Analysis of a hypothetical boron dilution event with RETRAN-02

The common method assumed for mitigation of a boron dilution event in a pressurized water reactor (PWR) safety analysis is to prevent reactor criticality by allowing ample time for operator action following dilution detection. Therefore, the consequences of the event, which lead to reactor overpower condition and subsequent overpressurization of the reactor coolant system, are precluded. To date, no boron dilution incident has occurred which resulted in criticality. The purpose of this analysis is to study the primary system response to the event, which relies solely on the reactor's inherent characteristics and plant safeguard features using the RETRAN-02 computer code. It is important to keep in mind that the assumptions of the analysis are more conservative than the design basis accident, which represents the licensing basis of the plant