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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement
Results
Other: ML071210530, ML071840939, ML072830629, ML083540614, ML090790176, ML090790187, ML090820316, ML090820317, ML090820318, ML090820319, ML092860253, ML102930012, ML103060210, ML110200539, ML110350022, ML110550751, ML11187A054, ML11187A055, ML11200A052, ML11276A008, ML11286A140, ML11290A232, ML11305A021, ML12055A234, ML12055A254, ML12157A287, ML12165A684, ML13014A633, ML13161A389, ML13162A604, ML13162A616, ML14136A005, ML14192B395, ML14220A317, ML15114A080, ML15114A081, ML15114A082, ML15114A083, ML15114A084, ML15114A085, ML15166A070, NL-08-023, Entrainment and Impingement at IP2 and IP3: a Biological Impact Assessment, NL-11-024, Letter from Fred Dacimo to Andrew Stuyvenberg Regarding Endangered Species Act Consultation for Indian Point Nuclear Generating Unit Nos. 2 & 3, NL-11-078, License Renewal Thermal Study Documents, NL-11-081, Clean Water Act Section 401 Water Quality Certification Waiver
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MONTHYEARML0712105302007-04-23023 April 2007 License Renewal Application. Appendix E, Applicant'S Environment Report Project stage: Other ML0719900932007-06-26026 June 2007 Ltr. Michael Kaplowitz Re Incompleteness and Inaccurate License Renewal Application for Indian Point Energy Center, Units 2 and 3 Project stage: Request ML0718409392007-08-0606 August 2007 Notice of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process for License Renewal for the Indian Point Nuclear Generating Units 2 and 3 (TAC MD5411 and MD 5412) Project stage: Other ML0728902092007-09-19019 September 2007 Transcript of Indian Point License Renewal Public Meeting: Evening Session, September 19, 2007, Pages 1-126 Project stage: Meeting ML0728901992007-09-19019 September 2007 Transcript of Indian Point License Renewal Public Meeting: Afternoon Session, September 19, 2007, Pages 1-105 Project stage: Meeting ML0728306132007-09-19019 September 2007 License Renewal Application, Environmental Scoping Meeting - September 19, 2007, Written Submittals from Audience - 7:00 Pm Project stage: Meeting ML0728306292007-09-19019 September 2007 License Renewal Application Environmental Scoping Mtg., Written Submittals from Audience - 1:30 Project stage: Other ML0728508952007-10-11011 October 2007 License Renewal Environmental Scoping Meeting Project stage: Meeting ML0728510792007-10-24024 October 2007 09/19/2007 Summary of Public Environmental Scoping Meetings Related to the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application (TAC Nos. MD5411 and MD5412) Project stage: Meeting ML0731009852007-10-25025 October 2007 Revised Fuse Comments on Scope of Environmental Impact Statement and Scoping Process Indian Point Energy Center Unit 2 and Unit 3 Project stage: Request ML0733309312007-12-0505 December 2007 Request for Additional Information Regarding Environmental Review for Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal (TAC Nos. MD5411 and MD5412) Project stage: RAI ML0731104472007-12-0707 December 2007 Request for Additional Information Regarding Severe Accident Mitigation Alternatives for Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Project stage: RAI ML0803800962008-01-30030 January 2008 Supplemental Response to Request for Additional Information Regarding Environmental Review for License Renewal Application Project stage: Response to RAI NL-08-023, Entrainment and Impingement at IP2 and IP3: a Biological Impact Assessment2008-01-31031 January 2008 Entrainment and Impingement at IP2 and IP3: a Biological Impact Assessment Project stage: Other NL-08-028, Official Exhibit - ENT000460-00-BD01 - NL-08-028, Letter from Fred Dacimo, Entergy, to NRC Reply to Request for Additional Information Regarding License Renewal Application - Severe Accident Mitigation Alternatives Analysis (Feb. 5, 2008)2008-02-0505 February 2008 Official Exhibit - ENT000460-00-BD01 - NL-08-028, Letter from Fred Dacimo, Entergy, to NRC Reply to Request for Additional Information Regarding License Renewal Application - Severe Accident Mitigation Alternatives Analysis (Feb. 5, 2008) Project stage: Response to RAI ML0809904032008-02-28028 February 2008 Essential Fish Habitat Information Request for Docket 50-247 and 50-286; Indian Point Nuclear Generating Units 2 and 3 License Renewal, at the Village of Buchanan, Town of Cortlandt, Westchester County, Ny Project stage: Request ML0807704572008-03-0707 March 2008 Document Request for Additional Information Regarding Environmental Review for License Renewal Application - Hudson River Fisheries Program Data (Year Class Report) Project stage: Request ML0809209832008-04-0909 April 2008 03/18/2008-Summary of Telephone Conference Call Between NRC and Entergy Nuclear Operations, Inc., Pertaining to the Indian Point Units 2 & 3, License Renewal Application - Environmental Request for Additional Information Project stage: RAI ML0808801042008-04-0909 April 2008 Request for Additional Information, Review of License Renewal Application Project stage: RAI ML0809404082008-04-14014 April 2008 Request for Additional Information Regarding the Review of the License Renewal Application for Indian Point Nuclear Generating Unit Nos. 2 & 3 (TAC Nos. MD5411 and MD5412) Project stage: RAI NL-08-061, Reply to Document Request for Additional Information Regarding Site Audit Review of License Renewal