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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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Enteray Nuclear Northeast Indian Point Energy Center
%--Entergy 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel (914) 254-2055 Fred Dacimo Vice President Operations License Renewal NL-13-131 September 26, 2013 U.S. Nuclear Regulatory Commission Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738
SUBJECT:
Amendment 14 to License Renewal Application (LRA)
Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 License No. DPR-26 REFERENCES 1. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application" (NL-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" (NL-07-041)
- 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-07-133)
Dear Sir or Madam:
In the referenced letters, Entergy Nuclear Operations, Inc. applied for renewal of the Indian Point Energy Center operating license. This letter contains Amendment 14 of the License Renewal Application (LRA).
Should you have any questions concerning this report, please contact Mr. Robert W. Walpole, Licensing Manager, at (914) 254-6710.
NL-13-131 Dockets 50-247 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on Sincerely, FRD/rw Attachment 1. Partial Annual Update Amendment for Indian Point Unit No. 2 cc: Mr. William Dean, Regional Administrator, NRC Region I Mr. Sherwin E. Turk, NRC Office of General Counsel, Special Counsel Mr. Dave Wrona, NRC Branch Chief, Engineering Review Branch I Ms. Kimberly Green, NRC Sr. Project Manager, Division of License Renewal Mr. Douglas Pickett, NRR Senior Project Manager Ms. Bridget Frymire, New York State Department of Public Service NRC Resident Inspector's Office Mr. Francis J. Murray, Jr., President and CEO NYSERDA
ATTACHMENT 1 TO NL-13-131 Partial Annual Update Amendment for Indian Point Unit No. 2 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247
NL-13-131 Page 1 of 14 Docket 50-247 Attachment 1 INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 LICENSE RENEWAL APPLICATION PARTIAL ANNUAL UPDATE 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 (LRA), including the FSAR supplement.
This amendment is based on a review of IP2 documents potentially affecting the CLB during the period of September 1, 2012 through June 30, 2013. The purpose of this amendment is to provide an LRA that is consistent with the CLB and IP2 UFSAR as of June 30, 2013. The UFSAR will be submitted to the NRC on or before September 28, 2013 in accordance with NRC letter, "Indian Point Nuclear Generating Unit No. 2 - Actions to be Completed Prior to Entering the Period of Timely Renewal", dated August 19, 2013 (ML13197A034).
The last annual update of the LRA included a review of documents through August 31, 2012. The annual update will be submitted in accordance with 10 CFR 54.21 (b) and will include IP2 document reviews for the period 7/1/13 thru 8/31/13 and Indian Point Unit 3 (IP3) document reviews for the entire period 9/1/12 thru 8/31/13. These two submittals will together provide the IPEC 2013 Annual Update for IP2 and IP3. The annual update will be submitted in December 2013.
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.
LRA Sections Affected LRA Section Changes Affected Add GT2/3 Fuel Oil Storage Tank as Appendix A Section requiring periodic thickness A.2.1.8 measurements to the tank bottom.
Add listing of PSPMs for the Fuel Oil Appendix A Section System related to inclusion of GT3-BSD ApedASci in the scope of LR. A.2.1.28
NL-13-131 Page 2 of 14 Docket 50-247 Attachment 1 LRA Section Changes Affected Add black start diesel (GT3-BSD) related to Fuel Oil System to listing for requirement to maintain cooling water to EPRI guidelines in the WCC-Closed Cooling Water Program. Appendix A Section Add station air (IP1) cooling and fresh A.2.1.39 water cooling and black start diesel (GT3-BSD) cooling to the listing of systems to which WCC-Closed Cooling Water Program is applied.
Add GT2/3 Fuel Oil Storage Tank as Appendix B Section requiring periodic thickness B.1.9 measurements to the tank bottom.
Add listing of PSPMs for the Fuel Oil System related to inclusion of GT3-BSD Appendix B Section in the scope of LR. 6.1.29 Add station air (IP1) cooling and fresh water cooling and black start diesel (GT3-BSD) cooling to the listing of systems to which WCC-Closed Cooling Water Program is applied. Appendix B Section Add black start diesel (GT3-BSD) related 8.1.40 to Fuel Oil System to listing for requirement to maintain cooling water to EPRI guidelines.
Add component types to Table 2.3.3 IP2 for the Fuel Oil System (IPEC 2012 Table 2.3.3-13-1P2 Annual Update showed these changes as applying to IP3)
NL-13-131 Page 3 of 14 Docket 50-247 Attachment 1 Changes j LRA Section Affected Add component type fine items to Table 3.3.2-13-1P2 for the Fuel Oil System Table 3.3.2-13-1P2 (IPEC 2012 Annual Update showed these changes as applying to IP3)
EC 40495 added component line items for 'piping' to Table 3.3.2-2-1P2, Service Table 3.3.2-2-1P2 Water and material and aging effects to Section 3.3.2.1.2 Section 3.3.2.1.2 LRA Appendix A A.2.1.8 Diesel Fuel Monitoring Program The Diesel Fuel Monitoring Program is an existing program that entails sampling to ensure that adequate diesel fuel quality is maintained to prevent loss of material and fouling in fuel systems.
Exposure to fuel oil contaminants such as water and microbiological organisms is minimized by periodically draining and cleaning tanks and by verifying the quality of new oil before its introduction into the storage tanks. Sampling and analysis activities are in accordance with technical specifications on fuel oil purity and the guidelines of ASTM Standards D4057-95 and D975-95 (or later revisions of these standards).
Thickness measurements of storage tank bottom surface verify that significant degradation is not occurring.
The One-Time Inspection Program describes inspections planned to verify the effectiveness of the Diesel Fuel Monitoring Program.
The Diesel Fuel Monitoring Program will be enhanced to include the following.
e Revise applicable procedures to include cleaning and inspection of the GT1 gas turbine fuel oil storage tanks, EDG fuel oil day tanks, and SBO/Appendix R diesel generator fuel oil day tank once every ten years.
- Revise applicable procedures to include quarterly sampling and analysis of the SBO/Appendix R diesel generator fuel oil day tank, security diesel fuel oil storage tank, and security diesel fuel oil day tank. Particulates (filterable solids), water and sediment checks will be performed on the samples. Filterable solids acceptance criterion will be _ 10mg/l.
Water and sediment acceptance criterion will be _ 0.05%.
e Revise applicable procedures to include thickness measurement of the bottom surface of the EDG fuel oil storage tanks, EDG fuel oil day tanks, SBO/Appendix R diesel generator fuel oil day tank, GT1 gas turbine fuel oil storage tanks, GT2/3 fuel oil storage tank, and diesel fire pump fuel oil storage tank once every ten years.
NL-13-131 Page 4 of 14 Docket 50-247 Attachment 1 A.2.1.28 Periodic Surveillance and Preventive Maintenance Program Surveillance testing and periodic inspections using visual or other non-destructive examination techniques verify that the following components are capable of performing their intended function.
