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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
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24173A2132024-06-13013 June 2024 NRC Presentation; Indian Point Decommissioning Oversight Board, Dated June 13, 2024 ML23031A2532022-12-0707 December 2022 NRC Presentation at New York State Decommissioning Oversight Board on December 7, 2022 in Cortlandt, New York (Dockets 50-003, 247, 286) ML21217A1992021-08-18018 August 2021 Virtual Public Meeting Presentation Slides - Post Shutdown Decommissioning Activities Report, 08/15/2021 PSDAR Public Webinar Meeting ML21207A0262021-07-29029 July 2021 Public Meeting Presentation Slides - Post Shutdown Decommissioning Activities Report, 07/29/2021 PSDAR Public Meeting ML21214A1402021-07-29029 July 2021 Updated Indian Point Public Meeting Presentation Slides - Post Shutdown Decommissioning Activities Report, 07/29/2021 PSDAR Public Meeting ML21036A0382021-02-0808 February 2021 Pre-submittal Meeting Presentation (02/08/2021) Relief Request No. IP3-ISI-RR-16 ML20269A1722020-09-30030 September 2020 Presentation Material for 9/30/2020 Pre-Submittal Meeting Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Onsite Exercise Requirements ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML20265A2902020-09-22022 September 2020 Annual Assessment Meeting - Quick Start Guide for Meeting Access ML20265A2842020-09-22022 September 2020 Annual Assessment Meeting - Webinar Presentation 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 ML19289A0042019-10-17017 October 2019 Presentation Material for 10/17/19 Pre-Submittal Meeting Entergy to Holtec Proposed License Transfer Application ML19269B6832019-10-0202 October 2019 NEIMA Section 108 Public Meeting Slides - Indian Point - October 2, 2019 ML19198A2392019-07-17017 July 2019 Annual Assessment Meeting for Indian Point Energy Center - Meeting Summary ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML17200C9272017-07-0606 July 2017 07/26/2017 Entergy Presentation Slides for Public Meeting Regarding Spent Fuel Pool Management Project, New Criticality Analysis ML17150A0012017-06-20020 June 2017 6/20/2017 Meeting Slides - Entergy Nuclear Operations, Inc. - Licensing Action Submittal Plan - Decommissioning (CAC Nos. MF9624, MF9625, MF9626, MF9627, and MF9628) ML17166A2892017-06-20020 June 2017 Entergy Slides for 06/20/2017 Public Meeting, Licensing Action Submittal Plan - Decommissioning. ML17171A1922017-06-14014 June 2017 NRC Staff Presentation - Power Reactor Decommissioning Program ML17171A1872017-06-14014 June 2017 NRC Staff Presentation - Baffle-Former Bolt Inspections at Indian Point ML16182A1772016-06-30030 June 2016 6/8/2016 - Indian Point Units 2 & 3 Annual Assessment Meeting - Handouts & Submissions from Individuals ML16182A1022016-06-30030 June 2016 6/8/2016 - Indian Point Units 2 & 3 Annual Assessment Meeting - Presentations from the Public ML16182A0672016-06-30030 June 2016 6/8/2016 - Indian Point Units 2 & 3 Annual Assessment Meeting - NRC Presentation Slides ML14232A6552014-06-0404 June 2014 Waka Imamichi - Concerns from Indian Point Annual Assessment Meeting ML14232A5962014-06-0404 June 2014 Gary Shaw - Statement and Questions from Indian Point Annual Assessment Meeting IR 05000247/20130112014-04-29029 April 2014 IR 05000247-13-011 & 05000286-13-011, and Notice of Violation, Indian Point Energy Center Units 2 & 3, and Office of Investigations Report No. 1-2012-036 ML12361A1552012-12-26026 December 2012 Summary of Entergy Drop-In on December 19, 2012 ML12130A1312012-05-0909 May 2012 Annual Assessment Posterboard Slides 2012 ML1117906392011-06-28028 June 2011 Summary of Meeting with Entergy Operations Inc ML1117400622011-06-23023 June 2011 Summary of June 2, 2011 Annual Assessment Meeting with Members of the Public ML1116801732011-06-17017 June 2011 Annual Assessment Meeting - Written Statements from the Public ML1112502382011-05-0909 May 2011 Summary of Category 1 Public Meeting with Entergy on the Transfer of Spent Fuel from Unit 3 to Unit 2 at Indian Point Nuclear Generating Unit Nos. 2 and 3 (TAC Nos. ME1671, ME1672, and L24299) ML1011303462010-04-22022 April 2010 Annual Assessment Meeting Slides - Entergy Presentation ML1011303362010-04-22022 April 2010 Annual Assessment Meeting - NRC Slides ML1009900312010-04-13013 April 2010 Entergy Nuclear Operations (Entergy): Meeting Presentation 2009 Nuclear Safety Culture Assessment Meeting ML0913906312009-06-0404 June 2009 ACRS Meeting with the U.S. Nuclear Regulatory Commission, - June 4, 2009, Slides ML0914700202009-05-26026 May 2009 Annual Assessment Meeting Attendance Sheet ML0914700132009-05-26026 May 2009 Meeting Slides, Plant Performance Review Indian Point Energy Center, Entergy NRC Annual Assessment Meeting ML0914700162009-05-26026 May 2009 NRC Slides for Indian Point Units 2 & 3, Annual Assessment Meeting ML1100410152009-05-20020 May 2009 Visit Briefing Package -Kristine L. Svinicki, NRC Commissioner; Indian Point Energy Center Site Visit; Indian Point Nuclear Generating Unit Nos. 1, 2 & 3; Entergy Nuclear Northeast,, Entergy Nuclear Operations, Inc ML0913804352009-04-15015 April 2009 Meeting Slides SM-0902, Testing the Functionality of Parameter Change Enable Keyswitch ML0913804362009-04-15015 April 2009 Meeting Slides, Teleperm Xs Permissions and Operating Modes ML11083A0542009-03-0606 March 2009 Lr Hearing - Slides from ACRS Subcommittee Meeting on March 4, 2009 ML0823107362008-08-0808 August 2008 IPEC ANS Public Meeting - Entergy Slides ML0823107202008-08-0808 August 2008 IP ANS Public Meeting - August 8, 2008; NRC Slides ML0818404872008-07-0202 July 2008 NRC/DRS/EB1 Slides for Indian Point License Renewal Exit Meeting, June 18, 2008 ML0821305302008-06-18018 June 2008 License Renewal, Slides ML0905401612008-05-31031 May 2008 NRC Slides for Public Meeting, Assessment: Indian Point Contaminated Groundwater ML0905401622008-05-31031 May 2008 NRC Government to Government Meeting Slides - NRC Assessment: Indian Point Contaminated Groundwater ML0814804812008-05-27027 May 2008 NRC Graphics - Indian Point 2024-06-13
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24173A2132024-06-13013 June 2024 NRC Presentation; Indian Point Decommissioning Oversight Board, Dated June 13, 2024 ML23031A2532022-12-0707 December 2022 NRC Presentation at New York State Decommissioning Oversight Board on December 7, 2022 in Cortlandt, New York (Dockets 50-003, 247, 286) ML21217A1992021-08-18018 August 2021 Virtual Public Meeting Presentation Slides - Post Shutdown Decommissioning Activities Report, 08/15/2021 PSDAR Public Webinar Meeting ML21207A0262021-07-29029 July 2021 Public Meeting Presentation Slides - Post Shutdown Decommissioning Activities Report, 07/29/2021 PSDAR Public Meeting ML21214A1402021-07-29029 July 2021 Updated Indian Point Public Meeting Presentation Slides - Post Shutdown Decommissioning Activities Report, 07/29/2021 PSDAR Public Meeting ML21036A0382021-02-0808 February 2021 Pre-submittal Meeting Presentation (02/08/2021) Relief Request No. IP3-ISI-RR-16 ML20269A1722020-09-30030 September 2020 Presentation Material for 9/30/2020 Pre-Submittal Meeting Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Onsite Exercise Requirements ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML20265A2842020-09-22022 September 2020 Annual Assessment Meeting - Webinar Presentation 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 ML19289A0042019-10-17017 October 2019 Presentation Material for 10/17/19 Pre-Submittal Meeting Entergy to Holtec Proposed License Transfer Application ML19269B6832019-10-0202 October 2019 NEIMA Section 108 Public Meeting Slides - Indian Point - October 2, 2019 ML19198A2392019-07-17017 July 2019 Annual Assessment Meeting for Indian Point Energy Center - Meeting Summary ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML18075A1232018-03-20020 March 2018 Entergy Nuclear Operations - March 20, 2018, Presentation Slides for Surveillance Frequency Control Program, UFSAR