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U.S. Department of Energy
Office of Scientific and Technical Information

Auxiliary feedwater system risk-based inspection guide for the Prairie Island Units 1 and 2 nuclear power plants

Technical Report ·
OSTI ID:6908790
; ;  [1]
  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 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