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:
and all downstream piping to the nuclear steam supply system are designed in accordance with seismic Category I requirements. The review for seismic design and the review for seismic and quality group classification are performed as indicated in subsection I of this SRP section. 4. The CFS design is such that the plant can be safely shut down using the auxiliary feedwater system (PWR) or the reactor core isolation cooling system (BWR), if required. 5. The CFS design, or other plant systems, provide the capability to detect and control leakage from the system, including leakage from spargers. 6. The essential portion of the system has been designed so that system function will be maintained as required in the event of adverse environmental phenomena or loss of offsite power. The review for protection against natural phenomena is performed in the Chapter 3 SRP sections. The reviewer evaluates the system, using engineering 10.4.7-10 Revision 4 - March 2007 judgment and the results of failure modes and effects analyses, to determine that the failure of nonessential portions of the system or of other systems not designed to seismic Category I standards (and located close to essential portions of the system), will not preclude operation of the essential portions of the CFS. The reviewer shall also ensure that failure of nonseismic Category I structures that house, support, or are close to essential portions of the CFS will not preclude operation of the essential portions of the CFS. 7. Piping system designs, including material standards and inspection programs, incorporate adequate considerations to avoid erosion and corrosion. Guidance for acceptable inspection programs is found in Generic Letter 89-08 and in EPRI NP-3944, "Erosion/Corrosion in Nuclear Plant Steam Piping: Causes and Inspection Guidelines." 8. For BWRs, feedwater nozzle design, inspection, and testing procedures, and CFS operating procedures are adequate to minimize nozzle cracking at low feedwater flow.