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Amos, C.N.; Benjamin, A.S.; Kunsman, D.M.; Williams, D.C.; Boyd, G.J.; Lewis, S.R.; Smith, L.N.
Sandia National Laboratories, Albuquerque, NM (United States); Sandia National Laboratories, Livermore, CA (United States). Funding organisation: U.S. Nuclear Regulatory Commission, Division of Reactor Systems Safety, Office of Nuclear Regulatory Research, Washington, DC (United States)1987
Sandia National Laboratories, Albuquerque, NM (United States); Sandia National Laboratories, Livermore, CA (United States). Funding organisation: U.S. Nuclear Regulatory Commission, Division of Reactor Systems Safety, Office of Nuclear Regulatory Research, Washington, DC (United States)1987
AbstractAbstract
[en] The Severe Accident Risk Reduction Program (SARRP) has completed a rebaselining of the risks to the public from a boiling water reactor with a Mark III containment (Grand Gulf, Unit 1). Emphasis was placed on determining the magnitude and character of the uncertainties, rather than focusing on a point estimate. The risk-reduction potential of a set of proposed safety option backfits was also studied, and their costs and benefits were also evaluated. It was found that the risks from internal events are generally low relative to previous studies; for example, most of the uncertainty range is lower than the point estimate of risk for the Peach Bottom plant in the Reactor Safety Study (RSS). However, certain unresolved issues cause the top of the uncertainty band to appear at a level that is comparable with the RSS point estimate. These issues include the diesel generator failure rate, iodine and cesium revolatilization after vessel breach and the possibility of reactor vessel pedestal failure caused by core debris attack. Some of the postulated safety options appear to be potentially cost effective for the Grand Gulf power plant, particularly when onsite accidents costs are included in the evaluation of benefits. Principally these include procedural modifications and relatively inexpensive hardware additions to insure core cooling in the event of a station blackout. This work supports the Nuclear Regulatory Commission's assessment of severe accidents in NUREG-1150. (author)
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Apr 1987; 775 p; INIS-XA-N--069; SAND--86-1309(VOL.4); CONTRACT DE-AC04-76DP00789; A1322; MEMORANDUM OF UNDERSTANDING DOE 40-550-75; Refs, figs, tabs
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