Document: NUREG-0800
Document ID: 4d7d277e-c006-45d6-94df-c84845dd68d0
Document Type: srp
Title: INADVERTENT OPENING OF A PWR PRESSURIZER PRESSURE RELIEF VALVE OR A BWR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350144.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.1
CFR Part: 
CFR Title: 

Content:
ems and components which may alter the course of the transient. In this phase of the review the system reviews are performed as described in the SRP sections for Chapters 5, 6, 7 and 8 of the SAR. The reviewer considers possible single failures in systems that replenish or maintain the reactor coolant inventory. The mathematical models used by the applicant to evaluate core performance and to predict system pressure in the reactor coolant system and main steam line are reviewed by RSB to determine if these models have been previously reviewed and found acceptable by the staff. If not, the reviewer initiates a generic review of the model proposed by the applicant. The values of system parameters and initial core and system conditions used as input to the model are reviewed by RSB. Of particular importance are the reactivity coefficients and control rod worths used by the applicant in his analysis, and the variation of moderator temperature, void, and Doppler coefficients of reactivity with core life. The justification provided by the 15.6.1-5 Rev. 1 - July 1981 applicant to show that he has selected the core burnup that yields the minimum margins is evaluated. The results of the analysis are reviewed and compared to the acceptance criteria presented in subsection II regarding the maximum pressure in the reactor coolant and main steam systems. The variations with time during the transient of the neutron power, heat fluxes (average and maximum), reactor coolant system pressure, minimum DNBR (PWR) or CPR (BWR); core and recirculation loop coolant flow rates (BWR), coolant conditions (inlet temperature, core average temeperature (PWR), core average steam volume fraction (BWR), average exit and hot channel exit temperatures, and steam fractions), steamline pressure, containment pressure, pressure.rellef valve flow rate, and flow rate from the reactor coolant system to the containment system (if applicable) are reviewed. Values of the more important of these parameters for