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
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Content:
ity 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 consequences of the event.9 15.4.4-3 DRAFT Rev. 2 - April 1996 Review Interfaces10 1. SRXB also performs the following reviews under the SRP sections indicated: SRP Sections 4.2 through 4.4. The Core Performance Branch (CPB)Reactor Systems Branch (SRXB) performs generic reviews of the thermal-hydraulic computer models 11 used for this transientAOO and also performs, upon request, additional analyses related to these accidents for selected reactor types as part of its primary review responsibility. 2. In addition, the RSBSRXB will coordinate other branches' evaluations that interface with the overall review of the system, as follows: a. The Instrument and Control Branch (ICSB)(HICB) reviews the instrumentation 12 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. b. The Accident Evaluation Branch (AEB)Emergency Preparedness and Radiation Protection Branch (PERB) is notified regarding the extent of the fuel failures 13 that are predicted by the analysis. AEBPERB then evaluates the radiological 14 consequences of the event. For those areas of review identified above as being reviewed as part of the primary review responsibility of other branches, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP sections of the corresponding branch.15 II. ACCEPTANCE CRITERIA The RSBSRXB acceptance criteria are based on meeting the relevant requirements of the following regulations: A. General Design Criteria (GDC) 10 (GDC 10) and 20 (GDC 20) as itthey relates to the 16 reactor coolant system