Format and Content of the Safety Analysis Report for Nuclear Power Plants  
Specific Safety Guide
Published by International Atomic Energy Agency
Publication Date:  Available in all formats
ISBN: 9789201173201
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This Safety Guide provides recommendations on the structure and content of the safety analysis report to be submitted by the operating organization to the regulatory body for authorization of the siting, construction, commissioning, operation and decommissioning of a nuclear power plant. It is intended to facilitate both the development of the safety analysis report by the operating organization and the checking of its completeness and adequacy by the regulatory body. The publication is a revision of IAEA Safety Standards Series No. GS-G-4.1, Format and Content of the Safety Analysis Report for Nuclear Power Plants, which it supersedes. The revision reflects feedback experience from the Fukushima Daiichi accident and the subsequent stress tests performed. It also describes good practices and experience from the use of safety analysis reports for newly built nuclear power plants in different States and informs on recent progress made in approaches to safety assessment.
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Description
This Safety Guide provides recommendations on the structure and content of the safety analysis report to be submitted by the operating organization to the regulatory body for authorization of the siting, construction, commissioning, operation and decommissioning of a nuclear power plant. It is intended to facilitate both the development of the safety analysis report by the operating organization and the checking of its completeness and adequacy by the regulatory body. The publication is a revision of IAEA Safety Standards Series No. GS-G-4.1, Format and Content of the Safety Analysis Report for Nuclear Power Plants, which it supersedes. The revision reflects feedback experience from the Fukushima Daiichi accident and the subsequent stress tests performed. It also describes good practices and experience from the use of safety analysis reports for newly built nuclear power plants in different States and informs on recent progress made in approaches to safety assessment.
Table of contents
  • 1. Introduction
    • Background
    • Objective
    • Scope
    • Structure
  • 2. General considerations
    • Role of the safety analysis report
    • Safety rules of different origins
    • Structure of the safety analysis report for various stages of the lifetime of a nuclear power plant
    • Structure of the safety analysis report
    • Unified description of the design of plant structures, systems and components
    • Use, review and updating of the safety analysis report during plant operation
    • Formal aspects regarding the documentation of the safety analysis report
    • Relationship of the safety analysis report to other licensing documents
    • Treatment of sensitive information
    • Structure of the safety analysis report for different types of nuclear installation
  • 3. Content and structure of individual chapters of the safety analysis report
    • Chapter 1: Introduction and general considerations
      • Introduction
      • Project implementation
      • Identification of interested parties regarding design, construction and operation
      • Information on the plant layout and other aspects
      • General plant description
      • Comparison with other plant designs
      • Drawings and other more detailed information
      • Modes of normal operation of the plant
      • Principles of safety management
      • Additional supporting or complementary documents to the safety analysis report
      • Conformance with applicable regulations, codes and standards
    • Chapter 2: Site characteristics
      • Geography and demography
      • Evaluation of site specific hazards
      • Proximity of industrial, transportation and other facilities
      • Activities at the plant site that might influence the safety of the plant
      • Hydrology
      • Meteorology
      • Geology, seismology and geotechnical engineering
      • Site characteristics and the potential effects of the nuclear power plant in the region
      • Radiological conditions due to external sources
      • Site related issues in emergency preparedness and accident management
      • Monitoring of site related parameters
    • Chapter 3: Safety objectives and design rules for structures, systems and components
      • General safety design basis
      • Classification of structures, systems and components
      • Protection against external hazards
      • Protection against internal hazards
      • General design aspects for civil engineering works of safety classified buildings and civil engineering structures
      • General design aspects for mechanical systems and components
      • General design aspects for instrumentation and control systems and components
      • General design aspects for electrical systems and components
      • Equipment qualification
      • In-service monitoring, tests, maintenance and inspections
      • Compliance with national and international standards
    • Chapter 4: Reactor
      • Summary description
      • Fuel design
      • Nuclear design
      • Thermohydraulic design
      • Design of the reactor control, shutdown and monitoring systems
      • Evaluation of the combined performance of reactivity control systems
      • Core components
    • Chapter 5: Reactor coolant system and associated systems
      • Summary description
      • Materials
      • Reactor coolant system and reactor coolant pressure boundary
      • Reactor vessel
      • Reactor coolant pumps or recirculation pumps
      • Primary heat exchangers (steam generators) in pressurized water reactors
      • Reactor coolant piping
      • Reactor pressure control system
      • Reactor coolant system component supports and restraints
      • Reactor coolant system and connected system valves
      • Access and equipment requirements for in-service inspection and maintenance
      • Reactor auxiliary systems
    • Chapter 6: Engineered safety features
      • Emergency core cooling systems and residual heat removal systems
      • Emergency reactivity control system
      • Safety features for stabilization of the molten core
      • Containment and associated systems
      • Habitability systems
      • Systems for the removal and control of fission products
      • Other engineered safety features
    • Chapter 7: Instrumentation and control
      • Description of the instrumentation and control system
