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Guidelines on Modeling Common-Cause Failures in Probabilistic Risk Assessment.

NUREGCR5485

Publication Date	1998
Personal Author	Mosleh, A.; Rasmuson, D. M.; Marshall, F. M.
Page Count	208
Abstract	This report provides a set of guidelines to help probabilistic risk assessment (PRA) analysis in modeling common cause failure (CCF) events in commercial nuclear power plants. The aim is to enable the analyst to identify imporant common cause vulnerabilities, incorporate their impact into system reliability models, perform data analysis, and quantify system unavailability in the presence of CCFs. Much of the material in this report has been presented in previous reports issued by United States Nuclear Regulatory Commission (NRC). The present document brings together the key aspects of these procedural guidelines supplemented by additional insights gained from their application, and enhanced by the capabilities of the CCF software and its data analysis capabilities, recently developed by the NRC.
Keywords	Nuclear power plants Models Failures Risk assessment Guidelines Reactor safety Reactor components Quantitative analysis Qualitative analysis Data analysis Probabilistic risk assessment Common cause failures CCF events
Source Agency	Nuclear Regulatory Commission
Corporate Authors	Idaho National Engineering and Environmental Lab., Idaho Falls.; Maryland Univ., College Park. Dept. of Materials and Nuclear Engineering.; Nuclear Regulatory Commission, Washington, DC. Office for Analysis and
Supplemental Notes	Prepared in cooperation with Maryland Univ., College Park. Dept. of Materials and Nuclear Engineering. Sponsored by Nuclear Regulatory Commission, Washington, DC. Office for Analysis and Evaluation of Operational Data.
Document Type	Technical Report
Title Note	Technical rept.
NTIS Issue Number	199907

Guidelines on Modeling Common-Cause Failures in Probabilistic Risk Assessment.

Guidelines on Modeling Common-Cause Failures in Probabilistic Risk Assessment.
NUREGCR5485

Publication Date	1998
Personal Author	Mosleh, A.; Rasmuson, D. M.; Marshall, F. M.
Page Count	208
Abstract	This report provides a set of guidelines to help probabilistic risk assessment (PRA) analysis in modeling common cause failure (CCF) events in commercial nuclear power plants. The aim is to enable the analyst to identify imporant common cause vulnerabilities, incorporate their impact into system reliability models, perform data analysis, and quantify system unavailability in the presence of CCFs. Much of the material in this report has been presented in previous reports issued by United States Nuclear Regulatory Commission (NRC). The present document brings together the key aspects of these procedural guidelines supplemented by additional insights gained from their application, and enhanced by the capabilities of the CCF software and its data analysis capabilities, recently developed by the NRC.
Keywords	Nuclear power plants Models Failures Risk assessment Guidelines Reactor safety Reactor components Quantitative analysis Qualitative analysis Data analysis Probabilistic risk assessment Common cause failures CCF events
Source Agency	Nuclear Regulatory Commission
Corporate Authors	Idaho National Engineering and Environmental Lab., Idaho Falls.; Maryland Univ., College Park. Dept. of Materials and Nuclear Engineering.; Nuclear Regulatory Commission, Washington, DC. Office for Analysis and
Supplemental Notes	Prepared in cooperation with Maryland Univ., College Park. Dept. of Materials and Nuclear Engineering. Sponsored by Nuclear Regulatory Commission, Washington, DC. Office for Analysis and Evaluation of Operational Data.
Document Type	Technical Report
Title Note	Technical rept.
NTIS Issue Number	199907