Auxiliary feedwater system risk-based inspection guidance for the Davis-Besse nuclear power plant
- Pacific Northwest Lab., Richland, WA (United States)
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Safety and Analysis
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. Davis-Besse 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 Davis-Besse 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:
- 10187159
- Report Number(s):
- NUREG/CR-5829; PNL-7905; ON: TI94000513; TRN: 93:022995
- Resource Relation:
- Other Information: PBD: Sep 1993
- Country of Publication:
- United States
- Language:
- English
Similar Records
Auxiliary feedwater system risk-based inspection guide for the Comanche Peak Nuclear Power Plant
Auxiliary feedwater system risk-based inspection guide for the Maine Yankee Nuclear Power Plant
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
AUXILIARY SYSTEMS
REACTOR COOLING SYSTEMS
RISK ASSESSMENT
FEEDWATER
INSPECTION
FAILURES
REACTOR SAFETY
DAVIS BESSE-1 REACTOR
DAVIS BESSE-2 REACTOR
DAVIS BESSE-3 REACTOR
PUMPS
MOTORS
VALVES
220900
210200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED