Letter Sequence Response to RAI |
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EPID:L-2020-LLA-0051, New York State Motion for Leave to Amend Contentions NY-2 and NY-3 (Approved, Closed) |
Results
Other: ML21092A091, ML21194A408, ML21231A182, ML21314A218, ML21346A000, ML21363A165, NL-20-021, Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device, RS-21-077, License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink
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MONTHYEARNL-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 Project stage: Other ML20084Q1912020-03-24024 March 2020 New York State Motion for Leave to Amend Contentions NY-2 and NY-3 Project stage: Request ML20108E9482020-04-17017 April 2020 Acceptance Review Determination for Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device Project stage: Acceptance Review ML20184A0012020-07-0606 July 2020 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML21363A1582020-07-31031 July 2020 E-mail from A. Peterson,Nyserda to R. Guzman, NRC, Informal Questions Indian Point Unit 3, HI-LIFT Crane License Amendment Request Project stage: Request ML20233B0152020-08-20020 August 2020 Request for Additional Information (E-mail Dated 8/20/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device Project stage: RAI ML20268C2352020-09-24024 September 2020 Request for Additional Information (E-mail Dated 9/24/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device Project stage: RAI 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 Project stage: Response to RAI ML21363A1602020-10-22022 October 2020 E-mail from A. Peterson, NYSERDA, to R. Guzman, NRC, Informal Questions Indian Point Unit 3, HI-LIFT Crane License Amendment Request Project stage: Request NL-20-077, Submittal of Quality Assurance Program Manual Revision 22020-11-0909 November 2020 Submittal of Quality Assurance Program Manual Revision 2 Project stage: Request 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 Project stage: Response to RAI ML21013A0142020-12-21021 December 2020 Clarification Call for Draft RAIs (E-mail Dated 12/21/20) License Amendmet Request to Revise Licensing Basis for New Auxiliary Lifting Device Project stage: Draft RAI ML21013A0152021-01-12012 January 2021 Draft Request for Additional Information (E-mail Dated 1/12/2021) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device Project stage: Draft RAI ML21019A5672021-01-19019 January 2021 Second Round Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device Project stage: RAI ML21363A1642021-01-19019 January 2021 E-mail from A. Peterson, NYSERDA, to R. Guzman, NRC, Informal Questions Indian Point Unit 3, HI-LIFT Crane License Amendment Request Project stage: Request 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 Project stage: Request ML21060B6022021-03-11011 March 2021 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML21078A5102021-03-19019 March 2021 E-mail from P. Couture to R. Guzman) Hi-Lift Crane Proposed License Amendment Request Confirmatory Information Project stage: Request ML21363A1652021-03-23023 March 2021 3/23/2021 E-mail from R. Guzman, NRC, to A. Peterson, NYSERDA, State Comments for IP3 HI-LIFT Crane License Amendment Request Project stage: Other ML21092A0912021-04-0202 April 2021 E-mail NRR Review Hour Estimate Change Supporting the Hi-Lift Crane Proposed License Amendment Request Review Project stage: Other ML21096A3332021-04-0606 April 2021 E-mail Dated 4/6/2021, Transmittal of Draft Safety Evaluation for Proposed License Amendment Revision to Licensing Basis to Incorporate the Installation and Use of of New Auxiliary Lifting Device Project stage: Draft Approval ML21111A3612021-04-21021 April 2021 4/21/2021 Letter from A. Peterson (NYSERDA) to R. Guzman (Nrc), New York State Comments Indian Point Energy Center Unit 3 License Amendment Request (HI-LIFT Crane) Project stage: Request ML21112A2672021-04-22022 April 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (Public Redacted Version) Project stage: RAI 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 Project stage: Response to RAI ML21194A4082021-07-13013 July 2021 (7-13-2021) E-mail NRR Review Hour Estimate Change Supporting the Hi-Lift Crane Proposed License Amendment Request Review Project stage: Other RS-21-077, License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink2021-08-0202 August 2021 License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink Project stage: Other ML21231A1822021-08-26026 August 2021 Unit, No. 3 - Audit Plan in Support of Review of License Amendment Request Regarding the Installation and Use of a New Auxiliary Lifting Device Project stage: Other ML21337A2952021-12-0303 December 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (E-mail Dated 12/3/2021) Project stage: RAI ML21346A0002021-12-16016 December 2021 Unit, No. 3 - Regulatory Audit Summary Concerning License Amendment Request to Install and Use a New Auxiliary Lifting Device Project stage: Other ML22003A1932022-01-0303 January 2022 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 Project stage: Response to RAI ML21314A2182022-01-18018 January 2022 Audit Plan in Support of Review of License Amendment Request Regarding the Ultimate Heat Sink Project stage: Other ML22028A1032022-01-28028 January 2022 E-mail Dated 1/28/2022, Transmittal of Draft Safety Evaluation for Proposed License Amendment Revision to Licensing Basis to Incorporate the Installation and Use of of New Auxiliary Lifting Device Project stage: Draft Approval ML21091A3052022-02-28028 February 2022 Issuance of Amendment No. 272 Revision to Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device (EPID L-2020-LLA-0051) (Non-Proprietary) Project stage: Approval 2021-12-03
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Category:Legal-Affidavit
MONTHYEARML22003A1932022-01-0303 January 2022 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-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-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-20-021, 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 ML14259A1152014-09-0909 September 2014 Submittal of Westinghouse Review of Draft NRC Audit Report Regarding Indian Point Nuclear Generating Units Nos. 2 and 3 NL-13-123, EPRI Letter to NRC Request for Withholding of the Following Proprietary Information Included in: Dated September 25, 20132013-09-25025 September 2013 EPRI Letter to NRC Request for Withholding of the Following Proprietary Information Included in: Dated September 25, 2013 ML12048B4552012-02-15015 February 2012 Attachment 1: Declaration of Arnold Gundersen on Behalf of Riverkeeper, Inc ML12191A4142011-02-25025 February 2011 Expert Witness Declaration of Arnold Gundersen Regarding Aging Management of Nuclear Fuel Racks ML1035106932010-11-12012 November 2010 Email from Janice Dean, Indian Point, State of New York Nondisclosure Agreements for Teresa Manzi and Adam Dobson on Behalf of the State of New York ML11230B0762009-11-0101 November 2009 Nondisclosure Agreement and Acknowledgment from Richard T. Lahey ML0906204632009-02-27027 February 2009 Indian Point - Affidavit of Andrew L. Stuyvenberg Concerning Mandatory Disclosure Requirements of 10 C.F.R. 2.336(b) ML0804501812008-02-11011 February 2008 Transmittal of Petitioners Westchester Citizen'S Awareness Network (Westcan), Et Al., Answer and Affidavit of Richard L. Brodsky, Esq. in Response to Atomic Safety and Licensing Board Order Dated February 1, 2008 ENOC-07-00042, Supplemental Information 2 in Support of Application for Order Approving Indirect Transfer of Control of Licenses2007-12-0505 December 2007 Supplemental Information #2 in Support of Application for Order Approving Indirect Transfer of Control of Licenses ENOC-07-00036, Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses2007-10-31031 October 2007 Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses ML0224604542002-07-25025 July 2002 Certified Index of Record ML0214201392002-02-13013 February 2002 Motion to Reopen Closed Record - Hearings Held in White Plains, New York During 1982 & 1983 Concerning Feasibility of Evacuation Plan for Indian Point Nuclear Power Plant 2022-01-03
[Table view] Category:Letter
MONTHYEARIR 07200051/20244022024-11-20020 November 2024 NRC Independent Spent Fuel Storage Security Inspection Report No. 07200051/2024402 (Public) ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000003/20240022024-08-0606 August 2024 NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 ML24171A0122024-06-18018 June 2024 Reply to a Notice of Violation EA-24-037 ML24156A1162024-06-0404 June 2024 Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000003/20240052024-05-21021 May 2024 And 3 - NRC Inspection Report Nos. 05000003/2024005, 05000247/2024005, 05000286/2024005, 07200051/2024001, and Notice of Violation ML24128A0632024-05-0707 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 ML24116A2412024-04-25025 April 2024 Annual Environmental Protection Plan Report ML24114A2282024-04-23023 April 2024 Annual Radioactive Effluent Release Report L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) IR 05000003/20240012024-03-20020 March 2024 NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only) ML24080A1722024-03-20020 March 2024 Reply to a Notice of Violation EA-2024-010 ML24045A0882024-02-22022 February 2024 Correction to the Technical Specifications to Reflect Appropriate Pages Removed and Retained by Previous License Amendments ML24053A0642024-02-22022 February 2024 2023 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report IR 05000003/20230042024-02-22022 February 2024 NRC Inspection Report Nos. 05000003/2023004, 05000247/2023004, 05000286/2023004, and 07200051/2023004 and Notice of Violation ML24011A1982024-01-12012 January 2024 ISFSI, Notice of Organization Change for Site Vice President ML23342A1082024-01-0909 January 2024 – Independent Spent Fuel Storage Installation Security Inspection Plan ML23353A1742023-12-19019 December 2023 ISFSI, Emergency Plan, Revision 23-04 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23338A2262023-12-0404 December 2023 Signed Amendment No. 27 to Indemnity Agreement No. B-19 ML23356A0212023-12-0101 December 2023 American Nuclear Insurers, Secondary Financial Protection (SFP) Program ML23242A2772023-11-30030 November 2023 NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 ML22339A1572023-11-27027 November 2023 Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E IR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 ML23100A1252023-11-17017 November 2023 Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23100A1432023-11-16016 November 2023 Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments ML23306A0992023-11-0202 November 2023 And Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23237A5712023-09-22022 September 2023 09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23242A2182023-09-12012 September 2023 IPEC – NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286) ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23255A0142023-08-31031 August 2023 LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 ML23227A1852023-08-15015 August 2023 Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML23222A1442023-08-10010 August 2023 Registration of Spent Fuel Casks ML23208A1642023-07-26026 July 2023 Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater ML23200A0422023-07-19019 July 2023 Registration of Spent Fuel Casks 2024-09-18
