Safety Analysis for Hanul no.5 Reactor Trip due to RCP Trip

Review and validate design related to reactor coolant pump trip event. Assessment of reactor system and nuclear fuel integrity using system safety code. The reactor trip due to the trip of the reactor coolant pump at Hanul 5 on July 5, 2017 was assessed to confirm whether the reactor system remained safe during the transient period and the integrity of the nuclear fuel was maintained. The range of evaluation was analyzed by analyzing the main operating variables of the power plant during the transient period, and it was confirmed whether each operating variable was kept within the limit. We also analyzed the transient events using system safety analysis codes to confirm the safety of the system and fuel during the transient period. With the appropriate action of the operator, the power plant remained safe after the transient event. As a result of analysis using the systematic safety analysis code, it was confirmed that the maximum pressure and minimum DNBR satisfied the limit of safety analysis and the integrity of the nuclear fuel and reactor system was maintained.