JNES e-Learning Site for Nuclear Safety Regulators

What′s new? JNES e-learning web site has opened on new URL; http://www.jnes-elearning.org/. Site framework was modified for more easy-understanding. (March 2011)

Nuclear Safety Regulation

Major objectives of the nuclear safety regulation are licensing, inspection and enforcement.
In the Japanese nuclear safety regulation, a two-step approach is taken to start construction of a nuclear power plant, ie. permit for reactor establishment and approval of construction plan. The electric utility cannot start construction of the nuclear power plant until the construction plan is approved by the competent authority. In the reactor establishment permit process, safety review of the basic design of the plant is conducted. After reactor establishment is permitted, structural integrity and construction methods are reviwed during construction plan review process.
Before starting operation of the plant, various inspections are conducted by the Government and its associated organization, JNES, during construction.
This is called "pre-service inspection." Before receiving fuel at the site, the utility must submit a fitness-for-safety program to assure health and safety of the public. The utility cannot start operation of the plant until the fitness-for-safety program is approved by the authority. After the performance of the plant is confirmed through commissioning tests and the performance test results are admitted as satisfactory by the authority, the utility can start commercial operation. As the Japanese regulatory practices, the authority does not issue an operating license. Admission of the performance test results is considered that an operating license was issued.

The Japanese nuclear safety regulation for nuclear power stations and nuclear emergency preparedness and response are described in detail in the following documents:

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Rev. Date Updated R0-r1  March 29,2012  R0-r0  March 15,2011		Nuclear Safety Regulation for Nuclear Power Stations JNESeL-SR-001 R0-r1 1. Outline of Safety Regulation for Nuclear Power Stations 2. Site Selection   2.1 Environmental Review   2.2 Site Evaluation  3. Pre-Construction Phase Regulation   3.1 Permit for Reactor Establishment   3.2 Approval of Construction Plan 4. Construction Phase Regulation   4.1 Pre-Service Inspection   4.2 Approval for Fitness-for-Safety Program 5. Operation Phase Regulation   5.1 Inspections   5.2 Periodic Safety Review (PSR) and Aging Management   5.3 Enforcement
Rev. Date Updated R0-r2  March 26,2012  R0-r0  March 15,2011		Nuclear Emergency Preparedness and Response JNESeL-SR-002 R0-r2 1. System of Nuclear Emergency Preparedness and Response in Japan 2. Special Act of Emergency Preparedness for Nuclear Disaster 3. Nuclear Emergency Response Operations Facility (Off-Site Center) 4. Nuclear Emergency Response Drills and Exercises

Safety Evaluations for Safety Review

The basic design principles and the basic design of a nuclear reactor are reviewed during the establishment permit process. The Act for the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors (so called the Reactor Regulation Act) stipulates that a person who intends to construct a nuclear power reactor facility shall obtain permission from the Minister of Economy, Trade and Industry. This process is called "establishment permit." When constructing a reactor, the electric utility submits an application for establishment permit to the Minister. The establishment of the nuclear power reactor facility is permitted when the application is judged conforming to permission criteria. In the establishment permit process, the authority reviews the safety design and safety analyses of the plant. This process is called "safety review." Safety review is conducted based on the review guides issued by the Nucelar Safety Commission.

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Rev. Date Updated R0-r1  March 26,2012  R0-r0  March 15,2011

Outline of Safety Evaluations for Safety Review JNESeL-SE-001 R0-r1 1. Review Criteria for an Establishment Permit   1.1 Dose Evaluation   1.2 Safety Design Review   1.3 Safety Analysis Review 2. Design and Safety Evaluation During Establishment Permit 3. Seismic Design

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What aspects are dealt with in the establishment permit application and how the authority reviews the application are shown in detail in the following documents:

