status and trends report. The results are also summarized in the Overview Report Scorecard for National Systems for Radioactive Waste Management within this fourth issue of the Radioactive Waste Management Profiles report.

• The NEWMDB can support the compilation of a radioactive waste inventory in IAEA Member States. The inventory would be based on a common waste classification scheme. However, the compilation of a comprehensive inventory cannot be supported by the NEWMDB alone. In addition, the full and effective co-operation of IAEA Member States is needed to support the compilation of the inventory. This subject is discussed in detail in subsection 11.2 of the second issue of the status and trends report. The results are also summarized in the Overview Report Consolidated Radioactive Waste Inventory within this fourth issue of the Radioactive Waste Management Profiles report.

• The NEWMDB can be used to compile some of the same information that is required for Contracting Party reports for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management [3]. The strategy is that relevant and publicly accessible information submitted to the NEWMDB could be used to form part of Joint Convention reports, thereby allowing dual reporting with a single effort. This issue is discussed in detail in the Overview Report The Joint Convention and the NEWMDB within this fourth issue of the Radioactive Waste Management Profiles report.

• The NEWMDB can be used to collect and compile some of the nationally-based information that would be needed by countries to compute the newly developed Indicator of Sustainable Development for Radioactive Waste Management (ISD-RW). Countries that prepare NEWMDB submissions should be able to calculate the ISD-RW based on those submissions plus supplemental information that is likely to be available. This issue is discussed in detail in the Overview Report Indicator of Sustainable Development for Radioactive Waste Management within this fourth issue of the Radioactive Waste Management Profiles report.

• The NEWMDB is an effective tool to routinely collect and disseminate information about the status of radioactive waste processing methods (see Figure 1), inventories of waste in storage (see Figure 2) and inventories of waste disposed (see Figure 3) in Agency Member States.

The NEWMDB is the only publicly available, international source of information about the management and inventories of spent/disused sealed radioactive sources (SRS) when these sources are declared to be or are managed


as radioactive waste and categorized according to the IAEA’s newly published source categorization scheme, see Figure 4 [4]. Due to the low participation rate in the first NEWMDB data collection cycle, the amount of information about these SRS is limited. The full and effective co-operation of Member States is required during future NEWMDB data collection cycles to ensure that more data become available.

Figure 1: Example of Waste Processing Information Submitted to the NEWMDB

Figure 2: Example of Waste Storage Information Submitted to the NEWMDB


Figure 3: Example of Waste Disposal Information Submitted to the NEWMDB

Figure 4: Example of SRS Information Submitted to the NEWMDB


• The NEWMDB allows Member States to customize how they submit information to the database. This feature was incorporated into the NEWMDB based on problems encountered by Member States with the Agency’s previous waste management database, the WMDB. For WMDB submissions, some Member States stated that they could not “fit” their information into the rigid structure of the WMDB.

Customization involves: • defining the number of reporting groups • specifying the waste classification scheme used by each group (a reporting

group can be assigned one and only one classification scheme) • identifying the waste management sites in each reporting group (a waste

management site must have at least one waste processing, storage or disposal facility) and specifying their attributes (name, license holder)

• identifying the waste management facilities at the site and specifying their attributes (such as name, description, type, …)

Figures 5a through 5c provide examples of how Member States customized their submissions to the NEWMDB.

Over time, as information is routinely collected from Agency Member States, trends in radioactive waste processing, storage, disposal and SRS management can be established.

• In the General Information section of the NEWMDB, Member States submit information about regulator(s), regulation(s) and milestone(s) associated with radioactive waste management. Figures 6 to 8 provide examples of submissions. The General Information section also contains a “policy questionnaire” – this questionnaire supports the collection and dissemination information about the implementation of national systems for radioactive waste management (please refer to the first bullet on Page S&T-2). Over time, as information is routinely collected from Agency Member States, trends in the status of radioactive waste management infrastructures in Member States can be established.


Figure 5a: Example of Customizing an NEWMDB Submission (Chile)


Figure 5b: Example of Customizing an NEWMDB Submission (France)


Figure 5c: Example of Customizing an NEWMDB Submission (USA)


Figure 6: Example of Regulators Reported in an NEWMDB Submission (USA)


Figure 7: Example of Regulations Reported in an NEWMDB Submission (Germany)


Figure 8: Example of Milestones Reported in an NEWMDB Submission (Hungary)

References




[4] “Categorization of Radiation Sources”, International Atomic Energy Agency Technical Document, IAEA-TECDOC-1191, IAEA, Vienna, December 2000 (corrected March 2001).


OVERVIEW REPORT: The Joint Convention and the NEWMDB

One of the objectives for developing the NEWMDB was to conform, to the greatest extent practicable, with the reporting requirements of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the Joint Convention) [1]. Contracting Parties to the Joint Convention are required to “establish… …guidelines regarding the form and structure of the national reports to be submitted pursuant to Article 32”.

The use of an international database, like the NEWMDB, to collect the full scope of information required under Joint Convention reporting requirements is currently not feasible. Member States would have to expend a great deal of effort to provide the full scope of information to the NEWMDB and in many cases they may not be able (or may be unwilling) to report this information within the requirements of NEWMDB data collection cycles. The objective set out was “to conform, to the greatest extent practicable, with the reporting requirements of the Joint Convention”. The extent of this conformance is described next.

When the Agency’s Waste Management Database (WMDB) was upgraded to the NEWMDB, a number of objectives were established for the NEWMDB. Tables I and II summarize how the initial version of the NEWMDB meets the objective related to the Joint Convention. Please refer to the Overview Report Consolidated Radioactive Waste Inventory of this fourth Radioactive Waste Management Profiles report for a detailed discussion on the scope of data collection for the NEWMDB and deviations from that scope during the first data collection cycle held July 2001 to March 2002.

The first data collection cycle has shown that the NEWMDB can be used to collect some of the information required for Contracting Party reports under the Joint Convention. As such, Member States that are Contracting Parties and that also participate in NEWMDB data collection cycles could include information from NEWMDB reports in their Contracting Party reports to minimize the costs and efforts for reporting.

A major reason for seeking conformance with the Joint Convention is that the availability of Contracting Party reports is a decision that will be made by the Contracting Parties themselves. If the decisions are made that (a) the reports will not be publicly available and (b) reporting will only be done under the Joint Convention and not to the NEWMDB, much of the information that would be publicly available via the NEWMDB would disappear from the public domain. This would be contrary to Agency activities to improve the availability of waste management information. Please refer to the INTRODUCTION of this fourth Radioactive Waste Management Profiles report for additional discussions on the importance of publicly available information on radioactive waste management.

The use of the NEWMDB by Agency Member States that are also Contracting Parties to the Joint Convention to assist with reporting to the Joint Convention is a matter strictly determined by individual Contracting Parties.

References


IAEA/WMDB/4 Page JC-1

Table I: Joint Convention Objective versus Information to be Collected with the NEWMDB WMDB Upgrade Objective Is the objective met by the NEWMDB, version 1? take into account, to the greatest extent practicable, reporting requirements stipulated in the Joint Convention Note 1: The NEWMDB does not include spent fuel storage facilities or uranium mining and milling facilities. Note 2: waste in storage in Member States will be reported to the NEWMDB subject to the limitations cited in Table II. Note 3: Please refer to the limitations cited in Table II. Note 4: Activity is reported qualitatively by way of classification (such as LILW-SL, LILW-LL, HLW). Note 5: Specific radionuclides will be reported only for spent, sealed radioactive sources. Note 6: Information about facility decommissioning status in Member States is managed in another Agency database, the Nuclear Fuel Cycle Information System.

• spent fuel management policy ...................................... .• spent fuel management practices .................................. .• radioactive waste management policy .......................... .• radioactive waste management practices ...................... .• criteria used to define and categorize radioactive

waste ............................................................................. .• a list of the spent fuel management facilities subject

to this Convention, their location, main purpose and essential features........................................................... .

• an inventory of spent fuel that is subject to this Convention and that is being held in storage and of that which has been disposed of ................................... .

• a list of the radioactive waste management facilities subject to this Convention, their location, main purpose and essential features .......................................

• an inventory of radioactive waste that is subject to this Convention that - is being held in storage at radioactive waste management and nuclear fuel cycle facilities ..............- has been disposed........................................................- has resulted from past practices...................................

• this inventory shall contain a description of the material ..........................................................................and other appropriate information available, such as: volume or mass,.............................................................activity ...........................................................................specific radionuclides ....................................................

• a list of nuclear facilities in the process of being decommissioned and the status of decommissioning activities at those facilities.............................................

No No Yes Yes

Yes

No

No

see Note 1

see Note 2 Yes see Note 3 Yes

Yes see Note 4 see Note 5

see Note 6

Please refer to the Overview Report Consolidated Radioactive Waste Inventory of this fourth Radioactive Waste Management Profiles report for a detailed discussion on the scope of data collection for the NEWMDB and deviations from that scope during the first data collection cycle held July 2001 to March 2002.


Table II: Waste to be Included/Excluded from the Initial NEWMDB Data Collection Cycles waste excluded included low specific activity (LSA) waste in situ moved (1) abandoned/contaminated sites X exempt/clearance waste X spent fuel X UMMT/TE-NORM waste X discharges to the environment X special fissionable materials that are considered a resource (e.g. Pu) X remediation waste in situ moved (2) waste awaiting transfer to ”disposition option” that is available X (3) HLW at processing facilities X (4)

(1) LSA waste that is moved to a “licensed waste management facility”, i.e., storage/disposal, will be included (2) waste generated during remediation of a site and moved to a “licensed waste management facility” is included - waste that remains in situ is excluded (the former may be accurately quantified, the latter may not) (3) to avoid the possibility of double accounting, waste that is awaiting transfer to an available “disposition option” is excluded from the NEWMDB. Examples are hospitals & research centres carrying out what is often referred to as “interim storage” prior to transfer of the waste to a central facility (either storage or disposal). Waste that is being held because there is no disposition option, e.g., greater than class C waste held at reactor sites in the US, would be included in the NEWMDB as inventory because a disposition option is not available. (4) HLW at processing facilities (vitrified, cemented) should be reported by the facility holding the waste as of the “reporting date” for the NEWMDB. While this waste may be considered as part of (3), they should be reported to avoid missing “significant” waste in any given reporting cycle. Please refer to the Overview Report Consolidated Radioactive Waste Inventory of this fourth Radioactive Waste Management Profiles report for a detailed discussion on the scope of data collection for the NEWMDB and deviations from that scope during the first data collection cycle held July 2001 to March 2002.


OVERVIEW REPORT: Scorecard for National Systems for Radioactive Waste Management

The following describes some of the mechanisms that have been used up to now to document national radioactive waste management programmes:

The Agency’s Waste Management Database (WMDB) The report, “Radioactive Waste Management Profiles - Compilation of Data from the Waste Management Database, No. 3” [1] is a summary and compilation of waste management data collected from Member States from February 1998 to December 1999 in response to the Agency’s 1997/98 WMDB Questionnaire. The report contains information about national programmes in 55 IAEA Member States. The information was collected from Member States as free-format text. The information is difficult to evaluate and to make comparisons between countries because the format of each submission is unique.

Waste Management Symposium In 1997, WM Symposia Incorporated issued a CD-ROM based report entitled “International Waste Management: A Compendium of Programs and Standards” [2]. This report provides an overview of waste classification schemes used in 18 countries. In addition, the 18 countries provided national overviews of (a) sources of radioactive waste, (b) the regulation of radioactive waste, and (c) radioactive waste management activities.

Nuclear Energy Agency’s Nuclear Waste Bulletin The Nuclear Waste Bulletin [3] of the Nuclear Energy Agency (NEA) provides concise information on current activities, policies and programmes in NEA Member countries and within other international organizations. The Bulletin does not include an exhaustive description of national programmes, rather it provides yearly updates. The Bulletin encourages readers to go back to the information given in previous bulletins and, if necessary, to contact national correspondents in order to obtain more complete information.

The Radioactive Waste Management Committee of the NEA [4] and its two technical sub-groups provide an overall forum for information exchange amongst national programmes. Information exchanges are accomplished through written reports on activities within national programmes and through discussions amongst the national representatives. Main meetings, which occur once a year, provide opportunities for discussing a variety of issues. Meetings usually have a large block of time devoted to one technical topic at which several presentations are given and then discussed in detail. These discussions provide each participating member with an in-depth view of advanced programmes in the particular subject. Detailed technical work is carried out by means of working groups, topical sessions, workshops or symposia, and technical reviews. Working groups produce state-of-the-art reports and detailed analyses. Workshops and symposia provide opportunities for in-depth information exchange, communications and discussion of new ideas and hypotheses. The NEA publishes the proceedings of these workshops and symposia.

IAEA/WMDB/4 Page NS-1

Radioactive Waste Management in the European Union

In 1999 June, Directorate General XI of the European Commission (Environment, Nuclear Safety and Civil Protection) published a CD ROM entitled “Radioactive Waste Management in the European Union” [5]. The CD ROM contains information on the origins and classification of waste and details of waste management programmes and regulations in 15 European Union countries.

While the mechanisms described above provide extensive detail on national systems for radioactive waste management, they do not provide information in a concise manner that would be easy to digest by policy and decision makers. This issue has been addressed by the NEWMDB.

The NEWMDB provides a simple, easy-to-use method for Member States to indicate the status of the development and implementation of their national systems for radioactive waste management. The General Information section of the NEWMDB contains a “policy questionnaire”. Instead of free-form text, Member State representatives simply point-and-click to select the appropriate answers to policy questions. Figure 1 shows some of the policy questions.

The intent of the questions is to assess the status of and the trends for various aspects of national systems for managing radioactive waste. With the low response rate for the first data collection cycle (July 2001 to March 2002), too few data have been collected to date to draw broad conclusions. The results obtained were not rigorously assessed because a “lessons learned” process is required to clarify some of the questions and responses.

Table I lists the various policy questions along with the results from the first NEWMDB data collection cycle. The results are reported “as-is” to familiarize the reader with the questions asked and to indicate the number of responses to the various questions. The results are reported only for cases where the status of the overall submission by a Member State (known as the Country Waste Profile) and the General Information section of the submission were set to “Approved by Admin” by the database administrator.

The second collection cycle (July 2002 - January 2003), which asks IAEA Member States that did not contribute to the first cycle to do so for the second, is expected to provide enough additional information to begin the assessment process.


Figure 1: Example Policy Questions in the NEWMDB


Table I: Responses to “General Information” Policy Questions

Has your Country implemented a national policy for radioactive waste management? Yes: 71% Partially: 29% No: 0% # of responses: 21

Has your country developed strategies to implement a national policy? Yes: 75% Partially: 25% No: 0% # of responses: 20 (see note below)

Has your country identified the parties involved in the different steps of radioactive waste management? Yes: 80% Partially: 20% No: 0% # of responses: 20

Has your country specified a rational set of safety, radiological and environmental protection objectives? Yes: 85% Partially: 15% No: 0% # of responses: 20

Has your country implemented a mechanism to identify existing and anticipated radioactive wastes? Yes: 65% Partially: 25% No: 10% # of responses: 20

Has your country implemented controls over radioactive waste generation? Yes: 85% Partially: 15% No: 0% # of responses: 20

Has your country identified available methods and facilities to process, store and dispose of radioactive waste on an appropriate time-scale? Yes: 80% Partially: 20% No: 0% # of responses: 20

Has your country taken into account interdependencies among all steps in radioactive waste generation and management? Yes: 75% Partially: 25% No: 0% # of responses: 20

Has your country implemented appropriate research and development to support the operational and regulatory needs? Yes: 65% Partially: 25% No: 10% # of responses: 20

Has your country implemented a funding structure and the allocation of resources that are essential for radioactive waste management? Yes: 60% Partially: 20% No: 20% # of responses: 20

Has your country implemented formal mechanisms for disseminating information to the public and for public consultation? Yes: 50% Partially: 40% No: 10% # of responses: 20

NOTE: Table I was extracted from Table 11-I in the report “Radioactive Waste Management Status and Trend”, report IAEA/WMDB/ST/2 (September 2002). During the preparation of this Overview Report, some errors were discovered in Table 11-I. The highlighted data indicates corrected data.


Table I: Responses to “General Information” Policy Questions (Part 2)

Indicate whether or not the following responsibilities have been defined in your country according to IAEA Safety Series No. 111-S-1

Member State Responsibility

establish and implement a legal framework for the management of radioactive waste

Complete: 60% Incomplete: 40% # of responses: 20

establish or designate a regulatory body that has the responsibility for carrying out the regulatory function with regard to safety and the protection of human health and the environment


define the responsibilities of waste generators and operators of waste management facilities


provide for adequate resources Complete: 60% Incomplete: 40% # of responses: 20

Regulatory Body Responsibility

enforce compliance with regulatory requirements


implement the licensing process Complete: 95% Incomplete: 5% # of responses: 20

advise the government Complete: 90% Incomplete: 10% # of responses: 20

Waste Generator and Operators of Waste Management Facilities Responsibility

identify an acceptable destination for the radioactive waste


comply with legal requirements Complete: 90% Incomplete: 10% # of responses: 20



To indicate whether or not waste generators and operators of waste management facilities have the responsibility to manage radioactive waste safely, the following policy questions were asked in theGeneral Information section of the NEWMDB. The NEWMDB states “…To indicate the status for implementing the responsibility to "manage radioactive waste safely" in your country, please answer the [following] questions…”. Note: One Member State indicated that it had difficulty with the questions because the option of “partially” was not included.

Does your country perform safety and environmental impact assessments for radioactive waste management facilities?

Yes: 85% No: 15% # of responses: 20

Does your country ensure adequate radiation protection for workers, the general public and the environment?


Does your country ensure suitable staff, equipment, facilities, training and operating procedures are available to perform the safe radioactive waste management steps?


Does your country establish and implement a quality assurance programme for the radioactive waste generated or its processing, storage and disposal?


Does your country establish and keep records of appropriate information regarding the generation, processing, storage and disposal of radioactive waste, including an inventory of radioactive waste?


Does your country provide surveillance and control of activities involving radioactive waste as required by the regulatory body?


Does your country collect, analyze and, as appropriate, share operational experience to ensure continued safety improvements in radioactive waste management?


Does your country conduct or otherwise ensure appropriate research and development to support operational needs in radioactive waste management?




Please indicate if any of the following are part of your Country's current waste disposal facility Licensing Policy Environmental Assessment (EA) Yes - All: 75% Yes - Some: 10% No: 15% # of responses: 20 Environmental Impact Statement (EIS) Yes - All: 75% Yes - Some: 15% No: 10% # of responses: 20 Performance Assessment (PA) Yes - All: 65% Yes - Some: 25% No: 10% # of responses: 20 Quality Assurance (QA) Yes - All: 70% Yes - Some: 5% No: 25% # of responses: 20 Safety Assessment (SA) Yes - All: 90% Yes - Some: 5% No: 5% # of responses: 20 If Quality Assurance is part of your Country's current, waste disposal facility licensing policy, does the QA Program conform to international standards (such as the ISO9000 series)? Yes - All: 73% Yes - Some: 27% No: 0% # of responses: 15 Does your Country have formal, documented waste acceptance criteria for its operating disposal facilities? Yes - All: 40% Yes - Some: 25% No: 35% # of responses: 20 Does your Country have any written policies to address the maintenance of records that describe the design, location and inventory of waste disposal facilities? Yes: 50% No: 50% # of responses: 20 If the answer to the previous question was YES, does your Country have any policies, laws or regulations that prescribe what records are to be maintained? Yes: 70% No: 30% # of responses: 10 Does your Country have any written policies to address active institutional controls or passive institutional controls, such as monitoring or access restrictions? Yes: 40% No: 60% # of responses: 20 If the use of active institutional controls is part of your Country's written policies, please indicate which of the following practices are either implemented or are being considered access restrictions Yes: 88% No: 13% # of responses: 8 drainage and/or leachate collection system(s) Yes: 63% No: 38% # of responses: 8 leachate treatment systems Yes: 50% No: 50% # of responses: 8 environmental monitoring Yes: 88% No: 13% # of responses: 8 facility monitoring Yes: 88% No:13 % # of responses: 8 Surveillance Yes: 88% No: 13% # of responses: 8 plans for intervention measures during active institutional control if there is an unplanned release of radioactive materials from the disposal facility Yes: 63% No: 38% # of responses: 8



The following policy questions are related to pre-disposal waste management

Does your country have written policies or written procedures for waste sorting/segregation?


Does your country have written policies or written procedures for waste minimization?


Does your country have written policies or written procedures for waste storage?


Does your country have written policies or written procedures for processing and/or storing and/or disposing of nuclear fuel cycle waste separately from non-nuclear fuel cycle waste (also known as nuclear applications waste)?


Does your country have any legislation, regulation, or policy that waste processing must take place prior to storage? NOTE: The statement above implies wastes that require processing should not be placed into storage facilities (except for short-term, interim storage awaiting processing) in an unprocessed state for significant periods, where significant is defined by the regulatory body.


Does your Country have any waste processing facilities at the same location where the waste is generated?


Does your Country have any centralized waste processing facilities?


Does your Country have any mobile waste processing facilities?




The following NEWMDB policy questions are related to the management of spent and/or disused sealed radioactive sources (SRS) Is there a national level registry? Yes: 91% No: 10% # of responses: 21 If answer was yes, is the registry used only for disused/spent SRS?


Are there regional-level registries (one or more)?


If the answer was yes, are any registries used only for disused/spent SRS?


Are there local-level registries (one or more)?


If the answer was yes, are any registries used only for disused/spent SRS?


Does your Country have documented procedures in place to ensure that sealed radioactive sources (SRS) are transferred to secure facilities in a timely manner after their user declares them to be spent?


Does your Country have any agreements in place whereby spent sealed radioactive sources (SRS) are returned to their supplier by the user (check all options that apply)?

Government - Government agreements Yes: 0% No: 100% # of responses: 20 Government - Supplier agreements Yes: 10% No: 90% # of responses: 20 Supplier-User agreements Yes: 86% No: 14% # of responses: 21

Do any agreements include suppliers that are outside of your Country?

Yes: 76% No: 24% # of responses: 21 (see note below)

Does your Country have any regulations to free-release spent sealed radioactive sources (SRS)? (see note below table)


Has your Country disposed of spent SRS in existing disposal facilities for LILW or HLW waste?


Does your Country plan to dispose of spent SRS in existing or planned disposal facilities for LILW or HLW waste?


Has your Country implemented dedicated disposal facilities for spent SRS?


Does your Country have plans to implement dedicated disposal facilities for spent SRS?



Many Member States use the term free-release to indicate release from regulatory control or clearance.



Additional NEWMDB policy questions Does your Country have laws or Regulations restricting either the import or export of radioactive waste (excluding spent fuel)?

Yes: 86% No: 14% # of responses: 21 (see note below)

Does your Country have laws or Regulations restricting either the import or export of spent fuel?


Does your Country have high-level liquid wastes in storage?


If your Country has high-level liquid wastes in storage, are there documented plans in place to process these liquids?

Yes - All: 75%

Yes - Some: 0%

No: 25%

# of responses: 4

If your Country has high-level liquid wastes in storage, are there plans to have this waste be processed within a specified time frame?

Yes - All: 50%

Yes - Some: 25%

No: 25%

# of responses: 4

If the answer to the previous question is Yes, what year is this processing planned to be completed (format = YYYY)

2005 (two countries) 2020 (one country)

Does your Country have any Uranium Mine and Mill Tailings sites that do not have a designated authority to manage them?


If the answer to the previous question was yes, are there any regulations or plans for regulations to ensure that UMMT sites have a designated authority?


Does your Country require that funds should be set aside in support of future waste management activities, such as decommissioning activities?

Yes - All: 55%

Yes - Some: 25%

No: 20%

# of responses: 20

Does your Country require a time frame for the decommissioning of nuclear fuel cycle facilities once these facilities cease operation?

Yes - All: 15%

Yes - Some: 15%

No: 70%

# of responses: 20

Does your Country require a time frame for the decommissioning of non-nuclear fuel cycle facilities once these facilities cease operation?

Yes - All: 15%

Yes - Some: 20%

No: 65%

# of responses: 20



References

[1] “Radioactive Waste Management Profiles - Compilation of Data from the Waste Management Database, No. 3”, International Atomic Energy Agency Report IAEA/WMDB/3, Vienna, April 2000.


[3] “Nuclear Waste Bulletin - Update on Waste Management Policies and Programmes”, No 14 – 2000 Edition, Organization of Economic Co-operation and Development/Nuclear Energy Agency, Paris, 2001.

[4] Internet home page of the Radioactive Waste Management Committee of the Nuclear Energy Agency, http://www.nea.fr/html/rwm/rwmc.html/.

[5] “Radioactive Waste Management in the European Union”, European Commission Directorate General XI - Environment, Nuclear Safety and Civil Protection, Brussels, Belgium, CD ROM, June 1999.


http://www.nea.fr/html/rwm/rwmc.html/

Guide to Reading

Member State “Country Waste Profile” Reports

(from the IAEA’s Net Enabled Waste Management Database)

for further information, please contact the Responsible Officer via e-mail: [email protected]

This document was prepared as a sub-document for the report “Radioactive Waste Management Profiles No 4 – a compilation of data from the Net Enabled Waste Management Database”,

International Atomic Energy Agency report IAEA/WMDB/4 (2002)

IAEA/WMDB/4 Page Guide-1

mailto:[email protected]

Guide to Reading Member State “Country Waste Profile” Reports

The Net Enabled Waste Management Database (NEWMDB) is the International Atomic Energy Agency’s main tool for collecting and disseminating information about radioactive waste management activities and waste inventories in Agency Member States. This guide explains how data are collected with the NEWMDB and it explains the format of NEWMDB reports.

The NEWMDB is an on line database [1]. Only authorized users are permitted to enter and modify data in the database. On October 3, 2000 and again on February 14, 2002, the Agency issued Notes Verbale asking Agency Member States to appoint a single point-of-contact, known as a Country Co-ordinator (CC), to interact with the NEWMDB’s Programme Officer. The Programme Officer establishes user accounts for CCs, who can, in turn, designate and register other users, Report Co-ordinators (RCs) and Waste Experts (WEs), to assist them with their NEWMDB submissions. Country Co-ordinators are responsible for the quality of data and completeness of information provided in NEWMDB data submissions.

The NEWMDB’s on line Help provides extensive detail about the purpose, scope and limitations, and use of the NEWMDB [2]. Additional details of the current scope and limitations of the NEWMDB are described in Reference [3] and in the Overview Report Consolidated Radioactive Waste Inventory of this fourth Radioactive Waste Management Profiles report.

A data submission, full or partial, is known as a Country Waste Profile. A submission is completed when it is first “Approved by CC” and then “Approved by Admin”, where “Admin” is the NEWMDB Administrator (currently, this is the NEWMDB Programme Officer).

After completing a submission to the NEWMDB, CCs indicate which report pages are to be made publicly accessible. For partial submissions, where some data were not available for input to the NEWMDB, some report pages cannot be made publicly accessible (NEWMDB rules prevent the publication of report pages that include incomplete data). Once a CC has finished designating which report pages are to be public and which are to be private (private means the pages are only viewable by authorized users within a Member State and by the NEWMDB Administrator and Programme Officer), the Administrator sets the submission status to Published, which allows public pages to be viewed by everyone, as described next.

Access to on line, publicly available NEWMDB reports is accomplished via the following web page:


On the cited web page, users click on the Reports link (see next):

The Reports link will display the following web page:



As indicated above, Public Users must sign in to access publicly available reports. To do this, users click on the “Sign in” link shown above, which will display the following web page:

To register as a Public User, the form shown above is completed and then the user clicks the REGISTER button. A confirmation e-mail is sent to the user. The e-mail contains the following information:

From: NEWMDB - Waste Management Database Contact Point Sent: Wednesday, 30 October, 2002 11:25 To: Lastname, Firstname Subject: NEWMDB reports Public User registration Please use the following link to confirm your NEWMDB registration and to proceed with accessing NEWMDB reports. http://www-newmdb.iaea.org/activate.asp?key=XXXX LINK to activate registration Note: for some e-mail systems, users will have to copy the link and then paste it into the Address line (Internet Explorer) or Location Line (Netscape) of their browser.

Users must use the link to access the NEWMDB the first time. The link will display the following web page:


http://www-newmdb.iaea.org/activate.asp?key=XXXX

Once signed in, Public Users can access repoas shown in the graphic above. A descriptionReports” link in the list.

The “NEWMDB Reports” link provides acceand Acrobat PDF versions of reports. The top

On line reports provide quick access to iunderstand the significance of the on line NEWMDB's On Line Help using the link nereports provide full details of the scope of explain the NEWMDB's reporting format.

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Page Guide-4

This fourth Radioactive Waste Management Profiles report contains a compilation of publicly available NEWMDB reports that are based upon submissions to the NEWMDB during the first data collection cycle, which was held July 2001 to March 2002. The reporting year for the first cycle was 2000. The following is from the NEWMDB’s on line help (http://www-newmdb.iaea.org/showhelp.asp?Topic=2-1-4):

The following describes the data submission process and the reports that are created based on data submitted.

The NEWMDB was implemented as a series of components that requires authorized users to input and approve information in a step-wise process, as indicated in Figure 1.

Step 1

usersmatrices

Step 2

structuregen info

CC Admin CC Admin

Step 3

“wastedata”

APPROVALS APPROVALS

Figure 1: Steps in the NEWMDB Data Submission Process




Step 1: Country Co-ordinators input their contact information and they register RCs and WEs to assist with data submission (optional). Next, CCs use the waste class matrix tool to identify all waste classification schemes used in their country and to compare these schemes with the IAEA’s proposed waste classification scheme [4]. The waste class matrix tool is described in both the INTRODUCTION and the Overview Report Consolidated Radioactive Waste Inventory of this fourth Radioactive Waste Management Profiles report.

Contact information for users is not published in publicly available reports. Only Agency staff and authorized users in a given country may view the contact information for users from that country. The information that is entered into waste class matrices is published in publicly available reports. See Figure 2 for an example and Table I for an explanation of the example.

Table I: Explanation of the Waste Class Matrix Report in Figure 2 Item in Fig. 2 Description (A) Member States were asked to identify the waste classification schemes they use and to

compare these schemes with the IAEA proposed waste classification scheme [4]. However, some Member States do not have formally recognized waste classification schemes. Some have schemes that cannot be readily compared with the IAEA scheme. For these Member States to be able to make a submission to the NEWMDB, they were given the option of indicating that they use the Agency scheme for the purposes of reporting to the NEWMDB. A few Member States have adopted the Agency scheme for use. Given this situation, Member States had to indicate whether or not they use the Agency waste classification scheme. Figure 1 indicates that the USA does not use the Agency’s waste classification scheme.

(B) and (C) Figure 2 provides an example of a Member State that defined at least one waste class matrix, since it does not use the IAEA’s common waste classification scheme. The example shows that the USA uses two waste classification schemes. One (USDOE) is used to classify wastes generated and managed by the US Department of Energy and another (USNRC) is used to classify waste generated by Nuclear Power Plants. Therefore, the CC for the USA defined two waste matrices that indicate the relationship between waste classes used in the USA (LLW, TRU, CLASS A LLW, etc.) and the IAEA’s waste classes (LILW-SL, LILW-LL and HLW). The Comments and Attachments features of the NEWMDB were used by CCs to indicate whether or not the identified waste classes are required by any law/regulation and also how the relationship (%) between waste classes was determined.


(A)

(B)

comment

attachment (this is a hyperlink to the attachment in the on line report)

(C)

Figure 2: Example Waste Class Matrix Report (please see Table I) Note: Attachments can be made “visible for public” or “invisible for public”. If the state is “visible”, users can click on the hyperlink for the attachment and can view the attachment (this assumes that the user is reading the on line version of the report and has an active connection to the Internet). Please also note, users must have the appropriate software to view the attachments since they are provided in a format that is preferred by the Member State / Country Co-ordinator that provided the attachment.


The matrix tool provides support for the Joint Convention [5] requirement that “For each Contracting Party the report shall also address its... ...criteria used to define and categorize radioactive waste”.

Country Co-ordinators are unable to proceed to Step 2 until waste class matrices are approved by them and by the NEWMDB Administrator (see Figure 1). Step 1 proved to be a major stumbling block for many CCs [6].

Step 2: CCs customize how information about radioactive waste management programmes and inventories will be reported to the NEWMDB. This feature was added because a number of respondents to the 1997/98 Waste Management Database (WMDB) questionnaire stated that they found it difficult to “fit” their information into the WMDB’s rigid structure. With the NEWMDB, CCs define the number of Reporting Groups and within each Reporting Group they identify the waste management sites and waste management facilities (processing, storage, disposal and dedicated spent/disused sealed radioactive source (SRS) management facilities). For facilities, CCs indicate attributes such as type, capacity, percent filled, etc.

The NEWMDB on line help page http://www-newmdb.iaea.org/showhelp.asp?Topic=6-4-100 states the following:

Some Member States opted to prepare national level submissions in which information was “rolled up”. This type of submission provides less detail about individual sites and facilities. The CCs for these Member States created theoretical sites, such as Sites = “All Sites” for France and Site = “National” for Germany.

Step 2 includes the “General Information” component where CCs identify who regulates radioactive waste, the laws and regulations that are relevant to radioactive waste management, significant milestones in radioactive waste management in their countries, and radioactive waste management policies. CCs answer up to 80 policy related questions (some questions are conditional “if” questions, where “Yes” answers require additional questions to be answered).

The following describes the NEWMDB reports that are based on Step 2.

Figure 3 indicates that two Reporting Groups were defined for the submission from Hungary. Table II explains the information in Figure 3.


http://nesisda2/newmdb/showhelp.asp?Topic=6-4-100

Table II: Explanation of the Reporting Groups Overview Report in Figure 3

Item in Fig. 3 Description (A) short name of the Reporting Group

(B) the date to which the radioactive waste inventories are reported for waste management

sites in the Reporting Group Not all countries can report radioactive waste inventories according to the same date. In some countries, Reporting Groups may have different reporting dates. Therefore, Member States are allowed to indicate the date to which their inventories are reported on a group-by-group basis. For the first data collection cycle, the latest date to report inventories was December 2000.

(C) the waste class matrix used by the Reporting Group a Reporting Group must be assigned one, and only one, waste class matrix

(D) brief description of the Reporting Group (E) the waste management site(s) in the Reporting Group

The following is from the NEWMDB’s on line glossary (http://www-newmdb.iaea.org/showhelp.asp?Topic=8-1-1)

Waste Management Site For reporting to the NEWMDB, a Waste Management Site is (a) limited to sites licensed under nuclear or radioactive materials regulations of the Member State and (b) includes at least one waste management facility. With regards to licensing, the identified facilities could be covered under the license of another facility, such as a nuclear reactor.

(F) list of the types of waste management facilities at each site The following is from the NEWMDB’s on line glossary

Waste Management Facility 1. a facility specifically designated to handle, treat, condition, store or dispose of radioactive waste.

2. any facility or installation the primary purpose of which is radioactive waste management, including a nuclear facility in the process of being decommissioned only if it is designated by the Contracting Party as a radioactive waste management facility. [Joint Convention definition - not recommended for IAEA publications]

The on line database pages allow the user to select various reports. The list of reports includes short names that fit within the width of the column that contains the list. The red arrow indicates the maximum column width; short names (up to 10 characters) fit within the allowed width.



(A)(B)

(C)(D)

(E) (F)

Figure 3: Example of Reporting Group Overview Report (please see Table II)

Together, Figures 4a to 4c provide an example of a Site Structure report. The contents of the report depends upon the types of waste management facilities that were specified for the site (processing, storage, disposal and/or dedicated spent/disused sealed radioactive source (SRS) management facilities). The following is from the NEWMDB’s on line glossary:

dedicated used in the NEWMDB to indicate a facility for managing sealed radioactive sources (SRS) within the following scope: (1) encompasses all SRS, not just disused or spent SRS (2) the only wastes processed, stored or disposed by the facility are disused and/or spent SRS declared to be waste or the facility has a programme to track the location and characteristics of all SRS in the facility The intent of the definition is to help ensure that Member States can report the inventory of SRS at waste management sites, which may be difficult or impossible to do for facilities at sites in which not all SRS are tracked individually.

Table III explains the information in Figures 4a to 4c.


http://www-newmdb.iaea.org/showhelp.asp?Topic=8-1-1&










Table III: Explanation of Site Structure Report in Figures 4a to 4c

Item in Fig. 4a

Description

(A) short name of the waste management site (see Table II for a discussion of short names) (B) full name of the site (C) location of the site

The Agency does not allow the publication of locations that specify geographical co-ordinates. In addition, CCs can select whether or not they want locations to be made publicly available.

(D) license holder(s) for the site (E) list of waste processing facilities at the site

A site may not have any processing facilities, therefore a site structure report may not list any such facilities (E1): short name of processing facility (E2): description of the facility (E3): type of facility (treatment and/or conditioning) The following is from the NEWMDB’s on line glossary: processing any operation that changes the characteristics of waste, including pretreatment, treatment and conditioning

pre-treatment any or all of the operations prior to waste treatment, such as collection, segregation, chemical adjustment and decontamination

treatment operations intended to benefit safety and/or economy by changing the characteristics of waste. Three basic treatment objectives are: - volume reduction; - removal of radionuclides from the waste; and - change of composition.

conditioning operations that produce a waste package suitable for handling, transport, storage and/or disposal

Conditioning may include the conversion of the waste to a solid waste form, placement of the waste in containers and, if necessary, providing an overpack.

Note: the definition of conditioning is currently under review at the IAEA (as of Oct 2001) to remove an inherent ambiguity related to putting waste into containers. The placement of raw waste into a container to facilitate shipment to a processing facility should not be considered to be conditioning. For the 1st data collection cycle, containerization was not included in the list of conditioning methods (pending the results of the review of the definition of conditioning).

(F) list of waste storage facilities at the site A site may not have any storage facilities, therefore a site structure report may not list any such facilities (F1) short name of storage facility (F2): description of the facility (F3): list of the types of storage units at the facility

The following is from the NEWMDB’s on line help:


Items (4) through (8) in the graphic above are described in the continuation of this table (see next page). For the first data collection cycle, the list of storage unit types included the following:

building bunkers cask cave concrete pad container (HIC) container (ISO) container (marine) mound not in list pit pool shaft silo tank (concrete) tank (other) tank (stainless steel) tile hole trench (lined) trench (unlined) well

Interactions between CCs and the NEWMDB Programme Officer, notably at international workshops held October 21 to 23, 2002 (Vienna, Austria) and November 4 to 6, 2002 (Las Vegas, Nevada, USA), indicated that not all CCs interpreted items (5) through (8) the same way (despite the descriptions indicated on the next page). In addition, several CCs reported that if they “rolled up” information by not identifying individual storage units and/or not identifying individual facilities, they could not properly use items (4) to (8) since these parameters vary from unit-to-unit and facility-to-facility and totals or overall values were meaningless.

