Document: NUREG-0800
Document ID: 598d070d-fb96-43ce-ad4f-27f14623be46
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350119.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15
CFR Part: 
CFR Title: 

Content:
modes, interlocks, and the feasibility of manual operation if the SAR states that operator action is needed or expected. To the extent deemed necessary, the RSB reviewer evaluates the effect of single active failures of systems and components which may affect the course of the transient. This phase of the review uses the system review procedures described in the standard review plans for Chapters 5, 6, 7, and 8 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 line are reviewed by RSB to determine if these models have been previously reviewed and found acceptable by the staff. If not, RSB initiates a generic review of the model proposed by the applicant. CPB is consulted regarding the specified acceptable fuel design limits (SAFDLs). 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 values 15. 2.1-5 Rev. 1 - July 1981 of reactivity coefficients and control rod worths used by the applicant in his analysis, and the variations of moderator temperature, void, and Doppler coeffi- cients of reactivity with core life. The reviewer evaluates the justification provided by the applicant to show that the core burnup selected yields the mini- mum margins. 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 regarding fuel integrity and the maximum pressure in the reactor coolant and main steam systems. The varia- tions with time during the transient of the 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 conditions (inlet temperature, core average temperature (PWR),