201.1 Long term station blackout analyses of two loop PWR using RELAP5/MOD3.3 Andrej Prošek Institut "Jožef Stefan" Jamova cesta 39 SI-1000 Ljubljana, Slovenia andrej.prosek@ijs.si Leon Cizelj Institut "Jožef Stefan" Jamova cesta 39 SI-1000 Ljubljana, Slovenia leon.cizelj@ijs.si ABSTRACT Stress tests which had to be performed in European countries required evaluation of the consequences of loss of safety functions from any initiating event (e.g., earthquake or flooding) causing loss of electrical power, including station blackout (SBO), loss of the ultimate heat sink or both. Long term SBO in a pressurized water reactor (PWR) leads to severe accident sequences, assuming that existing plant means (systems, equipment and procedures) are used for accident mitigation. Therefore the main objective was to study the accident management strategies for SBO scenarios (with different reactor coolant pumps (RCPs) leaks assumed) to delay the time before core uncovers and significantly heats up. The most important strategies assumed were primary side depressurization and additional makeup water to reactor coolant system (RCS). For simulations of long term SBO scenarios, including early stages of severe accident sequences, the latest best estimate RELAP5/MOD3.3 and the verified input model of Krško two-loop PWR were used. The results suggest that for the expected magnitude of RCPs seal leak, the core uncovery during the first seven days could be prevented by using the turbine driven auxiliary feedwater pump and manually depressurizing the RCS through the secondary side. For larger RCPs seal leaks, in general this is not the case. Nevertheless, the core uncovery can be significantly delayed by increasing the RCS depressurization. 1 INTRODUCTION Following the accident at the nuclear power plant Fukushima Daiichi in Japan the “stress tests” had to be performed in European countries [1]. Stress tests required evaluation of the consequences of loss of safety functions from any initiating event (e.g., earthquake or flooding) causing loss of electrical power, including station blackout (SBO). SBO scenario involves a loss of offsite power, failure of the redundant emergency diesel generators, failure of alternate current (AC) power restoration and the eventual degradation of the reactor coolant pump (RCP) seals resulting in a long term loss of coolant. In the literature there are many examples of station blackout analyses (e.g. [2], [3]), using severe accident codes for simulations of station blackout scenarios with core damage in the first 24 hours, while simulations lasting several days (long term) are very rare. The reason is that the long term heat sink that may prevent early core and containment damage was not