Document: NUREG-0800
Document ID: a650b8f2-b0fa-4f0f-bc8f-55bb3f6ec603
Document Type: srp
Title: INADVERTENT OPENING OF A PWR PRESSURIZER PRESSURE RELIEF VALVE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0708/ML070820094.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.1
CFR Part: 
CFR Title: 

Content:
re and its coolant, control, and protection systems with appropriate margin so specified acceptable fuel design limits are not exceeded during any conditions of normal operation, including the effects of AOOs. GDC 10 applies to this section because the reviewer evaluates the consequences of an inadvertent opening of a PWR pressurizer pressure relief valve or a BWR pressure relief valve. These AOOs could exceed allowable thermal design criteria for fuel cladding integrity. RG 1.53 provides guidance for applying the single-failure criterion to the design and analysis of nuclear power plant protection systems. RG 1.105 provides guidance for ensuring that instrument setpoints remain within the technical specification limits. GDC 10 requirements provide assurance that specified acceptable fuel design limits are not exceeded in the inadvertent opening of a PWR pressurizer pressure relief valve or a BWR pressure relief valve. 2. GDC 13 requires the provision of instrumentation that is capable of monitoring variables and systems over their anticipated ranges to assure adequate safety, and of controls that can maintain these variables and systems within prescribed operating ranges. GDC 13 applies to this section because the reviewer evaluates the sequence of events, including automatic actuations of protection systems, and manual actions, and determines whether the sequence of events is justified, based upon the expected values of the relevant monitored parameters and instrument indications. 15.6.1-6 Revision 2 - March 2007 3. GDC 15 requires design of the RCS and its auxiliary, control, and protection systems with sufficient margin so reactor coolant pressure boundary design conditions are not exceeded during any condition of normal operation, including AOOs. GDC 15 applies to this section because the reviewer evaluates the consequences of the inadvertent opening of a PWR pressurizer pressure relief valve or a BWR pressure relief valve (i.e., AOOs). As part of the reactor