Analysis of core damage frequency: Peach Bottom, Unit 2 internal events

Kolaczkowski, A.M.; Cramond, W.R.; Sype, T.T.; Maloney, Kevin J.; Wheeler, Timothy A.; Daniel, S.L.

doi:10.2172/5530339

Cited by 10 publications

(4 citation statements)

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“…Partitioning the CCF events by method of discovery shows no CCF events occurred during unplanned demands. When the CCF events were further partitioned by testing frequency (cyclic and monthly tests), about the same number of CCF events were found during cyclic surveillance tests (6) and monthly surveillance tests (8). Considering that there are 18 times more monthly tests performed than cyclic tests, the proportion of CCFs found on monthly tests should be significantly higher assuming the tests are comparable.…”

Section: Common Cause Failure Eventsmentioning

confidence: 93%

Emergency Diesel Generator Power System Reliability 1987–1993

Grant

Poloski

Luptak

et al. 1996

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This report documents an analysis of the reliability of emergency diesel generator (EDG) power systems at U.S. commercial nuclear plants during the period 1987-1993. To evaluate EDG power system performance, estimates are given of individual EDG train reliability to supply emergency ac power to the safety-related bus. The estimates are based on EDG train performance data that would be typical of an actual response to a lowvoltage condition on a safety-related bus for averting a station blackout event. A risk-based analysis and an engineering analysis of trends and patterns are performed on data from EDG operational events to provide insights into the reliability performance of EDGs throughout the industry and at a plant-specific level. Comparisons are made to EDG train statistics from Probabilistic Risk Assessments, Individual Plant Examinations, and NUREG reports, representing 40% of the U.S. commercial nuclear power plants. In addition, EDG train reliability estimates and associated uncertainty intervals are compared to station blackout target reliability goals.

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Section: Common Cause Failure Eventsmentioning

confidence: 93%

Emergency Diesel Generator Power System Reliability 1987–1993

Grant

Poloski

Luptak

et al. 1996

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“…50, p. 32138, August 8, 1985. 1.2 USNRC, "Individual Plant Examination for Severe Accident Vulnerabilities -10 CFR $50.54(f)," Generic Letter 88-20, . 1.3 USNRC, "Individual Plant Examination: Submittal Guidance, "NUREG-1335, August 1989 1.4 USNRC, "Severe Accident Risks: An Assessment for Fire U.S. Nuclear Power Plants," NUREG-1150, December 1990.…”

Section: References For Chaptermentioning

confidence: 99%

Individual plant examination program: Perspectives on reactor safety and plant performance. Part 1: Final summary report; Volume 1

Washington¹

1997

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“…Although V, = 0.01 m/sec is used in J2q. (13) for all isotopes, there is no groundshine dose from noble gases because their groundshine dose factors are zero.…”

Section: =Dfck (K; Rfk I K ) Sfc Tc; =K; R F K I K Tc; (Dfck Sfck)mentioning

confidence: 99%

A Methodology for Grouping Source Terms for Consequence Calculations in Probabilistic Risk Assessments

1990

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The individual plant analyses in the U.S. Nuclear Regulatory Commission's reassessment of the risk from commercial nuclear power plants (NUREG-1 150) consist of four parts: systems analysis, accident-progression analysis, source-term analysis, and consequence analysis. Careful definition of the interfaces between these parts is necessary for both information flow and computational efficiency. This paper describes the procedure used to define the interface between the sourceterm analysis and the consequence analysis. This interface is accomplished by forming groups of source terms with similar properties and then performing one set of MACCS calculations for each group.

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Analysis of core damage frequency: Peach Bottom, Unit 2 internal events

Cited by 10 publications

References 0 publications

Emergency Diesel Generator Power System Reliability 1987–1993

Emergency Diesel Generator Power System Reliability 1987–1993

Individual plant examination program: Perspectives on reactor safety and plant performance. Part 1: Final summary report; Volume 1

A Methodology for Grouping Source Terms for Consequence Calculations in Probabilistic Risk Assessments

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