Document: NUREG-0800
Document ID: 6d6e43af-f998-40fc-9062-1277b9cebd60
Document Type: srp
Title: REACTOR AUXILIARY COOLING WATER SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350544.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.2.2
CFR Part: 
CFR Title: 

Content:
on- ditions resulting from high and moderate energy line breaks and dynamic effects associated with flow instabilities and attendant loads (i.e., water hammer) during normal plant operation as well as during upset or accident conditions. 3. General Design Criterion 5, as related to shared systems and components important to safety being capable of performing required safety functions. 4. General Design Criterion 44, as its relates to: a. The capability to transfer heat leads from safety-related structures, systems, and components to a heat sink under both normal operating and accident conditions. b. Component redundancy so that safety functions can be performed assum- ing a single active component failure coincident with the loss of offsite power. c. The capability to isolate components, systems, or piping, if required, so that the system safety function will not be compromised. d. Task Action Plan items II.K.2.16 and II.K.A.25 of NUREGs-0718 and 0737 as they related to loss of cooling water to reactor coolant pump (RCP) seals. e. A single failure in the CWS does not result in fuel damage or reactor coolant leakage in excess of normal coolant-makeup capability. Single failure includes but is not limited to operator error, spurious activation of a valve operator, and loss of a cooling water pump. A moderate-energy leakage crack or an accident that is initiated from a failure in the CWS piping does not result in excessive fuel damage or reactor coolant leakage in excess of normal coolant-makeup capa- bility. A single active failure is considered when evaluating the consequences of this accident. Moderate leakage cracks are determined in accordance with the guidelines of Branch Technical Position ASB 3-1, "Protection Against Postulated Failures in Fluid Systems Outside Containment." It has been demonstrated by testing that the reactor coolant pumps will withstand a complete loss of cooling water for 20 minutes, and instrumentation in accordance with IEEE 279 that