The above indicates that the NEWMDB reports based on the NEWMDB’s first data collection cycle may include inconsistent information. This issue will have to be addressed to ensure that CCs have a common, consistent interpretation of NEWMDB submission requirements and/or that the NEWMDB is re-designed to eliminate such inconsistencies.


Item in Fig. 4b

Description

(A) list of waste disposal facilities at the site A site may not have any disposal facilities, therefore a site structure report may not list any such facilities

(B) short name of disposal facility (see Table II for a discussion of short names) (C) description of the facility

the information shown here is

from the NEWMDB’s on line help


(D) type of disposal facility For the first data collection cycle, the list of disposal facility types included the following:

borehole engineered near surface engineered surface geological (cavern) geological (deep bore hole)

rock cavern rock cavern (mountain / hill)

rock cavern (under sea, land access)

sea dumping (deep sea disposal)

sea dumping (sea bed disposal)

trenches

Sea dumping was included for historical disposals since sea dumping is no longer practiced. No countries reported waste disposed of at sea during the first NEWMDB data collection cycle. Interactions between CCs and the NEWMDB Programme Officer at an international workshop held October 21 to 23, 2002, indicated that sea dumping may have to be handled as a special case. This might be accomplished by referencing national or international reports that include inventories of waste disposed at sea. However, the issue is complicated by the fact that unique waste classifications were used. This issue needs to be addressed in future data collection cycles.

(E) indicates if the disposal facility is modular or not The following is from the NEWMDB’s on line help:

Yes indicates that additional disposal units can be added to increase the available capacity. No indicates that the disposal capacity is fixed.

(F) the disposal facility capacity for the reporting year (2000 for the first data collection cycle) (G) the planned disposal facility capacity

For modular facilities, the planned capacity is typically higher than the existing capacity. For non-modular facilities, the existing and planned capacity are likely the same.

(H) percent of existing capacity used (Note: some CCs felt that percent of planned capacity should have been used)

(I) depth of the facility 0 indicates at surface, a negative number indicates a facility that rises above the surface, such as a mounded facility

(J) host medium (this reflects the environment around the disposal facility) For the first data collection cycle, the list of host medium types included the following:

crystalline rock (basalt) crystalline rock (gneiss) crystalline rock (granite) crystalline rock (other) salt dome sedimentary (other) sedimentary (salt-dome) sedimentary (sand) sedimentary rock (bedded salt)

sedimentary rock (consolidated clay)

sedimentary rock (plastic clay)

volcanic tuff

(K) classes of waste disposed and/or planned for disposal If both actual and planned are indicated, this means that the waste class has already been disposed and there are plans to continue disposal. If actual is indicated and planned is not, this means that there are no plans to dispose of any more of the identified waste class in the facility.

(L) indicates whether or not spent and/or disused sealed radioactive sources have been disposed in the facility and / or there are plans for future disposal

(M) disposal facility implementation phases Interactions between CCs and the NEWMDB Programme Officer, at international workshops held October 21 to 23, 2002 (Vienna, Austria) and November 4 to 6, 2002 (Las Vegas, Nevada, USA), indicated a need for additional phases to be considered. Of note, Norway reported waste at a facility for the reporting year (2000). However, in 2001 remedial actions were initiated to recover the waste and to move it to another facility. Possible additions to the list of phases include the following:

remediation (no waste recovered)

remediation (some waste recovered)

remediation (all waste recovered)

decommissioned (in lieu of the option to the left?)

operation suspended


Item in Fig. 4c

Description

(A) list of dedicated SRS management facilities at the site (see page Guide-10 for the definition of dedicated) A site may not have any dedicated SRS management facilities, therefore a site structure report may not list any such facilities

(B) short name of the SRS facility (see Table II for a discussion of short names) (C) description of the facility (D) type of SRS facility

For the first data collection cycle, the list of SRS facility types included the following: conditioning storage disposal

(A)(B)(C)

(D)

(E) (E1) (E2)

(E3) in this case, the facility type was not specified

(F)(F1) (F2)

(F3)

Figure 4a: Example of a Site Structure Report (Processing and Storage Facilities)


(A) (B) (C) (D)

(E) (F) (G) (H) (I)

(J)(K)

(L)

(M)

Figure 4b: Example of a Site Structure Report (Disposal Facilities) (Figure 4b is a continuation of the report shown in Figure 4a)

(A) (B) (C)

(D)

Figure 4c: Example of a Site Structure Report (Dedicated SRS Facilities) (Figure 4c is a continuation of the report shown in Figure 4b)

As indicated on page Guide-8, Step 2 includes the General Information section of the NEWMDB where CCs identify who regulates radioactive waste, the regulations/laws that are relevant to radioactive waste management, significant milestones in radioactive waste management in their countries, and radioactive waste management policies. Figures 5 through 7 provide examples of reports associated with regulators, regulations/laws and milestones information entered into the


General Information section of the NEWMDB. Table IV explains the information in Figures 5 to 7. Please refer to the Overview Report, “Scorecard for National Systems for Radioactive Waste Management” in this fourth Radioactive Waste Management Profiles report, which reports the answers to the policy questions from the General Information section.

Table IV: Explanation of the Reports in Figures 5 to 7 Item in Fig. 5

Description

(A) short name of regulator (see Table II for a discussion of short names) (B) full name of regulator (C) division within the regulator

Some regulators may have more than one division. (D) city or town where the regulator is located (E) wastes that are regulated by the regulator

In some countries, not all wastes are regulated by one regulator; therefore CCs can indicate which ones are regulated. Interactions between CCs and the NEWMDB Programme Officer, at international workshops held October 21 to 23, 2002 (Vienna, Austria) and November 4 to 6, 2002 (Las Vegas, Nevada, USA), indicated that some Member States felt that they could not properly use this section of the database since either they do not have formally recognized waste classes or the Regulator regulates all radioactive wastes without explicit identification of classes. A suggestion was made to replace the requirement to “identify which wastes are regulated by the Regulator” with a comment field to allow CCs to provide additional information about their Regulator(s) if they deem it appropriate. This issue will be addressed in future data collection cycles.

Item in Fig. 6

Description

(A) short name of regulation or law (see Table II for a discussion of short names) (B) full name or title of the regulation or law (C) Member State’s reference number (most regulations and laws have a Member State specified

reference number) (D) date the regulation or law was either proclaimed or promulgated (E) used to indicate whether if this is a regulation or law that is cited (F) wastes that are covered by the identified regulation or law

Not all wastes may be covered by a regulation or law; therefore, CCs can indicate which waste classes are covered. Interactions between CCs and the NEWMDB Programme Officer, at international workshops held October 21 to 23, 2002 (Vienna, Austria) and November 4 to 6, 2002 (Las Vegas, Nevada, USA), indicated that some Member States felt that they could not properly use this section of the database since either they do not have formally recognized waste classes or the regulations/laws do not explicitly reference waste classes. A suggestion was made to replace the requirement to “identify which wastes are covered by the regulation or law” with a comment field to allow CCs to provide additional information about their Regulation(s)/Law(s) if they deem it appropriate. This issue will be addressed in future data collection cycles.


Table IV: Explanation of the Reports in Figures 5 to 7 (continued) Item in Fig. 7

Description

(A) and (B)

If a milestone took place within a single year, CCs enter the year into the "Start Year or Reference Year" field. If the milestone spanned 2 or more years, CCs enter the starting year in the "Start Year or Reference Year" field and the end year in the "End Year" field. "End Year" must be greater than "Start Year or Reference Year"

(C) description of milestone (used in the NEWMDB to indicate significant or noteworthy developments, occurrences, or circumstances related to radioactive waste management)

(A)(B)

(C) (D)

(E)

Figure 5: Example of a Regulators Report (Hungary)

(A)(B)

(C)(D) (E)

(F)

Figure 6: Example of a Regulations Report, includes laws (Romania)


(A) (B)

(C)

Figure 7: Example of a Milestones Report (Spain)

Step 3: The “Waste Data” component of the NEWMDB is used by CCs (and those they designate to assist them) to identify waste treatment and conditioning methods at each waste management site (see Table V and Figure 8), to specify the inventory of radioactive waste for each waste class at each waste management site (see Table VI and Figure 9) and to specify inventories of spent/disused SRS in dedicated SRS management facilities at each waste management site (see Table VII and Figure 10). The number and types of data entry screens in Waste Data depends upon the waste classes identified with the waste matrix (or matrices) in Step 1 and the number of waste management sites specified in Step 2.


Table V: Explanation of the Reports in Figure 8 Item in Fig. 8

Description

(A) list of treatment methods at the site or list of conditioning methods at the site (B) name of treatment method or conditioning method (C) implementation/usage status for the treatment or conditioning method (the following is from

the NEWMDB’s on line help): Valid combinations for the status of a method are shown in the table that follows. If the trend for a current treatment method is specified in combination with indicating that it is also a planned or a past practice, the trend selected will be nulled when the SAVE button is clicked.

If Planned = Yes, the Member State plans to use the method in the future but it does not currently use the method nor does it have an R&D programme in place for the method. Database rules require that Planned must be No if R&D = Yes and/or Current = increase, same or decrease (since an active R&D programme implies planned use (if the results of the R&D programme are positive) and Current indicates that the method is currently in use).

R&D = Yes indicates that the Member State has an active research and development programme for the method. The Member State can indicate that it has an R&D programme even though the method is currently in use (e.g., for improving the method).

Current = increase, same or decrease: If the method is currently in use, the Member State indicates if there is a change in usage over the last five years. The values increase, same and decrease are relative, not absolute, indicators. The following illustrates how to select the value:

# of drums to condition # of drums conditioned (%) Case 1 Year 1 1000 1000 (100%) Year 2 200 200 (100%) Year 3 500 500 (100%) Year 4 700 700 (100%) Case 2 Year 1 1000 1000 (100%) Year 2 200 150 (75%) Year 3 800 400 (50%) Year 4 1000 200 (20%)

In case 1, the Member State would indicate Current = same, in case 2, the Member State would indicate Current = decrease.

Past practice = Yes if the Member State had used the method in the past but currently the method is no longer in use.


(A) (C)

(B)

(A)(C)

(B)

Figure 8: Example of Waste Treatment and Conditioning Methods Reports (Slovak Republic)

Table VI: Explanation of the Report in Figure 9 Item in Fig. 9

Description

(A) Inventory report table: Waste management sites are identified for each Reporting Group. Each Reporting Group is assigned a waste class matrix, which identifies one or more waste classes. The inventory report table is used to indicate the total volume of waste for each class of waste at each waste management site in the Reporting Group (if a site has multiple waste management facilities, only the total volume in all facilities is reported).

(B) name of waste class (C) location (storage or disposal) (D) processing status (Yes = waste is processed, No = waste is not processed)

Interactions between CCs and the NEWMDB Programme Officer, at international workshops held October 21 to 23, 2002 (Vienna, Austria) and November 4 to 6, 2002 (Las Vegas, Nevada, USA), indicated that some Member States had difficulty with the processing status data field. Processing includes treatment and/or conditioning; however, if the Member State indicated Yes for the processing status, is the waste treated?, conditioned?, treated and conditioned?, processed to a form suitable for handling?, for storage?, for disposal?… In its current implementation, the processing status only indicates if the waste is “as generated” (unprocessed) or if some treatment and/or conditioning has been performed. The usefulness of the processing status field will have to be evaluated.


(E) volume of waste in m3 Interactions between CCs and the NEWMDB Programme Officer, at international workshops held October 21 to 23, 2002 (Vienna, Austria) and November 4 to 6, 2002 (Las Vegas, Nevada, USA), indicated that some Member States feel it is necessary to indicate the accuracy of the data reported. This will be considered for enhancements to the NEWMDB for future data collection cycles. Note: Member States were asked to not report wastes in “interim storage”, where storage and “interim storage” are defined as follows (from the NEWMDB’s on line glossary):

storage: the holding of spent fuel or radioactive waste in a facility that provides for its containment, with the intention of retrieval. Storage is by definition an interim measure, and the term interim storage would therefore be appropriate only to refer to short term temporary storage when contrasting this with the longer term fate of the waste. Storage as defined above should not be described as interim storage. In the NEWMDB, interim storage applies to waste that is being held for a short time while awaiting transfer to an available disposition option. For example, waste being stored in a processing facility awaiting transfer to an available storage or disposal facility would be considered to be in interim storage. If waste is being storage because there is no place to send it, for example, it is being stored because there is no processing or disposal alternative available, the waste would be considered to be in storage, not in interim storage. In general, the NEWMDB considers temporary to imply periods of less than one year.

Interactions between CCs and the NEWMDB Programme Officer, at international workshops held October 21 to 23, 2002 (Vienna, Austria) and November 4 to 6, 2002 (Las Vegas, Nevada, USA), indicated that not all Country Co-ordinators interpreted this guidance the same way. As such, there are likely to be inconsistencies in reporting inventories. In addition, one Member State reported that the exclusion of waste in interim storage reported internationally would cause deviations from national level reports, which include waste in interim storage. As such, the reporting of waste in interim storage will have to be review for future NEWMDB data collection cycles.

(F) distribution of waste by origin: The purpose of this field is to indicate the amounts of waste that have relatively consistent characteristics versus those that may have more widely varying characteristics. This can be useful for estimating future requirements for managing wastes.

For example, many wastes from nuclear power plants (reactor operations waste) have relatively consistent characteristics. Therefore, a knowledge of today’s wastes can be used to estimate the inventories (volumes, radionuclides, chemical properties, etc) of future wastes. On the other hand, there may be large uncertainties about the characteristics of decommissioning wastes, notably if different types of facilities are to be decommissioned. A knowledge of today’s decommissioning wastes may not be a good indicator of the inventories of future decommissioning wastes.

Many Member States, even those with advancde data management systems, do not track wastes according to the origins indicated. Therefore, the percentages reported are often best estimates.

Interactions between CCs and the NEWMDB Programme Officer, at international workshops held October 21 to 23, 2002 (Vienna, Austria) and November 4 to 6, 2002 (Las Vegas, Nevada, USA), indicated that some Member States had difficulty with estimating the percentages for waste origins, particularly for wastes stored or disposed many years previously. Some indicated that they could estimate part of the waste by origin (e.g. 50% reactor operations and 20% Nuclear Applications) but they could not make reasonable estimates of the distribution by origin for part of their wastes. A solution for future data collection cycles may be to include an option “% unassessed”, which will be considered for enhancements to the NEWMDB.

(G) This field is used to indicate the additional characteristics of wastes. The following shows how this information is entered into the NEWMDB:










The intent of was to have Member States report additional characteristics on a site-by-site basis. However, as explained on page Guide-7, some Member States opted to prepare national level submissions in which information was “rolled up”. In these cases, CCs reported that they had difficulty indicating additional characteristics since the information could be misleading (one site of many may have some toxic wastes, which could not be indicated with rolled up information).

Interactions between CCs and the NEWMDB Programme Officer, at international workshops held October 21 to 23, 2002 (Vienna, Austria) and November 4 to 6, 2002 (Las Vegas, Nevada, USA), indicated that it would be better to replace the check box mechanism with the ability to use comment or attachments to indicate additional characteristics of wastes. This will be considered for enhancements to the NEWMDB.

(A) (F) (C) (B) (D) (E)

(G)

Figure 9: Example of a Waste Inventory Report (USA)


Table VII: Explanation of the Reports in Figure 10

Item in Fig. 10

Description

(A) SRS inventory report table: Spent/disused sealed radioactive sources (SRS) were handled as a special case in the NEWMDB for two reasons:

(1) For some Member States, the only radioactive wastes requiring management are (a) wastes that can undergo delay/decay and be released as non-radioactive waste and (b) spent/disused SRS. Typically the volumes of spent/disused SRS are small but the hazard can be high (such as high activity Co-60 SRS or long-lived radium SRS). If these Member States were to report only volumes of waste (see Figure 9), the low volumes would not be indicative of the risk involved and the waste management efforts needed to deal with SRS.

(2) Accidents with spent/disused SRS account for a significant proportion of all radiation accidents and they can lead to severe injuries or death. Accidents occur because SRS fall out of regulatory or operational control, for example they get lost or abandoned, and they are discovered by persons who are unaware of the risks they pose. Therefore, some Member States felt that it was necessary to include lists of spent/disused SRS in the NEWMDB. However, often there is confusion about the relationship between controlling SRS and the purpose of waste management databases, like the NEWMDB.

The tracking and accounting of individual SRS before they reach waste management facilities is important to ensure that they do not fall out of regulatory or operational control. However, once they reach waste management facilities, there is no strict need to track all SRS individually. For example, some Member States’ waste management facilities accept hospital, university, industrial and/or research facility wastes that contain SRS as a component of waste packages. A 210L drum may contain items such as paper, cloth, and glass contaminated with radionuclides and it may also contain a number of small activity, low hazard SRS. Typically, a package is tracked in a waste management facility, not the individual items in the package. While a package’s characteristics may be entered into a database (such as the amount of Cs-137 in the package), the CS-137 may derive from one or more SRS in the package as well as from other items.

The result is that some waste management facilities may not maintain a complete listing of individual SRS they possess. This is especially true for wastes managed over many years when SRS tracking was not the issue it is today. For many large waste management organizations, “waste is waste” and only “significant” SRS may be tracked individually. These organizations would not be able to report a comprehensive list of the SRS in their storage or disposal facilities.

The previous IAEA database asked Member States to indicate if their lists or SRS were complete. For Member States that responded no, there was no indication how incomplete the information was (10% of SRS, 90% of SRSs, …)

The intent of the NEWMDB was to have Member States provide lists of SRS at their waste management sites only if they could provide a complete listing. Therefore, the definition of a dedicated SRS management facility was introduced for the NEWMDB (see page Guide-9). Interactions between the NEWMDB Programme Officer and CCs for the NEWMDB indicated that there were differing interpretations of the term “dedicated”, therefore there was inconsistent reporting of SRS inventories in the NEWDMB during the first data collection cycle.

The above discussion indicates that the provision of lists of SRS to the NEWMDB will not result in the compilation of a complete list of SRS in Agency Member States since some Member States cannot report complete lists of SRS (and they were discouraged from doing so if they did not have “dedicated” SRS management facilities). For the foreseeable future, the


provision of lists of SRS to the NEWMDB could be considered as a valuable source of information for (a) Member States where spent/disused SRS are the most significant (or only) wastes managed and (b) Member States that report only inventories of highest hazard SRS (such as the SRS inventories reported for the Los Alamos and Hanford sites in the submission by the USA in the first data collection cycle).

The inventories of spent/disused SRS are reported in two groups: (1) SRS with half lives less than or equal to the half life of Cs-137 (30.12 years, nominally indicated in the database as 30 years) and (2) SRS with half lives greater than the half life of Cs-137.

(B) name of radionuclide: Currently, the NEWMDB can only be used to list single radionuclide SRS. A request has been made by some Member States to allow multiple radionuclide SRS. A request has also been made to identify SRS that are neutron generators (such as Am/Be SRS).

(C) number of SRS and their activity: Based on manufacturing data for SRS, Member States were asked to identify SRS according to activity ranges. Item (C) in Figure 10 indicates that there are three activity ranges for radionuclides with half lives less than or equal to 30 years and two ranges for SRS with half lives greater than 30 years. In the Agency’s previous waste management database, Member States were asked to list individual SRS, which can be an enormous burden to do. The NEWMDB allows the input of groups of SRS, where the number of SRS in the group and their total activity is entered. PLEASE NOTE: grouping is according to the activity of individual SRS, it is not according to the total activity of SRS in the group. In the example in Figure 10, the average activity of SRS in a group (the total activity reported for the group divided by number of SRS in a group) must be within the range of activities for the group. The following is the Internet address to an Acrobat PDF file that provides examples of how Member States can group SRS in their NEWMDB submissions:

http://www-newmdb.iaea.org/help/examples.pdf

The activity of SRS or groups of SRS is reported in GBq.

(D) conditioning status: This field indicates whether or not SRS are in an “as generated” state or they have been conditioned (please refer to the discussion on processing status in Table VI). If SRS are grouped, the following combinations are valid: cond = No, uncond = Yes (all SRS unconditioned) cond = Yes, uncond = No (all SRS conditioned) cond = Yes, uncond = Yes (mix of unconditioned and conditioned SRS)

(E) hazard category: At the time NEWMDB development was nearing completion, the Agency issued a technical document entitled, “Categorization of Radiation Sources” (IAEA-TECDOC-1191, December 2000, revised March 2001). This document states:

…the IAEA developed an Action Plan (GOV/1999/46-GC(43)) containing several new initiatives in addition to enhancing existing programmes. One of these is the Categorization of Sources. The wide variety of uses of radiation sources and radioactive materials necessitates the development of some form of categorization so that the controls to be applied will be commensurate with the radiological risks that the sources and materials present. Of particular concern are those radiation sources containing substantial levels of radioactivity which have the potential for causing significant harm to persons in the short term. Such categorization would be relevant to decisions regarding: notification and authorization by registration or licensing; the security requirements during each stage from manufacture, through transport, storage, use, transfer and repair, to decommissioning and disposal; and emergency preparedness. It would also be relevant to any future international databases of lost and found sources and incidents and accidents involving sources….

A internal Agency request was made to include the newly developed source categorization scheme described in TECDOC-1191 into the SRS data entry screen. During the first data collection cycle, the following issues were revealed:

1. Some Member States (such as France) had not categorized their SRS according to the newly published Agency categorization scheme, which prevented them from


http://www-newmdb.iaea.org/help/examples.pdf

entering SRS information into the NEWMDB. 2. The activity groupings (see item C) and the new categorization scheme are not

directly related and, therefore, some Member States had difficulty entering SRS information.

3. At least one Member State asked to have the new categorization scheme removed from the SRS data entry screen since, it was argued, the scheme was developed in relation to the control of sources prior to being received in secure, waste management facilities (“this is a not a waste management issue”).

The continued inclusion of the new source categorization scheme into the NEWMDB needs to be assessed.

(F) total activity: the value in this field is calculated by an NEWMDB algorithm. It is the total activity reported for all radionuclides listed on the same line of the report. The activity is reported in GBq.

(G) decay date: Due to radioactive decay, the activity of SRS decline over time. This is particularly significant for SRS with half lives less than or equal to 30 years, especially for radionuclides like Co-60 (about 5 years). As such, it is common practice to report the activity of SRS as of a particular reference date to allow anyone to calculate the activity of the SRS at any future date relative to the reference date. The decay date field means that the activity cited for the identified SRS or group of SRS is the activity as of the cited date. Interactions between CCs and the NEWMDB Programme Officer at an international workshop held November 4 to 6, 2002 (Las Vegas, Nevada, USA), indicated that some CCs did not enter a decay date when the exact date was not certain. The question was asked, “Would it be better to enter an approximate date than leave the field blank?”. The answer is yes, however, currently the database does not allow CCs to indicate that the date is approximate. This will be considered for enhancements to the NEWMDB for future data collection cycles.


(C)(A) (D) (E)

(B)

(F) (G)

(C)(A)

Figure 10: Example of an SRS Inventory Report (Peru)


References

[1] Common home page for the Waste Management Database (WMDB) and the Net-Enabled Waste Management Database (NEWMDB) http://www-newmdb.iaea.org/start.asp

[2] Top page for the NEWMDB’s On Line Help http://www-newmdb.iaea.org/help.asp




[6] G.W. Csullog, A. Petö, D. Tonkay and R. Burcl, “The Net Enabled Waste Management Database in the Context of Radioactive Waste Classification”, a contributed paper for the International Conference on Issues and Trends in Radioactive Waste Management, to be held in Vienna, Austria, December 9-13, 2002.



Country Waste Profile Reports for Reporting Year 2000

This is the top level document for accessing individual Country Waste Profile reports from the report “Radioactive Waste Management Profiles No 4 – a compilation of data from the Net Enabled Waste Management Database”, International Atomic Energy Agency report IAEA/WMDB/4 (2002). Table I provides links to the individual reports, which are in Adobe Acrobat PDF format (electronic version). For guidance on reading Country Waste Profile Reports from report IAEA/WMDB/4, please refer to the following internet based document:

http://www-newmdb.iaea.org/help/profiles4/guide.pdf

For further information, please contact the NEWMDB Programme Officer via e-mail at the following address:

[email protected]

© 2002, International Atomic Energy Agency

– 2 –

Table I: Links to Individual Country Waste Profile Reports (please see notes after table)

Report Name Country Waste Profile for Argentina Country Waste Profile for Belarus Country Waste Profile for Belgium Country Waste Profile for Chile Country Waste Profile for Cuba Country Waste Profile for Ecuador Country Waste Profile for Finland Country Waste Profile for France Country Waste Profile for Germany Country Waste Profile for Greece Country Waste Profile for Hungary Country Waste Profile for the Islamic Republic of Iran Country Waste Profile for Kuwait Country Waste Profile for Peru Country Waste Profile for Romania Country Waste Profile for the Slovak Republic Country Waste Profile for Spain Country Waste Profile for Tunisia Country Waste Profile for Turkey Country Waste Profile for Ukraine Country Waste Profile for the United States of America

Notes: Only Country Waste Profiles for submissions received during the first NEWMDB data collection cycle are included. One submission from the first cycle is not included because the Member State requested changes to its submissions. The changes were not implemented at the time this 4th Profiles report was created.

Country Waste Profile Report for

Argentina

Reporting year: 2000

This is a sub-document from the report “Radioactive Waste Management Profiles No 4 – a compilation of data from the Net Enabled Waste Management Database”, International

Atomic Energy Agency report IAEA/WMDB/4 (2002)

For guidance on reading Country Waste Profile Reports from report IAEA/WMDB/4, please refer to the following internet based document:


For further information, please contact the Responsible Officer via e-mail:

[email protected]

2002 ©, International Atomic Energy Agency

International Atomic Energy Agency NEWMDB Report

Waste Class Matrix(ces) Used/DefinedCountry: Argentina Reporting Year: 2000Waste Class Matrix: IAEA Def. , Used

The Agency's standard matrixDescription:

© 2000-2002, International Atomic Energy Agency. This page generated at 2002-09-02 11:14:43 (local Vienna time.)


Groups Overview Country: Argentina Reporting Year: 2000Reporting Group: RG1

December 2000Inventory Reporting Date:

IAEA Def.Waste Matrix Used:

This group will inform about the waste inventory located in the only authorized site to manage radwaste in Argentina.The name of the place is Ezeiza Waste Management Area.

Description:

Site Name Processing Storage Disposal Dedicated SRSFacilities Defined

AGE 1 1 3 0

Attachment #148: This is a list with the Spent radioactive sources that have been stored in Ezeiza Management Area (AGE) Storage Facility (M1) during the last years.

File name: AGE_M1_SRS.xls

Member State's Reference # Age_M1_SRS



Country: Argentina Reporting Year: 2000

Page 1 of 2Site Structure: AGE

Full Name: EZEIZA WASTE MANAGEMENT AREA

License Holder(s) :

Processing FacilitiesCOMPACTORThis plant is used to compact low level solid waste in 200 liters drums.

Name Description

Type treatment

Storage FacilitiesM1This facility is used for storing Intermediate level waste, long lived low level waste and also spent/ disused radiation sources that according to the operation license can not be disposed of in the disposal facilities

Name Description

Types of Storage Units Unit Name Type Status Operating

Life (years) % filled Modular

M1 building open20 15 NO

Disposal FacilitiesLLSWTTrench Nª1 (700m3) has been closed with some historic waste in it.Trench Nº2 (1120m3) is in operation. It has been licensed to disposed of 200 litters drums with compacted solid waste, cemented liquid waste and conditioned spent radiation sources.

Name Description

trench(es)TypeFacility is modular

1820Capacity - existing (m3) Capacity -planned (m3) 182090% of

used Depth (m) 1.2

sedimentary (other)Host medium

existingcapacity

Waste Class Actual Planned Waste Class Actual Planned

Disused/spent, sealed radioactive sources (SRS). Yes No

Phase Start Year End Year

LILW-SL Yes No LILW-LL Yes No

HLW No No

planning and/or concept assessment

site selection

design 1974 1988

construction 1974 1988

commissioning 1974 1995

operation 1975 2002

closure 2002 2004

institutional control 2020 2070

OSCAR PEDRO HALUSKAe-mail: [email protected]: (54-11) 4379-8534Fax: (54-11) 4379-8535




Page 2 of 2Site Structure: AGE

LLLWTThere are three semi-containment trenches for low activity liquid wastes. This facility have been used for the semi-containment of very low liquid waste that were not able to be directly discharged as efluents.

Name Description



used Depth (m) 3


existingcapacity


Disused/spent, sealed radioactive sources (SRS). No No


LILW-SL Yes No LILW-LL No No

HLW No No


site selection

design 1968 1970



operation 1971 2001

closure 2002 2004


CPConcrete pits. This facility is considered an alternative for the management of low impact solid waste that according to its activity or geometry can not be disposed of in the existing trenches.Historic waste have been disposed of in them

Name Description

boreholeTypeFacility is modular


used Depth (m) 10


existingcapacity





HLW No No


site selection

design 1968 1970



operation 1969 2020

closure 2020 2020





Page 1 of 1Site Data: AGE

Inventory Reporting Date: December 2000 Waste Matrix: IAEA Def.

Full Name: EZEIZA WASTE MANAGEMENT AREA

Distribution in %RO FF/FE RP NA DF DC/RE

Proc.=Is the waste processed (Yes/No)?RO=Reactor Operations, FF/FE=Fuel Fabrication/Fuel Enrichment, RP=Reprocessing, NA=Nuclear Applications,DF=Defence, DC/RE=Decommissioning/Remediation

Waste Inventory

Class Location Proc. Volume (m3)

Storage No 20 33 0 0 67 0 0LILW-SL

The additional characteristics of the waste: liquid (aqueous); liquid (organic); resin; solid (dispersible); solid (non-dispersible)

Storage Yes 5.4 37 0 0 63 0 0LILW-SL

The additional characteristics of the waste: solid (dispersible); solid (non-dispersible)

Disposal Yes 2714 66 0 0 34 0 0LILW-SL

The additional characteristics of the waste: liquid (aqueous); resin; sludge; solid (dispersible); solid (non-dispersible)

Storage No 20.6 11 53 0 36 0 0LILW-LL

The additional characteristics of the waste: liquid (organic); resin; solid (dispersible); solid (non-dispersible)

Storage Yes 34.3 67 25 0 8 0 0LILW-LL


Disposal Yes 171.8 2 29 12 57 0 0LILW-LL

The additional characteristics of the waste: liquid (aqueous); sludge; solid (dispersible); solid (non-dispersible)

Processing - Treatment method(s) Status

R&D program

Current practicemethod use over the last 5 years

Past Practice Planned

Method

Chemical Precipitation No Yes No

Compaction No No Nosame

Encapsulation Yes No No

Radionuclide Separation No Yes No



REGULATORSCountry: Argentina Reporting Year: 2000

Page 1 of 1

ARNName

Division

Autoridad Regulatoria Nuclear.Full Name

Buenos AiresCity or Town

Matrix IAEA Def. - LILW-SL, LILW-LL, HLWWastes that are regulated by the Regulator



REGULATIONSCountry: Argentina Reporting Year: 2000

Page 1 of 2

LNANName LEY NACIONAL DE ACTIVIDAD NUCLEARTitle or Name

Matrix IAEA Def. - LILW-SL, LILW-LL, HLWWastes that are covered by the identified Law

24804Reference Number 1997-04-23Date Promulgated

or ProclaimedLaw

Act Nª 24804 establishes that the Nuclear Regulatory Authorithy (ARN) is in charge of nuclear regulations and control concerning radilolgical and nuclear safety, safeguards and physical protection, giving in addition, advice to the Executive Power on subjects of its competence. It appoints the National Comission of Atomic Energy - independent from the Regulatory Body - as the responsible organization for radioactive waste management in the country.

Comment #301: National Law of Nuclear Activity

Attachment #149: This document contains the text of the National Law of Nuclear Activity (Spanish version) for Argentina.

File name: LNAN.doc

Member State's Reference # LNAN

RGRRName REGIMEN DE GESTION DE RESIDUOS RADIACTIVOSTitle or Name



or ProclaimedLaw

Act Nº 25018 creates the National Radioactive Waste Management Programme, belonging to the Atomic Energy Commission. This programme deals with the treatment, conditioning, storage, transport and disposal of low, medium and high level radioactive waste, as well with the development and implementation of all mechanisms required to attain their objectives.

Comment #302: National Law of Radioactive Waste Management

Attachment #150: This document contains the text of the National Law of Radioactive Waste Management (Spanish Version) for Argentina.

File name: RGRR.doc

Member State's Reference # RGRR



REGULATIONSCountry: Argentina Reporting Year: 2000

Page 2 of 2

AR 10.12.1Name Gestion de Residuos RadiactivosTitle or Name


ARN 29/99Reference Number 1999-12-01Date Promulgated

or ProclaimedRegulation

Attachment #147: The objective of this document is to establish general requirements for the management of radioactive wastes, taking into account the protection of human health and the environment for both present and future generations.

File name: 10-12-1R0.pdf

Member State's Reference # 10-12-1R0



Belarus







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Belarus Reporting Year: 2000Waste Class Matrix: IAEA Def. , Used


The IAEA classification was recognized as the most appropriate for reporting to the NEWMBD from the EKORES site in connection with the below stated motives.

Due to a number of objective and economical reasons management and regulation of radioactive waste in Belarus, except for “Chernobyl waste”, has been so far performed in accordance with the regulations of the former USSR:- Basic Sanitary rules for working with radioactive substances and other sources of ionizing radiation (OSP - 72/87);- Basic sanitary rules for the Management of Radioactive Wastes (SPORO -85).The last document embodies a classification for radioactive waste which is based:- on dose rate (when measuring in 10 cm from surface ) for solid waste and - on concentration activity (Bq/l) for liquid waste.

The classification has not found an application in Belarus, where all generated wastes are disposed of at the same facility (“Ekores”) in accordance with the acceptance criteria developed for this facility. At the same time the IAEA definitions have been widely used in practice of radioactive waste management despite they have not been adopted officially.

The Draft Strategy for the radioactive waste management in Belarus suggests for consideration a new national classification system, which has been developed in accordance with the recommendation of the IAEA TECDOC-1067 “Organization and implementation of national regulatory infrastructure governing protection against ionizing radiation and the safety of radiation sources, 1999”. The proposed waste classes are quite the same as those proposed in the IAEA Safety Guide 111-G-1.1

Comment #98: Reason for use of IAEA Def. Class



Waste Class Matrix(ces) Used/DefinedCountry: Belarus Reporting Year: 2000Waste Class Matrix:

DWT include low level waste resulting from clean up activity in the territory affected by the Chernobyl AccidentDWI include low level waste resulting from decontamination of industrial (ventilation) equipment at Gomel enterprises.

Description:

ChernDW

Waste Class Name LILW_SL% LILW_LL% HLW%DWT 100 0 0

DWI 100 0 0

As a result of the Chernobyl Accident a total of 46 450 km2 (23 % of the country) of Belarus territory was subjected to radioactive contamination with Cs137 content in soil over 37 kBq/m2. Decontamination and remediation activities in the affected areas just after the accident resulted in thousands of tons of low-level and very low level waste. Currently several tens of tons of such waste are formed annually in the course of clean-up activities in socially important locations and from decontamination of industrial equipment in the affected territory. The levels of radioactivity in part of the wastes are lower than those within IAEA LLW class, and are often in a range of only two orders of magnitude. However, the amounts of the waste are enormous and resulting chronic exposure can be a factor for a great number of people.

The grouping of such waste under a separate category (ChernDW) has been caused by its peculiarities and special requirements needed for their management, quite different from those for existing waste.

The special regulation in force ‘Provisional sanitary rules for the management of decontamination waste of the Chernobyl origin’ (SPOOD-98) define this class of waste as substances which are formed as a result of work to eliminate the consequences of the Chernobyl accident with a view to bring the state of environment in industrial and civil facilities in the contaminated areas to an acceptable radioecological level and which contain more than 0.96 kBq/kg of Cs-137 (for DWT).DW are divided into two different categories, each requiring a separate approach towards selection of processing technologies:

DWT are solid ChernDW, arisen in the course of clean-up activities in the affected areas (removed soil, roofing slate, other building materials)

DWI are solid and liquid ChernDW, generated during clean-up of equipment contaminated owing to intensive work of ventilation systems at Gomel enterprises in the period after the Chernobyl accident.

Comment #99: Origin of CHERW class of waste



Groups Overview Country: Belarus Reporting Year: 2000Reporting Group: Brest


ChernDWWaste Matrix Used:

Construction Amalgamation "Brestoblcelstroi"Description:


Stolin 0 0 1 0

Reporting Group: EKORES



Special enterprise under auspice of Unitary enterprse for waste management "Ekores"

Description:


RWF Ekores 0 1 3 5

Special enterprise “Ekores" is the part of the Unitary Enterprise “Ekores” that is intended for management of municipal waste. It is the only organization in the country that has license for storage/disposal of radioactive waste generated in industry, medical and research institutions.

Comment #145: What is "Ekores" ?

Reporting Group: Polyesie



Republican Specialized Unitary Enterprise "Polyesie"Description:


Complex 1 0 0 0 Khatky 0 0 1 0 Padkamenne 0 0 1 0 Rechky 0 0 1 0 Shepetov 0 0 1 0

Specialized enterprise ‘Polyesie’ was set up in 1992 under the auspices of the Committee for Liquidation of Consequences of the Chernobyl Accident for conducting activity on clean up of the territory, contaminated by the Chernobyl fall-out in Gomel Region. The work includes removal of contaminated soil, decontamination of installations and industrial equipment, dismantling of structures and buildings being not subjected to clean-up. The waste arised from this activity have been named “the decontamination wastes” (hereinafter ChernDW). Since 1992 Polyesie has operated four near-surface repositories, constructed from type designs specially for ChernDW in the Gomel region.

The enterprise also operates a facility for immobilization of liquid waste generated in the process of decontamination of ventilation equipment polluted as a consequences of the Chernobyl accident.

Comment #173: What is Pollyesie enterprise?



Groups Overview Country: Belarus Reporting Year: 2000Reporting Group: RADON



Republican Unitary Specialized Enterprise "Radon"Description:


Gatkov ichy 0 0 1 0 Kalodezsk 0 0 1 0 Kulikovka 0 0 1 0 Lysavka 0 0 1 0

Like the enterprise “Polyesie” in Gomel, a specialized enterprise ‘Radon’ was set up in Mogilev , specially for conducting activity on clean up of the territory, contaminated by the Chernobyl fall-out. The work results in generating “decontamination wastes” (hereinafter ChernDW) which are disposed of in four near-surface repositories, constructed from type designs. According to the existing regulations these repositories are called DWR –2 .They represent territories with one or two reservoirs banked up with embankments 4 m high. The compacted earth bottom and slopes are covered with pugged clay barriers of 0.5 m thick, which are then covered with stabilized polyethylene film. The film is buried with a protective earth layer 0.6 m thick. The repositories are equipped with a net of bore holes along its perimeter.

Comment #178: What is Radon enterprise ?



Country: Belarus Reporting Year: 2000

Page 1 of 1Site Structure: Stolin

Full Name: Stolin Republican Unitary Building Enterprise #32 under Construction Amalgamation "Brestoblcelstroi"

License Holder(s) :

Disposal FacilitiesKasharyRepository for disposal of decontamination waste (type 2)Kashary

Name Description

engineered near surfaceTypeFacility is non modular


used Depth (m) 3

sedimentary (sand)Host medium

existingcapacity




DWT Yes Yes DWI No No


site selection

design 1993 1994



operation 1995

closure

institutional control

Stolin Republican Unitary Building Enterprise #32 under Construction Amalgamation "Brestoblcelstroi"

The site covers one near surface Decontamination Waste Repository (DWR) of type 2 “Kashary” intended for disposal of waste generated in the process of clean up activity in the areas of Brest Province which were contaminated as a result of the Chernobyl Accident. This is one of 8 DWR, constructed from type design specially for Chernobyl waste disposal. All the repositories of this type represent territories with one or two reservoirs banked up with embankments 4 m high. The compacted earth bottom and slopes are covered with pugged clay barriers of 0.5 m thick, which are then covered with stabilized polyethylene film. The film is buried with a protective earth layer 0.6 m thick. The repository is equipped with a net of bore holes along its perimeter

Comment #172: Disposal Facility "Kashary"




Page 1 of 1Site Data: Stolin

Inventory Reporting Date: December 2000 Waste Matrix: ChernDW

Full Name: Stolin Republican Unitary Building Enterprise #32 under Construction Amalgamation "Brestoblcelstroi"



Waste Inventory


Disposal No 3537 0 0 0 0 0 100DWT





Page 1 of 4Site Structure: RWF Ekores

Full Name: Special enterprise for radioactive waste storage/disposal under auspice of Unitary enterprse for waste management "Ekores"

License Holder(s) :

Storage FacilitiesRep #2Repository # 2 for storage of solid low- and intermediate level waste which include also SRS in their biological shielding.

Name Description



Rep #2 trench (lined) open23 82 NO

Disposal FacilitiesKanion 1Kanion 1 is the name of closed "historical" repository #1 which contains variety of unconditioned waste generated by small users.

Name Description



used Depth (m) 3


existingcapacity





HLW No No

planning and/or concept assessment 1958 1960

site selection 1960 1961

design 1961 1962



operation 1963 1977

closure 1977 1977

institutional control 1977

Unitary enterprse for waste management "Ekores", PU Shabany, Selitskogo Str.35, Minsk





Kanion 2Kanion 2 is the name of closed "historical" repository # 2 which contains variety of unconditioned waste generated by small users.

Name Description



used Depth (m) 3


existingcapacity





HLW No No



design 1961 1962



operation 1963 1977

closure 1977 1977


Rep 1Rep 1 is the name of closed repository # 1, which contains variety of conditioned and unconditioned waste generated by small users. It contains also ten containers with irradiated nuclear material.

Name Description



used Depth (m) 3


existingcapacity





HLW Yes No


site selection

design



operation 1977 1992

closure 1992 1993


Dedicated SRSWell1Bore-hole repository for disposal of SRS

Name Description

disposalType





Well2Bore-hole repository for disposal of SRS

Name Description

disposalTypeWell3Bore-hole repository for disposal of SRS

Name Description

disposalTypeWell4Bore-hole repository for disposal of SRS

Name Description

disposalTypeRep 2SSSeveral sections of Rep 2 for storage of solid low- and intermediate level waste which is intended for storage of SRS in their biological shielding.

Name Description

storageType

RWF Ekores (radioactive waste faclity Ekores) is a special enterprise for management of radioactive waste. This is is a typical RADON-type facility, constructed in accordance with the standard project TP-416-9-1 “Disposal radioactive waste enterprise” developed by Moscow Project Institute (GSPI) for Radon-type facilities of the former USSR in 1970. The site comprised laundry, garage for transport vehicles and 2 below surface, reinforced concrete vaults for solid radioactive waste, all of them being put in operation in 1977. There are 2 concrete lined trenches containing so called “historic” radioactive waste in the territory of the site. They were filled with solid waste between 1964 and 1977.The "Ekores" radioactive waste facility is situated about 10 km from the center of city of Minsk, a few hundred meters from the location of the former Nuclear Research Reactor and Scientific Center «Sosny». It is the only facility in the country that has been intended for storage/disposal of radioactive waste from small users. Currently this site is under reconstruction. The reconstruction project is directed at improving physical protection and setting advanced technologies for new coming wastes and spent sources. It also makes provisions that the wastes currently disposed in the vaults and trenches should be retrieved, sorted and treated in the same way as new coming wastes.

Comment #147: What is "RWF Ekores" ?

The historic Ekores waste disposal facility was originally commissioned in 1964 and comprised 2 concrete lined trenches, up to 4 meters deep. A variety of solid radioactive waste (including sealed sources containing short-lived and long-lived radionuclides) was placed in these trenches. The solid waste was not segregated in the different waste types or conditioned. The trenches were filled with waste between 1964 and 1977. In 1977 the trenches were closed. Concrete slabs were placed on top of the trenches and these were covered by a layer of bitumen and by a mounded layer of soil. Today the mounds over the trenches can be seen with local vegetation growing on them. At the current rate the total activity of the waste disposed of in the trenches amounts to 17,6 TBq

Comment #150: Historic Ekores Disposal Facility





Second generation waste storage/disposal facilities (repositories) were put into operation in 1977. This comprised 2 below surface, reinforced concrete vaults. Each vault was covered by a lightly constructed building to provide environmental protection and acceptable working conditions to operate the facility throughout the year. Each vault has a storage capacity of 830 m3 and is divided into 8 cells. In addition, at one end of each vault there are a pair of so-called «wells» for spent sourcedisposal.Each of the cells is covered by six concrete slabs. To load waste into a cell, one of the slabs is lifted by overhead crane, the waste is tipped into the cell and the concrete slab is replaced. According to the design the total activity of wastes to be disposed of in the vault is 7,4 TBq/a, with a specific activity of 3,7 MBq/kg.The waste is collected from the waste producer by "Ekores" staff. It is not conditioned or volume reduced prior to emplacement in the repository. When a storage cell is considered to be full, free space at the top of the cell is filled with sand and a concrete grout.One of the repositories ( Repository # 1) is full to capacity. The total activity of disposed wastes is 252,8 TBq. The concrete slabs over the storage cells have been covered with a layer of asphalt, thus preventing further access to the cells. It should be noted that in 1989, irradiated fuel from the nearby research reactor was placed in one of the cells in this repository. This comprises around 2kg of ' U in 10 purpose-built stainless steel containers.

Comment #151: Ekores storage and disposal facilities

SRS Inventory

Storage and disposal of spent sealed radioactive sources at the Ekores Waste Disposal Facility All spent SRS which had entered entered the facility until 1977 were buried in the concrete trenches (Kanyon 1, Kanyon 2,). After 1977 there existed two options for spent SRS disposal. Those in protective containers with upper wall unloading were disposed of in the vaults for low and intermediate level waste (Rep 1 and Rep 2) together with their biological shielding. SRS from containers with bottom unloading were disposed of in the bore-hole repositories: Well 1, Well 2, Well 3, Well 4. By the mid of 90s Kanyon 1, Kanyon 2, and Rep 1 had been closed. Spent SRS disposed of in these repositories are declared today as disposed (not retrievable) radioactive waste. Within Waste data Component of the NEWMBD, the inventory of these SRSs is included into the inventory of LILW in disposal facilities at the Ekores site. SRS in Rep 2 should be regarded as spent SRS (waste) being in storage in the facilities intended for storage of both SRS and LILW. The structure of the Framework Section of the NEWMBD does not permit to report such kind “mixed” storage. So to settle the issue we need to define an additional dedicated SRS facility “Rep 2SS” at the Ekores site, which is in reality the same facility Rep 2, used for storage of all kinds of wastes. It should be emphasised that SRS inventory reported to the Waste Data Component of the NEWMBD shows not all but only the most important SRS being under storage and disposal at the Ekores site.

Comment #152: Ekores SRS Facilities

Due to the fact that at the Ekores site waste inventory information is available only in “kg”, not in m3, the input screens for inventories of the waste in the Ekores facilities show weight, not volumes (1 m3 = 1 tonne)

Comment #283: Waste inventory at the RWF “Ekores”




Page 1 of 1Site Structure: Complex

Full Name: Complex on conditioning decontamination waste

License Holder(s) :

Processing FacilitiesComplexA facility for immobilization of waste generated in the process of decontamination of ventilation equipment, which was polluted as a result of Chernobyl Accident

Name Description

Type treatment, conditioning

Republican Specialized Unitary Enterprise "Polyesie", Carpovicha Str.11 246017 Gomel




Page 1 of 1Site Data: Complex


Full Name: Complex on conditioning decontamination waste


R&D program



Method

Decontamination No No Nosame

Evaporation No Yes Nosame

Filtration No Yes Nosame

Organic Destruction No Yes Nosame

Processing - Conditioning method(s) Status

R&D program



Method

Cementation No Yes Nosame




Page 1 of 1Site Structure: Khatky

Full Name: Repository for disposal of biological waste of Chernobyl origin Khatky

License Holder(s) :

Disposal FacilitiesKhatkyRepository for disposal of biological and other waste of Chernobyl origin Khatky

Name Description

engineered near surfaceTypeFacility is modular


used Depth (m) 3.6

sedimentary rock (plastic clay)Host medium

existingcapacity




DWT Yes Yes DWI No Yes

planning and/or concept assessment 1986

site selection

design 1990 1991



operation 1992

closure



The site covers near surface repository which was constructed in 1991 specially to dispose of beef, contaminated as a result of the Chernobyl Accident. It consists of 9 trenches, filled with the concrete cells (3x3x3 m). Now 300 cells are full and closed. 60 cells are empty and open to the atmospheric condensation. The project of rehabilitation of the site is under consideration. It aimed at construction of a facility for disposal of items of the Chernobyl origin having specific activity higher than 96 kBq/kg.

Comment #174: What is Khatky facility




Page 1 of 1Site Data: Khatky


Full Name: Repository for disposal of biological waste of Chernobyl origin Khatky



Waste Inventory


Disposal No 900 0 0 0 0 0 100DWT

The additional characteristics of the waste: biohazardous; solid (non-dispersible)




Page 1 of 1Site Structure: Padkamenne

Full Name: Repository for disposal of decontamination waste (type 2) DWR-2 "Padkamenne"

License Holder(s) :

Disposal FacilitiesPadkamenneRepository for disposal of decontamination waste (type 2) -DWR "Padkamenne"

Name Description



used Depth (m) 3


existingcapacity






site selection

design

construction 1994


operation 1994

closure



The site covers one near surface Decontamination Waste Repository (DWR) of type 2 “ Podkamenne” intended for disposal of waste generated in the process of clean up activity in Gomel Province which were contaminated as a result of the Chernobyl Accident. This is one of 8 repositories, constructed from type design specially for Chernobyl waste disposal. All the repositories of this type represent territories with one or two reservoirs banked up with embankments 4 m high. The compacted earth bottom and slopes are covered with pugged clay barriers of 0.5 m thick, which are then covered with stabilized polyethylene film. The film is buried with a protective earth layer 0.6 m thick. The repository is equipped with a net of bore holes along its perimeter

Comment #175: DWR Padkamenne




Page 1 of 1Site Data: Padkamenne


Full Name: Repository for disposal of decontamination waste (type 2) DWR-2 "Padkamenne"



Waste Inventory


Disposal No 4050 0 0 0 0 0 100DWT





Page 1 of 1Site Structure: Rechky

Full Name: Repository for disposal of decontamination waste (type 2)- DWR-2 "Rechky"

License Holder(s) :

Disposal FacilitiesRechkyRepository for disposal of decontamination waste (type 2)- DWR-2 "Rechky"

Name Description



used Depth (m) 3


existingcapacity






site selection

design

construction 1991


operation 1991

closure



The site covers one near surface Decontamination Waste repository (DWR) of type 2 “ Rechky” intended for disposal of waste generated in the process of clean up activity in Gomel Province which were contaminated as a result of the Chernobyl Accident. This is one of 8 repositories, constructed from type design specially for Chernobyl waste disposal. All the repositories of this type represent territories with one or two reservoirs banked up with embankments 4 m high. The compacted earth bottom and slopes are covered with pugged clay barriers of 0.5 m thick, which are then covered with stabilized polyethylene film. The film is buried with a protective earth layer 0.6 m thick. The repository is equipped with a net of bore holes along its perimeter.

Comment #176: DWR "Rechky"




Page 1 of 1Site Data: Rechky


Full Name: Repository for disposal of decontamination waste (type 2)- DWR-2 "Rechky"



Waste Inventory


Disposal No 81000 0 0 0 0 0 100DWT





Page 1 of 1Site Structure: Shepetov

Full Name: Repository for disposal of decontamination waste (type 2)- DWR-2 "Shepetovichy"

License Holder(s) :

Disposal FacilitiesShepetovRepository for disposal of decontamination waste (type 2) DWR-2 "Shepetovichy"

Name Description



used Depth (m) 3


existingcapacity




DWT Yes Yes DWI Yes Yes


site selection

design

construction 1991


operation 1991

closure



Shepetovichy is one of the 8 typical repositories constructed in the contaminated territories of Belarus for disposal of decontamination waste. All these repositories represent territories with one or two reservoirs banked up with embankments 4 m high. The compacted earth bottom and slopes are covered with pugged clay barriers of 0.5 m thick, which are then covered with stabilized polyethylene film. The film is buried with a protective earth layer 0.6 m thick. The repository is equipped with a net of bore holes along its perimeter.

Comment #154: DWR "Shepetovichy"




Page 1 of 1Site Data: Shepetov


Full Name: Repository for disposal of decontamination waste (type 2)- DWR-2 "Shepetovichy"



Waste Inventory


Disposal No 20670 0 0 0 0 0 100DWT





Page 1 of 1Site Structure: Gatkovichy

Full Name: Repository for disposal of decontamination waste (type 2)- DWR-2 "Gatckovichy"

License Holder(s) :

Disposal FacilitiesGatkovichyRepository for disposal of decontamination waste (type 2)- DWR "Gatckovichy"

Name Description



used Depth (m) 4


existingcapacity







design 1986 1987



operation 1987

closure


Republican Unitary Specialized Enterprise "Radon", Kaludzkaya Str.29 212 Mogilev




Page 1 of 1Site Data: Gatkovichy


Full Name: Repository for disposal of decontamination waste (type 2)- DWR-2 "Gatckovichy"



Waste Inventory


Disposal No 20760 0 0 0 0 0 100DWT





Page 1 of 1Site Structure: Kalodezsk

Full Name: Repository for disposal of decontamination waste (type 2)-DWR-2"Kalodezskaya"

License Holder(s) :

Disposal FacilitiesKalodezskRepository for disposal of decontamination waste (type 2)- DWR-2 "Kalodezskaya"

Name Description



used Depth (m) 4


existingcapacity







design 1986 1987



operation 1987

closure






Page 1 of 1Site Data: Kalodezsk


Full Name: Repository for disposal of decontamination waste (type 2)-DWR-2"Kalodezskaya"



Waste Inventory


Disposal No 18300 0 0 0 0 0 100DWT





Page 1 of 1Site Structure: Kulikovka

Full Name: Repository for disposal of decontamination waste (type 2)-DWR-2 "Kulikovka"

License Holder(s) :

Disposal FacilitiesKulikovkaRepository for disposal of decontamination waste (type 2)Kulikovka

Name Description



used Depth (m) 4


existingcapacity




DWT Yes No DWI No No



design 1986 1987



operation 1987 2000

closure






Page 1 of 1Site Data: Kulikovka


Full Name: Repository for disposal of decontamination waste (type 2)-DWR-2 "Kulikovka"



Waste Inventory


Disposal No 3800 0 0 0 0 0 100DWT





Page 1 of 1Site Structure: Lysavka

Full Name: Repository for disposal of decontamination waste (type 2) -DWR-2 "Lysavka"

License Holder(s) :

Disposal FacilitiesLysavkaRepository for disposal of decontamination waste (type 2)DWR-2 "Lysavka"

Name Description



used Depth (m) 4


existingcapacity







design 1986 1987



operation 1987

closure






Page 1 of 1Site Data: Lysavka


Full Name: Repository for disposal of decontamination waste (type 2) -DWR-2 "Lysavka"



Waste Inventory


Disposal No 20852 0 0 0 0 0 100DWT




REGULATORSCountry: Belarus Reporting Year: 2000

Page 1 of 1

ATOMNADZOR

Division for Supervision and Regulation of Nuclear and Radiation Safety

Name

Division

Department for Regulation of Industrial and Nuclear Safety under Ministry of Emergency (Promatomnadzor)

Full Name

MinskCity or Town

Matrix IAEA Def. - LILW-SL, LILW-LL, HLW; matrix ChernDW - DWT, DWIWastes that are regulated by the Regulator

RCHE

Division of Radiation Hygiene

Name

Division

Republican Center of Hygiene and Epidemiological Service under Ministry of Health

Full Name

MinskCity or Town

Matrix IAEA Def. - LILW-SL, LILW-LL; matrix ChernDW - DWT, DWIWastes that are regulated by the Regulator



REGULATIONSCountry: Belarus Reporting Year: 2000

Page 1 of 4

RadSafeLawName On Radiation Safety of PopulationTitle or Name

Matrix IAEA Def. - LILW-SL, LILW-LL, HLW; matrix ChernDW - DWT, DWIWastes that are covered by the identified Law

122-3Reference Number 1998-01-05Date Promulgated

or ProclaimedLaw

The Law defines the basis for legal regulation in the area of radiation protection of the public and is intended for creation of conditions ensuring protection of life and health of people against harmful effects of ionising radiation.It introduces the principles of norm-setting, justification and optimisation in ensuring radiation safety (article 3) and establishes basic hygienic standards (acceptable dose limits) of radiation exposure in the territory of Belarus which occurs as a result of using ionising radiation sources (article 8), in particular:- the average annual effective dose for population is 0.001 Sv or the effective dose for life (70 years) is 0,07 Sv;- the average annual effective dose for personnel is 0.02 Sv or the effective dose for the whole period of work (50 years) is 1 Sv which corresponds to the international standards.

The Law defines:· Functions of the state in the field of radiation safety;· General requirements for radiation safety assurance, including those for radioactive waste and radiation emergency;· Rights and duties of people and public associations in the field of radiation safety;· Liability for non-observance of the requirements concerning radiation safety, including safety of radiactive waste management, etc. In particular, the Law says that any activity involving the use and disposal of ionising radiation sources shall only be performed if prior authorisation is given by the competent state authority.

Comment #183: Law on Radiation Protection of Population

SanLawName The Law of the Republic Belarus "On Sanitary and Epidemiological Welfare of the Public"

Title or Name


2583-XIIReference Number 1993-10-23Date Promulgated

or ProclaimedLaw

The Law of the Republic Belarus "On sanitary and epidemiological welfare of the public" defines the sphere of competence of state governing and control bodies, the responsibilities of economic entities in relation to observance of sanitary norms and regulations as well as undertaking of sanitary-hygienic and radiation protection measures. It says that production, use, storage, transportation of ionising radiation sources and disposal of radioactive substances are only allowed with prior authorisation of these kinds of activities obtained from state sanitary control authorities and other empowered bodies. All cases of violation of radiation safety standards in working with radioactive materials are subject to investigation with obligatory participation of executives exercising technical and sanitary control on behalf of the state

Comment #184: Law "On sanitary welfare of the public"




Page 2 of 4

ChernLawName Law "On legal treatment of territories contaminated as a result of the Chernobyl NPP catastrophe"

Title or Name

Matrix ChernDW - DWT, DWIWastes that are covered by the identified Law

1227-XIIReference Number 1991-11-19Date Promulgated

or ProclaimedLaw

He Law'On legal treatment of territories contaminated as a result of the Chernobyl NPP catastrophe' establishes concrete requirements for the disposal of waste formed as a result of clean-up and rehabilitation works. It prohibits acceptance of radioactive waste from abroad except of the waste resulting from the services rendered to Belarus by the states under contractual obligations.

Comment #186: Law 'On legal treatment of territories ..."

AdmLawName Administrative CodeTitle or Name



or ProclaimedLaw

The Administrative Code has the following articles:

Article 531 .Violation of safety rules of management of substances and waste posing danger to the environment – fine of up to 50 minimal salaries for citizens and 100 – for officials.Article 1711 . Violation of radiation control rules – fine of up to 3 minimal salaries.

Comment #188: Administrative Code

Post/L-nseName On licensing activities carried out by economic subjectsTitle or Name




The regulation “On licensing activities carried out by economic subjects” prescribes a license procedure for specific activities related to transportation, storage and disposal of radioactive waste.

Comment #191: The Ordinance on licensing




Page 3 of 4

Post/NadzName Ordinance "On the state control over safe conduct of work in industry and atomic power engineering"

Title or Name




The Ordinance "On the state control over safe conduct of work in industry and atomic power engineering" which has been approved by special Governmental resolution empowers Promatomnadzor to exercise state technical control over nuclear and radiation-hazardous production facilities, objects, installations using radioactive materials and radiation sources in their activities, and installations performing processing and disposal of radioactive waste.

Comment #192: Ordinance "On the state control ..."

OSP -72/87Name "Basic sanitary rules for handling radioactive substances and otherionizing radiation sources"

Title or Name




OSP 72/87 is one of the normative documents of the former USSR which have been in force so far. It has a special section on management of solid and liquid radioactive waste.New Basic radiation safety regulations for work with ionizing radiation sources are being drafted to meet the requirements of the new national standards (NRB-2000) and the international standards.

Comment #193: OSP 72/87

SPORO-85Name Basic sanitary rules for the Management of Radioactive WastesTitle or Name


SanPin 42-129-11-3938-85Reference Number 1985-10-01Date Promulgated


SPORO-85 is one of the former USSR regulations which have been in force so far. It includes general requirements on safety collection, storage, transportation, processing and disposal of radioactive waste arisen from use of radioactive materials and other radiation sources in medicine, industry and research

Comment #194: SPORO-85




Page 4 of 4

SPOOD-98Name Provisional sanitary rules for the management of decontamination waste of Chernobyl origin

Title or Name

Matrix ChernDW - DWT, DWIWastes that are covered by the identified Law

San-PiN N 1-71-98Reference Number 1998-12-03Date Promulgated


The Provisional sanitary rules for the management of decontamination waste of Chernobyl origin (SPOOD-98) were designed for regulation of a ‘special’ group of waste (ChernDW) which are formed as a result of work to eliminate the consequences of the Chernobyl accident and which contain more than 0.96 kBq/kg of Cs-137 (for solid waste).The SPOOD-98 requirements were formulated taking into account waste peculiarities, situation developed on “emergency” storage sites, and predictive estimates of nuclides migration from those sites, based on the results of radioecological monitoring. In view of regulatory requirements, all the Chernobyl decontamination waste repositories (DWR) were classified under three different categories, each requiring a separate approach towards their maintenance and operation conditions, regulatory control and selection of disposal technologies.The SPODO-98 contains regulations on waste collection, temporary storage, transportation, inventory taking, radiological and technical control for all stages of handling this waste category. Measures for individual protection of personnel are also covered.

Comment #195: SPOOD-98

NRB-2000Name Radiation Safety Standards (NRB-2000)

Title or Name


GN 2.6.1.8 -127 -2000Reference Number 2000-04-19Date Promulgated


New Radiation Safety Standards NRB - 2000 have been developed on the basis of the Russian standards NRB-1999 and the International Basic Safety Standards (IAEA Safety Series ¹115). The Standards comprise the basic requirements to be fulfilled in all activities involving radiation exposure including management of radioactive waste.

Comment #196: NRB-2000



MILESTONESCountry: Belarus Reporting Year: 2000

Page 1 of 1

1977Start Year or Reference Year:

The first reconstruction of the Radioactive Waste management Facility under “Ekores" enterprise (RWF “Ekores”) was completed. The site, which before reconstruction had consisted of 2 simple concrete lined trenches only, was provided with laundry for cloth decontamination, garage for transport vehicles, 2 below surface, reinforced concrete vaults for solid radioactive waste and 4 bore holes for spent sealed sources storage

Description of Milestone 1977End Year


Owing to contamination of the 23% of Belarus territory by Chernobyl fallout the tasks of safety management of so-called “Chernobyl wastes”, generated in the course of clean-up, economic and other human activities in the contaminated territory became highly acute. The waste consisting of removed soil, roofing slate, boards, household articles, domestic garbage, structural elements was put into 82 interim storage sites, arranged mostly in ‘natural’ locations (ravines, sand pits, foundation pits, trenches, etc. )In this period eight repositories were constructed from type designs in the abandoned areas specially for Chernobyl waste storage



The national regulatory regime was set up, resulting in establishing adequate control and supervision for the management of all type waste, including “Chernobyl waste”.Within framework of the State Chernobyl Program, examination and inventory-taking of the sites packed with Chernobyl waste were carried out .



The project for the second Ekores facility reconstruction was launched by Belarus Government.The design included construction of some new repositories for spent sources storage, vaults for radioactive waste disposal and premises for radioactive waste sorting and conditioning.

Description of Milestone End Year


A number of the Governmental normative acts were developed to create an adequate legal basis for safety radioactive waste management. The most important ones were the Law of the Republic of Belarus “On radiation safety of public” (1998) and the Governmental Resolution to amend the Regulation “On licensing activities carried out by economic subjects” (1999), which improved the authorisation regime for the activities involving management of radioactive waste.

The Law ‘On legal treatment of territories contaminated as a result of the Chernobyl NPP catastrophe’ enacted in 1991 was appropriately amended and special Regulation ‘Provisional sanitary rules for the management of decontamination waste of the Chernobyl origin’ (SPOOD-98) were put in force.



An advanced strategy for the Ekores facility reconstruction was developed due to great pressure of public opinion. The strategy states that the Ekores facility is regarded as the facility for long storage of waste, not for its disposal. All the wastes at the Ekores vaults should be identified, conditioned, packaged and labelled to assure that the waste storage conditions meet updated safety requirements.




Belgium







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Belgium Reporting Year: 2000

Waste Class Matrix: IAEA Def. , Not UsedThe Agency's standard matrixDescription:

Waste Class Matrix:

This Matrix outlines the link between the classification scheme of conditioned radioactive waste, as developed by ONDRAF/NIRAS (the Belgian National Agency for Radioactive Waste and Enriched Fissile Materials) and the Agency's proposed scheme.

Description:

NIRAS

Waste Class Name LILW_SL% LILW_LL% HLW%Category A 100 0 0

Category C 0 93.4 6.6

Category B 0 100 0

Category R 100 0 0



Groups Overview Country: Belgium Reporting Year: 2000Reporting Group: NIRAS


NIRASWaste Matrix Used:

The Belgian National Agency for Radioactive Waste Management and Enriched Fissile Materials, NIRAS, manages all radioactive category A, B and C waste in Belgium and has an industrial branch, namely Belgoprocess, with 2 sites in Dessel, Belgium.

Umicore is an industrial company which produced category R-waste.

Description:


BP1 4 6 0 0 BP2 3 1 0 0 UMICORE 0 1 0 0



Country: Belgium Reporting Year: 2000

Page 1 of 2Site Structure: BP1

Full Name: Belgoprocess, site 1

License Holder(s) :

Processing FacilitiesCILVACILVA is Belgium's central facility for treatment and conditioning of solid and liquid LILW-SL.

Name Description


EUROBITEurobitumen is a facility for the treatment and conditioning of liquid, alpha bearing LILW-LL.

Name Description


PAMELAPAMELA is a former pilot plant for vitrification of high-level liquid waste. During the 1990's, it was heavily modified and is currently used for the conditioning of solid ILW-LL

Name Description

Type conditioning

B110XB110X is a new facility for the treatment and conditioning of solid (mostly alpha bearing) LLW-LL.

Name Description


Storage FacilitiesB127Building B127 is a storage facility for category B-waste.

Name Description



B127A bunker closed75 100 NOB127B bunker open75 72 NOB127C bunker open75 61 NO

B129Building B129 is a storage facility for category C-waste other than the HLW produced during the abroad reprocessing of spent fuel.

Name Description



B129A bunker open75 99 NOB129B building open75 79 NO

Belgoprocess N.V.Gravenstraat 73B-2480 DesselBelgium





B136Building B136 is a storage facility for category B- (bunker 170) and category C-waste (bunker 140/141) produced during the abroad reprocessing of spent fuel.

Name Description



140/141 bunker open75 9 YES170 bunker open75 0 YES

B150Building 150 is a storage facility for category A-waste.

Name Description



B150N bunker closed50 100 NOB150C bunker closed50 100 NOB150Z bunker closed50 100 NO

B151Building 151 is a storage facility for category A-waste.

Name Description



B151A bunker open50 96 NOB151B bunker open50 100 NOB151C bunker open50 4 NOB151D bunker open50 61 NO

B155Building B155 is a storage facility for alpha- and radiumcontaminated category B-waste.This building is currently under construction and will be put into operation in 2003.

Name Description



LAGAL bunker open75 0 YESRAGAL bunker open75 0 YES




Page 1 of 1Site Data: BP1

Inventory Reporting Date: December 2000 Waste Matrix: NIRAS




Waste Inventory


Storage No 2096 8 14 30 35 0 13Category A

The additional characteristics of the waste: liquid (aqueous); liquid (organic); solid (non-dispersible)

Storage Yes 11008 41 0 0 40 0 19Category A

The additional characteristics of the waste: solid (non-dispersible)

Storage No 596 0 39 41 11 0 9Category B

The additional characteristics of the waste: liquid (aqueous); liquid (organic); solid (non-dispersible)

Storage Yes 3818 18 0 78 4 0 0Category B


Storage Yes 225 0 0 91 9 0 0Category C



R&D program



Method

Compaction No No Nodecrease

Incineration No No Nodecrease

Size Reduction No No Nodecrease

Super Compaction No No Nodecrease

Thermal Treatment (non incineration) Yes No No


R&D program



Method

Cementation No No Nodecrease

Bituminization No No Nodecrease

Vitrification No No Yes






License Holder(s) :

Processing FacilitiesMUMMIEMUMMIE is a treatment- and conditioningfacility for liquid LLW-SL and liquid LLW-LL.

Name Description


KWB/BREKWB/BRE is a new treatment- and conditioningfacility for liquid LLW-SL.

Name Description


B280XB280X is a new treatment- and conditioningfacility for solid, radium contaminated LILW.

Name Description


Storage FacilitiesB270MBuilding 270M is a temporary storage facility for radiumcontaminated category B-waste. It will be replaced by a new facility in the near future (see B155, BP1-site.

Name Description



B270M building open25 20 NO

Belgoprocess N.V.Gravenstraat 73B-2480 DesselBelgium




Page 1 of 1Site Data: BP2





Waste Inventory


Storage No 1307 0 0 0 98 0 2Category A

The additional characteristics of the waste: liquid (aqueous); liquid (organic); sludge; solid (non-dispersible)

Storage No 353 0 0 0 100 0 0Category B

The additional characteristics of the waste: sludge; solid (non-dispersible)

Storage Yes 535 1 0 1 62 0 36Category B



R&D program



Method

Chemical Precipitation No No Nodecrease

Size Reduction No No Noincrease

Wastewater Treatment No No Nosame


R&D program



Method

Cementation Yes No No

Bituminization No No Nosame




Page 1 of 1Site Structure: UMICORE

Full Name: Umicore N.V.

License Holder(s) :

Storage FacilitiesOPLOPL stands for the Dutch word "OPsLagplaats", which simply means storage facility. At present, it is considered by Umicore as a DISPOSAL facility, but the necessary licences are not yet aquired.

Name Description



OPL bunker closed300 100 NO

UMICORE N.V.Broekstraat 31B-1000 BrusselsBelgium




Page 1 of 1Site Data: UMICORE


Full Name: Umicore N.V.



Waste Inventory


Storage No 45000 0 0 0 100 0 0Category R



REGULATORSCountry: Belgium Reporting Year: 2000

Page 1 of 1

Interior

Ministry of the Interior

Name

Division

Ministry of the InteriorFull Name

BrusselsCity or Town

Matrix NIRAS - Category RWastes that are regulated by the Regulator

State

State Secretary for Energy and Sustainable Development

Name

Division

State Secretary for Energy and Sustainable DevelopmentFull Name

BrusselsCity or Town

Matrix NIRAS - Category A, Category B, Category CWastes that are regulated by the Regulator



REGULATIONSCountry: Belgium Reporting Year: 2000

Page 1 of 1

08081980Name Law of 8th August, 1980Title or Name

Matrix NIRAS - Category A, Category B, Category CWastes that are covered by the identified Law

NoneReference Number 1980-08-08Date Promulgated

or ProclaimedLaw

11011991Name Law of 11th January, 1991, replacing the Law of 8th August 1980.Title or Name



or ProclaimedLaw

16101991Name Royal Decree of 16th Octobre, 1991 modifying the Law of 11th January 1990.

Title or Name



or ProclaimedLaw



MILESTONESCountry: Belgium Reporting Year: 2000

Page 1 of 2


Umicore opens a refinery in Sint-Jozef-Olen, Belgium. For years, the factory is the world's largest producer of radium.



The Research Centre for Nuclear Energy Application is founded, later renamed the Nuclear Research Centre. The Nuclear Research Centre's site in Mol houses two research reactors and has a staff of 700.



Eurochemic's experimental spent nuclear fuel reprocessing plant is commissioned in Dessel, Belgium.



The Belgian government gives the go-ahead for the construction of the first commercial nuclear power plants at Doel and Tihange.



The first commercial nuclear power plants are commissioned in Doel and Tihange. There are now seven reactors in operation, all of the PWR-type.



Since 1978 great progress has been made in research on deep disposal of radioactive waste, thanks to the HADES underground laboratory at Mol.



ONDRAF/NIRAS, the Belgian National Agency for Radioactive Waste Management and Enriched Fissile Materials, is established by law in 1980.



Building 150, the first Belgian purpose-designed storage facility for category A-waste, is put into operation.



Since 1986, ONDRAF/NIRAS has used its subsidiary Belgoprocess N.V. in Mol-Dessel for processing and interim storage of radioactive waste and decommissioning of nuclear facilities.



CILVA, a solid and liquid low level waste processing plant, is commissioned on the Belgoprocess site.Description of Milestone

End Year


The first transport of vitrified waste, arising from the abroad reprocessing of Belgian spent fuel, arrives at the Belgoprocess site in Mol-Dessel and is stored in building 136, a purpose-designed facility for the storage of category B- and category C-waste.




MILESTONESCountry: Belgium Reporting Year: 2000

Page 2 of 2


EIG EURIDICE is the joint venture set up by ONDRAF/NIRAS and the Nuclear Research Centre to implement the PRACLAY programme. PRACLAY is a demonstration programme designed to prove the technical feasability of disposing of category B- and category C-waste in deep clay layers.




Chile







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Chile Reporting Year: 2000Waste Class Matrix: IAEA Def. , Not Used


Waste Class Matrix:

CATEGORY 1:ALFA EMITTERS, WHATEVER PERIOD OR HALF LIFECATEGORY 2: BETA, GAMMA EMITTERS, HALF LIFE LONGER THAN 100 DAYS

Description:

CHILECLASS

Waste Class Name LILW_SL% LILW_LL% HLW%CATEGORY 1 98 2 0

CATEGORY 2 100 0 0

The distribution of activities relative to the IAEA scheme was based upon known activities of low activity uranium containing waste. Most of this waste has activities below 400 Bq/g, therefore it is considered as near surface disposal waste (i.e. LILW-SL). Some Americium 241 waste from neutron generators and guages have activities >4000 Bq/g. This is LILW-LL (about 2% by volume)

Comment #141: Category 1



Groups Overview Country: Chile Reporting Year: 2000Reporting Group: UGDR


CHILECLASSWaste Matrix Used:

Unidad Gestion de Deseschos Radioactivos. The UGDR is organized under the Chilean Comission for Nuclear Energy (CCHEN) and it is charged with collecting, processing, conditioning and storage of all radioactive waste produced in the country due to its own nuclear development which is solely for peaceful purposes. UGDR centralizes its activites in the Metropolitan Region of Santiago, to give the service to all radioactive waste producers in the country.

Description:


CEN LA 1 1 0 1 CEN LR 0 2 0 2



Country: Chile Reporting Year: 2000

Page 1 of 1Site Structure: CEN LA

Full Name: Centro de Estudios Nucleares Lo Aguirre

License Holder(s) :

Processing FacilitiesPTDRPlanta de Tratamiento de Desechos Radiactivos, where spent sealed sources, compactible waste, heterogeneous and liquid waste are processed.

Name Description


Storage FacilitiesIADRAInstalacion de Almacenamiento de Desechos Radiactivos Acondicionados

Name Description



IADRA building open20 33 NO

UGDR

Dedicated SRSPTDRPlanta de Tratamiento de Desechos Radiactivos

Name Description

conditioning, storageType




Page 1 of 2Site Data: CEN LA

Inventory Reporting Date: December 2000 Waste Matrix: CHILECLASS

Full Name: Centro de Estudios Nucleares Lo Aguirre



Waste Inventory


Storage No 2 0 0 0 100 0 0CATEGORY 1

The additional characteristics of the waste: hazardous (chemical); liquid (aqueous); liquid (organic); resin; solid (dispersible); solid (non-dispersible); toxic

Storage Yes 3 0 0 0 100 0 0CATEGORY 1



The additional characteristics of the waste: hazardous (chemical); resin; solid (dispersible); solid (non-dispersible); toxic

Storage Yes 3.4 0 0 0 100 0 0CATEGORY 2

The additional characteristics of the waste: biohazardous; hazardous (chemical); liquid (organic); solid (non-dispersible); toxic


R&D program



Method

Chemical Precipitation Yes No No


Encapsulation No No Nosame

Ion Exchange No No Nosame

Organic Destruction Yes No No


R&D program



Method

Cementation No No Noincrease

Solidification No No Nodecrease

Spent Sources <=30 years

Number of Sources/Total Activity of Sources (GBq) cond

Group I less than or equal 4GBq

Nuclide

num./activity

Group II more than 4GBq but less than or

equal 4E+4GBq

num./activity

Group III more than

4E+4GBq

num./activity

uncond

cat.

