Document: NRC Regulatory Guide
Document ID: cdc706d5-60ed-40a4-b55a-9771904107a7
Document Type: regulatory_guide
Title: Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1809/ML18093A675.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.100
CFR Part: 
CFR Title: 

Content:
he seismic qualification of electrical and active mechanical equipment and the functional qualification of active mechanical equipment for nuclear power plants (NPPs). Applicability This RG applies to reactor applicants and licensees subject to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, “Domestic Licensing of Production and Utilization Facilities” (Ref. 1), and 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 2). Applicable Regulations • 10 CFR Part 50 provides for the licensing of production and utilization facilities. o Appendix A, “General Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50 contains general design criteria (GDC) for NPPs. GDC related to seismic qualification of electrical and active mechanical equipment and functional qualification of active mechanical equipment for nuclear power plants include the following: - GDC 1, “Quality Standards and Records” - GDC 2, “Design Bases for Protection against Natural Phenomena” - GDC 14, “Reactor Coolant Pressure Boundary” DG-1328, Page 2 - GDC 15, “Reactor Coolant System Design” - GDC 30, “Quality of Reactor Pressure Boundary” - GDC 37, “Testing of Emergency Core Cooling System” - GDC 40, “Testing of Containment Heat Removal System” - GDC 43, “Testing of Containment Atmosphere Cleanup Systems” - GDC 46, “Testing of Cooling Water System” - GDC 54, “Systems Penetrating Containment” o Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50 establishes quality assurance requirements for the design, manufacture, construction, and operation of NPP structures, systems, and components (SSCs) that prevent or mitigate the consequences of postulated accidents that could cause undue risk to public health and safety. The pertinent requirements of Appendix B apply to all activities that affect the safety-related functions of those SSCs. o