Document: NUREG-0800
Document ID: 2cd63ebf-9196-42c0-880d-a80500b202a4
Document Type: srp
Title: - 15.1.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550005.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.1
CFR Part: 
CFR Title: 

Content:
eviously reviewed and found acceptable by the staff. If not, a generic review of the models is initiated. 5. The values of system parameters and initial core and system conditions used as input to the model are reviewed by the reactor systems. Of particular importance are the values of reactivity coefficients and control rod worths used by the applicant in this analysis, and the variations of moderator temperature, void, and Doppler coefficients of reactivity with core life. The reviewer evaluates the justification provided by the applicant to show that the core burn-up selected yields the minimum margins. The reactor systems reviews the values of the reactivity parameters used in the applicant's analysis. 6. The results of the analysis are reviewed and compared with the acceptance criteria presented in subsection II of this SRP section regarding the maximum pressure in the reactor coolant and main steam systems. 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; 15.1.1-15.1.4-9 Revision 2 - March 2007 – containment pressure; – pressure relief valve flow rate; and – flow rate from the reactor coolant system to the containment system (if applicable). The values of the more important of these parameters, as listed in subsection I of this SRP section, are compared with those predicted for other similar plants to see that they are within the range expected. The NRC has completed a program to reduce the sensitivity of B&W plants to feedwater transients, with emphasis on overcooling events that have occurred at B&W plants (Items II.E.5.1 and II.E.5.2,