Investigations of inter-system common cause failures
Creators
- 1. Electricite de France, Recherche/Developpement, 1 avenue du General De Gaulle, 92140 Clamart (France)
Description
Intra-system common-cause failures (CCF) are widely studied and addressed in existing PSA models, but the information and studies that incorporate the potential for inter-system CCF is limited. However, the French Safety Authority has requested that EDF investigate the possibility of common-cause failure across system boundaries for Flamanville 3 (an EPR design). Also, the modeling of inter-system CCF, or the proof that their impact is negligible, would satisfy Capability Category III for one of the requirements in the ASME/ANS PRA standard in the U.S. EDF and EPRI have been working on a method to assess when it is necessary to take into account inter-system CCF in a PSA model between 2008 and 2010. This method is based both on the likelihood of inter-system CCF and on its demonstrated potential impact on CDF (core damage frequency). This method was first applied on pumps in different systems of the 900 MWe series plants. The second application concerned the motor-operated valves across different systems, using the same PSA model. This second application helped us refine the method, which was not optimal when the number of concerned components is very large. Since then, the method has been successfully applied on the pumps and 10 kV breakers of the EPR power plant in Flamanville. This paper describes the method and the results obtained in some of these studies. All studies have shown either that components in different systems, when they were not already part of a common cause failure group in the model, are not susceptible to common causes of failure, or that the potential for inter-system common-cause failure is negligible regarding the overall risk. (authors)
Files
48018763.pdf
Files
(1.6 MB)
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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. 700-733
- 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
- 48018763
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FLAMANVILLE-3 REACTOR; PROBABILISTIC ESTIMATION; REACTOR SAFETY; RISK ASSESSMENT; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 6 refs.