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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
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Text
SEnterg Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 788-2055 Fred Dacimo Vice President License Renewal NL-1 1-134 December 20, 2011 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-Pl-17 Washington, D.C. 20555-0001
Subject:
Amendment 11 to License Renewal Application (LRA)
Indian Point Nuclear Generating Unit Nos. 2 & 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" (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 11 of the License Renewal Application (LRA).
If you have any questions, or require additional information, please contact Mr. Robert Walpole at 914-254-6710.
4(28
NL-1 1-134 Docket Nos. 50-247 and 50-286 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on
-4Z 1 . 0Zo,0 Sincerely, PAZ jZ' FRD/aas
Attachment:
- 1. Annual Update Amendment cc: Mr. William Dean, Regional Administrator, NRC Region 1 Mr. Sherwin E. Turk, NRC Office of General Counsel, Special Counsel Mr. Kenneth Chang, NRC Branch Chief, Engineering Review Branch I Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. Paul Eddy, New York State Dept. of Public Service Mr. Francis J. Murray, Jr., President & CEO, NYSERDA NRC Resident Inspector's Office
ATTACHMENT 1 TO NL-11-134 Annual Update Amendment ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION 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 attachment is that required amendment for the Indian Point Energy Center (IPEC).
The review included documents affecting the CLB during the period of May 1, 2010 through August 31, 2011. The last annual update of the LRA included a review of documents thru April 30, 2010.
This review concluded that certain sections of the LRA are affected by changes to the CLB over the period of review. 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.
IPEC LRA Sections Affected LRA Section CLB Change Affected Engineering change EC-4061 and drawing B/9321-2723, Rev. 75 replaced nitrogen regulators PCV-942 and PCV-7726 with smaller Table 2.3.3-5-1P2 flow capacity regulators Table 3.3.2-5-IP2 Change deleted component type
'flow element' from IP2 Nitrogen system Engineering Change EC-35974 Fl-612, 615, 618, 621 RCP Lower Bearing flow indicator added flow element Table 2.3.3-3-IP3 Change added new component Table 3.3.2-3-1P3 type 'flow element' to IP3 Component Cooling Water system
IPEC LRA changes are shown below.
(Changes are shown as strikethroughs for del-tienRs and underlines for additions)
Table 2.3.3-5-1P2 Nitrogen System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flex hose Pressure boundary Piping Pressure boundary Regulator Pressure boundary Strainer Pressure boundary
Table 3.3.2-5-1P2 Nitrogen System Summary of Aging Management Review
Table 2.3.3-3-1P3 Component Cooling Water System Components Subject to Aging Management Review Component Type Intended Function Bolting Pressure boundary Flex hose Pressure boundary Heat exchanger (bonnet) Pressure boundary Heat exchanger (shell) Pressure boundary Heat Transfer Heat exchanger (tubes) Pressure boundary Flow element Pressure boundary Orifice Pressure boundary Piping Pressure boundary Pump casing Pressure boundary
Table 3.3.2-3-1P3 Component Cooling Water Summary of Aging Management Review Component Intended Aging Effect Aging NUREG-1801 Type Functieneon Material Environment Requiring Management Vol. 2 Table 1 Notes Type Function Management Programs Item Item Pressure Carbon Air - indoor (ext) Loss of material Bolting integrity VII.1-4 3.3.1-43 A Bolting boundary steel (AP-27)
Pressure Carbon Boric acid corrosion VII.1-2 3.3.1-89 A Bolting boundary steel Air - indoor (ext) Loss of material prevention (A-102)
Pressure Stainless Air - indoor (ex) None None VII.J-15 3.3.1-94 C Bolting boundary steel (AP-17)
Flex hose Pressure Stainless VIIJ-15 3.3.1-94 A boundary steel Air - indoor (ext) None None (AP-17)
Water chemistry VII.C2-10 3.3.1-50 B Flex hose boundary steel (int) Loss of material control cooling- closed water (A-52)
Pressure Stainless Air- indoor (ext) None None VII.J-15 3.3.1-94 A Flow element boundary steel (AP-17)
Water chemistry VII.C2-10 3.3.1-50 B Flow element Peure staes Trete Loss of material control - closed (A-521 boundary steel cooling water
