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| {{#Wiki_filter:-En tery Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 254-6710 Robert Walpole Manager Licensing Tel (914) 254-6710 NL-13-111 August 06, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738 | | {{#Wiki_filter:Entergy Nuclear Northeast Indian Point Energy Center |
| | -En tery 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 254-6710 Robert Walpole Manager Licensing Tel (914) 254-6710 NL-13-111 August 06, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738 |
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| ==Subject:== | | ==Subject:== |
| Indian Point Energy Center Registration of Unit 3 Spent Fuel Cask Use Indian Point, Unit 3 Docket Nos. 50-286 & 72-51 License No. DPR-64 | | Indian Point Energy Center Registration of Unit 3 Spent Fuel Cask Use Indian Point, Unit 3 Docket Nos. 50-286 & 72-51 License No. DPR-64 Dear Sir or Madam; Entergy Nuclear Operations, Inc. (Entergy) operates the Indian Point Energy Center (IPEC) |
| | Independent Spent Fuel Storage Installation (ISFSI) in accordance with the general license provisions of 10 CFR 72.210. The conditions of 10 CFR 72.212(b)(2) include the registration of a spent fuel cask within 30 days of using a cask for storage of spent nuclear fuel. |
| | Accordingly, this letter hereby registers the use on July 31, 2013, of the fourth (4) IPEC Unit 3 dry fuel storage cask. The cask was loaded to Amendment #6 of the Holtec CoC #1014 and the corresponding Holtec CFSAR Revision 8. This cask is the twenty third (23) IPEC dry fuel storage cask to be added to the IPEC ISFSI pad. |
| | This letter also provides the following registration information associated with twenty third Holtec HI-STORM 100 spent fuel cask system that was placed into storage on the IPEC ISFSI pad [Docket No. 72-51]. The fuel contained in these casks are from IPEC Unit 3 Nuclear Power Plant, Reactor License No. DPR-64, Docket No. 50-286. |
| | [Fourth (4) Unit 3 Spent Fuel Cask] |
| | Twenty third (23rd) IPEC Soent Fuel Cask System: Date Dlaced in use: July 31. 2013 Licensee's Name: Entergy Nuclear Operations, Inc. |
| | Licensee's Address: Indian Point Energy Center 450 Broadway P.O. Box 249 Buchanan, NY 10511 Cask Model Number: HI-STORM 100 Cask Certificate Number: 1014 MPC Serial Number: 272 HI-STORM Overpack Serial Number: 0652 Number of Fuel Bundles: 32 fuel bundles Vk sA ' |
| | pKU-S3 |
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| ==Dear Sir or Madam;Entergy Nuclear Operations,==
| | Indian Point Unit 3 Docket Nos. 50-286 & 72-51 License No. DPR-64 NL-13-111 Page 2 of 2 Total Cask Systems stored at the IPEC ISFSI pad [Docket No. 72-511: |
| Inc. (Entergy) operates the Indian Point Energy Center (IPEC)Independent Spent Fuel Storage Installation (ISFSI) in accordance with the general license provisions of 10 CFR 72.210. The conditions of 10 CFR 72.212(b)(2) include the registration of a spent fuel cask within 30 days of using a cask for storage of spent nuclear fuel.Accordingly, this letter hereby registers the use on July 31, 2013, of the fourth (4) IPEC Unit 3 dry fuel storage cask. The cask was loaded to Amendment
| | Twenty three (23) HI-STORM 100 Cask Systems Entergy is making no new commitments in this letter. Should you have any questions regarding this matter, please contact Mr. Timothy J. Salentino, Superintendent Dry Fuels Storage, at Indian Point Energy Center at (914) 254-6773. |
| #6 of the Holtec CoC #1014 and the corresponding Holtec CFSAR Revision 8. This cask is the twenty third (23) IPEC dry fuel storage cask to be added to the IPEC ISFSI pad.This letter also provides the following registration information associated with twenty third Holtec HI-STORM 100 spent fuel cask system that was placed into storage on the IPEC ISFSI pad [Docket No. 72-51]. The fuel contained in these casks are from IPEC Unit 3 Nuclear Power Plant, Reactor License No. DPR-64, Docket No. 50-286.[Fourth (4) Unit 3 Spent Fuel Cask]Twenty third (23rd) IPEC Soent Fuel Cask System: Date Dlaced in use: July 31. 2013 Licensee's Name: Licensee's Address: Cask Model Number: Cask Certificate Number: MPC Serial Number: HI-STORM Overpack Serial Number: Number of Fuel Bundles: Entergy Nuclear Operations, Inc.Indian Point Energy Center 450 Broadway P.O. Box 249 Buchanan, NY 10511 HI-STORM 100 1014 272 0652 32 fuel bundles Vk sA 'pKU-S3 Indian Point Unit 3 Docket Nos. 50-286 & 72-51 License No. DPR-64 NL-13-111 Page 2 of 2 Total Cask Systems stored at the IPEC ISFSI pad [Docket No. 72-511: Twenty three (23) HI-STORM 100 Cask Systems Entergy is making no new commitments in this letter. Should you have any questions regarding this matter, please contact Mr. Timothy J. Salentino, Superintendent Dry Fuels Storage, at Indian Point Energy Center at (914) 254-6773.Sincerely yours, RW/as cc: NRC Resident Inspector's Office Mr. Douglas Pickett, NRR Senior Project Manager Mr. William Dean, Regional Administrator, NRC Region 1 Mr. Francis J. Murray, Jr., President and CEO, NYSERDA Ms. Bridget Frymire, New York State Dept. of Public Service}}
