Published July 19, 2012 | Version v1
Report Open

Investigations of inter-system common cause failures

  • 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)

Name Size Download all
md5:342f97e7450618354e243d3aae1858f4
1.6 MB Preview Download
Part of:
Workshop on PSA for New and Advanced Reactors

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.