INTERSYSTEM LOCA RISK ASSESSMENT - METHODOLOGY AND RESULTS

The United States Nuclear Regulatory Commission is sponsoring a resear ch program to develop an improved understanding of the human factors, hardware and accident consequence issues that dominate the risk from a n intersystem loss-of-coolant accident (ISLOCA) at a nuclear power pla nt. To accomplish the goals of this program, a mehtodology has been de veloped for estimating ISLOCA core damage frequency and risk. The step s in this methodology are briefly described, along with the results ob tained from an application of the methodology at three pressurized wat er reactors. Also included are the results of a screening study of boi ling water reactors.