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:
perform containment atmosphere cleanup following a postulated accident. o 10 CFR Part 50, Appendix A, GDC 42, “Inspection of containment atmosphere cleanup systems,” requires that the containment atmosphere cleanup systems be designed to permit the appropriate periodic inspection of important components. o 10 CFR Part 50, Appendix A, GDC 43, “Testing of containment atmosphere cleanup systems,” requires, in part, that the containment atmosphere cleanup systems be designed to permit appropriate periodic testing to ensure their integrity and operability. o 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” applies to all components of the facility, which would include suction strainer design, fabrication, testing, and operation. o 10 CFR Part 50, Appendix B, Section XI, “Test Control,” requires that a test program be established to assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service. The regulation requires that appropriate testing be identified and performed in accordance with written test procedures that DG-1385, Page 3 incorporate the requirements and acceptance limits contained in design documents. As components the ECCS suction strainers are subject to the requirements of 10 CFR 50, Appendix B, Section XI. For nuclear power plants licensed before the GDC were developed, the licensee’s updated final safety analysis report provides the applicable design criteria. • 10 CFR Part 52 addresses licenses, certifications, and approvals for nuclear power plants. o 10 CFR 52.48, “Standards for review of applications,” states that the GDC and quality assurance criteria also apply to nuclear power reactor licenses issued under 10 CFR Part 52. Related Guidance • NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition” (Ref. 4) Purpose of Regulatory Guides