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Convention on Nuclear Safety National Report of Japan for the Third Review Meeting

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Convention on Nuclear Safety National Report of Japan for the Third Review Meeting Provisional Translation Convention on Nuclear Safety National Report of Japan for the Third Review Meeting August 2004 Government of Japan 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 Major Events in the Existing Nuclear Installations after the Previous Report………….. 6-2 6.3 Evaluation and Verification of Safety, and Position as to Continued Operation………... 6-3 B. Legislation and Regulation Article 7 Legislative and Regulatory Framework…………………………………………. 7-1 7.1 Basic Legislation Governing the Utilization of Nuclear Energy………………………... 7-1 7.2 Legislations and Regulations Governing the Safety of Nuclear Installations…………... 7-2 7.3 Legislative Regulatory Framework at Each Stage………………………………………. 7-5 7.4 Enforcement of Applicable Regulations and Terms of License…………………………. 7-7 Article 8 Regulatory Body…………………………………………………………………… 8-1 8.1 Mandate and Duties of Regulatory Body………………………………………………... 8-1 8.2 Organizations for Enforcement of Safety Regulation of Nuclear Installations…………. 8-2 8.3 Nuclear and Industrial Safety Agency (NISA)………………………………………….. 8-2 8.4 Organization related to NISA…………………………………………………………… 8-5 8.5 The Nuclear Safety Commission (the NSC)…………………………………………….. 8-6 8.6 The Atomic Energy Commission (the AEC)…………………………………………….. 8-7 8.7 Other Administrative Bodies…………………………………………………………….. 8-8 Article 9 Responsibility of the License Holder……………………………………………… 9-1 9.1 Regulatory measures for the license holder to take the prime responsibility for the 9-1 safety of nuclear installations……………………………………………………………. 9.2 Supervision of the License Holders by Regulatory Body……………………………….. 9-1 C. General Safety Considerations Article 10 Basic Policy for Priority to Safety………………………………………………. 10-1 10.1 Basic Policy for Priority to Safety………………………………………………………. 10-1 10.2 Efforts for Improvement in Safety Culture……………………………………………… 10-1 i Article 11 Financial and Human Resources………………………………………………... 11-1 11.1 Financial Resources of the License Holder……………………………………………... 11-1 11.2 Human Resources of the License Holder………………………………………………... 11-1 11.3 Efforts for Ensuring Infrastructure of Human Resources in Japan……………………… 11-2 Article 12 Human Factors…………………………………………………………………… 12-1 12.1 Efforts by Regulatory Body……………………………………………………………... 12-1 12.2 Efforts by License Holders……………………………………………………………… 12-2 Article 13 Quality Assurance………………………………………………………………... 13-1 13.1 Regulatory Requirements for QA of Nuclear Installation………………………………. 13-1 13.2 Confirmation of QA by Regulatory Body……………………………………………….. 13-2 13.3 Implementation and Assessment of QA Program by License Holders………………….. 13-2 Article 14 Assessment and Verification of Safety…………………………………………... 14-1 14.1 Assessment and Verification of Safety Prior to Construction…………………………… 14-1 14.2 Assessment and Verification of Safety Prior to the Commissioning……………………. 14-3 14.3 Assessment and Verification of Safety during Operating Life Time……………………. 14-4 14.4 Probabilistic Approach in Regulation…………………………………………………… 14-6 14.5 Introduction of Safety Goals…………………………………………………………….. 14-7 14.6 Activities for Introduction of the Safety Regulation with Utilization of Risk Information……………………………………………………………………………… 14-9 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 License Holders.............................................. 15-2 15.3 Regulatory Control Activities…………………………………………………………… 15-6 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…………………………………… 16-2 16.3 Implementation of Nuclear Emergency Drill…………………………………………… 16-4 16.4 International Framework and Relationship with Neighboring Countries………………. 16-6 ii D. Safety of Installations Article 17 Siting………………………………………………………………………………. 17-1 17.1 Basic Concept on the Siting of Nuclear Facilities………………………………………. 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 Facilities……. 17-5 Article 18 Design and Construction………………………………………………………… 18-1 18.1 Licensing Process at the Design and Construction Stages of Nuclear Facilities………... 18-1 18.2 Realization of Defense with Multiple Steps and Methods (Defense in Depth) and Confinement of Radioactive Materials at Design and Construction Stages…………….. 