Change Considerations ML17200C9272017-07-0606 July 2017 07/26/2017 Entergy Presentation Slides for Public Meeting Regarding Spent Fuel Pool Management Project, New Criticality Analysis ML17171A1982017-06-20020 June 2017 Presentations by Members of the Public - Indian Point Annual Assessment Meeting ML17171A1922017-06-14014 June 2017 NRC Staff Presentation - Power Reactor Decommissioning Program ML17171A1872017-06-14014 June 2017 NRC Staff Presentation - Baffle-Former Bolt Inspections at Indian Point ML17160A1952017-06-12012 June 2017 Meeting Slides for Pre-Submittal Meeting with Entergy Regarding the Plan for Decommissioning Licensing Actions ML16182A1022016-06-30030 June 2016 6/8/2016 - Indian Point Units 2 & 3 Annual Assessment Meeting - Presentations from the Public ML16182A0672016-06-30030 June 2016 6/8/2016 - Indian Point Units 2 & 3 Annual Assessment Meeting - NRC Presentation Slides ML16166A2812016-06-0606 June 2016 Media Briefing Slides June 6, 2016 IR 05000247/20130112014-04-29029 April 2014 IR 05000247-13-011 & 05000286-13-011, and Notice of Violation, Indian Point Energy Center Units 2 & 3, and Office of Investigations Report No. 1-2012-036 ML12361A1552012-12-26026 December 2012 Summary of Entergy Drop-In on December 19, 2012 ML12130A1312012-05-0909 May 2012 Annual Assessment Posterboard Slides 2012 ML1116801732011-06-17017 June 2011 Annual Assessment Meeting - Written Statements from the Public ML1116721212011-06-16016 June 2011 Annual Assessment Meeting Slides ML1112502382011-05-0909 May 2011 Summary of Category 1 Public Meeting with Entergy on the Transfer of Spent Fuel from Unit 3 to Unit 2 at Indian Point Nuclear Generating Unit Nos. 2 and 3 (TAC Nos. ME1671, ME1672, and L24299) ML1011303462010-04-22022 April 2010 Annual Assessment Meeting Slides - Entergy Presentation ML1011303362010-04-22022 April 2010 Annual Assessment Meeting - NRC Slides ML0926400612009-09-24024 September 2009 Summary of Conference Call with Entergy on Proposed Response to a Request for Additional Information on Generic Letter 2004-02 ML0926401682009-08-28028 August 2009 Diffusion Models ML0913906312009-06-0404 June 2009 ACRS Meeting with the U.S. Nuclear Regulatory Commission, - June 4, 2009, Slides ML0914700162009-05-26026 May 2009 NRC Slides for Indian Point Units 2 & 3, Annual Assessment Meeting ML0914700132009-05-26026 May 2009 Meeting Slides, Plant Performance Review Indian Point Energy Center, Entergy NRC Annual Assessment Meeting ML0913804362009-04-15015 April 2009 Meeting Slides, Teleperm Xs Permissions and Operating Modes ML11083A0542009-03-0606 March 2009 Lr Hearing - Slides from ACRS Subcommittee Meeting on March 4, 2009 ML11083A0252009-03-0303 March 2009 Lr Hearing - Latest Slides ML11077A0332009-02-24024 February 2009 Lr Hearing - Draft Slides ML0823107362008-08-0808 August 2008 IPEC ANS Public Meeting - Entergy Slides ML0823107202008-08-0808 August 2008 IP ANS Public Meeting - August 8, 2008; NRC Slides ML0819303272008-07-11011 July 2008 NRC Annual Performance Assessment of Indian Point, Units 2 & 3, Reactor Oversight Program, Meeting Slides ML0819605452008-07-0202 July 2008 Entergy End of Cycle Plant Performance Review Slides, 7/2/08 ML0818404872008-07-0202 July 2008 NRC/DRS/EB1 Slides for Indian Point License Renewal Exit Meeting, June 18, 2008 ML0904102282008-07-0101 July 2008 2 SBO DG PM003.png; Develop Annual PM for Sbo/App R DG Swgr/Sfmrs Space Heaters ML0821305302008-06-18018 June 2008 License Renewal, Slides ML0904102082008-06-0505 June 2008 2 SBO DG PM001.png; Develop PM for Sbo/App R DG Battery ML0905401612008-05-31031 May 2008 NRC Slides for Public Meeting, Assessment: Indian Point Contaminated Groundwater ML0905401622008-05-31031 May 2008 NRC Government to Government Meeting Slides - NRC Assessment: Indian Point Contaminated Groundwater 2024-06-13
[Table view] |
Text
Proprietary Information* Withhold from Public Disclosure Under 10 CFR 2.390
- The balance of this letter may be considered non-proprietary upon removal of Attachment 2.
