Assessment of ISLOCA risk: Methodology and application to a Babcock and Wilcox nuclear power plant. Volume 2, Appendices A--H

This report presents information essential to understanding the risk associated with inter-system loss-of-coolant accidents (ISLOCAs). The methodology developed and presented in this report provides a state- of-the-art method for identifying and evaluating plant-specific hardware designs, human performance issues, and accident consequence factors relevant to the prediction of the ISLOCA risk. This ISLOCA methodology was developed and then applied to a Babcock and Wilcox (B & W) nuclear power plant. The results from this application are described in detail. For this particular B & W reference plant, the assessment indicated that the probability of a severe ISLOCA is approximately 2.2E-06/reactor-year. This document Volume 3, provides appendices I-M for the report. Topics are: Consequence Calculations; External events analysis of ISLOCA sequences; Review of Pressure Fragility Calculations; Uncertainty Analysis; and Steam Propagation Analysis for the B & W Plant Auxiliary Building.