Decay Date Total

Activity for all Groups

(GBq)

10

4.40E+00

No Yes 3 2000.12Sr-90 4.40E+00

19

4.10E+01

21

3.70E+02

No Yes 3 2000.12Cs-137 4.11E+02

140

4.70E+02

Yes No 3 2000.12Cs-137 4.70E+02

2

3.80E+03

Yes No 1 2000.12Co-60 3.80E+03

79

2.20E+02

1

2.80E+04

Yes No 3 2000.12Co-60 2.82E+04

5

1.10E+05

No Yes 1 2000.12Co-60 1.10E+05




Page 2 of 2Site Data: CEN LA

2

1.10E-02

No Yes 3 2000.12Co-60 1.10E-02

1

4.70E-04

No Yes 3 2000.12Cd-109 4.70E-04

Spent Sources >30 years



Nuclide

num./activity


equal 4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

319

7.80E+01

Yes No 2 2000.12Ra-226 7.80E+01

25

3.00E+01

Yes No 3 2000.12Am-241 3.00E+01




Page 1 of 1Site Structure: CEN LR

Full Name: Centro de Estudios Nucleares La Reina

License Holder(s) :

Storage FacilitiesCaseta LRInstalacion de almacenamiento de desechos no acondicionados. (En espera de tratamiento t1/2 > 100 dias; y en decaimiento t1/2<100 dias)

Name Description



Caseta LR building open50 70 NOPozo trench (lined) open50 100 NO

PozoLRPozo subterráneo de concreto para guardar desechos radiactivos en espera de tratamiento en CEN La Reina

Name Description



Pozo LR trench (lined) open50 100 NO

To be licensed - in process

Dedicated SRSCDLRInstalacion almacenamiento "Caseta de desechos La Reina"

Name Description

storageTypePozoLRInstalación subterránea, forrada en concreto para guardar fuentes en espera de tratamiento

Name Description

storageType




Page 1 of 1Site Data: CEN LR

Inventory Reporting Date: December 2000 Waste Matrix: CHILECLASS

Full Name: Centro de Estudios Nucleares La Reina



Waste Inventory


Storage No 0.1 0 0 0 100 0 0CATEGORY 1

The additional characteristics of the waste: liquid (aqueous); toxic


The additional characteristics of the waste: hazardous (chemical); liquid (aqueous); liquid (organic); resin; solid (dispersible); toxic




Nuclide

num./activity


equal 4E+4GBq

num./activity

Group III more than

4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

9

5.60E+00

No Yes 3 2000.12Sr-90 5.60E+00

4

8.80E+00

2

9.40E+00

No Yes 2 2000.12Kr-85 1.82E+01

3

1.10E+00

No Yes 2 2000.12Co-60 1.10E+00

26

3.30E+01

11

1.00E+03

No Yes 2 2000.12Cs-137 1.03E+03




Nuclide

num./activity


equal 4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

4

1.80E+00

No Yes 3 2000.12Ra-226 1.80E+00

3

4.80E+00

1

3.60E+00

No Yes 2 2000.12Am-241 8.40E+00



REGULATORSCountry: Chile Reporting Year: 2000

Page 1 of 1

C.Ch.E.N.

Radiological & Nuclear Safety Department

Name

Division

Chilean Comission for Nuclear EnergyFull Name

Santiago de ChileCity or Town

Matrix CHILECLASS - CATEGORY 1, CATEGORY 2Wastes that are regulated by the Regulator



REGULATIONSCountry: Chile Reporting Year: 2000

Page 1 of 2

Law 18.302Name Ley de Seguridad Nuclear Nº 18.302 (Nuclear safety Law Nº 18.302)Title or Name

Matrix CHILECLASS - CATEGORY 1, CATEGORY 2Wastes that are covered by the identified Law

Law Nº 18.302Reference Number 1984-05-02Date Promulgated

or ProclaimedLaw

Reg 133Name Reglamento sobre autorizaciones para instalaciones radiactivas o equipos generadores de radiaciones inizantes y personal que se desempeña en ellas, u opere tales equipos u otras actividades afines. (Regulation on authorization for radioactive facilities or ionizing radiation generation equipments and people working there, or who operate those equipments and other related activities).

Title or Name


Regl. Nº 133Reference Number 1984-05-22Date Promulgated


DFL 725Name Código sanitario (Health Officer Code)Title or Name


DFL Nº 725Reference Number 1968-01-31Date Promulgated


Law 19.300Name Ley de bases del medioambiente. (Environmental Basic Law)Title or Name


Law Nº 19.300Reference Number 1997-04-01Date Promulgated

or ProclaimedLaw



REGULATIONSCountry: Chile Reporting Year: 2000

Page 2 of 2

Dec.30Name Reglamento del Sistema de evaluación e impacto ambiental. (Reg. on Environmental assessment Impact)

Title or Name


Dec. Nº 30Reference Number 1997-04-03Date Promulgated


Law 18.730Name Modifica Ley de Seguridad NuclearTitle or Name

Wastes that are covered by the identified Law

Law 18.730Reference Number 1988-08-10Date Promulgated

or ProclaimedLaw

NCS-DR-01Name Norma de Seguridad CCHEN : NCS-DR-01 Gestión de desechos radiactivos. (Radioactive waste management. CCHEN safety Standard.

Title or Name


NCS-DR-01Reference Number 1987-06-02Date Promulgated




MILESTONESCountry: Chile Reporting Year: 2000

Page 1 of 1


A Storage building (on surface) for conditioned radioactive waste is finished. It is a concrete and steal building, with internal structures to stand 200 l drums in an horizontal way.



The Radioactive Waste Management Unit is created under the Chilean Comission for Nuclear Energy organization, with the purpose of centralizing all activities related to radioactive waste management in the country.



A Radioactive Waste Treatment Plant is built and started up. Low and intermadiate activity waste are processed : spent sealed sources and solid waste. (volume reduction, immobilization in cements and conditioned).



A modification and enlargement of the Radioactive Waste Treatment Plant for the treatment of radioactive liquid waste is built.



The Radioactive Waste Treatment Unit (capacity of facilities and personnel) is evaluated by IAEA, to serve as Demonstration Center for methodologies an procedures in the management of radioactive waste from nuclear applications. The first Demonstration Course for latin America and el Caribe Region is held in 1997. (4 courses are followed after that).The



A segregation and characterization laboratory for exempted waste is built annexed to the Storage Facility for Decay.



An ion exchange Plant (3 columns of ion exchange resin) to reduce liquid waste volume from nuclear research is installed and started up at Radioactive Waste Treatment Plant.




Cuba







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Cuba Reporting Year: 2000Waste Class Matrix: IAEA Def. , Used


The waste classification scheme defined in Cuban National regulation (Regulation for Radioactive Waste Management, that will come into force this year) is similar to the IAEA Def matrix. But there is not high level waste in Cuba.

Comment #171: Waste Classification Scheme



Groups Overview Country: Cuba Reporting Year: 2000Reporting Group: CPHR



Center for Radiation Protection and HygieneDescription:


Repository 0 0 1 0 WPSF 1 1 0 1

The Center for Radiation Protection and Hygiene (CPHR) is the institution responsible for radioactive waste management in Cuba

Comment #180: Reporting group



Country: Cuba Reporting Year: 2000

Page 1 of 1Site Structure: Repository

Full Name: Repository for final disposal of radioactive waste

License Holder(s) :

Disposal FacilitiesRepositoryRepository for final disposal of radioactive wastes

Name Description

engineered near surfaceTypeFacility is modular


used Depth (m) 15

crystalline rock (granite)Host medium

existingcapacity



Phase Start Year End Year planning and/or concept assessment 1990 1994


design

construction

commissioning

operation

closure


The repository was planned for the final disposal of low and intermediate level radioactive wastes from Juragua Nuclear Power Plant and nuclear applications. The construction of the NPP was momentally stopped

Comment #230: Repository




Page 1 of 1Site Structure: WPSF

Full Name: Waste Processing and Storage Facility

License Holder(s) :

Processing FacilitiesWPFWaste Processing Facility, includes compaction of solid waste, immobilization by cementation of liquid waste and non compactible solids and conditioning of spent sealed sources.

Name Description


Storage FacilitiesWSFWaste storage facility, includes conditioning and non conditioning radioactive waste storage in an above ground construction.

Name Description



SSS silo open30 20 NORW Storage silo open30 50 NO

Center for Radiation Protection and Hygiene, Calle 20 No. 4113 Playa C. Habana

Dedicated SRSSRSFDedicated Spent Sealed Radiation Source Facility

Name Description


The Waste Processing and Storage Facility belongs to the Center for Radiation Protection and Hygine, which is the License Holder

Comment #181: WPSF

The Dedicated SRS Facility is the same facility used for the management of solid and liquid radioactive wastes. It was defined as "additional" facility for reporting individual sources in the Waste Data Component.

Comment #229: Dedicated SRS Facility




Page 1 of 2Site Data: WPSF


Full Name: Waste Processing and Storage Facility



Waste Inventory



The additional characteristics of the waste: liquid (aqueous); liquid (organic); solid (dispersible); solid (non-dispersible)




R&D program



Method

Compaction Yes No No


R&D program



Method





Nuclide

num./activity


equal 4E+4GBq

num./activity

Group III more than

4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

15

1.48E+05

No Yes 1Co-60 1.48E+05

34

4.40E+01

No Yes 2Co-60 4.40E+01

100

2.70E+01

9

4.40E+02

No Yes 3Co-60 4.67E+02

3

3.00E+00

No Yes 3Eu-154 3.00E+00

189

1.80E+02

No Yes 3Sr-90 1.80E+02

3

1.00E-02

No Yes 3Ba-133 1.00E-02

46

6.50E+04

No Yes 1Cs-137 6.50E+04

322

4.80E+04

No Yes 2Cs-137 4.80E+04

97

5.70E+01

100

3.40E+03

No Yes 3Cs-137 3.46E+03




Nuclide Group II more than 4GBq but less than or

equal 4E+4GBq

uncond

cat.

Decay Date Total


(GBq)




Page 2 of 2Site Data: WPSF

num./activity num./activity d

530

9.80E+01

No Yes 2Ra-226 9.80E+01

32

6.00E+00

No Yes 3Ra-226 6.00E+00

14

1.30E+01

No Yes 3Pu-238 1.30E+01

5401

6.00E+01

No Yes 3Am-241 6.00E+01



REGULATORSCountry: Cuba Reporting Year: 2000

Page 1 of 1

CNSNName

Division

National Center for Nuclear SafetyFull Name

HavanaCity or Town




REGULATIONSCountry: Cuba Reporting Year: 2000

Page 1 of 1

DL-207Name On the uses of Nuclear EnergyTitle or Name


Decree - Law 207Reference Number 2000-02-17Date Promulgated

or ProclaimedLaw

Although there is not HLW at present in Cuba, the Decree Law 207 includes spent fuel.

Comment #289: Decree Law 207 and HLW

R-121Name Regulation for the Safe Transport of Radioactive MaterialsTitle or Name


Resolution 121/2000Reference Number 2000-12-15Date Promulgated


R-25Name Regulation for the Authorization of Practices Associated with the Use of Ionizing Radiation

Title or Name

Matrix IAEA Def. - LILW-SL, LILW-LLWastes that are covered by the identified Law

Resolution 25/98Reference Number 1998-07-06Date Promulgated




MILESTONESCountry: Cuba Reporting Year: 2000

Page 1 of 1


The construction of the Waste Processing and Storage Facility (WPSF)and the implementation of centralized collection of radioactive waste around the country. The WPSF is at present licensed for the treatment, conditioning and storage of radioactive waste.



Chemical and radiological characterization of centralized stored low level liquid waste.Description of Milestone

1997End Year


Radiological characterization of unknown disused sealed sourcesDescription of Milestone

1997End Year


Establisment of a Quality Assurance Programme for the radioactive waste management service, including all the stages: from the collection of waste until their storage as conditioned packages.



Development of the acceptance requirements for the wastes that will be collected from the users. Wastes are segregated at the point of origin in accordance with established classification.



Establishment of requirements and methods for low and intermediate level waste package acceptability in the storage facility.



Decommissioning of small nuclear facilitiesDescription of Milestone

2001End Year


Safety analysis for Cuban Long Term Storage FacilityDescription of Milestone

2001End Year



Ecuador







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Ecuador Reporting Year: 2000Waste Class Matrix: IAEA Def. , Not Used


Waste Class Matrix:

"Information about the "A" matrix"The Ecuadorian law does not consider radioactive wastes by classes. It is a old law (released 1978) und therefore wastes are regulated in a general manner. Our law literally states : "The licensee must do every existent operation to treat and to evacuate radioactive wastes.

Description:

A

Waste Class Name LILW_SL% LILW_LL% HLW%IND. + HOSPITAL WASTES 80 20 0



Groups Overview Country: Ecuador Reporting Year: 2000Reporting Group: Quito-CEEA


AWaste Matrix Used:

For spent sealed radioactive sourcesDescription:


Quito-CEEA 0 0 0 1



Country: Ecuador Reporting Year: 2000

Page 1 of 1Site Structure: Quito-CEEA

Full Name:

License Holder(s) :

Dedicated SRSAychapichoA small building to store SRS. Operating life 22 years. 30% filled. Modular designe.

Name Description

storageType



REGULATORSCountry: Ecuador Reporting Year: 2000

Page 1 of 1

CEEA

Dirección de Seguridad Radiológica

Name

Division

Comisión Ecuatoriana de Energía AtómicaFull Name

QuitoCity or Town

Matrix A - IND. + HOSPITAL WASTESWastes that are regulated by the Regulator



REGULATIONSCountry: Ecuador Reporting Year: 2000

Page 1 of 1

RSRName Reglamento de Seguridad RadiológicaTitle or Name

Matrix A - IND. + HOSPITAL WASTESWastes that are covered by the identified Law

Registro Oficial No. 891 de 1979Reference Number 1979-08-08Date Promulgated

or ProclaimedLaw



MILESTONESCountry: Ecuador Reporting Year: 2000

Page 1 of 1


The CEEA have collected SRS during this time span in a unique location within the country. This place is named Aychapicho provided with a small facility to support the task.




Finland







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Finland Reporting Year: 2000Waste Class Matrix: IAEA Def. , Not Used


Waste Class Matrix: FIN_RADW

Waste Class Name LILW_SL% LILW_LL% HLW%reactor waste 100 0 0

The classification of reactor wastes used in Finland are given in Safety Guide 8.3, where the reactor wastes are devided to low level and to intermediate level waste categories (http://www.stuk.fi/saannosto/YVL8-3e.html.) According to national laws also spent fuel is classified as waste but not reported here. At the Loviisa site there are wet reactor wastes (about 1150 m3) at an interim storage waiting for disposal starting in a few years not reported here. Safety Guide 1.5 concerns on reporting.

Comment #104: basis of the classification for reactor wastes

SRS wastes are part of the LLW & ILW waste classes.

Comment #105: SRS

Waste Class Matrix: FIN_RADW2

Waste Class Name LILW_SL% LILW_LL% HLW%LILW 100 0 0

Waste Class Matrix: FIN_RADW3

Waste Class Name LILW_SL% LILW_LL% HLW%small waste 100 0 0

"Small waste" term includes few amount of SRS and some contaminated material. The small wastes are managed by the government and kept so far in a cave. It is planed to dispose them together with reactor waste.

Comment #335: Meaning of the term "small waste"



Groups Overview Country: Finland Reporting Year: 2000Reporting Group: Lo_NPP


FIN_RADWWaste Matrix Used:

Loviisa NPP.Description:


Loviisa 2 0 1 0

Reporting Group: Ol_NPP


FIN_RADWWaste Matrix Used:

Olkiluoto NPPDescription:


Olkiluoto 2 0 2 0

Reporting Group: STUK/TKO


FIN_RADW3Waste Matrix Used:

Research Department of STUK(STUKin tutkimusosasto)

Description:


VLJ-cave 1 1 0 0

Reporting Group: VTT/FIR


FIN_RADW2Waste Matrix Used:

Technical Research Centre of FinlandDescription:


FIR 1 1 0 0



Country: Finland Reporting Year: 2000

Page 1 of 1Site Structure: Loviisa

Full Name:

Location:Loviisa NPPLoviisa, Finland

License Holder(s) :

Processing Facilitiesmatala-aktLow-level reactor waste

Name Description


keski-aktIntermediate level reactor waste.

Name Description

Type treatment

Disposal FacilitiesLuolaDisposed LILW waste.

Name Description

geological (cavern)TypeFacility is non modular


used Depth (m) 110

crystalline rock (basalt)Host medium

existingcapacity




reactor waste Yes No



design 1983 1986



operation 1998

closure


Fortum Power and Heat Oy




Page 1 of 1Site Data: Loviisa

Inventory Reporting Date: December 2000 Waste Matrix: FIN_RADW

Full Name: Loviisa NPP



Waste Inventory


Disposal Yes 728 100 0 0 0 0 0reactor waste



R&D program



Method



R&D program



Method





Page 1 of 2Site Structure: Olkiluoto

Full Name:

Location:Olkiluoto NPPEurajoki, Finland

License Holder(s) :

Processing FacilitiesMAJ-jateTreatment and conditioning of LLW.

Name Description


KAJ-jateTreatment and conditioning of ILW (LILW).

Name Description


Disposal FacilitiesMAJsiiloDisposal of LLW

Name Description



used Depth (m) 100


existingcapacity




reactor waste Yes Yes



design 1983 1986



operation 1992

closure


Teollisuuden Voima Oy




Page 2 of 2Site Structure: Olkiluoto

KAJsiiloDisposal of mainly ILW (LILW).

Name Description



used Depth (m) 100


existingcapacity




reactor waste Yes Yes



design 1983 1986



operation 1992

closure





Page 1 of 1Site Data: Olkiluoto

Inventory Reporting Date: December 2000 Waste Matrix: FIN_RADW

Full Name: Olkiluoto NPP



Waste Inventory


Disposal Yes 3548 100 0 0 0 0 0reactor waste



R&D program



Method



Evaporation No No Nosame

Filtration No No Nosame




R&D program



Method


Solidification No No Nosame




Page 1 of 1Site Structure: VLJ-cave

Full Name:

Location:The VLJ-cave at Olkiluoto.Eurajoki, Finland

License Holder(s) :

Processing FacilitiesVLJ-caveTreatment and conditioning of small users' waste.

Name Description


Storage FacilitiesVLJ-caveStorage of small users' waste (pienjateluola)located in a bedrock cave.

Name Description



SSUW not in list open20 30 NO

STUK




Page 1 of 1Site Data: VLJ-cave

Inventory Reporting Date: December 2000 Waste Matrix: FIN_RADW3

Full Name: The VLJ-cave at Olkiluoto.



Waste Inventory


Storage No 21.9 0 0 0 100 0 0small waste


Storage Yes 5.2 0 0 0 100 0 0small waste

The additional characteristics of the waste: solid (dispersible)


R&D program



Method



R&D program



Method

Cementation No No Nosame




Page 1 of 1Site Structure: FIR

Full Name:

Location:VTT FIREspoo, Finland

License Holder(s) :

Processing FacilitiesLILWLow- and intermediate level waste.

Name Description

Type treatment

Storage FacilitiesLILWLow and intermediate level waste.

Name Description



Kellari building open60 50 NO

Technical Research Centre of Finland (Valtion Teknillinen Tutkimuskeskus)




Page 1 of 1Site Data: FIR

Inventory Reporting Date: December 2000 Waste Matrix: FIN_RADW2

Full Name: VTT FIR



Waste Inventory


Storage No 9.5 50 0 0 50 0 0LILW

The additional characteristics of the waste: resin; solid (non-dispersible)


R&D program



Method




REGULATORSCountry: Finland Reporting Year: 2000

Page 1 of 1

STUK

Nuclear Waste and Materials Regulation

Name

Division

Radiation and nuclear Safety AuthorityFull Name

HelsinkiCity or Town

Matrix FIN_RADW - reactor waste; matrix FIN_RADW2 - LILW; matrix FIN_RADW3 - small waste

Wastes that are regulated by the Regulator



REGULATIONSCountry: Finland Reporting Year: 2000

Page 1 of 4

YElakiName  Nuclear Energy Act and Decree of (1988) define the responsibilities of various parties, licensing procedures for nuclear activities and financial liabilities for future nuclear waste management.

Title or Name

Matrix FIN_RADW - reactor waste; matrix FIN_RADW2 - LILWWastes that are covered by the identified Law

990/1987 and 161/1988Reference Number 1988-12-12Date Promulgated

or ProclaimedLaw

RahastoName  Decree on the State Nuclear Waste Management Fund (1988) specifies the system for financing future nuclear waste management.

Title or Name

Matrix FIN_RADW - reactor wasteWastes that are covered by the identified Law

165/1988Reference Number 1988-02-18Date Promulgated


YVAName  Environmental Impact Assessment Act (1994) defines the EIA process to be implemented prior to the first licensing step pursuant to nuclear energy legislation.

Title or Name



or ProclaimedLaw

SATlakiName  Radiation Act and Decree (1991) include e.g. general radiation protection principles, provisions for radiation work and provisions for management of non-nuclear radioactive waste.

Title or Name

Matrix FIN_RADW3 - small wasteWastes that are covered by the identified Law


or ProclaimedLaw




Page 2 of 4

VnP478Name  General regulations for the safety of spent fuel disposal (1999) address disposal of spent fuel into bedrock.

Title or Name


VnP 478/1999Reference Number 1999-05-01Date Promulgated


VnP398Name  General regulations for the safety of a disposal facility (1991) address disposal of operating LILW from NPPs.

Title or Name




VnP395Name  General regulations for the safety of nuclear power plants (1991) address interim storage of spent fuel and treatment and conditioning of operating LILW at NPPs.

Title or Name




YVL8.1Name  Guide YVL 8.1, Disposal of reactor waste (1991).Title or Name


YVL 8.1Reference Number 1991-09-20Date Promulgated





Page 3 of 4

YVL8.2Name  Guide YVL 8.2, Clearance from regulatory control of nuclear waste (1992).

Title or Name




YVL8.3Name  Guide YVL 8.3, Treatment and storage of radioactive waste at nuclear power plant (1996).

Title or Name



or ProclaimedLaw

YVL8.4Name  Guide YVL 8.4, Long-term safety of disposal of spent nuclear fuel (2001).

Title or Name




ST6.2Name  Guide ST 6.2, Radioactive wastes and discharges (1992).Title or Name


ST 6.2Reference Number 1992-07-01Date Promulgated





Page 4 of 4

ST5.1Name ST Guide 5.1 Radiation Safety of Sealed Sources and Equipment Containing Them, 17 February 1999

Title or Name


ST 5.1Reference Number 1999-02-17Date Promulgated




MILESTONESCountry: Finland Reporting Year: 2000

Page 1 of 1


1992 start of operation of Olkiluoto LILW repository.Description of Milestone

1992End Year


1998 start of operation of Loviisa LILW repository.Description of Milestone

1998End Year


DiP and site selection for SF disposal.Description of Milestone

2001End Year



France







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: France Reporting Year: 2000Waste Class Matrix: IAEA Def. , Not Used


Waste Class Matrix:

M1 valid for all producers. Classification based on disposal options & nature of waste (act. level & half-life of main radionuclides) and not specified by law/regulation. The French classes are: TFA (VLLW), FMA-VC (LILW, short-lived), FA-VL (LLW, long-lived), MA-VL (ILW, long-lived), HA (HLW). Percentages have been indicated for TFA and FA-VL as required by the NEWMDB system. However they are artificial since, according to our opinion, they do not correspond to any IAEA classes (see comments).

Description:

M1

Waste Class Name LILW_SL% LILW_LL% HLW%TFA 100 0 0

FMA-VC 100 0 0

FA-VL 0 100 0

MA-VL 0 100 0

HA 0 0 100

TFA waste mainly originates from nuclear plants dismantling. Its activity level is close to the one defined by the international organizations for exempt waste. The disposal option is a surface repository the design of which is more simple that the design of the Centre de l'Aube facility. It can be assimilated to neither of the IAEA classes. FA-VC waste comprises graphite waste and radium waste which mainly originates from non-nuclear industries. The disposal option is a sub-surface repository. This type of waste can be assimilated to neither of the IAEA classes.

Comment #139: TFA and FA-VC waste



Groups Overview Country: France Reporting Year: 2000Reporting Group: National


M1Waste Matrix Used:

A single "theoretical" site is considered for the present submission: the quantities of waste correspond to the sum of the quantities existing on the various sites.

Description:


All sites 4 1 2 1

Storage areas or storage buildings often exist on the sites where waste is generated, and, if it is the case, treated and conditionned. The storage facilities are either modular or non-modular. In general, storage facilities have adequate remaining capacity. A value of 0 was entered because an average percent filled value was not available within the deadline for NEWMDB reporting.

Comment #284: Storage

The Centre de l'Aube is authorized for 1000000 m3 and the piece of land which belongs to Andra (the operator of the disposal facility) is sufficient for that. The waste which has already been diposed of represents 11% of the authorized capacity, being understood that it represents 66% of the engineered units built up to now. The engineered units are built as and when required: that explains that the waste occupies 66% of the build units but 11% of the authorized capacity.

Comment #287: Centre de l'Aube capacity

As it is explained in the comment related to the waste matrix, France considers that TFA waste is not a LIL-SL waste andFA-VL is something between 2 classes of the IAEA classification (LIL-SL waste and LIL-LL waste). Therefore the Country Coordinator has decided not to report them in the present IAEA report. However, the quantities of those specific categories of waste are given here: the existing TFA waste in stock is estimated at 60000 m3 (unprocessed waste); the existing FA-VL waste in stock is estimated at 60000 m3 (50000 m3 unprocessed waste plus 10000 m3 processed waste).

Comment #307: Comment about TFA and FA-VL waste



Country: France Reporting Year: 2000

Page 1 of 2Site Structure: All sites

Full Name: All French sites

License Holder(s) :

Processing FacilitiesNPPNuclear power plants (production of electricity).

Name Description


R.C.Research centers (for electro-nuclear activities, defense,...) located at FONTENAY AUX ROSES, SACLAY, CADARACHE, GRENOBLE, BRUYERE LE CHATEL, VALDUC.

Name Description


R.P.LA HAGUE and MARCOULE reprocessing plants (reprocessing of spent fuels).

Name Description


OTHERSSeveral sites (enrichment, fuel manufacture, maintenance, Defense, non electro-nuclear activities...)

Name Description


Storage FacilitiesAll sitesGenerally, processing/conditioning sites have storage facilities.

Name Description



All building open50 0 YES

Disposal FacilitiesC. M.Centre de la Manche facility: surface disposal facility for LIL-SL waste.

Name Description

engineered surfaceTypeFacility is modular


used Depth (m) 0

crystalline rock (other)Host medium

existingcapacity




TFA No No FMA-VC Yes No

FA-VL No No MA-VL No No

HA No No


Electricity of France (EdF), CEA, COGEMA, ANDRA, FBFC, CEZUS, COMURHEX, EURODIF, SICN, SOMANU, STMI, SOCODEI, SOCATRI, CERCA,CIS-BIO, Direction Générale des Armées,...




Page 2 of 2Site Structure: All sites


design 1967 1994



operation 1969 1994

closure 1991 1997


C.A.Centre de l'Aube facility: surface disposal facility for LIL-SL waste.

Name Description



used Depth (m) 0

sedimentary rock (consolidated clay)Host medium

existingcapacity




TFA No No FMA-VC Yes Yes

FA-VL No No MA-VL No No

HA No No



design 1985 2060



operation 1992 2060

closure 2060 2065


Dedicated SRSAll SRSvarious sites ( SACLAY, CADARACHE, PIERRELATTE, Nuclear Power Plant)

Name Description

storageType

1- storage areas or storage buildings often exist on the sites where waste is generated, and, if it is the case, treated and conditionned. The storage facilities are either modular or non-modular. The occupied capacity varies from one facility to another.2- The authorized capacity of the Centre de l'Aube facility is 1000000 m3, but the engineered units are build as and when required.

Comment #281: All Sites




Page 1 of 1Site Data: All sites

Inventory Reporting Date: December 2000 Waste Matrix: M1

Full Name: All French sites



Waste Inventory


Storage No 5000 20 5 40 0 25 10FMA-VC

The additional characteristics of the waste: liquid (aqueous); liquid (organic); resin; sludge; solid (dispersible); solid (non-dispersible)

Disposal Yes 640000 45 7 35 3 5 5FMA-VC

The additional characteristics of the waste: resin; sludge; solid (non-dispersible)

Storage No 20000 20 0 75 0 5 0MA-VL

The additional characteristics of the waste: sludge; solid (dispersible); solid (non-dispersible)

Storage Yes 26000 20 0 75 0 5 0MA-VL


Storage No 500 0 0 100 0 0 0HA

The additional characteristics of the waste: liquid (aqueous)

Storage Yes 1450 0 0 100 0 0 0HA



R&D program



Method

Calcination No No Nosame

Chemical Precipitation No No Nodecrease


Deactivation (of Sodium) No Yes No


Encapsulation No No Nosame


Incineration No No Noincrease


Mercury Treatment No Yes No

Metal Melting No No Noincrease

Organic Destruction No No Nosame

Radionuclide Separation No Yes No

Shredding and Compaction No No Noincrease

Size Reduction No No Nosame

Stabilization No No Nosame

Super Compaction No No Nosame


R&D program



Method



Polymerization No No Nosame

Vitrification No No Nosame



REGULATORSCountry: France Reporting Year: 2000

Page 1 of 1

DGSNRName

Division

Direction Générale de laSûreté Nucléaire et de la Radioprotection

Full Name

ParisCity or Town

Matrix M1 - FMA-VC, FA-VL, MA-VL, HAWastes that are regulated by the Regulator

DPPRName

Division

Direction de la Prévention des Pollutions et des Risques (Ministère de l'Environnement)

Full Name

ParisCity or Town

Matrix M1 - TFAWastes that are regulated by the Regulator



REGULATIONSCountry: France Reporting Year: 2000

Page 1 of 2

LawName Law 91-1381 on Radioactive Waste Management Research(research on high level long lived radioactive waste and creation of the French Radioactive Waste Management Agency)

Title or Name

Matrix M1 - TFA, FMA-VC, FA-VL, MA-VL, HAWastes that are covered by the identified Law


or ProclaimedLaw

The law 91-1381 has two aspects:1- it defines the research in the field of high level long lived radioactive waste management(MA-VL and HA waste),2- it creates Andra, the French Agency in charge of the radioactive waste management.As such, the law involves all the classes of the radioactive wastes.

Comment #162: Law 91-1381

RFS 1-2Name Basic Safety Rule I-2concerning the safety objectives and the design bases of surface repositories for low intermediate level short lived waste.

Title or Name

Matrix M1 - FMA-VCWastes that are covered by the identified Law

RFS I-2Reference Number 1984-06-19Date Promulgated


RFS 3-2-eName Basic Safety Rule III-2-econcerning the acceptance conditions of low intermediate short lived waste in a surface repository.

Title or Name

Matrix M1 - FMA-VCWastes that are covered by the identified Law

RFS III-2-eReference Number 1995-05-29Date Promulgated


The first version of the RFS III-2-e was issued on 31 october 1986.

Comment #163: RFS III-2-e



REGULATIONSCountry: France Reporting Year: 2000

Page 2 of 2

RFS 3-2-fName Basic Safety Rule III-2-fconcerning the objectives to be adopted in the design and construction of a deep geological formation radioactive waste repository to ensure safety after closure of the repository.

Title or Name

Matrix M1 - MA-VL, HAWastes that are covered by the identified Law

RFS III-2-fReference Number 1991-06-10Date Promulgated




MILESTONESCountry: France Reporting Year: 2000

Page 1 of 1


Operation of the Centre de la Manche facility (surface disposal of LIL-SL). A new repository started in 1992 (Centre de l'aube facility).



Following the mediation mission led by a national assemblyman, Andra conducted surveys on 3 sites for underground research laboratories (URL). In 1996 Andra filed 3 applications for installation and operating permits for the URL's. In 1999, the French government authorized Andra to construct a URL in a clay formation at the border of Meuse and Haute-Marne departments (east of France). The works are in progress.Parallel to the works regarding the east of France URL, Andra uses the available knowledge of the French granitic formations and participates to experiments in URL's (in granite) abroad in order to build up a file which will be sent to the government at the same time as the file concerning the feasibility of a deep geological disposal in the clay formation at the east of France URL. CEA studies the 2 other research directions set by the law of 30 december 1991 ( separation/transmutation, long term storage and conditionning) and the works are well in progress.



Geological surveys for a very low level waste repository and choice of the site.Description of Milestone

2000End Year



Germany







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Germany Reporting Year: 2000Waste Class Matrix: IAEA Def. , Not Used


Waste Class Matrix:

NHGW = negligible heat generating wasteHGW = heat-generating wasteThe percentages in the matrix are based uponwaste characteristics including radionuclideinventory and estimated annual arisingsprovided by the waste generators (InternalBfS-report ET-IB-52). The characteristics werecompared with the limits for long lived nuclidesand heat generation specified for the IAEA'swaste classification scheme.

Description:

GER

Waste Class Name LILW_SL% LILW_LL% HLW%NHGW 90 10 0

HGW 0 0 100

According to repository-relevant aspects all radioactive waste produced is basicallyclassified in waste with negligible heat generation (NHGW) and heat-generating waste(HGW). NHGW is defined in the "guideline concerning the controlling of radioactivewaste with negligible heat generation that do not have to be delivered to a federalstate collecting depot" [1] as waste to be disposed of in the planned Konradrepository. I.e. the radionuclide inventory of NHGW is limited by the Konrad wasteacceptance requirements [2]. Radioactive waste exceeding these limits (i.e. spentfuel and radioactive waste from reprocessing of spent fuel) is considered HGW.

[1] "Bekanntmachung der Richtlinie zur Kontrolle radioaktiver Abfälle mitvernachlässigbarer Wärmeentwicklung, die nicht an eine Landessammelstelleabgeliefert werden vom 16. Januar 1989", Bundesanzeiger 41 (1989) no. 63a, p. 1-12

[2] P. Brennecke, "Anforderungen an endzulagernde radioaktive Abfälle(Endlagerungsbedingungen, Stand: Dezember 1995) - Schachtanlage Konrad -",Interner BfS-Bericht ET-IB-79, Bundesamt für Strahlenschutz, Salzgitter (1995)

Comment #255: waste-classification



Groups Overview Country: Germany Reporting Year: 2000Reporting Group: BfS


GERWaste Matrix Used:

Description:


National 4 14 3 0



Country: Germany Reporting Year: 2000

Page 1 of 6Site Structure: National

Full Name: National is a "theoretical site" that includes some individual existingsites as well as sites grouped to facilitate reporting. There are variouslocations and license holders.

License Holder(s) :

Processing FacilitiesFZJResearch Center Juelich

Name Description


FZKResearch Center Karlsruhe

Name Description


GNS-DUGNS processing facility for radioactive waste in Duisburg

Name Description


ZLNProcessing facility for radioactice waste in the storage facility north (ZLN)

Name Description


Storage FacilitiesGorlebenStorage facility for NHGW (ALG) and HGW (TBLG) in Gorleben

Name Description



ALG building open50 38 NOTBLG building open50 4 NO

KKUStorage facility for NHGW from the NPPs Stade and Unterweser

Name Description



KKU building open50 20 NO

FZKStorage facility in the research center Karlsruhe

Name Description



FZK building open60 65 NO





FZJStorage facility in the research center Juelich

Name Description



FZJ building open50 60 NO

VKTAStorage facility in the research center Rossendorf

Name Description



VKTA building open35 25 NO

ZLNStorage facility north in Greifswald for radioactive waste from the NPPs Greifswald and Rheinsberg

Name Description



ZLN building open35 23 NO

NukemNukem storage facility in Hanau

Name Description



Nukem building open45 2 NO

SiemensStorage facility for radioactive waste from the Siemens-MOX plant in Hanau

Name Description



MOX building open50 78 NO

GRBStorage facility in Mitterteich

Name Description



EVU building open45 7 NO

LSStFederal States Collecting Depots

Name Description



LSSt building open50 23 NO





IndustryNuclear Industry

Name Description



Industry building open50 47 NO

NPPStorage at Nuclear Power Plants

Name Description



NPP building open60 23 NO

ResearchStorage at Research Instituts

Name Description



Research building open60 32 NO

OtherOther waste generators

Name Description



Other building open50 6 NO

Disposal FacilitiesKonradPlanned repository for NHGW Konrad

Name Description

geological (cavern)TypeFacility is modular


used Depth (m) 800 - 1300


existingcapacity


Disused/spent, sealed radioactive sources (SRS). No Yes


NHGW No Yes HGW No No



design 1982 1990

construction

commissioning

operation

closure






ERAMRepository for radioactive waste Morsleben

Name Description



used Depth (m) 500

salt domeHost medium

existingcapacity




NHGW Yes No HGW No No



design 1970 1983



operation 1971 1998

closure 2008 2022


GorlebenGorleben salt dome; since 2000 interruption of investigations for 3 to 10 years

Name Description

geological (cavern)TypeFacility is modular


used Depth (m) 900

salt domeHost medium

existingcapacity




NHGW No Yes HGW No Yes



design

construction

commissioning

operation

closure


In addition to the stationary waste processing facilities there are several mobile waste processing facilities available which can be transported and operated at the waste generator's site.

Comment #324: Processing Facilities

Radioactive waste has to be stored until a final repository is available. The intended start of operation of a German repository for radioactive waste is aproximately in the year 2030. The estimated Operating Life of the storage facilities is the time from facility construction to 2030.

Comment #325: Operating Life of Storage Facilities





The Federal States Collecting Depots combined in this group are:Landessammelstelle Baden-Württemberg,Landessammelstelle Bayern,Landessammelstelle Berlin,Landessammelstelle Hessen,Landessammelstelle Niedersachsen,Landessammelstelle Nordrhein-Westfalen,Landessammelstelle Rheinland-Pfalz,Landessammelstelle Saarland,Landessammelstelle Sachsen,Landessammelstelle Schleswig-Holstein,Vorläufige Verwahrstelle Brandenburg

Comment #326: LSSt

The Nuclear Industry combined in this group are:Advanced Nuclear Fuels GmbH,Siemens AG - Unternehmensbereich Kraftwerk Union,Urenco GmbH Gronau,Urenco GmbH Jülich.

