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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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Text
Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Tel 601-368-5102 Philip Couture Sr. Manager, Regulatory Assurance 10 CFR 50.54(f)
NL-21-005 May 11, 2021 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions Indian Point Nuclear Generating Unit Nos. 2 and 3 NRC Docket Nos. 50-247 and 50-286 Renewed Facility Operating License Nos. DPR-26 and DPR-64 In Reference 1, the U.S. Nuclear Regulatory Commission (NRC) issued a "Request for Information Pursuant to Title 10 of the Code of Federal Regulations [10 CFR] 50.54(f)
Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident" to all NRC power reactor licensees and holders of construction permits in active or deferred status. The Enclosures in Reference 1 contain specific requested actions, requested information, and required responses associated with Recommendations 2.1 (Seismic and Flooding), 2.3 (Seismic and Flooding), and 9.3 (Emergency Preparedness).
In Reference 2, Entergy Nuclear Operations, Inc. (Entergy) notified the NRC that it had decided to permanently cease power operations of Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3, collectively referred to as the Indian Point Energy Center (IPEC)) by April 30, 2020 and April 30, 2021, respectively.
In Reference 3, Entergy requested NRC approval to defer completion of regulatory commitments associated with the "Beyond-Design-Basis External Event Seismic Actions" for IPEC. The requested seismic deferral applied to the Entergy commitments to use the insights gained through the performance of the Seismic Probabilistic Risk Assessments (SPRAs) for IPEC to determine the modifications, procedure, or strategy changes that would provide the best safety improvement. The SPRA results are used to develop the seismic Mitigation Strategies Assessments (MSAs) for each unit. In Reference 4, Entergy requested NRC approval to defer completion of regulatory commitments associated with the "Beyond-Design-Basis External Event Flooding Actions" for IPEC. The requested deferral of the flooding actions commitments pertained to completion of an IPEC flooding Integrated Assessment.
NL-21-005 Page 2 of 4 The requested deferral of these commitments was predicated on the determination that there is insufficient time for the SPRA and flooding Integrated Assessment efforts to result in any appreciable safety benefit considering that IP2 and IP3 will cease operation in 2020 and 2021, respectively (Reference 2).
Regarding the continued applicability of the commitments, the NRC stated in the Reference 5 approval letter that:
"If the licensee decides to continue to operate the units beyond 2020 and 2021, respectively, the licensee would need to provide the SPRAs and the SFP [spent fuel pool] assessments associated with the seismic hazard reevaluations at IP2 and IP3 by August 1, 2020, and August 1, 2021, respectively. The seismic MSAs associated with the seismic hazard reevaluations at IP2 and IP3 would need to be provided by August 1, 2020, and August 1, 2021, respectively. In addition, the licensee would need to provide the flooding IA [Integrated Assessment] for IP2 and IP3 by August 31, 2021."
In References 6 and 7, Entergy submitted certifications in accordance with 10 CFR 50.82(a)(1)(i) and (a)(1)(ii) that power operations had ceased at IP2 on April 30, 2020 and IP3 on April 30, 2021, respectively, and that the fuel was permanently removed from the IP2 and IP3 reactor vessels and placed in the IP2 and IP3 spent fuel pools on May 12, 2020 and May 11, 2021, respectively. By docketing these certifications, Entergy has established that the IP2 and IP3 10 CFR Part 50 licenses no longer authorize operation of the reactors or emplacement or retention of fuel in the reactor vessels. These certifications also establish the non-applicability of the Reference 5 conditional actions if IP2 and IP3 would have operated beyond the planned dates for permanent cessation of power operations.
In the 10 CFR 50.54(f) information request (Reference 1), it states that: "Operating power reactor licensees under 10 CFR Part 50 are required to respond to all of the information requests." However, as described above, IP2 and IP3 are no longer licensed as operating power reactors, in that the reactors for both units have been permanently shutdown and defueled and the 10 CFR Part 50 licenses no longer authorize operation of the reactors.
Therefore, the Reference 3 commitments regarding performance of the SPRAs in response to the 10 CFR 50.54(f) information request are no longer applicable to IP2 and IP3.
In Reference 8, Entergy notified the NRC that the IP2 SPRA commitment was cancelled on June 8, 2020, and the NRC acknowledged the commitment cancellation in Reference 9. This letter provides notification that Entergy is similarly cancelling the IP3 commitment regarding performance of the SPRAs. In addition, this letter provides notification that Entergy is cancelling the Reference 4 commitments pertaining to the IPEC flooding Integrated Assessment since the commitments are no longer applicable to IP2 and IP3 in their current permanently shutdown and defueled conditions.
NL-21-005 Page 3 of 4 If you have any questions regarding this submittal, please contact Mr. Matthew Johnson, Nuclear Manager - IPEC Decommissioning, at 914-254-6288.
There are no new regulatory commitments made in this letter.
Respectfully, Philip Digitally signed by Philip Couture Couture Date: 2021.05.11 14:52:42 -05'00' Philip Couture PC/sp
References:
- 1) U.S. Nuclear Regulatory Commission (NRC) Letter to Entergy Nuclear Operations, Inc. (Entergy), "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," (ML12053A340), dated March 12, 2012
- 2) Entergy letter to NRC, "Notification of Permanent Cessation of Power Operations," (Letter No. NL-17-021) (ML17044A004), dated February 8, 2017
- 3) Entergy letter to NRC, "Request for Deferral of Actions Related to Beyond-Design-Basis External Event Seismic Actions - Commitment Date Changes," (Letter No. NL-17-062) (ML17136A345), dated May 10, 2017
- 4) Entergy letter to NRC, "Request for Deferral of Actions Related to Beyond-Design-Basis External Events Flooding Actions - Commitment Changes,"
(Letter No. NL-17-091) (ML17209A740), dated July 24, 2017
- 5) NRC letter to Entergy, "Indian Point Nuclear Generating Unit Nos. 2 and 3 - NRC Response to Request for Deferral of Actions Related to Beyond-Design-Basis Seismic and Flooding Hazard Reevaluations,"
(ML17222A239), dated October 4, 2017
- 6) Entergy letter to NRC, "Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel,"
(Letter No. NL-20-042), (ML20133J902), dated May 12, 2020
- 7) Entergy letter to NRC, "Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel,"
(Letter No. NL-21-033) (ML21131A157), dated May 11, 2021
NL-21-005 Page 4 of 4
- 8) Entergy letter to NRC, "Cancellation of Commitment Related to Beyond-Design-Basis External Event Seismic Actions," (Letter No. NL-20-046)
(ML20160A029), dated June 8, 2020
- 9) NRC letter to Entergy, "Indian Point Nuclear Generating Unit No. 2 -
Cancellation of Commitment Related to Beyond-Design-Basis External Event Seismic Actions (EPID No. L-2020-JLD-0002)," (ML20182A125),
dated July 30, 2020 cc: NRC Senior Project Manager, NRC NRR DORL NRC Region I Regional Administrator NRC Senior Resident Inspector, Indian Point Energy Center New York State Liaison Officer Designee, NYSERDA New York State (NYS) Public Service Commission
