Document: NRC Regulatory Guide
Document ID: 6f0a99f2-d25a-44e3-b7f2-3286449a9752
Document Type: regulatory_guide
Title: Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident (Rev. 5)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2126/ML21266A185.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.82
CFR Part: 
CFR Title: 

Content:
s for sumps and suppression pools that provide water sources for emergency core cooling, containment heat removal, or containment atmosphere cleanup systems. It also provides guidelines for evaluating the adequacy and the availability of the sump or suppression pool for long-term recirculation cooling following a loss-of-coolant accident (LOCA), and the use of containment accident pressure (CAP) in determining the net positive suction head (NPSH) for the emergency core cooling and containment heat removal pumps. This guide applies to both the pressurized-water reactor (PWR) and boiling-water reactor (BWR) types of light-water reactors. Applicability This RG applies to reactor licensees subject to Title 10 of the Code of Federal Regulations (10 CFR) Part 20, “Standards for Protection against Radiation” (Ref. 1), and Appendix I, “Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion ‘As Low as is Reasonably Achievable’ for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents,” to 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities” (Ref. 2). It also applies to all holders of and applicants for a power reactor combined license, design certification, standard design approval, or manufacturing license under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 3). Applicable Regulations • 10 CFR Part 50 provides regulations for licensing production and utilization facilities. o 10 CFR 50.46(b)(5) requires that licensees of nuclear power plants provide long-term cooling of the reactor core. DG-1385, Page 2 o 10 CFR Part 50, Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion (GDC) 1, “Quality standards and records,” requires that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance