Document: NUREG-0800
Document ID: c447d6bd-a500-4e1a-acf0-d819cc4f0e41
Document Type: srp
Title: FOUNDATIONS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550055.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.5
CFR Part: 
CFR Title: 

Content:
ibed herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. The referenced regulatory guides include the implementation schedules for conformance to parts of the method discussed herein. VI. REFERENCES 1. 10 CFR 50.55(a), “Codes and Standards.” 2. 10 CFR 50.65, “Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.” 3. 10 CFR Part 50, Appendix A, General Design Criterion 1, “Quality Standards and Records.” 4. 10 CFR Part 50, Appendix A, General Design Criterion 2, “Design Bases for Protection Against Natural Phenomena.” 5. 10 CFR Part 50, Appendix A, General Design Criterion 4, “Environmental and Dynamic Effects Design Bases.” 6. 10 CFR Part 50, Appendix A, General Design Criterion 5, “Sharing of Structures, Systems and Components.” 7. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.” 8. 10 CFR Part 50, Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants.” 9. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.” 10. American Concrete Institute, ACI 349, “Code Requirements for Nuclear Safety-Related Concrete Structures.” 11. ANSI/AISC N690-1994 including Supplement 2 (2004), “Specification for the Design, Fabrication and Erection of Steel Safety-Related Structures for Nuclear Facilities.” 3.8.5-18 Revision 2 - March 2007 12. American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section III, Division 2, “Code for Concrete Reactor Vessels and Containments.” 13. Regulatory Guide 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, LWR Edition.” 14. Regulatory Guide 1.127, “Inspection of Water-Control Structures