IC modelling in the IRSN EPR level 1 PSA
Description
Today in France, an EPR (European Pressurized Water Reactor) Unit is under construction at the Flamanville site. The creation authorization was granted in April 2007 and the plant commissioning is planned for 2012. The plant operator (EDF) provided for the construction license several PSA (Probabilistic Safety Assessment) studies. IRSN, as TSO (Technical Safety Organisation), wishes to dispose of the appropriate knowledge and tools for the independent verification of the operator studies and so developed its own model of PSA level 1. The goal is not to rebuild the plant operator PSA (with a full scope...) but to dispose of a simplified model able to clearly point out specific important issues. In the IRSN model a particular effort has recently been done on the Digital IC modelling. The IC (Instrumentation and Control) is modelled in the IRSN EPR PSA by using Fault Trees. Instead, EDF EPR PSA applies the COMPACT model to simplify the command and instrumentation logics. The IRSN model is more detailed in order to be more accurate in the global analysis of the Digital IC. For instance the communication ways between automates are considered as well as the failure of support systems. The model is still under development mainly in order to define the CCF (Common Cause Failure) which may be considered. (authors)
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48018743.pdf
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Additional details
Publishing Information
- Imprint Title
- Workshop on PSA for New and Advanced Reactors
- Imprint Pagination
- 733 p.
- Journal Page Range
- p. 324-337
- Report number
- NEA-CSNI-R--2012-2
Conference
- Title
- Workshop on PSA for New and Advanced Reactors
- Dates
- 20-24 Jun 2011
- Place
- Paris (France)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 48018743
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAULT TREE ANALYSIS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR SAFETY; RISK ASSESSMENT
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs.