Document: NUREG-0800
Document ID: 5cdeed4a-6cd5-4840-90c0-5159fbf2c9f0
Document Type: srp
Title: CHILLED WATER
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1409/ML14093A350.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.2.7
CFR Part: 
CFR Title: 

Content:
nonsafety-related defense-in-depth functions in order to meet NRC safety goal guidelines. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the methods described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted 6 months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. 10 CFR 20.1406, “Minimization of Contamination.” 2. 10 CFR 50.34, “Contents of Applications, Technical Information.” 3. 10 CFR Part 50, Appendix A, GDC 1, “Quality standards and records.” 4. 10 CFR Part 50, Appendix A, GDC 2, “Design Bases for Protection Against Natural Phenomena.” 5. 10 CFR Part 50, Appendix A, GDC 4, “Environmental and Dynamic Effects Design Bases.” 6. 10 CFR Part 50, Appendix A, GDC 5, “Sharing of Structures, Systems, and Components.” 7. 10 CFR Part 50, Appendix A, GDC 44, “Cooling Water.” 8. 10 CFR Part 50, Appendix A, GDC 45, “Inspection of Cooling Water System.” 9. 10 CFR Part 50, Appendix A, GDC 46, “Testing of Cooling Water System.” 10. 10 CFR Part 52.47, “Contents of Applications, Technical Information.” 11. 10 CFR Part 52.80(a), “Contents of Applications, Additional Technical Information, Inspections, Tests, Analyses, and Acceptance Criteria.” 12. RG 1.29, “Seismic Design Classification.” 13. RG 1.68, “Initial Test Programs for Water-Cooled Nuclear Power Plants.” 9.2.7-31 Draft Revision 0 – July 2014 14. RG 1.153, ”Criteria for Safety Systems.” 15. RG 1.155, ”Station Blackout.” 16. RG 1.160, “Monitoring the Effectiveness of Maintenance at Nuclear Power