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(Workshop on Level 2 PSA and Severe Accident Management, March 2004 ) 1 International Workshop International Workshop On On Level 2 PSA and Severe Accident Management Level 2 PSA and Severe Accident Management Hosted by: Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbh, Hosted by: Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbh, Köln, Germany Köln, Germany 29th to the 31st of March 2004 29th to the 31st of March 2004 Barry Kaufer, Deputy Head, Regulation Nuclear Safety Division Le Seine St.-Germain 12, boulevard des Iles 92130 Issy-les-Moulineaux, France ([email protected])
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Page 1: (Workshop on Level 2 PSA and Severe Accident Management, March 2004 ) 1 International Workshop On Level 2 PSA and Severe Accident Management Hosted by:

(Workshop on Level 2 PSA and Severe Accident Management, March 2004 )

1

International WorkshopInternational WorkshopOnOn

Level 2 PSA and Severe Accident ManagementLevel 2 PSA and Severe Accident Management Hosted by: Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbh, Hosted by: Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbh, Köln, GermanyKöln, Germany

29th to the 31st of March 200429th to the 31st of March 2004

Barry Kaufer, Deputy Head, Regulation

Nuclear Safety Division

Le Seine St.-Germain

12, boulevard des Iles

92130 Issy-les-Moulineaux, France

([email protected])

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Table of contentsTable of contents

Safety and Regulation at OECD/NEA Committee on the Safety of Nuclear

Installations (CSNI) Working Group on Risk Assessment

(WGRisk) – Level 2 PSA– 1997 State-of-the-Art Report– 2004 Programme of Work

Summary

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COMMITTEE ON THE SAFETY OF NUCLEAR INSTALLATIONS (CSNI)CHAIRMAN: A. THADANI - SECRETARY: J. REIG

BUREAU: G. LOWENHIELM, L. HAHN, K. ABE, J.C. NIEL, K. VALTONEN

CSNI PROGRAMME REVIEW GROUP (PRG) CHAIRMAN: T. KING - SECRETARY: M. HREHOR

FUEL CYCLE SAFETY

(FCS)

CHAIR: J. M. LANORE

SECRETARY: B. KAUFER

JOINT CSNI/CNRATASK ON PLANT SAFETY

PERFORMANCE

INDICATORS

CO-ORDINATED

PROGRAMME SERENA

WORKING GROUPS

RISK

ASSESSMENT

(WGRISK)

SPECIAL EXPERT GROUPS

ANALYSIS AND

MANAGEMENT OF

ACCIDENTS

(GAMA)

INTEGRITY AND

AGEING OF

COMPONENTS AND

STRUCTURES

(IAGE)

OPERATING

EXPERIENCE

(WGOE)

SEISMIC BEHAVIOUR OF

STRUCTURES

CONCRETE STRUCTURES

AGEING

INTEGRITY OF METAL

COMPONENTS &

STRUCTURES

CHAIR: M. DURIN

SECRETARY: J. ROYEN

CHAIR: N. CHOKSHI

SECRETARY: E. MATHET

CHAIR: A. VANDEWALLE

SECRETARY: P. PYY

CHAIR: A. FRISCHKNECHT

SECRETARY: P. PYY

CHAIR: W. WIESENACK

SECRETARY: M. HREHOR

HUMAN &

ORGANISATIONAL

FACTORS

(SEGHOF)

FUEL SAFETY

MARGINS

(SEGFSM)

SESAR/SFEAR GROUP

SECRETARY: C. VITANZA

SAFETY MARGINS ACTION PLAN

CHAIR: O. SANDVERAG

SECRETARY: J. ROYEN

January 2004

HALDENCABRI WATER

LOOP

MASCA II

SETH

MCCI ICDE

OECD-FIRE

PSB-VVER

OPDEOECD PROJECTS

SECRETARIES: C. VITANZA

E.MATHET, P. PYY

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COMMITTEE ON NUCLEAR REGULATORY ACTIVITIES (CNRA)CHAIRMAN: J. LAAKSONEN - SECRETARY: J. REIG

