Document: NUREG-0800
Document ID: a09b1666-b289-4ea9-9e8f-3ee5fbd5bf41
Document Type: srp
Title: CONCRETE AND STEEL INTERNAL STRUCTURES OF STEEL OR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1319/ML13198A250.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.3
CFR Part: 
CFR Title: 

Content:
l 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. VI. REFERENCES 1. 10 CFR 50.55a, “Codes and Standards.” 2. 10 CFR 50.65, “Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.” 3. 10 CFR Part 50, Appendix A, GDC 1, “Quality Standards and Records.” 4. 10 CFR Part 50, Appendix A, GDC 2, “Design Bases for Protection Against Natural Phenomena.” 5. 10 CFR Part 50, Appendix A, GDC 4, “Environmental and Dynamic Effects Design Basis.” 6. 10 CFR Part 50, Appendix A, GDC 5, “Sharing of Structures, Systems, and Components.” 7. 10 CFR Part 50, Appendix A, GDC 50, “Containment Design Bases.” 8. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.” 9. 10 CFR Part 50, Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants.” 3.8.3-37 Revision 4 – September 2013 10. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.” 11. ACI 349, “Code Requirements for Nuclear Safety Related Concrete Structures,” American Concrete Institute. 12. ANSI/AISC N690-1994 including Supplement 2 (2004), “Specification for Design, Fabrication and Erection of Steel Safety-Related Structures for Nuclear Facilities.” 13. ASME Boiler and Pressure Vessel Code, Section III, Division 2, Subsection CC, “Code for Concrete Reactor Vessels and Containments,” ASME. 14. ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NE, “Class MC Components,” ASME. 15. NUREG/CR-6486, “Assessment of Modular Construction for Safety-Related Structures at Advanced Nuclear Power Plants,” March 1997. 16. RG 1.57, “Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components.” 17. RG 1.69, “Concrete Radiation Shields for Nuclear