Document: NUREG-0800
Document ID: b172ba61-9651-45f8-ac8e-6d6e00e27060
Document Type: srp
Title: STEEL CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1006/ML100630179.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.2
CFR Part: 
CFR Title: 

Content:
ubmitted 6 months or more after the date of issuance of this SRP section, unless superseded by a later revision. The referenced RGs contain the implementation schedules for conformance to parts of the method discussed herein. VI. REFERENCES 1. ASME, Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NE, AClass MC Components.@ 2. ASME, Boiler and Pressure Vessel Code, Section XI, Subsection IWE, ARequirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Plants.@ 3. RG 1.7, AControl of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident.@ 3.8.2-27 Revision 3 - May 2010 4. RG 1.57, ADesign Limits and Loading Combinations for Metal Primary Reactor Containment System Components.@ 5. RG 1.70, AStandard Format and Content of Safety Analysis Reports for Nuclear Power Plants.@ 6. RG 1.84, ADesign, Fabrication, and Materials Code Case Acceptability, ASME Section III.@ 7. RG 1.147, AInservice Inspection Code Case Acceptability, ASME Section XI, Division 1.@ 8. RG 1.193, AASME Code Cases Not Approved for Use.@ 9. 10 CFR Part 50, Appendix A, GDC 1, AQuality Standard and Records.@ 10. 10 CFR Part 50, Appendix A, GDC 2, ADesign Bases for Protection Against Natural Phenomena.@ 11. 10 CFR Part 50, Appendix A, GDC 4, AEnvironmental and Dynamic Effects Design Bases.@ 12. 10 CFR Part 50, Appendix A, GDC 16, AContainment Design.@ 13. 10 CFR Part 50, Appendix A, GDC 50, AContainment Design Basis.@ 14. 10 CFR Part 50, Appendix J, APrimary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.@ 15. 10 CFR Part 50, Appendix S, AEarthquake Engineering Criteria for Nuclear Power Plants." 16. 10 CFR 50.34, AContents of Application; Technical Requirements.@ 17. 10 CFR 50.44, ACombustible Gas Control for Nuclear Power Reactors.@ 18. 10 CFR 50.55a, ACodes and Standards.@ 19. NUREG/CR-6906, AContainment Integrity Research at Sandia National Laboratories,@ July 2006. 20. SEI/ASCE Standard 37-02, ADesign