Shutdown decay heat removal analysis of a Westinghouse 2-loop pressurized water reactor: Case study

Technical Report · Sun Mar 01 04:00:00 EST 1987

OSTI ID:6799168

Cramond, W R; Ericson, Jr, D M; Sanders, G A

This is one of six case studies for USI A-45 Decay Heat Removal (DHR) Requirements. The purpose of this study is to identify any potential vulnerabilities in the DHR systems of a typical Westinghouse 2-loop PWR, to suggest possible modifications to improve the DHR capability, and to assess the value and impact of the most promising alternatives to the existing DHR systems. The systems analysis considered small LOCAs and transient internal initiating events, and seismic, fire, extreme wind, internal and external flood, and lightning external events. A full-scale systems analysis was performed with detailed fault trees and event trees including support system dependencies. The system analysis results were extrapolated into release categories using applicable past PRA phenomenological results and improved containment failure mode probabilities. Public consequences were estimated using site specific CRAC2 calculations. The Value-Impact (VI) analysis of possible alternatives considered both onsite and offsite impacts arriving at several risk measures such as averted population dose out to a 50-mile radius and dollars per person rem averted. Uncertainties in the VI analysis are discussed and the issues of feed and bleed and secondary blowdown are analyzed.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Safety Review and Oversight; Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6799168
• Report Number(s): NUREG/CR-4458; SAND-86-2496; ON: TI87007512
• Country of Publication: United States
• Language: English

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