Document: NRC Regulatory Guide
Document ID: ae72d1f2-aba4-4afd-bf00-6a4263c3f3e9
Document Type: regulatory_guide
Title: Control of Heavy Loads at Nuclear Facilities
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2100/ML21006A335.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.244
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CFR Title: 

Content:
otection against equipment failure that could result in a heavy load drop. It endorses, with clarifications, the American Society of Mechanical Engineers (ASME) Standard (Std.) NML-1, “Rules for the Movement of Loads Using Overhead Handling Equipment in Nuclear Facilities” (Ref. 1) and ASME Std. NOG-1, “Rules for Construction of Overhead and Gantry Cranes (Top Running Bridge, Multiple Girder)” (Ref. 2). It also endorses, with clarifications, Chapters 1-3 of ASME Std. BTH-1, “Design of Below-the-Hook Lifting Devices” (Ref. 3). The NRC staff expects endorsement of these consensus standards to provide safety and efficiency benefits. Applicability This RG applies to 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. 4), all applicants and licensees for a power reactor combined license under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 5), and applicants and licensees for an independent spent fuel storage installation (ISFSI) under 10 CFR Part 72, “Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste” (Ref. 6). This RG also applies, in part, to applicants and holders of standard design certifications, standard design approvals, or manufacturing licenses for power reactors under 10 CFR Part 52. Applicable Regulations The regulations in 10 CFR Part 50 establish criteria for the licensing of production and utilization facilities, including nuclear power plants. The specific sections applicable to this RG include the following: _____________________________________________________________________________________ DG - 1381, Page 2 of 16 • 10 CFR 50.34, “Contents of application; technical information,” requires, in part, that power reactor license applicants include in the safety analysis report: