Document: NUREG-0800
Document ID: 050fa52d-0a13-4146-93e4-0f4659c7d893
Document Type: srp
Title: LOSS OF NONEMERGENCY AC POWER TO THE STATION AUXILIARIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350140.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
CFR Part: 
CFR Title: 

Content:
rotection, engineered safety, standby diesel generator, and other systems needed to limit the consequences of the transient to an acceptable level. The RSB reviewer compares the predicted variation of system parameters with various trip and system initiation setpoints. The ICSB review of Chapter 7 of the SAR confirms that the instrumentation and control systems design is consistent with the requirements for safety systems actions for these events. To the extent deemed necessary, the RSB reviewer evaluates the effects of single active 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 RSB 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 RSB. 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 coeffi- cients of reactivity with core life. The Justification provided by the applicant to show that he has selected the core burnup that yields the minimum margins is evaluated. CPB is consulted regarding'the values of the reactivity parameters used in the applicant's analysis. The results of the analysis are reviewed and-compared to the acceptance criteria presented in subsection II of this SRP section regardina 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