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Methodologies for Seismic Safety Evaluation of Existing Nuclear Installations / IAEA.
- Format:
- Book
- Author/Creator:
- International Atomic Energy Agency, author.
- Series:
- Safety reports series ; Volume 103.
- Safety Reports Series ; Volume 103
- Language:
- English
- Subjects (All):
- Earthquake hazard analysis.
- Nuclear facilities.
- Risk assessment.
- Physical Description:
- 1 online resource (116 pages)
- Edition:
- First edition.
- Place of Publication:
- Vienna, Austria : International Atomic Energy Agency, [2020]
- Summary:
- This publication by the International Atomic Energy Agency (IAEA) provides comprehensive methodologies for evaluating the seismic safety of existing nuclear installations. It is based on the IAEA Safety Standard Series No. NS-G-2.13 and incorporates lessons learned from the Fukushima Daiichi nuclear disaster. The report details the processes for assessing seismic hazards, evaluating plant conditions, and determining necessary upgrades or procedural changes. It aims to guide regulatory authorities and nuclear facility operators in ensuring the safety and resilience of nuclear installations against seismic events. The publication is intended for professionals involved in nuclear safety and regulatory compliance. Generated by AI.
- Contents:
- Intro
- 1. INTRODUCTION
- 1.1. Background
- 1.2. Objective
- 1.3. Scope
- 1.4. Structure
- 2. FORMULATION OF THE PROGRAMME FOR SEISMIC SAFETY EVALUATION OF EXISTING Nuclear INSTALLATIONS
- 2.1. Perspective
- 2.1.1. Existing nuclear installations
- 2.1.2. Reasons to perform seismic safety evaluations
- 2.1.3. Margins beyond the design basis for new nuclear installations
- 2.1.4. Margins beyond the design basis for existing nuclear installations
- 2.2. Selection of methodology
- 2.2.1. Seismic probabilistic safety assessment
- 2.2.2. Methodology for seismic margin assessment
- 2.2.3. Design basis re-constitution
- 2.2.4. Selection considerations
- 3. DATA COLLECTION AND INVESTIGATIONs
- 3.1. General
- 3.2. Hazard classification of installations and structures, systems and components
- 3.3. Seismic design basis data
- 3.4. Data collection and documents
- 3.4.1. Site data
- 3.4.2. Assumptions and methods of analysis of existing structures, systems and components
- 3.4.3. Standards and procedures
- 3.4.4. Nuclear installation documentation
- 3.4.5. Data for structures, systems and components
- 3.4.6. Upgrades and nuclear installation modifications
- 3.4.7. Results of other safety evaluations
- 4. ASSESSMENT OF SEISMIC HAZARDS
- 4.1. Probabilistic seismic hazard analysis
- 4.2. Review level earthquake
- 4.2.1. General characteristics of the review level earthquake
- 4.3. Bases for development of the review level earthquake
- 4.3.1. Probabilistic seismic hazard analysis
- 4.3.2. Absence of probabilistic seismic hazard analysis
- 4.3.3. Regulatory specified
- 4.3.4. New nuclear power plants
- 5. SEISMIC SAFETY ASSESSMENT
- 5.1. Seismic margin assessment
- 5.1.1. General
- 5.1.2. Elements of the seismic margin assessment
- 5.1.3. Enhancements
- 5.1.4. Documentation
- 5.2. Seismic probabilistic safety analysis.
- 5.2.1. General
- 5.2.2. Elements of the seismic probabilistic safety assessment
- 5.2.3. Special issues
- 5.3. PSA based seismic safety assessment
- 5.3.1. System and accident sequence analysis
- 5.3.2. Fragility analysis
- 5.4. Off-site seismic induced effects
- 6. MODERATE AND LOW HAZARD INSTALLATIONS
- 6.1. Categorization
- 6.2. Selection of methodology
- 6.3. Review level earthquake
- 6.4. Selection of SSCs to be evaluated
- 6.5. SSC evaluation and walkdown
- 6.6. Seismic margin assessment
- 6.7. Seismic instrumentation
- 7. CONSIDERATIONS FOR UPGRADING
- 7.1. Structure and substructure upgrades
- 7.2. Mechanical and electrical distribution systems and mechanical components upgrades
- 7.2.1. Pressure retaining mechanical distribution systems and components
- 7.2.2. Other mechanical components
- 7.3. Electrical and instrumentation and control components
- 8. MANAGEMENT SYSTEM FOR SEISMIC SAFETY EVALUATION
- 8.1. General
- 8.2. Peer review
- 8.3. Configuration control
- 8.4. Quality assurance
- Appendix I EXAMPLES OF SEISMIC DESIGN CATEGORIES AND SITE FOUNDATION CLASSIFICATION
- Appendix II SUGGESTED DAMPING VALUES AND INELASTIC ENERGY ABSORPTION FACTORS
- Appendix III BACKGROUND AND TERMINOLOGY FOR THE INELASTIC ENERGY ABSORPTION FACTORS
- Appendix IV HYBRID METHOD FOR FRAGILITY CALCULATIONS
- Appendix V TYPICAL WALKDOWN FORMS
- REFERENCES
- DEFINITIONS
- ABBREVIATIONS
- CONTRIBUTORS TO DRAFTING AND REVIEW.
- Notes:
- Description based on publisher supplied metadata and other sources.
- Description based on print version record.
- Part of the metadata in this record was created by AI, based on the text of the resource.
- Includes bibliographical references.
- Other Format:
- Print version: IAEA Methodologies for Seismic Safety Evaluation of Existing Nuclear Installations
- ISBN:
- 9789201060228
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