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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:Status Report
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status 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) L-22-022, And Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.2022-03-25025 March 2022 And Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec. L-21-134, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations2021-12-17017 December 2021 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations ML21084A7892021-03-25025 March 2021 Entergy Nuclear Operations, Inc. Status of Funding for Managing Irradiated Fuel for Year Ending December 31, 2020 - 10 CFR 50.82(a)(8)(vii) CNRO-2019-00006, Stations - Status of Funding for Managing Irradiated Fuel for Year Ending December 31, 2018 - 10 CFR 50.82(a)(8)(vii) - Entergy Nuclear Operations, Inc2019-03-28028 March 2019 Stations - Status of Funding for Managing Irradiated Fuel for Year Ending December 31, 2018 - 10 CFR 50.82(a)(8)(vii) - Entergy Nuclear Operations, Inc CNRO-2019-00005, Stations - Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) - Entergy Nuclear Operations, Inc2019-03-28028 March 2019 Stations - Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) - Entergy Nuclear Operations, Inc ML18088B2462018-03-29029 March 2018 Status of Funding for Managing Irradiated Fuel for Year Ending December 31, 2017, Per 10 CFR 50.82(a)(8)(vii) CNRO-2017-00009, Entergy Nuclear Operations, Inc. - Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v)2017-03-31031 March 2017 Entergy Nuclear Operations, Inc. - Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) ENOC-17-00006, Status of Funding for Managing Irradiated Fuel for Year Ending December 31, 2016 - 10 CFR 50.82(a)(8)(vii)2017-03-30030 March 2017 Status of Funding for Managing Irradiated Fuel for Year Ending December 31, 2016 - 10 CFR 50.82(a)(8)(vii) NL-16-024, Center'S Sixth 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 Events2016-02-29029 February 2016 Center'S Sixth 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-15-111, Implementation of Order EA-12-051 Modifying Licenses with Regard to Requirements for to Reliable Spent Fuel Pool Instrumentation2015-08-28028 August 2015 Implementation of Order EA-12-051 Modifying Licenses with Regard to Requirements for to Reliable Spent Fuel Pool Instrumentation NL-15-112, Fifth 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 Events2015-08-28028 August 2015 Fifth 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-15-026, Fourth Six-Month Status Report for the Implementation of Order EA-12-051 Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation2015-02-27027 February 2015 Fourth Six-Month Status Report for the Implementation of Order EA-12-051 Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation NL-14-059, Status of Planned Resolutions of the Unapproved III.G.2 Operator Manual Actions2014-04-29029 April 2014 Status of Planned Resolutions of the Unapproved III.G.2 Operator Manual Actions ENOC-14-00009, Decommissioning Funding Status Report Per 10 CFR Section 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) - Entergy Nuclear Operations, Inc2014-03-28028 March 2014 Decommissioning Funding Status Report Per 10 CFR Section 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) - Entergy Nuclear Operations, Inc NL-14-031, Center'S Second 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 Events2014-02-27027 February 2014 Center'S Second 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-14-029, Second Six-Month Status Report for the Implementation of Order EA-12-051, Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation2014-02-27027 February 2014 Second Six-Month Status Report for the Implementation of Order EA-12-051, Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation NL-13-109, First Six-Month Status Report for the Implementation of Order EA-12-051 Modifying Licenses with Regard to Requirements for to Reliable Spent Fuel Pool Instrumentation2013-08-27027 August 2013 First Six-Month Status Report for the Implementation of Order EA-12-051 Modifying Licenses with Regard to Requirements for to Reliable Spent Fuel Pool Instrumentation NL-13-110, First 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 Events2013-08-27027 August 2013 First 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-13-072, Status of Planned Resolutions of the Unapproved III.G.2 Operator Manual Actions2013-05-0202 May 2013 Status of Planned Resolutions of the Unapproved III.G.2 Operator Manual Actions ENOC-13-00007, Decommissioning Funding Status Report Per 10 CFR Section 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) - Entergy Nuclear Operations, Inc2013-03-29029 March 2013 Decommissioning Funding Status Report Per 10 CFR Section 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) - Entergy Nuclear Operations, Inc ENOC-13-00011, Status of Funding for Managing Irradiated Fuel for Year Ending December 31, 2012 - 10 CFR 50.82(a)(8)(vii)2013-03-29029 March 2013 Status of Funding for Managing Irradiated Fuel for Year Ending December 31, 2012 - 10 CFR 50.82(a)(8)(vii) ML12137A1362012-05-29029 May 2012 Decommissioning Funding Status Report ML12137A1052012-05-29029 May 2012 Decommissioning Funding Status Report ML12137A0902012-05-29029 May 2012 Decommissioning Funding Status Report ML12122A0712012-05-14014 May 2012 Enclosure 1: April 2012 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 ENOC-11-00005, Status of Decommissioning Funding for Plants Operated by Entergy Nuclear Operations, Inc., for Year Ending December 31, 2010 - 10 CFR 50.75(f)(1)2011-03-31031 March 2011 Status of Decommissioning Funding for Plants Operated by Entergy Nuclear Operations, Inc., for Year Ending December 31, 2010 - 10 CFR 50.75(f)(1) ML1029403622010-11-12012 November 2010 October 2010 10 CFR 2.206 Monthly Status Report: Enclosures ENOC-10-00010, Entergy Nuclear Operations, Inc. - Status of Decommissioning Funding for Year Ending December 31, 20092010-03-31031 March 2010 Entergy Nuclear Operations, Inc. - Status of Decommissioning Funding for Year Ending December 31, 2009 ML1100404362009-09-16016 September 2009 Plant Issue Tracking Application; Plant Status Daily - Oconee Information for 09/16/2009 ML0830800812008-11-20020 November 2008 October 2008 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations (10 CFR) Section 2.206- Enclosures ML0905708302008-11-0505 November 2008 Entergy Center Status Report NL-08-131, Siren Project Status Update2008-08-12012 August 2008 Siren Project Status Update NL-08-121, Siren Project Milestone Schedule - Status Update, Letter Dated 07/25/082008-07-25025 July 2008 Siren Project Milestone Schedule - Status Update, Letter Dated 07/25/08 ENOC-08-00028, J.A. FitzPatrick, Palisades, and Big Rock Point, Decommissioning Fund Status Report2008-05-0808 May 2008 J.A. FitzPatrick, Palisades, and Big Rock Point, Decommissioning Fund Status Report ML0729506172007-09-13013 September 2007 E-mail from K. Mcmullin, Entergy to J. Boska, NRR Et Al on IPEC Status Report, September 13, 2007 ML0729705242007-08-0707 August 2007 E-mail from K. Mcmullin of Entergy to Various, Regarding IPEC Status Report for Aug 7 2007 ML0729705222007-08-0606 August 2007 E-mail from K. Mcmullin of Entergy to Various, Regarding IPEC Status Report for Aug 6 2007 ML0729705042007-07-31031 July 2007 E-mail from K. Mcmullin of Entergy to Various, Regarding IPEC Status Report for July 31 2007 ML0729704422007-07-27027 July 2007 E-mail from K. Mcmullin of Entergy to Various, Regarding IPEC Status Report for July 27, 2007 ML0729704332007-07-26026 July 2007 E-mail from K. Mcmullin of Entergy to Various, Regarding IPEC Status Report for July 26 ML0729703852007-07-18018 July 2007 E-mail from K. Mcmullin of Entergy to Various, Regarding IPEC Status Report for July 18 2007 ML0729506092007-06-11011 June 2007 E-mail from