Guidance for DOE Use of NRC Certificates
NRC NUREGs [link to NRC website: NUREG-Series Publications] 
NUREG-1458: Emergency Response to a Highway Accident on Springfield, Mass., on December 16, 1991
NUREG-1536: Standard Review Plan for Spent Fuel Dry Storage Systems at a General License Facility
NUREG-1608: Categorizing and Transporting Low Specific Activity Materials and Surface Contaminated Objects
NUREG-1609: Standard Review Plan for Transportation Packages for Radioactive Material (consolidated in NUREG-2216 August 2020)
NUREG-1617: Standard Review Plan for Transportation Packages for Spent Nuclear Fuel (consolidated in NUREG-2216 August 2020)
NUREG-1617, Supplement 1: Standard Review Plan for Transportation Packages for MOX Spent Nuclear Fuel
NUREG-1660: U.S.-Specific Schedules of Requirements for Transport of Specified Types of Radioactive Material Consignments
NUREG-1815: Recommendations for Protecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers up to Four Inches Thick (basis for Reg. Guide 7.11)
NUREG-1886: Joint Canada - United States Guide for Approval of Type B(U) and Fissile Material Transportation Packages
NUREG-1927: Standard Review Plan for Renewal of Spent Fuel Dry Cask Storage System Licenses and Certificates of Compliance
NUREG-2125: Spent Fuel Transportation Risk Assessment
NUREG-2216: Standard Review Plan for Transportation Packages for Spent Fuel and Radioactive Material
NUREG/BR-0292: NRC brochure on Safety of Spent Fuel Transportation, published March 2003.
NUREG/CR-0128: Shock and Vibration Environments for a Large Shipping Container during Truck Transport
NUREG/CR-0322: Effects of Temperature on the Energy Absorbing Characteristics of Redwood
NUREG/CR-0481: An Assessment of Stress-Strain Data Suitable for Finite-Element Elastic-Plastic Analysis of Shipping Containers
NUREG/CR-2146, Volume 1: Dynamic Analysis to Establish Normal Shock and Vibration of Radioactive Material Shipping Packages
NUREG/CR-2146, Volume 2: Dynamic Analysis to Establish Normal Shock and Vibration of Radioactive Material Shipping Packages
NUREG/CR-2146, Volume 3: Dynamic Analysis to Establish Normal Shock and Vibration of Radioactive Material Shipping Packages
NUREG/CR-3019: Recommended Welding Criteria For Use in the Fabrication of Shipping Containers for Radioactive Materials [3-MB file]
NUREG/CR-3452: Mechanical Analysis of a Transportation Accident Involving Empty Shipping Casks for Radioactive Material Near Hilda, SC, in November 1982
NUREG/CR-3760: A Study on Ductile and Brittle Failure Design Criteria for Ductile Cast Iron Spent-Fuel Shipping Containers
NUREG/CR-3826: Recommendations for Protecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers Greater than Four Inches Thick
NUREG/CR-3854: Fabrication Criteria for Shipping Containers [3-MB file]
NUREG/CR-3966: Methods for Impact Analysis of Shipping Containers
NUREG/CR-4035: A Highway Accident Involving Radio-pharmaceuticals Near Brookhaven, MS, on December 3, 1983
NUREG/CR-4363: A Study on Fabrication Criteria for Ductile Cast Iron Spent-Fuel Shipping Containers
NUREG/CR-4554: SCANS, A Microcomputer Based Analysis System for Shipping Cask Design Review [10-MB file]
NUREG/CR-4775: Guide for Preparing Operating Procedures for Shipping Packages [8-MB file]
NUREG/CR-4829: Shipping Container Response to Severe Highway and Railway Accident Conditions [9-MB file]
NUREG/CR-5342: Assessment and Recommendations for Fissile-Material Packaging Exemptions and General Licenses Within 10 CFR Part 71
NUREG/CR-5403: Predicting the Pressure Dimension Flow of Gasses Through Micro-Capillaries and Micro-Orifices [3-MB file]
NUREG/CR-5502: Engineering Drawings for 10 CFR Part 71 Package Approvals
NUREG/CR-5657: AUTOCASK: A Microcomputer Based System for Shipping Cask Design Review Analysis [6-MB file]
NUREG/CR-5661: Recommendations for Preparing the Criticality Safety Evaluation of Transportation Packages
NUREG/CR-5892: A Highway Accident Involving Unirradiated Nuclear Fuel in Springfield, Mass., on December 16, 1991
NUREG/CR-6007: Stress Analysis of Closure Bolts for Shipping Casks
NUREG/CR-6314: Quality Assurance Inspections for Shipping and Storage Containers
NUREG/CR-6322: Buckling Analysis of Spent Fuel Basket [3-MB file]
NUREG/CR-6361: Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages [19-MB file]
NUREG/CR-6407: Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety
