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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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- ~~Entergx Entergv Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel (914) 254-6700 Anthony J Vitale Site Vice President NL-'17-062 May 10, 2017 U.S. Nuclear Regulatory Commission Document Control Desk 11545 Rockville Pike, TWFN-2 F1
,Rockville, MD 20852-2738
SUBJECT:
Request for Deferral of Actions Related to Beyond-Design-Basis External Event Seismic Actions - Commitment Date Changes Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64
REFERENCES:
- 1) NRC letter, "Request for Information Pursuant to Title 1O 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", dated March 12, 2012(ML12056A046).
- 2) NEI letter, Proposed Path Forward for NTTF Recommendation 2. 1:
Seismic Reevaluations, dated April 9, 2013(ML13101A379).
- 3) NRC letter, Endorsement of EPRI Final Draft Report 1025287, "Seismic Evaluation Guidance," dated February 15, 2013 (ML12319A074).
- 4) Entergy's Letter NL-14-152, "Entergy's Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident", dated December 22, 2014 (ML15008A086).
- 5) Report 1025287, Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, dated February 2013 (ML12333A170).
- 6) Entergy Letter NL-16-033, "Commitment Changes Concerning Expedited Seismic Evaluation process Report Plant Modifications in Regard to Seismic Hazard Re-Evaluations for Recommendation 2.1 of
NL-17-062 Docket Nos. 50-24 7 and 50-286 Page 2 of 3 the Near-Term Task Force Review of Insights from the.Fukushima Dai-ichi Accident, dated March 31, 2016.
- 7) Final Determination of Licensee Seismic Probabilistic Risk Assessments under the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(F) Regarding Recommendation 2.1 "Seismic" of The Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated October 27, 2015 (ML15194A015).
- 8) Entergy Letter NL-17-021, "Notification of Permanent Cessation of Power Operations, Indian Point Nuclear Generating Unit Nos. 2 and 3",
dated February 8, 2017(ML17044A004).
- 9) NSIR /DPR-ISG-02, Interim Staff Guidance Emergency Planning Exemption Requests for Decommissioning Nuclear Power Plants.
Dear Sir or Madam:
In Reference 1, the Nuclear Regulatory Commission (NRC) issued a 50.54(f) letter to all power reactor licensees and holders of construction permits in active 'or deferred status. Enclosure 1 of Reference 1 requested each addressee located in the Central and Eastern United States (CEUS) to submit a Seismic Hazard Evaluation and Screening Report within 1.5 years from the date of Reference 1.
In Reference 2, the Nuclear Energy Institute (NEI) requested NRC agreement to delay submittal of the final GEUS Seismic Hazard Evaluation and Screening Reports so that an update to the Electric Power Research Institute (EPRI) ground motion attenuation model could be completed and used to develop that information. NEI proposed that descriptions of subsurface materials and properties and base case velocity profiles be submitted to the NRC by September 12, 2013, with the remaining seismic hazard and screening information submitted by March 31, 2014.
NRG agreed with that proposed path forward in Re~erence 3.
1 Reference 1 requested that licensees provide interim evaluations and actions taken or planned to address the higher seismic hazard relative to the design basis, as appropriate, prior to completion of the risk evaluation. In accordance with the NRC endorsed guidance in Reference 3, Entergy submitted the Expedited Seismic Evaluation Process (ESEP) Report for Indian Point Units 2 and 3 in Reference 4, which provided the information described in Section 7 of Reference 5 in accordance with the schedule identified in Reference 2.
As i~eritified in References 6 and 7, the completion dates for the SRPAs and associated commitments are currently June 30, 2017 for IP2 and June 30, 2018 for IP3. As stated in Reference 8, IP 2 and IP3 will cease operation in 2020 and 2021 respectively. In light of this decision, this letter p'rovides notification of the deferral of the completion dates for the IP2 and IP3 SPRAs and associated commitments to August 1, 2020 for IP2 and August 1, 2021 for IP3.
The attachments provide the revised commitments to reflect the revised dates and provide the bases for the acceptability.
NL-17-062 Docket Nos. 50-247 and 50-286 Page 3 of 3 If you have any questions, or require additional information, please contact Mr. Robert Walpole at 914-254-6710.
The1*e are no new regulatory commitments contained in this letter.
Sincerely, AJV/mm
Attachment:
- 1. Bases for Acceptability of Revised Completion Dates for IP2 and IP3 Seismic Probabilistic Risk Assessment (SPRA) and Associated Commitments
- 2. Revised Dates of the Regulatory Commitments Made In Entergy Letter NL-16-033 cc: Mr. Daniel H. Dorman, Regional Administrator, NRC Region I Mr. John Beska, Branch Chief (Acting), NRR/JLD/JOMB Mr. Richard Guzman, NRR Senior Project Manager Ms. Bridget Frymire, New York State Department of Public Service Mr. John B. Rhodes, President and CEO NYSERDA NRC Resident Inspector's Office
ATTACHMENT 1 TO NL-17-062 BASES FOR ACCEPTABILITY OF REVISED COMPLETION DATES FOR IP2 AND IP3 SEISMIC PROBABILISTIC RISK ASSESSMENTS (SPRA) AND ASSOCIATED COMMITMENTS ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286
NL-17-062 Attachment 1 Page 1 of 2
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BASES FOR ACCEPTABILITY OF REVISED COMPLETION DATES FOR IP2 AND IP3 SEISMIC PROBABILISTIC RISK ASSESSMENTS (SPRA) AND ASSOCIATED COMMITMENTS Bases for Extension In ML16235A292 and ML15149A140 Indian Pont Energy Center (IPEC) informed the NRC that it has completed the actions required by NRC Orders EA-12-049 and EA-12-051. The completion of these NRC orders provides IPEC with tangible safety benefits that address the licensing basis seismic risks. Compliance with these orders provides not only the ability to address ELAP and LUHS events, but also provides the ability to provide make up water to the SFP under these conditions.
Additionally, in order to meet the requirements of 10CFR50.54(hh)(2) IPEC has additional acti0ns in place to restore core cooling, containment, and spent fuel pool cooling under loss of large areas of the plant.
Seismic Probabilistic Risk Assessment (SPRA)
IPEC has performed an interim seismic evaluation, and provided the results to the NRC in December 2014(ML15008A086). Additionally, IPEC has completed the Seismic Probabilistic Risk Assessment (SPRA) for IP2 and has determined the estimates for the seismic core damage frequency and the seismic large early release frequency to be 3.13 E-05 and 3.52 E-06 respectively. This evaluation will be available at IPEC for inspection/evaluation by the NRC if desired. These values are below the 1O E-04 value used in the Commission Safety Goal Polic:y Statement to determine if adequate protection of the public is provided. The SPRA for IP3, although not completed, was progressing in a manner similar to the IP2 SPRA and considering the close proximity of the 2 units the results would be expected to be similar.
The results of these evaluations confirm the NRC's previous conclusions that adequate protection of the public is provided for seismic events at IPEC. This evaluation is contained in the NRC May 9, 2014 letter, "Screening and prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Re-Evaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights From the Fukushima Dai-ichi Accident." This evaluation concluded that" ... the staff has confirmed that
. the conclusions reached in Gl-199 safety/risk assessment remain valid and that the plants can continue to operate while additional evaluations are conducted."
- Additionally, the basis for performance of SPRAs is contained in the May 9, 2014 NRC letter. In the letter the NRC states:
Seismic Risk Evaluation - Longer-term seismic risk evaluation provides the most comprehensive information to make regulatory decisions, such as whether to amend a plant's design or licensing basis or make additional safety enhancements. These evaluations provide information to make risk-informed decisions. The staff will use this information in conjunction with the existing regulatory tools, such as backfit analysis, to decide on further regulatory actions. The longer-term seismic risk evaluations could be
f NL-17-062 Attachment 1 Page 2of2 decide on further regulatory actions. The longer-term seismic risk evaluations could be either a Seismic Margins Analysis or a Seismic Probabilistic Risk Assessment, depending on the magnitude of the exceedance.
As can be seen from the NRC letter, the use of the SPRAs is to provide information to input to decisions on future actions. The SPRA completion is currently scheduled for June 30, 2017 for IP2 and June 30, 2018 for IP3. As discussed in Entergy Letter NL-17-021, "Notification of.
Permanent Cessation of Power Operations, Indian Point Nuclear Generating Unit Nos. 2 and 3",
dated February 8, 2017 (ML17044A004), IP 2 and IP3 will cease operation in 2020 and 2021 respectively. Considering the SPRA due dates, time required for NRC review of the SPRA, time for NRC decision process, the issuing of actions, time for the plant to evaluate, design, schedule, and implement these actions, there is simply insufficient time for the SPRA effort to result in any actual appreciable safety benefit.
Therefore, this letter provides notification of the deferral of the completion dates for the IP2 and IP3 SPRAs and associated commitments to August 1, 2020 for IP2 and August 1, 2021 for IP3.
Spent Fuel Pool Seismic Evaluation For similar reasons, the performance of the Spent Fuel Pool Seismic Evaluations associated with the SPRAs is not warranted for the remaining period of operation. IPEC understands that unlike the Reactor Pressure Vessel, the Spent Fuel Pool will not be immediately defueled.
However, as indicated in Reference 9 of this Letter, a Spent Fuel Pool checklist or seismic evaluation is required to be performed to support the effective and efficient decommissioning of the facility. This criterion will provide reasonable safety assurance needed for the shutdown and defueled plant.
Conclusion IPEC is providing notification of the deferral of the remaining actions, required to complete the response to Recommendation 2.1 Seismic, including the SPRAs, to August 1, 2020 for IP-2 and August 1, 2021 for IP-3.
ATTACHMENT 2 TO NL-17-062 REVISED DATES OF THE REGULATORY COMMITMENTS MADE IN ENTERGY LETTER NL-16-033 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286
NL-17-062 Attachment 2 Page 1 of 1 REVISED DATES OF THE REGULATORY COMMITMENTS MADE IN ENTERGY LETTER NL-16-033 The following table identifies revised dates for those actions committed to by Entergy in NL 033. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
TYPE (Check one) SCHEDULED COMMITMENT COMPLETION DATE ONE-TIME CONTINUING (If Required)
ACTION COMPUANCE Entergy will use the insights gained x August 1, 2020 through the performance of the SPRA for Indian Point Unit 2 to determine what modifications, procedure or strategy changes would provide the best safety improvement Entergy will use the insights gained x August 1, 2021 through the performance of the SPRA for Indian Point Unit 3 to determine what modifications, procedure or strategy changes would provide the best safety improvement