Document: NUREG-0800
Document ID: 7b7303eb-a3a7-433b-8301-fcaba03194ea
Document Type: srp
Title: - 15.1.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070676.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.1
CFR Part: 
CFR Title: 

Content:
hapter 7 of the SAR confirms that the instrumentation and control 46 systems design is consistent with the requirements for safety systems actions for these events. To the extent deemed necessary, the RSBSRXB reviewer evaluates the effect of single active 47 failures of systems and components which may affect the course of the transient. This phase of the review uses the system review procedures described in the SRP sections for Chapters 4, 5, 6, 7, 8, and 9 of the SAR. The mathematical models used by the applicant to evaluate core performance and to predict system pressure in the reactor coolant system and main steam lines are reviewed by RSBSRXB48 to determine if these models have been previously reviewed and found acceptable by the staff. If not, a generic review of the models is initiated. The values of system parameters and initial core and system conditions used as input to the model are reviewed by RSBSRXB. Of particular importance are the values of reactivity 49 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 burnup selected yields the minimum margins. CPBSRXB is consulted regardingreviews the values of the reactivity 50 parameters used in the applicant's analysis. The results of the analysis are reviewed and compared to with the acceptance criteria presented 51 in subsection II of this SRP section 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 temperature (PWR), core average steam volume fraction (BWR), average exit and hot channel exit