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:
Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent Fuel Pool Storage,” ORNL/TM-2000/230, Oak Ridge National Laboratory, Washington, DC, September 2012 (ADAMS Accession No. ML003751298) 9. NRC, 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,” PNL- 3314, Pacific Northwest National Laboratory, Washington, DC, July 1980. (ADAMS Accession No. ML070310488) 10. NRC, NUREG/CR-7109, “An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses—Criticality (keff) Predictions,” ORNL/TM-2011/514, Oak Ridge National Laboratory, Washington, DC April 2012 (ADAMS Accession No. ML12116A128) 2 Publicly available NRC published documents are available electronically through the NRC Library on the NRC’s public Web site at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRC’s Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html. The documents can also be viewed online or printed for a fee in the NRC’s Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD. For problems with ADAMS, contact the PDR staff at 301-415-4737 or (800) 397-4209; fax (301) 415-3548; or e-mail pdr.resource@nrc.gov. DG-1373, Page 12 11. NRC, NUREG/CR-7194, “Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems,” ORNL/TM-2014/240, Oak Ridge National Laboratory, Washington, DC, April 2015 (ADAMS Accession No. ML15097A186 12. NRC, Regulatory Guide 1.13, “Spent Fuel Storage Facility Design Basis,” Washington, DC. 13. NRC, Information Notice 1997-77, “Exemptions from the Requirements of Section 70.24 of Title 10 of the Code of Federal Regulations,” Washington, DC, October 10, 1997. 14. NRC, DSS-ISG-2010-01, “Staff Guidance Regarding the Nuclear Criticality Safety Analysis for Spent Fuel