CNRA BUREAU: S. COLLINS, C. VIKTORSSON, J. FURNESS/M. WEIGHTMAN, A. SCHMITT, K. ABE, J.J. VAN BINNEBEEK

JOINT CSNI/CNRATASK ON PLANT SAFETY

PERFORMANCE INDICATORS

SECRETARY: P. PYY

REGULATORY EFFECTIVENESS

INDICATOR INFORMATION EXCHANGE

(PILOT CONTINUATION)

SECRETARY: B. KAUFER

WORKING GROUP ON

INSPECTION PRACTICES

(WGIP)

CHAIRMAN: H. KLONK

SECRETARY: B. KAUFER

WORKING GROUP ON PUBLIC

COMMUNICATION (WGPC)

CHAIRMAN: A JÖRLE

SECRETARY: J. ROYEN

NEA/WANO/IAEANUCLEAR EVENTS BASED WEB

SYSTEM (NEWS)

SECRETARY: B. KAUFER

TASK GROUP ON

REGULATORY DECISION

MAKING

CHAIRMAN: U. SCHMOCKER

SECRETARY: B. KAUFER

WORKING GROUPS TASK GROUPS JOINT ACTIVITIES

NEA REGULATOR/INDUSTRY FORUM (RIF2004)

SECRETARY: B. KAUFER

January 2004

RADIOACTIVE WASTE MANAGEMENT COMMITTEE

REGULATORS’ FORUM (RWMC-RF)

ANNUAL REPORT ON REGULATORY RELATED

ISSUES

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WGRiskWGRisk Over the past 24 years, PWG5 and now WGRisk have looked at the

technology and methods used for identifying contributors to risk and assessing their importance. Work during the early part of this period was concentrated on Level 1 PSA methodology, but in recent years, the focus has shifted into specific PSA methodologies modelling issues and risk informed applications. During this long period WGRisk has produced over 40 technical reports, held over 25 international workshops and has issued several important consensus statements and opinion papers on specific aspects of PSA.

The main mission of the Working Group on Risk Assessment (WGRisk) is to advance the understanding and utilisation of Probabilistic Safety Assessment (PSA) in ensuring continued safety of nuclear installations and in improving the effectiveness of regulatory practices in Member countries. In pursuing this goal, the Working Group shall recognise the different methodologies for identifying contributors to risk and assessing their importance. While the Working Group shall continue to focus on the more mature PSA methodologies for Level 1, Level 2, internal, external, shutdown, etc. It shall also consider the applicability and maturity of PSA methods for considering evolving issues such as human reliability, software reliability, ageing issues, etc., as appropriate.

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WGRisk Classification of Probabilistic Safety Assessment Topics

Risk Informed Regulation and Safety Management

Level 1 PSA Level 2 PSA and Severe Accident Management

Level 3 PSA Living PSA

Integrated Methods for PSA Methodologies

Non-reactor nuclear facilities Exchange of Information PSA Standards

Human Reliability Seismic Risk Fire Assessment Other External

Events Low Power &

Shutdown Events PSA Topic Specific Methods Development

Modelling Ageing Issues in PSA

Software Reliability Reliability of Passive

Systems Uncertainty Analysis

PSA Applications Risk Monitors Event Analysis

(PSAEA) Plant Modifications

PSA for Operation (Tech. Specs., ISI,

IST, etc.)

PSA for Power Upgrades, Life Extensions, etc.

PSA Related Information Collection

Common Cause Failures (ICDE)

Software (COMPSIS) Piping (OPDE) Fire (OECD-FIRE) Human Reliability

Other PSA Issues Alternative approaches

Dynamic PSA PSA Comparison PSA for Advanced

Reactors Public Perception of

Risks

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Pri

orit

y

Importance

Hig

h

HighLow

Med

ium

Low

Medium

Level 1 PSA

Exchange of InformationHuman Reliability

Fire AssessmentLevel 2 PSA

Low Power/ShutdownEvent Analysis

ICDEOECD-FIRE

HRAD

Level 3 PSANon-reactor Nuclear

FacilitiesPSA Comparison

Advanced Reactors

Living PSASeismic Risk

PSA for OperationOPDE

PSA Standards

Other External EventsAgeing Issues

Software ReliabilityCOMPSIS

PSA for Power Upgrades,Life Extension, etc.

