Document: NUREG-0800
Document ID: 824740ba-eb51-4b24-bd6f-df01c35d75f3
Document Type: srp
Title: LOSS OF NONEMERGENCY AC POWER TO THE STATION AUXILIARIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550008.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
CFR Part: 
CFR Title: 

Content:
ent analyses is provided in SRP Section 15.0. 2. Design basis radiological consequence analyses associated with design basis accidents are reviewed under SRP Section 15.0.3. 3. Aspects of the sequence described in the SAR are reviewed for whether the reactor and plant protection and safeguards controls and instrumentation systems function as assumed in the safety analysis for automatic actuation, remote sensing, indication, control, and interlocks with auxiliary or shared systems under SRP Chapter 7. 4. Technical specifications are reviewed under SRP Section 16.0. 15.2.6-3 Revision 2 - Month 2007 5. Reliability of the auxiliary feedwater system is reviewed to ensure compliance with the requirements and guidance of NUREG-0737, II.E.1.1, 2, and NUREG-0660, II.K.2.(1) (item 1 of Table C.2), and 10 CFR 50.34(f)(1)(ii) and 50.34(f)(2)(xii) under SRP Section 10.4.9. The reviewers consult on whether the operational assumptions for the auxiliary feedwater system including appropriate delay time for auxiliary feedwater initiation assumed in the analysis are appropriate (PWR). 6. Values of the parameters in the analytical models of the reactor core are reviewed for compliance with plant design and specified operating conditions, acceptance criteria for fuel cladding damage limits are determined, and the core physics, fuel design, and core thermal-hydraulics data in the SAR analysis are reviewed under SRP Sections 4.2, 4.3, and 4.4. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. General Design Criterion (GDC) 10, as to RCS design with appropriate margin so specified acceptable fuel design limits are not exceeded during normal operation including anticipated operational occurrences. 2. GDC 13, as to the availability of instrumentation to monitor variables and systems over their