K. Mcmullin of Entergy to Various, Regarding IPEC Status Report for June 11, 2007 ML0729506082007-06-0707 June 2007 E-mail from K. Mcmullin of Entergy to Various, Regarding IPEC Status Report for June 7, 2007 ML0729506032007-06-0505 June 2007 E-mail from K. Mcmullin of Entergy to Various, Regarding Indian Point Energy Center Status Report, June 5, 2007 ML0729506002007-06-0101 June 2007 E-mail from K. Mcmullin of Entergy to Various, Regarding IPEC Status Report for June 1, 2007 ML0729505982007-05-31031 May 2007 E-mail from K. Mcmullin of Entergy to Various, Regarding IPEC Status Report for May 31, 2007 ML0729505922007-05-30030 May 2007 E-mail from K. Mcmullin of Entergy to Various, Regarding IPEC Status Report for May 30, 2007 ML0729505912007-05-29029 May 2007 E-mail from K. Mcmullin of Entergy to Various, Regarding IPEC Status Report for May 29, 2007 2024-09-18
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Enterqy Nuclear Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 254 6700 John A. Ventosa Site Vice President NL-14-059 April 29, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Subject:
Status of Planned Resolutions of the Unapproved III.G.2 Operator Manual Actions Indian Point Nuclear Generating Unit Nos. 2 & 3 Docket Nos. 50-247, 50-286 License Nos. DPR-26, DPR-64
References:
- 1. Entergy letter NL-1 3-072 dated May 2, 2013, "Status of Planned Resolutions of the Unapproved III.G.2 Operator Manual Actions"
- 2. Entergy letter NL-12-179 dated December 7, 2012, "Revision to the Reply to Notices of Violation Regarding Unapproved III.G.2 Operator Manual Actions"
- 3. Entergy letter NL-12-122 dated September 17, 2012, "Reply to Notices of Violation Regarding Unapproved III.G.2 Operator Manual Actions"
- 4. NRC letter dated August 16, 2012, "Indian Point Nuclear Generating Units 2 and 3 - NRC Inspection Report 05000247/2012009 and 05000286/2012008 and Notices of Violation"
- 5. NRC letter dated February 1, 2012, "Indian Point Nuclear Generating Unit No. 2 - Exemption from the Requirements of 10 CFR Part 50, Appendix R, Paragraph III.G.2 (TAC No. ME0798)"
- 6. NRC letter dated February 1, 2012, "Indian Point Nuclear Generating Unit No. 3 - Exemption from the Requirements of 10 CFR Part 50, Appendix R, Paragraph III.G.2 (TAC No. ME0799)"
NL-14-059 Docket Nos. 50-247 & 50-286 Page 2 of 3
Dear Sir or Madam:
By letter dated September 17, 2012 (Reference 3), Entergy Nuclear Operations, Inc.
(Entergy) replied to the violations issued in Reference 4 for Indian Point Nuclear Generating Unit No. 2 (IP2) and Unit No. 3 (IP3) for the use of unapproved operator manual actions (OMAs) to mitigate safe shutdown equipment malfunctions caused by a fire-induced single spurious actuation in lieu of protecting the equipment in accordance with 10 CFR Part 50 Appendix R, Paragraph III.G.2. The violations resulted from the denial of a number of OMAs in the Exemptions transmitted by letters dated February 1, 2012 (References 5 and 6). A revised response to the NOV was transmitted by letter dated December 7, 2012 (Reference 2). By letter dated May 2, 2013, a status update of the Planned Resolutions for the unapproved OMAs was provided. herein provides the status update of the Planned Resolutions for the unapproved OMAs for IP2, which was last provided in Attachment 2 in Reference 2, as follows:
The "Scheduled Completion Date" for OMAs 5, 6, 9, 10, 20 and 21 in all applicable Fire Areas/Fire Zones is now "Completed" (previously "Spring 2014 RFO") as the Planned Resolutions were completed during or following the Spring 2014 RFO. Note that the physical work for resolution of OMA 6 in Fire Zones 6, 7A, 22A and 27A of Fire Area F was completed on April 25 following the Spring 2014 RFO. The full resolution of this OMA required the construction of a fire-rated enclosure around valve LCV-1 12C. Branch Chief John Rogge was notified on March 17, 2014 that this enclosure modification would be completed online following the RFO.
