Guidance for DOE Use of NRC Certificates


NUREGs Regulatory Guides Regulatory Issue Summaries Information Notices Bulletins Interim Staff Guidance

NRC NUREGs [link to NRC website: NUREG-Series Publications] External Link

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

NUREG-1617:   Standard Review Plan for Transportation Packages for Spent Nuclear Fuel

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/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-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 ]External Link

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

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]External Link

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] External Link

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]External Link

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]External Link

SFST-ISG-1, Revision 2:   Damaged Fuel

SFST-ISG-2, Revision 1:   Fuel Retrievability

SFST-ISG-8, Revision 3:   Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

SFST-ISG-11, Revision 3:   Cladding Considerations for the Transportation and Storage of Spent Fuel

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)

SFST-ISG-20:   Transportation Package Design Changes Authorized Under 10 CFR Part 71 Without Prior NRC Approval

SFST-ISG-21:   Use of Computational Modeling Software

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

SFST-ISG-23:   Application of ASTM Standard Practice C1671-07 when performing technical reviews of spent fuel storage and transportation packaging licensing actions

SFST-ISG-25, Revision 0:   Pressure Test and Helium Leakage Test of the Confinement Boundary for Spent Fuel Storage Canister


Updated January 23, 2019




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