Document: NUREG-0800
Document ID: 16650158-402d-4897-850a-bc9e2cce7648
Document Type: srp
Title: INADVERTENT OPENING OF A PWR PRESSURIZER PRESSURE RELIEF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070726.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.1
CFR Part: 
CFR Title: 

Content:
herein are contained in the referenced regulatory guides and NUREGs. 15.6.1-11 DRAFT Rev. 2 - April 1996 VI. REFERENCES 1. ANSI B95.1-1972, "Terminology for Pressure Relief Devices," American Society of Mechanical Engineers. 2. 10 CFR Part 50, Appendix A, General Design Criterion 10, "Reactor Design." 3. 10 CFR Part 50, Appendix A, General Design Criterion 15, "Reactor Coolant Pressure Boundary." 4. 10 CFR Part 50, Appendix A, General Design Criterion 26, "Reactivity Control System Redundancy and Capability." 5. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," Article NB-7000, "Protection Against Overpressure," American Society of Mechanical Engineers. 6. Standard Review Plan Section 4.2, "Fuel System Design." 7. ANSI N18.2, "Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants," American National Standards Institute (1974). 8. ANS Trial Use Standard N212, "Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants," American Nuclear Society (1974). 9. Regulatory Guide 1.105, "Instrument Spans and Setpoints for Safety-Related Systems."74 10. Regulatory Guide 1.53, "Application of the Single Failure Criterion to Nuclear Power Plant Protection Systems." 11. NUREG-0718, "Licensing Requirements for Pending Applications for Construction Permits and Manufacturing Licenses." 12. NUREG-0737, "Clarification of TMI Action Plan Requirements." 13. NRC Generic Letter 85-12, "Implementation of TMI Action Item II.K.3.5, 'Automatic Trip of Reactor Coolant Pumps,' for Westinghouse-Designed Nuclear Steam Supply Systems."75 14. NRC Generic Letter 86-05, "Implementation of TMI Action Item II.K.3.5, 'Automatic Trip of Reactor Coolant Pumps,' for Babcock and Wilcox-Designed Nuclear Steam Supply Systems." 76 15. NRC Generic Letter 86-06, "Implementation of TMI Action Item II.K.3.5, 'Automatic Trip of Reactor Coolant Pumps,' for Combustion Engineering-Designed Nuclear Steam Supply Systems."77 DRAFT