Document: NUREG-0800
Document ID: 4d7d277e-c006-45d6-94df-c84845dd68d0
Document Type: srp
Title: INADVERTENT OPENING OF A PWR PRESSURIZER PRESSURE RELIEF VALVE OR A BWR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350144.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.1
CFR Part: 
CFR Title: 

Content:
viewed and accepted by the staff. If a referenced method has not been previously reviewed, the reviewer initiates a generic evaluation of the new analytical model. The values of all 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. 2O5 the parameters used in the new analytical model, including the initial conditions of the core and system, are reviewed. The predicted results of the transient are reviewed to assure that the consequences meet the acceptance criteria given in subsection II of this SRP section. The analysis results are reviewed to ascertain that pertinent system parameter valves are within ranges expected for the type and class of reactor under review. The RSB will coordinate other branch evaluations that interface with the overall review of this SRP section as follows: The Instrumentation and Controls Systems Branch (ICSB) reviews the instrumentation and controls aspects of the sequence described to confirm that the reactor and plant