Common-Cause Failure Analysis for Reactor Protection System Reliability Studies

Conference · Sun Aug 01 00:00:00 EDT 1999

OSTI ID:8312

Gentillon, C; Rasmuson, D; Eide, S; Wierman, T

Analyses were performed of the safety-related performance of the reactor protection system (RPS) at U.S. Westinghouse and General Electric commercial reactors during the period 1984 through 1995. RPS operational data from these reactors were collected from the Nuclear Plant Reliability Data System (NPRDS) and Licensee Event Reports (LER). The common-cause failure (CCF) modeling in the fault trees developed for these studies and the analysis and use of common-cause failure data were sophisticated, state-of-the-art efforts. The overall CCF effort helped to test and expand the limits of the U.S. Nuclear Regulatory Commission's CCF methodology.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: US Department of Energy (US)
• DOE Contract Number: AC07-94ID13223
• OSTI ID: 8312
• Report Number(s): INEEL/CON-99-00445; TRN: US0101962
• Resource Relation: Conference: PDA 99, Washington, DC (US), 08/22/1999--08/26/1999; Other Information: PBD: 1 Aug 1999
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PERFORMANCE
REACTOR PROTECTION SYSTEMS
RELIABILITY
FAULT TREE ANALYSIS
REACTOR SAFETY
GE STANDARD REACTOR
WESTINGHOUSE STANDARD REACTOR
REACTOR PROTECTION SYSTEM (RPS)
WESTINGHOUSE
GENERAL ELECTRIC
NUCLEAR PLANT RELIABILITY DATA SYSTEM (NPRDS)
LICENSEE EVENT REPORTS (LER)
COMMON-CAUSE FAILURE (CCF)
RELIABILITY STUDIES