Some insights gained from conducting an EPRI-sponsored review of five PRA studies
- 1. Electric Power Research Inst., Palo Alto, CA
- 2. NUS Corp., San Diego, CA
Description
A number of Probabilistic Risk Assessment (PRA) studies have been completed for specific plants at specific sites, and many more are in progress. These studies, motivated by a variety of objectives, range in scope from limited extrapolations of the Reactor Safety Study (RSS, 1975) methods or adaptations of RSS results (studies conducted under the NRC's Reactor Safety Study Methodology Applications Program - RSSMAP) to full-scale PRAs which retain the key elements of the RSS methodology, but have introduced new and improved techniques. As of mid-1983, twelve full scope (Level 3) PRA studies have been completed for LWRs located in the United States. These are presented together with information on operating license date, the plant basic design features, study sponsorship, report availability, initiation and completion dates
Additional details
Publishing Information
- Imprint Title
- Eleventh water reactor safety research information meeting. Volume 3. Containment systems research; status of source term reassessment; fuel systems research program; risk analysis
- Journal Page Range
- p. 610-622.
- Report number
- NUREG/CP--0048-Vol.3
Conference
- Title
- 11. NRC water reactor safety research information meeting.
- Dates
- 14-24 Oct 1983.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16010985
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ARKANSAS-1 REACTOR; BIG ROCK POINT REACTOR; BWR TYPE REACTORS; FAILURES; FIRES; GRAND GULF-1 REACTOR; LIMERICK-1 REACTOR; LOSS OF COOLANT; MELTDOWN; PROBABILITY; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; RESEARCH PROGRAMS; RISK ANALYSIS; TRANSIENTS; ZION-1 REACTOR
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS