TY  - BOOK
AU  - IAEA
TI  - Safety Analysis and Licensing Documentation for Nuclear Fuel Cycle Facilities
T2  - Safety Reports Ser.
SN  - 9201067224
AV  - TK9152 .S244 2020
PY  - 2020///
CY  - Havertown
PB  - International Atomic Energy Agency
KW  - Nuclear facilities
KW  - Safety measures
KW  - Licenses
KW  - Documentation
KW  - Nuclear fuels
KW  - Management
KW  - Electronic Books
N1  - Description based upon print version of record; Annex I FACTORS AFFECTING THE APPLICATION OF A GRADED APPROACH AND AREAS SUBJECTED TO GRADING IN SAFETY ANALYSIS OF NUCLEAR FUEL CYCLE FACILITIES; 2; 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; 2; b
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