Document: NUREG-0800
Document ID: ff5838f8-986a-4d8b-a039-fb26df280426
Document Type: srp
Title: – 15.5.2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070725.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.5.1
CFR Part: 
CFR Title: 

Content:
RSBSRXB will coordinate other branch evaluations that interface with the overall review 13 of the transient analysis as follows: 14 The Instrumentation and Controls Systems Branch (ICSB)(HICB) reviews the 15 instrumentation and controls aspects of the sequence described in the SAR to evaluate whether the reactor and plant protection and safeguards controls and instrumentation 15.5.1-3 DRAFT Rev. 2 - April 1996 systems will function as assumed in the safety analysis with regard to automatic actuation, remote sensing, indication, 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 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 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 4.4.16 The Accident Evaluation Branch (AEB), using fuel damage results provided by RSB, evaluates the radiological consequences associated with the fuel failure.17 The review of the Technical Specifications is coordinated and performed by the Licensing Guidance Branch (LGB)Technical Specifications Branch (TSB) as part of its 18 primary review responsibility for SRP Section 16.0. The SRXB also performs the following review under the SRP sections indicated: The SRXB 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 as part of its primary review responsibility for SRP