Document: NUREG-0800
Document ID: dd8f36ba-bf50-446f-97d9-20e92cbdee8a
Document Type: srp
Title: CONDENSATE AND FEEDWATER SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070380221.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.4.7
CFR Part: 
CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of power conversion systems Secondary - None 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. The primary reviewer reviews the CFS from the condenser outlet, up to and including the nozzle connections with the nuclear steam supply system, the feedwater spargers, and the heater drain system to ensure conformance to General Design Criteria (GDC) 2, 4, 5, 44, 45, and 46. For PWRs, there are also interfaces with the secondary water makeup 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. 10.4.7-2 Revision 4 - March 2007 The specific areas of review are as follows: 1. Review of the characteristics of the CFS with respect to the capability to supply adequate feedwater to the nuclear steam supply system as required for normal operation and shutdown. 2. Determination that an acceptable design has been established for: 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 (PWR), including the auxiliary feedwater system