Results of core damage frequency analysis for the reference plants
Description
The Nuclear Regulatory Commission (NRC) is preparing NUREG-1150 to examine risk from a selected group of nuclear power plants. NUREG-1150 will provide a basis for comparison of NRC research to industry results and resolution of numerous severe accident issues. In support of NUREG-1150, Sandia National Laboratories has directed the production of NUREG/CR-4550. NUREG/CR-4550 includes Level 1 Probabilistic Risk Assessments (PRAs) for the Surry, Sequoyah, Peach Bottom, and Grand Gulf nuclear power plants and a limited reanalysis of the Zion PRA. A brief summary of the current results of these five analyses will be presented in this paper. A paper describing and evaluating the methodology used to perform the four Level 1 PRAs will also be presented at this conference
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE87002054.
Files
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The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 21 p.
- Report number
- SAND--86-2521C
Conference
- Title
- 14. water reactor safety information meeting.
- Dates
- 27-31 Oct 1986.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18057531
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- GRAND GULF-1 REACTOR; GRAND GULF-2 REACTOR; PEACH BOTTOM-1 REACTOR; PEACH BOTTOM-2 REACTOR; PEACH BOTTOM-3 REACTOR; REACTOR ACCIDENTS; REACTOR CORES; REACTOR OPERATION; RISK ASSESSMENT; SEQUOYAH-2 REACTOR; SURRY-1 REACTOR; SURRY-2 REACTOR; SURRY-3 REACTOR; SURRY-4 REACTOR; ZION-1 REACTOR; ZION-2 REACTOR
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.
- Secondary number(s)
- CONF-8610135--21.