Document: NUREG-0800
Document ID: 621763b9-bd48-4ded-8c42-b942a23a06d4
Document Type: srp
Title: – 15.2.5
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070680.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.1
CFR Part: 
CFR Title: 

Content:
dures described in the 42 standard review plans for Chapters 5, 6, 7, and 8 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 line are reviewed by RSBSRXB to determine if these models have been previously reviewed and found acceptable by the staff. If not, RSBSRXB initiates a generic review of the model proposed by the applicant. CPB is consulted regarding the specified acceptable fuel design limits (SAFDLs).43 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 (1) the values of reactivity coefficients and control rod worths used by in the applicant's analysis and (2) the variations of moderator temperature, void, and Doppler coefficients of reactivity with core life. The 44 reviewer evaluates the justification provided by the applicant to show that the core burnup selected yields the minimum safety margins. CPB is consulted regarding the values of the 45 reactivity parameters used in the applicant's analysis.46 The results of the analysis are reviewed and compared to with the acceptance criteria presented 47 in subsection II of this SRP section regarding fuel integrity and 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 temperatures, and steam fractions), steam line pressure, containment pressure, pressure relief valve flow rate, and flow rate from the reactor 15.2.1-9 DRAFT Rev. 2 - April 1996 coolant system to the containment system (if applicable) are reviewed.