Document: NUREG-0800
Document ID: 94ab38ac-ddfc-4ba1-ae38-bc25ffa6e976
Document Type: srp
Title: – 15.4.5
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070716.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.4
CFR Part: 
CFR Title: 

Content:
analytical model, and the predicted consequences of the transientsAOOs. The RSBSRXB reviewer concentrates on the need for the 7 reactor protection system and operator action to secure and maintain the reactor in a safe condition. The analytical methods are reviewed by RSBSRXB 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 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 the transientsAOOs are reviewed to assureensure that the consequences 8 meet the acceptance criteria given in subsection II, below. Further, the results of the transientsAOOs are reviewed to ascertain that the values of pertinent system parameters are within ranges expected for the type and class of reactor under review. In addition, the RSB will coordinate other branches' evaluations that interface with the overall review of the system as follows: The Instrument and Control Branch (ICSB) reviews the instrumentation and controls aspects of the sequence described in the SAR to confirm that reactor and plant protection and safeguards controls and instrumentation systems will function as assumed in the safety analysis as part of its primary review responsibility for SRP Sections 7.2 through 7.5. The Core Performance Branch (CPB) performs generic reviews of the thermal-hydraulic computer models used for this transient and also performs, upon request, additional analyses related to these accidents for selected reactor types as part of its primary review responsibility for SRP Sections 4.2 through 4.4. The Accident Evaluation Branch (AEB) is notified regarding the extent of the fuel failures that are predicted by the analysis. AEB then evaluates the radiological