Document: NRC Regulatory Guide
Document ID: 7fa0e9f9-cb40-463b-adc5-53fe2057e43f
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:
d 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 NEI 12-16, Revision 4, the following documents may include information that is useful to users of this guidance. • NUREG-1475, “Applying Statistics,” (Ref. 6), provides an overview of different statistical approaches that may be used in demonstrating compliance with the requirement in 10 CFR 50.68(b) for 95-percent probability, 95-percent confidence level, including limitations on their area of applicability. • NUREG/CR-7108, “An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses—Isotopic Composition Predictions,” (Ref. 7), provides guidance on the expected uncertainty associated with actinides and fission products in nuclear criticality safety analyses where the burnup of the spent fuel assemblies is credited. • NUREG/CR-6683, “A Critical Review of the Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent Fuel Pool Storage,” (Ref. 8), describes limitations to the use of “fresh fuel equivalencing” methods used by some licensees. DG-1373, Page 3 • NUREG/CR-1547, “Criticality Experiments with Subcritical Clusters of 2.35 Wt% and 4.31 Wt% 235U Enriched UO2 Rods in Water at a Water-to-Fuel Volume Ratio of 1.6,” (Ref. 9), provides an additional source of experiments for criticality code validation. • NUREG/CR-7109, “An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses—Criticality (keff) Predictions,” (Ref. 10), provides additional information relevant to using NUREG/CR-7108. • NUREG/CR-7194, “Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems,” (Ref. 11), provides additional information regarding the use of