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This page intentionally left blank TABLE OF CONTENTS Preface A. General Provisions Article 6 Existing Nuclear Installations ···················································································· 6-1 6.1 Existing Nuclear Installations in the Scope of this Convention ·········································· 6-1 6.2 The Safety of Existing Nuclear Installations ······································································· 6-2 6.3 Evaluation and Verification of Safety, and Position as to Continued Operation ··············· 6-12 B. Legislation and Regulation Article 7 Legislative and Regulatory Framework ··································································· 7-1 7.1 System of Legislations Governing the Nuclear installations ··············································· 7-1 7.2 Legislative and Regulatory Framework at Each Stage ························································ 7-7 7.3 Record, Applicable Regulations and Enforcement of Terms of License ··························· 7-11 7.4 Change the Technical Standards for Nuclear Installations to Performance Requirements ············································································································································· 7-12 Article 8 Regulatory Body ·········································································································· 8-1 8.1 Mandate and Duties of Regulatory Body ············································································ 8-2 8.2 Organizations for Enforcement of Safety Regulation of Nuclear Installations ··················· 8-2 8.3 Nuclear and Industrial Safety Agency (NISA) ···································································· 8-3 8.4 Organization related to NISA ······························································································ 8-6 8.5 The NSC ······························································································································ 8-7 8.6 The AEC ······························································································································ 8-9 8.7 Other Administrative Bodies ······························································································· 8-9 Article 9 Responsibility of Licensee ·························································································· 9-1 9.1 Regulatory Measures for the Licensee to take the Prime Responsibility ···························· 9-1 9.2 Supervision of Licensees by Regulatory Body ··································································· 9-2 9.3 Communication with Licensees ·························································································· 9-4 C. General Safety Considerations Article 10 Priority to Safety ····································································································· 10-1 10.1 Basic Policy for Priority to Safety ····················································································· 10-1 10.2 Efforts for Improvement in Safety Culture ········································································ 10-2 i Article 11 Financial and Human Resources ··········································································· 11-1 11.1 Financial Resources of the Licensee ················································································· 11-1 11.2 Human Resources concerning the Nuclear Installation of the Licensee ··························· 11-2 11.3 Efforts for Ensuring Infrastructure of Human Resources in the Regulatory Bodies ········· 11-4 11.4 Maintaining Human Resources in Nuclear Fields in Japan ··············································· 11-5 Article 12 Human Factors ········································································································ 12-1 12.1 Efforts by Regulatory Body ······························································································· 12-1 12.2 Efforts by Licensee ············································································································ 12-4 Article 13 Quality Assurance ··································································································· 13-1 13.1 Legislative Framework for QA of Nuclear Installation ····················································· 13-1 13.2 Verification of Quality Assurance by Nuclear and Industrial Safety Agency ··················· 13-2 13.3 Implementation and Evaluation of QA Program by Licensee ··········································· 13-4 Article 14 Assessment and Verification of Safety ·································································· 14-1 14.1 Safety Assessment prior to Construction ··········································································· 14-2 14.2 Assessment and Verification of Safety Prior to the Commissioning ································· 14-3 14.3 Assessment and Verification of Safety during Operating Life Time ································· 14-5 14.4 Utilization of Probabilistic Safety Assessment in Regulation ··········································· 14-8 14.5 Assessment of Seismic Safety ························································································· 14-12 14.6 Promotion of Nuclear Safety Research ············································································ 14-14 Article 15 Radiation Protection ······························································································· 15-1 15.1 Summary of Laws and Requirements on Radiation Protection ········································· 15-1 15.2 Laws and Requirements and Response of Licensees ························································ 15-3 15.3 Regulatory Control Activities ···························································································· 15-8 Article 16 Emergency Preparedness ······················································································· 16-1 16.1 Development of Laws and Rules for Nuclear Emergency Preparedness ·························· 16-1 16.2 Nuclear Emergency Preparedness and the Measures ························································ 16-4 16.3 Implementation of Nuclear Emergency Drill ···································································· 16-7 16.4 International Framework and Relationship with Neighboring Countries ·························· 16-9 ii D. Safety of Installations Article 17 Siting ······················································································································· 17-1 17.1 Basic Concept on the Siting of Nuclear Installations ························································ 17-1 17.2 Principal Assessment System Concerning the Siting of Commercial Power Reactors ····· 17-1 17.3 Evaluation to Events Caused by External Factor ······························································ 17-2 17.4 Evaluation for the Impacts to the Public of Accidents ······················································ 17-3 17.5 Environmental Impact Assessment ····················································································17-4 17.6 Re-evaluation of Site Related Factors ··············································································· 17-5 17.7 Arrangements with Neighboring Countries on Safety Impact of Nuclear Installations ···· 17-5 Article 18 Design and Construction ························································································ 18-1 18.1 Review at the Design and Construction Stage of Nuclear Installations ···························· 18-1 18.2 Realization of Defense in Depth and Confinement of Radioactive Materials at the Design and Construction Stage ······················································································································ 18-2 18.3 Systems for preventing the occurrence of abnormalities and for mitigating the impact of abnormalities (Regulatory Guide for Reviewing Classification of Importance of Safety Functions for Light Water Nuclear Power Reactor Facilities) ··········································································· 18-4 18.4 Safety Design Assessment ································································································· 18-6 18.5 New Regulatory Guide for Reviewing Seismic Design of Nuclear Power Reactor Facilities ············································································································································· 18-7 18.6 Preparation of Accident Management Measures ····························································· 18-10 18.7 Measures to Ensure the Technical Reliability by Experience, Test and Analysis ············ 18-11 18.8 Consideration of Human Factors and Man-Machine Interface ······································· 18-13 Article 19 Operation ················································································································· 19-1 19.1 Initial License ···················································································································· 19-2 19.2 Limiting Conditions for Operation ···················································································· 19-2 19.3 Regulations for Operation, Maintenance, Inspection and Testing ····································· 19-2 19.4 Response to Accidents and Anticipated Operational