Intersystem LOCA risk assessment: methodology and results

Abstract The United States Nuclear Regulatory Commission is sponsoring a research program to develop an improved understanding of the human factors, hardware and accident consequence issues that dominate the risk from an intersystem loss-of-coolant accident (ISLOCA) at a nuclear power plant. To accomplish the goals of this program, a mehtodology has been developed for estimating ISLOCA core damage frequency and risk. The steps in this methodology are briefly described, along with the results obtained from an application of the methodology at three pressurized water reactors. Also included are the results of a screening study of boiling water reactors.