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
CFR Part: 
CFR Title: 

Content:
ropriate consideration in the design basis of (1) the most severe natural phenomena historically reported, (2) combinations of normal and accident conditions with the effects of the natural phenomena, and (3) the importance of the safety functions threatened by the natural phenomena. o GDC 4, “Environmental and dynamic effects design bases,” requires appropriate protection for SSCs important to safety against dynamic effects, including the effects of missiles (e.g., falling heavy loads) that may result from equipment failures. The regulations in 10 CFR Part 52 establish criteria for the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. To that end, the specific 10 CFR Part 52 regulations applicable to this RG include the following: • 10 CFR 52.47, “Contents of applications; technical information;” 10 CFR 52.137, “Contents of applications; technical information;” and 10 CFR52.157, “Contents of applications; technical information in final safety analysis report;” , require, in part, that applicants for nuclear power facility standard design certifications, standard design approvals, and manufacturing licenses, respectively, include in the safety analysis report: the design of the facility (including the principle design criteria, the design bases, and the relationship of the design bases to the principle design criteria); and a description and analysis of auxiliary and fuel handling systems insofar as they are pertinent to showing that safety functions will be accomplished. The description shall be sufficient to permit understanding of the system designs and their relationship to safety evaluations. • 10 CFR 52.79, “Contents of applications; technical information in final safety analysis report,” requires, in part, that power reactor combined license applicants include in the safety DG - 1381, Page 3 of 16 analysis report: the