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:
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 certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. o 10 CFR 52.79(a)(43) requires that applications for a combined license must include sufficient information to demonstrate compliance with the requirements of 10 CFR 50.68. o 10 CFR 52.47(a)(17) requires that applicants for a standard design certification comply with the requirements for criticality accidents in 50.68(b)(2)-(b)(4). o 10 CFR 52.137(a)(17) requires that applicants for a standard design approval comply with the requirements for criticality accidents in 50.68(b)(2)-(b)(4). o 10 CFR 52.157(a)(8) requires that applicants for a manufacturing license comply with the requirements for criticality accidents in 50.68(b)(2)-(b)(4). • 10 CFR Part 70, “Domestic Licensing of Special Nuclear Material,” (Ref. 5), governs the issuance of licenses to receive, possess, deliver, and transfer special nuclear material. o 10 CFR 70.24, “Criticality accident requirements,” provides that licensees authorized to possess special nuclear material that exceeds specified amounts, must maintain a monitoring system to detect criticality, maintain emergency response plans should a criticality occur, and to periodically conduct drills to exercise those plans. A common practice was for commercial power reactor licensees to request exemptions to 10 CFR 70.24. Typically, those exemptions were granted if the licensee demonstrated sufficient subcriticality to criteria very similar to those in 10 CFR 50.68(b)(2)-(4). When the NRC issued 10 CFR 50.68 in 1998, licensees had the option to retain their exemption to 10 CFR 70.24. This guidance applies to the applicable portions of those exemptions. Related Guidance In addition to the NUREG and NUREG/CR documents listed in