Document: NUREG-0800
Document ID: 0b17303b-e5cc-4091-b22c-056b0c78eb34
Document Type: srp
Title: – 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070707.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
ted the core burnup that yields the minimum margins is evaluated. CPB is consulted regarding the values of the reactivity parameters used in the applicant's analysis. 51 The results of the applicant's 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 temporal changes 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 temperature (PWR), core average steam volume fraction (BWR), average exit and hot channel exit temperatures, and steam fractions), steam line pressure, containment pressure, pressure relief valve flow rate, and flow rate from the reactor coolant system to the containment systems (if applicable) during the transient are reviewed. Time-related variations of the following parameters are reviewed: - reactor 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 temperature (PWR), core average steam volume fraction (BWR), average exit and hot channel exit temperatures, and steam fractions); - steam line pressure; - containment pressure; - pressure relief valve flow rate; and - flow rate from the reactor coolant system to the containment system (if applicable).52 The more important of these parameters (as listed in subsection I of this SRP section) are compared to those predicted for other similar plants to confirm that they are within the expected range. The percentage of fuel rods that experience failure is reviewed and AEBPERB is 53 notified regarding the extent of fuel failures predicted by the analysis. CPB is consulted regarding the acceptance criteria for fuel rod failure and core