...the decommissioning plan for a nuclear power plant in Korea

来自 : www.researchgate.net/publicati 发布时间：2021-03-26

Jungmin Lee. et al : Development of the draft guidelines of the decommissioning plan for a nuclear power plant in KoreaJNFCWT(Korean) Vol.11 No.3 pp.213-227, September 2013 223Items Sub-items to be mentioned1. Overview of nuclear facilityⅰ. Facilities and site · To describe name, location and decommissioning entity of nuclear power reactor and its relevant facilities, hereafter, nuclear reactor facilities. · To describe the status of nuclear reactor facilities at that time when their decommissioning plan is being written. · To describe impacts, in terms of integrity and maintenance of their structures and equipment. due to permanent cessation of operation of the nuclear reactor facilities. · To describe the status of the site based on the latest FSAR and environmental impact assessment report. ⅱ. Operating history · To describe the operating history of the nuclear reactor facilities by year since the rst issuance of the nuclear power reactor operating license. · To describe changes in operating license approved by NSSC since the rst issuance of the nuclear power reactor operating license.ⅲ. Maintenance and accidents records · To describe the details of maintenance activities at the nuclear reactor facilities. · To describe causes and follow-up measures of all incidents and accidents beyond INES (International Nuclear and Radiological Event Scale) Level 1 rated in compliance with NSSC notice 2012-11. · To describe the details regarding it, such as date and time, location, material to be buried, type and form of radionuclides, activity, and activity concentration, if there is any radioactive material landll during the nuclear reactor facilities operation.2. Methods and schedule of decommissioning of the nuclear reactor facilityⅰ. Spent fuel transport and management · To describe results of characteristics assessment of all nuclear spent fuel at the interim spent fuel pool against acceptance criteria and their management method(including physical protection and safeguard measures) during the decommissioning period. · To describe the management method of the storage facility during the decommissioning period, including the followings, if there is any separate spent fuel storage facility at the site: - nuclear spent fuel storage type (dry vs. wet storage etc); - its physical, chemical and radiological states according to storage type; and - on-site management method until all nuclear spent fuel are moved to other facility or site. · To describe the followings, if it is necessary to transport nuclear spent fuel: - a plan to safely transport nuclear spent fuel to nal destination; and - its transport safety assessment, including integrity of nuclear spent fuel itself. ⅱ. Decommissioning methods and schedule · To describe decommissioning method, technical backgrounds for selection of the decommissioning method, and preparation activities for decommissioning, i.e., activities after permanent operation cessation. · To describe the methods for dismantlement and management of the following components: - reactor vessel and internals, steam generator, pressurizer, large size reactor coolant piping, large radioactive equipment and components. · To describe the order, starting and expected completion time of major decommissioning activities, and relationship between them. - activities required for approval or permission by NSSC, such as nuclear fuel discharge, nuclear spent fuel management and storage, transport of major components should be described as in detail as possible. - decommissioning schedule including expected starting and completion time of major decommissioning activities.ⅲ. Equipment and supplies · To describe equipment and supplies for decontamination and dismantlement of the nuclear reactor facilities · To describe the existing equipment and supplies and the new that will be needed to be installed or operated additionally for decommissioning. · To describe the post-use management methods of the used equipment and supplies.ⅳ. Industrial safety measures · To identify the potential non-radiological hazards related to decontamination and dismantlement of the nuclear reactor facilities and assess likelihoods of the hazards. - models and methods to assess non-radiological hazards should be based on the industrial standards. · To describe industrial safety related principles and standards to manage or control non-radiological hazards, and measures to secure workers safety by minimizing non-radiological hazards. ⅴ. Project organization and responsibilities · To describe the decommissioning entity, working groups, and their authorities and responsibilities during decommissioning period. Table 8. The draft guidelines of the decommissioning plan for an NPP