Determination of ‘Decommissioned for Safeguards Purposes’ of the Post-Accident Facilities
at Fukushima Dai-ichi

Year
2023
Author(s)
M. Murray - International Atomic Energy Agency, Regional Office in Tokyo, Japan
G. Horton - International Atomic Energy Agency, Regional Office in Tokyo, Japan
Y. Meiliza - International Atomic Energy Agency, Regional Office in Tokyo, Japan
J. Persin - International Atomic Energy Agency, Regional Office in Tokyo, Japan
G. Spence - International Atomic Energy Agency, Regional Office in Tokyo, Japan
File Attachment
finalpaper_619_0516102355.pdf394.04 KB
Abstract
The status of a post-operational facility being decommissioned for safeguards purposes is determined in part by the designated essential equipment for that facility either being removed or rendered inoperable. Inherent in that determination is the ability of the IAEA to visit the essential equipment in the facility to observe its status. It is not possible to visit many of the essential equipment locations at the post-accident facilities on the Fukushima Dai-ichi site due to the radiological conditions. This paper examines the methodology by which these facilities can be considered decommissioned for safeguards purposes without full access to the essential equipment, by taking a holistic approach to the equipment systems required for the operation of a reactor.