Safety Analysis and Licensing Documentation for Nuclear Fuel Cycle Facilities

Description based upon print version of record.

Includes bibliographies and index.

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

Annex I FACTORS AFFECTING THE APPLICATION OF A GRADED APPROACH AND AREAS SUBJECTED TO GRADING IN SAFETY ANALYSIS OF NUCLEAR FUEL CYCLE FACILITIES

COPYRIGHT NOT covered - Click this link to request copyright permission:

https://lib.ciu.edu/copyright-request-form