As previously reported in Reference 2, the Planned Resolutions for all of the IP3 unapproved OMAs are complete. Attachment 2 provides the status as previously reported in Reference 2.
There are no new commitments contained in this letter. In the event of any questions, please contact Mr. Robert W. Walpole, Manager, Licensing at 914-254-6710.
Sincerely, JAV/gd
NL-14-059 Docket Nos. 50-247 & 50-286 Page 3 of 3 Attachments:
- 1. Status of Resolution of Indian Point Unit 2 Unapproved III.G.2 OMAs (Revision of Attachment 1 from Entergy Letter NL-13-072 dated May 2, 2013)
- 2. Status of Resolution of Indian Point Unit 3 Unapproved III.G.2 OMAs (Attachment 2 from Entergy Letter NL-13-072 dated May 2, 2013) cc: Mr. William Dean, Regional Administrator, NRC Region I Mr. Douglas V. Pickett, Senior Project Manager, NRC NRR DORL Ms. Bridget Frymire, New York State Department of Public Service Mr. John B. Rhodes, President and CEO, NYSERDA NRC Resident Inspectors
Attachment 1 to NL-14-059 Status of Resolution of Indian Point Unit 2 Unapproved III.G.2 OMAs (Revision of Attachment 1 from Entergy Letter NL-13-072 dated May 2, 2013)
ENTERGY NUCLEAR OPERATIONS, INC.
Indian Point Nuclear Generating Unit Nos. 2 & 3 Docket Nos. 50-247 & 50-286 License Nos. DPR-26 & DPR-64
NL-14-059 Docket Nos. 50-247 & 50-286 Attachment 1 Page 1 of 4 STATUS OF RESOLUTION OF INDIAN POINT UNIT 2 UNAPPROVED III.G.2 OMAS Fire Area OMA Scheduled IZone No.M Planned Resolution Completion Date F/5A 6 Revise Appendix R safe-shutdown analysis and methodology to Completed credit equipment train independent of the fire area/zone and implement modification to establish separate fire area OR implement modification to protect circuits of concern, thereby eliminating this OMA F/6 6 As described for OMA 6, Fire Area F, Fire Zone 5A Completed 7 Revise Appendix R safe-shutdown analysis and methodology to Completed credit equipment train independent of the fire area/zone, thereby eliminating this OMA F/7A 6 Implement modification to protect circuits of concern, thereby Completed eliminating this OMA 7 As described for OMA 7, Fire Area F, Fire Zone 6 Completed 20 Implement modification to protect circuits of concern, thereby Completed eliminating this OMA (see Note on page 4) 21 Implement modification to protect circuits of concern, thereby Completed eliminating this OMA (see Note on page 4)
F/22A 6 As described for OMA 6, Fire Area F, Fire Zone 5A Completed F/27A 5 Revise Appendix R safe-shutdown analysis and methodology to Completed credit equipment train independent of the fire area/zone, thereby eliminating this OMA 6 As described for OMA 6, Fire Area F, Fire Zone 7A Completed F/33A 5 As described for OMA 5, Fire Area F, Fire Zone 27A Completed F/59A 5 As described for OMA 5, Fire Area F, Fire Zone 27A Completed H/72A 8 Revise Appendix R safe-shutdown analysis and methodology to Completed credit equipment train independent of the fire area/zone, thereby eliminating this OMA As identified in table on pages 5 and 6 in Exemption transmitted by NRC letter dated February 1, 2012, "Indian Point Nuclear Generating Unit No. 2 - Exemption from the Requirements of 10 CFR Part 50, Appendix R, Paragraph III.G.2 (TAC No. ME0798)", with the exception of OMAs 19, 20 and 21 - see Note on page 4
