Document: NUREG-0800
Document ID: 050fa52d-0a13-4146-93e4-0f4659c7d893
Document Type: srp
Title: LOSS OF NONEMERGENCY AC POWER TO THE STATION AUXILIARIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350140.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
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CFR Title: 

Content:
of pertinent system parameters are within expected ranges for the type and class of reactor under review. The RSB will coordinate other branch evaluations that interface with the overall review of the transient analysis as follows: The ICSB 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 instrumentation systems will function as assumed in the safety analysis with regard to automatic actuation, remote sensing, indication, control, and inter- locks with auxiliary or shared systems. The ICSB evaluates the design of the auxiliary feedwater system to determine that the requirements and guidance of II.E.1.2 of NUREG-0737 are met. The RSB reviewer consults with the ICSB reviewer to assure that the appropriate delay time for auxiliary feedwater initiation is 3ssumed in the analysis. The reliability of the auxiliary feedwater system is reviewed by the ASB in accordance with SRP Section 10.4 and in accordance with the requirements and guidance of II.E.1.1 of NUREG-0737 and II.K.2.(1) (item 1 of Table C.2) of NUREG-0660. The RSB reviewer consults with the ASB reviewer 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 limits; and reviews the core physics, fuel design, and core thermal- hydraulics data used in the SAR analysis as part of its primary review respon- sibility 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