Published February 1991
| Version v1
Report
Impact of support system failure limitations on probabilistic safety assessment and in regulatory decision making
Description
When used as a tool for safety decision making, probabilistic safety assessment (PSA) is as effective as it realistically characterizes the overall frequency and consequences of various types of system and component failures. If significant support system failure events are omitted from consideration, the PSA process omits the characterization of possibly unique contributors to core damage risk, possibly underestimates the frequency of core damage, and reduces the future utility of the PSA as a decision making tool for the omitted support system. This paper is based on a review of several recent US PSA studies and the author's participation in several International Atomic Energy Agency (IAEA) sponsored peer reviews
Additional details
Publishing Information
- Imprint Title
- CSNI workshop on PSA applications and limitations. Proceedings
- Imprint Pagination
- 475 p.
- Journal Page Range
- p. 259-271.
- Report number
- NUREG/CP--0115
Conference
- Title
- Committee on the Safety of Nuclear Installations (CSNI) on Probabilistic Safety Assessment (PSA) applications and limitations.
- Dates
- 4-6 Sep 1990.
- Place
- Santa Fe, NM (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23008697
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALTERNATING CURRENT; AUXILIARY WATER SYSTEMS; BWR TYPE REACTORS; DIRECT CURRENT; ELECTRIC POWER; EPRI; FAILURE MODE ANALYSIS; FAILURES; IAEA; MANAGEMENT; MITIGATION; POWER SYSTEMS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR CORE DISRUPTION; REACTOR INSTRUMENTATION; REACTOR LICENSING; REACTOR OPERATION; REACTOR OPERATORS; REACTOR SAFETY; REGULATIONS; RELIABILITY; RISK ASSESSMENT; SAFETY ENGINEERING; SURRY-1 REACTOR; SURRY-2 REACTOR
- Descriptors DEC
- ACCIDENTS; AUXILIARY SYSTEMS; CURRENTS; ELECTRIC CURRENTS; ENRICHED URANIUM REACTORS; INTERNATIONAL ORGANIZATIONS; LAWS; LICENSING; OPERATION; PERSONNEL; POWER; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Secondary number(s)
- SAND--90-2797; CONF-9009346--.