NUREG/CR-6487: Containment Analysis for Type B Packages Used to Transport Various Contents [3-MB file]
NUREG/CR-6673: Hydrogen Generation in TRU Waste Transportation Packages [6-MB file]
NUREG/CR-6802: Recommendations for Shielding Evaluations for Transport & Storage Packages
NUREG/CR-6886: Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire Scenario [9-MB file]
NUREG/CR-7239: Review of Exemptions and General Licenses for Fissile Material in 10 CFR 71
NRC Regulatory Guides [link to NRC website: Transportation (Division 7): Regulatory Guides ]
Reg Guide 7.1: Administrative Guide for Packaging and Transporting Radioactive Material
Reg Guide 7.2: Packaging and Transportation of Radioactively Contaminated Biological Materials
Reg Guide 7.3: Procedures for Picking Up and Receiving Packages of Radioactive Material
Reg Guide 7.4: Leakage Tests on Packages for Shipment of Radioactive Materials, (Revision 2, 07/2020)
Reg Guide 7.5: Administrative Guide for Obtaining Exemptions from Certain NRC Requirements over Radioactive Material Shipments
Reg Guide 7.6: Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels
Reg Guide 7.7: Administrative Guide for Verifying Compliance with Packaging Requirements for Shipping and Receiving of Radioactive Material
Reg Guide 7.8: Load Combinations for the Structural Analysis of Shipping Casks for Radioactive Material
Reg Guide 7.9: Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material
Reg Guide 7.10: Establishing Quality Assurance Programs for Packaging Used in Transport of Radioactive Material
Reg Guide 7.11: Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Maximum Wall Thickness of 4 Inches (0.1 m)
Reg Guide 7.12: Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Wall Thickness Greater than 4 Inches (0.1 m) But Not Exceeding 12 Inches (0.3 m)
NRC Regulatory Issue Summaries [link to NRC website: Regulatory Issue Summaries]
Regulatory Issues Summary 2003-04: Use of the Effective Dose Equivalent in Place of the Deep Dose Equivalent in Dose Assessments
Regulatory Issues Summary 2003-07: Issuance of Regulations Revising Filing Requirements for Advance Notification of the Shipment of Spent Nuclear Fuel and Special Nuclear Material
Regulatory Issues Summary 2004-11: Supporting Information Associated with Requests for Withholding Proprietary Information
Regulatory Issues Summary 2004-18: Expiration Date for 10 CFR Part 71 Quality Assurance Program Approvals
Regulatory Issues Summary 2004-20: Lessons Learned from Review of 10 CFR Parts 71 and 72 Applications
Regulatory Issues Summary 2005-27, Revision 1: NRC Timeliness Goals, Prioritization of Incoming License Applications and Voluntary Submittal of Schedule for Future Actions for NRC Review
Regulatory Issues Summary 2005-31: Control of Security-Related Sensitive Unclassified Non-Safeguards Information Handled by Individuals, Firms, and Entities Subject to NRC Regulation of the Use of Source, Byproduct, and Special Nuclear Material
Regulatory Issues Summary 2006-01: Expiration Date for NRC-Approved Spent Fuel Transportation Routes
Regulatory Issues Summary 2006-05: Withdrawal of Transportation Safeguards Advisories SA-01-01, Rev.1 and SA-03-02
Regulatory Issues Summary 2006-11: Requesting Quality Assurance Program Approval Renewals Online by Electronic Information Exchange
Regulatory Issues Summary 2007-07: Clarification of Increased Controls for Licensees that Possess Collocated Radioactive material During Transportation Activities
Regulatory Issues Summary 2007-09: Examples of Recurring Requests for Additional Information (RAIs) for 10 CFR Part 71 and 72 Applications
Regulatory Issues Summary 2008-18 (Advanced Copy): Information on Requests for Extending Use of Expiring Transportation Packages
Regulatory Issues Summary 2011-03: Issuance of Spent Fuel Storage and Transportation (SFST)-14, "Acceptance Review Process"
Regulatory Issues Summary 2013-04: Content Specification and Shielding Evaluations for Type B Transportation Packages
Regulatory Issues Summary 2013-07: NRC Staff Position on the Use of American Society of Mechanical Engineers Certification Mark
Regulatory Issues Summary 2013-11: Resolution of Licensing Process Expectations for Pressurized Water Reactor Fuel Assemblies Susceptible to Top Nozzle Stress Corrosion Cracking in Dry Cask Spent Fuel Storage and Transportation
Regulatory Issues Summary 2015-08: Oversight of Couterfeit, Fraudulent, and Suspect Items in The Nuclear Industry
NRC Information Notices [link to NRC website: Information Notices]
Information Notice 80-25: Transportation of Pyrophoric Uranium, (Note: see also 49 CFR 173.418, Authorized packages - pyrophoric Class 7 (radioactive) materials)
Information Notice 84-72: Clarification of Conditions for Waste Shipments Subject to Hydrogen Gas Generation
Information Notice 97-47: Inadequate Puncture Tests For Type B Packages Under 10 CFR 71.73(c)(3)
Information Notice 97-51: Problems Experienced Loading and Unloading Spent Nuclear Fuel Storage and Transportation Casks
Information Notice 97-57: Leak Testing of Packaging Used in the Transport of Radioactive Material
Information Notice 97-86: Additional Controls for Transport of the Amersham Model No. 660 Series Radiographic Exposure Devices
Information Notice 99-15: Misapplication of 10 CFR Part 71 Transportation Shipping Cask Basis to 10 CFR Part 50 Design Basis
Information Notice 2002-31: Potentially Defective UF6 Cylinder Valves (1-Inch)
Information Notice 2002-31, Supplement 1: Potentially Defective UF6 Cylinder Valves (1-Inch)
Information Notice 2002-33: Notification of Permanent Injunction Against Neutron Products Incorporated of Dickerson, Maryland
Information Notice 2002-35: Changes to 10 CFR Parts 71 and 72 Quality Assurance Programs
Information Notice 2004-13: Registration, Use, and Quality Assurance Requirements for NRC-Certified Transportation Packages
Information Notice 2005-10: Changes to 10 CFR Part 71 Packages
Information Notice 2005-13: Potential Non-Conservative Error in Modeling Geometric Regions in the Keno-V.a Criticality Code
Information Notice 2006-12: Exercising Due Diligence When Transferring Radioactive Materials
Information Notice 2016-04: ANSI N14.5-2014 Revision and Leakage Rate Testing Considerations
Information Notice 2018-01: Noble Fission Gas Releases during Spent Fuel Cask Loading Operations
NRC Bulletins [link to NRC website: Bulletins]
Bulletin 94-02: Corrosion Problems in Certain Stainless Steel Packagings Used to Transport Uranium Hexafluoride
Bulletin 95-01: Quality Assurance Program for Transportation of Radioactive Material
Bulletin 96-04: Chemical, Galvanic, or Other Reactions in Spent Fuel Storage and Transportation Casks
Bulletin 97-02: Puncture Testing of Shipping Packages Under 10 CFR Part 71
Bulletin 2003-03: Potentially Defective 1-Inch Valves for Uranium Hexafluoride Cylinders
Interim Staff Guidance [link to NRC website: Interim Staff Guidance]
SFST-ISG-1, Revision 2: Damaged Fuel (consolidated in NUREG-2216 August 2020)
SFST-ISG-2, Revision 1: Fuel Retrievability
SFST-ISG-6: Establishing minimum initial enrichment for the bounding design basis fuel assembly(s). (consolidated in NUREG-2216 August 2020)
SFST-ISG-7: Potential Generic Issue Concerning Cask Heat Transfer in a Transportation
Accident (consolidated in NUREG-2216 August 2020)
SFST-ISG-8, Revision 3: Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks (consolidated in NUREG-2216 August 2020)
SFST-ISG-11, Revision 3: Cladding Considerations for the Transportation and Storage of Spent Fuel (consolidated in NUREG-2216 August 2020)
SFST-ISG-15: Materials Evaluation (consolidated in NUREG-2216 August 2020)
SFST-ISG-18, Revision 1: The Design and Testing of Lid Welds on Austenitic Stainless Steel Canisters as the Confinement Boundary for Spent Fuel Storage
SFST-ISG-19: Moderator Exclusion Under Hypothetical Accident Conditions and Demonstrating Subcriticality of Spent Fuel Under the Requirements of 10 CFR 71.55(e) (consolidated in NUREG-2216 August 2020)
SFST-ISG-20: Transportation Package Design Changes Authorized Under 10 CFR Part 71 Without Prior NRC Approval (consolidated in NUREG-2216 August 2020)
SFST-ISG-21: Use of Computational Modeling Software (consolidated in NUREG-2216 August 2020)
SFST-ISG-22: Potential Rod Splitting Due to Exposure to an Oxidizing Atmosphere During Short-Term Cask Loading Operations in LWR or Other Uranium Oxide Based Fuel (consolidated in NUREG-2216 August 2020)
SFST-ISG-23: Application of ASTM Standard Practice C1671-07 when performing technical reviews of spent fuel storage and transportation packaging licensing actions (consolidated in NUREG-2216 August 2020)
SFST-ISG-25, Revision 0: Pressure Test and Helium Leakage Test of the Confinement Boundary for Spent Fuel Storage Canister
Updated April 3, 2023