Document: NUREG-0800
Document ID: 7170d2a7-5e60-46c5-befd-fc30c9f85dc8
Document Type: srp
Title: 15.3.2.-11
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550010.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.1
CFR Part: 
CFR Title: 

Content:
Revision 2 - March 2007 VI. REFERENCES 1. 10 CFR 50, "Domestic Licensing of Production and Utilization Facilities." 2. 10 CFR 50, Appendix A, GDC 10, "Reactor Design." 3. 10 CFR 50, Appendix A, GDC 13, “Instrumentation and Control.” 4. 10 CFR 50, Appendix A, GDC 15, "Reactor Coolant System Design." 5. 10 CFR 50, Appendix A, GDC 17, "Electric Power Systems." 6. 10 CFR 50, Appendix A, GDC 20, "Protection System Functions." 7. 10 CFR 50, Appendix A, GDC 26, "Reactivity Control System Redundancy and Capability." 8. 10 CFR 52, "Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants." 9. RG 1.206, "Combined License Applications for Nuclear Power Plants (LWR Edition)." 10. RG 1.53, "Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems." 11. RG 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." 12. RG 1.105, "Instrument Spans and Setpoints." 13. NUREG-0737, "Clarification of TMI Action Plan Requirements." 14. NUREG-0933, "A Prioritization of Generic Safety Issues." 15. NUREG-1801, "Generic Aging Lessons Learned Report," Revision 1, volumes 1-2. 16. SECY-77-439, "Single Failure Criterion." 17. SECY-94-084, "Policy and Technical Issues Associated With the Regulatory Treatment of Non-Safety Systems in Passive Plant Designs." 18. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," Article NB-7000, "Protection Against Overpressure," American Society of Mechanical Engineers. 19. ANSI/ANS-51.1-1983, "Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants," (replaced ANSI N18.2-1974, reaffirmed 1988, withdrawn 1998).