      • Design basis, overall architecture and functional allocation of the instrumentation and control system
      • General design considerations for instrumentation and control systems
      • Control systems important to safety
      • Reactor protection system
      • Actuation systems for engineered safety features
      • Systems required for safe shutdown
      • Information systems important to safety
      • Interlock systems important to safety
      • Diverse actuation system
      • Data communication systems
      • Instrumentation and control in the main control room
      • Instrumentation and control in supplementary control rooms
      • Emergency response facilities
      • Automatic control systems not important to safety
      • Digital instrumentation and control systems
      • Hazard analysis for instrumentation and control systems
    • Chapter 8: Electrical power
      • Description of the electrical power system
      • General principles and design approach
      • Electrical equipment, cables and raceways
      • Grounding, lightning protection and electromagnetic compatibility
    • Chapter 9: Auxiliary systems and civil structures
    • Chapter 9A: Auxiliary systems
      • Fuel storage and handling systems
      • Water systems
      • Process and post-accident sampling systems
      • Air and gas systems
      • Heating, ventilation and air-conditioning systems
      • Fire protection systems
      • Supporting systems for diesel generators or for gas turbine generators
      • Overhead lifting equipment
      • Miscellaneous auxiliary systems
    • Chapter 9B: Civil engineering works and structures
      • Foundations and buried structures
      • Reactor building
      • Other structures
    • Chapter 10: Steam and power conversion systems
      • Role and general description
      • Main steam supply system
      • Feedwater systems
      • Turbine generator
      • Turbine and condenser systems
      • Steam generator blowdown processing system
      • Implementation of break preclusion for the main steam and feedwater lines
    • Chapter 11: Management of radioactive waste
      • Sources of waste
      • Systems for management of liquid radioactive waste
      • Systems for management of gaseous radioactive waste
      • Systems for management of solid radioactive waste
      • Process and effluent radiological monitoring and sampling systems, including on-site and off-site monitoring
    • Chapter 12: Radiation protection
      • Optimization of protection and safety
      • Sources of radiation
      • Design features for radiation protection
      • Dose constraints and dose assessment
      • Radiation protection programme
    • Chapter 13: Conduct of operations
      • Organizational structure of the operating organization
      • Training
      • Implementation of the operational safety programme
      • Plant procedures and guidelines
      • Nuclear safety and nuclear security interfaces
    • Chapter 14: Plant construction and commissioning
      • Specific information to be included in the safety analysis report prior to construction
      • Specific information to be included in the safety analysis report prior to commissioning
    • Chapter 15: Safety analysis
      • General considerations
      • Identification, categorization and grouping of postulated initiating events and accident scenarios
      • Safety objectives and acceptance criteria
      • Human actions
      • Deterministic safety analyses
      • Analysis of internal and external hazards
      • Probabilistic safety assessment
      • Summary of results of the safety analyses
    • Chapter 16: Operational limits and conditions for safe operation
      • Scope and application
      • Bases for development
      • Safety limits
      • Requirements for limits and conditions for normal operation, surveillance and testing
      • Administrative requirements
    • Chapter 17: Management for safety
      • General characteristics of the management system
      • Specific elements of the management system
      • Quality management
      • Measurement, assessment and improvement of the management system
      • Fostering a culture for safety
    • Chapter 18: Human factors engineering
      • Management of the human factors engineering programme
      • Human factors engineering analysis
      • Design of the human–machine interface
      • Verification and validation of human factors engineering analysis results
      • Design implementation
      • Human performance monitoring
    • Chapter 19. Emergency preparedness and response
      • Arrangements for performing functions essential for the emergency response
      • Emergency response facilities
      • Capability of the operating organization to assess potential radioactive releases in accident conditions
      • Emergency preparedness for multiple unit sites
    • Chapter 20: Environmental aspects
      • General aspects of the environmental impact assessment
      • Site characteristics that are important in terms of environmental impact
      • Plant features that minimize the environmental impact
      • Environmental impact of construction
      • Environmental impact of normal operation
      • Environmental impact of postulated accidents involving radioactive releases
      • Environmental impact of plant decommissioning
      • Environmental measurements and monitoring programmes
      • Records of radioactive releases and availability of information to the authorities and the public
    • Chapter 21: Decommissioning and end of life aspects
      • General principles and regulations
      • Decommissioning strategy
      • Facilitating decommissioning during design and operation
      • Decommissioning plan
      • Provisions for safety during decommissioning
      • End of life aspects of the decommissioned site
  • Appendix I DEVELOPMENT OF THE SAFETY ANALYSIS REPORT IN DIFFERENT LICENSING STAGES
  • Appendix II STANDARIZED FORMAT TO DESCRIBE THE DESIGN OF STRUCTURES, SYSTEMS AND COMPONENTS AND PLANT EQUIPMENT
    • Functions of each structure, system and component, and item of equipment
      • Design basis
      • Description of the structure, system or component
      • Materials
      • Interfaces with other equipment or systems
      • System, component or equipment operation
      • Instrumentation and control
      • Monitoring, inspection, testing and maintenance
      • Radiation protection aspects
      • Performance and safety assessment
  • REFERENCES
  • Annex TYPICAL TABLE OF CONTENTS OF A SAFETY ANALYSIS REPORT
  • CONTRIBUTORS TO DRAFTING AND REVIEW
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