~ Ent'Dr'i~ c; I
- Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Tel 601-368-5573 Ron Gaston Director. Nuclear Licensing 10 CFR 50.12 NL-20-008 January 6, 2020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Indian Point Nuclear Generating Unit 3 Fuel Handling Building Crane Indian Point Nuclear Generating Unit 3 NRC Docket Nos. 50-286 Renewed Facility Operating License No. DPR-64
Reference:
Meeting Notice, "Partially Closed Meeting with Entergy Operations, Inc. and Holtec International to Discuss License Amendment Request to Replace the Indian Point Nuclear Generating Unit No. 3 Fuel Handling Building Crane with a New Holtec High-Lift Crane)," (ADAMS Accession No. ML20002A033), dated January 2, 2020 A partially closed meeting between Entergy Operations, Inc. (Entergy), Holtec International (Holtec), and the U.S. Nuclear Regulatory Commission (NRC) staff is scheduled for January 16, 2020. The purpose of this meeting is to discuss a planned license amendment request to replace the Indian Point Nuclear Generating Unit 3 Fuel Handling Building Crane with a new Holtec High-Lift Crane. The purpose of this letter is to transmit both proprietary and non-proprietary versions of the presentation slides that Entergy will use during the meeting.
Attachment 1 provides a non-proprietary version of the presentation slides. Attachment 2 provides a proprietary version of the presentation slides. Since Attachment 2 contains information proprietary to Holtec, it is supported by an Affidavit signed by Holtec, the owner of the information, which is provided in Attachment 3. The Affidavit sets forth the basis on which the information may be withheld from public disclosure by the NRC and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commission's regulations.
Accordingly, it is respectfully requested that the information which is proprietary to Holtec (i.e.,
Attachment 2) be withheld from public disclosure in accordance with 10 CFR Section 2.390 of the Commission's regulations.
NL-20-008 Page 2 of 2 Correspondence with respect to the copyright or proprietary aspects of the items listed above, or the supporting Holtec Affidavit, should be addressed to Ms. Kimberley Manzione, Licensing Manager, Holtec International, 2500 Broadway, Camden, NJ 08104 This letter contains no new commitments and no revisions to existing commitments.
Should you have any questions or require additional information, please contact Ron Gaston at 601-368-5573.
