[en] An analysis of BWR/4 plant response to a simultaneous closing of all main steam isolation valves followed by a failure of the reactor protection system scram function was performed using the RETRAN-01 computer code. The purpose of the analysis was to determine what power level the plant must operate at such that the vessel pressure does not exceed 1500 psig during the postulated transient. No credit was taken for a ATWS Recirculation Pump Trip. Analyses were performed both at 100% flow conditions and at reduced core flow conditions. The results of the analyses show that the 1500 psig vessel pressure criteria were met for operating conditions of less than or equal to 85% power