Document: NUREG-0800
Document ID: ff5838f8-986a-4d8b-a039-fb26df280426
Document Type: srp
Title: – 15.5.2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070725.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.5.1
CFR Part: 
CFR Title: 

Content:
ed a single failure; each increase of inventory transient should be analyzed with and without a LOOP in combination with a single active failure. (This position is based upon interpretation of GDC 17, as documented in the Final Safety Evaluation Report for the ABB-CE System 80+ design certification.) In this phase of the review, the system reviews are performed as described in the 54 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 RSBSRXB55 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 reactivity coefficients and 56 control rod worths used by the applicant in his analysis in the applicant's analysis, and the 57 variation of moderator temperature, void, and Doppler coefficients of reactivity with core life. The justification provided by the applicant to show that he has selected the core burnup has been selected that yields the minimum margins is evaluated. CPBThe appropriate SRXB reviewer 58 59 is consulted regarding the values of the reactivity parameters used in the applicant's analysis. The results of the applicant's analysis are reviewed and compared to with the acceptance 60 criteria-presented in subsection II regarding maximum pressure in the reactor coolant and main steam systems and the minimum critical heat flux ratio (MCHFR) or departure from nucleate boiling ratio (DNBR)DNBR. The variations with time during the transient of the neutron 61 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