18-1 18.3 Prevention of Accidents and their Mitigation Systems (Regulatory Guide for Reviewing Classification of Importance of Safety Functions for Light Water Nuclear Power Reactor Facilities)………………………………………………………………... 18-3 18.4 Preparation of Accident Management Policy…………………………………………… 18-4 18.5 Measures to Ensure the Technical Reliability by Experience, Test and Analysis………. 18-5 18.6 Consideration of Human Factors and the Man-Machine Interface……………………… 18-7 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 Occurrences……………………… 19-4 19.5 Engineering and Technical Support: Application of the Results of Research and Development…………………………………………………………………………….. 19-4 19.6 Reporting of Incidents…………………………………………………………………… 19-5 19.7 Collection, Utilization and Sharing of Operating Experience Information……………... 19-6 19.8 Management of Spent Fuel and Radioactive Waste……………………………………... 19-6 Annexes iii Acronym and Abbreviation Used in this Report ABWR advanced boiling water reactor ACNRE Advisory Committee for Natural Resources and Energy AEC Atomic Energy Commission AESJ Atomic Energy Society of Japan ALARA as low as reasonably achievable AOT Allowed Out of Service Times ABWR Advanced boiling water reactor APWR advanced pressurized water reactor ASCOT Assessment of Safety Culture in Organizations Team BSS Basic Safety Standards BTC BWR Operation Training Center BWR boiling water reactor Dose Limit Notification Notification for Dose Limits on the basis of the Rules for Commercial Power Reactors EIS Environmental Impact Statement Regulatory Guide for Regulatory Guide for Reviewing Safety Design of Light Water Safety Design Nuclear Power Reactor Facilities Regulatory Guide for Regulatory Guide for Reviewing Safety Assessment of Light Reviewing Safety Water Nuclear Power Reactor Facilities Assessment Regulatory Guide for Regulatory Guide for Reviewing Seismic Design of Nuclear Reviewing Seismic Power Reactor Facilities etc Design Regulatory Guide for Regulatory Guide for Reviewing Nuclear Reactor Siting Reactor Siting Evaluation and Application Criteria Fugen heavy water moderated boiling light water cooled reactor owned by JNC FY Fiscal Year IAEA International Atomic Energy Agency ICRP International Commission on Radiological Protection INES International Nuclear Event Scale INPO Institute of Nuclear Power Operations ISO International Standards Organization JAERI Japan Atomic Energy Research Institute JAPEIC Japan Power Engineering and Inspection Corporation iv JCO Criticality Accident Criticality Accident at JCO Co. Uranium Fuel Fabrication Facility JEA Japan Electric Association JEAC(G) Japan Electric Association Code (Guideline) JNC Japan Nuclear Cycle Development Institute JPDR Japan Power Demonstration Reactor JSME Japan Society of Mechanical Engineers LCO Limiting Conditions for Operation METI Ministry of Economy, Trade and Industry Minister of METI Minister of Economy, Trade and Industry MEXT Ministry of Education, Culture, Sports, Science and Technology Minister of MEXT Minister of Education, Culture, Sports, Science and Technology MITI Ministry of International Trade and Industry (METI at present) Mj Japan Meteorological Agency seismic intensity scale MLIT Ministry of land , Infrastructure and Transportation Monju prototype fast breeder reactor owned by JNC MOX Mix Oxide NISA Nuclear and Industrial Safety Agency NPS nuclear power station NSC Nuclear Safety Commission NS Network Nuclear Safety Network NSRR Nuclear Safety Research Reactor NTC Nuclear Power Training Center NUPEC Nuclear Power Engineering Corporation NUSS Nuclear Safety Standards, IAEA OECD/NEA Organization of Economic Co-operation and Development/Nuclear Energy Agency OSART Operational Safety Assessment Review Team PSA probabilistic safety assessment PSR periodic safety review PWR pressurized water reactor QA quality assurance Reactor Regulation Law Law for the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors v R & D reactor Power reactors at the stage of research and development RHRS Residual Heat Removal System RPS Reactor Protection System SCL Steam Condensation Line SSC Structures, Systems and Components STS Standard Technical Specifications Special Law for Nuclear Special Law of Emergency Preparedness for Nuclear Emergency Disaster TEPCO Tokyo Electric Power Company TNS Thermal
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