Ron Gaston RWG/jls Attachments: 1. Presentation Slides, "Indian Point Energy Center Unit 3, Pre-Submittal Meeting, License Amendment Request, HI-LIFT System," (Non-Proprietary)
- 2. Presentation Slides, "Indian Point Energy Center, Unit 3 Pre-Submittal Meeting, License Amendment Request NRC, HI-LIFT System,"
(Proprietary)
- 3. Holtec Affidavit Pursuant to 10 CFR 2.390, "Pre-Submittal Meeting on IPEC HI-LIFT, dated December 31, 2019 cc: Regional Administrator, NRC Region I NRC Senior Resident Inspector, Indian Point Nuclear Generating Units 2 and 3 NRC Senior Project Manager, NRC/NRR/DORL President and CEO, NYSERDA New York State Public Service Commission
Attachment 1 NL-20-008 Presentation Slides Indian Point Energy Center Unit 3, Pre-Submittal Meeting License Amendment Request, HI-LIFT System (Non-Proprietary)
Indian Point Nuclear Generating Unit 3 NRC Docket No. 50-286 Renewed Facility Operating License DPR-64
Indian Point Energy Center Unit 3 Pre-Submittal Meeting License Amendment Request HI-LIFT System
~ Enferpv b.J
Introduction and Meeting Purpose Present information on the design, operation, and qualification of a new auxiliary lifting device that will be installed at Indian Point Unit 3 (IP3) to facilitate improved handling of dry cask storage (DCS) transfer casks Describe planned LAR necessary to implement the new auxiliary lifting device Solicit NRC Staff feedback prior to LAR submittal to facilitate a more efficient NRC review 2 6)1----- - - ---------./IJV-------o WE POWE R LI F ESM
Agenda
- Current Dry Cask Loading Process at IP3
- Proposed Change to Current Process
- Benefits of HI-LIFT System
- Technical Discussion of HI-LIFT System
- License Amendment Request Schedule 3 (S)i--------11----------.l'H------O WE POWE R L I F E SM
Dry Cask Loading at IPEC Using Wet Transfer
- Fuel is transferred from IP3 Spent Fuel Pool (SFP) to IP2 SFP using the Shielded Transfer Canister (STC).
- The STC is placed in a HI-TRAC to transfer from U3 to U2
- At this time IPEC is the only licensee in the country that transfers spent fuel from one SFP to another SFP prior to loading fuel 4 0---------11~1------.J,J,J.IW---o WE P OWE R L I F ESM
The Wet Transfer Process - Unit 3 Process:
Use 40-ton crane to Lower STC into Load 8 -12 transfer STC U3 SFP Fuel Bundles to U3 SFP into STC l
Transport Lift from SFP Perform STC STC/HTto U2 and lower Closure Process FSB STC into HT Shielded Transfer Cask - STC Spent Fuel Pool - SFP Lift STC from Fuel Storage Building - FSB HT & Lower into HI-TRAC -HT U2 SFP 5 (S)i-----1-----------./'N-------O WE POWE R LI F ESM
Wet Transfer Process Unit 2 Process:
Unload fuel At later date from STC & transfer fuel from racks to MPC Transfer Perform Transfer the loade loaded HS to Stack-up in TB 32M/HT to U2 TB the ISFSI Pad & Transfer MPC into HS STC - Shielded Transfer Cask HT-HI-TRAC SFP - Spent Fuel Pool Multi Purpose Canister - MPC HS - High Storm 100 TB -Truck Bay ISFSI - Interim Spent Fuel Storage Facility 6 (S)---~1-------------l'N-------O WE POWE R LI F ESM
Dry Cask Loading at IP3 using the HI-LIFT System Process:
Use HL to transfer the MPC/HT to the SFP Load fuel assemblies into the MPC
... transfer the M PC/HT to the l
HL - HI-LIFT MPC - Multi Purpose Canister HT - HI-TRAC Move the M PC/HT SFP - Spent Fuel Pool to ISFSI then Stack TB - Truck Bay HS - HI-STORM 100 ISFSI - Independent Spent Fuel Storage Installation 7 (S)---~1---------Ml'-------o WE POWER LI F ESM
HI-LIFT Benefits Over Current Process
- Direct loading of fuel into MPC 32M/HI-TRAC from the IP3 SFP
- Reduced number of fuel handling movements
- Current method: 3 load movements per cask
- HI-LIFT method: 1 load movement per cask
- Reduced potential for loading errors
- Approximately 12 years longer to remove all spent fuel from the IP3 SFP using wet transfer system
- Approximately 50 mrem per wet transfer
- Estimate a minimum of 100 wet transfers