NL-14-059 Docket Nos. 50-247 & 50-286 Attachment 1 Page 2 of 4 STATUS OF RESOLUTION OF INDIAN POINT UNIT 2 UNAPPROVED III.G.2 MAS FireZone Area OMA No.A Planned Resolution Scheduled Completion Date H/75A 8 Revise Appendix R safe-shutdown analysis and methodology to Completed credit a train of equipment free of fire damage in the fire area/zone, thereby eliminating this OMA 9,10 Implement modification to protect circuits of concern, thereby Completed eliminating these OMAs H/77A 8 As described for OMA 8, Fire Area H, Fire Zone 72A Completed 9,10 As described for OMAs 9,10, Fire Area H, Fire Zone 75A Completed H/84A 8 As described for OMA 8, Fire Area H, Fire Zone 72A Completed H/85A 8 As described for OMA 8, Fire Area H, Fire Zone 72A Completed H/87A 8 As described for OMA 8, Fire Area H, Fire Zone 72A Completed 9,10 As described for OMAs 9,10, Fire Area H, Fire Zone 75A Completed J/19 11 Reassess electrical circuit and power supply loading analyses and Completed revise Appendix R safe-shutdown analysis and methodology to provide the basis for elimination of this OMA J/25 12 Revise Appendix R safe-shutdown analysis and methodology to Completed credit equipment train independent of the fire area/zone, thereby eliminating this OMA J/39A 11 As described for OMA 11, Fire Area J, Fire Zone 19 Completed 12 As described for OMA 12, Fire Area J, Fire Zone 25 Completed J/43A 11 As described for OMA 11, Fire Area J, Fire Zone 19 Completed 12 As described for OMA 12, Fire Area J, Fire Zone 25 Completed 13 Revise Appendix R safe-shutdown analysis and methodology to Completed credit equipment train independent of the fire area/zone, thereby eliminating this OMA J/45A 11 As described for OMA 11, Fire Area J, Fire Zone 19 Completed J/46A 11 As described for OMA 11, Fire Area J, Fire Zone 19 Completed 12 As described for OMA 12, Fire Area J, Fire Zone 25 Completed 13 As described for OMA 13, Fire Area J, Fire Zone 43A Completed J/47A 11 As described for OMA 11, Fire Area J, Fire Zone 19 Completed J/50A 11 As described for OMA 11, Fire Area J, Fire Zone 19 Completed 12 As described for OMA 12, Fire Area J, Fire Zone 25 Completed
NL-14-059 Docket Nos. 50-247 & 50-286 Attachment 1 Page 3 of 4 STATUS OF RESOLUTION OF INDIAN POINT UNIT 2 UNAPPROVED III.G.2 MAS Fire Area OMA Scheduled Zone No.A Planned Resolution Completion Date J/270 12 As described for OMA 12, Fire Area J, Fire Zone 25 Completed K/60A 14 Implement modification to protect circuits of concern, thereby Completed eliminating this OMA 15 Implement modification to protect circuits of concern, thereby Completed eliminating this OMA 19 Implement modification to protect circuits of concern, thereby Completed eliminating this OMA (see Note on page 4)
K/65A 14 As described for OMA 14, Fire Area K, Fire Zone 60A Completed 15 As described for OMA 15, Fire Area K, Fire Zone 60A Completed 19 As described for OMA 19, Fire Area K, Fire Zone 60A Completed
NL-14-059 Docket Nos. 50-247 & 50-286 Attachment 1 Page 4 of 4 Description of Unit 2 Unapproved OMAs
- 5. Open HCV-142 bypass valve 227 to align charging pump makeup path to the Reactor Coolant System (RCS)
- 6. Align charging pump suction source to the Refueling Water Storage Tank (RWST)
- 7. Transfer instrument buses 23 and 23A to alternate power
- 8. Fail open valves 204A (charging flow to Loop 2 hot leg) and 204B (charging flow to Loop 1 cold leg) to align charging pump makeup path to the RCS
- 9. Activate or enable Alternate Safe Shutdown System pneumatic instruments (steam generator level, pressurizer pressure and level) at Fan House local control panel
- 10. Enable Alternate Safe-Shutdown System source-range channel and Loop 21 and 22 hot leg (Th) and cold leg (Tc) temperature channels
