ML22028A103: Difference between revisions

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=Text=
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{{#Wiki_filter:From:             Guzman, Richard To:               Andrea Sterdis Cc:               Cruz Perez, Zahira; Jean Fleming
{{#Wiki_filter:From: Guzman, Richard To: Andrea Sterdis Cc: Cruz Perez, Zahira; Jean Fleming


==Subject:==
==Subject:==
Indian Point Unit 3 - Transmittal of Draft Safety Evaluation - Proposed License Amendment re: Revision to Licensing Basis to Incorporate the Installation and Use of New Auxiliary Lifting Device (EPID L-2020-LLA-0051)
Indian Point Unit 3 - Transmittal of Draft Safety Evaluation - Proposed License Amendment re: Revision to Licensing Basis to Incorporate the Installation and Use of New Auxiliary Lifting Device (EPID L-2020-LLA-0051)
Date:             Friday, January 28, 2022 11:16:00 AM Ms. Sterdis, By {{letter dated|date=March 24, 2020|text=letter dated March 24, 2020}}, as supplemented by letters dated October 2, 2020, November 9, 2020, February 26, 2021, May 20, 2021, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML20084U773, ML20276A322, ML20314A355, ML21057A186, and ML21140A451 respectively), Entergy Nuclear Operations Inc. (the licensee at the time) submitted a license amendment request (LAR or the application) to revise the Updated Final Safety Analysis Report (UFSAR) for Indian Point Nuclear Generating Unit No. 3 (Indian Point 3 or IP3). The amendment would revise the current licensing basis in the UFSAR with regard to the design, installation and use of a new single failure proof auxiliary lifting device, termed HI-LIFT, in the Indian Point 3 Fuel Storage Building. On May 28, 2021, Holtec Decommissioning International, LLC (HDI) became the licensee for Indian Point 3. By {{letter dated|date=January 3, 2022|text=letter dated January 3, 2022}} (ADAMS Accession No. ML22003A193), HDI submitted an additional supplement that included a complete HI-LIFT failure modes and effects analysis, a revised design specification for the HI-LIFT, and a revised HI-LIFT structural analysis, all considered proprietary.
Date: Friday, January 28, 2022 11:16:00 AM
 
Ms. Sterdis,
 
By {{letter dated|date=March 24, 2020|text=letter dated March 24, 2020}}, as supplemented by letters dated October 2, 2020, November 9, 2020, February 26, 2021, May 20, 2021, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML20084U773, ML20276A322, ML20314A355, ML21057A186, and ML21140A451 respectively), Entergy Nuclear Operations Inc. (the licensee at the time) submitted a license amendment request (LAR or the application) to revise the Updated Final Safety Analysis Report (UFSAR) for Indian Point Nuclear Generating Unit No. 3 (Indian Point 3 or IP3). The amendment would revise the current licensing basis in the UFSAR with regard to the design, installation and use of a new single failure proof auxiliary lifting device, termed HI-LIFT, in the Indian Point 3 Fuel Storage Building. On May 28, 2021, Holtec Decommissioning International, LLC (HDI) became the licensee for Indian Point 3. By {{letter dated|date=January 3, 2022|text=letter dated January 3, 2022}} (ADAMS Accession No. ML22003A193 ), HDI submitted an additional supplement that included a complete HI-LIFT failure modes and effects analysis, a revised design specification for the HI-LIFT, and a revised HI-LIFT structural analysis, all considered proprietary.
 
A draft proprietary copy of the NRC staffs safety evaluation has been placed in the cloud-based collaboration tool application, BOX - Enterprise File Synchronization and Sharing (BOX-EFSS) in the folder called IP3 HI-LIFT Crane at https://account.box.com/login?
A draft proprietary copy of the NRC staffs safety evaluation has been placed in the cloud-based collaboration tool application, BOX - Enterprise File Synchronization and Sharing (BOX-EFSS) in the folder called IP3 HI-LIFT Crane at https://account.box.com/login?
redirect_url=/.
redirect_url=/.
Pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations (10 CFR 2.390),
Pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations (10 CFR 2.390),
we have determined that the draft SE contains proprietary information as identified in bolded brackets (( proprietary information )). Please review the document to ensure the intended information to be withheld is properly marked.
we have determined that the draft SE contains proprietary information as identified in bolded brackets (( proprietary information )). Please review the document to ensure the intended information to be withheld is properly marked.
Per our discussion, please provide an electronic marked-up copy of the draft SE via the same BOX-EFSS folder by February 11. The electronic copy should be in redline/strikeout to help facilitate the NRC staffs review of the mark-up and/or comments.
Per our discussion, please provide an electronic marked-up copy of the draft SE via the same BOX-EFSS folder by February 11. The electronic copy should be in redline/strikeout to help facilitate the NRC staffs review of the mark-up and/or comments.
This email and draft SE will be placed in ADAMS and made an official agency record. The draft SE will be non-public. If you have questions, please contact me.
This email and draft SE will be placed in ADAMS and made an official agency record. The draft SE will be non-public. If you have questions, please contact me.
Richard V. Guzman Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov}}
Richard V. Guzman Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov}}

Latest revision as of 19:07, 18 November 2024

E-mail Dated 1/28/2022, Transmittal of Draft Safety Evaluation for Proposed License Amendment Revision to Licensing Basis to Incorporate the Installation and Use of of New Auxiliary Lifting Device
ML22028A103
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 01/28/2022
From: Richard Guzman
NRC/NRR/DORL/LPL1
To: Sterdis A
Holtec Decommissioning International
Guzman R
References
EPID L-2020-LLA-0051
Download: ML22028A103 (2)
v • d • e


Text

From: Guzman, Richard To: Andrea Sterdis Cc: Cruz Perez, Zahira; Jean Fleming

Subject:

Indian Point Unit 3 - Transmittal of Draft Safety Evaluation - Proposed License Amendment re: Revision to Licensing Basis to Incorporate the Installation and Use of New Auxiliary Lifting Device (EPID L-2020-LLA-0051)

Date: Friday, January 28, 2022 11:16:00 AM

Ms. Sterdis,

By letter dated March 24, 2020, as supplemented by letters dated October 2, 2020, November 9, 2020, February 26, 2021, May 20, 2021, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML20084U773, ML20276A322, ML20314A355, ML21057A186, and ML21140A451 respectively), Entergy Nuclear Operations Inc. (the licensee at the time) submitted a license amendment request (LAR or the application) to revise the Updated Final Safety Analysis Report (UFSAR) for Indian Point Nuclear Generating Unit No. 3 (Indian Point 3 or IP3). The amendment would revise the current licensing basis in the UFSAR with regard to the design, installation and use of a new single failure proof auxiliary lifting device, termed HI-LIFT, in the Indian Point 3 Fuel Storage Building. On May 28, 2021, Holtec Decommissioning International, LLC (HDI) became the licensee for Indian Point 3. By letter dated January 3, 2022 (ADAMS Accession No. ML22003A193 ), HDI submitted an additional supplement that included a complete HI-LIFT failure modes and effects analysis, a revised design specification for the HI-LIFT, and a revised HI-LIFT structural analysis, all considered proprietary.

A draft proprietary copy of the NRC staffs safety evaluation has been placed in the cloud-based collaboration tool application, BOX - Enterprise File Synchronization and Sharing (BOX-EFSS) in the folder called IP3 HI-LIFT Crane at https://account.box.com/login?

redirect_url=/.

Pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations (10 CFR 2.390),

we have determined that the draft SE contains proprietary information as identified in bolded brackets (( proprietary information )). Please review the document to ensure the intended information to be withheld is properly marked.

Per our discussion, please provide an electronic marked-up copy of the draft SE via the same BOX-EFSS folder by February 11. The electronic copy should be in redline/strikeout to help facilitate the NRC staffs review of the mark-up and/or comments.

This email and draft SE will be placed in ADAMS and made an official agency record. The draft SE will be non-public. If you have questions, please contact me.

Richard V. Guzman Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov

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