Auxiliary feedwater system risk-based inspection guide for the San Onofre Unit 2 Nuclear Power Plant
- Pacific Northwest Lab., Richland, WA (United States)
In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. San Onofre-2 was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the San Onofre-2 plant.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Safety and Analysis; Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 10131338
- Report Number(s):
- NUREG/CR--5766; PNL--7609; ON: TI93007538
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
AUXILIARY SYSTEMS
FAILURE MODE ANALYSIS
FAILURES
FEEDWATER
INSPECTION
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
REACTOR COMPONENTS
REACTOR SAFETY
RISK ASSESSMENT
SAN ONOFRE-2 REACTOR