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:
ms, 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 previously reviewed and accepted by the staff. If a referenced analytical method has not been previously reviewed, the RSB reviewer initiates a generic evaluation of the new analytical model. In addition, the values of all the parameters used in the new analytical model, including the initial conditions of the core and system, are reviewed. The predicted results of those transients analyzed are reviewed to assure that the consequences meet the acceptance criteria given in subsection II, below. Further, the results of the analysis are reviewed to ascertain that the values of pertinent system parameters 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 the transient analysis as follows: The Instrumentation and Control Systems Branch (ICSB) reviews the instrumentation and controls aspects of the sequence described in the SAR to evaluate whether the reactor and plant protec- tion and safeguards controls and instrumentation systems will function as assumed in the safety analysis with regard to automatic actuation, remote sensing, indica- tion, control, and interlocks with auxiliary or.shared systems as part of its primary review responsibility for SRP Sections 7.2 through 7.5. The Core Perform- ance Branch (CPB), upon request from RSB, reviews the values of the parameters used in the analytical models which relate to the reactor core for conformance to plant design and specified operating conditions; determines the acceptance criteria for fuel cladding damage limits; and reviews the core physics, fuel design, and core thermal-hydraulics data used in the SAR analysis a's part of its primary review responsibility for SRP Sections 4.2 through 4.4. The Accident