IAEA International Atomic Energy Agency

Technical Meeting

Practical Application of

Safety Assessment

Methodologies

(CRAFT Project)

IAEA Headquarters, 11-15 June 2012 Monika Kinker

Radioactive Waste and Spent Fuel Management Unit

Division of Radiation, Transport and Waste Safety - NSRW

Status of the IAEA safety standards and

Relation to the CRAFT project

IAEA 2

• Support to Member States in establishing proper safety framework for management of radioactive waste and spent fuel:

Development of Safety Standards

Provisions for use and application of Safety Standards

Joint Convention on the Safety of Spent Fuel and Radioactive Waste Management

Radioactive Waste and Spent Fuel

Management Unit

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http://www-ns.iaea.org/standards/default.asp

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Status of Safety Standards

• IAEA Safety standards are

• Binding for IAEA’s own activities

• Not binding on the Member States (but may be

adopted by them) EXCEPT in relation to

operations assisted by the IAEA:

• Integrated Regulatory Review Service

• Technical Cooperation Fund work

• States wishing to enter into project

agreements with the IAEA

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Development of Safety Standards

Outline and work plan Prepared by the Secretariat

Review by the Safety Standards Committees and the Commission on Safety Standards

Drafting or revising of safety standard

by the Secretariat and Consultants

Review by the Safety

Standards Committee(s)

Endorsement by Commission on Safety Standards

Member States

Approval by the IAEA’s Director General or BoG *

* Safety Requirements approved by BoG

* Safety Guides approved by DG

Member States = YOU !

Commission

on Safety Standards

(CSS)

Nuclear

Safety

Standards

Committee

(NUSSC)

Radiation

Safety

Standards

Committee

(RASSC)

Waste Safety

Standards

Committee

(WASSC)

Transport

Safety

Standards

Committee

(TRANSSC)

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New Structure of the Safety Standards

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Safety Standard Categories

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Safety Case &

Assessment

Predisposal

DS 284

Small

Generators RW

Storage

Classification

2010

2009

2006

2008

Management

Systems

L/ILW Reactors

DS 448

HLW FCFs

DS 447

RW in the Safety Standards

Spent Fuel

Storage

2012

Fundamental

Safety Principles

DS 454

2011

(2012?)

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Safety Standards: Predisposal RWM

Safety Case, Safety Assessment

Safety Case, Assessment Predisposal

DS 284

2009 2009

(2012?)

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1. Government responsibilities 2. National Policy & Strategy

3. Regulatory Responsibilities

4. Operator Responsibilities

5. Safety/Security

6. Interdependences

7. Management systems

8. Waste minimization

9. Characterization and classification

10. Waste treatment

11. Waste storage

12. Waste acceptance for processing, storage and/or disposal

13. Prepare safety case and supporting safety assessment

14. Safety case scope and regulatory compliance

15. Safety case documentation

16. Periodic safety review

17. Facilities location and design

18. Facility construction and commissioning

19. Facilities operation, maintenance, emergency preparedness

20. Decommissioning

21. Nuclear safeguards

22. Existing facilities

GSR Part 5, Safety Requirements for

Predisposal Management of RW

1. Introduction

2. Protection of

Human Health &

Environment

3. Responsibilities

4. Steps in the

Predisposal

Management of

RW

5. Development and

Operation of RWM

Facilities &

Activities

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DS 284: Safety Guide for SC and SA

1. Introduction

2. Demonstrating the Safety of Predisposal Management of Radioactive Waste

3. Objectives and Development of the Safety Case for Predisposal

4. Safety Assessment

5. Specific Issues

6. Documenting and Using the Safety Case

7. Regulatory Review Process

Annex A EXAMPLES OF HAZARDS AND INITIATING EVENTS

Annex B TOPICAL ISSUES FOR THE SAFETY ASSESSMENT REVIEW FOR RADIOACTIVE WASTE PREDISPOSAL FACILITIES AND ACTIVITIES

Annex C TEMPLATE OF REGULATORY REVIEW REPORT

Annex D SADRWMS

Safety Case &

Assessment

Predisposal

DS 284

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IAEA Requirements for

Safety Case, Safety Assessment …

• GSR Part 5, DS284: Safety Case • A collection of arguments and evidence in support of the safety of a

facility or activity. This will normally include the findings of a safety assessment and a statement of confidence in these findings.

