This publication gives practical information and examples of safety analysis principles and methods as well as the contents of licensing documentation needed to support application of IAEA safety standards to nuclear fuel cycle facilities. A systematic methodology is presented, covering the establishment of acceptance criteria, hazard evaluation, identification of postulated initiating events, analysis of accident sequences and consequences. Information is also provided on application of the results of the safety analysis in the design and operational phases, and on appropriate management system processes. The publication applies to all lifetime stages of relevant facilities and for modifications and upgrades. The information presented may be used for periodic safety reviews and consideration of extended lifetime of facilities. With respect to licensing documentation, the publication provides indicative contents and format of the safety analysis report as a higher level document that incorporates the information required at various steps in the licensing and relicensing process.

• 1. INTRODUCTION
  • 1.1. Background
  • 1.2. Objective
  • 1.3. Scope
  • 1.4. Structure
• 2. GENERAL CONSIDERATIONS IN SAFETY ANALYSISOF NUCLEAR FUEL CYCLE FACILITIES
  • 2.1. Purpose of safety analysis
    • 2.1.1. Safety analysis for design
    • 2.1.2. Safety analysis for licensing and periodic safety reviews
    • 2.1.3. Safety analysis supporting emergency planning and accident management
    • 2.1.4. Analysis of operating experience
  • 2.2. Types of safety analysis and computational tools
    • 2.2.1. Types of safety analysis
    • 2.2.2. Calculation tools and data
  • 2.3. Acceptance criteria for safety analysis
  • 2.4. Features of nuclear fuel cycle facilities affecting safety analysis
  • 2.5. Use of a graded approach in safety analysis
• 3. PERFORMING SAFETY ANALYSIS FOR NUCLEAR FUEL CYCLE FACILITIES
  • 3.1. Identification of hazards
    • 3.1.1. Internal hazards
    • 3.1.2. External hazards
  • 3.2. Identification and selection of postulated initiating events
    • 3.2.1. Postulated initiating events
    • 3.2.2. Combination of events
    • 3.2.3. Grouping of events
  • 3.3. Evaluation of event sequences
    • 3.3.1. Modelling the scenario
    • 3.3.2. Identifying physical phenomena and evaluation of associated parameters
    • 3.3.3. Defining boundary and initial conditions
  • 3.4. Analysis of facility states
    • 3.4.1. Anticipated operational occurrences
    • 3.4.2. Design basis accidents
    • 3.4.3. Design extension conditions
  • 3.5. Evaluation of consequences
  • 3.6. Comparison against acceptance criteria
  • 3.7. Presentation of safety analysis and conclusions
    • 3.7.1. Introduction
    • 3.7.2. Facility characteristics
    • 3.7.3. Identification of hazards and selection of PIEs
    • 3.7.4. Evaluation of event sequences
    • 3.7.5. Transient and accident analysis
    • 3.7.6. Summary and conclusions
• 4. APPLICATION OF SAFETY ANALYSIS
  • 4.1. Hazard categorization of the facility
  • 4.2. Safety classification of structures, systems and components
  • 4.3. Derivation of operational limits and conditions
  • 4.4. Modifications
  • 4.5. Ageing management and lifetime extension
  • 4.6. Emergency preparedness and response
• 5. LICENSING DOCUMENTATION
  • 5.1. General considerations
    • 5.1.1. Scope and amount of information in licensing documentation
    • 5.1.2. Types of licensing documentation
    • 5.1.3. Sites with multiple facilities
  • 5.2. Information needed at various steps of the licensing process
    • 5.2.1. Site evaluation
    • 5.2.2. Design and construction
    • 5.2.3. Commissioning
    • 5.2.4. Operation
  • 5.3. Content of the safety analysis report
• 6. MANAGEMENT SYSTEM FOR SAFETY ANALYSIS AND LICENSING DOCUMENTATION
  • 6.1. Management responsibility
  • 6.2. Resource management
  • 6.3. Process implementation
  • 6.4. Measurement, assessment and improvement
• Appendix INDICATIVE CONTENT OF SAFETY ANALYSIS REPORT FOR A NUCLEAR FUEL CYCLE FACILITY
• REFERENCES
• Annex I FACTORS AFFECTING THE APPLICATION OF A GRADED APPROACH AND AREAS SUBJECTED TO GRADING IN SAFETY ANALYSIS OF NUCLEAR FUEL CYCLE FACILITIES
• Annex II EXAMPLES OF FACTORS TO BE CONSIDERED AND TECHNIQUES USED IN HAZARD IDENTIFICATION FOR NUCLEAR FUEL CYCLE FACILITIES
• Annex III SELECTED POSTULATED INITIATING EVENTS FOR NUCLEAR FUEL CYCLE FACILTIES
• Annex IV EXAMPLES OF DESIGN EXTENSION CONDITIONS FOR NUCLEAR FUEL CYCLE FACILITIES
• Annex V EXAMPLES OF RULES FOR SAFETY ANALYSIS FOR NUCLEAR FUEL CYCLE FACILITIES
• Annex VI CONSIDERATIONS AND EXAMPLES OF ITEMS TO BE COVERED BY LIMITING CONDITIONS FOR SAFE OPERATION OF NUCLEAR FUEL CYCLE FACILITIES
• Annex VII EXAMPLES OF DOCUMENTATION TO BE SUBMITTED TO REGULATORY BODY IN VIEW OF LICENSING PROCESS FOR NUCLEAR FUEL CYCLE FACILITIES
• ABBREVIATIONS
• CONTRIBUTORS TO DRAFTING AND REVIEW