Document: NUREG-0800
Document ID: 2cd63ebf-9196-42c0-880d-a80500b202a4
Document Type: srp
Title: - 15.1.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550005.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.1
CFR Part: 
CFR Title: 

Content:
taken for the functioning of normally operating plant systems. D. The operation of engineered safety systems that is required. E. The extent to which operator actions are required. F. That appropriate margin for malfunctions, such as stuck rods are accounted for. 2. If the SAR states that a particular initiating event involving an increase in heat removal is not as limiting as some other similar event, the reviewer evaluates the justification presented by the applicant. The applicant is to present a quantitative analysis in the SAR of the increase-in-heat-removal event that is determined to be most limiting. For this event, the reactor systems reviewer, with the aid of the instrumentation and control systems reviewer, reviews the timing of the initiation of those protection, engineered safety, and other systems needed to limit the consequences of the transient to an acceptable level. The reactor systems reviewer compares the predicted variation of system parameters with various trip and system initiation setpoints. The instrumentation and control systems 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. 3. To the extent deemed necessary, the reactor systems 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 SRP sections for Chapters 4, 5, 6, 7, 8, and 9 of the SAR. 4. 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 reactor systems to determine if these models have been previously reviewed and found acceptable by the staff. If not, a generic review of the models is initiated. 5. The values of system parameters and initial core and system conditions used as input to the