Document: NRC Regulatory Guide
Document ID: 28bfa464-f1cc-4f82-9b3c-4cfbe773e040
Document Type: regulatory_guide
Title: Fresh and Spent Fuel Pool Criticality Analysis + HISTORY - HISTORY 08/2020 – DG-1373 , Proposed Revision 0
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2018/ML20182A788.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.240
CFR Part: 
CFR Title: 

Content:
ed in fresh fuel vaults and spent fuel pools at light-water reactor (LWR) power plants. It endorses, with clarifications and exceptions, the Nuclear Energy Institute (NEI) guidance document NEI 12-16, “Guidance for Performing Criticality Analyses of Fuel Storage at Light-Water Reactor Power Plants,” Revision 4, (Ref. 1). Applicability This RG applies to licensees and applicants subject to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities,” (Ref. 2), or 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” (Ref. 3). With respect to 10 CFR Part 50, this RG applies to holders of and applicants for a construction permit or operating licenses. With respect to 10 CFR Part 52, this RG applies to holders of and applicants for combined licenses, standard design certifications, standard design approvals, and manufacturing licenses. Applicable Rules and Regulations • 10 CFR Part 50, “Domestic licensing of production and utilization facilities,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion 62, “Prevention of criticality in fuel storage and handling,” (Ref. 4), requires that criticality in the fuel storage and handling system shall be prevented by physical systems or processes, preferably by use of geometrically safe configurations. o 10 CFR 50.68, “Criticality accident requirements,” contains criticality accident requirements for a construction permit or operating license for nuclear power reactors issued under 10 CFR Part 50 or a combined license issued for a nuclear power reactor under 10 CFR Part 52. Specifically, this RG provides guidance for licenses or applicants to comply with the criticality safety requirements of 10 CFR 50.68(b). DG-1373, Page 2 • 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” governs the issuance of early site permits, standard design