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Category:NUREG
MONTHYEARNUREG-1437 Volume 1, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report2024-08-31031 August 2024
NUREG-1437, Volume 1, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report
NUREG-1437 Volume 2, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report2024-08-31031 August 2024
NUREG-1437, Volume 2, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report
NUREG-1437 Volume 3, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report2024-08-31031 August 2024
NUREG-1437, Volume 3, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report
NUREG-1556 Volume 2, Rev. 1, Suppl. 1, Consolidated Guidance About Materials Licenses - Program-Specific Guidance About Industrial Radiography Licenses Final Report2024-05-31031 May 2024
NUREG-1556, Vol. 2, Rev. 1, Suppl. 1, Consolidated Guidance About Materials Licenses - Program-Specific Guidance About Industrial Radiography Licenses Final Report
ML23355A1432024-01-17017 January 2024
January 17, 2024 Public Meeting Handout - Fusion Systems Rulemaking
ML23303A2212023-10-31031 October 2023
NUREG/BR-0096, Revision. 2, Instructions and Guidance for Completing Physical Inventory Summary Reports - NRC Form 327 Final Report
NUREG-2266, Dfc, Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Levels2023-08-31031 August 2023
NUREG-2266 Dfc, Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Levels
ML23123A3322023-06-0606 June 2023
SGI Pamphlet
ML22299A2382022-10-31031 October 2022
NUREG-2237, Supplement 1, Environmental Impact Statements for Holtec International’S License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Lea County, New Mexico
NUREG-2263, Dfc, Environmental Impact Statement for the Construction Permit for the Kairos Hermes Test Reactor2022-09-30030 September 2022
NUREG-2263 Dfc, Environmental Impact Statement for the Construction Permit for the Kairos Hermes Test Reactor
ML22181B0942022-07-31031 July 2022
NUREG-2237, Environmental Impact Statement for the Holtec Internationals License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Lea County, New Mexico Final Report
NUREG-2159, Revision 1, Final, Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance2022-07-29029 July 2022
NUREG-2159, Revision 1, Final, Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance
ML22175A2032022-06-30030 June 2022
NUREG/BR-0058 Dfc, Rev. 5, Appendix L Replacement Energy Costs
ML22175A2022022-06-30030 June 2022
NUREG/BR-0058, Rev. 5, Appendix K Monetary Valuation of Nonfatal Cancer Risk for Use in Cost-Benefit Analysis Dfc
NUREG-2155, Rev 2, Implementation Guidance for 10 CFR Part 37, Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material2022-03-31031 March 2022
NUREG-2155, Rev 2, Implementation Guidance for 10 CFR Part 37, Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material
ML22042A1162022-02-0909 February 2022
Document to Support ACRS Subcommittee Meeting Draft NUREG 1021, Rev 13, Operator Licensing Examination Standards for Power Reactors
ML21209A9552021-07-31031 July 2021
NUREG-2239, Environmental Impact Statement for Interim Storage Partners LLCs License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Andrews County, Texas Final Report
NUREG-2248, DFC, Environmental Impact Statement for the License Renewal of the Columbia Fuel Fabrication Facility in Richland County, South Carolina2021-07-31031 July 2021
NUREG-2248 DFC, Environmental Impact Statement for the License Renewal of the Columbia Fuel Fabrication Facility in Richland County, South Carolina
ML21096A2922021-04-30030 April 2021
NUREG/BR-0058, Rev. 5, Appendix F Data Sources - DFC
ML21096A2952021-04-30030 April 2021
NUREG/BR-0058, Rev. 5, Appendix I National Environmental Policy Act Cost-Benefit Analysis - DFC
ML21096A2942021-04-30030 April 2021
NUREG/BR-0058, Rev. 5, Appendix H Severe Accident Risk Analysis - DFC
ML21096A2932021-04-30030 April 2021
NUREG/BR-0058, Rev. 5, Appendix G Regulatory Analysis Methods and Data for Nuclear Facilities Other than Power Reactors - DFC
ML21005A1532020-12-31031 December 2020
NUREG/BR-0520, State Programs at the U.S. Nuclear Regulatory Commission
NUREG-2242, Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030 - Draft for Comment2020-12-31031 December 2020
NUREG-2242, Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030 - Draft for Comment
NUREG-2224, Dry Storage and Transportation of High Burnup Spent Fuel2020-11-30030 November 2020
NUREG-2224, Dry Storage and Transportation of High Burnup Spent Fuel
NUREG-1556 Volume 20, Rev. 1, Consolidated Guidance About Materials Licenses: Guidance About Administrative Licensing Procedures Final Report2020-11-30030 November 2020
NUREG-1556, Vol. 20, Rev. 1, Consolidated Guidance About Materials Licenses: Guidance About Administrative Licensing Procedures Final Report
NUREG-2243, Environmental Impact Statement for the Disposal of Mine Waste at the United Nuclear Corporation Mill Site in Mckinley County, New Mexico - Draft for Comment2020-10-31031 October 2020
NUREG-2243 - Environmental Impact Statement for the Disposal of Mine Waste at the United Nuclear Corporation Mill Site in Mckinley County, New Mexico - Draft for Comment
ML20178A4332020-06-30030 June 2020
NUREG-BR-0204,Revision 3, Instructions for Completing the U.S. Nuclear Regulatory Commissions Uniform Low-Level Radioactive Waste Manifest - Final Report
ML20122A2202020-05-31031 May 2020
NUREG-2239 DFC, Environmental Impact Statement for Interim Storage Partners LLCs License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Andrews County, Texas
ML20321A1122020-04-30030 April 2020
Chapter 17 - Technical Specifications Evaluation
ML20321A1112020-04-30030 April 2020
Chapter 16 - Accident Analysis Evaluation
ML20321A1102020-04-30030 April 2020
Chapter 15 - Quality Assurance Evaluation
ML20321A1092020-04-30030 April 2020
Chapter 14 - Decommissioning Evaluation (SL)
ML20321A1082020-04-30030 April 2020
Chapter 13 - Waste Management Evaluation (SL)
ML20321A1072020-04-30030 April 2020
Chapter 12 - Conduct of Operations Evaluation
ML20321A1062020-04-30030 April 2020
Chapter 11 - Operation Procedures and Systems Evaluation
ML20321A0882020-04-30030 April 2020
Appendix a - Interim Staff Guidance (ISG) Incorporated Into NUREG-2215
ML20321A0892020-04-30030 April 2020
Appendix 4A - Computational Modeling Software Technical Review Guidance
ML20321A0902020-04-30030 April 2020
Appendix 4B - Pool and Pool Confinement Facilities
ML20321A0922020-04-30030 April 2020
Appendix 8A - Clarifications, Guidance, and Expectations to ASTM Standard Practice C1671-15
ML20321A0932020-04-30030 April 2020
Appendix 8B - Fuel Cladding Creep
ML20321A1052020-04-30030 April 2020
Chapter 10B - Radiation Protection Evaluation for Dry Storage Systems (CoC)
ML20321A0912020-04-30030 April 2020
Appendix 7A - Technical Recommendations for the Criticality Safety Review of PWR Transportation Packages and Storage Casks
ML20321A0952020-04-30030 April 2020
Chapter 1 - General Information for Evaluation
ML20321A0962020-04-30030 April 2020
Chapter 2 - Site Characteristics Evaluation for Dry Storage Facilities (SL)
ML20321A0972020-04-30030 April 2020
Chapter 3 - Principal Design Criteria Evaluation
ML20321A0982020-04-30030 April 2020
Chapter 4 - Structural Evaluation
ML20321A0992020-04-30030 April 2020
Chapter 5 - Thermal Evaluation
ML20321A1002020-04-30030 April 2020
