Document: NUREG-0800
Document ID: 2768345e-44b7-48d8-bfa7-69652aa4faa8
Document Type: srp
Title: CONCRETE CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1319/ML13198A245.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.1
CFR Part: 
CFR Title: 

Content:
e application must identify and describe all differences between this SRP section and the design features, analytical techniques, and procedural measures proposed for the facility, and discuss how the proposed alternative provides an acceptable method of complying with the regulations that underlie the SRP acceptance criteria. The referenced RGs contain implementation schedules for conformance to parts of the method discussed herein. 3.8.1-26 Revision 4 - September 2013 VI. REFERENCES 1. 10 CFR 50.34, “Contents of Applications; Technical Information.” 2. 10 CFR 50.44, “Combustible Gas Control for Nuclear Power Reactors.” 3. 10 CFR 50.55a, “Codes and Standards.” 4. 10 CFR Part 50, Appendix A, General Design Criterion 1, “Quality Standards and Records.” 5. 10 CFR Part 50, Appendix A, General Design Criterion 2, “Design Bases for Protection Against Natural Phenomena.” 6. 10 CFR Part 50, Appendix A, General Design Criterion 4, “Environmental and Dynamic Effects Design Bases.” 7. 10 CFR Part 50, Appendix A, General Design Criterion 16, “Containment Design.” 8. 10 CFR Part 50, Appendix A, General Design Criterion 50, “Containment Design Basis.” 9. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.” 10. 10 CFR Part 50, Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants.” 11. 10 CFR Part 50, Appendix J, “Primary Reactor Containment Leakage Testing for Water- Cooled Power Reactors.” 12. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.” 13. ASCE 4-98, “Seismic Analysis of Safety-Related Nuclear Structures and Commentary,” American Society of Civil Engineers (Sections 3.1.3 and C3.1.3 for concrete cracking, and Section 3.5.3.2 for embedded walls). 14. ASME Boiler and Pressure Vessel Code, Section III, “Code for Concrete Reactor Vessels and Containments,” Division 2, “Code for