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MONTHYEARPMNS20201348, Closed December 16, 2020 POST-SUBMITTAL Meeting to Discuss the Review of Holtec Topical Report HI-2200750, Revision 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology2020-12-0202 December 2020
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Email Proprietary Information Withholding Determination Form Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report
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ML20329A3732020-12-0404 December 2020
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ML21028A6382021-02-0202 February 2021
Summary of Closed Follow-up Call to Discuss U.S. Nuclear Regulatory Commission Review of HDI Topical Report HI-2200750, Rev.0, Holtec Spent Fuel Pool Heat Up Calculation Methodology and Initial Draft RAIs
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PMNS20211039, Closed Call Between U.S. Nuclear Regulatory Commission and Holtec Decommissioning International to Discuss Responses to the Requests for Additional Information for Hi-2200750, Rev. 0, Holtec Spent Fuel Pool Heat Up Calculation Methodolo2021-08-0505 August 2021
Closed Call Between U.S. Nuclear Regulatory Commission and Holtec Decommissioning International to Discuss Responses to the Requests for Additional Information for Hi-2200750, Rev. 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology
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ML21228A2622021-08-16016 August 2021
Revised Response to Request for Additional Information - Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report
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ML21239A3472021-09-0707 September 2021
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ML21239A3622021-09-0707 September 2021
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ML21291A1612021-10-18018 October 2021
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ML22075A3632022-03-25025 March 2022
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ML22075A3082022-03-25025 March 2022
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ML22069B0882022-03-30030 March 2022
Email Formal Transmittal of the U.S. NRC Final Safety Evaluation for Holtec International Topical Report HI-2200750 Revision 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology
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ML22182A4182022-06-30030 June 2022
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ML22346A1872022-12-21021 December 2022
International, Submittal of Topical Report HI-2200750 -A Version
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ML23103A0622023-04-19019 April 2023
NRC 897 Form for the U.S. Nuclear Regulatory Commission Proprietary Withholding Determination for HI-2200750-A, Revision 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology
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ML23103A0682023-04-20020 April 2023
NRC 896 Form for the U.S. Nuclear Regulatory Commission -A Verification of the HI-2200750-A, Rev 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology
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ML23103A0672023-04-20020 April 2023
Transmittal Email of the Proprietary Withholding Determination for the Accepted Version of the Holtec International Topical Report HI-2200750-A, Revision 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology
Project stage: Other
2021-09-10
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Text
From:
Ekaterina Lenning To:
Jean Fleming Cc:
Gerond George; Scott Krepel
Subject:
U.S. Nuclear Regulatory Commission Form 897 Topical Report Withholding Determination for the Accepted Version of the Holtec International Topical Report HI-2200750-A, REVISION 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology Date:
Thursday, April 20, 2023 11:01:00 AM Attachments:
NRC Form 897 Proprietary Withholding Determination for the Accepted Version of the Holtec International TR HI-2200750-A, Revision 0.pdf Jean Fleming Vice President, Regulatory and Environmental Affairs Holtec Decommissioning International, LLC.
Krishna P. Singh Technology Campus 1 Holtec Boulevard Camden, NJ 08104
Ms. Fleming,
Attached please findthe completed U.S.Nuclear Regulatory Commission (NRC) Form 897 for theNRC staffs proprietary withholding determination forthe Holtec International Topical Report HI2200750-A, Revision 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology.
If you have any questions, please feel free to contact me via telephoneat 301-415-3151 or email at Ekaterina.Lenning@nrc.gov.
Sincerely,
Ekaterina Lenning, Project Manager Licensing Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission
Docket No. 99902086