Document: NUREG-0800
Document ID: 824740ba-eb51-4b24-bd6f-df01c35d75f3
Document Type: srp
Title: LOSS OF NONEMERGENCY AC POWER TO THE STATION AUXILIARIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550008.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
CFR Part: 
CFR Title: 

Content:
sections for SAR Chapters 4, 5, 6, 7, 8, and 9. 3. The applicant’s mathematical models for evaluating core performance and predicting system pressure in the RCS and main steam lines are reviewed by for whether these models have been reviewed and accepted by the staff. If not, the reviewer initiates a generic review of the applicant’s proposed model. 4. System parameter values and initial core and system conditions as input to the model are reviewed. Of particular importance are the reactivity coefficients and control rod worths in the applicant's analysis and the variations of moderator temperature, void, and Doppler coefficients of reactivity with core life. The applicant’s justification to show that it has selected the core burn-up that yields minimum margins is evaluated. The values of the reactivity parameters in the applicant's analysis are reviewed. 5. The results of the analysis are reviewed and compared to the acceptance criteria of subsection II of this SRP section as to the maximum pressure in the reactor coolant and main steam systems. The variations during the transient of neutron power, heat fluxes (average and maximum), RCS 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 RCS to the containment system (if applicable) are reviewed. Time-related variations of the following parameters are reviewed: A. reactor power; B. heat fluxes (average and maximum); C. RCS pressure; D. minimum DNBR (PWR) or CPR (BWR); E. core and recirculation loop coolant flow rates (BWR); 15.2.6-8 Revision 2 - March 2007 F. coolant conditions (inlet temperature, core average temperature (PWR), core average steam volume fraction (BWR), average exit and