Document: NUREG-0800
Document ID: d53aca30-dbc8-4ddf-8aa5-2b1d5f31d140
Document Type: srp
Title: Revision 3 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0708/ML070850008.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5
CFR Part: 
CFR Title: 

Content:
III of the ASME Code. 7. The design of the overpressure protection system should function during an operating- basis earthquake. It should not compromise the design criteria of any other safety- grade system with which it would interface, such that the requirements of Regulatory Guide 1.29 are met. 8. The overpressure protection system should not depend on the availability of offsite power to perform its function. The system should be operable from battery-backed power sources, not necessarily Class 1E buses. 9. Overpressure protection systems that take credit for active component(s) to mitigate the consequences of an overpressurization event should include additional analyses considering inadvertent system initiation/actuation or should provide justification that existing analyses bound such an event. 10. If pressure relief is from a low-pressure system not normally connected to the primary system, interlocks that would isolate the low-pressure system from the primary coolant system should not defeat the overpressure protection function (see Branch Technical Position 7-1). C. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 15, “Reactor Coolant System Design.” 2. 10 CFR Part 50, Appendix G, “Fracture Toughness Requirements.” 3. NUREG-0138, “Staff Discussion of Fifteen Technical Issues Listed in Attachment to November 3, 1976, Memorandum from Director, NRR, to NRR Staff.” 4. IEEE Standard 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” (as endorsed by Regulatory Guide 1.153). 5. ASME Boiler and Pressure Vessel Code, Section II, “Materials Specifications.” 6. ASME Boiler and Pressure Vessel Code, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components.” 7. Branch Technical Position (BTP) 7-1, “Guidance on Isolation of Low-Pressure Systems from the High-Pressure Reactor Coolant System.” 8. Regulatory Guide 1.26, “Quality Group Classifications and