Document: NUREG-0800
Document ID: 2cb61281-91f4-400a-8eda-41e187e51d77
Document Type: srp
Title: AUXILIARY FEEDWATER SYSTEM (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070570007.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.4.9
CFR Part: 
CFR Title: 

Content:
SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. The procedures below are used during the construction permit (CP) review to determine that the design criteria and bases and the preliminary design as set forth in the preliminary safety analysis report meet the acceptance criteria given in subsection II. For operating license (OL) or applications, the procedures are utilized to verify that the initial design criteria and bases have been appropriately implemented in the final design as set forth in the final safety analysis report. The procedures for OL applications also include a determination that the content and intent of the technical specifications prepared by the applicant are in agreement with the requirements for system testing, minimum performance and surveillance developed as a result of the staff's review. Upon request from the primary reviewer, the coordinating review organizations will provide input for the areas of review stated in subsection I. The primary reviewer obtains and uses such input as required to assure that this review is complete. 10.4.9-11 Revision 3 - March 2007 For the purpose of this SRP section, a typical system is assumed which has redundant auxiliary feedwater trains, with a 50-percent capacity motor-driven pump in each train feeding directly to the steam generators, and a 100-percent capacity steam turbine-driven pump able to supply either of the redundant trains. The pumping capacity should permit the system to hold the plant at hot standby and subsequently to cool down the reactor at specified cool-down rates. The 50-percent capacity pump should have sufficient capacity for decay heat removal following any accident or transient although cool down to RHR cut in temperature may take longer than design. This capability