Document: NRC Regulatory Guide
Document ID: 46049842-54a7-40a0-a0cc-ab115059f05e
Document Type: regulatory_guide
Title: Ultimate Heat Sink for Nuclear Power Plants + HISTORY - HISTORY DG-1275 , Proposed Revision 3, published 09/2013 (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1304/ML13043A624.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.27
CFR Part: 
CFR Title: 

Content:
ite power is not available) the system safety function can be accomplished, assuming a single failure. GDC 45, “Inspection of Cooling Water System,” requires that the cooling water system shall be designed to permit appropriate periodic inspection of important components, such as heat exchangers and piping, to assure the integrity and capability of the system. GDC 46, “Testing of Cooling Water System,” requires that the cooling water system shall be designed to permit appropriate periodic pressure and functional testing to assure: (1) the structural and leak-tight integrity of its components, (2) the operability and the performance of the active components of the system, and (3) the operability of the system as a whole and, under conditions as close to design as practical, the performance of the full operational sequence that brings the system into operation for reactor shutdown and for loss-of-coolant accidents, including operation of applicable portions of the protection system and the transfer between normal and emergency power sources. 10 CFR 50.65 “Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants”, also known as the Maintenance Rule, requires in part that SSCs that are relied upon to remain functional during and following design basis events be subjected to performance monitoring in a manner sufficient to provide assurance that they will perform their safety functions, as designed. In addition, nuclear power plant facility licensees and applicants must meet the minimum requirements for quality assurance (QA) in Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50. These regulatory criteria apply to an application for a construction permit or operating license under 10 CFR Part 50, or an application for a standard design certification, combined license, or standard design approval under 10 CFR Part 52, “Licenses, Certifications, and Approvals for