Nukem and Siemens Brennelementewerk Hanau/MOX are listet as separate facilities.

Comment #327: Industry

The Nuclear Power Plants combined in this group are:Kernkraftwerk Biblis A und B,Kernkraftwerk Brokdorf,Kernkraftwerk Brunsbüttel,Kernkraftwerk Emsland,Kernkraftwerk Grafenrheinfeld,Kernkraftwerk Grohnde,Kernkraftwerk Gundremmingen Blöcke B und C,Kernkraftwerk Isar 1,Kernkraftwerk Isar 2,Kernkraftwerk Krümmel,Kernkraftwerk Mülheim-Kärlich,Kernkraftwerk Neckarwestheim Blöcke 1 und 2,Kernkraftwerk Obrigheim,Kernkraftwerk Philippsburg Blöcke 1 und 2,Kernkraftwerk Stade,Kernkraftwerk Unterweser,Kernkraftwerk Greifswald,Kernkraftwerk Gundremmingen Block A,Kernkraftwerk Hamm-Uentrop,Kernkraftwerk Jülich,Kernkraftwerk Lingen,Kernkraftwerk Rheinsberg,Kernkraftwerk Würgassen,Kernkraftwerk-Betriebsgesellschaft KNK,Kernkraftwerk-Betriebsgesellschaft MZFR,Versuchsatomkraftwerk Kahl VAK

Comment #328: NPP

The Research Institutes combined in this group are:Europäisches Institut für Transurane,Forschungs-und Meßreaktor Braunschweig,Forschungsreaktor Garching,Forschungszentrum Geesthacht GmbH,Hahn-Meitner-Institut Berlin GmbH,Institut für Radiochemie.

Forschungszentrum Jülich GmbH,Forschungszentrum Karlsruhe GmbH andVKT Rossendorf are listet as separate facilities.

Comment #329: Research





Waste Generators combined in this group are:Bundeswehr,AEAT Lehse

Comment #330: Other

Only liquid High Active Concentrate (as "unprocessed") and vitrified High Active Concentrate (as "processed") is included. Spent fuel and core scrap from light-water-reactors is not included.

Comment #331: HGW

Spent fuel from German NPPs was/is shipped to France and Great Britain for reprocessing. The waste products will be reported when they are returned to Germany.

Comment #332: Reprocessing abroad

Decommissioning waste is reported together with operational waste of the respective origin

Comment #333: Decommissioning waste




Page 1 of 1Site Data: National

Inventory Reporting Date: December 1999 Waste Matrix: GER

Full Name: National is a "theoretical site" that includes some individual existingsites as well as sites grouped to facilitate reporting. There are variouslocations and license holders.



Waste Inventory


Storage No 31634 29.7 34.6 2 33.7 0 0NHGW

The additional characteristics of the waste: flammable; liquid (aqueous); liquid (organic); resin; sludge; solid (dispersible); solid (non-dispersible)

Storage Yes 66656 26.8 4.8 17.8 50.6 0 0NHGW

The additional characteristics of the waste: flammable; resin; sludge; solid (dispersible); solid (non-dispersible)

Disposal Yes 36753 81.44 0.43 0 18.13 0 0NHGW

The additional characteristics of the waste: flammable; resin; sludge; solid (dispersible); solid (non-dispersible)

Storage No 70 0 0 100 0 0 0HGW


Storage Yes 15 0 0 100 0 0 0HGW



R&D program



Method

Calcination No No Nosame

Chemical Precipitation No No Nosame




Incineration No No Nosame


Super Compaction No No Nosame


R&D program



Method





REGULATORSCountry: Germany Reporting Year: 2000

Page 1 of 1

BMU

Department RS, Safety of Nuclear Installations, Radiological Protection, Nuclear Fuel Cycle and Waste Management

Name

Division

Federal Minister for the Environment, Nature Conservation and Nuclear Safety (Bundesministerium fuer Umwelt, Naturschutz und Reaktorsicherheit - BMU)

Full Name

D-53048 BonnCity or Town

Matrix GER - NHGW, HGWWastes that are regulated by the Regulator



REGULATIONSCountry: Germany Reporting Year: 2000

Page 1 of 2

ATGName Atomic Energy Act (Atomgesetz)Title or Name

Matrix GER - NHGW, HGWWastes that are covered by the identified Law

Reference Number 1959-12-23Date Promulgated

or ProclaimedLaw

StrlSchVName Radiation Protection Ordinance (Strahlenschutzverordnung)Title or Name




UVPGName Act on the Assessment of Environmental Impact (Gesetz über die Umweltverträglichkeitsprüfung)

Title or Name



or ProclaimedLaw

BBergGName Federal Mining Act (Bundesberggesetz)Title or Name



or ProclaimedLaw



REGULATIONSCountry: Germany Reporting Year: 2000

Page 2 of 2

StrVGName Act on the Precautionary Protection of the Population against Radiation Exposure (Strahlenschutzvorsorgegesetz)

Title or Name



or ProclaimedLaw



Greece







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Greece Reporting Year: 2000Waste Class Matrix: IAEA Def. , Used


Since we do not have any waste, except for used sealed sources, we automatically approve the IAEA Waste Matrix.

Comment #87: New Comment



Groups Overview Country: Greece Reporting Year: 2000Reporting Group: GAEC



national competent authority for radiation protectionDescription:


NRCPS 0 0 0 1



Country: Greece Reporting Year: 2000

Page 1 of 1Site Structure: NRCPS

Full Name:

Location:National Research Centre for Physical SciencesAg. Paraskevi, Attiki

License Holder(s) :

NRCPS does have a lisence, issued by GAEC, for the short-term storage of radioactive waste

Dedicated SRSNRCPSresearch centre

Name Description

storageType



REGULATORSCountry: Greece Reporting Year: 2000

Page 1 of 1

GAEC

Licensing & Inspections

Name

Division

Greek Atomic Energy CommissionFull Name

AttikiCity or Town Wastes that are regulated by the Regulator



REGULATIONSCountry: Greece Reporting Year: 2000

Page 1 of 1

216bName Ministerial Order on Radiation Protection RegulationsTitle or Name






Hungary







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Hungary Reporting Year: 2000Waste Class Matrix: IAEA Def. , Not Used


Waste Class Matrix:

LLW: low level waste (A < 5x10E5 Bq/g)MLW: medium level waste, (5x10E5 Bq/g < A < 5x10E8 Bq/g)HLW: high level waste (5x10E8 Bq/g < A )

Description:

PURAM

Waste Class Name LILW_SL% LILW_LL% HLW%LLW 100 0 0

MLW 0 100 0

HLW 0 90 10

The percentages in both matrices are based upon waste characterization results, which provided a general understanding of the wastes in Hungary. These characteristics were compared with the specifications for the IAEA's waste classification scheme.

Comment #319: determination of matrix percentages

Waste Class Matrix:

LLW: low level waste (A < 5x10E5 Bq/g)MLW: medium level waste, (5x10E5 Bq/g < A < 5x10E8 Bq/g)HLW: high level waste (5x10E8 Bq/g < A)

Description:

PNPP

Waste Class Name LILW_SL% LILW_LL% HLW%LLW 100 0 0

MLW 0 100 0

HLW 0 80 20



Groups Overview Country: Hungary Reporting Year: 2000Reporting Group: PNPP


PNPPWaste Matrix Used:

Paks Nuclear Power Plantoperational radioactive wastestored on-site

Description:


Paks 2 1 0 0

Reporting Group: PURAM


PURAMWaste Matrix Used:

Public Agency for Radioactive Waste ManagementDescription:


Püspökszil 0 1 1 1 Üveghuta 1 0 1 0



Country: Hungary Reporting Year: 2000

Page 1 of 1Site Structure: Paks

Full Name:

Location:Paks Nuclear Pover PlantPaks

License Holder(s) :

Processing FacilitiesCompactionsolid waste compression

Name Description

Type treatment

Evaporat.Liquid waste evaporation

Name Description

Type treatment

Storage FacilitiesTemporaryTemporary storage for operational waste

Name Description



SOLID building open30 32 NOLIQUID tank (other) open30 80 NOSOLID_H well open30 40 NO

Paks Nuclear Power Plant Ltd.




Page 1 of 1Site Data: Paks

Inventory Reporting Date: December 2000 Waste Matrix: PNPP

Full Name: Paks Nuclear Pover Plant



Waste Inventory


Storage No 360 100 0 0 0 0 0LLW

The additional characteristics of the waste: flammable; liquid (aqueous); resin; sludge; solid (non-dispersible)

Storage Yes 819 100 0 0 0 0 0LLW


Storage No 1440 100 0 0 0 0 0MLW


Storage Yes 3275 100 0 0 0 0 0MLW


Storage No 78 100 0 0 0 0 0HLW



R&D program



Method

Compaction No No Noincrease







Page 1 of 1Site Structure: Püspökszil

Full Name:

Location:Püspökszilágy LILW RepositoryPüspökszilágy

License Holder(s) :

Storage FacilitiesTEMPORARYTemporary storage for long lived radioactive sources

Name Description



Act. bldg. building open30 10 NO

Disposal FacilitiesVAULTSconcrete disposal vaults

Name Description



used Depth (m) 6


existingcapacity




LLW Yes No MLW Yes No

HLW No No



design 1974 1974


commissioning 1976

operation 1977

closure


Public Agency for Radioactive Waste Management

Dedicated SRSSSRSsteel lined disposal wells

Name Description

conditioning, disposalType

The percentage of disposal facility capacity used takes in to consideration the volume of waste plus losses due to voids, buffer and backfill materials

Comment #339: Percentage of Capacity Used




Page 1 of 2Site Data: Püspökszil

Inventory Reporting Date: December 2000 Waste Matrix: PURAM

Full Name: Püspökszilágy LILW Repository



Waste Inventory


Storage No 0.2 0 0 0 100 0 0LLW

The additional characteristics of the waste: hazardous (chemical)

Disposal No 800 20 0 0 70 2 8LLW

The additional characteristics of the waste: flammable; liquid (organic); solid (non-dispersible)

Disposal Yes 200 100 0 0 0 0 0LLW

The additional characteristics of the waste: flammable; sludge; solid (non-dispersible)

Disposal No 1200 20 0 0 70 2 8MLW

The additional characteristics of the waste: flammable; liquid (organic); solid (non-dispersible)

Disposal Yes 800 100 0 0 0 0 0MLW

The additional characteristics of the waste: flammable; sludge; solid (non-dispersible)

Storage Yes 0.2 0 0 0 100 0 0HLW





Nuclide

num./activity


equal 4E+4GBq

num./activity

Group III more than

4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

1838

2.14E+03

No Yes 2Cs-137 2.14E+03

1117

4.20E+04

Yes No 1Sr-90 4.20E+04

1825

2.60E+05

No Yes 1H-3 2.60E+05

4099

1.80E+02

No Yes 3Kr-85 1.80E+02

6000

4.80E+01

577

2.60E+05

Yes Yes 1Co-60 2.60E+05

701

3.60E+03

No Yes 2Pm-147 3.60E+03

516

3.20E+03

No Yes 2Po-210 3.20E+03

117

2.10E+04

No Yes 2Tm-170 2.10E+04

3574

4.50E+05

Yes No 1Ir-192 4.50E+05




Nuclide

num./activity


equal 4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)




Page 2 of 2Site Data: Püspökszil

num./activity num./activity d

3067

8.00E+01

No Yes 2Tc-99 8.00E+01

29

1.00E+01

19

7.70E+02

No Yes 1Pu-239 7.80E+02

131

7.00E+00

Yes No 2C-14 7.00E+00

708

1.30E+02

Yes No 1Ra-226 1.30E+02

2376

7.17E+02

85

1.33E+03

No Yes 2Am-241 2.05E+03

68

1.22E+02

4

4.80E+02

No Yes 1Pu-238 6.02E+02




Page 1 of 1Site Structure: Üveghuta

Full Name:

Location:Bátaapáti LILW repositoryBátaapáti

License Holder(s) :

Processing FacilitiesCement.Solid or solidified waste cementation to the concrate box.

Name Description

Type conditioning

Disposal FacilitiesDISPOSALsolid or solidified waste disposal

Name Description



used Depth (m) 250-300


existingcapacity




LLW No Yes MLW No Yes

HLW No No


site selection 1996

design 1996

construction

commissioning

operation

closure





Page 1 of 1Site Data: Üveghuta

Inventory Reporting Date: December 2000 Waste Matrix: PURAM

Full Name: Bátaapáti LILW repository


R&D program



Method




REGULATORSCountry: Hungary Reporting Year: 2000

Page 1 of 1

SPHAMOSName

Division

State Public Health and Medical Officer ServiceFull Name

BudapestCity or Town

Matrix PURAM - LLW, MLW, HLW; matrix PNPP - LLW, MLW, HLWWastes that are regulated by the Regulator

HAEAName

Division

Hungarian Atomic Energy AuthorityFull Name

BudapestCity or Town

Matrix PNPP - LLW, MLW, HLWWastes that are regulated by the Regulator



REGULATIONSCountry: Hungary Reporting Year: 2000

Page 1 of 3

Atomic LawName Act No. CXVI. of 1996 on Atomic EnergyTitle or Name


116/1996 tv.Reference Number 1996-12-18Date Promulgated

or ProclaimedLaw

HAEC/HAEAAName Governmental Decree No. 87/1997. (V. 28) Korm. on Duties and Scope of Authority of the HAEC and on the Scope of Duty of Authority, and Jurisdiction for Imposing Penalties, of the HAEA.

Title or Name


87/1997 korm.Reference Number 1997-05-28Date Promulgated


PURAMName Governmental Decree No. 240/1997. (XII. 18.) Korm., on the establishment of the organisation designated for implementing disposing of radioactive waste disposal and spent fuel, as well as decommissioning of nuclear installations, and on the financial source of performing its tasksactivities.

Title or Name




ExemptionName Governmental Decree No. 124/1997. (VII. 18.) Korm., on radioactive materials as well as equipment generating ionising radiation, exempted from the scope of the Atomic Energy Act No. CXVI of 1996.

Title or Name







Page 2 of 3

ActLevelsName Order of the Minister of Public Welfare No. 23/1997. (VII. 18.) NM defining the exemption levels (activity concentrations and activities cf. ICRP-60) of radionuclides.

Title or Name


23/1997 NMReference Number 1997-07-18Date Promulgated


RadProtName Order of the Minister of Health No. 16/2000. (VI. 8.) EüM on the execution of certain provisions of the Act No. CXVI. of 1996 on Atomic Energy associated with radiation protection.

Title or Name


16/2000 EüMReference Number 2000-06-08Date Promulgated


RadProtOldName Order of the Minister of Health and Social Affairs No. 7/1988 (VII. 20) SZEM regarding the enforcement of the Enacting Clause of the Council of Ministers No. 12/1980 (IV.5)MT to Act No. I. of 1980 on Atomic Energy (its regulations on radioactive waste are still in force until the new order in preparation on radioactive waste management enters into force).

Title or Name


7/1988 SzEMReference Number 1988-07-20Date Promulgated





Page 3 of 3

SiteSelectName Order of the Minister of EconomyEconomic Affairs No. 62/1997(XI.26.) IKIM on the Geological and Mining Requirements for the Siting and Planning of Nuclear Facilities and Radioactive Waste Disposal Facilities.

Title or Name


62/1997 GMReference Number 1997-11-26Date Promulgated


NuclFundName Order of the Minister of EconomyEconomic Affairs No. 67/1997(XII.18.) IKIM on the operation and administration of the Central Nuclear Financial Fund.

Title or Name


67/1997 IKIMReference Number 1997-12-18Date Promulgated




MILESTONESCountry: Hungary Reporting Year: 2000

Page 1 of 2


LILW: Start of operation of an interim storage in Solymár.Description of Milestone

1960End Year


LILW: Licencing of the Radioactive Waste Treatment and Disposal Facility in Püspökszilágy for institutional waste.



LILW: A disposal site for NPP waste was investigated in Ófalu, but the licence for construction was not granted by the Hungarian authorities.



HLW: Preliminary geological investigation of the Boda claystone formation.Description of Milestone

1993End Year


LILW: A National Program was launched to select a site for a repository for NPP waste (countrywide screening and regional screening for potential sites).



HLW: Geological exploration 1100 m below surface in an underground research object in the Boda claystone formation.



LILW: Decision to investigate the Üveghuta (Bátaapáti) site for a subsurface repository in granite, while keeping the Udvari site for a surface repository stand-by.



LILW: Exploration of the suitability of the potential site Üveghuta (Bátaapáti).Description of Milestone

1998End Year


HLW: Country-wide screening for a potential site.Description of Milestone

1999End Year


LILW: IAEA WATRP Mission confirms the results of the investigation and recommends further exploration of Üveghuta (Bátaapáti).



LILW: Collection of existing data and preparation of a preliminary safety assessment to establish further investigation in Üveghuta (Bátaapáti).



HLW: Elaboration of a national policy for HLW management, aiming at the establishment of a national strategy.




MILESTONESCountry: Hungary Reporting Year: 2000

Page 2 of 2


LILW: Detailed geological and hidrogeological survey as well as safety assessment of Üveghuta(Bátaapáti) site, preparation of the environment impact study.



LILW: Safety upgrading program (based on previous safety assessments) for the Radioactive Waste Treatment and Disposal Facility in Püspökszilágy.




Iran, Islamic Republic of







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Iran, Islamic Republic of Reporting Year: 2000Waste Class Matrix: IAEA Def. , Not Used


Waste Class Matrix:

The percentages for high level waste is rough estimated and it will be changed after NPP stat up.

Waste classification scheme for Iran is not designated in a law or regulation but is in progress.

Description:

Iran

Waste Class Name LILW_SL% LILW_LL% HLW%VLLW 100 0 0

LLW 100 0 0

ILW-SL 100 0 0

ILW-LL 0 100 0

HLW 0 0 100



Groups Overview Country: Iran, Islamic Republic of Reporting Year: 2000Reporting Group: WMD


IranWaste Matrix Used:

Waste Management DepartmentDescription:


ASB 0 1 0 1 CWMB 1 1 0 1 KRC 0 1 0 1 LA 0 0 1 0



Country: Iran, Islamic Republic of Reporting Year: 2000

Page 1 of 1Site Structure: ASB

Full Name: Anarak Storage Building

License Holder(s) :

Storage FacilitiesASBAnarak Storage Building

Name Description



ASB building open50 60 YES

Waste Management Dept.

Dedicated SRSASBAnarak Storage Building

Name Description

storageType




Page 1 of 1Site Data: ASB

Inventory Reporting Date: December 2000 Waste Matrix: Iran

Full Name: Anarak Storage Building



Waste Inventory


Storage No 1.4 100 0 0 0 0 0ILW-SL

The additional characteristics of the waste: resin

Storage Yes 6 100 0 0 0 0 0ILW-SL

The additional characteristics of the waste: resin




Nuclide

num./activity


equal 4E+4GBq

num./activity

Group III more than

4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

3

1.90E+00

No Yes 3 1990.01Sr-90 1.90E+00

1

1.90E+02

No Yes 1 1975.01Co-60 1.90E+02

34

1.80E+01

No Yes 3 1975.01Co-60 1.80E+01

58

2.00E+01

Yes No 3 1975.01Co-60 2.00E+01

11

6.10E+02

Yes No 1 1975.01Cs-137 6.10E+02

1

3.70E-01

No Yes 3Cs-137 3.70E-01




Nuclide

num./activity


equal 4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

113

9.30E+00

Yes No 1Ra-226 9.30E+00

1

2.20E+01

No Yes 2Am-241 2.20E+01

2

1.50E+00

1

2.20E+00

No Yes 3Am-241 3.70E+00




Page 1 of 1Site Structure: CWMB

Full Name: Centralized Waste Management Building

License Holder(s) :

Processing FacilitiesCWMFCentralized Waste Management Facility

Name Description


Storage FacilitiesCWMFCentralized Waste Management Facility

Name Description



CWMF building open50 0 NO

Waste Management Department(AEOI,TEHRAN,IRAN)

Dedicated SRSCWMFCentralized Waste Management Facility

Name Description





Page 1 of 1Site Data: CWMB


Full Name: Centralized Waste Management Building


R&D program



Method


Filtration Yes No No

Ion Exchange Yes No No

Membrane Technology Yes No No


R&D program



Method





Page 1 of 1Site Structure: KRC

Full Name: Karaj Research Center

License Holder(s) :

Storage FacilitiesKSBKaraj Storage Building

Name Description



KSB building open50 0 YES


Dedicated SRSKSBKaraj Storage Building

Name Description

storageType




Page 1 of 1Site Structure: LA

Full Name: Landfill Area

License Holder(s) :

Disposal FacilitiesLALandfill Area

Name Description



used Depth (m) 3


existingcapacity




VLLW Yes No LLW No No

ILW-SL No No ILW-LL No No

HLW No No


site selection 1975

design

construction

commissioning 1976

operation 1976

closure






Page 1 of 1Site Data: LA


Full Name: Landfill Area



Waste Inventory


Disposal No 4000 20 0 0 80 0 0VLLW

The additional characteristics of the waste: liquid (aqueous); solid (non-dispersible)



REGULATORSCountry: Iran, Islamic Republic of Reporting Year: 2000

Page 1 of 1

INRA

Nuclear Safety

Name

Division

Iranian Nuclear Regulatory Authority Full Name

TehranCity or Town

Matrix Iran - VLLW, LLW, ILW-SL, ILW-LL, HLWWastes that are regulated by the Regulator



REGULATIONSCountry: Iran, Islamic Republic of Reporting Year: 2000

Page 1 of 1

RS-RWMName Regulation and standards for the radioactive waste managementTitle or Name

Matrix Iran - VLLW, LLW, ILW-SLWastes that are covered by the identified Law

RCNS-CS-1Reference Number 1995-01-01Date Promulgated


BRSSName BASIC RADIATION SAFETY STANDARDSTitle or Name

Matrix Iran - VLLW, LLW, ILW-SLWastes that are covered by the identified Law

NRPD-BRSS-1Reference Number 1999-10-01Date Promulgated


RPAIName Radiation Protection Act of IranTitle or Name

Matrix Iran - VLLW, LLW, ILW-SL, ILW-LL, HLWWastes that are covered by the identified Law


or ProclaimedLaw

RWDName Radioactive waste and dischargeTitle or Name

Matrix Iran - VLLW, LLWWastes that are covered by the identified Law

NRPD-RWD-1Reference Number 2001-12-01Date Promulgated




MILESTONESCountry: Iran, Islamic Republic of Reporting Year: 2000

Page 1 of 1


Official foundation of WM office under safety affairs Dept. of AEOI.Description of Milestone

1977End Year


Planning of WM infrastructure on the basis of 2300MW of nuclear electricity.Description of Milestone

1978End Year


Official foundation of WM office under nuclear fuel division of AEOI.Description of Milestone

End Year


Cancellation of all nuclear programms.Description of Milestone

End Year


Refoundation of waste management department.Description of Milestone

End Year


New efforts for development of WM infrastructure and requirements.Description of Milestone

End Year


Direct co-operation with IAEA to obtain assistance in construction of a CWMF(Centralized waste management facility).



Planning and area survey for NS Repository.Description of Milestone

2002End Year


Technical co-operation with IAEA for development of National Waste Management Strategy.Description of Milestone

2003End Year


Commisioning of centralized waste management facility.Description of Milestone

End Year



Kuwait







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Kuwait Reporting Year: 2000Waste Class Matrix: IAEA Def. , Used




Groups Overview Country: Kuwait Reporting Year: 2000Reporting Group: RG-KUW



Central Reporting Group in Kuwait. One Reporting Group in the Country situated in the Ministry of Health.

Description:


KCCC 0 1 0 1 KUM 0 1 0 0 KUS 0 1 0 0



Country: Kuwait Reporting Year: 2000

Page 1 of 1Site Structure: KCCC

Full Name: Kuwait Cancer Control Centre

License Holder(s) :

Storage FacilitiesKCCCThree areas are used for radioactive waste temporary storage: The Hot Laboratory, Ward No. 2 and the Basement Store

Name Description



CR building open10 25 NOWard 2 building open10 1 NOBasement building open10 15 NO

Mrs. Asha JacobTel: +(965) 4849100 ext.2144

Dedicated SRSKCCC1. Ra-226 needles and tubes2. Cs-137 old irradiator for radiotherapy3. Am-Be Spent Neutron sourcesAll sources are stored temporary only.

Name Description

storageType




Page 1 of 1Site Data: KCCC


Full Name: Kuwait Cancer Control Centre



Waste Inventory




Storage No 1 0 0 0 100 0 0LILW-LL





Nuclide

num./activity


equal 4E+4GBq

num./activity

Group III more than

4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

47

2.70E+01

No Yes 1 1977.12Cs-137 2.70E+01

1

1.50E+03

No Yes 1 1964.12Cs-137 1.50E+03




Nuclide

num./activity


equal 4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

473

5.50E+01

No Yes 1Ra-226 5.50E+01




Page 1 of 1Site Structure: KUM

Full Name: Faculty of Medicine, University of Kuwait

License Holder(s) :

Storage FacilitiesKUMSolution of H-3 and C-14 stored temporary

Name Description



Laboratory building open10 1 NO

Mr. Mohammed SagrTel: (965) 5312300 Ext. 6409email: [email protected]




Page 1 of 1Site Data: KUM


Full Name: Faculty of Medicine, University of Kuwait



Waste Inventory


Storage No 0.01 0 0 0 100 0 0LILW-SL

The additional characteristics of the waste: liquid (aqueous); liquid (organic)






Page 1 of 1Site Structure: KUS

Full Name: Faculty of Science, University of Kuwait

License Holder(s) :

Storage FacilitiesKUSSolution of H-3 and C-14 stored temporary

Name Description



Store building open2 15 NO

Mr. Tiruvachi Natarajan NageswaranTel: (965) 4811188 Ext. 7291email: [email protected]




Page 1 of 1Site Data: KUS


Full Name: Faculty of Science, University of Kuwait



Waste Inventory








REGULATORSCountry: Kuwait Reporting Year: 2000

Page 1 of 1

MOH

Radiation Protection Committee

Name

Division

Minister of HealthFull Name

KuwaitCity or Town

Matrix IAEA Def. - LILW-SL, LILW-LLWastes that are regulated by the Regulator

AMIRIName

Division

His Highness the AmirFull Name

KuwaitCity or Town




REGULATIONSCountry: Kuwait Reporting Year: 2000

Page 1 of 1

MinDecrName Ministerial Decree (324) of 2001Title or Name


MD-324 /2001Reference Number 2001-02-28Date Promulgated

or ProclaimedLaw

DecLaw62Name Amiri Decree: Decree Law No.62 for the year 1980 Regarding Protection of the Environment & the General Policy for the Environment Protection

Title or Name


Decree Law No. 62/1980Reference Number 1980-12-31Date Promulgated

or ProclaimedLaw



Peru







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Peru Reporting Year: 2000Waste Class Matrix: IAEA Def. , Used




Groups Overview Country: Peru Reporting Year: 2000Reporting Group: NWMP

March 2000Inventory Reporting Date:


NATIONAL WASTE MANAGEMENT PERUVIANDescription:


NWMS 1 1 1 1



Country: Peru Reporting Year: 2000

Page 1 of 1Site Structure: NWMS

Full Name: NATIONAL WASTE MANAGEMENT SITE

License Holder(s) :

Processing FacilitiesCNIPCENTRO NACIONAL DE INVESTIGACION DEL PERU

Name Description


Storage FacilitiesCNIPA1CENTRO NUCLEAR DE INVESTIGACION DEL PERU AREA 1

Name Description



LLWSTORAGE building closed10 60 YES

Disposal FacilitiesCNIPA2CENTRO NUCLEAR DE INVESTIGACION DEL PERU AREA 2 (THIS IS UNDER STUDY)

Name Description

engineered surfaceTypeFacility is non modular


used Depth (m)


existingcapacity




LILW-SL No Yes LILW-LL No Yes

HLW No Yes


site selection

design

construction

commissioning

operation

closure


INSTITUTO PERUANO DE ENERGIA NUCLEAR

IPEN

Dedicated SRSCNIPA3CENTRO NUCLEAR DE INVESTIGACION DEL PERU AREA 3

Name Description





Page 1 of 2Site Data: NWMS

Inventory Reporting Date: March 2000 Waste Matrix: IAEA Def.

Full Name: NATIONAL WASTE MANAGEMENT SITE



Waste Inventory



The additional characteristics of the waste: flammable; solid (non-dispersible); toxic

Storage Yes 15 0 0 0 100 0 0LILW-SL


Storage No 5 0 0 0 100 0 0LILW-LL

The additional characteristics of the waste: flammable; solid (non-dispersible)

Storage Yes 1 0 0 0 100 0 0LILW-LL



R&D program



Method

Chemical Precipitation Yes No No

Compaction No No Noincrease

Ion Exchange Yes No No



R&D program



Method


Solidification No No Noincrease




Nuclide

num./activity


equal 4E+4GBq

num./activity

Group III more than

4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

1

1.90E+05

Yes No 1Co-60 1.90E+05

1

3.70E+05

Yes No 1Cs-137 3.70E+05

2

3.50E+00

Yes No 3Sr-90 3.50E+00

6

7.00E-03

Yes No 3Ir-192 7.00E-03

21

6.50E+00

36

1.80E+03

No Yes 2Cs-137 1.81E+03

11

4.10E+01

3

2.70E+01

Yes No 2Co-60 6.80E+01


Number of Sources/Total Activity of Sources (GBq) coNuclide Group II more than

unc

ca

Decay Date Total

Activity for © 2000-2002, International Atomic Energy Agency. This page generated at 2002-11-19 20:16:03 (local Vienna time.)



Page 2 of 2Site Data: NWMS

ond


Nuclide

num./activity


equal 4E+4GBq

num./activity

cond

at.

Decay Date Activity for all Groups

(GBq)

30

8.70E+00

Yes No 2Ra-226 8.70E+00

162

1.60E+01

No Yes 3Am-241 1.60E+01

3

6.00E+00

Yes No 2Am-241 6.00E+00

2

1.20E+03

Yes No 2Am-241 1.20E+03



REGULATORSCountry: Peru Reporting Year: 2000

Page 1 of 1

OTAN

DEPARTAMENTO DE INSTALACIONES RADIACTIVAS

Name

Division

OFICINA TECNICA DE LA AUTORIDAD NACIONALFull Name

LIMACity or Town




REGULATIONSCountry: Peru Reporting Year: 2000

Page 1 of 1

RSRName REGLAMENTO DE SEGURIDAD RADIOLOGICATitle or Name


DECRETO SUPREMO Nro.009-97-EMReference Number 1997-05-20Date Promulgated

or ProclaimedLaw



MILESTONESCountry: Peru Reporting Year: 2000

Page 1 of 1


Inicio de operaciones del Centro Nuclear. Instalación centralizada para residuos radiactivos.Construcción de edificio de tratamiento y acondicionamiento de residuos




Romania







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Romania Reporting Year: 2000Waste Class Matrix: IAEA Def. , Used


The use of IAEA Def. matrix is not required by any law or regulation.The matrix is just being used to report-non-power wastes to the NEWMDB.


Waste Class Matrix:

type 1: nominal activity less than 7.5E09 Bq/m3 (1 nominal Bq is the emission of 1 photon/sec of 0.8 MeV energy); or gamma dose rate less than 2 mGy/h at container surfacetype 2: nominal activity between 7.5E09 and 3.7E12 Bq/m3; or gamma dose rate between 2 mGy/h and 125 mGy/h at container surfacetype 3: nominal activity higher than 3.7E12 Bq/m3; or gamma dose rate higher than 125 mGy/h at container surface

Description:

NPP waste

Waste Class Name LILW_SL% LILW_LL% HLW%type 1 100 0 0

type 2 40 60 0

type 3 0 100 0

The NPP types of waste were established by the reference document of NPPRD-01364-RP1 (rev.3) "Solid Radioactive Waste Management Concept for Cernavoda NPP", approved by the regualtory authority (CNCAN) on 14 Nov.1994.


The percentages in the NPP waste matrix were estimated based on best knowledge of the waste (not on detailed analytical information).The percentages will be modified after more information will be available.




Groups Overview Country: Romania Reporting Year: 2000Reporting Group: Non-Power



Non-Power group is reporting the waste originated from non-power application, except the uranium mining and milling waste, which is not reported in this database.

Description:


NIPNE 1 1 1 0 NRI 1 1 0 0

Reporting Group: NPP


NPP wasteWaste Matrix Used:

NPP Group is reporting the waste stored at NPP Cernavoda site.Description:


CNE - PROD 0 1 0 0



Country: Romania Reporting Year: 2000

Page 1 of 1Site Structure: NIPNE

Full Name:

Location:

National Institute for Development&Research for Physics andNuclear Engeneering - "Horia Hulubei"

407 Atomistilor street, Magurele, jud. Ilfov

License Holder(s) :

Processing FacilitiesSTDR-MagRadioactive waste treatment facility for LILW-SL(solid&liquid radwaste+ spent sealed sources)

Name Description


Storage FacilitiesSTDR-MagStorage of LL spent sources and LILW-LL

Name Description



Storage building open100 40 YES

Disposal FacilitiesDNDRDisposal for LILW-SL and SL spent sorces sited at Baita-Bihor, ina former uranium exploration mine (coastal gallery).

Name Description

rock cavern (mountain/hill)TypeFacility is non modular


used Depth (m) 0-40 m


existingcapacity


Disused/spent, sealed radioactive sources (SRS). Yes Yes


LILW-SL Yes Yes LILW-LL No No

HLW No No



design 1975 1977



operation 1985 2030

closure 2030 2035


NIPNE, General Director dr. Emilian Dragulescu,tel.:+(401)4042300, fax:+(401)4574440




Page 1 of 1Site Data: NIPNE


Full Name: National Institute for Development&Research for Physics andNuclear Engeneering - "Horia Hulubei"



Waste Inventory


Disposal Yes 1330 30 0 0 70 0 0LILW-SL





R&D program



Method







Ion Exchange No No Nodecrease

Shredding and Compaction No No Nosame


R&D program



Method


Polymerization No Yes No




Page 1 of 1Site Structure: NRI

Full Name:

Location:

Authonomus Company for Nuclear Activities - Nuclear ResearchInstitute Pitesti1 Campului street, Mioveni, jud. Arges

License Holder(s) :

Processing FacilitiesSTDR-PitRadioactive waste treatment facility for LILW-SL(solid&liquid radwaste)

Name Description


Storage FacilitiesLEPIPost irradiation laboratory, storing fuel fragmentsand high activity spent sources. The sources arestored in pits sited in hot cells.

Name Description



Stor.cells pit open100 20 YES

Authonomus Company for Nuclear Activities through NuclearResearch Institute Pitesti, Director dr. Marin Ciocanescu,tel.:+(4048)213400, fax:+(4048)262449




Page 1 of 1Site Data: NRI


Full Name: Authonomus Company for Nuclear Activities - Nuclear ResearchInstitute Pitesti



Waste Inventory




Storage No 0.025 100 0 0 0 0 0HLW

The additional characteristics of the waste: solid (dispersible)


R&D program



Method



Membrane Technology No Yes No


R&D program



Method






Page 1 of 1Site Structure: CNE - PROD

Full Name:

Location:National Company NUCLEARELECTRICA, CNE -PROD1 Medgidiei street, Cernavoda, jud. Constanta

License Holder(s) :

Storage FacilitiesDIDRInterim storage for operational radioactive waste.