Rev. Date Updated R0-r1  March 26,2012  R0-r0  March 15,2011		Dose Evaluation JNESeL-SE-002 R0-r1 1. Summary  2. Safety requirements   2.1 Requirements for siting conditions   2.2 Requirements for evaluation of exposure dose during normal operation   2.3 Requirements for safety evaluation   2.4 Requirements for siting evaluation 3. Evaluations to be performed   3.1 Evaluation of exposure dose during normal operation   3.2 Siting evaluation
Rev. Date Updated R0-r1  March 23,2012  R0-r0  March 15,2011		Safety Design JNESeL-SE-003 R0-r1 1. Review Guides for Safety Design    1.1 Fundamentals for Ensuring Safety   1.2 Overview of Safety Review for Establishment Permit 2. Description on the Review Guide for Safety Design   2.1 General Requirements for Nuclear Reactor Facilities   2.2 Reactor and the Reactor Shutdown System   2.3 Reactor Cooling System   2.4 Reactor Containment   2.5 Safety Protection System   2.6 Control Room and Emergency Provisions   2.7 Instrumentation and Control Systems and Electrical Systems   2.8 Fuel Handling Systems   2.9 Radioactive Waste Processing Systems   2.10 Radiation Control
Rev. Date Updated R0-r1  July 12,2011  R0-r0  March 15,2011		Safety Analysis JNESeL-SE-004 R0-r1 1. Requirements   1.1 Basic Requirements   1.2 Specific events to be postulated     (1) Anticipated Operational Transients     (2) Accidents 2. Examples of analysis    2.1 Anticipated Operational Transients      (1) For BWR         (2) For PWR   2.2 Accidents      (1) For BWR         (2) For PWR
Rev. Date Updated R0-r0  March 15,2011		Seismic Safety Evaluation JNESeL-SE-005 R0-r0 1. Lessons Learned in Japan and the new "Regulatory Guide for Reviewing     Seismic Design of Nuclear Power Reactor Facilities (Seismic Guide)" 2. Efforts following the Niigata-Chuetsu Offshore Earthquake

Safety Review Guides

The Nuclear Safety Commission provides guides to be used for reviewing the basic design of the nuclear power plants. Some of the important review guides and a guide for dose objectives are provisionally translated into English by JNES.

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Rev. Date Updated R0-r1  March 30,2012  R0-r0  March 15,2011		List of Safety Review Guides by the Nuclear Safety Commission JNESeL-RG-001 R0-r1 1. Guides   1.1 Guides Concerning Light Water Nuclear Power Reactor Facilities Etc   1.2 Guides Concerning Test and Research Reactors, Fast Breeder         Reactors, Advance Thermal Reactors, Nuclear Ships, Etc.   1.3 Guides Concerning Nuclear Fuel Cycle Facilities   1.4 Guides Concerning Technical Capability 2. Reports of Special Committees, Etc.   2.1 Reports of the Special Committee on Safety Standards of Reactors   2.2 Reports of the Special Committee on the Safety Standards of          Nuclear Fuel   2.3 Reports of the Special Committee for Radioactive Waste          Safety regulation   2.4 By-Law of the Committee on Review of Reactor Safety   2.5 Guides Concerning Emergency Preparedness and Environment
Rev. Date Updated R0-r0  March 15,2011		Review Guide for Nuclear Reactor Siting and Reference Criteria Concerning its Application JNESeL-RG-002 R0-r0 1. Basic principle   1.1 Siting conditions in principle   1.2 Basic objective 2. Guide for siting review   2.1 The area around the reactor of a certain distance from the reactor          must be an exclusion area.   2.2 The zone outside of the exclusion area as well as of a certain distance          from the reactor must be the low population zone (LPZ).   2.3 The reactor site must be a certain distance apart from          the highly populated area. 3. Applicability
Rev. Date Updated R0-r2  March 30,2012  R0-r0  March 15,2011		Review Guide for Safety Design of Light Water Nuclear Power Reactor Facilities JNESeL-RG-003 R0-r2  1. Introduction  2. Position of this Guide and its scope of application  3. Definitions of Terms  4. General Requirements for Nuclear Reactor Facilities  5. Reactor and the Reactor Shutdown System  6. Reactor Cooling System  7. Reactor Containment  8. Safety Protection System  9. Control Room and Emergency Provisions 10. Instrumentation and Control Systems and Electrical Systems 11. Fuel Handling Systems 12. Radioactive Waste Treatment Systems 13. Radiation Control
Rev. Date Updated R0-r0  March 15,2011		Review Guide for Classification of Importance of Safety Functions of Light Water Nuclear Power Reactor Facilities JNESeL-RG-004 R0-r0 1. Objective 2. Position and scope of this Guide 3. Classification of importance of safety functions 4. Principles of classification application 5. Design considerations for structures,      systems and components with safety functions
Rev. Date Updated R0-r0  March 15,2011		Review Guide for Safety Evaluation of Light Water Nuclear Power Reactor Facilities JNESeL-RG-005 R0-r0 1. Introduction 2. Safety Design Evaluation   2.1 Objective of Safety Design Evaluation   2.2 Scope of Evaluation   2.3 Selection of Events for Evaluation   2.4 Criteria   2.5 Considerations in Analysis 3. Siting Evaluation   3.1 Objective of Siting Evaluation   3.2 Scope of Evaluation   3.3 Selection of Events for Evaluation   3.4 Criteria   3.5 Considerations in Analysis
Rev. Date Updated R0-r1  March 26,2012  R0-r0  March 15,2011		Review Guide for Safety Evaluation of Light Water Nuclear Power Reactor Facilities Appendix I JNESeL-RG-005App.I R0-r1 1. Safety Design Evaluation   1.1 Specific events to be evaluated   1.2 Analysis of anticipated operational occurrences   1.3 Analyses of accidents 2. Siting Evaluation   2.1 Specific events of the major accidents and hypothetical accident   2.2 Evaluation of the major accidents and hypothetical accident
Rev. Date Updated R0-r0  March 15,2011		Review Guide for Safety Evaluation of Light Water Nuclear Power Reactor Facilities Appendix II JNESeL-RG-005App.II R0-r0 1. Evaluation of dose equivalent under the "accidents"   1.1 Evaluation of effective dose due to external exposure   1.2 Evaluation of effective dose due to internal exposure 2. Dose evaluation during the "major accidents" and "hypothetical accidents"   2.1 Evaluation of dose to the whole body   2.2 Evaluation of dose to the thyroid gland   2.3 Evaluation of cumulative value of dose to the whole body
Rev. Date Updated R0-r0  March 15,2011		Guide for Dose Objective Around Light Water Nuclear Power Reactor Facilities JNESeL-RG-006 R0-r0 1. Dose Objective 2. Applicability of the Dose Objective
Rev. Date Updated R0-r0  March 15,2011		Meteorological Guide for Safety Analysis of Nuclear Power Reactor Facilities JNESeL-RG-007 R0-r0 I. Objectives  II. Meteorological Measurement Method   1. Purpose and Classification of Meteorological Measurement    2. Measurement Parameters    3. Measurement Method    4. Measurement Period  III. Statistical Processing Method of Measured Values    1. Hourly Meteorological Data    2. Statistical Processing of Meteorological Data  IV. Basic Dispersion Equation  V. Analytical method of atmospheric dispersion during normal operation    1. Concentrations in the air on the ground surface to be used for dose calculation    2. Calculation of yearly average concentration  VI. Analytical method of atmospheric dispersion during a postulated accident    1. Relative concentration to be used for dose calculation    2. Calculation of relative concentration  VII. Effective height of a release source  VIII. Wind tunnel test

