Auxiliary feedwater system risk-based inspection guide for the Prairie Island Units 1 and 2 nuclear power plants
Technical Report
·
OSTI ID:6908790
- 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 guidance for the a 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. Prairie Island was selected as the seventh plant 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 Prairie Island plant.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Radiation Protection and Emergency Preparedness; Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6908790
- Report Number(s):
- NUREG/CR-5839; PNL--7605; ON: TI93001866
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
AUXILIARY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FAILURES
FEEDWATER
HYDROGEN COMPOUNDS
INSPECTION
OXYGEN COMPOUNDS
POWER REACTORS
PRAIRIE ISLAND-1 REACTOR
PRAIRIE ISLAND-2 REACTOR
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
AUXILIARY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FAILURES
FEEDWATER
HYDROGEN COMPOUNDS
INSPECTION
OXYGEN COMPOUNDS
POWER REACTORS
PRAIRIE ISLAND-1 REACTOR
PRAIRIE ISLAND-2 REACTOR
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS