Document: NUREG-0800
Document ID: 6fd4d885-bb73-4ac0-9513-7365558c831e
Document Type: srp
Title: REACTOR AUXILIARY COOLING WATER SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550053.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.2.2
CFR Part: 
CFR Title: 

Content:
ontained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. GDC 2 as to capability of structures housing the system and the system itself to withstand the effects of natural phenomena like earthquakes, tornadoes, hurricanes, and floods. 2. GDC 4 as to effects of missiles inside and outside of containment, effects of pipe whip, jets, environmental conditions from high- and moderate-energy line breaks, and dynamic effects of flow instabilities and attendant loads (i.e., water hammer) during normal plant operation as well as upset or accident conditions. 3. GDC 5 as to capability of shared systems and components important to safety to perform required safety functions. 4. GDC 44 as to: A. The capability to transfer heat loads from safety-related SSCs to a heat sink under both normal operating and accident conditions. B. Component redundancy for performance of safety functions assuming a single, active component failure coincident with the loss of offsite power. C. The capability to isolate components, systems, or piping, if required, so system safety functions are not compromised. D. Remote manual isolation of the RCP seal coolant water by the main control room operator for continued long-term pump operation in an actual event. E. Whether a single CWS failure results 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. F. 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 evaluations of the consequences of this accident. Moderate leakage cracks are determined in accordance with the guidelines of