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML23192A1002023-07-11011 July 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme ML23103A2732023-04-25025 April 2023 Enclosuresponses to Q&A ML22308A2572022-11-0404 November 2022 Decommissioning International - Response to Request for Additional Information for the Proposed Amended IP2 Master Trust Agreement ML22132A1692022-05-12012 May 2022 Response to Requests for Additional Information Related to Exemption Request and License Amendment Request to Revise the Facilitys Emergency Plan ML22034A6032022-02-0303 February 2022 Response to Request for Additional Information - Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E for Low-level Radioactive Waste Shipments ML22034A7882022-02-0303 February 2022 Response to Requests for Additional Information - Related to Post Shutdown Decommissioning Activities Report ML22003A1932022-01-0303 January 2022 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-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 CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L 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-20-078, 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-20-070, 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 ML20220A6662020-08-0707 August 2020 Responses to NRC Requests for Additional Information (RAI) Re the Request for Indian Point Nuclear Generating Station Units 1, 2 & 3 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 ML20122A1222020-05-27027 May 2020 Letter from Margaret M. Doane to Mr. Lemuel Srolovic, Chief, Environmental Protection Bureau, Office of the Ny Attorney General: Response to Office of Ny Attorney General Regarding Natural Gas Transmission Pipelines Near Indian Point Power ML20122A1052020-05-27027 May 2020 Letter from Margaret M. Doane to John B. Rhodes, Chair and Executive Officer, Ny State Public Service Commission: Response to Ny State Public Service Commission Regarding Natural Gas Transmission Pipelines Near Indian Point Nuclear Power Pl 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 CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary NL-19-023, Response to Request for Additional Information (RAI) - Proposed License Amendment Request Regarding Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool2019-06-0606 June 2019 Response to Request for Additional Information (RAI) - Proposed License Amendment Request Regarding Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool NL-18-045, IP3 ILRT RAI Responses2018-07-0303 July 2018 IP3 ILRT RAI Responses NL-18-045, Indian Point Nuclear Generating Unit 3 - Response to Request for Additional Information for Acceptance of License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years2018-07-0303 July 2018 Indian Point Nuclear Generating Unit 3 - Response to Request for Additional Information for Acceptance of License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years ML18193A4512018-07-0303 July 2018 Response to Request for Additional Information for Acceptance of License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years CNRO-2018-00021, Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station NL-17-161, Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Units 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408)2017-12-21021 December 2017 Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Units 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408) NL-17-127, Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408)2017-11-0808 November 2017 Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408) NL-17-142, Response to Request for Additional Information Regarding Request IP2-ISI-RR-20 for Relief from Examinations of Code Class 1 Component Welds with Less than Essentially 100% Coverage for Fourth Ten-Year Inservice Inspection..2017-11-0101 November 2017 Response to Request for Additional Information Regarding Request IP2-ISI-RR-20 for Relief from Examinations of Code Class 1 Component Welds with Less than Essentially 100% Coverage for Fourth Ten-Year Inservice Inspection.. ML17300A1742017-10-27027 October 2017 10/27/17 E-mail from M. Mirzai to R. Guzman Inter-Unit Transfer of Spent Fuel LAR - Updated Clarification Response Following Teleconference on October 19, 2017 ML17298B6472017-10-25025 October 2017 10/25/17 E-mail from M. Mirzai to R. Guzman Inter-Unit Transfer of Spent Fuel LAR - Clarification Response Following Teleconference on October 19, 2017 NL-17-115, Response to Request for Additional Information Re Inter-Unit Transfer of Spent Fuel, Attachments 1, 2, 3 (non-proprietary Version of Report HI-2094289, Rev. 9) and 7 Enclosed2017-10-0202 October 2017 Response to Request for Additional Information Re Inter-Unit Transfer of Spent Fuel, Attachments 1, 2, 3 (non-proprietary Version of Report HI-2094289, Rev. 9) and 7 Enclosed NL-17-109, Request for Additional Information for Proposed License Amendment