CSNI/WGRISK Workshop

International Workshop on Level 2 PSA and Severe Accident Management

Cologne, Germany

29-31 March 2004

OPENING SESSION

Barry KAUFER, OECD Nuclear Energy Agency

Opening Remarks - Lothar HAHN, Technical-Scientific Director,

Gesellschaft für Anlagen- und Reaktorsicherheit mbH

INTRODUCTORY SESSION

• Outline of the work performed by WGRisk and summary the 1997 report on Level 2 PSA and Severe Accident Management., Barry Kaufer (PowerPoint file), OECD Nuclear Energy Agency / Ming Leang Ang, National Nuclear Corporation Ltd, United Kingdom (PowerPoint file)

SESSION 1: PSA LEVEL 2 APPLICATION

Level 2 PSA applications, such as the use of Level 2 PSA for emergency planning, plant specific severe accident management development and risk-informed regulation, etc.

• ·Experience Gained from the Mexican Nuclear Regulatory Authority in the Probabilistic Safety Assessment Level 2 Development for Laguna Verde Nuclear Power Plant, Verónica Godínez S. and Ramón López M., Comisión Nacional de Seguridad Nuclear y Salvaguardias, Mexico (Paper, Word file) (Presentation, PowerPoint file)
• An Integrated Approach to Living Level 2 PSA, Risto Himanen and Heikki Sjövall, Teollisuuden Voima Oy, Finland (Paper, Word File) (Presentation, PowerPoint file)

SESSION 2: PSA METHODOLOGY - PART I

Level 2 PSA Methodology - Methodological improvements based on recent Level 2 PSAs including knowledge gained in such areas as Level 1 Level 2 interface issues, use of severe accident codes and other computer codes, quantification and propagation of uncertainties.

• Full Power and Shutdown Level 2 PSA of the J. Bohunice V1 NPP, Zoltan Kovacs and Helena Novakova, RELKO Ltd., Engineering and Consulting Services, Bratislava, Slovak Republic (Presentation, PowerPoint file)
• Insights and lessons learned from PSA Level 2 for Bohunice V2 NPP, to be presented by Maciej Kulig, ENCONET Consulting, Vienna, Austria (Paper, Word File, PDF file) (Presentation, PowerPoint file)
• Level 2 PSA Model for Paks NPP, Attila Bareith, Gábor Lajtha, Zsolt Téchy, VEIKI Institute for Electric Power Research; József Elter, Paks Nuclear Power Plant Ltd (Presentation, PowerPoint file)

SESSION 2: PSA METHODOLOGY - PART II

• Level 2 PSA for the VVER 440/213 Dukovany NPP and its Implications for Accident Management , Jiri Dienstbier and Stanislav Hustak, Nuclear Research Institute Rez plc, Czech Republic (Paper, Word File, PDF File) (Presentation, PowerPoint file)
• Approach in the Periodic Safety Review for Sizewell B Living PSA - Aspects Specific to Level 2 PSA, Ming L Ang, E Grindon, K Peers (National Nuclear Corporation Ltd), and Peter Lightfoot (British Energy), United Kingdom (Paper, Word File) (Presentation, PowerPoint file)

TUESDAY, 30 MARCH 2004

SESSION 2: PSA METHODOLOGY - PART III

• Status of IRSN Level 2 PSA, Emmanuel Raimond, Mr. Caroli, Bernard Chaumont and Michel Durin, IRSN, France (Presentation,Word file)
• Examples for the Influence of Specific Plant Features on PSA level 2, Horst Loeffler, Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Koeln, Germany (Presentation, Word File, PDF file)
• A Proposal to Assess Conditional Probability Ranges for Plant Internal Phenomena during Core Melt Scenarios for German LWR, Thomas Froehmel, Bundesamt fuer Strahlenschutz, Horst Loeffler, Gesellschaft fuer Anlagen- und Reaktorsicherheit and Juergen Eyink, Framatome ANP, Germany (Paper, Word File) (Presentation, PowerPoint file)

Session 2: PSA Methodology - Part IV

• PSA Level 2 Source Term Approach in the Loviisa NPP, Tomi. Routamo, Satu Siltanen and Petra Lundström, Fortum Nuclear Services Ltd., Finland (Paper, Word File) (Presentation, PowerPoint file)
• Panel Discussion on Session 2

SESSION 3: PSA USED FOR DETAILED ANALYSIS - PART I

PSA Methodology used for detailed analysis, e.g. RPV and containment failure analysis.