| | Sincerely yours, RW/as cc: NRC Resident Inspector's Office Mr. Douglas Pickett, NRR Senior Project Manager Mr. William Dean, Regional Administrator, NRC Region 1 Mr. Francis J. Murray, Jr., President and CEO, NYSERDA Ms. Bridget Frymire, New York State Dept. of Public Service}} |
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Category:Letter type:NL
MONTHYEARNL-21-034, Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals2021-05-26026 May 2021 Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals NL-21-039, Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary2021-05-20020 May 2021 Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary NL-21-033, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2021-05-11011 May 2021 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-21-032, Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center2021-05-11011 May 2021 Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center NL-21-005, Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions2021-05-11011 May 2021 Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions NL-21-030, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0606 May 2021 Submittal of 2020 Annual Radiological Environmental Operating Report NL-21-027, Registration of Spent Fuel Cask Use2021-04-20020 April 2021 Registration of Spent Fuel Cask Use NL-21-021, Registration of Spent Fuel Cask Use2021-04-19019 April 2021 Registration of Spent Fuel Cask Use NL-21-017, Pre-Notice of Disbursement from Decommissioning Trusts2021-04-0808 April 2021 Pre-Notice of Disbursement from Decommissioning Trusts NL-21-010, Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2021-02-17017 February 2021 Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-21-006, Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement2021-02-10010 February 2021 Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement NL-21-014, Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2021-01-26026 January 2021 Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-082, Notice of Planned Transfer of Decommissioning Funds2020-12-14014 December 2020 Notice of Planned Transfer of Decommissioning Funds NL-20-081, Pre-Notice of Disbursement from Decommissioning Trusts2020-12-0909 December 2020 Pre-Notice of Disbursement from Decommissioning Trusts NL-20-080, Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-93212020-11-19019 November 2020 Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-9321 NL-20-079, (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-12012 November 2020 (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NL-20-077, Submittal of Quality Assurance Program Manual Revision 22020-11-0909 November 2020 Submittal of Quality Assurance Program Manual Revision 2 NL-20-078, Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-11-0909 November 2020 Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-076, Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal2020-11-0202 November 2020 Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal NL-20-069, One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-10-0808 October 2020 One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency NL-20-070, Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-10-0202 October 2020 Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-067, Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-09-16016 September 2020 Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-064, 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments2020-09-0101 September 2020 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments NL-20-060, Status of Remaining Actions for Generic Letter 2004-022020-08-11011 August 2020 Status of Remaining Actions for Generic Letter 2004-02 NL-20-057, Cancellation of Commitment Related to Large Break LOCA Reanalysis2020-07-30030 July 2020 Cancellation of Commitment Related to Large Break LOCA Reanalysis NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material2020-07-22022 July 2020 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material NL-20-051, Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center2020-07-0707 July 2020 Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center NL-20-052, Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results2020-07-0707 July 2020 Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results NL-20-012, Application to Revise Provisional Operating License and Technical Specifications2020-06-30030 June 2020 Application to Revise Provisional Operating License and Technical Specifications NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-06-24024 June 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-041, Registration of Unit 3 Spent Fuel Cask Use2020-05-13013 May 2020 Registration of Unit 3 Spent Fuel Cask Use NL-20-042, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2020-05-12012 May 2020 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-20-033, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2020-04-28028 April 2020 Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-20-038, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-04-23023 April 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-035, Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-16016 April 2020 Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-034, Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-13013 April 2020 Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-021, Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-03-24024 March 2020 Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-020, Submittal of 2019 Annual Fitness for Duty Performance Data Report Update2020-02-26026 February 2020 Submittal of 2019 Annual Fitness for Duty Performance Data Report Update NL-20-015, Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2020-02-10010 February 2020 Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-20-008, Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane2020-01-0606 January 2020 Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane NL-19-094, 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2019-12-16016 December 2019 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-19-084, Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments2019-11-21021 November 2019 Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments NL-19-093, Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.12019-11-21021 November 2019 Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.1 NL-19-092, Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-11-20020 November 2019 Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-043, Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.122019-10-22022 October 2019 Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.12 NL-19-073, Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-10-22022 October 2019 Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-078, Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-10-22022 October 2019 Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-19-091, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use2019-10-17017 October 2019 Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use NL-19-090, Registration of Unit 2 Spent Fuel Cask Use2019-10-0909 October 2019 Registration of Unit 2 Spent Fuel Cask Use NL-19-079, 50.59(d)(2) Summary Report of Changes, Tests and Experiments2019-09-26026 September 2019 50.59(d)(2) Summary Report of Changes, Tests and Experiments 2021-05-06
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Entergy Nuclear Northeast Indian Point Energy Center
-En tery 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 254-6710 Robert Walpole Manager Licensing Tel (914) 254-6710 NL-13-111 August 06, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738
Subject:
Indian Point Energy Center Registration of Unit 3 Spent Fuel Cask Use Indian Point, Unit 3 Docket Nos. 50-286 & 72-51 License No. DPR-64 Dear Sir or Madam; Entergy Nuclear Operations, Inc. (Entergy) operates the Indian Point Energy Center (IPEC)
Independent Spent Fuel Storage Installation (ISFSI) in accordance with the general license provisions of 10 CFR 72.210. The conditions of 10 CFR 72.212(b)(2) include the registration of a spent fuel cask within 30 days of using a cask for storage of spent nuclear fuel.
Accordingly, this letter hereby registers the use on July 31, 2013, of the fourth (4) IPEC Unit 3 dry fuel storage cask. The cask was loaded to Amendment #6 of the Holtec CoC #1014 and the corresponding Holtec CFSAR Revision 8. This cask is the twenty third (23) IPEC dry fuel storage cask to be added to the IPEC ISFSI pad.
This letter also provides the following registration information associated with twenty third Holtec HI-STORM 100 spent fuel cask system that was placed into storage on the IPEC ISFSI pad [Docket No. 72-51]. The fuel contained in these casks are from IPEC Unit 3 Nuclear Power Plant, Reactor License No. DPR-64, Docket No. 50-286.
[Fourth (4) Unit 3 Spent Fuel Cask]
Twenty third (23rd) IPEC Soent Fuel Cask System: Date Dlaced in use: July 31. 2013 Licensee's Name: Entergy Nuclear Operations, Inc.
Licensee's Address: Indian Point Energy Center 450 Broadway P.O. Box 249 Buchanan, NY 10511 Cask Model Number: HI-STORM 100 Cask Certificate Number: 1014 MPC Serial Number: 272 HI-STORM Overpack Serial Number: 0652 Number of Fuel Bundles: 32 fuel bundles Vk sA '
pKU-S3
Indian Point Unit 3 Docket Nos. 50-286 & 72-51 License No. DPR-64 NL-13-111 Page 2 of 2 Total Cask Systems stored at the IPEC ISFSI pad [Docket No. 72-511:
Twenty three (23) HI-STORM 100 Cask Systems Entergy is making no new commitments in this letter. Should you have any questions regarding this matter, please contact Mr. Timothy J. Salentino, Superintendent Dry Fuels Storage, at Indian Point Energy Center at (914) 254-6773.
Sincerely yours, RW/as cc: NRC Resident Inspector's Office Mr. Douglas Pickett, NRR Senior Project Manager Mr. William Dean, Regional Administrator, NRC Region 1 Mr. Francis J. Murray, Jr., President and CEO, NYSERDA Ms. Bridget Frymire, New York State Dept. of Public Service