Document: NUREG-0800
Document ID: 16afcc26-09c8-4627-8906-8c56ffe8434b
Document Type: srp
Title: LOSS OF NORMAL FEEDWATER FLOW
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070683.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.7
CFR Part: 
CFR Title: 

Content:
wer to assure that the operational assumptions for the auxiliary feedwater system in the analysis is appropriate as part of its primary review responsibility for SRP Sections 7.2 through 7.5. The Core Performance 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 15.2.7-3 DRAFT Rev. 2 - April 1996 limits; and reviews the core physics, fuel design, and core thermal-hydraulics data used in the SAR analysis as part of its primary review responsibility for SRP Sections 4.2 through 4.4. The Accident Evaluation Branch (AEB), using fuel damage results provided by RSB, evaluates the radiological consequences associated with fuel failure. The review of the technical specifications is coordinated and performed by the Licensing Guidance Branch (LGB) as part of its primary review responsibility for SRP Section 16.0.8 Review Interfaces9 1. SRXB also performs the following reviews under the Standard Review Plan (SRP)10 sections indicated: a. SRP Sections 4.2 through 4.4 for:The Core Performance Branch (CPB), upon request from RSB, reviews 11 i. the review of 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, ii. determining the acceptance criteria for fuel cladding damage limits, and iii. reviewing the core physics, fuel design, and core thermal-hydraulics data used in the SAR analysis as part of itsSRXB's primary review responsibility. 12 2. The RSBSRXB will coordinate other branch evaluations that interface with the overall review of the transient analysis as follows: a. The ICSBHICB reviews the instrumentation and controls aspects of the sequence described in the SAR to evaluate whether the reactor and plant protection and safeguards controls and