Best estimate analysis of complete loss of normal feedwater without reactor scram for a PWR plant

This paper presents the results of a complete loss of normal feedwater without reactor scram transient analysis, for the Salem Westinghouse four loop Pressurized Water Reactor. The analysis has been performed using the Best-Estimate code, RELAP5/MOD2 on a Cyber 932 computer under the NOS/VE Operating System. The loss of feedwater is an anticipated transient and is considered as a Condition II event, a Fault of Moderate Frequency as defined by ANSI-N182-1973. Although it has a low probability of occurrence, a complete loss of normal feedwater is here evaluated with the additional assumption that a nonmechanistic, common mode failure prevents the control rods from dropping into the core. This transient is one among others performed for this plant. It is here discussed using a set of parametric analysis. The effort is motivated by the current interest in using best-estimate methodologies to supplement design basis codes and Evaluation Models in Nuclear Utilities environments.