Document: NUREG-0800
Document ID: ecb92ac6-97df-4e4b-a20a-81638c2d573b
Document Type: srp
Title: - 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350157.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
the methods described in SRP Section 4.2 (Ref. 13). The system parameters that are evaluated include: core flow and flow distribution (including hydraulic instabil- ities), channel heat flux (average and hot), minimum critical heat flux ratio Rev. 2 - July 1981 USNRC STANDARD REVIEW PLAN Standard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responsible for the review of applications to construct and operate nuclear power plants. These documents are made available to the public as part of the Commission's policy to inform the nuclear Industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them Is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically. as appropriate, to accommodate comments and to reflect new informa- tion and experience. Comments and suggestions for Improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation. Washington, D.C. 2 (or minimum critical power ratio), departure from nucleate boiling ratio, vessel water level, thermal power, vessel pressure, steam line pressure (BWR), l main steam flow (BWR), and feedwater flow (BWR). 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 systems, 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