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:
safety analysis report (FSAR). Upon request from the primary reviewer, the interface reviewers will provide input for the areas of review stated in subsection I. The primary reviewer obtains and uses such input as required to ensure that this review procedure is complete. The SAR is reviewed to determine that the system description and diagrams delineate the function of the condensate and feedwater system under normal and abnormal conditions. The reviewer verifies the following: 1. The system has been designed to function as required for all modes of operation. The results of failure modes and effects analyses presented in the SAR, if any, are used in making this determination. 2. The system piping is designed to preclude hydraulic instabilities from occurring in the piping for all modes of operation. As appropriate, the reviewer evaluates the results of model tests and analyses that are relied on to verify that water hammer will not occur, or proposed tests of the installed system that are intended to verify design adequacy. Steam generators are reviewed in accordance with Branch Technical Position 10-2. The feedwater control valve and controller design shall be verified to be stable and to be compatible with system(s) under imposed operating conditions (e.g., control functions required, range of control and pressure drop characteristics, valve stroke, trim, etc.). Test data or operating experience data shall be used where available. In addition, the applicant has committed to review plant operating and maintenance procedures to ensure that precautions for avoidance of steam/water hammer and water hammer occurrences have been provided. Guidance for water hammer prevention and mitigation is found in NUREG-0927. 3. The outermost containment isolation valves 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