Document: NUREG-0800
Document ID: 32a990b8-4423-466f-a1f4-198cd17fe8bf
Document Type: srp
Title: 15.3.2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350154.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.1
CFR Part: 
CFR Title: 

Content:
nimum critical heat flux ratio (or minimum critical power ratio), departure from nucleate boiling ratio, vessel water level, thermal power, vessel pressure,. steam line pressure (BWR), main steam flow (BWR), and feedwater flow (BWR). The results of the applicant's fuel damage analysis are reviewed by the methods described in SRP Section 4.2 (Ref. 12). The sequence of events described in the SAR is reviewed by RSB. This review is coordinated with Instrumentation and Control Systems Branch (ICSB). The RSB review concentrates on the need for the reactor protection system; the engineered safety system, and operator action to secure and maintain the reactor in a safe condition. The analytical methods are reviewed by RSB to ascertain whether the mathematical modeling and computer codes have been previously reviewed and accepted by the staff. If a referenced analytical method has not been previously reviewed, the RSB reviewer requests initiation of a generic evaluation of the new analytical model by the Core Performance Branch (CPB). ( The values of all parameters used in a new analytical model, including the initial conditions of the core and system, are reviewed. It is the responsi- bility of the RSB reviewer to contact his counterpart in CPB to ensure that the appropriate physics and fuel data have been used in any staff calculations. In addition, the RSB will coordinate other branches' evaluations that interface with the overall review of the system as follows: The ICSB reviews the instru- mentation and control aspects of the sequence described in the SAR to confirm that reactor and plant protection and safeguards controls and instrumentation systems will function-as assumed in the system analysis as part of its primary review responsibility for SRP Sections 7.2 through 7.5 (Ref. 14 through 17). The CPB, as part of its primary review responsibility for SRP Section 4.4 (Ref. 13), performs generic reviews of the thermal-hydraulic computer models used for this transient