Study on technical issues of site release of nuclear power plants; Criteria for site release, procedures and verification requirements based on experiences in the U.S. (Contract research)

Sukegawa, Takenori; Shimada, Taro ; Katsurai, Kiyomichi; Tanaka, Tadao ; Nakayama, Shinichi 

In the field of safety regulation systems for nuclear facilities after completion of operation, criteria of residual radioactivities and confirmation and verification procedures for termination of decommissioning are important problems that should concretely be made a study. Safety standards and criteria in IAEA, USA, etc., and practical examples of site release of power reactors in USA were studied, therefore, problems for introducing the regulation system in Japan were discussed. In this report, final status survey of Trojan power plant were investigated as a particular case of site release, and, concept of specifying survey areas to be measured radioactivities and demonstrated to compliance with release criteria was discussed. In addition, the idea of confirmation and verification procedure for termination of decommissioning in Japan was proposed referring to the US guidance (MARSSIM).