Chapter 6 - Shielding Evaluation
ML20321A1012020-04-30030 April 2020
Chapter 7 - Criticality Evaluation
2024-08-31
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Category:Standard Review Plan
MONTHYEARML22041A3752022-02-0909 February 2022
Document to Support ACRS Subcommitee Meeting - Redline Standard Review Plan 1.0 Introduction and Interfaces
ML22041A4442022-02-0909 February 2022
Document to Support ACRS Subcommittee Meeting - Redline Standard Review Plan 13.3 Emergency Planning
ML22041A4462022-02-0909 February 2022
Document to Support ACRS Subcommittee Meeting - Redline Standard Review Plan 13.6.1 Physical Security-Combined License and Operating Reactors
ML22041A4562022-02-0909 February 2022
Document to Support ACRS Subcommittee Meeting - Redline Standard Review Plan 13.6.4 Access Authorization - Operational Program
ML22041A5272022-02-0909 February 2022
Document to Support ACRS Subcommittee Meeting Redline Standard Review Plan 19.0 Probablistic Risk Assessment and Accident Evaluation for New Reactors
ML22041A5322022-02-0909 February 2022
Document to Support ACRS Subcommittee Meeting Redline Standard Review Plan 19.1 Determining the Technical Adequacy of Probablistic Risk Assessment for Risk-Informed License Amendment Requests After Initial Fuel Load
ML20321A0932020-04-30030 April 2020
Appendix 8B - Fuel Cladding Creep
ML20321A0912020-04-30030 April 2020
Appendix 7A - Technical Recommendations for the Criticality Safety Review of PWR Transportation Packages and Storage Casks
ML20321A0952020-04-30030 April 2020
Chapter 1 - General Information for Evaluation
ML20321A0962020-04-30030 April 2020
Chapter 2 - Site Characteristics Evaluation for Dry Storage Facilities (SL)
ML20321A0972020-04-30030 April 2020
Chapter 3 - Principal Design Criteria Evaluation
ML20321A0982020-04-30030 April 2020
Chapter 4 - Structural Evaluation
ML20321A0992020-04-30030 April 2020
Chapter 5 - Thermal Evaluation
ML20321A1002020-04-30030 April 2020
Chapter 6 - Shielding Evaluation
ML20321A1012020-04-30030 April 2020
Chapter 7 - Criticality Evaluation
ML20321A1022020-04-30030 April 2020
Chapter 8 - Materials Evaluation
ML20321A1042020-04-30030 April 2020
Chapter 10A - Radiation Protection Evaluation for Dry Storage Facilities (SL)
ML20321A1052020-04-30030 April 2020
Chapter 10B - Radiation Protection Evaluation for Dry Storage Systems (CoC)
ML20321A1062020-04-30030 April 2020
Chapter 11 - Operation Procedures and Systems Evaluation
ML20321A1072020-04-30030 April 2020
Chapter 12 - Conduct of Operations Evaluation
ML20321A1082020-04-30030 April 2020
Chapter 13 - Waste Management Evaluation (SL)
ML20321A1092020-04-30030 April 2020
Chapter 14 - Decommissioning Evaluation (SL)
ML20321A1102020-04-30030 April 2020
Chapter 15 - Quality Assurance Evaluation
ML20321A1112020-04-30030 April 2020
Chapter 16 - Accident Analysis Evaluation
ML20321A1122020-04-30030 April 2020
Chapter 17 - Technical Specifications Evaluation
ML20321A0882020-04-30030 April 2020
Appendix a - Interim Staff Guidance (ISG) Incorporated Into NUREG-2215
ML20321A0892020-04-30030 April 2020
Appendix 4A - Computational Modeling Software Technical Review Guidance
ML20321A0902020-04-30030 April 2020
Appendix 4B - Pool and Pool Confinement Facilities
ML20321A0922020-04-30030 April 2020
Appendix 8A - Clarifications, Guidance, and Expectations to ASTM Standard Practice C1671-15
ML20321A0942020-04-30030 April 2020
Appendix 8C - Fuel Oxidation and Cladding Splitting
ML20321A1032020-04-0101 April 2020
Chapter 9 - Confinement Evaluation
2022-02-09
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Text
A-1 APPENDIX A INTERIM STAFF GUIDANCE (ISG) INCORPORATED INTO NUREG-2215 ISG #
& Rev.
