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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ted safely and that the plant licensing bases accurately reflect facility heavy load handling practices. These guidance documents continue to be relevant to those facilities that have incorporated the regulatory information into their facility licensing basis. However, ASME Std. NML-1 included changes to heavy load handling guidance derived from operating experience and an allowance for incorporation of existing heavy load handling program elements adopted through implementation of the NEI initiative. Therefore, licensees that choose to adopt the guidelines of ASME Std. NML-1 have implicitly adopted the guidance associated with the NUREGs and generic communications discussed above and further consideration of their content during license applications and other change processes is not necessary. Consideration of International Standards The International Atomic Energy Agency (IAEA) works with member states and other partners to promote the safe, secure, and peaceful use of nuclear technologies. The IAEA develops Safety Requirements and Safety Guides for protecting people and the environment from harmful effects of ionizing radiation. This system of safety fundamentals, safety requirements, safety guides, and other relevant reports, reflects an international perspective on what constitutes a high level of safety. To inform its development of this RG, the NRC considered IAEA Safety Requirements and Safety Guides pursuant to the Commission’s International Policy Statement (Ref. 13), and Management Directive and Handbook 6.6, “Regulatory Guides” (Ref. 14). The following IAEA Safety Requirements were considered in the development/ update of this Regulatory Guide: • IAEA Specific Safety Requirements (SSR)-2/1, “Safety of Nuclear Power Plants: Design” (Ref. 15), addresses design considerations for overhead lifting equipment in nuclear power plants in Section 6, “Design of Specific Plant Systems,” as “Requirement 76: Overhead Lifting Equipment,” and