- 11. Trip breakers 52/5A and 52-SAC on Bus 5A and 52/6A and 52/TAO at Bus 6A and remove control power fuses
- 12. Transfer Instrument Buses 23 and 23A to emergency power source
- 13. Align charging pump suction to RWST
- 14. Operate transfer switch EDC5 and close supply breaker at substation 12FD3 to transfer 21 AFW Pump to Alternate Safe Shutdown System power source
- 15. Open 21 AFW Pump recirculation bypass valve BFD-77
- 19. Operate 21 AFW Pump flow control valves to control AFW flow to Steam Generators 21 &
22
- 20. Locally operate 21 Charging Pump scoop tube positioner
- 21. Locally start 21 Charging Pump using the emergency control station located in the 480V Switchgear Room NOTE: With the exception of OMAs 19, 20 and 21, the descriptions are copied from the table on pages 5 and 6 in Exemption transmitted by NRC letter dated February 1, 2012, "Indian Point Nuclear Generating Unit No. 2 - Exemption from the Requirements of 10 CFR Part 50, Appendix R, Paragraph III.G.2 (TAC No.
ME0798)". OMA 19 was not addressed in the Exemption transmitted by that letter.
OMAs 20 and 21 were inadvertently omitted from the exemption request process, and are therefore unapproved OMAs. The three OMAs have been given the next sequential numbers.
Attachment 2 to NL-14-059 Status of Resolution of Indian Point Unit 3 Unapproved III.G.2 OMAs (Attachment 2 from Entergy Letter NL-13-02 dated May 2, 2013)
ENTERGY NUCLEAR OPERATIONS, INC.
Indian Point Nuclear Generating Unit Nos. 2 & 3 Docket Nos. 50-247 & 50-286 License Nos. DPR-26 & DPR-64
NL-14-059 Docket Nos. 50-247 & 50-286 Attachment 2 Page 1 of 5 STATUS OF RESOLUTION OF INDIAN POINT UNIT 3 UNAPPROVED III.G.2 OMAS Fire Area / OMA Scheduled Zone NoMA Planned Resolution Completion Date ETN-4{1} / 2 Revise Appendix R safe-shutdown analysis and methodology to Completed 7A credit existing separation within the fire area/zone, thereby eliminating this OMA 3 Revise Appendix R safe-shutdown analysis and methodology to Completed credit existing separation within the fire area/zone, thereby eliminating this OMA 4 Revise Appendix R safe-shutdown analysis and methodology to Completed credit existing separation within the fire area/zone, thereby eliminating this OMA 6 Revise Appendix R safe-shutdown analysis and methodology to Completed credit existing separation within the fire area/zone, thereby eliminating this OMA 7 Revise Appendix R safe-shutdown analysis and methodology to Completed credit existing separation within the fire area/zone, thereby eliminating this OMA 8 Revise Appendix R safe-shutdown analysis and methodology to Completed credit existing separation within the fire area/zone, thereby eliminating this OMA ETN-4{1} / Revise Appendix R safe-shutdown analysis and methodology to Completed 60A credit existing separation within the fire area/zone, thereby eliminating this OMA 6 As described for OMA 6, Fire Area ETN-4{1}, Fire Zone 7A Completed 7 As described for OMA 7, Fire Area ETN-4{1}, Fire Zone 7A Completed 8 As described for OMA 8, Fire Area ETN-4{1}, Fire Zone 7A Completed 9 Revise Appendix R safe-shutdown analysis and methodology to Completed credit existing separation within and/or independent of the fire area/zone, thereby eliminating this OMA 10 Implement modification to protect circuits of concern for valves Completed LCV-112B and LCV-112C, thereby eliminating this OMA 11 Revise Appendix R safe-shutdown analysis and methodology to Completed credit existing separation within the fire area/zone, thereby eliminating this OMA I 2 As identified in table on pages 5 and 6 in Exemption transmitted by NRC letter dated February 1, 2012, "Indian Point Nuclear Generating Unit No. 3 - Exemption from the Requirements of 10 CFR Part 50, Appendix R, Paragraph III.G.2 (TAC No. ME0799)"
NL-14-059 Docket Nos. 50-247 & 50-286 Attachment 2 Page 2 of 5 STATUS OF RESOLUTION OF INDIAN POINT UNIT 3 UNAPPROVED III.G.2 OMAS Fire Area I OMA Scheduled Zone No.2 Planned Resolution Completion Date ETN-4{1} / 12 Revise Appendix R safe-shutdown analysis and methodology to Completed 60A credit existing separation within and/or independent of the fire (continued) area/zone, thereby eliminating this OMA 13 Implement power/control circuit modification to ensure post-fire Completed functionality of the Service Water strainers for III.G.2 fire scenarios, thereby eliminating this OMA ETN-4{3} / 14 Revise Appendix R safe-shutdown analysis and methodology to Completed 73A credit existing separation within and/or independent of the fire area/zone, thereby eliminating this OMA 15 Revise Appendix R safe-shutdown analysis and methodology to Completed credit existing separation within and/or independent of the fire area/zone, thereby eliminating this OMA 16 Revise Appendix R safe-shutdown analysis and methodology to Completed credit existing separation within and/or independent of the fire area/zone, thereby eliminating this OMA 17 Revise Appendix R safe-shutdown analysis and methodology to Completed credit existing separation within and/or independent of the fire area/zone, thereby eliminating this OMA PAB-2{3} / 6 18 Revise Appendix R safe-shutdown analysis and methodology to Completed credit equipment train independent of the fire area/zone, thereby eliminating this OMA PAB-2{5} / 19 Revise Appendix R safe-shutdown analysis and methodology to Completed 17A credit equipment train independent of the fire area/zone, thereby eliminating this OMA 20 Revise Appendix R safe-shutdown analysis and methodology to Completed credit equipment train independent of the fire area/zone, thereby eliminating this OMA 22 Revise Appendix R safe-shutdown analysis and methodology to Completed credit equipment train independent of the fire area/zone, thereby eliminating this OMA PAB-2{5} / 19 As described for OMA 19, Fire Area PAB-2{5}, Fire Zone 17A Completed 19A 20 As described for OMA 20, Fire Area PAB-2{51, Fire Zone 17A Completed PAB-2{5} / 22 As described for OMA 22, Fire Area PAB-2{5}, Fire Zone 17A Completed 20A PAB-2{5} / 22 As described for OMA 22, Fire Area PAB-2{5}, Fire Zone 17A Completed 27A
NL-14-059 Docket Nos. 50-247 & 50-286 Attachment 2 Page 3 of 5 STATUS OF RESOLUTION OF INDIAN POINT UNIT 3 UNAPPROVED III.G.2 OMAS Area I FireZone OMA Scheduled No.M Planned Resolution Completion Date PAB-2{5} / 22 As described for OMA 22, Fire Area PAB-2{5} / 17A Completed 30A PAB-2{5} I 21 Revise Appendix R safe-shutdown analysis and methodology to Completed 59A credit equipment train independent of the fire area/zone, thereby eliminating this OMA TBL-5 / 37A 25 Implement power/control circuit modification to ensure post-fire Completed functionality of the Service Water strainers for III.G.2 fire scenarios, thereby eliminating this OMA TBL-5 / 38A 25 As described for OMA 25, Fire Area TBL-5, Fire Zone 37A Completed TBL-5 / 43A 25 As described for OMA 25, Fire Area TBL-5, Fire Zone 37A Completed TBL-5 / 44A 25 As described for OMA 25, Fire Area TBL-5, Fire Zone 37A Completed TBL-5 / 52A 23 Implement modification to protect affected circuits in this zone, Completed