Document: NUREG-0800
Document ID: 784779aa-bf3d-4538-b7b3-4358a3e2a604
Document Type: srp
Title: - 15.4.5-8
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550007.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.4
CFR Part: 
CFR Title: 

Content:
uld occur, the core flow rate increase would not be limited by the rate at which the valve opens, and the resulting rate of reactivity insertion could be greater than for other AOOs of this group. 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 to determine if these models have been previously reviewed and found acceptable by the staff. If not, a generic review of the model proposed by the applicant is initiated. The values of system parameters and initial core conditions, including fuel data and system conditions used as input to the model, are reviewed. Of particular importance are the reactivity coefficients and control rod worths used in the applicant's analysis, and the variation of moderator temperature, void and Doppler coefficients of reactivity with core life. The justification provided by the applicant to show that the selected core burnup yields the minimum margins is evaluated. The reviewer should review SAR Section 4.4 or the corresponding chapter of the DCD to evaluate how uncertainties of the input parameters are applied in the CPR and DNBR analyses. 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, as well as minimum DNBR (PWR) or MCPR (BWR, if applicable). Time-related variations of the following parameters should be reviewed for consistency: