Document: NUREG-0800
Document ID: e708512f-f35c-453e-9fc1-354ab0bf12ad
Document Type: srp
Title: STEEL CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550050.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.2
CFR Part: 
CFR Title: 

Content:
schedules for conformance to parts of the method discussed herein. VI. REFERENCES 1. American Society of Mechanical Engineers. Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NE, “Class MC Components,” ASME. 2. American Society of Mechanical Engineers. Boiler and Pressure Vessel Code, Section XI, Subsection IWE, “Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Plants,” ASME. 3. Regulatory Guide 1.7, “Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident.” 4. Regulatory Guide 1.57, “Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components.” 5. Regulatory Guide 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants.” 6. Regulatory Guide 1.84, “Design, Fabrication, and Materials Code Case Acceptability, ASME Section III.” 3.8.2-28 Revision 2 - March 2007 7. Regulatory Guide 1.147, “Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1.” 8. Regulatory Guide 1.193, “ASME Code Cases Not Approved for Use.” 9. 10 CFR Part 50, Appendix A, General Design Criterion 1, “Quality Standard and Records.” 10. 10 CFR Part 50, Appendix A, General Design Criterion 2, “Design Bases for Protection Against Natural Phenomena.” 11. 10 CFR Part 50, Appendix A, General Design Criterion 4, “Environmental and Dynamic Effects Design Bases.” 12. 10 CFR Part 50, Appendix A, General Design Criterion 16, “Containment Design.” 13. 10 CFR Part 50, Appendix A, General Design Criterion 50, “Containment Design Basis.” 14. 10 CFR Part 50, Appendix J, “Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.” 15. 10 CFR Part 50, Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants." 16. 10 CFR 50.34, “Contents of Application; Technical Requirements.” 17. 10 CFR 50.44, “Combustible Gas Control for Nuclear Power