Assessment of ISLOCA risk: Methodology and application to a Westinghouse four-loop ice condenser plant

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

DOI:https://doi.org/10.2172/10143577· OSTI ID:10143577

Kelly, D L; Auflick, J L; Haney, L N ^[1]

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

Inter-system loss-of-coolant accidents (ISLOCAs) have been identified as important contributors to offsite risk for some nuclear power plants. A methodology has been developed for identifying and evaluating plant-specific hardware designs, human factors issues, and accident consequence factors relevant to the estimation of ISLOCA core damage frequency and risk. This report presents a detailed description of the application of this analysis methodology to a Westinghouse four-loop ice condenser plant. This document also includes appendices A through I which provide: System descriptions; ISLOCA event trees; human reliability analysis; thermal hydraulic analysis; core uncovery timing calculations; calculation of system rupture probability; ISLOCA consequences analysis; uncertainty analysis; and component failure analysis.

• 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: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 10143577
• Report Number(s): NUREG/CR-5744; EGG-2649; ON: TI92013753
• Resource Relation: Other Information: PBD: Apr 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
NUCLEAR POWER PLANTS
LOSS OF COOLANT
PWR TYPE REACTORS
ICE CONDENSERS
AFTER-HEAT REMOVAL
HUMAN FACTORS
PUMPS
VALVES
RISK ASSESSMENT
HEAT TRANSFER
HYDRAULICS
REACTOR SAFETY
FAILURE MODE ANALYSIS
REACTOR COMPONENTS
220900
210200
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED