Document: NUREG-0800
Document ID: 8a69e211-8100-413b-aa05-61dd44b10160
Document Type: srp
Title: REVIEW RESPONSIBILITIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350115.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.4
CFR Part: 
CFR Title: 

Content:
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. P.WRs Only a. Inadvertent opening of a steam generator relief or safety valve. The topics covered in the primary review include: postulated initial core and reactor conditions which are pertinent to feedwater system malfunctions, pressure regulator or pressure relief valve malfunctions, methods of thermal and hydraulic analysis, postulated sequence of events including time delays prior to and after protective system actuation, assumed reactions of reactor system components, 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 transient analysis are reviewed to ensure that the values of pertinent system parameters are within the ranges expected for the type and class of reactor under review. The parameters include: core flow and flow distribution, channel heat flux (average and hot), minimum critical power ratio (MCPR), departure from nucleate boiling ratlo (1NBR), vessel water level, thermal power, vessel pressure, steam line pressure (for BWRs), steam line flow (for BWRs), feedwater flow (for BWRs), and reactivity. The sequence of events described in the SAR for these transients is reviewed by RSB. The RSB reviewer concentrates on the need for the reactor protection system, the engineered safety systems, and operator action to secure and main- tain the reactor in a safe condition. The analytical