Published August 1, 1999 | Version v1
Report

Common-Cause Failure Analysis for Reactor Protection System Reliability Studies

Description

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

Availability note (English)

Available from INIS in electronic form; Also available from OSTI as DE00008312; PURL: https://www.osti.gov/servlets/purl/8312-T3KPue/webviewable/

Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
INEEL/CON--99-00445

Conference

Title
International Topical Meeting on Probabilistic Safety Assessment
Acronym
PSA '99
Dates
22-25 Aug 1999
Place
Washington, DC (United States)

Optional Information

Contract/Grant/Project number
AC07-94ID13223
Funding organization
US Department of Energy (United States)