Results of core damage frequency analysis for the reference plants
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.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA); Energy, Inc., Kent, WA (USA); Science Applications International Corp., La Jolla, CA (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 7037458
- Report Number(s):
- SAND-86-2521C; CONF-8610135-21; ON: DE87002054
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
BWR TYPE REACTORS
DAMAGE
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAND GULF-1 REACTOR
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GRAPHITE MODERATED REACTORS
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POWER REACTORS
PWR TYPE REACTORS
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REACTOR COMPONENTS
REACTOR CORES
REACTOR OPERATION
REACTORS
RISK ASSESSMENT
SEQUOYAH-2 REACTOR
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
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THERMAL REACTORS
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