Abstract
The AREVA NP Inc. realistic large-break loss-of-coolant-accident (LOCA) analysis methodology references the 1988 amended 10 CFR 50.46 allowing best-estimate calculations of emergency core cooling system performance. This methodology
conforms to the code scaling, applicability, and uncertainty (CSAU) methodology developed by the
Technical Program Group for the United States Nuclear Regulatory Commission in the late
1980s. In addition, several practical considerations were revealed with the move to a production
application. This paper describes the methodology development within the CSAU framework and utility objectives, lessons
learned, and insight about current LOCA issues.