" reactor building cranes (polar and manipulator), crane rails, and girders, and refueling platform
" recirculation pump motor cooling coils and housing
" city water system strainer housings and valve bodies
" plant drain components and backwater valves
- station air containment penetration piping
" HVAC duct flexible connections
" HVAC stored portable blowers and flexible trunks
" EDG exhaust components
" EDG duct flexible connections
" EDG air intake and aftercooler components
" EDG air start components
" EDG cooling water makeup supply valves
" security generator exhaust components
" security generator radiator tubes
- SBO/Appendix R diesel exhaust components
- SBO/Appendix R diesel cooling water heat exchangers
- SBO/Appendix R diesel fuel oil cooler
- diesel fuel oil trailer transfer tank and associated valves
- containment cooling duct flexible connections
- containment cooling fan units internals
- control room HVAC condensers and evaporators
- control room HVAC ducts and drip pans
- control room HVAC duct flexible connections
" circulating water, city water, intake structure system, emergency diesel generator, fresh water cooling, instrument air, integrated liquid waste handling, lube oil, miscellaneous, radiation monitoring, river water, station air, waste disposal, wash water, and water treatment plant system piping, piping components, and piping elements
" main steam safety valve tailpipes
- atmospheric dump valve silencers
- off-site power feeder, 138 kV underground transmission cable
- main condenser tube internal surfaces and condensate system expansion joints
- instrument air aftercooler tube internal surfaces and filters
- fresh water/river water heat exchanger internal and external surfaces
- river water system pump casings
- wash water system pump casings
- GT3-BSD jacket water cooling heat exchanger
NL-1 3-131 Page 5 of 14 Docket 50-247 Attachment 1
- emergency fuel oil trailer transfer tank and related components A.2.1.39 Water Chemistry Control - Closed Cooling Water Program The Water Chemistry Control - Closed Cooling Water Program is an existing program that includes preventive measures that manage loss of material, cracking, or fouling for components in closed cooling water systems (component cooling water (CCW), instrument air cooling (IP2 only), fresh water cooling, black start diesel (GT3-BSD) cooling, conventional closed cooling (CCC),
instrument air closed cooling (IACC), emergency diesel generator cooling, security generator cooling, station air (IP1) cooling and SBO/Appendix R diesel generator cooling. These chemistry activities provide for monitoring and controlling closed cooling water chemistry using procedures and processes based on EPRI guidance for closed cooling water chemistry.
The One-Time Inspection Program for Water Chemistry utilizes inspections or non-destructive evaluations of representative samples to verify that the Water Chemistry Control - Closed Cooling Water Program has been effective at managing aging effects.
The Water Chemistry Control - Closed Cooling Water Program will be enhanced to include the following.
- Revise appropriate procedures to maintain water chemistry of the SBO/Appendix R diesel generator cooling system per EPRI guidelines.
" Revise appropriate procedures to maintain the security generator, black start diesel (GT3-BSD) and fire protection diesel cooling water pH and glycol within limits specified by EPRI guidelines.
Enhancements will be implemented prior to the period of extended operation.
NL-13-131 Page 6 of 14 Docket 50-247 Attachment 1 LRA Appendix B B.1.9 DIESEL FUEL MONITORING Attributes Affected Enhancement
- 4. Detection of Aging Effects IP2: Revise applicable procedures to include thickness measurement of the bottom surface of the EDG fuel oil storage tanks, EDG fuel oil day tanks, SBO/Appendix R diesel generator fuel day tank, GT1 gas turbine fuel oil storage tanks, GT2/3 fuel oil storage tank, and diesel fire pump fuel oil storage tank once every ten years.
IP3: Revise applicable procedures to include thickness measurement of the bottom surface of the EDG fuel oil day tanks, EDG fuel oil storage tanks, Appendix R fuel oil storage tank, and diesel fire pump fuel oil storage tank once every ten years.
B.1.29 PERIODIC SURVEILLANCE AND PREVENTIVE MAINTENANCE Fuel oil system IP2: Use visual or other NDE techniques to internally inspect the fuel oil cooler for the SBO/Appendix R diesel generator to manage fouling.
Use visual or other NDE techniques to inspect internal and external surfaces of the emergency fuel oil trailer transfer tank and associated valves for loss of material.
IP2 Black Start Diesel (GT3-BSD):
Use visual or other NDE techniques to inspect external surfaces for iacket water cooling heat exchanger (tubes) to manage fouling.
Use visual or other NDE techniques to internally inspect surfaces for stainless steel flexible bellows, carbon steel piping and silencer, and aluminum turbocharger exposed to exhaust gas to manage loss of material and cracking.
