Document: NUREG-0800
Document ID: 4b58df3f-1f93-4271-aa73-22de04083915
Document Type: srp
Title: LOSS OF NORMAL FEEDWATER FLOW
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070300709.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.7
CFR Part: 
CFR Title: 

Content:
tions (e.g., interface requirements and site parameters) included in the referenced DC. 15.2.7-3 Revision 2 - March 2007 Review Interfaces Other SRP sections interface with this section as follows: 1. General information on transient and accident 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. 1. 3. 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. 4. Technical specifications are reviewed under SRP Section 16.0. 5. Reliability of the auxiliary feedwater system is reviewed to ensure compliance with the requirements of 10 CFR 50.34(f)(1)(ii), 10 CFR 50.34(f)(2)(xii), and the guidance of TMI Action Item II.K.2.19 of NUREG-0737 under SRP Section 10.4.9. 6. Operational assumptions as factored into related instrumentation and controls for the auxiliary feedwater system used in the analysis are reviewed for appropriateness, under SRP Sections 7.2 through 7.5. 7. Instrumentation and controls aspects of the sequence described in the SAR is reviewed to confirm that 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, interlocks with auxiliary or shared systems and compliance with Regulatory Guide 1.105 under SRP Sections 7.2 through 7.5. Design of the auxiliary feedwater system is also evaluated to determine that: i. the requirements and guidance of 10 CFR 50.34(f)(2)(xii) are met, and ii. the appropriate delay time for auxiliary feedwater initiation is assumed in the analysis. The specific acceptance