Name Description



DIDR building open60 10 NO

National Company NUCLEARELECTRICA, CNE -PROD,General Director Ion Rotaru, tel.:+(401)3120800, fax:+(401)3120800




Page 1 of 1Site Data: CNE - PROD

Inventory Reporting Date: December 2000 Waste Matrix: NPP waste

Full Name: National Company NUCLEARELECTRICA, CNE -PROD



Waste Inventory


Storage No 91.4 100 0 0 0 0 0type 1


Storage No 35.3 100 0 0 0 0 0type 2

The additional characteristics of the waste: flammable; liquid (organic); resin; solid (dispersible); solid (non-dispersible)



REGULATORSCountry: Romania Reporting Year: 2000

Page 1 of 1

CNCAN

Radiation Protection, Radioactive Waste, Transport and RadiologicalEmergencies Section

Name

Division

National Commission for Nuclear Activities ControlFull Name

BucharestCity or Town

Matrix IAEA Def. - LILW-SL, LILW-LL, HLW; matrix NPP waste - type 1, type 2, type 3




REGULATIONSCountry: Romania Reporting Year: 2000

Page 1 of 1

111/1996Name Law 111/1996 (as amended) on safe conduct of nuclear activitiesTitle or Name




or ProclaimedLaw

RSFNName Radiation Safety Fundamental Norms approved by the order of the Presidentof National Commission for Nuclear Activities Control

Title or Name



Order 14/2001Reference Number 2000-08-29Date Promulgated




Slovakia







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Slovak Republic Reporting Year: 2000Waste Class Matrix: IAEA Def. , Used


Attachment #129: Development of Waste Classification Framework for Reporting Slovakian Waste Management Data to IAEA

File name: Development of Waste Classification Framework for Reporting Slovakian Waste Management Data to IAEA.docFile type: MS Office DocumentAttachment #131: Transport regulation

File name: 198 po korekt AJ.docFile type: MS Office Document



Groups Overview Country: Slovak Republic Reporting Year: 2000Reporting Group: 01 RG



Nuclear Regulatory Authority of the Slovak RepublikDescription:


NPP EBO 1 3 0 1 NPP EMO 0 1 0 0 RÚ RAO 0 0 1 0

Reporting Group: 02 RG



State Health Institute of the Slovak RepublikDescription:


HUMA LAB 0 0 0 1

Reporting Group: 03 RG



VÚJE,Plc.- engineering, project and research organizationDescription:


VÚJE 2 0 0 0



Country: Slovak Republic Reporting Year: 2000

Page 1 of 1Site Structure: NPP EBO

Full Name:

Location:NPP Jaslovske BohuniceJaslovské Bohunice

License Holder(s) :

Processing FacilitiesBTCCBohunice Treatment and Conditioning Complex

Name Description


Storage FacilitiesNPP V-1Nuclear Power Plant V-1 Waste Storage

Name Description



LILWStor. shaft open30 85 NOLILWStor. tank (stainless steel) open30 62 NO

NPP V-2Nuclear Power Plants V-2 Waste Storage

Name Description



LILWStor. shaft open35 36 NOLILWStor. tank (stainless steel) open35 60 NO

NPP A-1NPP A-1 Waste Storage

Name Description



LILWStor. pool open40 100 NOLILWStor. tank (concrete) open40 18.6 NOLILWStor. tank (stainless steel) open40 41 NOLILWStor. trench (lined) closed40 100 NOLILWStor. building open40 61 NOLILWStor. building open40 61 NO

Slovenské Elektrárne, a.s.Hranièná 12827 36 Bratislava 212

Dedicated SRSBSRSFBohunice Sealed Radioactive Source Facility

Name Description

storageType




Page 1 of 1Site Data: NPP EBO


Full Name: NPP Jaslovske Bohunice



Waste Inventory


Storage No 10701 16.2 0 0 0 0 83.8LILW-SL

The additional characteristics of the waste: liquid (aqueous); solid (dispersible); solid (non-dispersible); toxic

Storage Yes 160 100 0 0 0 0 0LILW-SL



R&D program



Method

Carbon Adsorption No No Nosame

Chemical Precipitation No No Yes





Incineration No No Noincrease


Macroencapsulation No No Nosame

Metal Melting Yes No No

Rinsing No No Nosame


Stabilization No Yes No

Super Compaction No No Noincrease



R&D program



Method




Solidification No Yes No




Page 1 of 1Site Structure: NPP EMO

Full Name:

Location:NPP MochovceMochovce

License Holder(s) :

Storage FacilitiesNPP EMO1,2Nuclear Power Plant EMO 1,2 Waste storage

Name Description



LILWStor. tank (stainless steel) open35 19.9 NOLILWStor. shaft open35 28 NO





Page 1 of 1Site Data: NPP EMO


Full Name: NPP Mochovce



Waste Inventory



The additional characteristics of the waste: liquid (aqueous); liquid (organic); resin; sludge; solid (dispersible); solid (non-dispersible)




Page 1 of 1Site Structure: RÚ RAO

Full Name:

Location:Near Surface Disposal FacilityMochovce

License Holder(s) :

Disposal FacilitiesRÚ RAORepublikové Úložisko Rádioaktívnych Odpadov

Name Description


11160Capacity - existing (m3) Capacity -planned (m3) 223200.2% of

used Depth (m) -2 to +3.5


existingcapacity




LILW-SL Yes Yes LILW-LL No No

HLW No No



design 1981 1997



operation

closure






Page 1 of 1Site Data: RÚ RAO


Full Name: Near Surface Disposal Facility



Waste Inventory


Disposal Yes 21.7 100 0 0 0 0 0LILW-SL





Page 1 of 1Site Structure: HUMA LAB

Full Name:

Location:HUMA LAB APEKO, Ltd.Košice

License Holder(s) :

HUMA-LAB APEKO, Ltd.Garbiarska 2040 01 KošiceSlovak Republic

Dedicated SRSHUMA LABHUMA LAB APEKO - Hummánne laboratóriá aplikovaná ekológia - Košice

Name Description

storageType




Page 1 of 1Site Structure: VÚJE

Full Name:

Location:

Výskumný ústav jadrových elektrární,Plc.-engineering, project and research organizationJaslovské Bohunice

License Holder(s) :

Processing FacilitiesEBLExperimental Bituminization Facility

Name Description

Type conditioning

ESLExperimental Incineration Facility

Name Description

Type conditioning

VUJE, a.s.Okružná 5918 64 TrnavaSlovak Republik




Page 1 of 1Site Data: VÚJE


Full Name: Výskumný ústav jadrových elektrární,Plc.-engineering, project and research organization


R&D program



Method




REGULATORSCountry: Slovak Republic Reporting Year: 2000

Page 1 of 1

NRA SR

Low and Internediate Level Waste Management

Name

Division

Nuclear Regulatory Authority of the Slovak RepublicFull Name

Bratislava, division TrnavaCity or Town


MZ SR

Low and Intermediate Level Waste Management

Name

Division

State Health Organisation of the Slovak Republic under Ministry of Health of the Slovak republic

Full Name

BratislavaCity or Town




REGULATIONSCountry: Slovak Republic Reporting Year: 2000

Page 1 of 2

130/1998Name Law No. 130/1998 Coll. on on the peaceful use of nuclear energyTitle or Name


Law No. 130/1998 Coll.Reference Number 1998-07-01Date Promulgated

or ProclaimedLaw

190/2000Name Regulation of Nuclear Regulatory Authority of the Slovak Republic No.190/2000 Coll. on the details of radioactive waste management and spent fuel management

Title or Name


R No. 190/2000Reference Number 2000-07-01Date Promulgated


284/1999Name Regulation of nuclear regulatory Authority of the Slovak republic No. 284/1999 Coll. on the details of transport of nuclear materials and radwaste

Title or Name




470/2000Name Law No. 470/2000 on alterations and amendments to Law No. 272/1994 Coll. on the protection of human health as amended

Title or Name


Law No. 470/2000Reference Number 2001-01-01Date Promulgated

or ProclaimedLaw



REGULATIONSCountry: Slovak Republic Reporting Year: 2000

Page 2 of 2

12/2001Name Regulation of Ministry of Health No. 12/2000 Coll on requirements for radiation safety assurance

Title or Name






MILESTONESCountry: Slovak Republic Reporting Year: 2000

Page 1 of 1


The Experimental Bituminisation Facility has been in operation since 1986 and Decisions of the Nuclear Regulatory Authority of the Slovak Republic which approved its operation were extended every three years. The last Decision which approved its operation is No. 89/1998.



Incinerator with additional cementation facility has been used only for experimental purposes since 1987 and Decisions of the Nuclear Regulatory Authority of the Slovak Republic which approved its operation were extended every three years. The last Decision which approved its operation is No. 232/1998.



The Bituminisation Facility PS 44 has been in operation since 1995. Its operation was approved by the Decision of the Nuclear Regulatory Authority of the Slovak Republic No. 27/1995.



The Bohunice Treatment and Conditioning Complex has been commissioned since 1999.Its commissioning was approved by Decisions of Nuclear Regulatory Authority of the Slovak Republic No. 416/1999 and No. 111/2000.



The National Near Surface Repository in Mochovceis determined for disposal of low and intermediate level short-lived radwaste in special fibre reinforced concrete (FRC) containers as additional engineering barrier of repository. The repository construction was finished in November 1992. Modifications of facility as well as additional documentation recommended by IAEA experts mission were finished in 1998 - 1999. Its commissioning was approved by the Decision of the Nuclear Regulatory Authority of the Slovak Republic No. 335/1999.



The Bituminisation Facility PS 100 has been commisssioned since 2000. Its commissioning was approved by the Decision of the Nuclear Regulatory Authority of the Slovak Republic No. 124/2000.




Spain







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Spain Reporting Year: 2000Waste Class Matrix: IAEA Def. , Used


The CSN (see Regulators) is the only body in Spain responsible for radiation protection and nuclear safety, regardless of the type of radioactive material or waste. Thus, the CSN has competence over all type of waste (Matrix IAEA Def.-LILW-SL, LILW-LL, HLW).

The Ministry of Economy is responsible for defining the policy and forestablishing the regulations on radioactive waste, so it has competence over all type of waste (Matrix IAEA Def.- LILW-SL, LILW-LL, HLW).

Comment #132: use of the IAEA Def matrix

Although the spent fuel pools at the nuclear reactors have been listed, thequantities of spent fuel will not be reported in this data base, as spentfuel should not formally be considered as radioactive waste at this stage.ENRESA as responsible for managing the Spanish radioactive waste takes intoaccount for planning and cost estimation purposes the quantities of spentfuel for direct disposal.

Comment #348: spent fuel

Although no explicit definition exists for LILW-SL in regulations currently in force, limits are defined according to the safety objectives set by safety authorities for El Cabril near surface disposal facility.

Other waste, different from spent nuclear fuel, exceding these limits are considered HLW.

Comment #349: explanation of classes used



Groups Overview Country: Spain Reporting Year: 2000Reporting Group: CCNN



NUCLEAR POWER PLANTS (CENTRALES NUCLEARES)Description:


ALMARAZ 1 2 0 0 ASCO 1 2 0 0 COFRENTES 1 2 0 0 GAROÑA 1 2 0 0 TRILLO 1 2 0 0 VANDELLOS 1 2 0 0 ZORITA 1 2 0 0

Reporting Group: ENRESA



National Waste Management CompanyDescription:


El Cabril 3 1 1 0



Country: Spain Reporting Year: 2000

Page 1 of 1Site Structure: ALMARAZ

Full Name: CENTRAL NUCLEAR DE ALMARAZ

License Holder(s) :

Processing FacilitiesRBMALILW

Name Description


Storage FacilitiesRBMALILW STORAGE

Name Description



RBMA building open43 31 NO

POOLSREACTOR POOLS

Name Description



POOL1 pool open43 49 NOPOOL2 pool open43 45 NO

CENTRAL NUCLEAR DE ALMARAZ




Page 1 of 1Site Structure: ASCO

Full Name: CENTRAL NUCLEAR DE ASCO

License Holder(s) :


Name Description


Storage FacilitiesRBMALILW STORE

Name Description




POOLSREACTOR POOLS

Name Description



POOL1 pool open43 56 NOPOOL2 pool open43 49 NO

ASOCIACION NUCLEAR DE ASCO




Page 1 of 1Site Structure: COFRENTES

Full Name: CENTRAL NUCLEAR DE COFRENTES

License Holder(s) :


Name Description



Name Description




POOLREACTOR POOL

Name Description



POOL pool open43 60 NO

IBERDROLA




Page 1 of 1Site Structure: GAROÑA

Full Name: CENTRAL NUCLEAR SANTA MARIA DE GAROÑA

License Holder(s) :


Name Description



Name Description




POOLREACTOR POOL

Name Description




NUCLENOR




Page 1 of 1Site Structure: TRILLO

Full Name: CENTRAL NUCLEAR DE TRILLO

License Holder(s) :


Name Description



Name Description




POOLREACTOR POOL

Name Description




CENTRAL NUCLEAR DE TRILLO




Page 1 of 1Site Structure: VANDELLOS

Full Name: CENTRAL NUCLEAR DE VANDELLOS 2

License Holder(s) :


Name Description


Storage FacilitiesPOOLREACTOR POOL

Name Description




RBMALILW STORAGE

Name Description




ASOCIACION NUCLEAR DE VANDELLOS




Page 1 of 1Site Structure: ZORITA

Full Name: CENTRAL NUCLEAR JOSE CABRERA

License Holder(s) :


Name Description


Storage FacilitiesPOOLREACTOR POOL

Name Description




RBMAName Description




UNION ELECTRICA FENOSA




Page 1 of 2Site Structure: El Cabril

Full Name: El Cabril facility

License Holder(s) :

Processing FacilitiesCOMPSUPERCOMPACTOR

Name Description

Type treatment

INCINCINERATOR

Name Description

Type treatment

BLOQFACILITY FOR PLACING THE WASTE PACKAGES IN CONCRETE CONTAINER AND GROUTING TO INMOBILIZE

Name Description

Type conditioning

Storage FacilitiesERTSTemporary storage Facilities

Name Description



ERTS building open40 51 NO

Disposal FacilitiesCELDASNEAR SURFACE DISPOSAL WITH ENGINEERED BARRIERS. WASTE PLACED IN REINFORCED CONCRETE CONTAINERS IN THE DISPOSAL CELLS

Name Description



used Depth (m) 9


existingcapacity




LILW-SL Yes No LILW-LL No No

HLW No No



design 1988 1989



operation 1993

closure

ENRESA




Page 2 of 2Site Structure: El Cabril




REGULATORSCountry: Spain Reporting Year: 2000

Page 1 of 1

CSNName

Division

Consejo de Seguridad NuclearFull Name

MadridCity or Town


MINECO

Dirección General de Política Energética y Minas

Name

Division

Ministerio de EconomiaFull Name

MadridCity or Town


MIMAName

Division

MINISTERIO DE MEDIO AMBIENTEFull Name

MADRIDCity or Town

Matrix IAEA Def. - LILW-SLWastes that are regulated by the Regulator



REGULATIONSCountry: Spain Reporting Year: 2000

Page 1 of 1

LENName Nuclear Energy ActTitle or Name


Law 25/1964Reference Number 1964-05-04Date Promulgated

or ProclaimedLaw

Attachment #146: Excel spreadsheet containing a list of basic nuclear legislation in force in Spain

File name: tabla legislacion WMDB.xlsFile type: MS Office Document

CSNName Establishment of the Nuclear Safety CouncilTitle or Name



or ProclaimedLaw

ENRESAName Establishment of Empresa Nacional de Residuos Radiactivos (ENRESA) as the Spanish RW management company

Title or Name


RD1522/1984Reference Number 1984-08-22Date Promulgated




MILESTONESCountry: Spain Reporting Year: 2000

Page 1 of 1


The Nuclear Energy Board (JEN) was created as the organization in charge of all fields related to nuclear energy. In 1986 it was renamed CIEMAT.



The Spanish Nuclear Energy Law was enactedDescription of Milestone

End Year


The first Spanish NPP (C.N. Jose Cabrera) was connected to the gridDescription of Milestone

End Year


The Spanish Nuclear Safety Council was createdDescription of Milestone

End Year


The Spanish Radioactive Waste Management Company (ENRESA) was created by Royal DecreeDescription of Milestone

End Year


The Spanish First General Radioactive Waste Plan was approved by the Government.Description of Milestone

End Year


Decommissioning of the Uranium Milling Plant of Andujar (FUA)Description of Milestone

1994End Year


The operational license for El Cabril facility was grantedDescription of Milestone

End Year


Vandellos I NPP decommissioning (stage 2).Description of Milestone

2002End Year



Tunisia







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Tunisia Reporting Year: 2000Waste Class Matrix: IAEA Def. , Not Used


Waste Class Matrix: Tunisia

Waste Class Name LILW_SL% LILW_LL% HLW%Category 1 100 0 0

Category 2 100 0 0

Category 3 100 0 0

Category 4 0 100 0

Category 5 0 0 100



Groups Overview Country: Tunisia Reporting Year: 2000Reporting Group: Tunisia


TunisiaWaste Matrix Used:

Tunisia has small quantities of radioactive waste from medical and research facilities and spent sealed sources . We opted for a single reporting group. All informations are provided by the CC who workes in the Centre National de Radio Protection (CNRP). See comments.The CNRP controled this waste and centralised all the information. The CC assure the contact with the IAEA.

Description:


Tunisia 0 0 0 1

The country does not have a central waste management facility - waste is at various locations throughout the country. - Medical and research radioactive waste (very low activity) stored in the decay local in their institions and controled by CNRP before disposal.- Spent sealed sources stored in their users (waiting central waste storage facility).The CNRP controled these sources. Some sources are condionned and stored in site of users. Registry of these sources is available in CNRP.

Comment #156: comment on reporting group Tunisia



Country: Tunisia Reporting Year: 2000

Page 1 of 1Site Structure: Tunisia

Full Name:

Location:TunisiaRadioactive waste is at various locations throughout the country - see comments

License Holder(s) :

a list of actual sites & license holders was provided to the IAEA as an attached document - this list is not available for public viewing

Dedicated SRSTunisiaTunisia does not have a central SRS facility. SRS are conditioned & stored at users' sites. Conditioning is with CNRP tech staff co-operation.

Name Description




Country: Tunisia Reporting Year: 2000

Page 1 of 1Site Data: Tunisia

Inventory Reporting Date: December 2000 Waste Matrix: Tunisia

Full Name: Tunisia




Nuclide

num./activity


equal 4E+4GBq

num./activity

Group III more than

4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

1

4.60E-01

No Yes 2 2000.12Co-60 4.60E-01

1

1.00E-02

No Yes 3 2000.12Co-60 1.00E-02

1

6.60E-01

No Yes 3 2000.12Cs-137 6.60E-01

4

8.30E+02

No Yes 1 2000.12Cs-137 8.30E+02

3

1.10E+01

Yes No 2Cs-137 1.10E+01

1

1.10E+01

Yes No 2Cs-137 1.10E+01

1

2.80E+02

Yes No 1 2000.12Cs-137 2.80E+02

13

5.00E+01

Yes No 2 2000.12Cs-137 5.00E+01

1

2.00E+03

No Yes 1 2000.12Co-60 2.00E+03

11

1.50E-01

Yes No 3 2000.12Co-60 1.50E-01




Nuclide

num./activity


equal 4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

3

9.30E+00

No Yes 2 2000.12Am-241 9.30E+00

41

8.70E+00

Yes No 1 2000.12Ra-226 8.70E+00

1

1.10E+00

Yes No 3 2000.12Am-241 1.10E+00

2

7.40E+00

Yes No 2 2000.12Am-241 7.40E+00



REGULATORSCountry: Tunisia Reporting Year: 2000

Page 1 of 1

MEAT - MSP

Service de la gestion des déchets solidesUnité Juridique et du ContentieuxCentre National de Radio-Protection

Name

Division

Ministère de l'Environnement et de l'Aménagement du TerritoireMinistère de la Santé Publique

Full Name

TunisCity or Town

Matrix Tunisia - Category 1, Category 2, Category 3, Category 4, Category 5Wastes that are regulated by the Regulator



REGULATIONSCountry: Tunisia Reporting Year: 2000

Page 1 of 1

LawName Loi relative aux déchets et au contrôle de leur gestion et de leur élimination.Title or Name

Matrix Tunisia - Category 1, Category 2, Category 3, Category 4, Category 5Wastes that are covered by the identified Law

Loi n°96-41Reference Number 1996-06-10Date Promulgated

or ProclaimedLaw



MILESTONESCountry: Tunisia Reporting Year: 2000

Page 1 of 1


Programme : - 1994 : inventory of waste (medical radioactive waste and spent sealed sources).- 1994-2002 : control of spent sealed sources stored in their users, control of medical radioactive waste after decay and before disposal.- 1994-2002 : conditioning of 32 spent sealed sources which are stored in their users.- 2000 : conditioning of needles and tubes of radium 226 (with the AIEA cooperation in the frame of project AFRA I-14).- 2001 : preparation of specific draft regulation on radioactive waste management according to law relative to waste management (Law 96-41).This regulation will been published in this year.- 2001 : facility for medical radioactive waste (in process) - 2006 : central waste storage site projected with Environmental Ministry (Ministère de l'Environnement et du Territoire - MEAT)- 2006 : collect all spent sealed sources and conditionning and stored in this central storage facility




Turkey







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Turkey Reporting Year: 2000Waste Class Matrix: IAEA Def. , Used




Groups Overview Country: Turkey Reporting Year: 2000Reporting Group: CNAEM



Centrelized Waste processing and storage facilityDescription:


ÇNAEM 1 1 0 1



Country: Turkey Reporting Year: 2000

Page 1 of 1Site Structure: ÇNAEM

Full Name: Cekmece Waste Processing and Storage Facility-Cekmece Nukleer Arastirma ve Egitim Merkezi

License Holder(s) :

Processing FacilitiesTre.&Cond.Cementation, compaction, precipitation units are available. Laboratory experiments are held.

Name Description


Storage FacilitiesStorageThe storage of the conditioned waste is held.

Name Description



Storage building open20 90 NO

Turkish Atomic Energy Authority

Dedicated SRSSRSConditioning and interim storage of the SRS are done in the ÇNAEM.

Name Description





Page 1 of 2Site Data: ÇNAEM


Full Name: Cekmece Waste Processing and Storage Facility-Cekmece Nukleer Arastirma ve Egitim Merkezi



Waste Inventory



Storage Yes 2.2 0 0 0 100 0 0LILW-SL


R&D program



Method

Chemical Precipitation No No Yes

Compaction No No Yes


R&D program



Method

Cementation No No Yes




Nuclide

num./activity


equal 4E+4GBq

num./activity

Group III more than

4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

10

1.28E+01

No Yes 2Kr-85 1.28E+01

4

4.40E+00

No Yes 2Co-60 4.40E+00

4

3.80E+02

Yes No 2Cs-137 3.80E+02

4

3.80E+02

Yes No 2Cs-137 3.80E+02

8

2.20E+02

Yes No 2Cs-137 2.20E+02

9

2.90E+02

Yes No 2Cs-137 2.90E+02

10

3.00E+02

Yes No 2Cs-137 3.00E+02

3

1.20E+03

Yes No 2Cs-137 1.20E+03

17

2.30E+02

Yes No 2Cs-137 2.30E+02

4

2.40E+02

Yes No 2Cs-137 2.40E+02




Page 2 of 2Site Data: ÇNAEM

1

3.30E+03

Yes No 1Co-60 3.30E+03

3

1.60E+02

Yes No 1Cs-137 1.60E+02

4

1.90E+02

Yes No 2Cs-137 1.90E+02

3

1.30E+02

Yes No 2Cs-137 1.30E+02

2

1.50E+02

Yes No 2Cs-137 1.50E+02

171

4.10E+03

No Yes 2Ir-192 4.10E+03

27

1.70E+05

No Yes 2Cs-137 1.70E+05

58

7.80E+01

No Yes 2Cs-137 7.80E+01

3

3.30E-01

No Yes 3Fe-55 3.30E-01

32

3.60E+05

No Yes 1Co-60 3.60E+05

150

1.20E+02

No Yes 2Co-60 1.20E+02




Nuclide

num./activity


equal 4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

1

1.10E-01

No Yes 2Ra-226 1.10E-01

67

4.90E-01

No Yes 2Ra-226 4.90E-01

369

1.00E+02

No Yes 2Am-241 1.00E+02

1023

1.00E-02

Yes No 2Am-241 1.00E-02

58

1.30E+01

Yes Yes 2Ra-226 1.30E+01

3

5.60E+00

Yes Yes 2Ra-226 5.60E+00

73

2.80E-01

Yes Yes 2Ra-226 2.80E-01

841

1.90E+00

Yes No 3Am-241 1.90E+00

301

1.10E+02

Yes No 3Am-241 1.10E+02

40

1.00E-01

Yes No 3Am-241 1.00E-01



REGULATORSCountry: Turkey Reporting Year: 2000

Page 1 of 1

Regulator

Radition Health and Safety Department

Name

Division

Turkish Atomic Energy AuthorityFull Name

AnkaraCity or Town




REGULATIONSCountry: Turkey Reporting Year: 2000

Page 1 of 1

Reg1Name Turkish Atomic Energy ActTitle or Name


Official Gazette 17753 and Turkish Law Number 2690Reference Number 1982-07-13Date Promulgated

or ProclaimedLaw

Reg2Name Radiation Safety Charter(Radyasyon Güvenliði Tüzüðü)Title or Name


Official Gazette 18861Reference Number 1985-09-07Date Promulgated


Reg3Name Radiation Safety Legislation (Radyasyon Güvenliði Yönetmeliði)Title or Name




Reg4Name Regulation for the Radioactive Discharges to the Environment from Non-Fuel Cycle Facilities (Özel Ýþlem Gerektirmeyen Radyoaktif Atýklara Ýliþkin Yönetmelik)

Title or Name

Matrix IAEA Def. - LILW-SLWastes that are covered by the identified Law





MILESTONESCountry: Turkey Reporting Year: 2000

Page 1 of 1


Waste management activities was started beginning from 1985, as a Technical Cooperation between Turkish Atomic Energy Authority (TAEK) and IAEA, a waste processing and interim storage facility was built up and has been operating since 1989 in Istanbul as a result of that successful project. Compaction, cementation and precipitation processes have been carried out. A series of beneficial regional Predisposal Waste Management Demonstration courses, aiming to the transfer of knowledge and information to the participants from developing countries, have been organized by TAEK and IAEA.




Ukraine







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: Ukraine Reporting Year: 2000Waste Class Matrix: IAEA Def. , Not Used


Waste Class Matrix:

Low-Active Radioactive WasteFor alpha emitters:1E-1 - 1E+3 kBq/kg For beta, gamma emitters:1E+1 - 1E+5 kBq/kg

Mid-Active Radioactive WasteFor alpha emitters: 1E+5 - 1E+8 kBq/kgFor beta, gamma emitters: 1E+3 - 1E+6 kBq/kg

High-Active Radioactive WasteThermal power above about 2 kW/m3

Description:

Ukraine

Waste Class Name LILW_SL% LILW_LL% HLW%Mid-Active 99 1 0

Low-Active 99 1 0

High-Active 0 0 100



Groups Overview Country: Ukraine Reporting Year: 2000Reporting Group: ChNPP


UkraineWaste Matrix Used:

Reporting group ChNPP - Chornobyl NPPDescription:


Chorn NPP 0 2 0 0

Reporting Group: NNEC



Reporting group NNEC - National Nuclear Energy Generating Company, which include Khmelnitsky NPP, Rivne NPP, South-Ukraine NPP and Zaporizhzhya NPP

Description:


Khmel NPP 1 2 0 0 Rivne NPP 0 2 0 0 SU NPP 0 2 0 0 Zap NPP 2 2 0 0

Reporting Group: RADON



Reporting group RADON - State association "RADON", which include Dnipropetrovsk, Donetsk, Kiev, Kharkov, Lviv, Odessa Special enterprises and Special enterprise "Komplex"

Description:


Dnipr SE 0 1 3 1 Kh SE 2 2 4 2 Kiev SE 0 2 2 1 LvivSE 0 1 1 2 Odessa SE 0 1 1 2 SE Komplex 0 1 1 0 SE Tech 0 0 1 0



Country: Ukraine Reporting Year: 2000

Page 1 of 1Site Structure: Chorn NPP

Full Name:

Location:Chornobyl nuclear power plantSlavutych, Ukraine, 07100

License Holder(s) :

Storage FacilitiesSLRWTanks for liquid radioactive waste storage

Name Description



SLRW1 tank (stainless steel) open27 55 YESSLRW2 tank (stainless steel) open15 60 YES

SSRWBuilding for solid radioactive waste storage

Name Description



SSRW building open23 65 YES

Chornobyl nuclear power plantGeneral Director: Neretin YuriTel: +38 04493 4 33 50Fax: +38 04479 2 63 59




Page 1 of 1Site Data: Chorn NPP

Inventory Reporting Date: December 2000 Waste Matrix: Ukraine

Full Name: Chornobyl nuclear power plant



Waste Inventory


Storage No 16402 100 0 0 0 0 0Mid-Active

The additional characteristics of the waste: flammable; hazardous (chemical); liquid (aqueous); liquid (organic); resin; sludge; solid (dispersible); solid (non-dispersible)

Storage No 4567 100 0 0 0 0 0Low-Active

The additional characteristics of the waste: flammable; hazardous (chemical); liquid (aqueous); liquid (organic); resin; sludge; solid (dispersible); solid (non-dispersible)

Storage No 4966 0 0 0 0 0 0High-Active





Page 1 of 1Site Structure: Khmel NPP

Full Name:

Location:Khmelnitsky nuclear power plantNeteshyn, Ukraine, 30100

License Holder(s) :

Processing FacilitiesFROIFacility for radioactive oil inciniration

Name Description

Type treatment


Name Description



SLRW tank (stainless steel) open14 67 YES

SSRWModuls for solid radioactive waste storage

Name Description



SSRW building open14 39 YES

National nuclear energy generating companyPresident: Nedashkovskiy YuriTel: +38 044 294 48 70Fax: +38 044 294 48 83




Page 1 of 1Site Data: Khmel NPP


Full Name: Khmelnitsky nuclear power plant



Waste Inventory



The additional characteristics of the waste: explosive; flammable; hazardous (chemical); liquid (aqueous); liquid (organic); resin; sludge; solid (dispersible); solid (non-dispersible)

Storage Yes 460 100 0 0 0 0 0Mid-Active

The additional characteristics of the waste: liquid (organic)






R&D program



Method





Page 1 of 1Site Structure: Rivne NPP

Full Name:

Location:Rivne nuclear power plantKuznetsovsk, Ukraine, 34400

License Holder(s) :


Name Description



SLRW1 tank (stainless steel) open21 89 YESSLRW2 tank (stainless steel) open15 73 NO

SSRWModuls for solid radioactive waste storage

Name Description



SSRW1,2 building open20 58 YESSSRW3 building open15 20 YES





Page 1 of 1Site Data: Rivne NPP


Full Name: Rivne nuclear power plant



Waste Inventory



The additional characteristics of the waste: explosive; flammable; hazardous (chemical); liquid (aqueous); liquid (organic); resin; sludge; solid (dispersible); solid (non-dispersible); toxic










Page 1 of 1Site Structure: SU NPP

Full Name:

Location:South-Ukraine nuclear power plantUzhnoukrainsk, Ukraine,

License Holder(s) :

Storage FacilitiesSLRWTanks for liquid radioactive waste

Name Description





Name Description



SSRW1 building open20 58 YESSSRW2 building open12 65 YESSSLLRW building open20 98 YES





Page 1 of 1Site Data: SU NPP


Full Name: South-Ukraine nuclear power plant



Waste Inventory











Page 1 of 1Site Structure: Zap NPP

Full Name:

Location:Zaporizhzhya Nuclear Power PlantEnergodar, Ukraine, 71500

License Holder(s) :

Processing FacilitiesIFIncineration facility

Name Description

Type treatment

PFPressing facility

Name Description

Type treatment

Storage FacilitiesSLRWTanks for liquid radioactive waste

Name Description





Name Description



SSRW1 building open17 67 YESSSRW2 building open17 0 YESSSRW3 building open7 50 NO





Page 1 of 1Site Data: Zap NPP


Full Name: Zaporizhzhya Nuclear Power Plant



Waste Inventory








Storage Yes 44 100 0 0 0 0 0Low-Active

The additional characteristics of the waste: flammable




R&D program



Method






Page 1 of 2Site Structure: Dnipr SE

Full Name:

Location:Dnipropetrovsk State Interregion Special Enterprise24Á, Stalingrad herois str., Dnipropetrovsk, Ukraine, 49061

License Holder(s) :

Storage FacilitiesModul 4Storage for liquid radioactive waste

Name Description



Modul 4 cask open30 30 NO

Disposal FacilitiesModul 1Concrite modules for solid radioactive waste

Name Description



used Depth (m) 6


existingcapacity




Mid-Active Yes No Low-Active Yes No

High-Active No No


site selection

design

construction

commissioning

operation 1962 1981

closure 1981


Dnipropetrovsk State Interreginal Special Enterprise,Director: Moskalenko Valentyn,Fax: +38 0562 93 07 33




Page 2 of 2Site Structure: Dnipr SE

Modul 2Concrite modules for solid radioactive waste

Name Description



used Depth (m) 6


existingcapacity




Mid-Active Yes Yes Low-Active Yes Yes

High-Active No No


site selection

design

construction

commissioning

operation 1983

closure


Modul 5Concrite modules for solid biological radioactive waste

Name Description



used Depth (m) 6


existingcapacity





High-Active No No


site selection

design

construction

commissioning

operation 1983

closure


Dedicated SRSSRS 1SRS Modul

Name Description

disposalType




Page 1 of 3Site Structure: Kh SE

Full Name:

Location:Kharkov State Interregional Special Enterprise1, Sokolova str., Kharkov, Ukraine, 61115

License Holder(s) :

Processing FacilitiesFAC 1Facility for liquid radioactive waste cementation

Name Description

Type conditioning

FAC 2Facility for liquid radioactive waste cementation

Name Description

Type conditioning

Storage FacilitiesModul 21Cask for liquid radioactive waste

Name Description



Modul 21 cask open40 30 NO

PIPEStorage for radioactive contaminated pipes

Name Description



PIPE building open5 50 NO

Disposal FacilitiesModul 1-14Concrite modules for solid radioactive waste

Name Description



used Depth (m) 6


existingcapacity





High-Active No No


site selection

design

construction

Kharkov State Interregional Special EnterpriseDirector: Letuchiy AleksandrFax: +38 0572 94 34 70





commissioning

operation 1990

closure


Modul 18Concrite module for biological radioactive waste

Name Description



used Depth (m) 6


existingcapacity





High-Active No No


site selection

design

construction

commissioning

operation 1968 1991

closure 1997



Name Description



used Depth (m) 6


existingcapacity





High-Active No No


site selection

design

construction

commissioning

operation 1962 1996

closure 1997







Name Description



used Depth (m) 6


existingcapacity





High-Active No No


site selection

design

construction

commissioning

operation 1968 1991

closure 1997


Dedicated SRSSRS 15-16Modules for Spent Radiation Sources are operating

Name Description

disposalTypeSRS 17Modul for Spent Radiation Sources are not operating

Name Description

disposalType




Page 1 of 2Site Structure: Kiev SE

Full Name:

Location:Kiev State Interregional Special Enterprise1, Komunalna str., Kiev, Ukraine, 03026

License Holder(s) :

Storage FacilitiesLRWCasks for liquid radioactive waste

Name Description



Modul 12 cask open40 95 NOModul 13 cask open40 90 NOModul 14 cask open40 20 NOModul 15 cask closed40 100 NOModul 16 cask closed40 100 NO

Stor 1-3Building for storage solid radioactive waste in containers

Name Description



Stor 1 building open10 70 NOStor 2 building open5 0 NOStor 3 building open5 0 NO

Disposal FacilitiesModul 5-7Concrite modules for solid radioactive waste

Name Description



used Depth (m) 4


existingcapacity





High-Active No No


site selection

design

construction

commissioning

operation 1962 1988

closure


Kiev State Interregional Special EnterpriseDirector: Raksha GalinaFax: +38 044 266 37 14




Page 2 of 2Site Structure: Kiev SE

Modul 8-10Concrite modules for solid radioactive waste

Name Description



used Depth (m) 4


existingcapacity





High-Active No No


site selection

design

construction

commissioning

operation 1962 1988

closure 1988


Dedicated SRSSRS 1-6Moduls for spent radiation sources disposal

Name Description

disposalType




Page 1 of 1Site Structure: LvivSE

Full Name:

Location:Lviv State Interregional Special Enterprise4,Tadzhitska str., Lviv, Ukraine, 79045

License Holder(s) :

Storage FacilitiesLRWCask for liquid radioactive waste

Name Description



Cask 1 cask open40 40 NO

Disposal FacilitiesModul 1Concrite modules for solid radioactive waste

Name Description



used Depth (m) 4


existingcapacity





High-Active No No


site selection

design

construction

commissioning

operation 1965 1982

closure 1983


Lviv State Interregional Special Enterprise. Director: Volochyi Yuri. Phone: +38 0322 71 23 26. Fax: +38 0322 71 80 58

Dedicated SRSSRS 1Metalic - concrit modul. Operation Years:1982-1989.

Name Description

disposalTypeSRS 2-32 Moduls for disposal SRS in operation from 1989

Name Description

disposalType




Page 1 of 1Site Structure: Odessa SE

Full Name:

Location:Odessa State Interregional Special Enterprise10, Volodymyra str., Odessa, Ukraine, 65031

License Holder(s) :

Storage FacilitiesLRWCask for liquid radioactive waste

Name Description



Cask 1 cask open40 15 NOCask 2 cask open40 15 NO

Disposal FacilitiesModul 1Concrete modul for radioactive waste disposal

Name Description



used Depth (m) 6


existingcapacity





High-Active No No


site selection

design

construction

commissioning

operation 1962

closure


Odessa State Interregional Special EnterpriseDirector: Bahchevan DmytryFax: +38 048 732 35 00

Dedicated SRSSRS 1Modul for disposal spent radioactive sources,0,2 m 3, closed

Name Description

disposalTypeSRS 2Modul for disposal spent radioactive sources,0,2 m 3

Name Description

disposalType




Page 1 of 1Site Structure: SE Komplex

Full Name:

Location:State Special Enterprise "Komplex"52, Kirova str., Chornobyl, Ukraine, 07270

License Holder(s) :

Storage FacilitiesPTLRWAbout 800 trenches and holes for temporary localization of radioactive waste

Name Description



PTLRW trench (unlined) open15 100 NO

Disposal FacilitiesPZRWTrenches for solid radioactive waste disposal - "Buryakivka"

Name Description



used Depth (m) 6


existingcapacity





High-Active No No


site selection

design

construction

commissioning

operation 1987

closure


State Special Enterprise "Komplex"Director: Zhylinskiy VladymyrFax: +38 04493 5 17 08




Page 1 of 1Site Structure: SE Tech

Full Name:

Location:State Special Enterprise "Technocentr"41, Radyanska str., Chornobyl, Ukraine, 07270

License Holder(s) :

Disposal FacilitiesVectorModules for radioactive waste disposal

Name Description



used Depth (m) 12


existingcapacity




Mid-Active No Yes Low-Active No Yes

High-Active No No



design 1991 1997

construction 1997

commissioning

operation

closure


State Special Enterprise "Technocentr"Director: Tokarevsky VolodymyrFax: +38 044 264 66 91



REGULATORSCountry: Ukraine Reporting Year: 2000

Page 1 of 1

SNRCUName

Division

State Nuclear Regulatory Committee of UkraineFull Name

KievCity or Town

Matrix Ukraine - Mid-Active, Low-Active, High-ActiveWastes that are regulated by the Regulator



REGULATIONSCountry: Ukraine Reporting Year: 2000

Page 1 of 3

Law 1Name About Ratification of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management

Title or Name

Matrix Ukraine - Mid-Active, Low-Active, High-ActiveWastes that are covered by the identified Law

1688-IIIReference Number 2000-04-20Date Promulgated

or ProclaimedLaw

Law 2Name On Use of Nuclear Energy and Radiation SafetyTitle or Name



or ProclaimedLaw

Law 3Name On Radioactive Waste ManagementTitle or Name



or ProclaimedLaw

Law 4Name On Permissive Activities in the Nuclear Energy FieldTitle or Name


1370-XIVReference Number 2000-01-11Date Promulgated

or ProclaimedLaw




Page 2 of 3

Law 5Name On Physical Protection of Nuclear Materials, Radioactive Wastes and Other Radiation Sources

Title or Name


2064-IIIReference Number 2000-10-19Date Promulgated

or ProclaimedLaw

Law 6Name On Protection of Population from Radiation EffectsTitle or Name


15/98-BPReference Number 1998-01-14Date Promulgated

or ProclaimedLaw

Reg 1Name Format and Content of Safety Assessment Report for Radioactive Waste Treatment Facility

Title or Name




Reg 2Name Format and Content of Safety Assessment Report for Near-Surface Disposal

Title or Name

Matrix Ukraine - Mid-Active, Low-ActiveWastes that are covered by the identified Law






Page 3 of 3

Reg 3Name Rules and Procedure to Release Radioactive Waste and By-product Radioactive Materials from Regulatory Control

Title or Name

Matrix Ukraine - Mid-Active, Low-ActiveWastes that are covered by the identified Law



Reg 4Name Procedure of the State Inventory of Radioactive WasteTitle or Name




Reg 5Name Norms of the Radiation Protection of Ukraine.Supplement:Radiation Protection from Sources of the Potential Irradiation

Title or Name




Reg 6Name Sanitary Rules of Radioactive Waste ManagementTitle or Name






MILESTONESCountry: Ukraine Reporting Year: 2000

Page 1 of 1


Creation of the unified center of processing and burial of low and intermediate level waste:short-lived on the basis of a complex "Vector", which is built in the exclusive zone of the Chornobyl NPP



Creation of normative base for radioactive waste disposal in geological facilityDescription of Milestone

2005End Year


Creation and operation of a united radioactive waste inventory systemDescription of Milestone

2005End Year



United States of America







[email protected]



Waste Class Matrix(ces) Used/DefinedCountry: United States of America Reporting Year: 2000Waste Class Matrix: IAEA Def. , Not Used


Waste Class Matrix:

Reference for USDOE classes: Radioactive Waste Management Manual, DOE M 435.1, 7/9/1999

Description:

USDOE

Waste Class Name LILW_SL% LILW_LL% HLW%HLW 0 0 100

TRU 0 100 0

LLW 99.5 0.5 0

11e2 100 0 0

The US DOE has a waste class called "11e2" which is essentially by-product material. Keeping with NEWMDB guidance, this year "exsitu" remediation waste, e.g., moved to a disposal cell, will be reported. UMMT disposal cells will not be reported.

