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:
lear Regulatory Commission, Washington, DC 20555, Attention: Reproduction and Distribution Services Section, or by fax to (301) 415-2289; or by email to DISTRIBUTION@nrc.gov. Electronic copies of this section are available through the NRC's public Web site at http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800/, or in the NRC's Agencywide Documents Access and Management System (ADAMS), at http://www.nrc.gov/reading-rm/adams.html, under Accession # ML070850008. NUREG-0800 U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN BRANCH TECHNICAL POSITION 5-2 OVERPRESSURIZATION PROTECTION OF PRESSURIZED-WATER REACTORS WHILE OPERATING AT LOW TEMPERATURES REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of reactor thermal-hydraulic systems in BWRs and PWRs. Secondary - None A. BACKGROUND GDC 15 of Appendix A to 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.” AOOs, as defined in Appendix A to 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 to 10 CFR Part 50 provides the fracture toughness requirements for reactor pressure vessels under certain conditions. To ensure that the Appendix G limits of the RCPB are not exceeded during any AOOs, technical specification pressure-temperature limits are provided for operating the plant. The primary concern of this position is that, during startup and BTP 5-2-2 Revision 3 - March 2007 shutdown conditions at low