Document: NUREG-0800
Document ID: b085cd1c-2d74-4547-b757-d8513d0cb353
Document Type: srp
Title: OVERPRESSURE PROTECTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070419.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.2
CFR Part: 
CFR Title: 

Content:
EG-0737, "Clarification of TMI Action Plan Requirements." 7. NUREG-1430, "Standard Technical Specifications, Babcock and Wilcox Plants." 8. NUREG-1431, "Standard Technical Specifications, Westinghouse Plants." 5.2.2-9 DRAFT Rev. 3 - April 1996 9. NUREG-1432, "Standard Technical Specifications, Combustion Engineering Plants." 10. NUREG-1433, "Standard Technical Specifications, General Electric Plants, BWR/4." 11. NUREG-1434, "Standard Technical Specifications, General Electric Plants, BWR/6." 12. NRC Letter to All Pressurized Power Reactor Licensees, "NUREG-0737 Technical Specifications," (Generic Letter 82-16), September 20, 1982. 13. NRC Letter to All Boiling Water Reactor Licensees, "NUREG-0737 Technical Specifications," (Generic Letter 83-02), January 10, 1983.43 14. NRC Letter to All Pressurized Water Reactor Licensees and Construction Permit Holders, "Resolution of Generic Issue 70, 'Power-Operated Relief-Valve and Block Valve Reliability,' and Generic Issue 94, 'Additional Low-Temperature Overpressure Protection for Light Water Reactors,' (Generic Letter No. 90-06)," June 25, 1990.44 215. ASME Boiler and Pressure Vessel Code, Section III, Article NM-7000, "Protection Against Overpressure," NB-7000, "Overpressure Protection," American Society of 45 Mechanical Engineers. 716. ASME Boiler and Pressure Vessel Code, Section III, Article NB-7611, "Spring-Loaded Safety Valves." NB-7511.1, "Spring-Loaded Valves."46 DRAFT Rev. 3 - April 1996 5.2.2-10 BRANCH TECHNICAL POSITION RSB 5-2 [Currently the responsibility of the Reactor Systems Branch (SRXB)]47 OVERPRESSURIZATION PROTECTION OF PRESSURIZED WATER REACTORS WHILE OPERATING AT LOW TEMPERATURES A. Background General Design Criterion 15 of Appendix A of 10 CFR Part 50 requires that "the Reactor Coolant System and associated auxiliary, control, and protection systems shall be designed with sufficient margin to assure that the design conditions of the reactor coolant pressure boundary are not exceeded during any