Comment #85: Waste Class Comment

Attachment #135: White paper with DOE waste classfication information and crosswalk to IAEA

File name: DOEwastematrix.wpdFile type: WordPerfect DocumentMember State's Reference # 1

Waste Class Matrix:

NRC waste classes defined in Title 10, Code of Federal Regulations, Part 61, Subpart 55.Class C split based on analysis of actual data

Description:

USNRC

Waste Class Name LILW_SL% LILW_LL% HLW%Class A LLW 100 0 0

Class B LLW 100 0 0

Class C LLW 75 25 0

Greater than Class C LLW 0 100 0

HLW 0 0 100

Attachment #134: White paper on USNRC waste classification crosswalk to IAEA classes

File name: NRCwastematrix.wpdFile type: WordPerfect DocumentMember State's Reference # 2



Groups Overview Country: United States of America Reporting Year: 2000Reporting Group: Commercial

September 2000Inventory Reporting Date:

USNRCWaste Matrix Used:

Sites Licensed by USNRC or Agreement StatesDescription:


Barnwell 0 0 1 0 Closed LLW 0 0 4 0 Envirocare 0 0 2 0 Richland 0 0 1 0

Reporting Group: Government

September 2000Inventory Reporting Date:

USDOEWaste Matrix Used:

United States Department of Energy owned facilitiesDescription:


ANL-E 2 1 0 0 Ashtabula 1 1 0 0 BNL 1 1 0 0 Cheney 0 0 1 0 ETEC 1 1 0 0 FEMP 1 1 1 0 Hanford 3 2 4 1 INEEL 3 3 2 0 ITRI 1 1 0 0 LANL 2 1 1 2 LBNL 1 1 0 0 LEHR 1 1 0 0 LLNL 2 1 0 0 MEMP 2 1 0 0 Monticello 0 0 1 0 NTS 0 1 3 0 OakRidge 2 1 2 0 OCRWM 0 0 1 0 OtherDOE 1 1 0 0 Paducah 1 1 0 0 Pantex 1 1 0 0 Portsmouth 0 1 0 0 RFETS 2 1 0 0 SNL 2 1 0 0 SRS 3 3 4 0 WIPP 0 0 1 0 WSSRAP 0 0 1 0 WVDP 3 3 0 0



Country: United States of America Reporting Year: 2000

Page 1 of 1Site Structure: Barnwell

Full Name:

Location:Chem NuclearBarnwell, South Carolina

License Holder(s) :

Disposal FacilitiesBarnwellLLW disposal facility

Name Description

trench(es)TypeFacility is non modular


used Depth (m) 1-9


existingcapacity




Class A LLW Yes Yes Class B LLW Yes Yes

Class C LLW Yes Yes Greater than Class C LLW No No

HLW No No


site selection

design

construction


operation 1971 2038

closure 2039 2044


Chem Nuclear




Page 1 of 1Site Data: Barnwell

Inventory Reporting Date: September 2000 Waste Matrix: USNRC

Full Name: Chem Nuclear



Waste Inventory


Disposal No 753732 61 0 0 16 23 0Class A LLW


Disposal Yes 11271 61 0 0 16 23 0Class B LLW


Disposal Yes 4223 61 0 0 16 23 0Class C LLW





Page 1 of 3Site Structure: Closed LLW

Full Name:

Location:Closed commercial LLW disposal sitesBeatty, Nevada; Sheffield, Illinois; Maxey Flats, KY; West Valley, NY

License Holder(s) :

Disposal FacilitiesBeattyClosed commercial LLW facility in Beatty, NevadaLong-term institutional control by State of Nevada

Name Description



used Depth (m)


existingcapacity




Class A LLW Yes No Class B LLW Yes No

Class C LLW Yes No Greater than Class C LLW No No

HLW No No


site selection

design

construction

commissioning

operation 1962 1992

closure 1992 1992


Licenses terminated on closure





SheffieldClosed commercial LLW disposal facility located in Sheffield, ILLong-term institutional control by Illinois Department of Nuclear Safety

Name Description



used Depth (m)


existingcapacity






HLW No No


site selection

design

construction


operation 1968 1978

closure 1978 1978


WestValleyClosed commercial LLW facility at West Valley Nuclear Services Site, New York,Under control of New York State Energy Research and Development Authority

Name Description



used Depth (m)


existingcapacity






HLW No No


site selection

design

construction


operation 1986 1986

closure 1986 1986






MaxeyFlatsClosed commercial LLW disposal site at Maxey Flats, KentuckyState of Kentucky

Name Description



used Depth (m)


existingcapacity






HLW No No


site selection

design

construction


operation 1963 1977

closure 1977 1977





Page 1 of 1Site Data: Closed LLW


Full Name: Closed commercial LLW disposal sites



Waste Inventory











Page 1 of 2Site Structure: Envirocare

Full Name:

Location:Envirocare of UtahClive, Utah

License Holder(s) :

Disposal FacilitiesLLWdispName

Descriptionengineered surfaceType

Facility is non modular100000Capacity - existing (m3) Capacity -planned (m3) 1000001% of

used Depth (m)


existingcapacity




Class A LLW Yes Yes Class B LLW No No

Class C LLW No No Greater than Class C LLW No No

HLW No No


site selection

design

construction

commissioning

operation 1988

closure


Envirocare of Utah




Page 2 of 2Site Structure: Envirocare

MLLWdispMLLW disposal unit at Envirocare.

Name Description



used Depth (m)


existingcapacity




Class A LLW Yes Yes Class B LLW No No

Class C LLW No No Greater than Class C LLW No No

HLW No No


site selection 1988

design 1988

construction 1990

commissioning 1990

operation 1990

closure





Page 1 of 1Site Data: Envirocare


Full Name: Envirocare of Utah



Waste Inventory



The additional characteristics of the waste: hazardous (chemical); solid (dispersible); solid (non-dispersible); toxic




Page 1 of 1Site Structure: Richland

Full Name:

Location:

Richland, Washington, Radioactive Disposal FacilityU.S. Ecology (subsidiary of American Ecology Inc.)Richland, Washington

License Holder(s) :

Disposal FacilitiesLLWdispNorthwest Compact and Rocky Mountain Compact regions LLW Disposal Facility, operated by U.S. EcologyDisposal facility land leased from USDOE by State of Washington

Name Description



used Depth (m) 1-9


existingcapacity




Class A LLW Yes Yes Class B LLW Yes Yes

Class C LLW Yes Yes Greater than Class C LLW No No

HLW No No


site selection

design

construction


operation 1965

closure


U.S. Ecology/American Ecology Corp.




Page 1 of 1Site Data: Richland


Full Name: Richland, Washington, Radioactive Disposal FacilityU.S. Ecology (subsidiary of American Ecology Inc.)



Waste Inventory











Page 1 of 1Site Structure: ANL-E

Full Name:

Location:Argonne National Laboratory - EastArgonne, Illinois 60439

License Holder(s) :

Processing FacilitiesLLWLLW treatment facilities

Name Description

Type treatment

TRUFaciilties to neutralize, sort, segregate, package and characterize TRU waste

Name Description


Storage FacilitiesSolidsInterim storage of LLW and TRU awaiting disposal

Name Description



LLW building open50 0 NOTRU building open50 0 NO

U.S. Department of Energy, Chicago Operations Office




Page 1 of 1Site Data: ANL-E

Inventory Reporting Date: September 2000 Waste Matrix: USDOE

Full Name: Argonne National Laboratory - East



Waste Inventory


Storage No 7 0 0 0 0 100 0TRU

The additional characteristics of the waste: hazardous (chemical); solid (non-dispersible)

Storage Yes 91.6 0 0 0 0 100 0TRU


Storage No 126.57 0 0 0 0 43 57LLW

The additional characteristics of the waste: hazardous (chemical); liquid (aqueous); liquid (organic); solid (non-dispersible); toxic

Storage Yes 33.71 0 0 0 0 100 0LLW

The additional characteristics of the waste: hazardous (chemical); solid (non-dispersible); toxic


R&D program



Method

Amalgamation (of Mercury) No No Nodecrease



Deactivation (of Sodium) No No Nosame







Page 1 of 1Site Structure: Ashtabula

Full Name:

Location:Ashtabula Environmental Management ProjectAshtabula, Ohio

License Holder(s) :

Processing FacilitiesLLWVolume reduction by shredding and compacting, macroencapsulation, neutralization, solidification, and thermal processing.

Name Description


Storage FacilitiesSolidsInterim storage of LLW awaiting disposal

Name Description



LLW building open50 0 NO

U.S. Department of Energy, Ohio Field Office




Page 1 of 1Site Data: Ashtabula


Full Name: Ashtabula Environmental Management Project



Waste Inventory


Storage No 3064 0 0 0 0 0 100LLW

The additional characteristics of the waste: hazardous (chemical); liquid (organic); sludge; solid (non-dispersible); toxic




R&D program



Method


Encapsulation Yes No No

Macroencapsulation Yes No No

Thermal Treatment (non incineration) Yes No No


R&D program



Method

Solidification Yes No No




Page 1 of 1Site Structure: BNL

Full Name:

Location:Brookhaven National LaboratoryUpton, New York 11973

License Holder(s) :

Processing FacilitiesLLWFacilities for compaction, processing, evaporation, neutralization, and packaging.

Name Description



Name Description




U.S. Department of Energy, Chicago Operations Office




Page 1 of 1Site Data: BNL


Full Name: Brookhaven National Laboratory



Waste Inventory


Storage No 11447.98 0 0 0 0 0 100LLW

The additional characteristics of the waste: flammable; hazardous (chemical); liquid (aqueous); liquid (organic); solid (non-dispersible)




R&D program



Method

Amalgamation (of Mercury) No No Nodecrease


Filtration No No Nodecrease



R&D program



Method





Page 1 of 1Site Structure: Cheney

Full Name:

Location:Cheney Disposal CellNear Grand Junction, Colorado

License Holder(s) :

Disposal Facilities11e2 cellCheney or Grand Junction Disposal Site

Name Description



used Depth (m) 2-20


existingcapacity




HLW No No TRU No No

LLW No No 11e2 Yes Yes


site selection

design

construction


operation 1991 2023

closure 1994 2023


U.S. Department of Energy, Idaho Operations Office, Grand Junction Office




Page 1 of 1Site Data: Cheney


Full Name: Cheney Disposal Cell



Waste Inventory


Disposal No 2850000 0 0 0 0 0 10011e2





Page 1 of 1Site Structure: ETEC

Full Name:

Location:Energy Technology Engineering CenterChatsworth, California

License Holder(s) :

Processing FacilitiesLLWLLW packaging facilities

Name Description

Type


Name Description




U.S. Department of Energy, Oakland Operations Office




Page 1 of 1Site Data: ETEC


Full Name: Energy Technology Engineering Center



Waste Inventory




Storage No 1817.6 0 0 0 0 0 100LLW





Page 1 of 1Site Structure: FEMP

Full Name:

Location:

Fernald Environmental Management Project, formerly Feed Materials Production CenterCincinnati, Ohio 45030

License Holder(s) :


Name Description

Type treatment


Name Description




Disposal FacilitiesOSDFOnsite Disposal Facility - Remediation Waste

Name Description



used Depth (m) 0-15


existingcapacity




HLW No No TRU No No

LLW Yes Yes 11e2 No No


site selection

design



operation 1997 2006

closure 2001 2006


U.S. Department of Energy, Ohio Field Office




Page 1 of 1Site Data: FEMP


Full Name: Fernald Environmental Management Project, formerly Feed Materials Production Center



Waste Inventory


Storage No 39665.6 0 0 0 0 0 100LLW

The additional characteristics of the waste: hazardous (chemical); liquid (aqueous); liquid (organic); sludge; solid (dispersible); solid (non-dispersible); toxic



Disposal No 426126 0 0 0 0 0 100LLW



R&D program



Method






Page 1 of 4Site Structure: Hanford

Full Name:

Location:Hanford SiteRichland, Washington 99352

License Holder(s) :

Processing FacilitiesHLWCurrent facilities include evaporation and filtration, construction has begun on low-activity waste phase 1 vitrification plant.

Name Description


LLWLLW treatment and conditioning facilities

Name Description


TRUTRU treatment facilities (WRAP)

Name Description

Type treatment

Storage FacilitiesHLW TanksHanford Tank Farms with HLW

Name Description



DST tank (stainless steel) open50 80 NOSST tank (other) open50 10 NO

SolidsInterim storage of LLW and TRU awaiting disposal

Name Description




Disposal FacilitiesLLWHanford 200 Area Burial Grounds, excluding Trenches 31 & 34 used for MLLW disposal

Name Description



used Depth (m) 6-24


existingcapacity

U.S. Department of Enery, Richland Operations Office

U.S. Department of Energy, Office of River Protection








HLW No No TRU No No




design 1945 1945



operation 1945 2046

closure 2046 2046


MLLWMixed Waste Trenches 31 & 34

Name Description



used Depth (m) 6-24


existingcapacity




HLW No No TRU No No




design 1986 1986



operation 2046 2046

closure 2046 2046






ERDFEnvironmental Restoration Disposal Facility

Name Description



used Depth (m) 0-70


existingcapacity




HLW No No TRU No No




design 1994 1996



operation 1996 2035

closure 2035 2035


ILAWImmobilized low activity waste trenches for disposal of incidental waste from HLW treatment

Name Description



used Depth (m) 0-10


existingcapacity




HLW No No TRU No No

LLW No Yes 11e2 No No



design 2001 2004



operation 2008 2026

closure 2026 2028


Dedicated SRSWESFWaste encapsulation and storage facilityHot cells and storage pool used for storage of Cs and Sr capsules separated from HLW

Name Description

storageType




Page 1 of 1Site Data: Hanford


Full Name: Hanford Site



Waste Inventory


Storage No 206831.89 0 0 0 0 100 0HLW

The additional characteristics of the waste: hazardous (chemical); liquid (aqueous); liquid (organic); solid (non-dispersible)

Storage No 16408.04 0 0 0 0 100 0TRU


Storage No 7975.58 0 0 0 0 100 0LLW

The additional characteristics of the waste: hazardous (chemical); liquid (organic); solid (non-dispersible); toxic

Disposal No 1079066 0 0 0 0 0 100LLW


Disposal Yes 259060 0 0 0 0 100 0LLW



R&D program



Method







R&D program



Method

Vitrification Yes No No




Nuclide

num./activity


equal 4E+4GBq

num./activity

Group III more than

4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

601

8.50E+08

No Yes 1 1996.06Sr-90 8.50E+08

1328

2.00E+09

No Yes 1 1996.06Cs-137 2.00E+09




Page 1 of 2Site Structure: INEEL

Full Name:

Location:Idaho National Engineering and Environmental LaboratoryIdaho Falls, ID

License Holder(s) :

Processing FacilitiesHLWExisting facilities for evaporation and calcination. Conditioning facilities in environmental impact statement process.

Name Description


LLWTreatment and conditioning facilities for LLW.

Name Description


TRUFacilities for characterization, packaging, sorting/size reduction (in construction)

Name Description

Type treatment


Name Description




HLW TanksLiquid HLW tanks

Name Description



HLW Tanks tank (other) open50 50 NO

CalcineCalcined Solids Storage Facility

Name Description



Calcine tank (stainless steel) open50 50 NO

Disposal FacilitiesRWMC-SDARadioactive Waste Management Complex

Name Description


U.S. Department of Energy, Idaho Operations Office




Page 2 of 2Site Structure: INEEL


used Depth (m) 1-8


existingcapacity




HLW No No TRU No No




design 1949 1951



operation 1952 2035

closure 2036 2036


CERCLAIdaho CERCLA Disposal Facility and INEEL Remediation Unit (under construction)

Name Description



used Depth (m) 0-5


existingcapacity




HLW No No TRU No No




design 1997 2002



operation 2002 2012

closure 2012 2012





Page 1 of 1Site Data: INEEL


Full Name: Idaho National Engineering and Environmental Laboratory



Waste Inventory


Storage No 9393.88 0 0 0 0 100 0HLW

The additional characteristics of the waste: hazardous (chemical); liquid (aqueous); liquid (organic); solid (non-dispersible)

Storage No 64370 0 0 0 0 100 0TRU


Storage Yes 501 0 0 0 0 100 0TRU


Storage No 4978 0 0 0 0 100 0LLW

The additional characteristics of the waste: flammable; hazardous (chemical); liquid (aqueous); liquid (organic); solid (non-dispersible); toxic

Storage Yes 85.88 0 0 0 0 100 0LLW


Disposal No 255 0 0 0 0 100 0LLW





R&D program



Method

Calcination No No Nodecrease

Calcine Dissolution Yes No No



Filter Leaching No No Nosame


Stabilization Yes No No


R&D program



Method


Vitrification Yes No No




Page 1 of 1Site Structure: ITRI

Full Name:

Location:

Inhalation Toxicology Research InstituteLovelace Biomedical LaboratoriesAlbuquerque, New Mexico

License Holder(s) :

Processing FacilitiesLLWSmall facility for onsite compaction, solidification, and neutralization of LLW

Name Description



Name Description




U.S. Department of Energy, Albuquerque Operations Office




Page 1 of 1Site Data: ITRI


Full Name: Inhalation Toxicology Research InstituteLovelace Biomedical Laboratories



Waste Inventory


Storage No 0.3 0 0 0 0 100 0TRU


Storage No 36 0 0 0 0 100 0LLW





R&D program



Method




R&D program



Method





Page 1 of 2Site Structure: LANL

Full Name:

Location:Los Alamos National LaboratoryLos Alamos, New Mexico 87545

License Holder(s) :

Processing FacilitiesLLWTA-54 Area G compactor

Name Description

Type treatment

TRUTRU packaging and characterization facilities

Name Description

Type


Name Description




Disposal FacilitiesTA54 AreaGArea G disposal area, Technical Area 54

Name Description



used Depth (m) 2-20


existingcapacity




HLW No No TRU No No



site selection

design

construction


operation 1958 2070

closure 2070 2070


U.S. Department of Energy, Albuqerque Operations Office, Los Alamos Area Office

Dedicated SRSTA-54Name

Description© 2000-2002, International Atomic Energy Agency. This page generated at 2002-11-19 19:10:56 (local Vienna time.)



Page 2 of 2Site Structure: LANL

Technical Area 54 provides storage for sources of the USDOE Offsite Recovery Program and limited disposal for sources meeting LLW disposal facility acceptance requirements

Description

conditioning, storage, disposalTypeCMRThe Chemical and Metallurgy Research Building provides source consolidation services

Name Description

conditioningType




Page 1 of 1Site Data: LANL


Full Name: Los Alamos National Laboratory



Waste Inventory


Storage No 9442.7 0 0 0 0 100 0TRU


Storage No 152.27 0 0 0 0 100 0LLW

The additional characteristics of the waste: gas; hazardous (chemical); liquid (aqueous); liquid (organic); sludge; solid (non-dispersible); toxic

Disposal No 47333 0 0 0 0 100 0LLW





R&D program



Method





Nuclide

num./activity


equal 4E+4GBq

num./activity

Group III more than

4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

9

7.60E+07

No Yes 1 2002.01Sr-90 7.60E+07




Nuclide

num./activity


equal 4E+4GBq

num./activity

uncond

cat.

Decay Date Total


(GBq)

2

4.80E+00

No Yes 3 2002.01Pu-239 4.80E+00

672

1.20E+03

592

1.90E+04

No Yes 2 2002.01Am-241 2.02E+04

81

1.50E+02

316

1.00E+04

No Yes 3 2002.01Am-241 1.02E+04

54

6.30E+03

No Yes 2 2002.01Pu-239 6.30E+03

1865

6.20E+05

No Yes 2 2002.01Pu-238 6.20E+05




Page 1 of 1Site Structure: LBNL

Full Name:

Location:Lawrence Berkeley National Laboratory1 Cyclotron Road, Berkeley, CA 94720

License Holder(s) :


Name Description

Type treatment


Name Description








Page 1 of 1Site Data: LBNL


Full Name: Lawrence Berkeley National Laboratory



Waste Inventory


Storage No 1.73 0 0 0 100 0 0TRU


Storage No 79.9 0 0 0 100 0 0LLW


Storage Yes 1.5 0 0 0 100 0 0LLW

The additional characteristics of the waste: hazardous (chemical); liquid (aqueous); solid (non-dispersible); toxic


R&D program



Method





Page 1 of 1Site Structure: LEHR

Full Name:

Location:Laboratory for Energy-Related Health ResearchDavis, California

License Holder(s) :


Name Description

Type treatment


Name Description





University of California




Page 1 of 1Site Data: LEHR


Full Name: Laboratory for Energy-Related Health Research



Waste Inventory





R&D program



Method

Stabilization No No Nodecrease




Page 1 of 1Site Structure: LLNL

Full Name:

Location:Lawrence Livermore National LaboratoryLivermore, California 94550

License Holder(s) :


Name Description

Type treatment

TRUTRU packaging facilities

Name Description

Type


Name Description








Page 1 of 1Site Data: LLNL


Full Name: Lawrence Livermore National Laboratory



Waste Inventory


Storage No 295 0 0 0 0 100 0TRU


Storage No 1661.28 0 0 0 0 100 0LLW



R&D program



Method


Size Reduction No No Nosame






Page 1 of 1Site Structure: MEMP

Full Name:

Location:Miamisburg Environmental Management ProjectMiamisburg, Ohio 45342-0066

License Holder(s) :

Processing FacilitiesTRUTRU waste packaging

Name Description

Type

LLWLLW packaging

Name Description

Type

Storage FacilitiesSolidsInterim storage of TRU awaiting disposal

Name Description



TRU building open10 0 NO

U.S. Department of Energy, Ohio Operations Office, Miamisburg Project Office




Page 1 of 1Site Data: MEMP


Full Name: Miamisburg Environmental Management Project



Waste Inventory


Storage No 247.01 0 0 0 0 0 100TRU





Page 1 of 1Site Structure: Monticello

Full Name:

Location:Monticello Remedial Action ProjectMonticello, Utah

License Holder(s) :

Disposal Facilities11e2 CellDisposal cell - mill tailing design

Name Description



used Depth (m) 0-15


existingcapacity




HLW No No TRU No No

LLW No No 11e2 Yes No


site selection 1994

design 1995 1995



operation 1997 2001

closure 2001 2001


U.S. Department of Energy, Idaho Operations Office, Grand Junction Office




Page 1 of 1Site Data: Monticello


Full Name: Monticello Remedial Action Project



Waste Inventory


Disposal No 2000000 0 0 0 0 0 10011e2





Page 1 of 2Site Structure: NTS

Full Name:

Location:Nevada Test SiteMercury, Nevada (northwest of Las Vegas) 89023

License Holder(s) :

Storage FacilitiesSolidsInterim storage of TRU awaiting disposal

Name Description



TRU building open50 0 NO

Disposal FacilitiesArea3&5LLWAreas 3&5 Radioactive Waste Management Sites(Area 3-use of subsidence craters from testing for LLW disposal)(Area 5-trenches)

Name Description



used Depth (m) 2-30


existingcapacity




HLW No No TRU No No



site selection

design



operation 1960 2015

closure 1965 2015


U.S. Department of Energy, Nevada Operations Office




Page 2 of 2Site Structure: NTS

Area 5 MWArea 5 Pit 3, Mixed Waste Disposal Unit

Name Description



used Depth (m)


existingcapacity




HLW No No TRU No No



site selection

design 2002

construction 2003

commissioning 2003

operation 1995 2015

closure 2015 2015


Area 5 GCDGreater confinement boreholes at Area 5

Name Description

boreholeTypeFacility is non modular


used Depth (m) 36

volcanic tuffHost medium

existingcapacity




HLW No No TRU Yes No

LLW Yes No 11e2 No No


site selection

design



operation 1983 1989

closure 1984 2015





Page 1 of 1Site Data: NTS


Full Name: Nevada Test Site



Waste Inventory


Storage No 459.86 0 0 0 0 100 0TRU


Storage Yes 154.75 0 0 0 0 100 0TRU


Disposal No 200 0 0 0 0 100 0TRU


Storage No 0.31 0 0 0 0 100 0LLW


Disposal No 378103 0 0 0 0 20 80LLW







Page 1 of 2Site Structure: OakRidge

Full Name:

Location:

Oak Ridge Reservation, including Oak Ridge National Laboratory and East Tennessee Technology ParkOak Ridge National Laboratory, Bethel Valley Road, Oak Ridge, Tennessee 37831East Tennessee Technology Park, Oak Ridge, Tennessee

License Holder(s) :

Processing FacilitiesLLWFacilities for neutralization, solidification, packaging, overpacking, evaporation, compaction, and incineration.

Name Description


TRUFacilities for sludge/supernate and debris stabilization and packaging,

Name Description


Storage FacilitiesSolidsInterim storage of LLW & TRU waste awaiting disposal

Name Description



TRUSolids building open50 0 NOLLW building open50 0 NOTRULiquids tank (concrete) open50 50 NOLegacyLLW concrete pad open10 0 NO

Disposal FacilitiesIWMFInterim Waste Management Facility

Name Description



used Depth (m) abovegrnd


existingcapacity




HLW No No TRU No No




design 1986 1990



operation 1991 2005

closure 2005 2005


U.S. Department of Energy, Oak Ridge Operations Office




Page 2 of 2Site Structure: OakRidge

EMWMFEnvironmental Mangagement Waste Management Facility- CERCLA Remedial Action Facility

Name Description



used Depth (m) 0-10


existingcapacity




HLW No No TRU No No



site selection

design 2001 2001



operation 2002 2015

closure 2015 2033





Page 1 of 1Site Data: OakRidge


Full Name: Oak Ridge Reservation, including Oak Ridge National Laboratory and East Tennessee Technology Park



Waste Inventory


Storage No 2437.6 0 0 0 0 100 0TRU


Storage No 38409.2 0 0 0 10 80 10LLW

The additional characteristics of the waste: hazardous (chemical); liquid (aqueous); liquid (organic); sludge; solid (dispersible); solid (non-dispersible); toxic

Storage Yes 4941 0 0 0 10 80 10LLW

The additional characteristics of the waste: hazardous (chemical); sludge; toxic




R&D program



Method



Oxidation No No Noincrease

Rinsing No No Nosame




R&D program



Method

Solidification Yes No No




Page 1 of 1Site Structure: OCRWM

Full Name:

Location:Site Investigation, Federal Geologic RepositoryYucca Mountain, Northwest of Las Vegas, Nevada

License Holder(s) :

Disposal FacilitiesRepositoryGeologic repository site investigation, currently at the Yucca Mountain site(capacity below is vol of HLW cannisters plannned to be disposed in the future)

Name Description



used Depth (m) 300

volcanic tuffHost medium

existingcapacity




HLW No Yes TRU No No

LLW No No 11e2 No No



design 2002 2005



operation 2010 2109

closure 2110 2116


US Department of Energy, Office of Civilian Radioactive Waste Management




Page 1 of 1Site Structure: OtherDOE

Full Name:

Location:All other US Department of Energy sites with rad waste storage facilitiesArgonne National Laboratory-West, Ames Laboratory, Columbus Environmental Management Project, Grand Junction Project Office, and Princeton Plasma Physics Laboratory

License Holder(s) :

Processing FacilitiesLLWLLW treatment facilities at Princeton andBattelle Columbus

Name Description

Type treatment


Name Description




U.S. Department of Energy




Page 1 of 1Site Data: OtherDOE


Full Name: All other US Department of Energy sites with rad waste storage facilities



Waste Inventory


Storage No 60.9 0 0 0 0 100 0TRU

Storage No 233.14 0 0 0 50 25 25LLW

The additional characteristics of the waste: hazardous (chemical); liquid (aqueous); liquid (organic); sludge; toxic

Storage Yes 0.1 0 0 0 100 0 0LLW



R&D program



Method


Deactivation (of Sodium) No No Nodecrease

Filtration No No Nodecrease





R&D program



Method





Page 1 of 1Site Structure: Paducah

Full Name:

Location:Paducah Gaseous Diffusion PlantWest Paducah, Kentucky

License Holder(s) :

Processing FacilitiesLLWPackaging and Vortec vitrification process in planning

Name Description



Name Description




U.S. Department of Energy, Oak Ridge Operations Office, Paducah Site Office

U.S. Enrichment Corporation




Page 1 of 1Site Data: Paducah


Full Name: Paducah Gaseous Diffusion Plant



Waste Inventory


Storage No 4.6 0 100 0 0 0 0TRU

The additional characteristics of the waste: hazardous (chemical); liquid (organic); solid (dispersible); solid (non-dispersible); toxic

Storage No 10757.18 0 100 0 0 0 0LLW



R&D program



Method





R&D program



Method





Page 1 of 1Site Structure: Pantex

Full Name:

Location:Pantex PlantAmarillo, Texas

License Holder(s) :


Name Description

Type treatment


Name Description








Page 1 of 1Site Data: Pantex


Full Name: Pantex Plant



Waste Inventory


Storage No 104.34 0 0 0 0 100 0LLW

The additional characteristics of the waste: explosive; flammable; gas; hazardous (chemical); liquid (aqueous); liquid (organic); solid (non-dispersible); toxic

Storage Yes 4.61 0 0 0 0 100 0LLW

The additional characteristics of the waste: liquid (organic); solid (non-dispersible)


R&D program



Method

Evaporation No No Nodecrease

Thermal Treatment (non incineration) No No Nodecrease




Page 1 of 1Site Structure: Portsmouth

Full Name:

Location:Portsmouth Gaseous Diffusion PlantPiketon, Ohio

License Holder(s) :


Name Description





U.S. Enrichment Corporation




Page 1 of 1Site Data: Portsmouth


Full Name: Portsmouth Gaseous Diffusion Plant



Waste Inventory


Storage No 24064.36 0 100 0 0 0 0LLW

The additional characteristics of the waste: gas; hazardous (chemical); liquid (aqueous); liquid (organic); solid (non-dispersible); toxic




Page 1 of 1Site Structure: RFETS

Full Name:

Location:Rocky Flats Environmental Technology SiteGolden, Colorado 80403-8200

License Holder(s) :


Name Description

Type treatment

TRUTRU characterization and packaging facilities

Name Description

Type

Storage FacilitiessolidsLegacy interim waste storage of LLW, TRU, and MLLW awaiting disposal - various buildings

Name Description



LLW building open50 0 NOMLLW building open50 0 NOTRU building open50 98 NO

US Department of Energy, Rocky Flats Field Office




Page 1 of 1Site Data: RFETS


Full Name: Rocky Flats Environmental Technology Site



Waste Inventory


Storage No 5309 0 0 0 0 100 0TRU

The additional characteristics of the waste: hazardous (chemical); solid (dispersible); solid (non-dispersible)

Storage Yes 19297.85 0 0 0 0 100 0LLW



R&D program



Method

Evaporation Yes No No




Page 1 of 1Site Structure: SNL

Full Name:

Location:Sandia National LaboratoriesAlbuquerque, New MexicoLivermore, California

License Holder(s) :


Name Description

Type treatment

TRUTRU packaging facilities

Name Description

Type


Name Description








Page 1 of 1Site Data: SNL


Full Name: Sandia National Laboratories



Waste Inventory




Storage Yes 8.2 0 0 0 0 100 0TRU


Storage No 613.9 0 0 0 44 44 12LLW


Storage Yes 33.35 0 0 0 50 50 0LLW

The additional characteristics of the waste: hazardous (chemical); sludge; solid (non-dispersible); toxic


R&D program



Method

Encapsulation No No Noincrease







Page 1 of 3Site Structure: SRS

Full Name:

Location:Savannah River SiteAiken, South Carolina 29802

License Holder(s) :

Processing FacilitiesLLWLLW treatment and conditioning facilities.

Name Description


HLWDefense Waste Processing Facility (vitrification); also facilities for evaporation and pretreatment for vitrification.

Name Description


TRUTRU treatment facility is planned; current facilities for characaterization and packaging

Name Description

Type treatment


Name Description




GlassGlass Waste Storage Building for interim storage of vitirified HLW awaiting shipment to repository

Name Description



Glass building open30 10 NO

HLW TanksF and H Area Tank Farms with HLW

Name Description



HLW Tanks tank (stainless steel) open50 75 NO

Disposal FacilitiesLAW VaultsLow Activity Waste Vaults

Name Description


U.S. Department of Energy, Savannah River Operations Office






used Depth (m) abovegrnd


existingcapacity




HLW No No TRU No No




design 1992 1993



operation 1995 2050

closure 2050 2050


ILW VaultsIntermediate Level Waste Vaults

Name Description



used Depth (m) 0-5


existingcapacity




HLW No No TRU No No




design 1992 1994



operation 1995 2050

closure 2050 2050






E-AreaE-Area Trenches

Name Description



used Depth (m) 1-6


existingcapacity




HLW No No TRU No No




design 1995 1997



operation 1998 2050

closure 2050 2050


SaltstoneStabilized (grouted) low-activity fraction from HLW processing

Name Description



used Depth (m) 0-5


existingcapacity




HLW No No TRU No No




design 1989 1995



operation 1996 2025

closure 2025 2025





Page 1 of 1Site Data: SRS


Full Name: Savannah River Site



Waste Inventory


Storage No 137206 0 0 0 0 100 0HLW

The additional characteristics of the waste: hazardous (chemical); liquid (aqueous); liquid (organic)

Storage Yes 600 0 0 0 0 100 0HLW


Storage No 10848.95 0 0 0 0 100 0TRU


Storage No 12397.63 0 0 0 10 80 10LLW


Storage Yes 2671 0 0 0 10 80 10LLW


Disposal No 13798 0 0 0 0 70 30LLW





R&D program



Method


Decontamination Yes No No


Incineration Yes No Yes

Size Reduction Yes No No

Sludge washing No No Noincrease

Stabilization Yes No Yes


Water/Acid Washing Yes No No


R&D program



Method





Page 1 of 1Site Structure: WIPP

Full Name:

Location:Waste Isolation Pilot Plant26 miles southeast of Carlsbad, New Mexico 88220

License Holder(s) :

Disposal FacilitiesWIPPGeologic Disposal Facility for Defense TRU Waste

Name Description



used Depth (m) 655

sedimentary rock (bedded salt)Host medium

existingcapacity




HLW No No TRU Yes Yes

LLW No No 11e2 No No



design 1980 1982



operation 1999 2034

closure 2035 2039


US Department of Energy, Carlsbad Field Office




Page 1 of 1Site Data: WIPP


Full Name: Waste Isolation Pilot Plant



Waste Inventory


Disposal Yes 645.6 0 0 0 0 100 0TRU

The additional characteristics of the waste: hazardous (chemical); solid (dispersible); solid (non-dispersible)




Page 1 of 1Site Structure: WSSRAP

Full Name:

Location:Weldon Spring Site Remedial Action ProjectSt. Charles, Missouri

License Holder(s) :

Disposal Facilities11e2 cellDisposal cell - mill tailing design

Name Description



used Depth (m) 65-0 (AG)


existingcapacity




HLW No No TRU No No

LLW No No 11e2 Yes No


site selection

design 1995 1997



operation 1998 2001

closure 1998 2002






Page 1 of 1Site Data: WSSRAP


Full Name: Weldon Spring Site Remedial Action Project



Waste Inventory


Disposal No 930000 0 0 0 0 0 10011e2


Disposal Yes 190000 0 0 0 0 0 10011e2





Page 1 of 1Site Structure: WVDP

Full Name:

Location:West Valley Demonstration Project, formerly West Valley Nuclear ServicesWest Valley, New York 14171

License Holder(s) :

Processing FacilitiesHLWHLW vitrification plant

Name Description


LLWLLW treatment facilities.

