[1G_PL04] Discussion
Since the magnitude of uncertainties involved in phenomena in nuclear accidents differs between a design basis (DB) accident and a severe accident (SA), it is necessary to have different approach to facility design and the evaluation of the effectiveness of countermeasures. In this session, the regulator will explain how the review of SA facilities differs from that of DB facilities, and operators will introduce the concept and equipment of SA measures corresponding to the regulatory standards and voluntary measures.