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:
ter the course of the transient. In this phase of the review the system reviews are as described in the SRP sections for SAR Chapters 5, 6, 7, and 8. The reviewer considers possible single failures in systems that replenish or maintain the reactor coolant inventory. 15.6.1-8 Revision 2 - March 2007 The applicant’s mathematical models to evaluate core performance and to predict system pressure in the RCS and main steam line are reviewed for whether they have been reviewed and found acceptable by the staff. If not, the reviewer initiates a generic review of the applicant’s proposed model. The values of system parameters and initial core and system conditions as input to the model also are reviewed. Of particular importance are the reactivity coefficients and control rod worths in the applicant's analysis and the variation of moderator temperature, void, and Doppler coefficients of reactivity with core life. The applicant’s justification showing that the selected core burn-up yields the minimum margins is evaluated. The results of the analysis are reviewed and compared to the acceptance criteria of subsection II for the maximum pressure in the reactor coolant and main steam systems. The following transient parameters are reviewed: • reactor power; • heat fluxes (average and maximum); • RCS pressure; • pressurizer water volume (PWR); • minimum DNBR (PWR) or CPR (BWR); • core and recirculation loop coolant flow rates (BWR); • coolant conditions (inlet temperature, core average temperature (PWR), core average steam volume fraction (BWR), average exit and hot channel exit temperatures, and steam fractions); • steamline pressure; • containment pressure; • pressure relief valve flow rate; and • flow rate from the RCS to the containment system (if applicable). Values of the more important of these parameters for the transient caused by the inadvertent pressure relief valve opening are compared to those predicted for other similar plants for whether