Document: NUREG-0800
Document ID: 0c95c042-addf-4bad-84f5-1d1692769268
Document Type: srp
Title: CONCRETE AND STEEL INTERNAL STRUCTURES OF STEEL OR CONCRETE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550052.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.3
CFR Part: 
CFR Title: 

Content:
he referenced regulatory guides. 3.8.3-35 Revision 2 - March 2007 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, 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 Basis.” 6. 10 CFR Part 50, Appendix A, General Design Criterion 5, “Sharing of Structures, Systems, and Components.” 7. 10 CFR Part 50, Appendix A, General Design Criterion 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.” 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,” American Society of Mechanical Engineers. 14. ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NE, “Class MC Components,” American Society of Mechanical Engineers. 15. NUREG/CR-6486, “Assessment of Modular Construction for Safety-Related Structures at Advanced Nuclear Power Plants,” March 1997. 16. Regulatory Guide 1.57, “Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components.” 3.8.3-36 Revision 2 -