Title NUREG-2215 Status ISG 1 Rev. 2 Damaged Fuel Added ISG 2 Rev. 2 Fuel Retrievability Added ISG 3 Post Accident Recovery and Compliance with 10 CFR 72.122(l)
Added ISG 4 Rev. 1 Cask Closure Weld Inspections Superseded by ISGs 15 and 18 ISG 5 Rev. 1 Confinement Evaluation Added ISG 6 Establishing Minimum Initial Enrichment for the Bounding Design Basis Fuel Assembly(s)
Added ISG 7 Potential Generic Issue Concerning Cask Heat Transfer in a Transportation Accident Added ISG 8 Rev. 3 Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks Added ISG 9 Rev. 1 Storage of Components Associated with Fuel Assemblies Added ISG 10 Rev. 1 Alternatives to the ASME Code Added ISG 11 Rev. 3 Cladding Considerations for the Transportation and Storage of Spent Fuel Added ISG 12 Rev. 1 Buckling of Irradiated Fuel Under Bottom End Drop Conditions Added ISG 13 Real Individual Added ISG 14 Supplemental Shielding Added ISG 15 Materials Evaluation Added ISG 16 Emergency Planning Added ISG 17 Interim Storage of Greater Than Class C Waste Added ISG 18 Rev. 1 The Design & Testing of Lid Welds on Austenitic Stainless Steel Canisters as Confinement Boundary for Spent Fuel Storage Added ISG 19 Moderator Exclusion Under Hypothetical Accident Conditions and Demonstrating Subcriticality of Spent Fuel Under the Requirements of 10 CFR 71.55(e)
NA ISG 20 Transportation Package Design Changes Authorized Under 10 CFR Part 71 Without Prior NRC Approval NA ISG 21 Use of Computational Modeling Software Added
A-2 ISG #
& Rev.
Title NUREG-2215 Status 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 Added ISG 23 Application of ASTM Standard Practice C1671-07 When Performing Technical Reviews of Spent Fuel Storage and Transportation Packaging Licensing Actions Added ISG 24
(
f )
Reserved N/A ISG 25 Pressure and Helium Leakage Testing of the Confinement Boundary of Spent Fuel Storage Casks Added ISG 26 (Draft)
Reserved N/A
NUREG-2215 Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Abstract This Standard Review Plan (SRP) provides guidance to the U.S. Nuclear Regulatory Commission (NRC) staff for reviewing safety analysis reports (SARs) for (1) a Certificate of Compliance (CoC) for a dry storage system for use at a general license facility and (2) a specific license for a dry storage facility that is either an independent spent fuel storage installation (ISFSI) or a monitored retrievable storage installation (MRS). This SRP does not apply to wet storage ISFSIs or MRSs (e.g., GE-Morris).
The objectives of this SRP are to assist the NRC staff in its reviews by doing the following:
x promoting a consistent regulatory review of a SAR for an ISFSI or MRS license, or for a CoC x
promoting quality and uniformity of these reviews across each technical discipline x
presenting a basis for the reviews scope x
identifying acceptable approaches to meeting regulatory requirements x
suggesting possible evaluation findings that can be used in the safety evaluation report This SRP may be revised and updated as the need arises on a chapter-by-chapter basis to clarify the content, correct errors, or incorporate modifications approved by the Director of the Division of Spent Fuel Management. Comments, suggestions for improvement, and notices of errors or omissions should be sent to and will be considered by the Director, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
List of keywords or phrases that will assist researchers in locating this NUREG.
standard review plan, spent nuclear fuel, spent fuel storage, independent spent fuel storage installation, specific license application, certificate of compliance application, monitored retrievable storage installation, dry storage system April 2020 Technical Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities Final Report
NUREG-2215
)LQDO Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities April 2020