Document: NUREG-0800
Document ID: 6fd4d885-bb73-4ac0-9513-7365558c831e
Document Type: srp
Title: REACTOR AUXILIARY COOLING WATER SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550053.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.2.2
CFR Part: 
CFR Title: 

Content:
valuate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. 10 CFR 50.34(f), “Contents of Applications, Technical Information, Additional TMI-Related Requirements.” 2. 10 CFR Part 50, Appendix A, GDC 2, “Design Bases for Protection Against Natural Phenomena.” 3. 10 CFR Part 50, Appendix A, GDC 4, “Environmental and Dynamic Effects Design Bases.” 4. 10 CFR Part 50, Appendix A, GDC 5, “Sharing of Structures, Systems, and Components.” 5. 10 CFR Part 50, Appendix A, GDC 44, “Cooling Water.” 6. 10 CFR Part 50, Appendix A, GDC 45, “Inspection of Cooling Water System.” 7. 10 CFR Part 50, Appendix A, GDC 46, “Testing of Cooling Water System.” 8. RG 1.29, “Seismic Design Classification.” 9. RG 1.153, “Criteria for Power, Instrumentation, and Control Portions of Safety Systems.” 10. RG 1.155, “Station Blackout.” 9.2.2-15 Revision 4 - March 2007 11. Branch Technical Position 3-3, “Protection Against Postulated Piping Failures in Fluid Systems Outside Containment.” 12. NRC Letter to All holders of operating licenses for nuclear power reactors, except for those licenses that have been amended to possession-only status, “Assurance of Equipment Operability And Containment Integrity During Design-Basis Accident Conditions (Generic Letter No. 96-06),” September 30, 1996. 13. NRC Letter to All holders of operating licenses for nuclear power reactors, except for those licenses that have been amended to possession-only status, “Assurance of Equipment Operability And Containment Integrity During Design-Basis Accident Conditions (Generic Letter No. 96-06, Supplement 1),” November 13, 1997. 14. NUREG-0927, Revision 1, “Evaluation of Water Hammer Occurrences in Nuclear Power Plants,” March 1984. 15. IEEE Std 603-1980, “IEEE Standard Criteria for