Document: NUREG-0800
Document ID: d4d35b7c-b4e5-4cb4-8dd9-1b7edddf0ad6
Document Type: srp
Title: CHEMICAL AND VOLUME CONTROL SYSTEM (PWR) (INCLUDING BORON
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070537.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.4
CFR Part: 
CFR Title: 

Content:
respect to the integrity of reactor coolant pump seals, the method for review of the adequacy of the reactor coolant pump seal integrity for station blackout described in subsection III.E is used for the evaluation of new applications.74 DRAFT Rev. 3 - April 1996 9.3.4-16 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.75 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES76 1. 10 CFR Part 50, §50.34(f), "Additional TMI-Related Requirements."77 2. 10 CFR 50, §50.63, "Loss of All Alternating Current Power."78 13. 10 CFR Part 50, Appendix A, General Design Criterion 1, "Quality Standards and Records." 24. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena." 35. 10 CFR Part 50, Appendix A, General Design Criterion 5, "Sharing of Structures, Systems, and Components." 46. 10 CFR Part 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure Boundary." 57. 10 CFR Part 50, Appendix A, General Design Criterion 29, "Protection Against Anticipated Operational Occurrences." 68. 10 CFR Part 50, Appendix A, General Design Criterion 33, "Reactor Coolant Makeup." 79. 10 CFR Part 50, Appendix A, General Design Criterion 35, "Emergency Core Cooling." 810. 10 CFR Part 50, Appendix A, General Design Criterion 60, "Control of Release of Radioactive Material to the Environment." 911. 10 CFR Part 50, Appendix A, General Design Criterion 61, "Fuel Storage and handling and Radioactivity Control." 102. Regulatory Guide 1.26, "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants." 113. Regulatory Guide 1.29, "Seismic Design Classification." 14. Regulatory Guide 1.155, "Station Blackout."79 125. NUREG-0737, "Clarification of TMI Action Plan Requirements.