Application2008-04-23023 April 2008 Reply to Document Request for Additional Information Regarding Site Audit Review of License Renewal Application Project stage: Request ML0810004412008-04-23023 April 2008 Revision of Schedule for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application Project stage: Approval ML0833805912008-04-30030 April 2008 SEIS Reference - Assessment of United Water New York Supply by Rockland County Department of Health Project stage: Request NL-08-083, Reply to Request for Additional Information Regarding License Renewal Application - Refurbishment2008-05-14014 May 2008 Reply to Request for Additional Information Regarding License Renewal Application - Refurbishment Project stage: Response to RAI ML0833805612008-05-21021 May 2008 SEIS Reference - Chemicals in Sportfish and Game: 2007-2008 Health Advisories by Nydoh Project stage: Request NL-08-086, Supplemental Reply to Request for Additional Information Regarding License Renewal Application - Severe Accident Mitigation Alternatives Analysis2008-05-22022 May 2008 Supplemental Reply to Request for Additional Information Regarding License Renewal Application - Severe Accident Mitigation Alternatives Analysis Project stage: Response to RAI ML0833900172008-07-17017 July 2008 SEIS Reference - Online Conservation Guide for Glyptemys Muhlenbergii Project stage: Request ML0835405942008-12-0101 December 2008 NUREG-1437, Suppl. 38, Vol. 1, Dfc, Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 38, Regarding Indian Point Nuclear Generating, Unit Nos. 2 and 3, Main Report Project stage: Acceptance Review ML0835406142008-12-0101 December 2008 NUREG-1437, Suppl. 38, Vol. 2, Dfc, Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 38, Regarding Indian Point Nuclear Generating, Unit Nos. 2 and 3, Appendices Project stage: Other ML0833900342008-12-0202 December 2008 SEIS Reference - Significant Habitats and Habitat Complexes of the New York Bight Watershed by Fws Project stage: Request ML0833900322008-12-0202 December 2008 SEIS Reference - Westchester County Federally Listed Endangered and Threatened Species and Candidate Species by Fws Project stage: Request ML0833900302008-12-0202 December 2008 SEIS Reference - Cynoscion Regalis Gray Weakfish Project stage: Request ML0833900252008-12-0202 December 2008 SEIS Reference - Native Plant Database by Npin Project stage: Request ML0833900232008-12-0202 December 2008 SEIS Reference - Maryland Fish Facts: American Gizzard Shad by Mdnr Project stage: Request ML0833806672008-12-0303 December 2008 SEIS Reference - Trinectes Maculates Fasciatus: Hogchoker Project stage: Request ML0833805702008-12-0303 December 2008 SEIS Reference - Plant Fact Sheets by Ncsu Project stage: Request ML0833805722008-12-0303 December 2008 SEIS Reference - Shortnose Sturgeon (Acipenser Brevirostrum) by Opr Project stage: Request ML0833805752008-12-0303 December 2008 SEIS Reference - Butterflies and Moths of North America Project stage: Request ML0833805402008-12-0303 December 2008 SEIS Reference - Peregrine Falcon Fact Sheet by NYSDEC Project stage: Request ML0833806192008-12-0303 December 2008 SEIS Reference - Status of Fishery Resources Off the Northeastern U.S.: Atlantic and Shortnose Sturgeons Project stage: Request ML0833806232008-12-0303 December 2008 SEIS Reference - Zebra Mussels and the Hudson River Project stage: Request ML0833806272008-12-0303 December 2008 SEIS Reference - Comprehensive Master Plan, Town of Cortlandt, July 2004 Project stage: Request ML0833806292008-12-0303 December 2008 SEIS Reference - Town Profile Project stage: Request ML0833806612008-12-0303 December 2008 SEIS Reference - Annual Drinking Water Quality Report for 2005 by Wjww Project stage: Request ML0833805532008-12-0303 December 2008 SEIS Reference - New York State Amphibian and Reptile Atlas Project by NYSDEC, Species of Turtles Found in New York Project stage: Request ML0833805452008-12-0303 December 2008 SEIS Reference - Bog Turtle Fact Sheet by NYSDEC Project stage: Request ML0833805422008-12-0303 December 2008 SEIS Reference - Peregrine Falcon by NYSDEC Project stage: Request ML0833806332008-12-0303 December 2008 SEIS Reference - Census of Agriculture, Volume 1 Chapter 2: Pennsylvania County Level Data Project stage: Request ML0833805312008-12-0303 December 2008 SEIS Reference - Bald Eagle Fact Sheet by NYSDEC Project stage: Request ML0833806592008-12-0303 December 2008 SEIS Reference - Westchester County Databook: History, Geography, and Land Use Project stage: Request 2008-12-02
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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:Report