thereby eliminating this OMA 24 Implement modification to protect affected circuits in this zone, Completed thereby eliminating this OMA TBL-5 / 54A 24 As described for OMA 24, Fire Area TBL-5, Fire Zone 52A Completed YARD-7 / 22 26 Reevaluate Appendix R safe-shutdown analysis, methodology, Completed and fire protection licensing basis to validate whether the OMA may be eliminated 27 Implement power/control circuit modification to ensure post-fire Completed functionality of the Service Water strainers for III.G.2 fire scenarios, thereby eliminating this OMA YARD-7 I 27 As described for OMA 27, Fire Area YARD-7, Fire Zone 22 Completed 222
NL-14-059 Docket Nos. 50-247 & 50-286 Attachment 2 Page 4 of 5 Description of Unit 3 Unapproved OMAs
- 2. Swap 32 Component Cooling Water (CCW) pump to alternate power supply or align city water to charging pumps
- 3. Operate 480V Bus 3A breaker locally to start 31 AFW Pump
- 4. Locally operate the bypass valve for Flow Control Valve (FCV)-1 121 in support of use of 31 AFW pump
- 5. Operate HCV-1 118 manually to control 32 AFW pump
- 6. Align Appendix R Diesel Generator (ARDG) to 480V Buses 2A, 3A, 5A, and 312
- 7. Swap 31 or 32 charging pump to alternate power supply
- 8. Locally operate FCV-405B, FCV-405D, or FCV-406B to control AFW flow to Steam Generators (SGs)
- 9. Locally open valve 227 to establish charging [previously "CVCS"] makeup flowpath to Reactor Coolant System (RCS)
- 10. Locally close Level Control Valve (LCV)-1 12C and open valve 288 to align charging pump suction to the Refueling Water Storage Tank (RWST)
- 11. Locally operate Pressure Control Valve PCV-1 139 to ensure steam supply to 32 AFW Pump
- 12. Locally operate PCV-1310A and PCV-1310B to ensure steam supply to 32 AFW pump
- 13. Locally manually perform Service Water (SW) pump strainer backwash as required
- 14. Operate HCV-1 118 manually to control 32 AFW pump
- 15. Locally operate PCV-1 139 to ensure steam supply to 32 AFW pump
- 16. Locally operate 32 PCV-1310A, PCV-1310B to ensure steam supply to 32 AFW pump
- 17. Locally operate FCV-405C and FCV-405D to control AFW flow to SG
- 18. Locally close valve LCV-112C, and open valve 288 to align charging pump suction path to RWST
NL-14-059 Docket Nos. 50-247 & 50-286 Attachment 2 Page 5 of 5
- 19. Locally close supply breaker for 32 Charging Pump [previously "CVCS"] Pump
- 20. Locally control 32 charging [previously "CVCS"] pump using scoop tube positioner
- 21. Open bypass valve 227 to establish charging flowpath to RCS around potentially failed closed HCV-142
- 22. Locally close valve LCV-1 12C and open bypass valve 288 to establish flowpath from RWST to charging pump suction
- 23. Locally operate [bypass valve for] FCV-1 121 AFW pump recirculation valve during pump startup
- 24. Locally operate FCV-406A and FCV-406B to control AFW flow to SGs
- 25. Locally/manually backwash SW pump strainer as required if power to strainer associated with selected SW pump is lost (use one of STR PMP-31 through STR PMP-36)
- 26. Locally start ARDG to supply Motor Control Center (MCC) 312A in support of the use of SW pump 38
- 27. Locally/manually backwash SW pump strainer as required if power to strainer associated with selected SW pump is lost NOTE: The descriptions are copied from the table on pages 5 and 6 in Exemption transmitted by NRC letter dated February 1, 2012, "Indian Point Nuclear Generating Unit No. 3 - Exemption from the Requirements of 10 CFR Part 50, Appendix R, Paragraph III.G.2 (TAC No. ME0799)