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:
taff 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. 205E. The review includes the postulated initial core and reactor conditions which are pertinent to the loss of flow transient) the methods of thermal and hydraulic analysis, the postulated sequence of events including time delays prior to and after protective system actuation, assumed reactions of reactor systems com- ponents, the functional and operational characteristics of the reactor protection .system in terms of how it affects.the sequence of events, and all operator actions required to secure and maintain the reactor in a safe condition. The results of the applicant's analyses are reviewed to ensure that-values of pertinent system parameters are within expected ranges for the type and class of reactor under review. The system parameters that are evaluated include: core flow and flow distribution, 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