• Probabilistic Evaluation of In-Vessel Retention Capability Applying Phenomenological Event Tree, Makoto Akinaga, Hirohide Oikawa, Ryoichi Hamazaki, Ken-ichi Sato and Takashi Uemura (Paper, Word File)
• Level 2 PSA Results Considered Mitigation Accident Management for a Japanese PWR Plant, Osamu Kawabata, Japan Nuclear Energy Safety Organization (JNES), Safety Analysis and Evaluation Division (Paper, Word File) (Presentation, PowerPoint file)
• Advanced Modelling and Response Surface Method for Physical Models of Level 2 PSA Event Tree, Messrs. Emmanuel Raimond, R. Meignen, J. Dupas , Georges Nahas, Bertrand Cirée, D. Plet and B. Laurent, IRSN, France (Paper, Word File) (Presentation, PowerPoint file)
• Additional Paper: A Monte Carlo Method for Estimation of the Probability of Combustion-Induced Containment Failure, M. Khatib-Rahbar and M. Zavisco, ERI, USA (Paper, PDF File)
• Panel Discussion on Session 3

SESSION 4: PSA - ADVANCED METHODS - PART I

Advanced Methodology to include uncertainty analysis, etc.

• An Approach to Evaluation of Uncertainties in Level 2PSAs, Tsutomu Ishigami, Japan Atomic Energy Research Institute (JAERI) Department of Reactor Safety Research (JAERI) Department of Reactor Safety Research (Paper, Word File, PDF file) (Presentation, PowerPoint file)
• Advances in Methods for Uncertainty and Sensitivity Analysis, Nicolas Devictor, CEA/Cadarache, DEN/DER/SESI/LCFR, France (Paper, Word File) (Presentation, PowerPoint file)
• MCDET and MELCOR - An Example of a Stochastic Module coupled with an Integral Code for PSA Level 2, Martin Sonnenkalb, Joerg Peschke, et. all., Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Koeln and Garching, Germany (Paper, Word File) (Presentation, PDF File, Word File)

WEDNESDAY, 31 MARCH 2004

SESSION 4: PSA - ADVANCED METHODS - PART II

• Classical Event Tree Analysis and Dynamic Event Tree Analysis for High Pressure Core Melt Accidents in a German Pressurised Water Reactor, Horst Loeffler, Joerg Peschke, Martin Sonnenkalb, Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Koeln, Germany (Paper, Word File) (Presentation, Word File, PDF file)
• Interpretation of the PSA2 Methodology on the Light of the Stimulus Driven Theory of Probabilistic Dynamics (SDTPD), Mr. José M Izquierdo Rocha, CSN Consejo de Seguridad Nuclear, Spain (Paper, PDF file) (Presentation, PowerPoint file)
• Panel Discussion on Session 4

Session 5: Accident Management and Training

• · Issues for Application of Severe Accident Management Guidelines to CANDU Reactors, Dinnie, Keith, Director, risk management, Nuclear Safety Solutions Ltd., Canada (Paper, Word File) (Presentation, PowerPoint file)
• SISIFO-GAS. A Computerised System to Support Severe Accident Training and Management, César Serrano, Senior Engineer, Iberdrola Ingeniería y Consultoría S.A. (IBERINCO) (Paper, Word File) (Presentation, PowerPoint file) (Demo SISIFO)
• Panel Discussion on Session 5

FINAL PANEL DISCUSSION AND CLOSING OF THE WORKSHOP (12:00 - 13:00)

FINAL PARTICIPANTS LIST (Word file)

© 2004 Organisation for Economic Co-operation and Development

Last updated: 27 April 2004