Document: NUREG-0800
Document ID: 03b93282-92df-4348-9759-27a647a10066
Document Type: srp
Title: - 15.3.4-9
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550012.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
Revision 3 - March 2007 Either a separate analysis should be presented or each mode of operation or the effects of each mode should be referenced to the limiting case. For the more limiting accident, the reviewer, with the aid of the staff reviews the timing of the initiation of those protection, engineered safety, and other systems needed to limit the consequences of the accident to acceptable levels. The reviewer compares the predicted variation of system parameters with various trip and system initiation setpoints. The staff 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 reviewer evaluates the effect of single active failures of safety systems and components which may alter the course of the accident. For new applications, the loss of off-site power is not considered a single active failure, but considered in addition to a single active failure as discussed in subsection II.7. This phase of the review uses the system review procedures described in the SRP sections 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 lines are reviewed by the staff to determine if these models have been previously reviewed and found acceptable by the staff. If not, the staff initiates a generic review of the model proposed by the applicant. The values of system parameters and initial core and system conditions used as input to the model are reviewed by the staff. 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 coefficients of reactivity with core life. The justification provided by the applicant to show that he has selected the core burnup that yields the