MONTHYEARML22013A7062022-01-13013 January 2022 Investigation Report of LLRW Shipment Pursuant to 10 CFR 20, Appendix G ML21056A0782021-04-0707 April 2021 Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Indian Point ISFSI (Docket: 72-51) 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 ML20259A2172020-09-14014 September 2020 Commitment Change Summary Report ML20260H0722020-06-18018 June 2020 IP-RPT-14-00013, Revision 3, Indian Point Nuclear Generating Units 2 and 3, Consequences of a Postulated Fire and Explosion Following the Release of Natural Gas from the New Aim 42 Pipeline Near Ipec 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 ML20100F6352020-04-0808 April 2020 Expert Team Final Report 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) ML19252A3182019-09-0909 September 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of Sept 2, 2019 NL-19-061, Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2019-06-13013 June 2019 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements ML19114A0742019-04-22022 April 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of April 15, 2019 NL-19-012, Request for Approval of a Certified Fuel Handler Training and Retraining Program2019-04-15015 April 2019 Request for Approval of a Certified Fuel Handler Training and Retraining Program ML18098A0882018-04-0606 April 2018 Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-021, Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-20-066, Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center2017-12-19019 December 2017 Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center ML17349A1562017-12-0808 December 2017 Risk Impact of One-Time Extending the ILRT Interval Associated with the Proposed Technical Specification Changes ML17279A2472017-10-0606 October 2017 2017 Annual Assessment Meeting Written Comments Compilation ML17222A2392017-10-0404 October 2017 NRC Response to Request for Deferral of Actions Related to Beyond-Design-Basis Seismic and Flooding Hazard Reevaluations ML17289A6552017-10-0202 October 2017 Attachment 6 to NL-17-115, Revised HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Energy Center, Revision 9 NL-17-122, Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,20172017-09-28028 September 2017 Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,2017 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-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan2017-02-0606 February 2017 License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan 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) ML16280A2282016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, Indian Point 2 Technical Requirements Manual2016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center.2016-09-19019 September 2016 HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center. ML16250A2762016-09-13013 September 2016 Evaluation of Impacts to Proposed Critical Habitat for the Atlantic Sturgeon for Indian Point Nuclear Generating Units 2 and 3 Proposed License Renewal NL-16-083, Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 32016-08-0101 August 2016 Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 3 ML18115A0592016-06-28028 June 2016 After Action Report/Improvement Plan, Drill Date June 28, 2016 ML17052A2662015-10-0202 October 2015 Sturgeon Mobile Tracking for the New Ny Bridge at Tappan Zee NL-15-128, Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update2015-09-28028 September 2015 Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update NL-15-118, Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 32015-09-0303 September 2015 Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 3 NL-15-099, Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2015-07-30030 July 2015 Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-15-072, 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2015-06-18018 June 2015 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-15-030, Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project2015-04-0808 April 2015 Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project NL-15-029, Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 20152015-04-0606 April 2015 Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 2015 ML15062A2002015-02-19019 February 2015 NET-300067-01, Revision 1, Criticality Safety Analysis of the Indian Point, Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels. (Non-Proprietary) NL-15-013, Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval2015-01-28028 January 2015 Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval ML15061A2772014-12-31031 December 2014 WCAP-17954-NP, Revision 0, Indian Point Unit 3 Heatup and Cooldown Limit Curves for Normal Operation. NL-14-152, Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...2014-12-22022 December 2014 Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From... ML14329A1952014-11-0404 November 2014 NET-300067-01, Rev. 0, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels NL-14-115, 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 20142014-09-18018 September 2014 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 2014 ML14304A7012014-09-16016 September 2014 Reliability Needs Assessment ML15166A0702014-08-31031 August 2014 Algonquin Incremental Market (Aim) Project, Phase 2 Acoustic Survey for Indiana Bats (Myotis Sodalis) and Northern Long-Eared Bats (Myotis Septentrionalis), August 2014 NL-14-110, Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-27027 August 2014 Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0592014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 ML14168A0602014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0612014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 2022-01-13
[Table view] Category:Miscellaneous
MONTHYEARML22013A7062022-01-13013 January 2022 Investigation Report of LLRW Shipment Pursuant to 10 CFR 20, Appendix G ML20260H0722020-06-18018 June 2020 IP-RPT-14-00013, Revision 3, Indian Point Nuclear Generating Units 2 and 3, Consequences of a Postulated Fire and Explosion Following the Release of Natural Gas from the New Aim 42 Pipeline Near Ipec 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-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) ML19252A3182019-09-0909 September 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of Sept 2, 2019 NL-19-061, Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2019-06-13013 June 2019 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements ML19114A0742019-04-22022 April 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of April 15, 2019 NL-19-012, Request for Approval of a Certified Fuel Handler Training and Retraining Program2019-04-15015 April 2019 Request for Approval of a Certified Fuel Handler Training and Retraining Program ML17279A2472017-10-0606 October 2017 2017 Annual Assessment Meeting Written Comments Compilation ML17222A2392017-10-0404 October 2017 NRC Response to Request for Deferral of Actions Related to Beyond-Design-Basis Seismic and Flooding Hazard Reevaluations NL-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan2017-02-0606 February 2017 License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan NL-16-083, Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 32016-08-0101 August 2016 Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 3 NL-15-128, Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update2015-09-28028 September 2015 Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update NL-15-118, Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 32015-09-0303 September 2015 Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 3 NL-15-099, Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2015-07-30030 July 2015 Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-15-072, 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2015-06-18018 June 2015 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-15-030, Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project2015-04-0808 April 2015 Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project NL-15-013, Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval2015-01-28028 January 2015 Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval NL-14-152, Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...2014-12-22022 December 2014 Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From... ML14329A1952014-11-0404 November 2014 NET-300067-01, Rev. 0, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels NL-14-115, 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 20142014-09-18018 September 2014 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 2014 ML15166A0702014-08-31031 August 2014 Algonquin Incremental Market (Aim) Project, Phase 2 Acoustic Survey for Indiana Bats (Myotis Sodalis) and Northern Long-Eared Bats (Myotis Septentrionalis), August 2014 NL-14-110, Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-27027 August 2014 Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML14141A5402014-05-0909 May 2014 Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14071A1832014-04-0101 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident NL-14-042, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi.2014-03-31031 March 2014 Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi. NL-14-043, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-03-31031 March 2014 Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. ML14071A1982014-03-20020 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14015A4172014-01-30030 January 2014 Staff Summary of the Steam Generator Tube Inservice Inspections for the Spring 2013 Refueling Outage ML14304A7512013-12-13013 December 2013 Unit 3 Coastal Zone Management Act Consistency Certification, Vol. II of III, Supplemental Information Regarding NYSDEC Record, Part 8 of 9 NL-13-133, 10 CFR 71.95 Report on Failure to Observe Certificate of Compliance Conditions for Radwaste Model 8-120B Cask Vent Port Leak Test Hold Time2013-10-0202 October 2013 10 CFR 71.95 Report on Failure to Observe Certificate of Compliance Conditions for Radwaste Model 8-120B Cask Vent Port Leak Test Hold Time ML13221A4172013-07-26026 July 2013 LTR-13-0662 - Susan Lerner, Common Cause New York Ltr Provides a Copy of Generating Influence, Entergy'S Political Spending and the Battle Over the Indian Point Nuclear Power Plant. ML14304A7522012-12-31031 December 2012 Unit 3 Coastal Zone Management Act Consistency Certification, Vol. II of III, Supplemental Information Regarding NYSDEC Record, Part 9 of 9 ML12346A3432012-11-20020 November 2012 Enclosure to NL-12-167 Seismic Walkdown Report - Page D-69 of 203 Through End ML12346A3422012-11-20020 November 2012 Enclosure to NL-12-167 Seismic Walkdown Report - Cover Through Page C-288 of 434 NL-12-167, Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Cover Through Page C-288 of 4342012-11-20020 November 2012 Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Cover Through Page C-288 of 434 NL-12-167, Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Page D-69 of 203 Through End2012-11-20020 November 2012 Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Page D-69 of 203 Through End NL-12-136, 10 CFR 72.48(d)(2) Report, Listing and Summary of Changes, Tests and Experiments2012-10-0101 October 2012 10 CFR 72.48(d)(2) Report, Listing and Summary of Changes, Tests and Experiments NL-14-002, Enclosure - NL-14-002, SAMA Engineering Project Cost Estimates Prepared by RCM Technologies2012-09-20020 September 2012 Enclosure - NL-14-002, SAMA Engineering Project Cost Estimates Prepared by RCM Technologies