Value-impact analysis of regulatory options for resolution of Generic Issue C-8: MSIV (Main Steam Isolation Valve) leakage and LCS (Leakage Control System) failure

Technical Report · Tue May 01 00:00:00 EDT 1990

DOI:https://doi.org/10.2172/7146835· OSTI ID:7146835

Jamison, J D; Vo, T V; Tabatabai, A S ^[1]

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1. Pacific Northwest Lab., Richland, WA (USA)

This report describes the analysis conducted to establish the basis for answering two remaining regulatory questions facing the NRC staff regarding the resolution of Generic Issue C-8, specifically:(1) What action should the NRC take concerning plants that currently have a leakage control system (LCS) and, (2) What action should the NRC take concerning plants that do not have an LCS Using individual MSIV leak test data, the performance of a system of eight such valves in a standard BWR con-figuration was modeled. The performance model was used along with estimates of core damage accident frequency and calculated dose consequences to determine the public risk associated with each of the alternatives. The occupational exposure implications of each alternative were calculated using estimates of labor hours in radiation zones that would be incurred or avoided. The costs to industry of implementing each alternative were estimated using standard cost formulae and NRC staff estimates. The cost to the NRC were estimated based on the effort incurred or avoided for reviews or other staff actions engendered by the selection of or avoided for reviews or other staff actions engendered by the selection of a particular alternative. The cost and risks thus calculated suggest that no regulatory action can be justified on the basis of risk reduction or cost savings. 12 refs., 1 tab.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Safety Issue Resolution; Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
• Sponsoring Organization: USNRC
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 7146835
• Report Number(s): NUREG/CR-5397; PNL-6931; ON: TI90011027; TRN: 90-016076
• Country of Publication: United States
• Language: English

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BWR TYPE REACTORS
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OCCUPATIONAL EXPOSURE
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