- Estimate dose reduction of 5 rem 8 0-----------ll----~----Nol-----O WE POW E R L I F ESM
HI-LIFT Design
- HI-LIFT is a custom designed lifting device to handle empty and fully loaded HI-TRAC transfer casks with MPC-32M storage canisters
- HI-LIFT is wall mounted and removable
- HI-LI FT capacity is rated for 100 tons and tested to 125%
capacity. The weight of a fully loaded MPC-32M/HI-TRAC is approximately 97 Tons
- HI-LIFT meets all applicable requirements of ASME NOG-1 to ensure all safety requirements are met during operation 9 G,...._--1------------.,\N-------O WE P O WE R L I F E SM
HI-LIFT Design (continued)
Provides handling for empty and fully loaded HI-TRAC with MPC-32M storage canisters at IP3
[
PROPRIETARY INFORMATION WITHHELD PER 10CFR2.390
]
10 0 - - - 1 1 - - - - - - - - - - - - . N . I - - - - - O WE POWE R LIFE SM
HI-LIFT Design (continued)
- Connects with a suitable lifting yoke to engage with lifting trunnions on the HI-TRAC positioned at ground level in the IP3 FSB washdown area
- Lifts MPC 32M/HI-TRAC from washdown area to clear SFP wall on southeast side of IP3 SFP
- Translates MPC 32M/HI-TRAC over SFP
- Lowers MPC 32M/HI-TRAC into SFP in a slow controlled manner within range of fuel handling machine
- Crane configuration prohibits cask movement over spent fuel assemblies
- Lifts loaded MPC 32M/HI-TRAC from SFP, translates and lowers MPC 32M/HI-TRAC to IP3 washdown area
- Retreats to clear area for completion of MPC-32M closure activities 11 0 - - - - - --------.NI--------<> WE P O WE R L I FE SM
HI-LIFT Design - Installation
- HI-LI FT is supported by the reinforced concrete structure of the FSB
- HI-LIFT is supported entirely on the robust southeast pool wall and balanced by imparting vertical reactions into the south truck bay wall of the FSB
- Field installed anchor system physically connects the HI-LIFT to the FSB walls
- [PROPRIETARY INFORMATION WITHHELD PER 10CFR2.390]
- Will require modifications to the existing building/systems
- Relocation of Backup SFP Cooling
- Removal of Waste Processing Skid
- Modification to Truck Bay curb 12 <91----1----------------i\lo/--------O WE POWE R LI F ESM
HI-LIFT Design - Demonstration PROPRIETARY INFORMATION WITHHELD PER 10CFR2.390 13 e--11---1---------------.-w-1.*- - o w E P o wE R L I F E SM
HI-LIFT Design - Demonstration PROPRIETARY INFORMATION WITHHELD PER 10CFR2.390 14 {S)------1111- - - - - l ' V J - - N- - o W E POWER LIFE sM
HI-LIFT Design - Demonstration PROPRIETARY INFORMATION WITHHELD PER 10CFR2.390 Q~----11-----~M-------o WE P OWE R L I F E SM
HI-LIFT Design - Demonstration PROPRIETARY INFORMATION WITHHELD PER 10CFR2.390 16 (S)--1------------.IW--------O WE POWER LI F ESM
HI-LIFT Design Compliance - NOG-1
- HI-LIFT is designed as a Type I crane per NOG-1 requirements
- Uti Iize N OG-1 load cases
- Utilize NOG-1 seismic analysis methodology
- Conforms with NOG-1 safety factors for mechanical and structural components
- Includes NOG-1 safety features in control systems
- Comply with NQA-1 quality requirements for procurement and fabrication
- Comply with NOG-1 requirements for factory and site testing 17 {9f----------l~-------..M/>------o WE POWER LI F ESM
HI-LIFT Design - Structural Analysis
- Analysis performed under normal and accident (seismic) conditions considering the 3 limiting configurations.
- The limiting conditions were based on;
- [PROPRIETARY INFORMATION WITHHELD PER 10CFR2.390 18 0 - - - 1 ~ 1--------.11.".M-\*- - - - - - < O wE p Ow E R L I F E SM
HI-LIFT Design - Structural Analysis PROPRIETARY INFORMATION WITHHELD PER 10CFR2.390 19 @>-----1-------------NV'-------<> WE P OWE R L I F E SM
HI-LIFT Design - Structural Analysis
- Reaction forces and bending moments from ANSYS analyses are obtained for all welded and bolted connections and anchor locations
- Support reactions are also obtained for FSB wall structural analyses.
