Document: NUREG-0800
Document ID: 0b17303b-e5cc-4091-b22c-056b0c78eb34
Document Type: srp
Title: – 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070707.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
em parameters are within expected ranges for the type and class of reactor under review. Fuel damage is assessed by the methods described in SRP Section 4.2 (Ref. 13). 5 The system parameters that are evaluated include: core flow and flow distribution (including hydraulic instabilities), channel heat flux (average and hot), minimum 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). System parameters to be reviewed include the following: - core flow and flow distribution (including hydraulic instabilities), - channel heat flux (average and hot), - minimum 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).6 The sequence of events described in the safety analysis report (SAR) is reviewed by RSBRSXB. 7 This review is coordinated with Instrumentation and Control Systems Branch (ICSB). The 8 RSBRSXB review concentrates on the need for the reactor protection system, the engineered safety systems, and operator action to secure and maintain the reactor in a safe condition. The analytical methods are reviewed by RSBSRXB 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 RSBSRXB reviewer requests initiation of initiates a generic evaluation of the new analytical model by CPBSRXB.9 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 responsibility of the RSBSRXB reviewer to contact his counterpart in the Core Performance Branch (CPB) to ensure that the appropriate physics 10 and fuel data