Document: NUREG-0800
Document ID: b1bccb14-17b6-422b-93ee-6d4f00b6512b
Document Type: srp
Title: CHILLED WATER SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1510/ML15103A559.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.2.7
CFR Part: 
CFR Title: 

Content:
afety functions to be performed. 2. GDC 2, “Design Bases for Protection against Natural Phenomena,” as to SSCs important to safety being designed to withstand the effects of natural phenomena such as earthquakes, tornadoes, hurricanes, tsunami, seiches and floods without loss of capability to perform their safety functions (as it relates to containment isolation function only). 3. GDC 4, “Environmental and Dynamic Effects Design Bases,” as to SSCs important to safety being appropriately protected against dynamic effects, including the effects of missiles, pipe whipping and discharging fluids that may result from equipment failures and from events and conditions outside the nuclear power unit. 4. GDC 5, “Sharing of Structures, Systems, and Components,” as to SSCs important to safety which shall be designed not to be shared among nuclear power units unless it can be shown that such sharing will not significantly impair their ability to perform their safety functions. 5. GDC 44, “Cooling Water,” as to: A. The capability to transfer heat loads from safety-related SSCs to a heat sink under both normal operating and accident conditions. 9.2.7-7 Revision 0 – September 2015 B. Component redundancy for performance of safety functions assuming a single, active component failure coincident with the loss of offsite power (LOOP). C. The capability to isolate components, systems, or piping, if required, so system safety functions are not compromised. D. Whether a single CWS failure results in fuel damage or reactor coolant leakage in excess of normal coolant-makeup capability. Sources of single failure include, but are not limited to, operator error, spurious activation of a valve operator, and loss of a cooling water pump. E. Whether a moderate-energy leakage crack or an accident from a CWS piping failure results in excessive fuel damage or reactor coolant leakage in excess of normal coolant makeup capability. A single active failure is considered in