Safety Analysis and Licensing Documentation for Nuclear Fuel Cycle Facilities

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Detalles Bibliográficos
Clasificación:Libro Electrónico
Autor principal: IAEA
Formato: Electrónico eBook
Idioma:Inglés
Publicado: Havertown : International Atomic Energy Agency, 2020.
Colección:Safety Reports Ser.
Temas:
Nuclear facilities > Safety measures.
Nuclear facilities > Licenses > Documentation.
Nuclear fuels > Management.
Electronic books.
Acceso en línea:Texto completo
Tabla de Contenidos:
  • Intro
  • 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

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