- Stress results from FEA and supplemental calculations used to show compliance with NOG-1
- These results were verified by a qualified 3 rd party reviewer (LPI) 20 6).__--~-------.JW------o WE POWER LI F ESM
HI-LIFT Design - Structural Analysis
- FEA results verify stress limits of all members of the HI-LIFT are below allowable stress limits per NOG-1
- Load reactions used to verify weld and bolted connections are below allowable stress limits per NOG-1
- Support reactions input to models of supporting concrete walls to verify reactions are below allowable limits.
21 6)------------11~1_ _ _ _ _ _M,.__.- - o wE p O wE R L I F E SM
HI-LIFT Design - Structural Analysis
- Heaviest loading condition in each configuration is considered
- Primary stress limits from NOG-1 Section 4300 used to qualify the structural members
- Load combinations per NOG-1 Section 4140 are used where applicable
- Single failure proof handling capability is demonstrated through compliance with NOG-1 requirements for structural and mechanical components 22 6)1----------11---------.M/'------o W E POW ER L IFE SM
HI-LIFT Design - Structural Analysis
- Accident Condition (Seismic Condition)
- Heaviest loading condition in each configuration is considered
- Seismic loads per NOG-1 Section 4136 along with load combinations per Section 4140 considered
- Seismic load combination is evaluated using a response spectrum analysis per NOG-1 Section 4150
- The stress limits from NOG-1 Section 4300 are used to qualify the structural members 23 <9..__--1------------1w------o WE POWER LI F ESM
Building Walls - Structural Analysis
- HI-LI FT is supported directly by the reinforced concrete structure of the FSB
- Analysis performed for the 6 foot 3-inch thick SFP wall and the 1-foot thick truck bay support wall
- FSB walls are analyzed per American Concrete Institute (ACI) 318-63 to match Plant UFSAR
- FSB walls analyzed using load combinations per ACI 318-63 to match plant UFSAR
- Reaction loads on the FSB walls obtained from structural analysis of the HI-LIFT design under normal and accident conditions 24 0,...____ ____.f----------lN'-----0 WE POWE R L I F E SM
Building Walls - Structural Analysis PROPRIETARY INFORMATION WITHHELD PER 10CFR2.390 25 (9i-------lf--------l'N-------O WE POWER LI F ESM
HI-LIFT Testing and Acceptance
- Follow NOG-1 Section 7000 requirements for factory and site testing
- Functional testing (factory and site)
- Load testing (factory and site) 26 0 - - ~ 1 11-- - .. - - -ow
./1,Hlo/'- E p Ow ER LI F ESM
HI-LIFT LAR
- Incorporate Design Functions into IPEC Licensing Basis
- Consistent with Humboldt Bay precedent
- No change to Technical Specifications
- Supporting technical reports
- Structural Analysis of HI-LIFT Device and FSB Walls at Indian Point Unit 3
- Licensing Drawing 27
-------,f-----------lVll'-------<l W E POWE R L I F E SM
Schedule
- NRC Submittal planned for 1st Quarter 2020
- Request approval in 13 months
- HI-LIFT fabrication and construction; 4 th Quarter 2021-2022
- IP3 Cask loading scheduled for 2 nd Quarter 2023 28 0---11-----------.N.1>------o WE POWE R L I F E SM
Attachment 2 NL-20-008 Presentation Slides Indian Point Energy Center Unit 3, Pre-Submittal Meeting License Amendment Request, HI-LIFT System (Proprietary)
Indian Point Nuclear Generating Unit 3 NRC Docket No. 50-286 Renewed Facility Operating License DPR-64 Proprietary Information - Withhold from Public Disclosure Under 10 CFR 2.390
Attachment 3 NL-20-008 Holtec Affidavit Pursuant to 10 CFR 2.390 Pre-Submittal Meeting on IPEC HI-LIFT, dated December 31, 2019 Indian Point Nuclear Generating Unit 3 NRC Docket No. 50-286 Renewed Facility Operating License DPR-64 Attachment 2 contains information proprietary to Holtec International. The proprietary determination is supported by this Affidavit, which is signed by Holtec International, the owner of the information.
This Affidavit sets forth the basis on which the information may be withheld from public disclosure by the NRC and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commission's regulations.
