Auxiliary feedwater system risk-based inspection guide for the Beaver Valley, Units 1 and 2 nuclear power plants

Technical Report · Mon Feb 01 00:00:00 EST 1993

OSTI ID:6982144

Lloyd, R C; Vehec, T A; Moffitt, N E; Gore, B F; Vo, T V ^[1]; Rossbach, L W; Sena, III, P P ^[2]

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1. Pacific Northwest Lab., Richland, WA (United States)
2. 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. Beaver Valley Units 1 and 2 were selected as two 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 Beaver Valley Units 1 and 2.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Safety and Analysis; Pacific Northwest Lab., Richland, WA (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6982144
• Report Number(s): NUREG/CR-5835; PNL-7925; ON: TI93009096
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BEAVER VALLEY-1 REACTOR
AUXILIARY SYSTEMS
RISK ASSESSMENT
BEAVER VALLEY-2 REACTOR
FAILURES
FEEDWATER
INSPECTION
REACTOR COMPONENTS
REACTOR SAFETY
ENRICHED URANIUM REACTORS
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
POWER REACTORS
PWR TYPE REACTORS
REACTORS
SAFETY
THERMAL REACTORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled