ML20321A088

Appendix a - Interim Staff Guidance (ISG) Incorporated Into NUREG-2215

ML20321A088
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Issue date:	04/30/2020
From:	Office of Nuclear Material Safety and Safeguards
To:
AWillis - 301.415.0479 ; SKumar
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ML20321A086	List: ML20321A088 ML20321A089 ML20321A090 ML20321A091 ML20321A092 ML20321A093 ML20321A094 ML20321A095 ML20321A096 ML20321A097 ML20321A098 ML20321A099 ML20321A100 ML20321A101 ML20321A102 ML20321A103 ML20321A104 ML20321A105 ML20321A106 ML20321A107 ML20321A108 ML20321A109 ML20321A110 ML20321A111 ML20321A112 NUREG-2215, Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities. Title, Table of Contents, Introduction
References
NUREG-2215
Download: ML20321A088 (6)

Text

APPENDIX A INTERIM STAFF GUIDANCE (ISG) INCORPORATED INTO NUREG-2215 ISG # NUREG-2215

& Rev. Title Status ISG 1 Damaged Fuel Added Rev. 2 ISG 2 Fuel Retrievability Added Rev. 2 ISG 3 Post Accident Recovery and Compliance Added with 10 CFR 72.122(l)

ISG 4 Cask Closure Weld Inspections Superseded by ISGs 15 Rev. 1 and 18 ISG 5 Confinement Evaluation Added Rev. 1 ISG 6 Establishing Minimum Initial Enrichment for the Added Bounding Design Basis Fuel Assembly(s)

ISG 7 Potential Generic Issue Concerning Cask Heat Transfer in Added a Transportation Accident ISG 8 Burnup Credit in the Criticality Safety Analyses of Added Rev. 3 PWR Spent Fuel in Transport and Storage Casks ISG 9 Storage of Components Associated with Fuel Assemblies Added Rev. 1 ISG 10 Alternatives to the ASME Code Added Rev. 1 ISG 11 Cladding Considerations for the Transportation and Added Rev. 3 Storage of Spent Fuel ISG 12 Buckling of Irradiated Fuel Under Bottom End Added Rev. 1 Drop Conditions 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 The Design & Testing of Lid Welds on Austenitic Stainless Added Rev. 1 Steel Canisters as Confinement Boundary for Spent Fuel Storage ISG 19 Moderator Exclusion Under Hypothetical Accident NA Conditions and Demonstrating Subcriticality of Spent Fuel Under the Requirements of 10 CFR 71.55(e)

ISG 20 Transportation Package Design Changes Authorized Under NA 10 CFR Part 71 Without Prior NRC Approval ISG 21 Use of Computational Modeling Software Added A-1

ISG # NUREG-2215

& Rev. Title Status ISG 22 Potential Rod Splitting Due to Exposure to an Oxidizing Added Atmosphere During Short-Term Cask Loading Operations in LWR or Other Uranium Oxide Based Fuel ISG 23 Application of ASTM Standard Practice C1671-07 When Added Performing Technical Reviews of Spent Fuel Storage and Transportation Packaging Licensing Actions ISG 24 Reserved N/A

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ISG f) 25 Pressure and Helium Leakage Testing of the Confinement Added Boundary of Spent Fuel Storage Casks ISG 26 Reserved N/A (Draft)

A-2

NUREG-2215 Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities April 2020 Final Report Technical 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

NUREG-2215 Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities April 2020

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