Document: NUREG-0800
Document ID: 5ba2907e-cf47-4a3b-b320-616735faa4cf
Document Type: srp
Title: AUXILIARY FEEDWATER SYSTEM (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350095.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.4.9
CFR Part: 
CFR Title: 

Content:
eedwater system, and system performance requirements during normal, abnormal, and accident conditions, the staff concludes that the design of the auxiliary feed- water system and supporting systems is acceptable and meets the Commission's regulations as set forth in General Design.Criteria 2, 4, 5, 19, 34, 44, 45, and 46. This conclusion is based on the following: 1. The AFW system design meets the requirements of General Design Criterion 2 with respect to protection against the effects of earthquakes since the safety related portions are designed to seismic'Category I requirements in accordance with position C.1 of Regulatory Guide 1.29 and the nonsafety-related portions are designed in accordance with position C.2 of Regulatory Guide 1.29. 2. The AFW system design meets the requirements of General Design Criterion 4 with respect to protection against the effects of pipe breaks and missiles. Acceptance was based on locating the AFW system pumps and trains in individual cubicles which separate redundant components and are protected against the effects of tornado missiles. Refer to the Chapter 3 sections of this report for a description of how this protection is accomplished. 3. 'The AFW system is designed in accordance with the requirements of General Design Criterion 5 with respect to sharing of structures systems and components. This is accomplished since a failure of any component including a pipe break and single active failure will not prevent the safe shutdown and cooldown of either unit (together or singularly). 4. The system design meets the requirements of General Design Criterion 19 as related to the design capability of system instrumentation and 10.4.9-8 Rev. 2- - July 1981 controls for prompt hot shutdown of the reactor and potential capabil- ity for subsequent cold shutdown since the design meets the requirement of Branch Technical Position RSB 5-1 which requires the capability to bring primary plant temperature to the RHR cut-in point following four