Document: NUREG-0800
Document ID: 632e6c59-03bd-4648-b0b3-e8b2efd6fa04
Document Type: srp
Title: CONTAINMENT ISOLATION SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070380197.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.4
CFR Part: 
CFR Title: 

Content:
a station blackout. 4. 10 CFR Part 50, Appendix A, GDC 1, "Quality Standards and Records." 5. 10 CFR Part 50, Appendix A, GDC 2, "Design Bases for Protection Against Natural Phenomena." 6. 10 CFR Part 50, Appendix A, GDC 4, "Environmental and Missile Design Basis." 7. 10 CFR Part 50, Appendix A, GDC 16, "Containment Design." 8. 10 CFR Part 50, Appendix A, GDC 54, "Piping Systems Penetrating Containment." 9. 10 CFR Part 50, Appendix A, GDC 55, "Reactor Coolant Pressure Boundary Penetrating Containment." 10. 10 CFR Part 50, Appendix A, GDC 56, "Primary Containment Isolation." 11. 10 CFR Part 50, Appendix A, GDC 57, "Closed System Isolation Valves." 12. 10 CFR Part 50, Appendix K, "ECCS Evaluation Models." 13. 10 CFR Part 100, "Reactor Site Criteria." 14. RG 1.11, "Instrument Lines Penetrating Primary Reactor Containment." 15. RG 1.26, "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants." 16. RG 1.29, "Seismic Design Classification." 6.2.4-18 Revision 3 - March 2007 17. RG 1.141, "Containment Isolation Provisions for Fluid Systems." 18. RG 1.155, "Station Blackout." 19. BTP 6-4, "Containment Purging During Normal Plant Operations." 20. NUREG-0737, "Clarification of TMI Action Plan Requirements." 21. NUREG-0718, "Licensing Requirements for Pending Application for Construction Permits and Manufacturing License." 22. NUREG-1449, "Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the United States," Final Report, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, September 1993. 23. NRC Generic Letter 83-02, "NUREG-0737 Technical Specifications," January 10, 1983. 24. NRC Letter to all Holders of Operating Licenses and Construction Permits for Pressurized Water Reactors (PWRs), “Loss of Decay Heat Removal (Generic Letter 88-17),” October 17, 1988. 25. Item II.E.4.2, "Containment Isolation Dependability," in NUREG-0737 and NUREG-0718. PAPERWORK