Technical Topics

Important technical topics are discussed at this site. Topics are selected from operating and decommissioning phases.

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<For Operating Phase>

Rev. Date Updated R0-r1  March 23,2012  R0-r0  March 15,2011		Fitness-for-Safety Program at Reactor Facility JNESeL-TT-001 R0-r1 1. Protection of Nuclear Safety 2. History of Fitness-for-Safety Rules Revised Since 2001 3. Corresponding of Chapters in Fitness-for-Safety Program to      Requirements 4. Characteristics of Fitness-for-Safety Program 5. PWR Reactor Condition Defined
Rev. Date Updated R0-r0  March 15,2011		Aging Management of Nuclear Power Plant JNESeL-TT-004 R0-r0 1. Status of nuclear power plants in Japan 2. Japanese nuclear safety regulation 3. Management of ageing nuclear plants 4. Ageing phenomena of major components and managements   4.1 Structure of reactor pressure vessel   4.2 Neutron irradiation embrittlement of reactor pressure vessel steel   4.3 Stress corrosion cracking  (SCC)   4.4 Fatigue   4.5 Corrosion   4.6 Reduction in Strength and Reduction in          Radiation Shielding Capability of Concrete   4.7 Insulation Degradation of Electrical and Instrumentation Equipment
Rev. Date Updated R0-r0  March 15,2011		Maintenance Management and New Inspection Program JNESeL-TT-008 R0-r0 1. Previous licensee's maintenance activities and inspections by NISA 2. Enhancement of NISA involvement by adopting inspections based on the Maintenance Program 3. Licensees' specific maintenance activities in the New Inspection Program 4. Aging Management in the New Inspection Program 5. Efforts to improve inspection effectiveness by      comprehensive evaluation of each power plant
Rev. Date Updated R2-r0  December 2011  R0-r0  December 2007		Digital Instrumentation and Control Systems for Safety System and Main Control Room Design JNESeL-TT-005 R2-r0 1. Instrumentation and Control Systems in the Most Advanced       Nuclear Power Plants 2. Digital Safety Protection Systems   2.1 Safety Requirements for Instrumentation and          Control Systems Important to Safety   2.2 Digital Safety Protection Systems in Japan 3. Main Control Room   3.1 Background of Main Control Room Improvement   3.2 Control Room Upgrade in Japan   3.3 The Latest Main Control Room
Rev. Date Updated R0-r1  March 29,2012  R0-r0  March 15,2011		Severe Accident and Accident Management JNESeL-TT-002 R0-r1 1. Severe Accident and Accident Management 2. PSA 3. Accident Management of LWR-Type Nuclear Power Reactor Facilities      in Japan   3.1 Accident Management   3.2 Implementation of Accident Management   3.3 Education, Training and Communication System
Rev. Date Updated R0-r1  March 29,2012  R0-r0  March 15,2011		Probabilistic Safety Assessment(PSA) JNESeL-TT-003 R0-r1 1. Introduction 2. History of Development of PSA Technologies 3. Summary of PSA Technologies 4. PSA Technology Utilization 5. Summary of Level 1 PSA 6. Summary of Level 2 PSA 7. Summary of Level 3 PSA 8. Summary of Seismic PSA 9. Issues in the Near Future