Regarding the Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank Entergy Nuclear Operations, Inc. Indian Point Nuclear Generating, Unit2017-08-17017 August 2017 Request for Additional Information for Proposed License Amendment Regarding the Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank Entergy Nuclear Operations, Inc. Indian Point Nuclear Generating, Unit NL-17-102, Response to Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel2017-08-16016 August 2017 Response to Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel NL-17-092, Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Re License Renewal Application RAI Set 2017-052017-07-27027 July 2017 Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Re License Renewal Application RAI Set 2017-05 NL-17-084, Reply to Requests for Additional Information for the Review of the License Renewal Application. Re RAI Set 2017-062017-07-27027 July 2017 Reply to Requests for Additional Information for the Review of the License Renewal Application. Re RAI Set 2017-06 NL-17-074, Supplemental Information Regarding Reply to Request for Additional Information Set 2017-01 for the Review of the License Renewal Application (LRA)2017-06-27027 June 2017 Supplemental Information Regarding Reply to Request for Additional Information Set 2017-01 for the Review of the License Renewal Application (LRA) NL-17-069, Reply to Requests for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application RAI Set 2017-05 (CAC Nos. MD5407 and MD5408)2017-06-0808 June 2017 Reply to Requests for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application RAI Set 2017-05 (CAC Nos. MD5407 and MD5408) NL-17-070, Additional Information for the Review of the Plants License Renewal Application (LRA) Regarding the Containment Leak Rate Program2017-05-31031 May 2017 Additional Information for the Review of the Plants License Renewal Application (LRA) Regarding the Containment Leak Rate Program NL-17-061, Reply to Requests for Additional Information for the Review of the License Renewal Application RAI Set 2017-042017-05-24024 May 2017 Reply to Requests for Additional Information for the Review of the License Renewal Application RAI Set 2017-04 NL-17-060, Reply to Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408)2017-05-19019 May 2017 Reply to Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408) NL-17-053, Reply to Request for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-03 (CAC Nos. MD5407 and MD5408)2017-05-18018 May 2017 Reply to Request for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-03 (CAC Nos. MD5407 and MD5408) NL-17-052, Reply to Request for Additional Information for the Review of the License Renewal Application, Set 2017-012017-05-0808 May 2017 Reply to Request for Additional Information for the Review of the License Renewal Application, Set 2017-01 NL-17-044, Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Amendment of Inter-Unit Transfer of Spent Fuel2017-04-19019 April 2017 Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Amendment of Inter-Unit Transfer of Spent Fuel NL-17-039, Updated Response to Request for Additional Information for the Review of License Renewal Application Environmental Review-Severe Accident Mitigation Alternatives Based on a Reduced Renewal Period2017-03-31031 March 2017 Updated Response to Request for Additional Information for the Review of License Renewal Application Environmental Review-Severe Accident Mitigation Alternatives Based on a Reduced Renewal Period ML17096A2122017-03-23023 March 2017 Entergy Engineering Report No. IP-RPT-16-00078, Indian Point RAI CLI-16-07 SAMA Cost-Benefit Sensitivities Rev. 1 (March 23, 2017) NL-17-002, Response to Request for Additional Information for Review of the License Renewal Application Environmental Review - Severe Accident Mitigation Alternatives2017-02-0101 February 2017 Response to Request for Additional Information for Review of the License Renewal Application Environmental Review - Severe Accident Mitigation Alternatives NL-17-013, Response to Request for Additional Information Regarding Relief Request IP3-ISl-RR-09, Alternative to the Depth Sizing Qualification Requirement2017-01-26026 January 2017 Response to Request for Additional Information Regarding Relief Request IP3-ISl-RR-09, Alternative to the Depth Sizing Qualification Requirement NL-17-005, Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components.2017-01-17017 January 2017 Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components. NL-17-002, Indian Point Nuclear Generating, Units 2 and 3, IP-RPT-16-00077, RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan. 4, 2017)2017-01-0404 January 2017 Indian Point Nuclear Generating, Units 2 and 3, IP-RPT-16-00077, RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan. 4, 2017) ML17096A2112017-01-0404 January 2017 Entergy Engineering Report No. IP-RPT-16-00077, Indian Point RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan 4, 2017) ML17040A4352017-01-0404 January 2017 IP-RPT-16-00078, RAI CLI-16-07 SAMA Cost-Benefit Sensitivities, Rev. 0 (Jan. 4, 2017) ML17040A4342017-01-0404 January 2017 IP-RPT-16-00077, RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan. 4, 2017) 2023-07-11
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Proprietary Information - Withhold from Public Disclosure Under 10 CFR 2.390 The balance of this letter may be considered non-proprietary upon removal of Enclosures 2, 3, 4 and 5.
Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 10 CFR 50.90 January 3, 2022 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 Renewed Facility Operating License No. DPR-64
Subject:
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
References:
- 1. Entergy letter to U.S. Nuclear Regulatory Commission (NRC), "Proposed License Amendment to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and use of a New Auxiliary Lifting Device," (ADAMS Accession No. ML20084U773), dated March 24, 2020
- 2. NRC Electronic Mail from R. Guzman (NRC) to A. Sterdis (Holtec Decommissioning International, LLC), " Indian Point Unit No. 3 - SUBSEQUENT REQUEST FOR ADDITIONAL INFORMATION: LAR to Revise Licensing Basis for New Auxiliary Lifting Device," (ADAMS Accession No. ML2337A295), dated December 3, 2021 In Reference 1, Entergy Nuclear Operations, Inc. (Entergy) submitted a request for a proposed amendment to Renewed Facility Operating License (FOL) DPR-64 for Indian Point Nuclear Generating Unit No. 3 (IP3). The proposed amendment requested U.S. Nuclear Regulatory Commission (NRC) approval to incorporate, into the IP3 Licensing Basis, the installation and use of a new single failure proof auxiliary lifting device (i.e., the Holtec International (Holtec)
HI-LIFT) to handle a dry cask storage (DCS) transfer cask (i.e., the HI-TRAC) in the IP3 Fuel Storage Building (FSB).
In Reference 2, the NRC transmitted a subsequent request for additional information (RAI) concerning the proposed license amendment. The Enclosures to this letter are provided in response to the RAI.
Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 Page 2 of 3 HDI-IPEC-22-001 provides a summary of the HDI response to the RAI. This enclosure is non-proprietary.
The following Enclosures provide design and procurement information referenced in the RAI response provided in Enclosure 1:
- HI-2210873-R0, Failure Modes and Effects Analysis (FMEA) for IP3 HI-LIFT Mechanical and Control Systems,
- HI-2188549-R3, IPEC Unit 3 HI-LIFT Specification,
- HI-2188625-R4, Structural Evaluation of HI-LIFT Device and Spent Fuel Building Walls at Indian Point Unit 3,
- DWG-11654-R5, HI-LIFT Ancillary Lift Device Licensing Drawing The documents provided in these enclosures are design and procurement specifications. The information included in these documents is proprietary to Holtec International, and therefore these enclosures (Enclosures 2, 3, 4 and 5) are proprietary in their entirety and are supported by an affidavit included as the Attachment to this letter. 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 Commissions regulations.
There are no new regulatory commitments in the RAI response enclosed in this letter.
Should you have any questions or require additional information, please contact Andrea Sterdis, HDI Decommissioning Vice President at (724)493-1833 or myself at 856-797-0900 ext. 3578.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b), a copy of this application, with non-proprietary enclosure and attachments, is being provided to the designated State Officials.
I declare under penalty of perjury that the foregoing is true and correct. Executed on January 3, 2022.
Sincerely, Jean A. Fleming HDI Vice President, Regulatory and Environmental Affairs Holtec Decommissioning International, LLC I I I I I H 0 LT E C DECOMMISSIONING I N T E R N A T I O N A L Digitally signed by Jean A. Fleming DN: cn=Jean A. Fleming, c=US, o=Holtec Decommissioning International, LLC, ou=Regulatory and Environmental Affairs, email=J.Fleming@Holtec.com Date: 2022.01.03 17:24:02 -05'00' Jean A.
