Interfacing systems LOCA (loss-of-coolant accidents): Pressurized water reactors

Technical Report · Wed Feb 01 04:00:00 EST 1989

DOI:https://doi.org/10.2172/6298405· OSTI ID:6298405

Bozoki, G.; Kohut, P.; Fitzpatrick, R.

This report summarizes a study performed by Brookhaven National Laboratory for the Office of Nuclear Regulatory Research, Reactor and Plant Safety Issues Branch, Division of Reactor and Plant Systems, US Nuclear Regulatory Commission. This study was requested by the NRC in order to provide a technical basis for the resolution of Generic Issue 105 ''Interfacing LOCA at LWRs.'' This report deals with pressurized water reactors (PWRs). A parallel report was also accomplished for boiling water reactors. This study focuses on three representative PWRs and extrapolates the plant-specific findings for their generic applicability. In addition, a generic analysis was performed to investigate the cost-benefit aspects of imposing a testing program that would require some minimum level of leak testing of the pressure isolation valves on plants that presently have no such requirements. 28 refs., 31 figs., 64 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Safety Issue Resolution; Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6298405
• Report Number(s): NUREG/CR-5102; BNL-NUREG-52135; ON: TI89009565
• Country of Publication: United States
• Language: English

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