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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARNL-18-063, Submission of IP2 Steam Generator Examination Program Results for the 2018 (2R23) Refueling Outage in Accordance with Technical Specification 5.6.72018-08-13013 August 2018 Submission of IP2 Steam Generator Examination Program Results for the 2018 (2R23) Refueling Outage in Accordance with Technical Specification 5.6.7 NL-18-049, 2018 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2018-07-10010 July 2018 2018 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-18-021, Indian Point, Unit 2 - Submittal of Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Indian Point, Unit 2 - Submittal of Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-021, Submittal of Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Submittal of Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability ML18103A0302018-04-0606 April 2018 Attachment 1 to NL-18-021, LTR-SDA-18-035-NP, Revision 0, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-019, Relief Request Number IP2-ISI-RR-06 - Proposed Alternative to Use Reactor Vessel Head Penetration Flaw Weld Repair Method2018-04-0404 April 2018 Relief Request Number IP2-ISI-RR-06 - Proposed Alternative to Use Reactor Vessel Head Penetration Flaw Weld Repair Method NL-17-059, Request IP2-ISI-RR-22 for Relief from Examination of Non-Regenerative Heat Exchanger Base Support Welded Attachments for Fourth Ten-Year Inservice Inspection Interval Closeout2017-05-30030 May 2017 Request IP2-ISI-RR-22 for Relief from Examination of Non-Regenerative Heat Exchanger Base Support Welded Attachments for Fourth Ten-Year Inservice Inspection Interval Closeout NL-17-057, Request IP2-ISI-RR-20 for Relief from Examinations of Code Class 1 Component Welds with Less than Essentially 100% Examination Coverage for Fourth Ten-Year Inservice Inspection Interval Closeout2017-05-30030 May 2017 Request IP2-ISI-RR-20 for Relief from Examinations of Code Class 1 Component Welds with Less than Essentially 100% Examination Coverage for Fourth Ten-Year Inservice Inspection Interval Closeout NL-16-096, 2016 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2016-09-0909 September 2016 2016 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-16-097, Fifth Ten Year Interval Inservice Inspection Program Plan2016-09-0606 September 2016 Fifth Ten Year Interval Inservice Inspection Program Plan NL-16-091, Submittal of Fifth Ten Year Interval Inservice Inspection Program Plan2016-08-17017 August 2016 Submittal of Fifth Ten Year Interval Inservice Inspection Program Plan NL-16-092, Submittal of Fifth Ten Year Interval Lnservice Testing Program Plan2016-08-17017 August 2016 Submittal of Fifth Ten Year Interval Lnservice Testing Program Plan NL-16-032, Entergy Transmittal of Indian Point 2 ASME Section XI, Iwl Concrete Containment Inspection in Accordance with the Parties Approved Settlement of License Renewal Contention NYS-24 Indian Point Unit 22016-03-16016 March 2016 Entergy Transmittal of Indian Point 2 ASME Section XI, Iwl Concrete Containment Inspection in Accordance with the Parties Approved Settlement of License Renewal Contention NYS-24 Indian Point Unit 2 NL-15-073, Request for Relief Request IP2-ISI-RR-18 Maintaining ISI Related Activities on the 2001 Edition/2003A ASME Section XI Code for Fifth 10-Year Inservice Inspection (ISI) Interval2015-06-0101 June 2015 Request for Relief Request IP2-ISI-RR-18 Maintaining ISI Related Activities on the 2001 Edition/2003A ASME Section XI Code for Fifth 10-Year Inservice Inspection (ISI) Interval NL-14-060, 2014 Summary Reports for In-Service Inspection and Repairs or Replacements2014-05-0909 May 2014 2014 Summary Reports for In-Service Inspection and Repairs or Replacements NL-13-032, Technical Specification 5.6.8 - IP3 Steam Generator Tube Inspection Report - Spring 2013 Refueling Outage2013-08-15015 