Document: NUREG-0800
Document ID: 050fa52d-0a13-4146-93e4-0f4659c7d893
Document Type: srp
Title: LOSS OF NONEMERGENCY AC POWER TO THE STATION AUXILIARIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350140.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
CFR Part: 
CFR Title: 

Content:
engineered safety systems, and operator action to secure and maintain the reactor in a safe condition. Rev. 1 - 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. 2C5 The analytical methods are reviewed by RSB 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 reviewer requests initiation of a generic evaluation of the new analytical model by RSB or the Core Performance Branch (CPB) as appropriate. The predicted results of the transient analysis are reviewed to assure that the consequences meet the acceptance criteria given in subsection II, below. The results of the analysis are reviewed to ascertain that the values of pertinent system parameters are within expected ranges for the type and class of reactor under review. The RSB will coordinate other branch evaluations that interface with the overall review of the