NL-13-131 Page 7 of 14 Docket 50-247 Attachment 1 B.1.40 WATER CHEMISTRY CONTROL - CLOSED COOLING WATER Program Description The Water Chemistry Control - Closed Cooling Water Program is an existing program that includes preventive measures that manage loss of material, cracking, or fouling for components in closed cooling water systems: component cooling water (CCW), instrument air closed cooling (IACC),
fresh water cooling, black start diesel (GT3-BSD) cooling, emergency diesel generator cooling, SBO/Appendix R diesel generator cooling (IP2), Appendix R diesel generator cooling (IP3),
security generator cooling, station air cooling (IP1), conventional closed cooling (CCC) (IP2 only),
and turbine hall closed cooling (THCC) (IP3 only). These chemistry activities provide for monitoring and controlling closed cooling water chemistry using IPEC procedures and processes based on EPRI guidelines for closed cooling water issued as EPRI TR-1007820, Closed Cycle Cooling Water Chemistry, Rev. 1, dated April 2004. This guideline supersedes EPRI TR-107396, Closed Cycle Cooling Water Chemistry Guideline, Revision 0, issued November 1997, referenced in NUREG-1 801. Differences in Revision 0 and Revision 1 are described below.
Enhancements Attributes Affected Enhancement
- 2. Preventive Actions IP2: Revise appropriate procedures to
- 3. Parameters Monitored or maintain water chemistry of the Inspected SBO/Appendix R diesel generator cooling
- 5. Monitoring and Trending system per EPRI guidelines.
- 6. Acceptance Criteria IP2: Revise appropriate procedures to maintain the security generator, black start diesel (GT3-BSD) and fire protection diesel cooling water pH and glycol within limits specified by EPRI guidelines.
NL-13-131 Page 8 of 14 Docket 50-247 Attachment 1 TABLE 2.3.3-13-1P2 FUEL OIL COMPONENTS SUBJECT TO AGING MANAGEMENT REVIEW Component Type Intended Function Filter housing Pressure boundary Flexible bellows Pressure boundary Heat exchanger (bonnet) Pressure boundary Heat exchanger (tubes) Heat transfer Heat exchanger (tubes) Pressure boundary Silencer Pressure boundary Turbocharger Pressure boundary
NL-1 3-131 Page 9 of 14 Docket 50-247 Attachment 1 3.3.2-13-1P2 Fuel Oil Systems Summary of Aging Management Review Table 3.3.2-13-1P2: Fuel Oil Systems Component Intended Aging Effect Aging NUREG- Table 1 Typet Fnctone Material Environment Requiring Management 1801 Vol. te Notes Type Function Management Programs 2 Item Item Filter housin Pressure Carbon Air - indoor Loss of External Surfaces VII.l-8 3.3.1-58 A F boundary steel (ext) material Monitoring (A-77)
F Pressure Carbon Loss of Diesel Fuel VII.HI-10 B F boundary steel material Monitoring (A-30) 316 Filter housin Pressure Carbon Air-indoor (int) Loss of External Surfaces V.B-1 boundary steel material Monitoring (E-25) 3.2.1-32 E Flexible Pressure Stainless Air - indoor (ext) None None 31 AAP-1 bellows boundary steel (AP-17)
Periodic -- -- H Flexible Pressure Stainless Exhaust gas Cracking- surveillance and bellows boundary steel (int) fatigue preventive maintenance Periodic VII.H2-2 3.3.1-18 E Flexible Pressure Stainless Exhaust gas Loss of surveillance and (-7 bellows boundary steel (int) material preventive maintenance
NL-13-131 Page 10 of 14 Docket 50-247 Attachment 1 Table 3.3.2-13-1P2: Fuel Oil Systems Component Intended Aging Effect Aging NUREG- Table 1 Function Material Environment Requiring Management 1801 Vol. Item Notes Type Management Programs 2 Item Heat Carbon Air - indoor Loss of External Surfaces VII.l-8 (A3.8 3.3.1-58 A Heat Pressure (bonnet) boundary steel (ext) material Monitoring Heat Pressure Carbon Treated water Loss of Water chemistry VII.C2-1 3.3.1-48 D exchan-qer Peure Carbo Treated control - closed (A-63)
