Document: NUREG-0800
Document ID: a4637484-a66d-4066-b2e7-77b0ea7d3187
Document Type: srp
Title: 2.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070601.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.4.9.16
CFR Part: 
CFR Title: 

Content:
4. General Design Criterion 44 (GDC 44), "Cooling Water," as it relates to: 46 a. The capability to transfer heat loads from the reactor system to a heat sink under both normal operating and accident conditions. b. Redundancy of components so that under accident conditions the safety function can be performed assuming a single active component failure. (This may be coincident with the loss of offsite power for certain events.) c. The capability to isolate components, subsystems, or piping if required so that the system safety function will be maintained. 5. General Design Criterion 45 (GDC 45), "Inspection of Cooling Water System," as 47 related to design provisions to permit periodic inservice inspection of system components and equipment. 6. General Design Criterion 46 (GDC 46), "Testing of Cooling Water System," as related 48 to design provisions to permit appropriate functional testing of the system and components to assureensure structural integrity and leak-tightness, operability and 49 performance of active components, and capability of the integrated system to function as intended during normal, shutdown, and accident conditions. Technical Rationale The technical rationale for application of these acceptance criteria to reviewing the condensate and feedwater system is discussed in the following paragraphs:50 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 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