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2021

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Key Words Probabilistic Risk Assessment
Component Reliability Parameters
Failure Rate
Demand Failure Probability
Bayesian Statistics

Estimation of the generic component reliability parameters for probabilistic risk
assessment of the Japanese nuclear power plants
Tomoaki Yoshida, Shota Soga and Hiroaki Seino

Abstract
This report provides improved estimates of the generic component reliability parameters for probabilistic risk assessmentof the Japanese nuclear power plants based on the data collected through an explanatory procedure with explicitly defined
criteria. The credibility of the previous generic reliability parameters was questioned because the failure data sources were theNUCIA industry database, which is not originally designed for PRA and might not cover the component populations modeledin PRA. To resolve this issue, we use the component failure information directly collected by the Japanese utilities according
to the sound definitions of component populations and failure criteria consistent with the utilities PRA models. The technicalproblems in the previous parameters have been resolved in the new parameters, which are believed to contribute to the enhanced
quality of PRA in Japan.

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...................................................................................... 3................................................................................................. 72.2.3.1........................................... 72.2.3.2........................................... 9.......................................................................................... 93.1......................................................................................................... 93.2............................................................................................ 103.3.............................................................................. 163.4.......................................................................... 16

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Reliability Data Sheets Update 2015,"2017/3-33-45%

2JANSI[7]29

3-53-6290.1 10.0

16

©CRIEPI, 2009

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1982
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NUREG/CR-6928,[1]

NuclearRegulatory

Commission, February 2007.

http://www.nucia.jp/,
[2]

U.S.

,

[11] United States Nuclear Regulatory Commission,

2021-09-30"Component Reliability Data Sheets," March 2008.

PSA

,,

[3]

,,

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[Online].Available:3.

http://nrcoe.inl.gov/resultsdb/publicdocs/AvgPerf/,

ComponentReliabilityDataSheets.pdf,
2021-09-30

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,
[4]

13,

[12] United States Nuclear Regulatory Commission,

P00001"Component Reliability Data Sheets Update.

2010," September 2012.

2,

BWR(ABWR)

49,[Online].Available:

PRA(PSA)

http://nrcoe.inl.gov/resultsdb/publicdocs/AvgPerf/

1 ,ComponentReliabilityDataSheets2010.pdf,

P03001,16

32021-09-30.

[13] United States Nuclear Regulatory Commission,[5]"Component Reliability Data Sheets Update
1982
2149

2002

2015," February 2017.

,[Online].Available:

25©CRIEPI

http://nrcoe.inl.gov/resultsdb/publicdocs/AvgPerf/
ComponentReliabilityDataSheets2015.pdf,
2021-09-30[14] Adery C. A. Hope, “A Simplified Monte CarloSignificance Test Procedure,” Journal of the Royal
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26©CRIEPIA-1-1©CRIEPIA-1-2©CRIEPIA-1-3©CRIEPIA-1-4©CRIEPIA-1-5©CRIEPIA-1-6©CRIEPIA-1-7©CRIEPIA-2-1©CRIEPIA-2-2©CRIEPIA-3-1©CRIEPIA-3-2©CRIEPIA-3-3©CRIEPIA-3-4©CRIEPIA-3-5©CRIEPIA-3-6©CRIEPIA-4-1©CRIEPIe-mail hokokusho@criepi.denken.or.jp

ISBN