Assessment of ISLOCA risk: Methodology and application to a Babcock and Wilcox nuclear power plant. Volume 2, Appendices A--H

Technical Report · Wed Apr 01 04:00:00 EST 1992

DOI:https://doi.org/10.2172/5424970· OSTI ID:5424970

Galyean, W J; Gertman, D I ^[1]

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1. EG and G Idaho, Inc., Idaho Falls, ID (United States)

This report presents information essential to understanding the risk associated with inter-system loss-of-coolant accidents (ISLOCAs). The methodology developed and presented in the report provides a state-of-the-art method for identifying and evaluating plant-specific hardware design, human performance issues, and accident consequence factors to relevant to the prediction of the ISLOCA risk. This ISLOCA methodology was developed and then applied to a Babcock and Wilcox (B W) nuclear power plants. The results from this application are described in detail. For this particular B W reference plant, the assessment indicated that the probability of a severe ISLOCA is approximately 2.2E-06/reactor-year. This document Volume 3 provides appendices A--H of the report. Topics are: Historical experience related to ISLOCA events; component failure rates; reference B W plant system descriptions; reference B W plant ISLOCA event trees; Human reliability analysis for the B W ISLOCA probabilistic risk assessment; thermal hydraulic calculations; bounding core uncovery time calculations; and system rupture probability.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: NRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5424970
• Report Number(s): NUREG/CR-5604-Vol.2; EGG--2608-Vol.2; ON: TI92013991
• Country of Publication: United States
• Language: English

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