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
Identifiers
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)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 32065498
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAULT TREE ANALYSIS; GE STANDARD REACTOR; PERFORMANCE; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RELIABILITY; WESTINGHOUSE STANDARD REACTOR
- Descriptors DEC
- BWR TYPE REACTORS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- AC07-94ID13223
- Funding organization
- US Department of Energy (United States)