Document: NUREG-0800
Document ID: 7024eeeb-1819-4d56-9b72-fb63eab3836b
Document Type: srp
Title: and 3.9.3.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1006/ML100620981.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.2
CFR Part: 
CFR Title: 

Content:
Design Basis.@ 6. 10 CFR Part 50, Appendix A, GDC 5, ASharing of Structures, Systems, and Components.@ 7. 10 CFR Part 50, Appendix A, GDC 50, AContainment Design Bases.@ 8. 10 CFR Part 50, Appendix B, AQuality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.@ 9. 10 CFR Part 50, Appendix S, AEarthquake Engineering Criteria for Nuclear Power Plants.@ 10. 10 CFR Part 52, AEarly Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.@ 11. ACI 349, ACode Requirements for Nuclear Safety Related Concrete Structures,@ American Concrete Institute. 12. ANSI/AISC N690-1994 including Supplement 2 (2004), ASpecification 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, ACode for Concrete Reactor Vessels and Containments,@ ASME. 14. ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NE, AClass MC Components,@ ASME. 15. NUREG/CR-6486, AAssessment of Modular Construction for Safety-Related Structures at Advanced Nuclear Power Plants,@ March 1997. 16. RG 1.57, ADesign Limits and Loading Combinations for Metal Primary Reactor Containment System Components.@ 17. RG 1.69, AConcrete Radiation Shields for Nuclear Power Plants.@ 18. RG 1.70, AStandard Format and Content of Safety Analysis Reports for Nuclear Power Plants.@ 3.8.3-33 Revision 3 - May 2010 19. RG 1.136, AMaterials, Construction, and Testing of Concrete Containments.@ 20. RG 1.142, ASafety-Related Concrete Structures for Nuclear Power Plants (other than Reactor Vessels and Containments).@ 21. RG 1.143, ADesign Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants.@ 22. RG 1.160, AMonitoring the Effectiveness of Maintenance at Nuclear Power Plants.@ 23. RG 1.199, AAnchoring Components and Structural Supports in Concrete.@ 24. RG 1.206,