Name Description

Type treatment

TRUPackaging facility

Name Description

Type

Storage FacilitiesGlassVitrified HLW canisters are stored in a former process cell awaiting shipment to a repository

Name Description



HLWcell building open50 50 NO

HLWtanksHLW tank farm

Name Description



HLW tanks tank (stainless steel) open50 1 NO

SolidsInterim storage of LLW and TRU waste awaiting disposal

Name Description




State of New York

U.S. Department of Energy, Ohio Field Office, West Valley Project Office




Page 1 of 1Site Data: WVDP


Full Name: West Valley Demonstration Project, formerly West Valley Nuclear Services



Waste Inventory


Storage No 69 0 0 100 0 0 0HLW

The additional characteristics of the waste: hazardous (chemical); liquid (aqueous); liquid (organic); sludge

Storage Yes 160 0 0 100 0 0 0HLW


Storage No 547.64 0 0 100 0 0 0TRU


Storage No 11317.22 0 0 0 0 0 100LLW

The additional characteristics of the waste: hazardous (chemical); liquid (organic); sludge; solid (non-dispersible); toxic

Storage Yes 5173 0 0 0 0 0 100LLW



R&D program



Method




R&D program



Method

Vitrification No No Nodecrease



REGULATORSCountry: United States of America Reporting Year: 2000

Page 1 of 1

EPA

Headquarters: Office of Radiation and Indoor Air and Office of Solid WasteRegional offices

Name

Division

U.S. Environmental Protection AgencyFull Name

Washington DC and regional offices throughout the USACity or Town

Matrix USDOE - HLW, TRU, LLW, 11e2; matrix USNRC - Class A LLW, Class B LLW, Class C LLW


States

Various State Radiation Protection Agencies for NRC Agreement State (33 states) authorityVarious State Environmental Departments for hazardous waste (RCRA) Authorityand permitting under environmental statutes

Name

Division

50 State government agencies throughout the USAFull Name

Various LocationsCity or Town



NRC

Headquarters: Office of Nuclear Materials and SafeguardsRegional Offices

Name

Division

US Nuclear Regulatory CommissionFull Name

Washington, DC and regional offices throughout the USACity or Town

Matrix USDOE - HLW; matrix USNRC - Greater than Class C LLW, HLWWastes that are regulated by the Regulator

DOE

Office of Environment, Safety, and HealthOffice of Independent Oversight and Performance AssuranceOffice of Environmental Management

Name

Division

United States Department of EnergyFull Name

Washington, DCCity or Town

Matrix USDOE - HLW, TRU, LLW, 11e2Wastes that are regulated by the Regulator

DOT

Headquarters - regulate transportation of radioactive waste

Name

Division

U.S. Department of TransportationFull Name

Washington, DCCity or Town





REGULATIONSCountry: United States of America Reporting Year: 2000

Page 1 of 15

DOEO435.1Name Radioactive Waste ManagementUS Department of Energy Order (Manual and Implementation Guide)

Title or Name

Matrix USDOE - HLW, TRU, LLWWastes that are covered by the identified Law

DOE O 435.1 (DOE M 435.1-1 DOE G 435.1-1)Reference Number 1999-07-09Date Promulgated


NWPAName Nuclear Waste Policy Act of 1982, as amended in 1987, Public Law 97-425Implementing Regulations: Title 10, Code of Federal Regulations, Parts 53, 60, and 960-962also Title 40, Code of Federal Regulations, Part 191

Title or Name

Matrix USDOE - HLW; matrix USNRC - Class A LLW, Class B LLW, Class C LLW, Greater than Class C LLW, HLW


Title 42, U.S. Code, Sect. 10101 et seq.Reference Number 1983-01-07Date Promulgated

or ProclaimedLaw

AEAName Atomic Energy Act of 1954 as amendedImplementing Regulations: Title 10, Code of Federal Regulations, Parts 20, 39, 60-61, 71, 100, 762, 960. and 962also Title 40, Code of Federal Regulations, Parts 190-194

Title or Name

Matrix USDOE - HLW, TRU, LLW, 11e2; matrix USNRC - Class A LLW, Class B LLW, Class C LLW, Greater than Class C LLW, HLW


Title 42, U.S. Code, Sections 2011-2259Reference Number 1954-01-01Date Promulgated

or ProclaimedLaw

UMTRCAName Uranium Mill Tailings Radiation Control Act of 1978, Public Law 95-604Implementing Regulation: Title 40, Code of Federal Regulations, Part 192

Title or Name

Matrix USDOE - 11e2Wastes that are covered by the identified Law

Title 42, U.S. Code, Sect. 7901-7942Reference Number 1978-11-08Date Promulgated

or ProclaimedLaw




Page 2 of 15

CERCLAName Comprehensive Environmental Response, Compensation, and Liability Actas amended by the Superfund Amendments and Reauthorization Act of 1984Implementing Regulations: Title 40, Code of Federal Regulations, Parts 300-372

Title or Name




or ProclaimedLaw

RCRAName Resource Conservation and Recovery Act. Public Law 94-580as amended by the Hazardous and Solid Waste Amendment of 1984 (public law 98-616)Implementing Regulations: Title 40 Code of Federal Regulations, Parts 240-257, 260-280

Title or Name



Title 42, U.S. Code, Sect. 6901-6991iReference Number 1976-01-01Date Promulgated

or ProclaimedLaw

FFCAName Federal Facilities Compliance ActTitle or Name


Public Law 102-386Reference Number 1992-10-01Date Promulgated

or ProclaimedLaw




Page 3 of 15

TSCAName Toxic Substances Control Act, Public Law 94-469including Asbestos Hazard Emergency Act, Public Law 99-519 Implementing Regulations: Title 40, Code of Federal Regulations, 1500-1508

Title or Name



Title 15, U.S. Code, Sections 2601-2654Reference Number 1976-10-11Date Promulgated

or ProclaimedLaw

NEPAName National Environmental Policy Act, Public Law 91-190Title or Name

Matrix USDOE - HLW, TRU, LLW, 11e2Wastes that are covered by the identified Law

Title 42, U.S. Code, Section 4321-4370aReference Number 1970-01-01Date Promulgated

or ProclaimedLaw

DOE Order 451.1B dated 10/26/2000

Comment #123: DOE Implementing Order

LLRWPAName Low-level Radioactive Waste Policy Act, Public Law 96-573, as amendedincludes Amendments Act of 1985 and Amendments Act of 1995includes consent of Congress for LLW compacts

Title or Name

Matrix USNRC - Class A LLW, Class B LLW, Class C LLW, Greater than Class C LLW, HLW


Title 42, US Code, Section 2021Reference Number 1980-12-22Date Promulgated

or ProclaimedLaw




Page 4 of 15

10CFR61Name Licensing requirements for land disposal of radioactive wasteTitle or Name

Matrix USNRC - Class A LLW, Class B LLW, Class C LLW, Greater than Class C LLW


Title 10, Code of Federal Reglations, Part 61Reference Number 1960-01-01Date Promulgated


Each agreement state has enabling regulations that must be equivalent or more restrictive than those promulgated by USNRC.

Comment #122: Agreement State Regulations

40CFR191Name Disposal Standards for Long-lived WasteTitle or Name

Matrix USDOE - HLW, TRUWastes that are covered by the identified Law



WIPP-LWAName Waste Isolation Pilot Plant Land Withdrawal ActTitle or Name

Matrix USDOE - TRUWastes that are covered by the identified Law

Public Law 102-549Reference Number 1992-10-01Date Promulgated

or ProclaimedLaw




Page 5 of 15

10CFR830Name Nuclear Safety ManagementTitle or Name


Title 10, Code of Federal Regulations, Part 830Reference Number 2001-01-01Date Promulgated


DOE Order 5480.21, Unreviewed Safety Questions 12/24/1991DOE Order 5480.22, Change 2, Technical Safety Requirements, 1/23/1996DOE Order 5480.23, Change 1, Nuclear Safety Analysis Reports, 3/10/1994

Comment #124: Additional DOE Orders related to Nuclear Safety

DOEO5400.5Name Radiation Protection of the Public and the EnvironmentTitle or Name


DOE Order 5400.5, Chg. 2Reference Number 1993-01-07Date Promulgated


DOE5480.19Name Conduct of Operations Requirements for Nuclear FacilitiesTitle or Name


DOE Order 5480.19, Change 1Reference Number 1992-05-18Date Promulgated


DOEO5400.1Name General Environmental ProtectionTitle or Name


DOE Order 5400.1Reference Number 1990-06-29Date Promulgated





Page 6 of 15

DOE5480.20Name Personnel Selection, Qualification, and Training RequirementsTitle or Name


DOE Order 5480.20AReference Number 2001-07-12Date Promulgated


DOEO151.1AName Comprehensive Emergency Management SystemTitle or Name




DOEO231.1Name Environment, Safety, and Health ReportingTitle or Name


DOE Order 231.1, Change 2Reference Number 1996-11-07Date Promulgated


DOEO232.1AName Occurrence Reporting and Processing of Operations InformationTitle or Name







Page 7 of 15

DOEO430.1AName Life Cycle Asset ManagementTitle or Name




DOE433.1Name Maintenance Management ProgramTitle or Name




HMTAName Hazardous Materials Transportation Act, Public Law 101-416Hazardous Materials Transportation Uniform Safety Act of 1990, Public Law 101-615Implementing Regulations: Title 49, Code of Federal Regulations, Parts 100-199

Title or Name



Title 49, U.S. Code, Sect. 1801-1812, 5101-5103Reference Number 1990-11-16Date Promulgated

or ProclaimedLaw

DOEO460.1AName Packaging and Transportation SafetyTitle or Name







Page 8 of 15

10CFR835Name Occupational Radiation ProtectionTitle or Name




DOE Order 5480.4, Change 4, 1/7/1993 was in effect when 10CFR835 was promulgated

Comment #125: Other DOE order on Rad Protection

DOE470.2AName Security and Emergency Management Independent Oversight and Performance Assurance Program

Title or Name




DOEO414.1Name Quality Assurance (guidance also)Title or Name




DOEO200.1Name Information Management ProgramTitle or Name







Page 9 of 15

DOE470.1Name Safeguards and SecurityTitle or Name


DOE Order 470.1, Chnage 1Reference Number 1995-09-28Date Promulgated


DOEO360.1Name Federal Employee TrainingTitle or Name




DOEO425.1BName Startup and restart of Nuclear FacilitiesTitle or Name


DOE Order 425.1BReference Number 2000-12-21Date Promulgated


DOE440.1AName Worker Protection Management for DOE Federal and Contractor EmployeesTitle or Name


DOE Order 440.1A, Change 3Reference Number 1998-03-27Date Promulgated





Page 10 of 15

DOEO420.1Name Facility SafetyTitle or Name




10CFR960Name General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories

Title or Name

Matrix USDOE - HLWWastes that are covered by the identified Law



10CFR961Name Standard contract for disposal of spent nuclear fuel and high level wasteTitle or Name

Matrix USDOE - HLW; matrix USNRC - HLWWastes that are covered by the identified Law



10CFR962Name Byproduct MaterialTitle or Name

Matrix USDOE - 11e2Wastes that are covered by the identified Law


or ProclaimedLaw




Page 11 of 15

10CFR51Name Environmental protection regulation for domestic licensing and related regulatory functions

Title or Name

Matrix USNRC - Class A LLW, Class B LLW, Class C LLW, Greater than Class C LLW, HLW




10CFR60Name Disposal of high-level radioactive wastes in geologic repositoriesTitle or Name




10CFR62Name Criteria and procedures for emergency accesss to non-federal and regional low-level waste disposal facilities

Title or Name

Matrix USNRC - Class A LLW, Class B LLW, Class C LLW, Greater than Class C LLW




10CFR71Name Packaging and transportation of radioactive wasteTitle or Name

Matrix USDOE - HLW, TRU; matrix USNRC - Class A LLW, Class B LLW, Class C LLW, Greater than Class C LLW, HLW







Page 12 of 15

10CFR72Name Licensing requirements for the independent storage of spent nuclear fuel and high level radioactive waste

Title or Name

Matrix USNRC - HLWWastes that are covered by the identified Law



CAAName Clean Air Act(Implementing Regulations: Title 40, Code of Federal Regulations, Parts 50-87)

Title or Name




or ProclaimedLaw

CWAName Clean Water ActImplementing Regulations, Title 40, Code of Federal Regulations, Parts 100-136, 230-233, 400-471)Implementing Regulations, Title 33, Code of Federal Regulations, Parts 320, 323, 325, 328 and 330

Title or Name




or ProclaimedLaw




Page 13 of 15

SDWAName Safe Drinking Water ActImplementing Regulations: Title 40, Code of Federal Regulations, Parts 141-149

Title or Name

Matrix USDOE - HLW, TRU, 11e2; matrix USNRC - Class A LLW, Class B LLW, Class C LLW, Greater than Class C LLW, HLW


Title 42, U.S. Code, Sect. 300f-300j-11Reference Number 1974-01-01Date Promulgated

or ProclaimedLaw

OSHAName Occupational Safety and Health ActImplementing Regulations: Title 29, Code of Federal Regulations, Parts 1990-19990

Title or Name



Title 29, U.S. Code, Sect. 651 et seq.Reference Number 1970-01-01Date Promulgated

or ProclaimedLaw

EnergyReorName Energy Reorganization Act of 1974, Public Law 93-438Title or Name



Title 42, US Code, Sections 5801-5891Reference Number 1974-10-11Date Promulgated

or ProclaimedLaw

WVDPAName West Valley Demonstration Project Act, Public Law 96-368Title or Name


Title 42, US Code, Section 2021aReference Number 1980-10-01Date Promulgated

or ProclaimedLaw




Page 14 of 15

FFCActName Federal Facilities Compliance Act of 1992, Public Law 102-386Title or Name


Title 42, US Code, Section 6961Reference Number 1992-01-01Date Promulgated

or ProclaimedLaw

EnPolActName Energy Policy Act of 1992Title or Name


Title42, United States Code, Part 2296Reference Number 1992-01-01Date Promulgated

or ProclaimedLaw

10CFR963Name Amended Yucca Mountain Site Suitabiilty GuidelinesTitle or Name


Title 10, Code of Federal Regulations, Subpart 963Reference Number 2001-11-14Date Promulgated


40CFR197Name Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada

Title or Name







Page 15 of 15

10CFR63Name Disposal of high-level radioactive waste in a geologic repository at Yucca Mountain. Nevada (licensing regulations)

Title or Name






MILESTONESCountry: United States of America Reporting Year: 2000

Page 1 of 4


Manhattan Project creates radioactive waste at several sites in the USADescription of Milestone

1945End Year


Chemical research activites begin at X-10 plant, predecessor to Oak Ridge National LaboratoryDescription of Milestone

1943End Year


Waste operations begin at Hanford Site. Over the ensuing decades millions of gallons of high-level waste will be generated and stored pending future treatment and conditioning and burial grounds continue to dispose of solid radioactive waste.



Atomic Energy Commission established to administer nuclear energy programsDescription of Milestone

1975End Year


Waste management, including low-level waste disposal and storage of high-level waste, begins at Savannah River Site continuing to the present



The National Academy of Sciences recommends salt as a geologic disposal mediaDescription of Milestone

1956End Year


The National Academy of Sciences concludes radioactive waste could be safely disposed in a variety of geologic media within the USA



Idaho Chemical Processing Plant calcines high-level waste into a dry granular powder for interim storage



Cesium and strontium are separated from Hanford high-level waste and made into capsules for storage and reuse



The Atomic Energy Commission begins to classify and separately manage long-lived transuranic waste from low-level waste



The Atomic Energy Commission proposes salt deposits near Lyons, Kansas, for permanent disposal of radioactive waste. In just two years the project was abandoned due to technical and political issues.





Page 2 of 4


Congress enacts legislation requiring environmental impact analysis for all major federal actions, including waste management projects, under the National Environmental Policy Act. The Clean Air Act and the Occupational Safety and Health Act become the first of several environmental laws impacting waste operations



The Atomic Energy Commission chooses a site in southeast New Mexico near Carlsbad for exploratory repository work.



The Atomic Energy Commission is disbanded. In its place are created the U.S. Nuclear Regulatory Commission with regulatory jurisdiction over US commercial nuclear power and the Energy Research and Development Administration which manages the government's nuclear complex.



A presidential decision is made not to reprocess commercial spent nuclear fuel in favor of a once-through fuel cycle



The Resource Conservation and Recovery Act and Toxic Substances Control Act, two environmental statutes dealing with hazardous waste, become law, having significant impacts on radioactive waste management in the USA.



The U.S. Department of Energy, a cabinet level agency, is formed from the Energy Research and Development Administration.



Congress gives authority to the Department of Energy for stabilization and control of inactive uranium mill tailing sites under the Uranium Mill Tailing Radiation Control Act.



Congress authorizes the Waste Isolation Pilot Plant, near Carlsbad, New Mexico, to demonstrate the safe disposal of transuranic waste



Congress enacts the Low-level Radioactive Waste Policy Act to promote commercial low-level waste disposal compacts for regional disposal.



Final Environmental Impact Statement on Management of Commercially Generated Radioactive Waste is issued





Page 3 of 4


Congress gives the Department of Energy responsibility for demonstrating high-level waste solidifcation at West Valley, New York, a former commercial reprocessing plant, under the West Valley Demonstration Project Act.



Congress passes "superfund" legislation, the Comprehensive Environmental Response, Compensation, and Liability Act, aimed at cleanup of hazardous, toxics and radioactive waste sites. The legislation creates a trust fund to finance investigation and cleanup of abandoned and uncontrolled hazardous waste sites.



The Nuclear Waste Policy Act becomes law directing the Department of Energy to find and characterize a repository site for spent nuclear fuel and high-level waste



Full construction begins at the Waste Isolation Pilot Plant after completion of initial shafts and exploratory characterization.



Nine potential repository sites are selected in 6 states in various geological media for further consideration.



Congress directs the Department of Energy to investigate only the Yucca Mountain Site, Nevada, for a potential repository ending studies on the remaining 8 sites. Characterization studies begin.



Congress gives consent to 3 low-level waste compacts. Several other compacts are formed, but no new regional repositories have moved to construction, although several were proposed but political and technical issues were not overcome.



The Department of Energy creates the Environmental Restoration and Waste Management Program (later called Environmental Management) to focus agency efforts on cleanup of government legacy radioactive waste sites.



Congress enacts the Federal Facility Compliance Act, requiring the federal government agencies to submit plans for treatment of mixed hazardous and radioactive waste to state agencies and the Environmental Protection Agency.



Vitrification of high-level waste begins at Savannah River Site and West Valley Demonstration Project.





Page 4 of 4


The Department of Energy achieved its complex-wide waste reduction goal of reducing waste by 50% compared to its 1993 baseline between 1996 and 1998.



The Department of Energy releases its Final Waste Management Programmatic Environmental Impact Statement. Decisions resulting from this analysis covered high-level waste treatement, transuranic storage and disposal, low-level waste storage and disposal, and hazardous waste disposal.



The Department of Energy initiates a sealed radioactive source acceptance program.Description of Milestone

1997End Year


DOE releases its viability assessment for the Yucca Mountain site investigations.Description of Milestone

1998End Year


After completion of all regulatory and legal requirements, the Waste Isolation Pilot Plant geologic repository begins disposal of transuranic waste.



Construction begins on Advanced Mixed Waste Treatment Facility designed to repackage and treat legacy transuranic waste at the Idaho National Engineering and Environmental Laboratory



NEWMDB Glossary

This section contains a printout of the NEWMDB’s On Line Glossary at the time the Radioactive Waste Management Profiles #4 was prepared (October 2002). The printout represents the glossary used during the 1st data collection cycle for the NEWMDB (July 2001 to March 2002) and during the extension of the 1st data cycle (scheduled for July 2002 to January 2003). The current version of the glossary is available on line, via the following Internet page:


The following is a screen capture of the glossary’s disclaimer page:


NEWMDB Glossary

Administrator The top-level user for the NEWMDB; has full read and write access to the database, grants permission to Country Co-ordinators

authorization The granting by a regulatory body or other governmental body of written permission for an operator to perform specified activities (could include, for example, licensing, certification, registration).

clearance The removal of radioactive materials or radioactive objects within authorized practices from any further regulatory control by the regulatory body.

client See client-server

client-server computer terminology to identify various computers on a network, such as the Internet The computers of NEWMDB users are the clients and the NEWMDB database resides on a server.

closed See closure

closeout In the context of uranium mill tailing impoundments, closeout refers to the operational, regulatoryand administrative actions required to place an impoundment into long term conditions such that little or no future surveillance and maintenance are required. The same concept may also apply to mining debris piles, heap and in situ leaching piles and mines. see closure and decommissioning.

closure 1. administrative and technical actions directed at a repository at the end of its operating lifetime — e.g. covering of the disposed waste (for a near surface repository) or backfilling and/or sealing (for a geological repository and the passages leading to it) — and termination and completion of activities in any associated structures 2. The completion of all operations at some time after the emplacement of spent fuel or radioactive waste in a disposal facility. This includes the final engineering or other work required to bring the facility to a condition that will be safe in the long term. [Joint Convention definition - not recommended for IAEA publications] see closeout and decommissioning

conditioning operations that produce a waste package suitable for handling, transport, storage and/or disposal Conditioning may include the conversion of the waste to a solid waste form, placement of the waste in containers and, if necessary, providing an overpack. Note: the definition of conditioning is currently under review at the IAEA (as of Oct 2001) to remove an inherent ambiguity related to putting waste into containers. The placement of raw waste into a container to facilitate shipment to a processing facility should not be considered to be conditioning.

contaminated site a geographical area, with or without buildings or other structures, with radioactive contamination and with or without non-radioactive contamination Throughout the world there are sites contaminated with radioactivity due to past practices and some form of remediation or environmental remediation of these sites may be needed to ensure the protection of human health and the environment. However, there is no international consensus on the definition of a site, the definition of contaminated, or the extent of remediation or environmental remediation, if any, that is required ("how clean is clean?"). Note: contaminated sites are excluded from consideration in the NEWMDB until otherwise indicated - however, the waste generated from remediation activities and placed into waste management facilities at waste management sites is not excluded from consideration.

contamination the presence of radioactive substances in or on a material or in the human body or other place where they are undesirable or could be harmful

cookies information in small files that are saved on your computer’s hard disk

Page 1 of 9NEWMDB HELP

2002-10-11http://www-newmdb.iaea.org/showhelp.asp?Topic=8-1-1&Print=Yes

When connecting with some Internet sites, these sites may attempt to save cookies on your computer. Cookies can contain information about you (such as your name and address) and your preferences for interacting with the Internet site. For example, if you inquire about a hotel room at a Web site, the site might create a cookie that contains your preferences, such as non-smoking rooms only or it might only contain a record of the pages within the site you visited, to help the site customize the view for you the next time you visit. Only the information that you provide to the site or the choices that you make while visiting a site are saved in a cookie. For example, a site cannot determine personal information about you unless you choose to provide it. Allowing an Internet site to create a cookie does not give that or any other site access to the rest of your computer. In addition, only the site that created the cookie can read it. Internet browsers, such as Internet Explorer or Netscape Navigator, allow the creation of cookies. They also allow the user to control this activity by setting preferences (such as to issue a prompt before accepting a cookie). When using the NEWMDB, users should enable cookies (please refer to your Internet browser’s help for additional information).

Country Co-ordinator

a Member State’s single point-of-contact to interact with the NEWMDB Programme Officer; has read and write access for all data entered for his/her country, grants permission to Report Co-ordinators and Waste Experts

Country Waste Profile

all information entered by a Member State during NEWMDB data collection cycles (the combined information provided by Member States in the Framework Component and Waste Data Component)

customer anyone who accesses and/or makes use of WMDB or NEWMDB information

data collection cycle

time periods in which Member States are requested to submit information to the NEWMDB Submissions of information are managed by way of a liaison between the NEWMDB Programme Officer and Country Co-ordinators. Initially, it is expected that Member States will be asked to submit information to the NEWMDB every two years, beginning in 2001. As experience is gained, Member States may be asked to submit information annually. Each request for a submission is a data collection cycle, which will have a start and end date.

decommissioning 1. administrative and technical actions taken to allow the removal of some or all of the regulatory controls from a facility (except for a repository, which is closed (see closure) and not decommissioned, or uranium mill tailing impoundments, for which the term closeout is used). 2. all steps leading to the release of a nuclear facility, other than a disposal facility, from regulatory control. These steps include the processes of decontamination and dismantling. [Joint Convention definition - not recommended for IAEA publications] The use of the term decommissioning implies that no further use of the facility (or part thereof) for its existing purpose is foreseen. The actions will need to be such as to ensure the long term protection of the public and the environment, and typically include reducing the levels of residual radionuclides in the materials and the site of the facility so that the materials can be safely recycled, reused or disposed of as exempt waste or as radioactive waste, and the site can be released for unrestricted use or otherwise reused. Decommissioning typically includes dismantling the facility (or part thereof), but in the Agency’s usage this need not be the case. It could, for example, be decommissioned without dismantling and the existing structures subsequently put to another use (after decontamination).

decontamination the complete or partial removal of contamination by a deliberate physical, chemical or biological process. This definition is intended to include a wide range of processes, but to exclude the removal of radionuclides from within the human body, which is not considered to be decontamination.

dedicated used in the NEWMDB to indicate a facility for managing sealed radioactive sources (SRS) within the following scope: (1) encompasses all SRS, not just disused or spent SRS (2) the only wastes processed, stored or disposed by the facility are disused and/or spent SRS declared to be waste or the facility has a programme to track the location and characteristics of all SRS in the facility



The intent of the definition is to help ensure that Member States can report the inventory of SRS at waste management sites, which may be difficult or impossible to do for facilities at sites in which not all SRS are tracked individually.

defense (defence) see defense/military

defense/military defense/military, defense (defence), and military are terms used in the NEWMDB to describe radioactive wastes derived from non-civilian applications of radioactive materials

discharge 1. planned and controlled release of (usually gaseous or liquid) radioactive material to the environment. 2. a planned and controlled release into the environment, as a legitimate practice, within limits authorized by the regulatory body, of liquid or gaseous radioactive materials that originate from regulated nuclear facilities during NORMal operation. [Joint Convention definition - not recommended for IAEA publications]

disposal 1. emplacement of waste in an appropriate facility without the intention of retrieval. 2. the emplacement of spent fuel or radioactive waste in an appropriate facility without the intention of retrieval. [Joint Convention definition - not recommended for IAEA publications] Some countries use the term disposal to include discharges of effluents to the environment. In some States, the term disposal is used administratively in such a way as to include, for example, incineration of waste or the transfer of waste between operators. In Agency publications, disposal should only be used in accordance with the more restrictive definition given above.The term disposal implies that retrieval is not intended; it does not mean that retrieval is not possible.

disposal facility synonymous with repository

disposed see disposal

disposition used in the NEWMDB to indicate a waste management related destination for waste - for example, waste can be routed to a facility for processing, storage or disposal

disposition option

used in the NEWMDB to indicate option(s) for routing waste to a waste management facility, as follows: origin => destination(s) generator => processing, storage, disposal processing => storage, disposal storage => processing, disposal

disused used in the NEWMDB to indicate a sealed radioactive source (SRS) that is no longer in use or intended to be used

exempt waste applies to waste that is released from regulatory control in accordance with exemption principles

exemption the determination by a regulatory body that a source or practice need not be subject to some or all aspects of regulatory control on the basis that the exposure (including potential exposure) due to the source or practice is too small to warrant the application of those aspects

facility nuclear facilities, irradiation installations, uranium/thorium mining and milling, waste management facilities and any other place where radioactive materials are produced, processed, used, handled, stored or disposed of - or where radiation generators are installed - on such a scale that consideration of radiation protection and safety is required

Framework Component

the NEWMDB component that is used by Country Co-ordinators to customize how information about radioactive waste management programmes and inventories for their country will be reported to the NEWMDB

free release see clearance

fuel cycle see nuclear fuel cycle

fuel enrichment the physical process of increasing the concentration of the uranium-235 isotope relative to the predominant uranium-238 isotope in natural uranium



fuel fabrication the manufacture of fuel for nuclear reactors

High Level Waste

see waste classification

HLW see waste classification

host medium the geological formation in which a repository is located

in situ in its original place

Indicators of Sustainable Development

an element of “Agenda 21”, which was issued from the United Nations Conference on Environment and Development, held in Rio de Janeiro in June 1992. Chapter 40 of Agenda 21 calls for the development of indicators for sustainable development (ISD). In particular, it requests countries at the national level, and international government and non-governmental organizations at the international level, to develop the concept of ISD in order to identify such indicators. As a follow up, the IAEA was assigned the responsibility to develop ISD for radioactive waste management, in accordance with Chapter 22 of Agenda 21 and the UN-wide indicators development work programme. Development of ISD for radioactive waste was still on-going at the IAEA in 2001/2002.

interim storage see storage

Joint Convention The Joint Convention on the Safety of spent Fuel Management and on the Safety of Radioactive Waste Management

law a body of enacted or customary rules recognized by a community as binding

license 1. a legal document issued by the regulatory body granting authorization to perform specified activities related to a facility or activity. 2. any authorization, permission or certification granted by a regulatory body to carry out any activity related to management of spent fuel or of radioactive waste. [Joint Convention definition - not recommended for IAEA publications]

licensed see license

LILW see waste classification

LILW-LL see waste classification

LILW-SL see waste classification

LLW see waste classification

Long Lived see waste classification

Low and Intermediate Level Waste

see waste classification

LSA low specific activity waste LSA is not part of the IAEA’s proposed waste classification scheme; however it is used by some Member States to indicate radioactive waste with very low levels of radionuclides. Some Member States refer to this as very low level waste (VLLW), which is also not part of the IAEA’s proposed scheme.

milestone used in the NEWMDB to indicate significant or noteworthy developments, occurrences, or circumstances related to radioactive waste management

military see defense/military



NEWMDB Programme Officer

the IAEA’s single point-of-contact for the NEWMDB

NORM naturally occurring radioactive material - material containing no significant amounts of radionuclides other than naturally occurring radionuclides. The exact definition of ‘significant amounts’ would be a regulatory decision

notification e-mail

the principal e-mail addressed used by the NEWMDB Programme Officer to communicate with Country Co-ordinators

nuclear applications

civilian practices using radioactive materials excluding the nuclear fuel cycle and activities that generate NORM waste

nuclear facility a facility and its associated land, buildings and equipment in which radioactive materials are produced, processed, used, handled, stored or disposed of on such a scale that consideration of safety is required

nuclear fuel cycle operations associated with the production of nuclear energy, including: - mining and milling, processing and enrichment of uranium or thorium; - manufacture of nuclear fuel; - operation of nuclear reactors (including research reactors); - reprocessing of nuclear fuel; - any related research and development activities; and - all related waste management activities (including decommissioning)

password a secret, NEWMDB user-specified code that is required to login to the NEWMDB

permission 1. consent 2. in the context of the NEWMDB, the granting of full or partial access to NEWMDB information The NEWMDB design requires that registered users (Country Co-ordinators, Report Co-ordinators and Waste Experts) be granted permission to view or edit/modify all or part of the information entered into the database for a Member State. Administrator - full access to all NEWMDB information for all Countries - grants permission to Country Co-ordinators Country Co-ordinator - full access to all information entered for his/her Country - grants permissions to Report Co-ordinators and Waste Experts Report Co-ordinator - full access to information within his/her Reporting Group - can grant permission to Waste Experts Waste Expert - full or partial access to information within Reporting Group (limits can be set by the Country Co-ordinator or Report Co-ordinator)

policy a course or general plan of action (to be) adopted by a government, body or person

practice any human activity that introduces additional sources of radiation exposure or exposure pathways or extends exposure to additional people or modifies the network of exposure pathways from existing sources, so as to increase the exposure or the likelihood of exposure of people or the number of people exposed

pretreatment any or all of the operations prior to waste treatment, such as collection, segregation, chemical adjustment and decontamination

processed see processing

processing any operation that changes the characteristics of waste, including pretreatment, treatment and conditioning

profile see Country Waste Profile



public user any non-registered NEWMDB user (see registered user)

radio button a round button with associated text (a label), an icon, or an image that indicates a choice the user can make by selecting the button A computer application typically uses radio buttons in a group box to permit the user to choose from a set of related, but mutually exclusive options. For example, the application might present a group of radio buttons from which the user can select a format preference for text selected. The user could select a left-aligned, right-aligned, or centred format by selecting the corresponding radio button. Typically, the user can select only one option at a time from a set of radio buttons.

reactor operations

used in the NEWMDB to indicate waste arising from the operation and maintenance of nuclear reactors, both power and research reactors (includes waste from commissioning operations and generated from hot cell work with reactor components, excludes decommissioning waste)

registered user any of the following: Administrator, Country Co-ordinator, Report Co-ordinator, Waste Expert

regulation an all-encompassing public policy term that includes various political and economic issues and ideas; government regulations include two distinct categories -- economic regulations and social regulations. Economic regulations generally cover sectors of an economy such as energy, communications, transportation, and financial institutions. These regulations usually take the form of overt barriers to entry or exit, licensing and tarif laws, and price and wage controls. Social regulations include statues or rules that are intended to protect citizen or worker health and safety, accomplish environmental and other aesthetic goals, or promote civil rights objectives.

regulator see regulatory body

regulators see regulatory body

regulatory body 1. an authority or a system of authorities designated by the government of a State as having legal authority for conducting the regulatory process, including issuing authorizations, and thereby regulating nuclear, radiation, radioactive waste and transport safety. 2. any body or bodies given the legal authority by the Contracting Party to regulate any aspect of the safety of spent fuel or radioactive waste management including the granting of licences. [Joint Convention definition - not recommended for IAEA publications]

regulatory control

any form of control applied to facilities or activities by a regulatory body for reasons related to protection or safety

release 1. see discharge 2. removal from regulatory control

released see release

remediation measures carried out to reduce the radiation exposure from existing contamination through actions applied to the contamination itself (the source) or to the exposure pathways to humans

Report Co-ordinator

a person designated by a Country Co-ordinator to assist with reporting to the NEWMDB Country Co-ordinators define the number and structure of Reporting Groups for reporting to the NEWMDB. Each Reporting Group must be assigned a Report Co-ordinator, who has read and write access for all information for the Reporting Group. A Report Co-ordinator grants permissionto Waste Experts

repository a nuclear facility where waste is emplaced for disposal

reprocessing a process or operation to extract radioactive isotopes from nuclear fuel removed from a reactor following irradiation

role a default set of permissions that define a user's access to a database (both registered users and public users) There are two types of permissions: explicit and implicit. Explicit permissions are those



permissions that are granted directly to a user account; no other users are affected. Implicit permissions are those permissions that are granted to a group account. Adding a user to that group grants the group's permissions to that user; removing a user from the group takes away the group's permissions from that user.

script a set of computer commands that are performed upon user request or due to user interaction with a computer program For example, when information is entered into an electronic form on a computer, a script may be used to process the information, such as adding numbers or to check spelling. The user can either request this action or it can happen automatically (for example, as soon as a user tabs between data entry fields).

sealed radioactive source

radioactive material that is permanently sealed in a capsule or closely bonded and in a solid form

server see client-server

Short Lived see waste classification

special fissionable material

a term used in the Statute of the IAEA with essentially the following meaning, but explicitly excluding source material: Plutonium except that with isotopic concentration exceeding 80% in plutonium-238; uranium-233; uranium enriched in the isotope 235 or 233; uranium containing the mixture of isotopes as occurring in nature other than in the form of ore or ore-residue; any material containing one or more of the foregoing Source material is defined as uranium containing the mixture of isotopes occurring in nature; uranium depleted in the isotope 235; thorium; any of the foregoing in the form of metal, alloy, chemical compound, or concentrate; any other material containing one or more of the foregoing in such concentration as the Board of Governors shall from time to time determine; and such other material as the Board of Governors shall from time to time determine

spent a term typically used for radioactive materials in the following context: spent fuel: nuclear fuel removed from a reactor following irradiation, which is no longer usable in its present form because of depletion of fissile material, poison build-up or radiation damage. spent sealed radioactive source (SRS): an SRS that is no longer suitable for its intended purpose as a result of radioactive decay Note: in the initial data collection cycles, Member States are not being asked to report spent fuel inventories. However, if a Member State uses a waste class matrix to equate spent fuel with High Level Waste, it may report spent fuel as HLW

SRS see sealed radioactive source

storage the holding of spent fuel or radioactive waste in a facility that provides for its containment, with the intention of retrieval. Storage is by definition an interim measure, and the term interim storage would therefore be appropriate only to refer to short term temporary storage when contrasting this with the longer term fate of the waste. Storage as defined above should not be described as interim storage. In the NEWMDB, interim storage applies to waste that is being held for a short time while awaiting transfer to an available disposition option. For example, waste being stored in a processing facility awaiting transfer to an available storage or disposal facility would be considered to be in interim storage. If waste is being storage because there is no place to send it, for example, it is being stored because there is no processing or disposal alternative available, the waste would be considered to be in storage, not in interim storage. In general, the NEWMDB considers temporary to imply periods of less than one year.

storage facility a nuclear facility where waste is emplaced for storage

stored see storage

TE-NORM technologically enhanced naturally occurring radioactive material (the anthropogenic concentration of NORM above naturally occurring levels)



treatment operations intended to benefit safety and/or economy by changing the characteristics of waste. Three basic treatment objectives are: - volume reduction; - removal of radionuclides from the waste; and - change of composition.

UMMT uranium mine and mill tailings

upload the process of transferring files from a NEWMDB user’s computer (client) to the IAEA server where the NEWMDB database resides

uploaded the completion of an upload

user name a unique identifier that is assigned to a registered user

waste classification

a method used to group various types of radioactive waste according to their physical characteristics Historically, Member States have developed and used a variety of waste classification schemes for their radioactive waste. Commonly used waste classes include: Low Level Waste (LLW), Intermediate Level Waste (ILW), Medium-Level Waste (MLW), Low and Intermediate Level Waste (LILW), Heat Generating Waste, High Level Waste (HLW), Alpha Bearing Waste, Transuranic Waste (TRU), spent sealed radioactive sources (SRS) - can be a subset of disused sources, Spent Fuel (SF), decommissioning Waste (DW), and Uranium Mine and Mill Tailings (UMMT). Other classes that have been used include de minimis, Below regulatory Concern (BRC), and Very Low-Level Waste (VLLW), which have been used by various Member States to classify waste with the lowest levels of radioactivity. The above waste classification schemes are based on both qualitative and quantitative criteria in which wastes are grouped according to their origin, activity content, radiotoxicity and thermal power. It is understood that there is a substantial overlap between the foregoing waste classes. It should be noted that waste classification schemes have been developed for practices and usually do not address natural material e.g. NORM and TE-NORM. A waste classification scheme was proposed by the IAEA in Section 3 of Safety Guide 111-G-1.1, "Classification of Radioactive Waste". The proposed classification scheme is based on quantitative criteria in which wastes are grouped according to the safety aspects of their management, especially disposal options. Click Here to view the IAEA’s proposed scheme. Member States may report their radioactive waste inventories to the NEWMDB according to their own waste classification schemes. However, Member States MUST specify the relationship between their own scheme(s) and the IAEA’s proposed scheme using the NEWMDB’s waste class matrix feature.

Waste Data Component

the NEWMDB component that is used by Country Co-ordinators to report radioactive waste inventories, waste treatment methods, waste conditioning methods and disused/spent, sealed radioactive source (SRS) inventories at waste management sites in their countries to the NEWMDB

Waste Expert a person designated by a Country Co-ordinator or a Report Co-ordinator to assist with reporting to the NEWMDB A Country Co-ordinator defines the number and structure of Reporting Groups for reporting to the NEWMDB. A Waste Expert can be assigned to one or more Reporting Groups and have read and write access for only the Reporting Groups to which they are assigned. A Country Co-ordinator or a Report Co-ordinator can also limit the information that a Waste Expert can access within an individual Reporting Group. A Country Co-ordinator and/or a Report Co-ordinator grants permission to a Waste Expert.

waste management facility

1. a facility specifically designated to handle, treat, condition, store or dispose of radioactive waste. 2. any facility or installation the primary purpose of which is radioactive waste management,



including a nuclear facility in the process of being decommissioned only if it is designated by the Contracting Party as a radioactive waste management facility. [Joint Convention definition - not recommended for IAEA publications]

waste management site

For reporting to the NEWMDB, a Waste Management Site is (a) limited to sites licensed under nuclear or radioactive materials regulations of the Member State and (b) includes at least one waste management facility. With regards to licensing, the identified facilities could be covered under the license of another facility, such as a nuclear reactor.

