Document: NUREG-0800
Document ID: 9551c0fd-dc14-40e8-aba3-3a15cb85ea2c
Document Type: srp
Title: 15.5.2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350142.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.5.1
CFR Part: 
CFR Title: 

Content:
These transients are the subject of other SRP sections that consider Rev. 1 - July 1981 USNRC STANDARD REVIEW PLAN Standard reviiew 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. 20555. their effects on system parameters other than coolant inventory. However, the impact of these transients on reactor coolant inventory is considered by the reviewer as a portion of the effort involved in this SRP section. The review of events leading to an increase in reactor coolant inventory con- siders the sequence of events, the analytical model, the values of parameters used in the analytical model, and the predicted consequences of"the transient. The sequence of events described in the applicant's SAR 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 maintain the reactor in a safe condition. The analytical methods are reviewed by RSB to ascertain whether the mathemat- ical modeling and computer codes have been