Fleming
Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax (856) 797-0909 Page 3 of 3 HDI-IPEC-22-001
Enclosures:
- 1. Response to Subsequent Request for Additional Information (RAI-9)
- 2. HI-2210873-R0, Failure Modes and Effects Analysis (FMEA) for IP3 HI-LIFT Mechanical and Control Systems (Proprietary)
- 3. HI-2188549-R3, IPEC Unit 3 HI-LIFT Specification (Proprietary)
- 4. HI-2188625-R4, Structural Evaluation of HI-LIFT Device and Spent Fuel Building Walls at Indian Point Unit 3 (Proprietary)
- 5. DWG-11654-R5, HI-LIFT Ancillary Lift Device Licensing Drawing (Proprietary
Attachment:
Affidavit Pursuant to 10 CFR 2.390 cc:
NRC Senior Project Manager, NRC NRR DORL NRC Senior Project Manager, NRC NMSS NRC Region l Regional Administrator NRC Senior Regional Inspector, Indian Point Energy Center New York State Liaison Officer Designee, NYSERDA New York State (NYS) Public Service Commission I I I I I H 0 LT E C DECOMMISSIONING I N T E R N A T I O N A L
HDI-IPEC-22-001 Response to Subsequent Request for Additional Information (RAI-9)
RAI 9 (SCPB-Plant Systems): Crane Stability following Component Failures Regulatory Basis:
The Nuclear Regulatory Commission (NRC, or Commission) staff evaluates whether the licensees request can be approved per Title 10 of the Code of Federal Regulations (10 CFR), Section 50.92, Issuance of Amendment, which states in part that, In determining whether to issue an amendment to a license, the Commission will be guided by the considerations which govern issuance of initial licenses. Applicable regulations considered in issuing initial licenses include 10 CFR 50.34, Contents of Applications; Technical Information, and applicable general design criteria (GDC) from Appendix A to 10 CFR Part 50. Specifically, 10 CFR 50.34(b)(2) requires, in part, that the safety analysis report contain a description and analysis of fuel handling systems, with emphasis upon performance requirements, the bases upon which such requirements have been established, and the evaluations required to show that safety functions will be accomplished. The description shall be sufficient to permit understanding of the system designs and their relationship to safety evaluations. In addition, 10 CFR 50.34(b)(6) requires, in part, that the safety analysis report include plans for preoperational testing and conduct of normal operations, including maintenance and testing. Finally, GDC 4 requires appropriate protection for SSCs important to safety (e.g., irradiated fuel) against dynamic effects, including the effects of missiles (e.g.,
falling heavy loads) that may result from equipment failures.
Request Consistent with regulatory guidance in NUREG-0554, heavy load handling systems should be designed to stop and hold the load following a loss of power and equipment failure. This standard satisfies GDC 4 by providing appropriate protection for irradiated fuel contained within a fuel transfer cask or within the spent fuel pit. In order to satisfy regulatory requirements related to evaluations demonstrating safety functions will be accomplished and plans for preoperational testing and normal operation, additional information is necessary to define additional design features and conduct of preoperational tests, normal operations, and maintenance. Accordingly, please provide the following information:
- 1. Provide an update to HI-2188549, IPEC Unit 3 HI-LIFT Specification, that includes:
- a. Information establishing the maximum acceptable threshold regarding uneven operation of the hydraulic cylinders, where the HI-LIFT structure, in its most limiting orientation(s), remains capable of supporting its full rated load. This update should include key assumptions, the method of analysis, the loading condition, and the acceptance criteria established for the HI-LIFT components and the interfacing structures. [The information in the response to a request for additional information provided by letter dated May 20, 2021 (ADAMS Accession No. ML21140A451), is acceptable for this purpose.]
- b. Information describing how the HI-LIFT would be prevented from exceeding this threshold considering credible single component failures and acceptable operating conditions that may affect the HI-LIFT response. This information may reference a separate failure modes and effects analysis to define credible failures and identify mitigating equipment. The response should specifically address:
(1) hydraulic swing cylinders; (2) hydraulic system for movement of the swing cylinders, including valves;
(3) control system for positioning swing cylinders; (4) instrumentation and actuation systems necessary to place the HILIFT in a safe state following credible malfunctions of the hydraulic control system; (5) operator actions; and (6) any equipment or design features necessary for the operator actions to be timely and effective.
- c. Information describing the basic design and performance requirements for systems or components performing important to safety functions controlling cylinder position (as described in the response to (b.) above).
- d. Preoperational and periodic test programs necessary to demonstrate that systems or components would be capable of performing important to safety functions in controlling cylinder position.
- 2. Provide a failure modes and effects analysis of the (a) hydraulic swing cylinders; (b) hydraulic system for movement of the swing cylinders, including valves; (c) control system for positioning swing cylinders; and (d) instrumentation and actuation systems necessary to place the HILIFT in a safe state following credible malfunctions of the hydraulic control system. To the extent necessary to support understanding of the design, failure mods, and mitigation strategies, also provide component descriptions and system drawings.
- 3. Provide an analysis demonstrating that the time available for any credited operator actions necessary to place the HILIFT in a safe configuration following credible failures affecting the hydraulic swing cylinders or the associated control system is adequate.
HDI Response:
The HDI response is provided in the following table. Enclosures 2, 3, 4 and 5 provide the detailed information in response to the RAI 9 requests. The table identifies where the response information is located in the Enclosures.