NL-12-009, Enclosure 1 to NL-12-009, Holtec International Licensing Report HI-2094289, Revision 52012-01-11011 January 2012 Enclosure 1 to NL-12-009, Holtec International Licensing Report HI-2094289, Revision 5 ML12040A3102012-01-11011 January 2012 Enclosure 1 to NL-12-009, Holtec International Licensing Report HI-2094289, Revision 5 ML11280A1212011-09-28028 September 2011 License Renewal Application - Completion of Commitment #30 Re Reactor Vessel Internals Inspection Plan NL-11-094, Request for Relief Request 14 - Code Case N-770-1 Weld Inspection Frequency Extension2011-08-0303 August 2011 Request for Relief Request 14 - Code Case N-770-1 Weld Inspection Frequency Extension NL-10-109, CFR 50.59(d) Report Listing and Summary Report of the Changes, Tests and Experiments Implemented Between 04/20/2008 and 04/12/20102010-10-12012 October 2010 CFR 50.59(d) Report Listing and Summary Report of the Changes, Tests and Experiments Implemented Between 04/20/2008 and 04/12/2010 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML11299A1752010-02-0808 February 2010 Lr Hearing - Indian Point Task I Report - Deliverable (Redacted Version) ML0936410942009-12-30030 December 2009 Preliminary Power Authority of the State of New York, Indian Point No. 3, Nuclear Power Plant, Systems Interaction Study. Volume II ML0926401772009-08-28028 August 2009 Environmental Science and Engineering NL-09-095, Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes2009-07-21021 July 2009 Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes ML0905407042009-01-0909 January 2009 American Radiation Services, Inc. Laboratory Analysis Report No. ARS1-08-02367, Revised 01/09/2009 2022-01-13
[Table view] |
Text
Indian Point Energy Center 450 Broadway, GSB
-Entergy P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 788-2055 Fred Dacimo Vice President License Renewal April 23, 2008 Re: Indian Points Unit 2 & 3 Dockets Nos. 50-247 & 50-286 NL-08-061 U.S. Nuclear Regulatory Commission ATTN: Document.Control Desk Washington, DC 20555-0001
SUBJECT:
Reply to Document Request for Additional Information Regarding Site Audit Review of License Renewal Application for Indian Point Nuclear Generating Unit Nos. 2 and 3
Reference:
NRCletter dated November 8, 2007, "Summary of Site Audit Related to the Review of the License Renewal Application for Indian Point Nuclear Generation Unit Nos. 2 & 3"
Dear Sir or Madam:
Entergy Nuclear Operations, Inc is providing, in Enclosure 1, the additional information requested in the reference letter pertaining to NRC audit of review of License Renewal Application for Indian Point 2 and Indian Point 3. The additional information provided in this transmittal addresses staff questions related to potential acute shock effects associated with transmission lines (identified as items #24 and 25 of reference letter).
During the audit, Entergy provided written documentation from Consolidated Edison that the 345 kV transmission lines to the Buchanan Substation, met the New York State Public Service Commission 4.5 mA criteria. However, the calculations to support this were not available.
Therefore, Entergy commissioned a new study to demonstrate that the high voltage transmission lines from Indian Point meet the steady state induced short circuit current requirements of both the New York Public Service Commission (4.5 mA) and the current edition of the National Electric Safety Code (5 mA). A copy of this report is included as Enclosure 1.
As demonstrated in the report, the lines of concern are currently nearly double the height necessary to meet the criteria Therefore, the Transmission Lines are acceptable right now as is. In the future, if there is a major configuration change at the Broadway crossing, IPEC will use the approved maintenance procedure (0-HVE-401-ELC) to ensure that the road clearances are acceptable at that time.
NL-08-61 Docket Nos. 50-247 & 50-286 Page 2 of 2 If you have any additional questions or require additional information, please contact Mr. R.
Walpole, Manager, Licensing at (914) 734-6710.
I declare under penalty of perjury that the foregoing is true and correct. Executed on Sinc Fred R. Dacimo Vice President License Renewal
Enclosure:
- 1. Enercon Study ELEC-IP-08001 for Indian Point License Renewal Project 345 kV Transmission Line-Induced Shock Study cc: Mr. Samuel J. Collins, Regional Administrator, NRC Region I Mr. John Boska, NRR Senior Project Manager Mr. Bo M. Pham, NRC Senior Project Manager Mr. Drew Stuyvenberg, NRC Environmental Project Manager Mr. Sherwin E. Turk, NRC Office of General Counsel, Special Counsel Mr. Paul Eddy, New York State Department of Public Service IPEC NRC Resident Inspector's Office Mr. Paul D. Tonko, President, New York State Energy, Research, & Development Authority
ENCLOSURE 1 TO NL-08-061 Enercon Study ELEC-IP-08001 for Indian Point License Renewal Project 345 kV Transmission Line-Induced Shock Study ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 and 3 DOCKETS 50-247 AND 50-286
ATTACHMENT 9.1 VENDOR DOCUMENT REVIEW STATUS APPLIQUE' Sheet I of I MANAGEMENT MANUAL
.,
-- FOR ACCEPTANCE E] FOR INFORMATION E IPEC L] JAF . LW PLP L[ PNPS [ VY EI ANO L] GGNS E] RBS LIW3 t
Document No.: ELEC-IP-08001 I Rev. No.DATED 3/26/2008 Document Title: Enercon Study ELEC-IP-08001 for Indian Point License Renewal Project 345 kV Transmission Line-Induced Shock study EC No:IP2-06-32959 . . Purchase Order No.
