Document: NUREG-0800
Document ID: 0b17303b-e5cc-4091-b22c-056b0c78eb34
Document Type: srp
Title: – 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070707.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
core and system, are reviewed. It is the responsibility of the RSBSRXB reviewer to contact his counterpart in the Core Performance Branch (CPB) to ensure that the appropriate physics 10 and fuel data have been used in any staff calculations. The CPBSRXB 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 Section 4.4 (Ref. 12).11 Review Interfaces12 In addition, the RSBSRXB will coordinate other branches' evaluations that interface with the overall review of the system, as follows: 1. The Instrumentation and Controls Branch ICSBHICB reviews the instrumentation and 13 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 15.3.3-3 DRAFT Rev. 3 - April 1996 in the safety analysis as part of its primary review responsibility for SRP Sections 7.2 through 7.5 (Refs. 14 through 17). The CPBSRXB performs generic reviews of the 14 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 Section 4.4 (Ref. 12).15 2. The Accident Evaluation Branch (AEB) Emergency Preparedness and Radiation Protection Branch (PERB) is notified regarding the extent of the fuel failures that are 16 predicted by the analysis. AEBPERB then evaluates the radiological consequences of 17 the event. 3. The Materials and Chemical Engineering Branch (EMCB) reviews the fracture toughness properties of the reactor coolant pressure boundary and reactor vessel as part of its primary review responsibility for SRP Sections 5.2.3 and 5.3.1.18 4. The SPLB reviews the integrity of the reactor coolant pump seals as part of its primary review