Document: NUREG-0800
Document ID: 8d959e53-4b1e-4b41-a530-d9544d6801c3
Document Type: srp
Title: CONDENSATE AND FEEDWATER SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070601.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.4.7
CFR Part: 
CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Auxiliary Systems Branch (ASB)Plant Systems Branch (SPLB)1 Secondary - NoneCivil Engineering and Geosciences Branch (ECGB)2 I. AREAS OF REVIEW The condensate and feedwater system (CFS) provides feedwater at the required temperature, pressure, and flow rate to the reactor for boiling water reactor (BWR) plants and to the steam generators for pressurized water reactor (PWR) plants. Condensate is pumped from the main condenser hotwell by the condensate pumps, passes through the low-pressure feedwater heaters to the feedwater pumps, and then is pumped through the high-pressure feedwater heaters to the nuclear steam supply system. ASBSPLB reviews the CFS from the condenser outlet to the, up to and including the nozzle 3 connections with the nuclear steam supply system, the feedwater spargers, and to the heater 4 drain system to assureensure conformance to General Design Criteria 2, 4, 5, 44, 45, and 46. 5 For indirect cycle plantsPWRs, there are also interfaces with the secondary water makeup 6 system and the auxiliary feedwater system. The CFS is used for normal shutdown. The only part of the CFS classified as safety-related, i.e., required for safe shutdown or in the event of postulated accidents, is the feedwater piping from the steam generators for PWRs and from the nuclear steam supply system for BWRs, up to and including the outermost containment isolation valve. 1. The ASBSPLB reviews the characteristics of the CFS with respect to the capability to 7 supply adequate feedwater to the nuclear steam supply system as required for normal operation and shutdown. DRAFT Rev. 4 - April 1996 10.4.7-2 2. The ASBSPLB review determines that an acceptable design has been established for: 8 a. The interfaces of the CFS with the auxiliary feedwater system (PWR), the reactor core isolation cooling system (BWR), and the condensate cleanup system with regard to functional design requirements and seismic design classification. b. The feedwater system