Document: NUREG-0800
Document ID: eb0ea00d-43e4-45d1-8a5e-4daa4263d2cf
Document Type: srp
Title: EMERGENCY CORE COOLING SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550068.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.3
CFR Part: 
CFR Title: 

Content:
ur prematurely (not enough inventory to provide pump suction) and adversely affect the accident (addresses GI-24). 8. The availability of an adequate source of water for the ECCS is confirmed, and the source volume, location, and susceptibility to failure (e.g., freezing) are evaluated. In PWRs, the piping from the water source to the ECCS safety injection pumps is evaluated for conformance with Branch Technical Position 6-5. 9. The ECCS flow paths are reviewed to determine the extent to which flow from the ECCS pumps is diverted as a backup feature to other safeguards equipment (e.g., RHR, containment spray). The reviewer should confirm that the remaining portion of the flow provides abundant core cooling, despite the most severe single failure that affects ECCS flow. 10. For a BWR or the advanced passive safety plants (both BWR and PWR), the reactor coolant ADS systems are reviewed utilizing the following additional procedures to verify compliance with the Acceptance Criteria: A. The ADS systems, including electrical power supplies, are reviewed to verify they have sufficient independence, redundancy, and capability to allow the ADS to function properly assuming a single failure. B. The ADS design is reviewed to verify that actuation of the system can be completed automatically and that manual actuation is not required to assure adequate core cooling. C. Design features and system analysis to verify performance of the ADS under all accident conditions are reviewed. The reviewer should verify the ADS can satisfy performance requirements without taking credit for non-safety-related equipment or instrumentation, and accounting for normal air (or nitrogen) leakage through the valves. For those BWR applicants which use a pneumatic supply for the ADS function, the capability and design of the pneumatic supply system is reviewed under SRP Section 9.3.1. 6.3-12 Revision 3 - March 2007 D. The applicant’s evaluation of the ADS with respect to reactor vessel integrity