IAEAInternational Atomic Energy Agency

International Standards for NPP I&C

Presented toTWG-NPPIC

2009 May 21Vienna, Ausria

Gary Johnsong.johnson@iaea.org+43 (1) 2600-22671

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Three organizations develop I&C standards that are used world-wide

• IAEA

• International Electrotechnical Commission

• IEEE

• I’ll speak about the first two

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The IAEA statue establishes the agencies standards development function

• One function of the IAEA is “to establish or adopt standards of safety … and to provide for the application of these standards, … at the request of a State, to any of that State's activities in the field of atomic energy”• These standards are to be established in consultation and, where

appropriate, in collaboration with the competent organs of the United Nations and with the specialized agencies concerned

• IAEA statute > http://www.iaea.org/About/statute_text.html

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The purpose of IAEA Safety Guides

• Provide guidance on how to comply with the safety requirements (In our case NS-R-1)

• Indicate international consensus that it is necessary to take the measures recommended (or equivalent alternatives)

• Reflect best practices.

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Use of IAEA Safety Guides

• Used as the basis for IAEA design reviews, regardless of the national regulations

• Some member states incorporate IAEA requirements (NS-R-1) and safety guides into their regulations

• Some member states incorporate IAEA requirements into their regulations but treat safety guides as recommendations

• Some member states use IAEA requirements and safety guides as references in development of regulations or national standards. (this is the most common)

• Some member states do not use IAEA safety guides at all• IEC uses NS-G-1.3 as the source of elementary guidelines for I&C

systems important to safety. • IEC standards provide further guidance on implementing these principles. • NS-G-1.3 is unique in this regard

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IAEA Guidance Overview

Safety of nuclear facilities

Radiation protection and safety of radiation sources

Safe management of radioactive waste

Safe transport of radioactive material

General safety (cross-cutting themes)

Legal and governmental infrastructure

Emergency preparedness and response

Management systems

Assessment and verification

Site evaluation

Radiation protection

Radioactive waste management

Decommissioning

Remediation of contaminated areas

Thematic standards

Nuclear power plants: design

Radiation related facilities and activities

Research reactors

Fuel cycle facilities

Waste treatment and disposal facilities

Transport of radioactive material

Facilities specific standards

Nuclear power plants: operation

Safety Fundamentals

All IAEA safety standards are available at:

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

All free!

All IAEA safety standards are available at:

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

All free!

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NS-R-1: “Safety of NPPs – Design” is the top IAEA design requirements document

• Not legally binding• Adopted as regulation in some states• Influenced regulations in other states

• Not intentionally LWR specific• Responds to safety fundamentals• Prepared by engineers - little lawyer input• Outside standards are not incorporated• No public comment process• Represent a broad consensus

• All member states have the opportunity to comment• Endorsed by the Commission for Safety Standards• Approved by the IAEA Board of Governors

• Other safety standards also relevant at a second order• For example, GS-R-3 on management systems (including quality)

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Current safety guidance for design

• Safety of Nuclear Power Plants: Design Safety Requirements NS-R-1• Software for Computer Based Systems Important to Safety NS-G-1.1• Safety Assessment and Verification NS-G-1.2• Instrumentation and Control Systems Important to Safety NS-G-1.3• Design of Fuel Handling and Storage NS-G-1.4• External Events Excluding Earthquakes NS-G-1.5• Seismic Design and Qualification NS-G-1.6• Protection Against Internal Fires and Explosions NS-G-1.7• Design of Emergency Power Systems NS-G-1.8• Design of the Reactor Coolant System and Associated Systems NS-G-1.9• Design of Reactor Containment Systems NS-G-1.10• Protection against Internal Hazards other than Fires and NS-G-1.11• Design of the Reactor Core NS-G-1.12

• Radiation Protection Aspects of Design NS-G-1.13

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There is plan to restructure IAEA safety guidesThis plan affects the design safety guides

Safety Classification

Deterministic Safety Analyses

PSA for Design & Operations

Design of I&C Systems

NS-G-1.2 Safety Assessment &Verification

Radiation Protection & Radioactive Waste Management

NS-G-1.4Fuel handling & storage systems

Reactor Containment Systems & Other Buildings

NS-G-1.8Reactor Coolant & Associated Systems

NS-G-1.12Reactor Core

Protection against Internal & External Hazards

NS-G-1.6Seismic Design & Qualification

NS-G-1.3I&C Systems Important to Safety

NS-G-1.1 Software for Computer Based Systems Important to Safety

NS-G-1.5External Events Excluding Earthquakes

NS-G-1.7 Protection Against Internal Fires & Explosions

NS-G-1.8Design of Emergency Power Systems

NS-G-1.10 Design of Reactor Containment Systems

NS-G-1.9Design of the RCS & Associated Systems

NS-G-1.11 Protection against Internal Hazards except Fires & Explosions

NS-G-1.12 Design of the Reactor Core

NS-G-1.13Radiation Protection Aspects of Design

NS-G-1.4Fuel Handling & Storage

+

+

Auxiliary Systems

Electric Power Systems

Completion scheduled for 2015+- material from additional documents to be included

Existing Structure New Structure

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Update of the I&C and electrical guides has started

• I&C Guide• Incorporate and replace the

software guide • Much less detail on software

• Leave details to standards

• Update to address new topics and new consensus, e.g.,

• Communications independence

• Soft control

• Cyber security

• Complex electronics

• Design for aging management

• Electrical Guide• Expand scope from emergency

power systems to all electrical systems

• To some extent this is a restructuring

• Offsite power now in an annex

• Much of the emergency power guidance is applicable to all systems

• Check guidance for completeness and tie to NS-R-1

• E.g., note the role of breaker coordination in limiting the effects of internal events, such as fire

