Document: NUREG-0800
Document ID: 504a24fe-9056-495a-8541-0e278016ce80
Document Type: srp
Title: in that offsite AC power remains available to operate the station
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070300702.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
CFR Part: 
CFR Title: 

Content:
cribed in the SRPs for SAR (or DCD) Chapters 5, 6, 7, and 8. 4. The applicant’s mathematical models to evaluate core performance and to predict system pressure in the reactor coolant system and main steam line are reviewed by the organization responsible for reactor systems for whether these models have been reviewed and accepted by the staff. If not, the organization responsible for reactor systems initiates a generic review of the applicant’s proposed model. 5. The values of system parameters and initial core and system conditions as input to the model are reviewed by the organization responsible for reactor systems. Of particular importance are (A) the values of reactivity coefficients and control rod worths in the applicant's analysis and (B) the variations of moderator temperature, void, and Doppler coefficients of reactivity with core life. The reviewer evaluates the applicant’s justification showing that the core burn-up selected yields the minimum safety margins. 6. The results of the analysis are reviewed and compared to the acceptance criteria of subsection II of this SRP section for fuel integrity, the possibility of the event becoming more serious, and the maximum pressure in the reactor coolant and main steam systems. The following parameters are reviewed: A. reactor power; B. heat fluxes (average and maximum); C. reactor coolant system pressure; D. minimum DNBR (PWR) or CPR (BWR); E. core and recirculation loop coolant flow rates (BWR); F. coolant conditions (inlet temperature, core average temperature (PWR), core average steam volume fraction (BWR), average exit and hot channel exit temperatures, and steam fractions); G. steam line pressure; H. containment and suppression pool (if applicable) pressures and temperatures; I. maximum pressurizer water volume (PWR); J. pressure safety and relief valve flow rates; and K. flow rate from the reactor coolant system to the containment system (if applicable). 15.2.1-15.2.5-10 Revision 2 - March 2007 The