Methodologies for Seismic Safety Evaluation of Existing Nuclear Installations.
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Superior document: | Safety Reports Series ; v.103 |
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Place / Publishing House: | Havertown : : International Atomic Energy Agency,, 2020. Ã2020. |
Year of Publication: | 2020 |
Edition: | 1st ed. |
Language: | English |
Series: | Safety Reports Series
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Online Access: | |
Physical Description: | 1 online resource (116 pages) |
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100 | 1 | |a IAEA. | |
245 | 1 | 0 | |a Methodologies for Seismic Safety Evaluation of Existing Nuclear Installations. |
250 | |a 1st ed. | ||
264 | 1 | |a Havertown : |b International Atomic Energy Agency, |c 2020. | |
264 | 4 | |c Ã2020. | |
300 | |a 1 online resource (116 pages) | ||
336 | |a text |b txt |2 rdacontent | ||
337 | |a computer |b c |2 rdamedia | ||
338 | |a online resource |b cr |2 rdacarrier | ||
490 | 1 | |a Safety Reports Series ; |v v.103 | |
505 | 0 | |a 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. | |
505 | 8 | |a 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. | |
588 | |a Description based on publisher supplied metadata and other sources. | ||
590 | |a Electronic reproduction. Ann Arbor, Michigan : ProQuest Ebook Central, 2024. Available via World Wide Web. Access may be limited to ProQuest Ebook Central affiliated libraries. | ||
655 | 4 | |a Electronic books. | |
776 | 0 | 8 | |i Print version: |a IAEA |t Methodologies for Seismic Safety Evaluation of Existing Nuclear Installations |d Havertown : International Atomic Energy Agency,c2020 |
797 | 2 | |a ProQuest (Firm) | |
830 | 0 | |a Safety Reports Series | |
856 | 4 | 0 | |u https://ebookcentral.proquest.com/lib/oeawat/detail.action?docID=6985970 |z Click to View |