• GSR Part 4 , DS284: Safety Assessment 1. Assessment of all aspects of a practice that are relevant to

protection and safety; includes siting, design & operation of the facility. This normally includes risk assessment and probabilistic SA.

2. Analysis to predict the performance of an overall system and its impact, where the performance measure is the radiological impact or some other global measure of the impact on safety.

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Safety Assessment

Ma

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Non

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Radiological

Impact

Scenarios

Models

Calculations

Safety Assessment: GSR Part 4, DS284

DS284

GSR Part 4

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The safety case for a predisposal radioactive waste management

facility shall include a description of how all the safety aspects of the

site, the design, operation, shutdown and decommissioning of the

facility, and the managerial controls satisfy the regulatory

requirements. The safety case and its supporting safety assessment

shall demonstrate the level of protection provided and shall provide

assurance to the regulatory body that safety requirements will be met.

• Design and operation considered and justified in the safety case

• Primary aim to ensure safety objectives and criteria set by regulatory body are met

• The safety case addresses operational safety and all safety aspects of the facility and activities

• Considerations for reducing hazards to workers, public and environment - normal operation and accident conditions

• Commensurate with the complexity of the operations and the magnitude of the hazards

GSR Part 5, Requirement 14:

Scope of the Safety Case and Regulatory Compliance

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DS284: Components of the

Safety Case and Safety Assessment

Safety Assessment

Ma

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En

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Non

ra

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nviro

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enta

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imp

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Op

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Radiological Impact

Scenarios

Models

Calculations

Safety Case

Safety Assessment

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• In order to provide additional guidance on

the level of depth and detail warranted for

safety cases, it was proposed that the IAEA

would develop illustrative safety reports

with example safety cases

-> CRAFT PROJECT

DS284:

Proposal to June 2010 WASSC for Approval

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International Intercomparison and

Harmonization Projects

• CRAFT (successor to SADRWMS) • SADRWMS Methodology and SAFRAN Tool

• Illustrative examples to complement SG (DS284)

• PRISM • Safety case

• Barrier performance

• WAC

• Uncertainty

• GEOSAF • Regulatory expectations throughout development and operation

• Review process

• Assessment – engineering, site, radiological impact, integration

• Working Group for the Dual Use Cask for Spent Nuclear Fuel • Safety case

• extended periods of storage and meeting transport requirements

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Long-term Project • 1st Plenary Meeting in 2003

• Final Plenary in 2011,

numerous consultancies,

workshops

Objectives: 1. EXAMINE the application of

safety assessment

methodology (ISAM, ASAM)

2. DEVELOP, document • Safety Assessment

Methodology

• Regulatory Review

• ---> DS284…

3. INTEGRATE methodology

into software tool (SAFRAN)

SADRWMS Project Safety Assessment Driving Radioactive Waste Management Solutions

Safety Case &

Assessment

Predisposal

DS 284

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http://www-ns.iaea.org/tech-areas/waste-safety/sadrwms/default.asp?s=8&l=69

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SADRWMS Project Results

20

SAFRAN Tool

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CRAFT (Complimentary Safety Reports, Development and

Application to Waste Management Facilities)

3 Year Project • 1st Plenary Meeting May 2011

• Regional Meetings in • Stockholm Oct 2011

• Vietnam May 2012

Objectives: 1. APPLY DS284, SADRWMS

methodology & SAFRAN Tool

2. PROVIDE a forum for application

of the methodology and SAFRAN tool

3. DEVELOP, document Safety Reports illustrating

application of DS284 • Facility/process specific

• Safety Case Process/Regulatory Review

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Fukushima Accident: WASSC

Discussions on Lessons Learnt

GSR Part 5 • Requirement 12 (WAC)

• No change required

• Application implies consideration of other

parameters when developing the SC for wastes

arising from an accident or remediation activities

• Could imply re-examination of safety cases for

existing facilities to accept wastes arising from

accidents or need of new facilities

• Examples of its application to be included in

lower tier documents

IAEA 23 Thank you!