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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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23024A0462023-01-17017 January 2023 License Amendment Request for the Independent Spent Fuel Storage Installation-Only Security, Training and Qualification, Safeguards Contingency Plan ML22332A0482022-11-22022 November 2022 New York State Alyse Peterson Comments on Completion of Emergency Planning Nd License Amendment Request Prior to Spent Fuel Transfer from Spent Fuel Pools to Casts (Dockets 50-003, 50-247, 50-286) ML22321A1482022-11-17017 November 2022 License Amendment Request to Approve the Independent Spent Fuel Storage Installation-Only Emergency Plan ML22306A1262022-11-0202 November 2022 License Amendment Request to Revise Indian Point Nuclear Generating Unit Nos. 2 and 3 Renewed Facility Licenses and Permanently Defueled Technical Specifications and IP3 Appendix C Technical Specifications to Reflect Permanent Removal of Sp ML22214A1282022-08-0202 August 2022 License Amendment Request to Revise Indian Point Nuclear Generating Unit No. 2 Permanently Defueled Technical Specifications to Modify Staffing Requirements Following Transfer of Spent Fuel to Dry Storage ML22140A1262022-05-20020 May 2022 License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements ML22035A1212022-02-0404 February 2022 Revision to Holtec Decommissioning International, LLC, License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme to Address the Permanently Defueled Condition ML21356B7042021-12-22022 December 2021 License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme to Address the Permanently Defueled Condition 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 ML20078L1402020-04-15015 April 2020 Issuance of Amendment Nos. 62, 293, and 268 Changes to Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML20017A2902020-01-17017 January 2020 Supplement to 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-19-084, 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-19-053, Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)2019-06-0606 June 2019 Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) NL-19-013, Proposed Technical Specifications Change - Administrative Controls for Permanently Defueled Condition2019-04-15015 April 2019 Proposed Technical Specifications Change - Administrative Controls for Permanently Defueled Condition NL-19-026, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-04-15015 April 2019 Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-19-001, License Amendment Request to Revise the Indian Point Energy Center Site Emergency Plan to Address the Permanently Shut Down and Defueled Condition2019-04-15015 April 2019 License Amendment Request to Revise the Indian Point Energy Center Site Emergency Plan to Address the Permanently Shut Down and Defueled Condition CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 NL-18-034, License Amendment Request- Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2018-06-20020 June 2018 License Amendment Request- Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions NL-17-157, Amendment 19 to License Renewal Application (LRA)2017-12-14014 December 2017 Amendment 19 to License Renewal Application (LRA) NL-17-070, Additional Information for the Review of the Plants License Renewal Application (LRA) Regarding the Containment Leak Rate Program2017-05-31031 May 2017 Additional Information for the Review of the Plants License Renewal Application (LRA) Regarding the Containment Leak Rate Program NL-17-049, Unit Nos., 1, 2, and 3, License Amendment Request - Cyber Security Plan Implementation Schedule2017-04-28028 April 2017 Unit Nos., 1, 2, and 3, License Amendment Request - Cyber Security Plan Implementation Schedule NL-17-035, Proposed License Amendment Regarding Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank2017-04-0707 April 2017 Proposed License Amendment Regarding Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank NL-17-018, Consistency Certification for Entergy Nuclear Indian Point 2 and Entergy Nuclear Indian Point 3 License Renewal Application2017-01-31031 January 2017 Consistency Certification for Entergy Nuclear Indian Point 2 and Entergy Nuclear Indian Point 3 License Renewal Application NL-16-138, Amendment 18 to License Renewal Application2016-12-15015 December 2016 Amendment 18 to License Renewal Application NL-16-118, Indian Point Nuclear Power Plant, Units 2 & 3, Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel2016-12-14014 December 2016 Indian Point Nuclear Power Plant, Units 2 & 3, Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel ML16355A0682016-12-14014 December 2016 Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel NL-16-118, Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel2016-12-14014 December 2016 Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel CNRO-2016-00020, Application for Order to Transfer Master Decommissioning Trust from PASNY to ENO, Consenting to Amendments to Trust Agreement, and Approving Proposed License Amendments to Modify and Delete Decommissioning .2016-08-16016 August 2016 Application for Order to Transfer Master Decommissioning Trust from PASNY to ENO, Consenting to Amendments to Trust Agreement, and Approving Proposed License Amendments to Modify and Delete Decommissioning . NL-15-148, Amendment 17 to License Renewal Application (LRA)2015-12-14014 December 2015 Amendment 17 to License Renewal Application (LRA) NL-15-144, License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement2015-12-10010 December 2015 License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement NL-15-144, Indian Point, Units 2 and 3 - License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement2015-12-10010 December 2015 Indian Point, Units 2 and 3 - License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement NL-15-109, Reply to Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-022015-09-0101 September 2015 Reply to Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-02 NL-15-067, License Amendment Request - Cyber Security Plan Implementation Schedule2015-06-16016 June 2015 License Amendment Request - Cyber Security Plan Implementation Schedule NL-15-021, Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems Indian Point Unit Number 22015-02-12012 February 2015 Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems Indian Point Unit Number 2 NL-14-146, Amendment 16 to License Renewal Application (LRA)2014-12-15015 December 2014 Amendment 16 to License Renewal Application (LRA) NL-14-128, Proposed License Amendment Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years2014-12-0909 December 2014 Proposed License Amendment Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years ML14304A7002014-04-30030 April 2014 Annual Energy Outlook 2014 NL-13-145, Proposed License Amendment to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Indian Point Unit Nuclear Generating Unit Nos. 2 and 32014-04-0101 April 2014 Proposed License Amendment to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Indian Point Unit Nuclear Generating Unit Nos. 2 and 3 NL-14-035, Proposed Changes to Technical Specifications Regarding Reactor Vessel Pressure/Temperature Limit Curves2014-04-0101 April 2014 Proposed Changes to Technical Specifications Regarding Reactor Vessel Pressure/Temperature Limit Curves NL-14-016, License Amendment Request - Cyber Security Plan Implementation Schedule2014-01-30030 January 2014 License Amendment Request - Cyber Security Plan Implementation Schedule NL-13-131, Amendment 14 to License Renewal Application (LRA)2013-09-26026 September 2013 Amendment 14 to License Renewal Application (LRA) NL-13-077, License Renewal Application-Update to Electrical Meb and Structures Monitoring Program Scope, Aging Management Programs2013-05-0606 May 2013 License Renewal Application-Update to Electrical Meb and Structures Monitoring Program Scope, Aging Management Programs NL-13-015, Proposed License Amendment Regarding Connection of Non Seismic Boric Acid Recovery System to the Refueling Water Storage Tank2013-04-15015 April 2013 Proposed License Amendment Regarding Connection of Non Seismic Boric Acid Recovery System to the Refueling Water Storage Tank ML13116A0082013-04-0909 April 2013 Engineering Evaluation of Postulated RWST Inventory Loss During the Reverse Osmosis Clean-up Skid Process in Accordance to 2-TAP-001-ROS Due to Seismic Event NL-13-046, Amendment 13 to License Renewal Application (LRA) Pertaining to One-Time Inspection and Selective Leaching Programs2013-03-18018 March 2013 Amendment 13 to License Renewal Application (LRA) Pertaining to One-Time Inspection and Selective Leaching Programs ML13046A1662013-02-22022 February 2013 Issuance of Amendment Connecting Non-Seismic Purification System Piping to the Refueling Water Storage Tank NL-12-190, Amendment 12 to License Renewal Application (LRA)2012-12-27027 December 2012 Amendment 12 to License Renewal Application (LRA) NL-12-090, Proposed License Amendment Regarding Connection of Non Seismic Purification Line to Refuel Water Storage Tank2012-08-14014 August 2012 Proposed License Amendment Regarding Connection of Non Seismic Purification Line to Refuel Water Storage Tank NL-12-107, Application to Renew Operating Licenses for Indian Point Nuclear Power Reactors Unit 2 and Unit 3, General Correspondence - NL-12-1072012-08-0808 August 2012 Application to Renew Operating Licenses for Indian Point Nuclear Power Reactors Unit 2 and Unit 3, General Correspondence - NL-12-107 2023-01-17
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Enterayv Nuclear Northeast
--- Entergy Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel (914) 254-2055 Fred Dacimo Vice President Operations License Renewal NL-1 5-148 December 14, 2015 U.S. Nuclear Regulatory Commission Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738
SUBJECT:
Amendment 17 to License Renewal Application (LRA)
Indian Point Nuclear Generating Unit Nos. 2 and 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64
REFERENCES:
- 1. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application" (N L-07-039)
- 2. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application Boundary Drawings" (NL-07-040)
- 3. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application Environmental Report References" (N L-07-04 1)
- 4. Entergy Letter dated October 11, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application (LRA)" (NL-07-124)
- 5. Entergy Letter dated November 14, 2007, F. R. Dacimo to Document Control Desk, "Supplement to License Renewal Application (LRA)
Environmental Report References" (NL-07-1 33)
Dear Sir or Madam:
In accordance with 10 CFR 54.21(b), each year following submittal of the license renewal application and at least 3 months before scheduled completion of the NRC review, an amendment to the renewal application must be submitted that identifies any change to the CLB of the facility that materially affects the contents of the license renewal application (LRA), including the FSAR supplement. In the referenced letters, Entergy Nuclear Operations, Inc. applied for renewal of the Indian Point Nuclear Generating Units 2 and 3 operating licenses. This letter provides Amendment 17 of the Indian Point Units 2 and 3 license renewal application.
There are no new commitments being made in this submittal.
Should you have any questions concerning this report, please contact Mr. Robert W. Walpole, Licensing Manager, at (914) 254-6710.
NL-15-148 Dockets 50-247 and 50-286 Page 2 of 2 I declare u d r penalty of perjury that the foregoing is true and correct. Executed on IZI,2o15.
FRD/rl Attachment 1. Annual Update Amendment cc: Mr. Daniel H. Dorman, Regional Administrator, NRC Region I Mr. Michael Wentzel, NRC Project Manager, Division of License Renewal Mr. Douglas Pickett, NRR Senior Project Manager Ms. Bridget Frym ire, New York State Department of Public Service Mr. John B. Rhodes, President and CEO NYSERDA NRC Resident Inspector's Office
ATTACHMENT I TO NL-15-148 ANNUAL AMENDMENT ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 and 3 DOCKET NO. 50-247 and 50-286.
NL-1 5-148 Page 1 of 4 Dockets 50-247 and 60-286 Attachment 1 INDIAN POINT NUCLEAR GENERATING UNIT Nos. 2 AND 3 LICENSE RENEWAL APPLICATION ANNUAL AMENDMENT In accordance with 10 CFR 54.21 (b), each year following submittal of the license renewal application and at least 3 months before scheduled completion of the NRC review, an amendment to the renewal application must be submitted that identifies any change to the CLB of the facility that materially affects the contents of the license renewal application (LIRA), including the FSAR supplement. This attachment is the required annual amendment to the LRA.
Amendment 17 is based on a review of documents potentially affecting the CLB during the periods of September 1, 2014 through August 31, 2015.
The review concluded that certain sections of the LRA are affected by changes to CLB documents and other related LRA reviews. The table below summarizes the changes listing the affected system (if applicable), an explanation of the change (including effect on the LRA), and the affected LRA section.
Change ]LRA LRA Sections Affected Section Affected IP3 - EC 59201 Added component IDs to strainers Scin33211 over floor drains in AFW pump room Tal3.2-8-P Identified brass material strainers over drains Issuance of IP-RPT-05-00071, Rev 2, IP2 10CFR50 Appendix R Safe Shutdown Separation Analysis Scin2334-I required inclusion of additional Scin2334-I components Issuance of 1P3-ANAL-FP-01 503, Rev 3, IP3 Safe Shutdown Analysis required inclusion of additional Section 2.3.3.17 components
NL-1 5-148 Page 2 of 4 Dockets 50-247 and 50-286 Attachment I IPEC LRA changes are shown below.
(Changes are shown as strikethroughs for deletions and underlines for additions) 2.3.3.4 Compressed Air
System Description
The compressed air system includes the instrument air (IA) and station air (SA) subsystems.
Unit 2 Instrument Air The IA Ssystem also supports station response to an Appendix R event. The system provides the capability to isolate air to the speed controller for the charging pump (the 21 pump in the chemical and volume control system) from the central control room (CCR), enabling the pump to run at high speed. Adjustment of the charging pump to maximum speed is necessary to establish the required charging flow rate credited in the IP2 Appendix R basis thermal-hydraulic analysis. In addition, the IA system provides compressed air to operate valves necessary to re-establish functional operation of the containment IA header credited in the IP2 Appendix R safe shutdown analysis.
The IA system has the following intended functions for 10 CFR 54.4(a)(3).
- Provide a baekup source of compressed gas for pneumatically operated components for the Appendix R event (10 CFR 50.48).
- Enable charging pump 21 to be run at high speed without the need for operator actions outside the CCR in response to a fire for the Appendix R event (10 CER 50.48).
