Document: NUREG-0800
Document ID: 2cb61281-91f4-400a-8eda-41e187e51d77
Document Type: srp
Title: AUXILIARY FEEDWATER SYSTEM (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070570007.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.4.9
CFR Part: 
CFR Title: 

Content:
ulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section, unless superceded by a later revision. VI. REFERENCES 1. 10 CFR 50.62, "Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water nuclear power plants." 2. 10 CFR 50.63, "Loss of all alternating current power." 3. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena." 4. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Dynamic Effects Design Bases." 5. 10 CFR Part 50, Appendix A, General Design Criterion 5, "Sharing of Structures, Systems, and Components." 6. 10 CFR Part 50, Appendix A, General Design Criterion 19, "Control Room." 7. 10 CFR Part 50, Appendix A, General Design Criterion 34, "Residual Heat Removal." 8. 10 CFR Part 50, Appendix A, General Design Criterion 44, "Cooling Water." 9. 10 CFR Part 50, Appendix A, General Design Criterion 45, "Inspection of Cooling Water System." 10. 10 CFR Part 50, Appendix A, General Design Criterion 46, "Testing of Cooling Water System." 11. Regulatory Guide 1.102, “Flood Protection for Nuclear Power Plants.” 12. Regulatory Guide 1.117, “Tornado Design Classification.” 13. Regulatory Guide 1.155, "Station Blackout." 14. Regulatory Guide 1.29, "Seismic Design Classification." 10.4.9-17 Revision 3 - March 2007 15. Regulatory Guide 1.59, “Design Basis Floods for Nuclear Power Plants.” 16. Regulatory Guide 1.62, "Manual Initiation of Protective Actions." 17. Regulatory Guide 1.76, “Design Basis Tornado for Nuclear Power Plants.” 18. Branch Technical Position 5-4, "Design Requirements of the Residual Heat Removal System". 19. Branch Technical Position 10-1, "Design Guidelines for Auxiliary Feedwater System Pump Drive and Power Supply