STATUS NO:
- 1. E ACCEPTED, WORK MAY PROCEED
- 2. -1 ACCEPTED AS NOTED RESUBMITTAL NOT REQUIRED, WORK MAY PROCEED
- 3. LI ACCEPTED AS NOTED RESUBMITTAL REQUIRED 4.; 3] NOT ACCEPTED Acceptance does not constitute approval of design details, calculations, analyses, test methods, or materials developed or selected by the supplier and does not relieve the supplier from full compliance with contractual negotiations.
Responsible Engineer wx~~~I~ e /CAY- 4
- IfI +.( f Print Name Date
, /gqature Engineering Supervisor KAREN TOM F
LEnteigy I0 ENERCON E*TIERGY IMUCAR Enercon Study ELEC-IP-08001 for Indian Point License Renewal Project 345 kV Transmission Line-Induced Shock Study A
4111/08 Prepared by: Date: /0 f Reviewed by: Date:.~/
Indian Point License Renewal Project 345 kV Transmission Line Induced Shock Study
Executive Summary This report shows the method and results used to demonstrate that the high voltage transmission lines (345 kV) from the Entergy's Indian Point Nuclear Stations meet the steady state induced short circuit current requirements given in the current edition of the National Electrical Safety Code (2007 Edition).
Background
Entergy Nuclear Indian Point 2, LLC and Entergy Nuclear Indian Point 3, LLC (hereafter referred to as "Entergy") have submitted an Environmental Report (ER) in conjunction with the application to the U.S. Nuclear Regulatory Commission (NRC) to renew the operating licenses for Indian Point Units 2 and 3 (IP2 and IP3) for twenty years beyond the end of the current license terms. This requires the preparation of volumes of studies and analyses to show the facilities remain safe and viable. As part of these evaluations, the transmission lines that connect these plants to the electric system are evaluated. While these lines have typically not changed in their usage, the governing safety regulations have changed since original construction.
Specifically, the National Electric Safety Code (NESC)1 establishes the minimum safety requirements for electric lines, and has changed to include a limitation on the magnitude of induced current available from a vehicle parked under these lines2. As a result, the Nuclear Regulatory Commission (NRC) now requires that each plant being re-licensed to evaluate the 2 transmission lines supplying the power plants to ensure conformance with the current NESC.
This requirement is the basis for the Indian Point 345 kV Transmission Line Induced Shock Study, which demonstrates conformance to the NESC requirements. In addition, this study also demonstrates conformance with the more restrictive induced shock hazard limit of 4.5 mA required by New York Public Service Commission.
There are two (2) in-scope 345 kV transmission lines that transmit power from Entergy's Indian Point Nuclear Stations #2 and #3 to the nearest switchyard just across Broadway. The 138kV lines are at similar ground crossing heights to the 345kV line and are therefore enveloped by this study.
National Electrical Safety Code 2007, American National Standard C2 2 NESC Rule 232Clc Indian Point License Renewal Project 345 kV Transmission Line Induced Shock Study Page 2 of 10
Study Overview The process used to determine conformance to the NESC requirements requires the following basic steps:
Data Collection This phase collects information about the transmission line geometry, utilization and right-of-way (R/W) configuration.
Data Review Data that is collected is organized into a useable form and checked for errors and consistency. Some parameters are directly calculated in this step using source data.
R/W Cross-Section The data is reviewed to choose a limited number of R/W cross sections that represent roadway crossings and areas with low phase conductors.
Electric Field Level The various cross sections are modeled in electric field software to calculate the electric field levels that are expected to exist under the transmission lines.
Short Circuit Current Using the electric field strengths calculated, an EPRI example is used to calculate the hypothetical steady-state current between a vehicle under the line and ground. This current is limited to 5 mA in the current NESC.
Data Collection Data detailing the transmission lines and network connecting into the Indian Point plant was obtained from Entergy's Transmission Group. The information received from Entergy generally included the following types of information:
" Transmission phasing diagram
" Structure drawings
- Transmission line data Data Review and Summarization From the documentation provided the height of each individual phase conductor above ground was determined for performance of the shock analysis portion of the study. In cases where the actual line height could not be determined from the prints, a SupaRule Cable Height Meter ultra-sonic measuring device was used to determine actual line height at location. Entergy's structure list information was provided in an Excel spreadsheet in electronic form. This data provided information about each structure in the appropriate transmission lines, along with information on each span (i.e. structure number, pole size / height, wire span, pole setting depth, and reference to a structure framing standard).
