Auxiliary feedwater system risk-based inspection guide for the Callaway Nuclear Power Plant

Technical Report · Thu Aug 01 04:00:00 EDT 1991

DOI:https://doi.org/10.2172/5340939· OSTI ID:5340939

Moffitt, N E; Gore, B F; Vo, T V ^[1]

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1. 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. Callaway was selected as the eleventh 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 Callaway plant. 23 refs., 1 fig., 1 tab.

• 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: 5340939
• Report Number(s): NUREG/CR-5763; PNL--7725; ON: TI91017816
• Country of Publication: United States
• Language: English

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
CALLAWAY-1 REACTOR
CALLAWAY-2 REACTOR
CONTROL EQUIPMENT
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
FAILURE MODE ANALYSIS
FAILURES
FEEDWATER
FLOW REGULATORS
HYDROGEN COMPOUNDS
INSPECTION
OXYGEN COMPOUNDS
POWER REACTORS
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RISK ASSESSMENT
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
VALVES
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS