Document: NUREG-0800
Document ID: 5ba2907e-cf47-4a3b-b320-616735faa4cf
Document Type: srp
Title: AUXILIARY FEEDWATER SYSTEM (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350095.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.4.9
CFR Part: 
CFR Title: 

Content:
licable portions of the protection system and the transfer between normal and emergency buses. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alterna- tive method for complying with specified portions of the Commission's regula- tions, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules for conformance to part of the method discussed herein are contained in the referenced regulatory guides and NUREGs. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena." 2. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Missile Design Bases." 10.4.9-9 Rev. 2- - July 1981 3. 10 CFR Part 50, Appendix A, General Design Criterion 5, "Sharing of Structures, Systems, and Components." 4. 10 CFR Part 50, Appendix A, General Design Criterion 19, "Control Room." 5. 10 CFR Part 50, Appendix A, General Design Criterion 34, "Decay Heat Removal." 6. 10 CFR Part 50, Appendix A, General Design Criterion 44, "Cooling Water." I 7. 10 CFR Part 50, Appendix Cooling Water System." 8. 10 CFR Part 50, Appendix Cooling Water System." A, General Design Criterion 45, "Inspection of A, General Design Criterion 46, "Testing of 9. Regulatory Guide 1.29, "Seismic Design Classification." 10. Branch Technical Position RSB 5-1, "Design Requirements of the Residual Heat Removal System," attached to SRP Section 5.4.7. I 11. Branch Technical Position ASB 10-1, "Design Guidelines for Feedwater System Pump Drive and Power Supply Diversity for Water Reactor Plants," attached to this SRP section. Auxiliary Pressurized 12. NUREG-0611 "Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in Westinghouse - Designed Operating Plants,"