Document: NRC Regulatory Guide
Document ID: 1ff1e9f9-6081-422a-b088-bc699514103c
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
CFR Part: 
CFR Title: 

Content:
erface of the crane with other structures. ASME Std. NOG-1 is used for the design of overhead cranes with multiple girders and top running trollies using wire rope hoists. NRC endorsement of ASME Std. NOG-1 in this RG provides an update to the guidance in NRC technical report NUREG-0554. • ASME BTH-1 provides criteria for the design of special lifting devices and load lifting attachments. The staff endorses this standard in part, limiting the endorsed scope to that for mechanical special lifting devices conforming to Design Categories B and C as defined in the standard and excluding sections that address specialized equipment (e.g., electrical components, vacuum lifting devices, and electromagnetic lifting devices). This specialized equipment would not be acceptable for the principle safety function of retaining the suspended load, but specialized equipment may be mounted on a special lifting device for other purposes. The use of consensus standards where available is consistent with Commission policy and provides updated information reflecting operating experience and risk-informed considerations. The existing technical reports, NUREG-0612, issued August 1980, and NUREG-0554, issued May 1979, are outdated and do not reflect the current risk-informed perspective on heavy load handling activities. Background The staff recognizes that safe control of heavy load handling activities in nuclear facilities may be accomplished in several ways. The preferred method, as suggested in RG 1.13, is to design the layout of the facility so that overhead lifting equipment cannot operate over or near SSCs essential to accomplishment of fundamental safety functions.1 However, light-water reactor design and operation involve certain load handling activities, such as transfer of irradiated fuel from storage pools to dry storage and removal of the reactor vessel head and internal structures in support of refueling, which, if the load were dropped, could challenge the performance of