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:
ications; 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 design of the facility (including the principle design criteria, the design bases, and the relationship of the design bases to the principle design criteria); a description and analysis of auxiliary and fuel handling systems insofar as they are pertinent to showing that safety functions will be accomplished, and a description of plans for conduct of normal operations, including maintenance, surveillance, and periodic testing of SSCs. The description shall be sufficient to permit understanding of the system designs and their relationship to safety evaluations. The regulations in 10 CFR Part 72 establish criteria for the issuance of specific or general licenses to receive, transfer, and possess power reactor spent fuel, power reactor-related greater than Class C (GTCC) waste, and other radioactive materials associated with spent fuel storage in an ISFSI. To that end, the specific 10 CFR Part 72 regulations applicable to this RG include the following: • 10 CFR72.24, “Contents of application: Technical information,” requires, in part, that applicants for ISFSIs include in the application: the design of the facility (including design criteria, the design bases, materials of construction, and applicable codes and standards); an evaluation of the design of SSCs important to safety with regard to their performance in preventing or mitigating accidents; and a description of the quality assurance program that satisfies the requirements of 10 CFR Part 72, Subpart G, “Quality Assurance,” applied to design, fabrication, construction, testing, and operation of SSCs important to safety. • 10 CFR 72.122, “Overall requirements,” requires, in part, that SSCs important to safety must be designed to withstand postulated accidents, such as handling system component