Document: NUREG-0800
Document ID: e75b7685-2a36-4e9b-a431-02d166dcf372
Document Type: srp
Title: LOSS OF NONEMERGENCY AC POWER TO THE STATION AUXILIARIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070681.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
CFR Part: 
CFR Title: 

Content:
er compares the 51 predicted variation of system parameters with various trip and system initiation setpoints. The ICSBHICB review of Chapter 7 of the SAR confirms that the instrumentation and control 52 systems design is consistent with the requirements for safety systems actions for these events. To the extent deemed necessary, the RSBSRXB reviewer evaluates the effects of single active 53 failures of systems and components which may affect the course of the transient. This aspect of the review uses the procedures described in 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 RSBSRXB54 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 and system conditions used as input to the model are reviewed by RSBSRXB. Of particular importance are the reactivity coefficients and 55 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 heit has selected the core burnup that yields the minimum margins is 56 evaluated. CPB is consulted regardingThe SRXB reviews the values of the reactivity 57 parameters used in the applicant's analysis. The results of the analysis are reviewed and compared to with the acceptance criteria presented 58 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 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