SN Dockets 50-247 and 50-286 L-1 5-148 Page 3 of 4 Attachment I 2.3.3.17 City Water
System Description
unit 3 The purpose of the city water (CWM) system is to provide water to various components throughout the plant. The city water supply was originally installed for Unit I but now has functions for all three units. The city water tank and many of the shared site components are included in the Unit 2 description of system code CYW. Only the Unit 3 components are included in the CWM system code. City water is used for a variety of purposes throughout Unit 3, including a supply of water to fire protection systems, to various equipment for makeup or cooling, and to sanitary and potable facilities, such as emergency showers, eye wash stations, hose connections, sinks, water coolers, water heaters, and lavatories. The system also provides a backup but not safety-grade source of water to the AFW and charging pumps and can provide makeup to the spent fuel pit.
The CWM system has no intended functions for 10 CER 54.4(a)(1).
The CWM system has the following intended function for 10 CFR 54.4(ai)(2).
- Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function.
- Provide a redundant source of water to the AFW pumps.
- Provide makeup to the spent fuel pit.
The CWM system has the fOllowing intended functions for 10 CFR 54.4(a)(3).
- Provide water supply to the AFW pumps during an Appendix R event (10 CER 50.48).
- Provide water supply to charging pumps oil and fluid drive coolers during an Appendix R event (10 CFR 50.48).
NL-1 5-148 Page 4 of 4 Dockets 50-247 and 50-286 Attachment I 3.3.2.1.18 Plant Drains Materials Plant drains components are constructed of the following materials.
' gray cast iron
'plastic
- 'copper alloy > 15% zinc Table 3.3.2-18-1P3: Plant Drains Aging Effect Aging NUREG- TalINoe Tympoen Functionde Material Environment Requiring Management 1801 Vol.Tal1Noe TpFucinManagement Programs 2 Item Item Strainer Filtration Copper alloy Air - indoor (ext) None None V.F-3 3.2.1-53 C_
> 15% Zn. (EP-1 0)
Enterayv Nuclear Northeast
--- Entergy Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel (914) 254-2055 Fred Dacimo Vice President Operations License Renewal NL-1 5-148 December 14, 2015 U.S. Nuclear Regulatory Commission Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738
SUBJECT:
Amendment 17 to License Renewal Application (LRA)
Indian Point Nuclear Generating Unit Nos. 2 and 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64
REFERENCES:
- 1. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application" (N L-07-039)
- 2. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application Boundary Drawings" (NL-07-040)
- 3. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application Environmental Report References" (N L-07-04 1)
- 4. Entergy Letter dated October 11, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application (LRA)" (NL-07-124)
- 5. Entergy Letter dated November 14, 2007, F. R. Dacimo to Document Control Desk, "Supplement to License Renewal Application (LRA)
Environmental Report References" (NL-07-1 33)
Dear Sir or Madam:
In accordance with 10 CFR 54.21(b), each year following submittal of the license renewal application and at least 3 months before scheduled completion of the NRC review, an amendment to the renewal application must be submitted that identifies any change to the CLB of the facility that materially affects the contents of the license renewal application (LRA), including the FSAR supplement. In the referenced letters, Entergy Nuclear Operations, Inc. applied for renewal of the Indian Point Nuclear Generating Units 2 and 3 operating licenses. This letter provides Amendment 17 of the Indian Point Units 2 and 3 license renewal application.
There are no new commitments being made in this submittal.
Should you have any questions concerning this report, please contact Mr. Robert W. Walpole, Licensing Manager, at (914) 254-6710.
NL-15-148 Dockets 50-247 and 50-286 Page 2 of 2 I declare u d r penalty of perjury that the foregoing is true and correct. Executed on IZI,2o15.
FRD/rl Attachment 1. Annual Update Amendment cc: Mr. Daniel H. Dorman, Regional Administrator, NRC Region I Mr. Michael Wentzel, NRC Project Manager, Division of License Renewal Mr. Douglas Pickett, NRR Senior Project Manager Ms. Bridget Frym ire, New York State Department of Public Service Mr. John B. Rhodes, President and CEO NYSERDA NRC Resident Inspector's Office
ATTACHMENT I TO NL-15-148 ANNUAL AMENDMENT ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 and 3 DOCKET NO. 50-247 and 50-286.
NL-1 5-148 Page 1 of 4 Dockets 50-247 and 60-286 Attachment 1 INDIAN POINT NUCLEAR GENERATING UNIT Nos. 2 AND 3 LICENSE RENEWAL APPLICATION ANNUAL AMENDMENT In accordance with 10 CFR 54.21 (b), each year following submittal of the license renewal application and at least 3 months before scheduled completion of the NRC review, an amendment to the renewal application must be submitted that identifies any change to the CLB of the facility that materially affects the contents of the license renewal application (LIRA), including the FSAR supplement. This attachment is the required annual amendment to the LRA.
Amendment 17 is based on a review of documents potentially affecting the CLB during the periods of September 1, 2014 through August 31, 2015.
The review concluded that certain sections of the LRA are affected by changes to CLB documents and other related LRA reviews. The table below summarizes the changes listing the affected system (if applicable), an explanation of the change (including effect on the LRA), and the affected LRA section.
Change ]LRA LRA Sections Affected Section Affected IP3 - EC 59201 Added component IDs to strainers Scin33211 over floor drains in AFW pump room Tal3.2-8-P Identified brass material strainers over drains Issuance of IP-RPT-05-00071, Rev 2, IP2 10CFR50 Appendix R Safe Shutdown Separation Analysis Scin2334-I required inclusion of additional Scin2334-I components Issuance of 1P3-ANAL-FP-01 503, Rev 3, IP3 Safe Shutdown Analysis required inclusion of additional Section 2.3.3.17 components
NL-1 5-148 Page 2 of 4 Dockets 50-247 and 50-286 Attachment I IPEC LRA changes are shown below.
(Changes are shown as strikethroughs for deletions and underlines for additions) 2.3.3.4 Compressed Air
System Description
The compressed air system includes the instrument air (IA) and station air (SA) subsystems.
Unit 2 Instrument Air The IA Ssystem also supports station response to an Appendix R event. The system provides the capability to isolate air to the speed controller for the charging pump (the 21 pump in the chemical and volume control system) from the central control room (CCR), enabling the pump to run at high speed. Adjustment of the charging pump to maximum speed is necessary to establish the required charging flow rate credited in the IP2 Appendix R basis thermal-hydraulic analysis. In addition, the IA system provides compressed air to operate valves necessary to re-establish functional operation of the containment IA header credited in the IP2 Appendix R safe shutdown analysis.
The IA system has the following intended functions for 10 CFR 54.4(a)(3).
- Provide a baekup source of compressed gas for pneumatically operated components for the Appendix R event (10 CFR 50.48).
- Enable charging pump 21 to be run at high speed without the need for operator actions outside the CCR in response to a fire for the Appendix R event (10 CER 50.48).
SN Dockets 50-247 and 50-286 L-1 5-148 Page 3 of 4 Attachment I 2.3.3.17 City Water
System Description
unit 3 The purpose of the city water (CWM) system is to provide water to various components throughout the plant. The city water supply was originally installed for Unit I but now has functions for all three units. The city water tank and many of the shared site components are included in the Unit 2 description of system code CYW. Only the Unit 3 components are included in the CWM system code. City water is used for a variety of purposes throughout Unit 3, including a supply of water to fire protection systems, to various equipment for makeup or cooling, and to sanitary and potable facilities, such as emergency showers, eye wash stations, hose connections, sinks, water coolers, water heaters, and lavatories. The system also provides a backup but not safety-grade source of water to the AFW and charging pumps and can provide makeup to the spent fuel pit.
The CWM system has no intended functions for 10 CER 54.4(a)(1).
The CWM system has the following intended function for 10 CFR 54.4(ai)(2).
- Maintain integrity of nonsafety-related components such that no physical interaction with safety-related components could prevent satisfactory accomplishment of a safety function.
- Provide a redundant source of water to the AFW pumps.
- Provide makeup to the spent fuel pit.
The CWM system has the fOllowing intended functions for 10 CFR 54.4(a)(3).
- Provide water supply to the AFW pumps during an Appendix R event (10 CER 50.48).
- Provide water supply to charging pumps oil and fluid drive coolers during an Appendix R event (10 CFR 50.48).
NL-1 5-148 Page 4 of 4 Dockets 50-247 and 50-286 Attachment I 3.3.2.1.18 Plant Drains Materials Plant drains components are constructed of the following materials.
' gray cast iron
'plastic
- 'copper alloy > 15% zinc Table 3.3.2-18-1P3: Plant Drains Aging Effect Aging NUREG- TalINoe Tympoen Functionde Material Environment Requiring Management 1801 Vol.Tal1Noe TpFucinManagement Programs 2 Item Item Strainer Filtration Copper alloy Air - indoor (ext) None None V.F-3 3.2.1-53 C_
> 15% Zn. (EP-1 0)