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:
essed by this SRP section is discussed in the following paragraphs: 1. GDC 2 requires that structures, systems, and components important to safety shall be designed to withstand the effects of natural phenomena such as earthquakes. This criterion applies to SRP Section 10.4.7 because the review identifies CFS components important to safety and determines that they are designed to withstand the 10.4.7-7 Revision 4 - March 2007 effects of earthquakes and other natural phenomena. Regulatory Guide 1.29, Positions C.1 and C.2, provide guidance for determining compliance with this criterion. Meeting the requirements of this criterion provides a level of assurance that the capability to shut down the reactor safety will be maintained during the most severe expected earthquake or other natural phenomena. 2. GDC 4 requires that structures, systems, and components important to safety shall be appropriately protected against dynamic effects that may result from equipment failures and from events and conditions outside the nuclear power unit. GDC 4 applies to SRP Section 10.4.7 because the review verifies that CFS components important to safety are protected against the effects of high-energy pipe ruptures. This review also considers the dynamic consequences of flow instabilities (specifically, water hammer) resulting from normal operation and during anticipated operational occurrences. Meeting the requirements of this criterion provides further assurance that the integrity of the feedwater piping inside the containment structure will be maintained, thereby minimizing the likelihood of a loss-of-coolant accident that could cause fuel damage. 3. GDC 5 requires that structures, systems, and components important to safety shall not be shared by nuclear power units, unless it can be shown that such sharing will not significantly impair the ability to perform safety functions, including an orderly shutdown and cooldown of remaining units in the event of an accident in one unit. GDC