Table 1: HDI Response to NRC Subsequent Request for Additional Information Concerning the HI-LIFT License Amendment Request Page 1 of 2 NRC DRAFT RAI-9 Holtec Response
- 1. Provide an update to HI-2188549, IPEC Unit 3 HI-LIFT Specification, that includes:
Revision 3 of the HI report HI-2188549 is now issued and submitted
- a.
Information establishing the maximum acceptable threshold regarding uneven operation of the hydraulic cylinders, where the HI-LIFT structure, in its most limiting orientation(s), remains capable of supporting its full rated load. This update should include key assumptions, the method of analysis, the loading condition, and the acceptance criteria established for the HI-LIFT components and the interfacing structures.
[The information in the response to a request for additional information provided by letter dated May 20. 2021, is acceptable for this purpose.]
Description of the load case added to Section 3.2.2 Evaluation added to structural report HI-2188625 Appendix. H
- b. Information describing how the HI-LIFT would be prevented from exceeding this threshold considering credible single component failures and acceptable operating conditions that may affect the HI-LIFT response. This information may reference a separate failure modes and effects analysis to define credible failures and identify mitigating equipment. The response should specifically address (1) hydraulic swing cylinders; (2) hydraulic system for movement of the swing cylinders, including valves; (3) control system for positioning swing cylinders; (4) instrumentation and actuation systems necessary to place the HI-LIFT in a safe state following credible malfunctions of the hydraulic control system, (5) operator actions, and (6) any equipment or design features necessary for the operator actions to be timely and effective.
(1) Hydraulic swing cylinders, included in Table 12-3 (2) Hydraulic system for movement of swing cylinders, included in Table 12-4 (3) Manual operating controls added to HI-2188549 Section 3.7.4 (4) Visual Indication System added to HI-2188549 Section 3.5.7 HI-Resolution Visual Indication System added to HI-2188549 Section 3.5.8 Requirements for mechanical limit switch system added to 3.7.3.12 and Appendix F (5) Operator actions established in 3.7.4 Requirements for analysis of operator actions Added to Section 6.6.4 Ongoing Inspections added to Table 6.1
( 6 ) Equipment and design established in Section 3.7.4.
Requirements for analysis of operator actions Added to Section 6.6.4
Table 1: HDI Response to NRC Subsequent Request for Additional Information Concerning the HI-LIFT License Amendment Request Page 2 of 2 The relationship of leak rate to time limit is explained in Section 6.6.4
- c.
Information describing the basic design and performance requirements for systems or components performing important to safety functions controlling cylinder position (as described in the response to b. above).
Control system information consolidated into Section 3.7 (of HI-2188549):
3.7.1 Swing Cylinder Primary Controls 3.7.2 Strand Jack Primary Controls 3.7.3 Protection Control System 3.7.4 Manual Operations System The supervisory system is described in 3.7.3.
The mechanical Position Differential Indication System is described in 3.7.3.12, and detailed in Appendix F.
- d. Preoperational and periodic test programs necessary to demonstrate that systems or components would be capable of performing important to safety functions in controlling cylinder position.
Preoperational and periodic tests added to HI-2188549. Summaries in Table 6.1, descriptions in the body of Section 6.
Load hold leak test added to 6.6 Testing programs in FMEA incorporated by reference.
- 2. Provide a failure modes and effects analysis of the All included under Holtec document HI-2210873-R0 (1) hydraulic swing cylinders; (2) hydraulic system for movement of the swing cylinders, including valves; (3) control system for positioning swing cylinders; (4) instrumentation and actuation systems necessary to place the HI-LIFT in a safe state following credible malfunctions of the hydraulic control system.
- i.. To the extent necessary to support understanding of the design, failure mods, and mitigation strategies, also provide component descriptions and system drawings.
- 3. Provide an analysis demonstrating that the time available for any credited operator actions necessary to place the HI-LIFT in a safe configuration following credible failures affecting the hydraulic swing cylinders or the associated control system is adequate.