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<For Decommissioning Phase>

Rev. Date Updated R0-r1  March 29,2012  R0-r0  March 15,2011		Safety Regulation on Decommissioning in Japan JNESeL-TT-006 R0-r1 1. History of Safety Regulation on Decommissioning in Japan 2. Points of Safety Regulation System for Decommissioning 3. Features of Nuclear Facility during Decommissioning 4. Issues Pointed Out by the Old Safety Regulation System at the       Decommissioning Phase 5. Overview of the Revised Nuclear Reactor Regulation Law 6. Safety Assessment in Decommissioning Progra 7. Measures for Wastes Arising during Decommissioning 8. Maintenance Status of Related Documents at IAEA
Rev. Date Updated R0-r1  March 30,2012  R0-r0  March 15,2011		Clearance System JNESeL-TT-007 R0-r1 1. CONCEPT OF CLEARANCE 2. DERIVATION OF CLEARANCE LEVELS 3. CLEARANCE REGULATION IN JAPAN 4. METHOD OF JUDGMENT ON CLEARANCE IN JAPAN

Basic Knowledge on LWRs

At this site, you can find brief explanations on light water reactors (LWRs), principles of LWR safety design, and basic aspects that people from the emerging nuclear power countries should know to utilize nuclear energy for peaceful purposes.

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Rev. Date Updated R0-r0  March 15,2011		Risks Associated with Utilization of Nuclear Energy and Radiation and Lessons Learned from Accidents and Disasters JNESeL-BK-001 R0-r0 1. Preface 2. Potential Risks Associated with the Utilization of Nuclear Energy    2.1 Nuclear Energy and Radiation   2.2 What Are the Potential Risks Involved in Utilization of Nuclear Energy?   2.3 Risks and Profits Involved in Utilization of Nuclear Energy   2.4 Effects of Radiological Exposure   2.5 Dose Limits for Radiation Control 3. History of Accidents and Disasters and the Lessons Learned   3.1 Major Accidents at Nuclear Facilities   3.2 Radiation Exposure Accidents Involved in          Radiation Utilization in the World
Rev. Date Updated R0-r0  March 15,2011		Safety Design of Nuclear Power Plants JNESeL-BK-002 R0-r0 1. Introduction 2. Safety Design of Nuclear Power Plants   2.1 Mechanism of nuclear power generation   2.2 Multiple barriers for preventing release of radioactive materials   2.3 Safety facilities of nuclear power plants   2.4 Safety design concept
Rev. Date Updated R0-r0  March 15,2011		The Pressurized Water Reactor JNESeL-BK-003 R0-r0 Part 1 Descriptions of PWRs   1. PWR Development   2. PWR Technologies   3. Power Control of PWR   4. PWRs in the World   5. Features of PWR Part 2. Advance Pressurized Water Reactor   6. Next generation designs
Rev. Date Updated R0-r0  March 15,2011		The Boiling Water Reactor JNESeL-BK-004 R0-r0 Part 1. Descriptions of BWR Power plants   1. BWR Development   2. BWR Technologies   3. Features of BWR Part 2. Advanced BWRs   4. ABWR Development   5. ABWR Technologies   6. Economic Simplified Boiling Water Reactor (ESBWR)   7. Current status

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Documents

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Relevant Links

The site provides you with a list of URLs which give you useful information on a) nuclear safety regulatory agency, b) education and training, c) innovative new plant designs, and d) basic knowledge.

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