• Integrate into new structure of safety guides• May involve broadening scope from NPP to Nuclear Installations

• Identify and eliminate unnecessary conflicts with national approaches

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Work plan

• Solicit input• Meetings to develop outline

• About 5 experts• About August

• Develop draft (homework)• Post draft for review• Meeting to discuss draft

• About November

• Revise draft (homework)• Post again for review• Meeting to review draft

• Different or larger group• About January 2010

• Finalize draft (homework)• Possibility of extra meetings if

needed

• Solicit input• Meetings to develop outline

• About 5 experts• About August

• Develop draft (homework)• Post draft for review• Meeting to discuss draft

• About November

• Revise draft (homework)• Post again for review• Meeting to review draft

• Different or larger group• About January 2010

• Finalize draft (homework)• Possibility of extra meetings if

needed

• Draft outline and current document is available on-line

• The website allows you to:• Initiate or participate in threaded

discussions• Post comments • Post markups

• If you post a mark-up please also post comments explaining the markup

• This is the first time I’ve tried a web-based process, so• Advise me on how to improve the

site.• Be patient

• You need an account to access

IAEAInternational Atomic Energy Agency

If you wish to participate

Contact me at

g.johnson@iaea.org

Or

Give me a business card

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IEC SC45A prepares standards applicable to electronic and electrical functions for I&C of nuclear facilities

• By agreement between IEC and IAEA SC45A standards provide detailed implementation guidance for IAEA safety standards.

• Thirty-one nations are members of SC45A• Twenty-two are voting members

• About half are regular, active participants

• Currently there are 7 working groups• Sensors & Measurements

• Digital Systems

• Special Process Measurements and Rad Monitoring

• Reliability

• I&C systems

• Modernization & Ageing Management

• Sixty-six standards issued to date

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Work in progress - I&C principles

• IEC 61513 Ed. 2.0 Nuclear power plants - Instrumentation and control important to safety - General requirement for systems

• IEC 61226 Ed. 3.0 Nuclear power plants - Instrumentation and control important to safety - Classification of instrumentation and control functions

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Work in progress - Sensors & Measurements

• IEC 60737 Ed. 2.0 Nuclear Power Plants - Instrumentation important to safety - Temperature sensors (In-core and primary coolant circuit) : Characteristics and test methods

• IEC 62584 Ed. 1.0 Nuclear Power Plants - Instrumentation important to safety - Application of Gamma Thermometers (GT) for Local Power Range Monitor (LPRM) calibration

• PNW 45A-750 Ed. 1.0 Nuclear Power Plants - Instrumentation important to safety - Thermocouples : Characteristics and test methods

• IEC 60988 Ed. 2.0 Nuclear power plants - Instrumentation important to safety - Acoustic monitoring systems for detection of loose parts: Characteristics, design criteria and operational procedures

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Work in progress - Radiation Monitoring

• IEC 60951-1 Ed. 2.0 Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Part 1: General requirements

• IEC 60951-2 Ed. 2.0 Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Part 2: Equipment for continuous off-line monitoring of radioactivity in gaseous effluents and ventilation air

• IEC 60951-3 Ed. 2.0 Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Part 3 : Equipment for continuous high range area gamma monitoring

• IEC 60951-4 Ed. 2.0 Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Part 4: Equipment for continuous in-line or on-line monitoring of radioactivity in process streams

These are actually in publication

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Work in progress - Control Rooms & Human Factors

• IEC 60965 Ed. 2.0 Nuclear power plants - Control rooms - Supplementary control points for reactor shutdown without access to the main control room

• PNW 45A-748 Ed. 1.0 Nuclear Power Plants - Control rooms - Computer based procedures

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Work in progress - Digital Systems

• IEC 61500 Ed. 2.0 Nuclear Power Plants - Instrumentation and control important to safety - Data communication

• IEC 62566 Ed. 1.0 Nuclear Power Plants- Instrumentation and control important to safety- Selection and use of complex electronic components for systems performing category A functions

• IPNW 45A-742 Ed. 1.0 Nuclear Power Plants - Instrumentation and control systems important to safety - Requirements for Computer Security Programmes

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Work in progress - Ageing

• IEC 62465 Ed. 1.0 Nuclear Power Plants - Instrumentation and control important to safety - Management of aging of electrical cabling systems

• IEC 62582-1 Ed. 1.0 Nuclear Power Plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 1: General

• IEC 62582-2 Ed. 1.0 Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 2: Method descriptions - Indenter modulus

• IEC 62582-3 Ed. 1.0 Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 3: Method descriptions - Elongation at break

• IEC 62582-4 Ed. 1.0 Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 4: Method descriptions - Oxidation induction temperature

• IEC 62582-5 Ed. 1.0 Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 5: Method descriptions - Optical cables

• PWI 45A-1 Ed. 1.0 Management of ageing of nuclear power plant sensors

• PWI 45a-3 Ed. 1.0 Management of aging of nuclear power plant connectors

• PWI 45a-4 Ed. 1.0 Management of aging of nuclear power plant relays

• PWI 45a-5 Ed. 1.0 Management of aging of nuclear power plant electronics

• PWI 45A-6 Ed. 1.0 Obsolescence management for digital and programmable I&C in nuclear power plant

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How to participates

• Participants must are representatives of their nation• You must be nominated by your national committee of the IEC

• Formal correspondence goes through the national committee

• Each country has a chief delegate for SC45A

• Next meeting Yokohama, Japan• 2009 September 10 to 18

• Much information is available at • www.iec.ch