The following steps were also performed to validate Entergy information:
- 1. Determined the height above ground for the transmission phase conductors at the crossing of Broadway using the actual wire heights.
- 2. Used these wire heights as the minimum wire height above ground for each conductor.
Indian Point License Renewal Project 345 kV Transmission Line Induced Shock Study Page 3 of 10
Electric Field Strength Calculations The right-of-way geometry depicted in the cross section for Broadway was used as the source to enter the line geometry into the EPRI TLWorkstation calculation software. This software is an industry accepted and tested model used to calculate electric and magnetic field strengths, and audible noise levels that exist along a transmission line corridor. For this analysis, only the electric field strengths are of interest.
The portion of the resulting output (Attached Below) summarizes the geometry that was used for the model of the R/W cross section at Broadway. Each of the Lines included in the calculation is represented in the table. Each three-phase circuit is identified as a circuit, along with each static wire. All conductors are individually identified as a bundle. Voltage (Phase to Phase), current (which is arbitrarily set to 2400 Amps), and voltage and current phase angles are provided. This analysis focuses on the effects of capacitive charge buildup on vehicles, therefore only the voltage parameters are of importance. These parameters are voltage, voltage angle, and the X &
Y coordinates of each wire. The coordinates are generated from the appropriate cross section of the right-of-way at the location or roadway with minimum ground clearance.
Short Circuit Current Calculations Once the highest ground level electric field strengths are determined from the TLWorkstation program for the cross section, a calculation is made to determine the maximum possible short circuit current. This current could occur between a large vehicle parked under a transmission line and the ground. The NESC concern is that this current could pass through a human body. The vehicle will act as a large charging capacitor since it is insulated from ground by tires, and is exposed to an electric field. The amount of charge that can build up on the vehicle is directly proportional to the size of the vehicle and the strength of the electric field. Therefore for this analysis the largest possible vehicle is chosen. For conservatism, the maximum field over the xz plane of the road crossing is used since the electric field strength varies along the length of a large vehicle. The procedure used to perform these calculations is outlined in the Electric Power Research Institute (EPRI) Transmission Line Reference Book, 200kV and Above, Third Edition.
This document is the industry-accepted reference for transmission line design and field effects.
Using the methods, and tables detailed in section 7.8 of the EPRI book and the specified parameters for a 65-foot long tractor-trailer, spreadsheet calculations were made for the crossing at Broadway.
Note: The EPRI parameters for a 55-foot long tractor Trailer were used but the length was increased to 65 feet to meet the maximum New York restrictions.
Indian Point License Renewal Project 345 kV Transmission Line Induced Shock Study Page 4 of 10
Figure 1: Shock Currents from Vehicles - Measured Cable Heights Shock Currents from Vehicles Indian Point - 345kV lines across Broadway Maximum E-Fields on the R/W Based on EPRI Transmission Line Reference Book, 200kV and Above Electric Fields from EPRI Model 1.4 kV/M peak E Field 1.4 kV/M From EPRI Model Vehicle Dimension -
65.00 Ft Long = 19.81 meters 8.00 Ft Long = 2.44 meters 13.50 Ft Long = 4.11 meters From Table 7.8-3 for a solid rectangle H= 4.11 A= 19.81 B= 2.441 Therefore: A/B= 8.125 A*B= 48.30958 H/B= 1.6875 S/AB = (1 +(1.4+(5/(ANB)A.6))*(0. 1*(H/B)A .5+.78*(H/B)+.07*(H/B)A2+.01 *((H/B)/(NB))A3))
S/AB = 5.644775 S= 272.6967 Isc=jwES= 377*8.85*1OA12E*S Isc= 1.27 mA Indian Point License Renewal Project 345 kV Transmission Line Induced Shock Study Page 5 of 10
Conclusions The calculations for maximum steady state induced current was made for the Indian Point 345 kV transmission lines that transport electric power from the Stations to the first switchyard. The calculation process utilized data from the Entergy, EPRI TLWorkstation Computer Code, and EPRI accepted calculation methodology. The resulting calculated values are well below the NESC 5 mA steady state current limits detailed in NESC Rule 232C1c. Therefore, the Indian Point 345 kV transmission lines are in conformance to NESC requirements. A theoretical run was also done using TLWorkstation to demonstrate that a lowered line height of 32 feet would be what is necessary to drive the induced current to 4.5mA New York Public Service Commission limit. This theoretical report is also attached below.