(bonnet) boundary steel (int) material cooling water Copper Periodic .... G Heat eat Heat Coy surveillance and exchan)er transfer alloy >15% Air- indoor (ext) Foulina preventive (tubes) Zn maintenance Heat Heat Copper Treated water Water chemistry VII.C2-2 3.3.1-52 D exchanger alloy >15% Tted Fouling control - closed (AP-80)
(tubes) Zn cooling water Heat Pressure Copper V.F-3 3.2.1-53 C exchangqer alloy >15% Air - indoor (ext) None None (EP-10)
(tubes) boundary Zn Heat Pressure Copper Treated water Loss of VII.H1-4 exchanger boundar alloy >15% (int) material Selective leachingq (AP43) 3.3.1-84 C (tubes) Zn Heat Pressure Copper Treated water Loss of Water chemistry VII.E1-2 exchangqer bounda alloy >15% control - closed (AP-34) 3.3.1-51 Q (tubes)n int) material coolingq water
NL-13-131 Page 11 of 14 Docket 50-247 Attachment 1 Table 3.3.2-13-1P2: Fuel Oil Systems Component Intended Aging Effect Aging NUREG- Table 1 Material Environment Requiring Management 1801 Vol. Item Notes Type Function Management Programs 2 Item Water chemistry VII.H2-23 3.3.1-47 D Loss of control - closed (A-253 Pressure Carbon Treated water Piping steel (int) material coolin-q water boundary Periodic VII.H2-2 3.3.1-18 E Pressure Carbon Exhaust gas Loss of surveillance and (A-27) boundary steel (int) material preventive maintenance V.A-19 (E-29) 3.2.1-32 E Carbon Air indLoss of External Surfaces PiingPressure Monitoring(
Presboundary sl Air- indoor (int) material None V.F-2 (EP-3) 3.2.1-50 C PiigPressure Air - indoor None boundary Aluminum (ext)
V.F-2 3.2.1-50 C Piping boundary Aluminum Air - indoor (int) None None (EP-3)
External surfaces VII.I-8 3.3.1-58 A Silencer Pressure Carbon Air - indoor (ext) Loss of boundary steel material monitoring (A-77)
Periodic .... H Pressure Carbon Exhaust gas Cracking- surveillance and boundary steel (int) fatigue preventive maintenance
NL-1 3-131 Page 12 of 14 Docket 50-247 Attachment 1 Table 3.3.2-13-1P2: Fuel Oil Systems Component Typoen Intended Incten Material Environment Aging Effect Requiring Aging Management NUREG-1801 Vol Table te 1 Notes Type Function Management Programs 2 Item Item Periodic VII.H2-2 3.3.1-18 E Silencer Pressure Carbon Exhaust gas Loss of surveillance and (A-27) boundary steel (int) material preventive maintenance Loss of External surfaces VII.I-8 3.3.1-58 A Turbocharger Pressure Gray cast Air - indoor (ext) boundary iron material monitoring (A-77)
Tbhr Pressure Gray cast Air - indoor (int) Loss of External surfaces V.A-19 3.2.1-32 E urocaerboundary iron material monitoring (E-29)
Pressure V.F-2 Turbocharger boundary Aluminum Air - indoor (int) None None (EP.-3) 3.2.1-50 C Periodic -- -- G Turbochare Pressure Aluminum Exhaust as Loss of surveillance and boundary (int) material preventive maintenance
NL-13-131 Page 13 of 14 Docket 50-247 Attachment I Table 3.3.2-2-1P2 Service Water System Summary of Aging Management Review Table 3.3.2-2-1P2: Service Water System Component Intended Aging Effect Aging NUREG- TableI No Material Environment Requiring Management 1801 Vol. Item tes Type Function Management Programs 2 Item ELM Pressure Plastic Raw water (int) Chanqe in Service Water F boundary material Integrity properties Piping Pressure Plastic Air - indoor (ext) None None F boundary
NL-13-131 Page 14 of 14 Docket 50-247 Attachment 1 3.3.2.1.2 Service Water Materials Service water system components are constructed of the following materials.
- Plastic Aging Effects Requiring Management The following aging effects associated with the service water system require management.
- chanae in material Droperties