U.S. Nuclear Regulatory Commission Pre-Submittal Meeting on IPEC HJ-LIFT AFFIDAVIT PURSUANT TO 10 CFR 2.390 I, Kimberly Manzione, being duly sworn, depose and state as follows:
(l) I have reviewed the information described in paragraph (2) which is sought to be withheld, and am authorized to apply for its withholding.
(2) The information sought to be withheld is marked information provided in the pre-submittal meeting slides for the Indian Point HI-LIFT LAR. These slides contain Holtec Proprietary information.
(3) In making this application for withholding of proprietary information of which it is the owner, Holtec International relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec.
552(6)(4) and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10CFR Part 9.17(a)(4), 2.390(a)(4), and 2.390(b)(1) for "trade secrets and commercial or financial information obtained from a person and privileged or confidential" (Exemption 4 ). The material for which exemption from disclosure is here sought is all "confidential commercial information", and some portions also qualify under the narrower definition of "trade secret",
within the meanings assigned to those terms for purposes ofFOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatorv Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2d 1280 (DC Cir. 1983).
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U.S. \luclear Regulatory Commission Pre*Submittal Meeting on IPEC Hl*LIFT AFFIDAVIT PURSUANT TO 10 CFR 2.390 (4) Some examples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by Holtec's competitors without license from Holtec International constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.
- c. Information which reveals cost or price information, production, capacities, budget levels, or commercial strategies of Holtec International, its customers, or its suppliers;
- d. Information which reveals aspects of past, present, or future Holtec International customer-funded development plans and programs of potential commercial value to Holtec International;
- e. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs 4.a, 4.b, and 4.e above.
(5) The information sought to be withheld is being submitted to the NRC in confidence. The information (including that compiled from many sources) is of a sort customarily held in confidence by Holtec International, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by Holtec International. No public disclosure has been made, and it is not available in public sources. All disclosures to third parties, including any required transmittals to the NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for 2 of 5
U.S. "luclear Regulatory Commission Pre-Submittal Meeting on IPEC HI-LIFT AFFIDAVIT PURSUANT TO 10 CFR 2.390 maintenance of the information in confidence. Its initial designation as proprietary information. and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge. Access to such documents within Holtec International is limited on a "need to know 11 basis.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his designee ), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside Holtec International are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information classified as proprietary was developed and compiled by Holtec International at a significant cost to Holtec International. This information is classified as proprietary because it contains detailed descriptions of analytical approaches and methodologies not available elsewhere. This information would provide other parties, including competitors, with information from Holtec lnternational's technical database and the results of evaluations performed by Holtec International. A substantial effort has been expended by Holtec International to develop this infonnation.
Release of this information would improve a competitor's position because it would enable Holtec's competitor to copy our technology and offer it for sale in competition with our company, causing us financial injury.
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U.S. Nuclear Regulatory Commission Pre-Submittal Meeting on IPEC HI-LIFT AFFIDAVIT PURSUANT TO 10 CFR 2.390 (9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to Holtec International's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of Holtec International's comprehensive spent fuel storage technology base, and its commercial value extends beyond the original development cost.
The value of the technology base goes beyond the extensive physical database and analytical methodology, and includes development of the expertise to determine and apply the appropriate evaluation process.
The research, development. engineering, and analytical costs comprise a substantial investment of time and money by Holtec International.
The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
Holtec Intemational's competitive advantage will be lost if its competitors are able to use the results of the Holtec International experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to Holtec International would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive Holtec International of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing these very valuable analytical tools.
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U.S. Nuclear Regulatory Commission Pre-Submittal Meeting on IPEC Hl-LIPT AFFIDAVIT PURSUANT TO 10 CFR 2.390 STATE OF NEW JERSEY )
) ss:
COUNTY OF CAMDEN )
Kimberly Manzione, being duly sworn, deposes and says:
That she has read the foregoing affidavit and the matters stated therein are true and correct to the best of her knowledge, information, and belief.
Executed at Camden, New Jersey, this 31 51 day of December, 2019.
Kimberly Manzione Licensing Manager Holtec International Subscribed and sworn before me this .,31 ~ day of.!J~ , 21JI .
Erika Grandrimo
'-:OT:\RY PURLIC
- ,;f\ff OF ".\LW JERSEY
~IY C0\1MISS\UN I.XPlRl:S far.uary \7, 2022 5 of 5