Indian Point License Renewal Project 345 kV Transmission Line Induced Shock Study Page 6 of 10
Table 1: TLWorkstation Output Profile: Truck Profile Points distributed laterally from 100.00 ft to 200.00 ft in 4.00 ft 1 1.4 =MaxkV/M 100 667 0.858 0.112 0.843 0.002 184 776 1.103 0.041 1.101 0.044 184 780 1.056 0.038 1.054 0.049 184 784 1.004 0.036 1.001 0.054 1848 788 0.947 0.034 0.944 0.059 184 792 0.886 0.031 0.883 0.062 184 796 0.822 0.029 0.819 0.064 188 660 1.418 0.05 1.418 0.001 188 664 1.418 0.049 1.417 0.001 188 668 1.4171 0.048 1.416 0.002 188 672 1.416 0.048 1.415 0.002 188 676 1.415 0.047 1.414 0.002 188 680 1.414 0.047 1.413 0.002 188 684 1.412 0.046 1.412 0.002 188 688 1.411 0.046 1.41 0.002 188 692 1.409 0.045 1.408 0.002 188 696 1.406 0.045 1.406 0.003 188 700 1.404 0.044 1.403 0.003
-188 704 1.4 0.044 1.4 0.004 188 708 1.397 0.043 1.396 0.004 188 712 1.393 0.043 1.392 0.005 188 716 1.388 0.043 1.387 0.005 "188 720 1.382 0.042 1.382 0.006 188 724 1.376 0.042 1.375 0.007 782188 1.368 0.041 1.367 0.0081 188 732 1.359 0.041 1.359 0.01 188 736 1.3491 0.041 1.348' 0.011 188 740 1.337 0.04 1.336 0.013
- 188 744 1.3231 0.04 1.323 0.015 188 748 1.307 0.04 1.306 0.017 188 752 1.288 0.039 1.288 0.02 188 756 1.267 0.038 1.266 0.023 188 760 1.242 0.038 1.241 0.027 188 764 1.213 0.037 1.212 0.031 188 768 1.179 0.036 1.178 0.035
- See Figure 2 For Plan View depicting Orientation of X and Z axis, Y axis is Height Indian Point License Renewal Project 345 kV Transmission Line Induced Shock Study Page 7 of 10
Protile 950
- 900 Description 850 800 750
=700 650 600 550 500 N
450 400 350 300 250
.200 Audible Noise 150 Couplingl5hielding 100 Detector, 4 00Ft Calculate Electric Field 50 Bandwidth:
4.000 0t t 0 Magnetic Field I
I Figure 2: TLWorkstation Profile Specifications I Indian Point License Renewal Project 345 kV Transmission Line Induced Shock Study Page 8 of 10
Figure 3: Shock Currents from Vehicles - Theorized Cable Theoretical Shock Currents from Vehicles at Lowered Line Height Indian Point - 345kV lines across Broadway Maximum E-Fields on the R/W Based on EPRI Transmission Line Reference Book, 200kV and Above Electric Fields from EPRI Model at Conductor Height 32' Above Ground 4.9 kV/M peak E Field 4.9 kV/M From EPRI Model Vehicle Dimension 65.00 Ft Long = 19.81 meters 8.00 Ft Long = 2.44 meters 13.50 Ft Long = 4.11 meters From Table 7.8-3 for a solid rectangle H= 4.11 A= 19.81 B= 2.44]
Therefore: A/B= 8.125 A*B= 48.30958 H/B= 1.68751 S/AB = (1+(1.4+(5/(A/B),.6))*(0.*1*(H/B)^5+.78*(H/B)+.07*(H/B)^2+.01*((HIB)/(AIB)) A3))
S/AB = 5.644775 S= 272.6967 Isc=jwES= 377*8.85*1OA.-12E*S lsc= 4.46 mA Indian Point License Renewal Project 345 kV Transmission Line Induced Shock Study Page 9 of 10
Enercon Study ELEC-IP-08001 Attachment A Page 1 of 1 IPEC OVERHEAD TRANSMISSION LINES CABLE DATA (LOOKING EAST)
CABLE HEIGHT CABLE DISTANCE LINE LEFT MIDDLE RIGHT L-M R-M 1 61.04 63.03 59.08 23-24 23-24 2 56.03 58.04 54.08 23 - 24 23 - 24 3 57.03 57.07 54.05 23 - 24 23 - 24 4 58.03 62.01 59.01 19-20 19-20 5 68.06 N/A 67.04 35.00 NOTES:
- 1) SEE ENTERGY DRAWING NO. EO-16214-A
- 2) LINE 1 = NORTHERN MOST TRANSMISSION LINE
- 3) CABLE HEIGHT = FEET ABOVE BROADWAY ROAD SURFACE
- 4) CABLE DISTANCE = BETWEEN ADJACENT CABLES AT BROADWAY Page 10 of 10