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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 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 Methodology Project stage: Request ML20329A3682020-12-0303 December 2020 Completeness Determination Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report Project stage: Other ML20329A3602020-12-0404 December 2020 Email Proprietary Information Withholding Determination Form Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report Project stage: Other ML20329A3642020-12-0404 December 2020 Form Proprietary Information Withholding Determination Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report Project stage: Other ML20329A3732020-12-0404 December 2020 E-mail Completeness Determination Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report Project stage: Other 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 Project stage: Draft Approval ML21028A6452021-02-0202 February 2021 Summary of the 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 Methodology Project stage: Meeting 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 Project stage: RAI ML21228A2622021-08-16016 August 2021 Revised Response to Request for Additional Information - Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report Project stage: Response to RAI ML21239A3472021-09-0707 September 2021 Proprietary Information Withholding Determination Form Responses to Requests for Additional Information for HDI Topical Report HI-2200750 Revision 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology Project stage: RAI ML21239A3622021-09-0707 September 2021 Proprietary Information Withholding Determination Forms Revised Responses to Requests for Additional Information for HDI Topical Report HI-2200750 Revision 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology Project stage: RAI ML21238A0212021-09-10010 September 2021 1Summary of Closed Call to Discuss Revised Responses to Requests for Additional Information for the U.S. Nuclear Regulatory Commission Review of Holtec Decommissioning International Topical Report HI-2200750, Rev 0, Holtec Spent Fuel Pool Project stage: RAI ML21291A1612021-10-18018 October 2021 Response to Request for Additional Information 10 - Holtec Spent Fuel Pool Heat Up Calculation Methodology Topical Report Project stage: Response to RAI ML21313A3852021-12-20020 December 2021 Email Formal Transmittal of the U.S. NRC Draft Safety Evaluation for Holtec International Topical Report HI-2200750 Revision 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology Project stage: Draft Approval ML22006A3622022-01-0606 January 2022 Submittal of Us NRC Draft Safety Evaluation by the Office of Nuclear Reactor Regulation for the Topical Report HI-2200750, Rev. 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology Identifying Information Proprietary to Holtec Internat Project stage: Draft Other ML22046A3182022-02-15015 February 2022 Submittal of Redacted U.S. Nuclear Regulatory Commission Draft Safety Evaluation by the Office of Nuclear Reactor Regulation for the Topical Report HI-2200750 Revision 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology Project stage: Draft Other ML22075A3632022-03-25025 March 2022 Proprietary Information Withholding Determination Form 897 for Holtec Prop Markup on the Draft SE HI-2200750 Rev 0 Spent Fuel Pool Heat Up Calculation Methodology Topical Report Project stage: Draft Approval ML22075A3082022-03-25025 March 2022 Non-Proprietary Enclosure 1 U.S. NRC Final Safety Evaluation for Holtec International Topical Report HI-2200750 Revision 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology Project stage: Approval 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 Project stage: Approval ML22182A4182022-06-30030 June 2022 Decommissioning International, Submittal of Topical Report HI-2200750 -A Version Project stage: Other ML22346A1872022-12-21021 December 2022 International, Submittal of Topical Report HI-2200750 -A Version Project stage: Other 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 Project stage: Other 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 Project stage: Other 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:
Lenning, Ekaterina To:
Jean Fleming Cc:
Chang, Richard; Lukes, Robert; Kaizer, Joshua
Subject:
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" Date:
Wednesday, March 30, 2022 10:56:00 AM Attachments:
Non-Prop Enclosure 1 Final SE Holtec HI-2200750 Rev 0 TR.pdf Jean Fleming Vice President, Regulatory and Environmental Affairs Holtec Decommissioning International, LLC.
Ms. Fleming,
By letter dated September 29, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20280A524), Holtec International (HI) submitted for U.S. Nuclear Regulatory Commission (NRC) staff review the Topical Report (TR)
HI-2200750 Revision 0, Holtec Spent Fuel Pool Heat Up Calculation Methodology. By email dated December 20, 2021, the NRC staff issued its draft safety evaluation (SE)
(ADAMS Accession No. ML21313A385).
The NRC staff has found the TR acceptable for referencing in licensing applications for nuclear power plants to the extent specified and under the limitations delineated in the TR and in the enclosed SE. The final SE defines the basis for our acceptance of the TR. A copy of the non-proprietary (redacted) Enclosure 1 is attached to this email and a copy of the proprietary Enclosure 2 of the final SE, which contains proprietary information, was provided to you via the NRC box.com folder.
Our acceptance applies only to material provided in the subject TR. We do not intend to repeat our review of the accepted material described in the TR. When the TR appears as a reference in license applications, our review will ensure that the material presented applies to the specific plant involved. License amendment requests that deviate from this TR will be subject to a plant-specific review in accordance with applicable review standards.
In accordance with the guidance provided on the NRC website, we request that HI publish accepted versions of the proprietary and non-proprietary TR within three months of receipt of the date of this email. The accepted proprietary version shall incorporate this email and the proprietary final SE (Enclosure 2), and the accepted non-proprietary version shall incorporate this email and the non-proprietary final SE (Enclosure 1) after the title page.
Also, the accepted version must contain historical review information, including NRC requests for additional information (RAIs) and your responses after the title page. The accepted version shall include an "-A" (designating accepted) following the TR identification symbol.
As an alternative to including the RAIs and RAI responses behind the title page, if changes to the TRs were provided to the NRC staff to support the resolution of RAI responses, and the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs:
- 1. The RAIs and RAI responses can be included as an Appendix to the accepted version.
- 2. The RAIs and RAI responses can be captured in the form of a table (inserted after the
final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR.
This email, non-proprietary Enclosure 1 and proprietary Enclosure 2 of the final SE have been placed in ADAMS and made Official Agency Records. The proprietary Enclosure 2 of the final SE is declared as nonpublic because it contains proprietary information. This email and non-proprietary Enclosure 1 are declared public.
Also, the accepted versions must contain historical review information, including NRC RAIs and responses. The accepted versions shall include a -A (designating approved) following the TR identification symbol.
If future changes to the NRCs regulatory requirements affect the acceptability of this TR, HI will be expected to revise the TR appropriately. Licensees referencing this TR would be expected to justify its continued applicability or evaluate their plant using the revised TR.
If you have any questions, please contact the Project Manager for the review, Ekaterina Lenning, at 301-415-3151, or by email at Ekaterina.Lenning@nrc.gov.
Richard Chang, Chief Licensing Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No.: 99902086