Document: NUREG-0800
Document ID: 7a841760-7020-433b-b182-63af2e6f5e72
Document Type: srp
Title: OVERPRESSURE PROTECTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340596.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.2
CFR Part: 
CFR Title: 

Content:
, "Protection Against Overpressure," American Society of Mechanical Engineers. 3. Branch Technical Position RSB 5-2, "Overpressurization Protection of Pressurized Water Reactors While Operating at Low Temperatures," attached to this SRP section. 4. NUREG-0718, "Licensing Requirements for Pending Applications for Construction Permits and Manufacturing License." 5. NUREG-0737, "Clarification of TMI Action Plan Requirements." 6. 10 CFR Part 50, Appendix G, "Fracture Toughness Requirements." 7. ASME Boiler and Pressure Vessel Code, Section III, Article NB-7611, "Spring-Loaded Safety Valves." 8. 10 CFR Part 50, Appendix A, General Design Criterion 31, "Fracture Prevention of Reactor Coolant Pressure Boundary." 5.2.2-6 Rev. 2 - November 1988 / BRANCH TECHNICAL POSITION RSB 5-2 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 condition of normal operation, including anticipated operational occurrences." Anticipated operational occurrences, as defined in Appendix A of 10 CFR Part 50, are "those conditions of normal operation which are expected to occur one or more times during the life of the nuclear power unit and include but are not limited to loss of power to all recirculation pumps, tripping of the turbine generator set, isolation of the main condenser, and loss of all offsite power." Appendix G of 10 CFR Part 50 provides the fracture toughness requirements for reactor pressure vessels under certain conditions. To assure that the Appendix G limits of the reactor coolant pressure boundary are not exceeded during any anticipated operational occurrences, technical specification pressure-temperature limits are