Operator actions established in 3.7.4 Requirements for analysis of operator actions Added to Section 6.6.4
Proprietary Information - Withhold from Public Disclosure Under 10 CFR 2.390 HDI-IPEC-22-001 HI-2210873-R0 Failure Modes and Effects Analysis (FMEA) for IP3 HI-LIFT Mechanical and Control Systems Proprietary
Proprietary Information - Withhold from Public Disclosure Under 10 CFR 2.390 HDI-IPEC-22-001 HI-2188549-R3 IPEC Unit 3 HI-LIFT Specification Proprietary
Proprietary Information - Withhold from Public Disclosure Under 10 CFR 2.390 HDI-IPEC-22-001 HI-2188625-R4 Structural Evaluation of HI-LIFT Device and Spent Fuel Building Walls at Indian Point Unit 3 Proprietary
Proprietary Information - Withhold from Public Disclosure Under 10 CFR 2.390 HDI-IPEC-22-001 DWG-11654-R5 HI-LIFT Ancillary Lift Device Licensing Drawing Proprietary
HDI-IPEC-22-001 Attachment Affidavit Pursuant to 10 CFR 2.390
US. Nuclear Regulatory Commission ATTN: Document Control Clerk Non-Proprietary Attachment to HDIlPEC-ZZ-Ol AFFIDAVIT PURSUANT TO 10 CFR 2.390 1, Jean A. Fleming, being duly sworn, depose and state as follows:
- 1) I have reviewed the information provided in HI-2210873-R0, Failure Modes and E"ects Analysis (FMEA) for 1P3 HILIF T Mechanical and Control Systems, HI-2188549-R3, IPEC Unit 3 HI-LIF T Specification, III-2188625-R4, Structural Evaluation of HI-LIF T Device and Spent Fuel Building Walls at Indian Point Unit 3, and DWGl 1654-R5, HI-LIFTAncillary Lift Device Licensing Drawing, which is sought to be withheld, and am authorized to apply for its withholding.
- 2) The information sought to be withheld is in III-2210873-R0, HI-2188549-R3, HI-2188625-R4 and DWG-11654-R5 is provided as Enclosures 2, 3, 4 and 5 to HDI Letter HDI-IPEC-22-01. These documents are design and procurement speci"cations and the information included in the documents is proprietary to Holtec International.
- 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(b)(4) and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR Part 9.17(a)(4), 2.390(a)(4), and 2.390(b)(1) for trade secrets and commercial or "nancial information obtained from a person and privileged or con"dential (Exemption 4). The material for which exemption from disclosure is here sought is all con"dential commercial information, and some portions also qualify under the narrower de"nition of trade secret, within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Proiect V. Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992),_and Public Citizen Health Research Group v. FDA, 704F2d1280 (DC Cir. 1983).
- 4) Some examples of categories of information which "t into the de"nition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by Holtecs Page 1 of 5
US. Nuclear Regulatory Commission ATTN: Document Control Clerk Non-Proprietary Attachment to HDIIPEC22-01 AFFIDAVIT PURSUANT TO 10 CFR 2.390 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 and 4.b, and 4.0 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 con"dence 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 con"dence 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 maintenance of the information in con"dence. 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.
Page 2 of 5
US. Nuclear Regulatory Commission ATTN: Document Control Clerk Non-Proprietary Attachment to HDIIPEC-22-Ol AFFIDAVIT PURSUANT TO 10 CFR 2.390
- 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 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 classi"ed as proprietary was developed and compiled by Holtec International at a signi"cant cost to Holtec International. This information is classi"ed 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 Internationals technical database and the results of evaluations performed by Holtec International. A substantial effort has been expended by Holtec International to develop this information. Release of this information would improve a competitors position because it would enable Holtecs competitor to copy our technology and offer it for sale in competition with our company, causing us "nancial injury.
- 9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to Holtec Internationals competitive position and foreclose or reduce the availability of pro"t-making opportunities. The information is part of Holtec Internationals comprehensive decommissioning and 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 Page 3 of 5
US. Nuclear Regulatory Commission ATTN: Document Control Clerk Non-Proprietary Attachment to HDI-IPEC-22-Ol AFFIDAVIT PURSUANT TO 10 CFR 2.390 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 dif"cult to quantify, but it clearly is substantial.
Holtec Intemationals 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 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.
Page 4 of 5
US. Nuclear Regulatory Commission ATTN: Document Control Clerk Non-Proprietary Attachment to HDl-IPEC-22-01 AFFIDAVIT PURSUANT TO 10 CFR 2.390 STATE OF NEW JERSEY )
)
ss:
COUNTY OF CAMDEN
)
Jean A. Fleming, being duly sworn, deposes and says:
That she has read the foregoing af"davit and the matters stated therein are true and correct to the best of her knowledge, information, and belief.
Executed at Camden, New Jersey, this 6 day of January 2022.
- 92. a. 2,?
Jean A. Fleming Holtec Decommissioning International Holtec International VP, Regulatory & Environmental Affairs Subscribed and sworn before me this <<3! day of @
2022 SHARON v. PAGE NOTARY PUBUC OF new <<sassy My 0mm Exam 0mm Page 5 of 5