Passive SystemsPublic Perception

Uncertainty Analysis,Plant Modifications

Risk Monitors

AlternativeApproaches

Dynamic PSA

Figure 1 Prioritisation of PSA Topics

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WGRisk – Level 2 PSA Discussion OutcomesWGRisk – Level 2 PSA Discussion Outcomes

[1996]– In the early 1990’s, with the advent of increasing use of PSAs, a proposal was made

at the 1993 PWG5 Annual meeting for future work in the area of Level 2 PSA. The main objective of the proposed task was to perform a state-of-the-art review of the methods available for performing level 2 PSAs and severe accident/source term uncertainty analyses for use in the regulatory process and the evaluation/implementation of severe accident management strategies.

[2002]– The reports from the experts and discussions within WGRisk show it is clear that if

one were to use NUREG 1150 as a basis, experimental evidence over the past 10 years or more indicates that the perceptions of risk in Level 2 PSA has changed what may be considered significant. While it is not clear how the results would specifically change, the body of information that has been compiled would change the distributions that were used in NUREG 1150. Additionally, based on the national reports presented at WGRisk meetings many countries (Germany, Korea, Finland, France, Hungary, Czech Republic, Switzerland and Japan) are actively working on Level 2 PSA. Therefore the proposed workshop is considered is seen as beneficial to getting a better understanding of the current state-of-the-art.

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WGRisk WGRisk State-of-the-Art Report, 1997State-of-the-Art Report, 1997

The report (Level 2 PSA Methodology and Severe Accident Management NEA/CSNI/R(1997)11) reviews and evaluates Level 2 PSA results and methodologies with respect to plant type specific and general insights

The report also looks at approaches and practices for using PSA results in the regulatory context and for supporting severe accident management programmes by input from Level 2 PSAs are examined.

– The report is based on information contained in: PSA procedure guides, PSA review guides and regulatory guides for the use of PSA

results in risk-informed decision making, and

Plant specific PSAs and PSA related literature exemplifying specific procedures, methods analytical models, relevant input data and important results, use of computer codes and results of code calculations. The PSAs are evaluated with respect to results and insights.

Review of Report was performed in 2002 (next presentation)

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Chapter 1Chapter 11. TASK DESCRIPTION AND WORKING

METHODOLOGY– 1.1 Background

– 1.2 Objective and Scope

– 1.3 Level 2 PSA methodologies

– 1.4 Accident management

– 1.5 OECD/NEA activities on accident management

– 1.6 OECD/NEA activities on severe accident phenomena

– 1.7 Structure of the report.

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Chapter 2Chapter 2

2 RESULTS AND INSIGHTS FROM RECENT LEVEL 2 PSA– 2.1 Examined PSAs and considered aspects

– 2.2 Objectives and scope of recent level-2 PSAs.

– 2.3 Plant characteristics influencing severe accident progression

– 2.4 Level 2 methodology and codes

– 2.5 Principal results, insights on containment failure modes and releases.

– 2.6 References

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Chapter 3Chapter 3

3 KEY SEVERE ACCIDENT ISSUES

– 3.1 Key Severe Accident Phenomena.

– 3.2 Review of severe accident computer codes

– 3.3 Documentation of the Use of Severe Accident Computer Codes in Selected Level 2 PSAs for Nuclear

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Chapter 4Chapter 4

4 SEVERE ACCIDENT MANAGEMENT– 4.1 Background and Objectives

– 4.2 Evolution of an accident from the operators perspective

– 4.3 Safety objectives for the development of SAM Guidance

– 4.4 Examples of implemented provisions for mitigative SAM (level 2) and of their effectiveness

– 4.5 Identification of Recovery and SAM Actions in the Level 1 Domain that can influence SAM in the Level 2 Domain. Some Examples

– 4.6 References

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Chapters 5 and 6Chapters 5 and 6

5 AVAILABLE METHODOLOGY FOR QUALITATIVE LEVEL 2 ANALYSIS– 5.1 Level 1/2 Interface

– 5.2 Accident progression Event Trees

– 5.3 Modelling of human intervention

6 EVALUATION OF LEVEL 2 PSA MODELS AND QUANTIFICATION– 6.1 Brief description of Methods

– 6.2 Use of Expert Judgement

– 6.3 Uncertainty Issue Quantification Technique

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Chapter 7Chapter 7 7 INTEGRATED AND PSA INFORMED APPROACH

TO DECISION MAKING– 7.1 Introduction

– 7.2 Recent activities and publications related to risk informed decision making

– 7.3 Quality requirements for PSAs

– 7.4 National Positions on risk informed decision making.

– 7.5 Treatment of Uncertainties

– 7.6 Examples of risk informed decisions in the level 2 domain

– 7.7 Conclusions

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AppendicesAppendicesAPPENDIX A: SEVERE ACCIDENT COMPUTER

CODES– A.1 Fully Integrated Plant Simulation Codes– A.2 Separate Phenomena Codes– A.3 Parametric Codes

APPENDIX B:– B.1 EVNTRE– B.2 SOLOMON– B.3 RISKMAN– B.4 SPSA

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2004 WGRisk Programme of Work (1)2004 WGRisk Programme of Work (1)

International Workshop on Level 2 PSA and Severe Accident Management.– The main objectives are:

To provide a forum to discuss recent developments in the state-of-the-art of Level 2 PSA and Severe Accident Management.

The information gathered will be used to produce an addendum to the 1997 WGRisk report,

Will provide input into the joint workshop planned by WGAMA, IAGE and WGRisk on Evaluation of Uncertainties in relation to Severe Accident and Level 2 Probabilistic Safety Analysis (to be held in the Fall of 2004), and

Will be used to develop future tasks by WGRisk.

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2004 WGRisk Programme of Work (2)2004 WGRisk Programme of Work (2)

The Use and Development of PSA in NEA Member Countries [NEA/CSNI/R(2002)18]– This report provides descriptions of the current status of PSA

programmes in 17 Member countries including basic background information, guidelines, various PSA applications, major results in recent studies, PSA based plant modifications and research and development topics. While the compilation is a not complete compilation it provides a “snapshot” of the current situation in the Member countries and hence it provides reference information and various insights to both the PSA practicien and others involved in the nuclear industry.

– The report forms the basis for a yearly round table discussion at WGRisk meetings and will be updated every 3 to 4 years.

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2004 WGRisk Programme of Work (3)2004 WGRisk Programme of Work (3)

Use of PSA in Emergency Planning [Task 2004-3]– The aim is to identify the approaches being used in the

member countries to define the emergency planning zones round nuclear facilities and how this relates to the information provided by the Level 2 PSA. The various approaches would be compared to identify similarities and differences. Consideration would also be given on whether it would be possible to define a common approach to using the Level 2 PSA information for this purpose.

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2004 WGRisk Programme of Work (4)2004 WGRisk Programme of Work (4)

GAMA/WGRISK/IAGE Workshop on Evaluation of Uncertainties in Relation to Severe Accidents and Level 2 PSA– The objectives are:

To transfer information among Working Groups on an important cross-cutting issue.

To develop a coherent approach/understanding regarding uncertainties. The product will be proceedings, and conclusions/recommendations

addressed to CSNI and the Working Groups.

– Tentative Date: Spring 2005

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SummarySummary

WGRisk State-of-the-Art report provided first in-depth look at Level 2 PSA Methodology in the Member Countries

WGRisk has an active programme in the area of Level 2 PSA and Severe Accident Management

WGRisk works (and will continue to work) with other working groups (e.g., GAMA) and other organisations (e.g., IAEA) to co-ordinate it work on this issue.


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