August 2013 Technical Specification 5.6.8 - IP3 Steam Generator Tube Inspection Report - Spring 2013 Refueling Outage NL-13-031, Submittal of 2013 Summary Reports for Inservice Inspection and Repairs or Replacements2013-06-18018 June 2013 Submittal of 2013 Summary Reports for Inservice Inspection and Repairs or Replacements NL-13-040, Relief Request IP2-ISI-RR-16: Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination2013-02-20020 February 2013 Relief Request IP2-ISI-RR-16: Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination NL-13-002, Proposed Technical Specification Bases Changes to Credit Four Fan Cooler Units in Containment Integrity Analysis2013-01-28028 January 2013 Proposed Technical Specification Bases Changes to Credit Four Fan Cooler Units in Containment Integrity Analysis NL-11-075, Submittal of Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination2011-06-29029 June 2011 Submittal of Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination NL-11-050, Submittal of 2011 Summary Reports for In-Service Inspection and Repairs or Replacements2011-06-20020 June 2011 Submittal of 2011 Summary Reports for In-Service Inspection and Repairs or Replacements ML1024400362010-08-24024 August 2010 Submittal of Steam Generator Examination Program Results 2010 Refueling Outage (2R19) NL-10-058, Summary Reports for In-Service Inspection and Repairs or Replacements2010-06-0909 June 2010 Summary Reports for In-Service Inspection and Repairs or Replacements NL-10-059, Relief Request IP2-ISI-RR-11 for Fourth Ten-Year Inservice Inspection Interval2010-06-0303 June 2010 Relief Request IP2-ISI-RR-11 for Fourth Ten-Year Inservice Inspection Interval NL-09-107, Relief Request 2-10 for Fourth Ten-Year Inservice Inspection Interval2009-08-0505 August 2009 Relief Request 2-10 for Fourth Ten-Year Inservice Inspection Interval NL-09-097, Submittal of Fourth Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan2009-07-21021 July 2009 Submittal of Fourth Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan NL-09-090, Relief Requests 08 and 09 for Fourth Ten-Year Inservice Inspection Interval2009-07-0101 July 2009 Relief Requests 08 and 09 for Fourth Ten-Year Inservice Inspection Interval NL-09-069, 2009 Summary Reports for In-Service Inspection and Repairs or Replacements2009-07-0101 July 2009 2009 Summary Reports for In-Service Inspection and Repairs or Replacements NL-09-087, Relief Request IP3-ISI-RR-01, IP3-ISI-RR-02, and IP3-ISI-RR-03 for Fourth Ten-Year Inservice Inspection Interval2009-06-24024 June 2009 Relief Request IP3-ISI-RR-01, IP3-ISI-RR-02, and IP3-ISI-RR-03 for Fourth Ten-Year Inservice Inspection Interval NL-09-037, Response to Request for Information Regarding Request for Relief 3-48 Supporting Refuel Outage 15 Inservice Inspection Program2009-03-23023 March 2009 Response to Request for Information Regarding Request for Relief 3-48 Supporting Refuel Outage 15 Inservice Inspection Program NL-09-003, Supplemental Response to Request for Additional Information on Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination2009-01-20020 January 2009 Supplemental Response to Request for Additional Information on Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination NL-08-110, Summary Reports for In-Service Inspection and Repairs for Replacements2008-07-14014 July 2008 Summary Reports for In-Service Inspection and Repairs for Replacements NL-08-053, 10 CFR 50.55a Request RR-CRV-75 - Relief from Examinations of Component Welds with Less than Essentially 100% Examination Coverage for Third-Ten Year Inservice Inspection Interval Closeout2008-03-26026 March 2008 10 CFR 50.55a Request RR-CRV-75 - Relief from Examinations of Component Welds with Less than Essentially 100% Examination Coverage for Third-Ten Year Inservice Inspection Interval Closeout NL-07-069, Inservice Inspection Third Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval2007-06-13013 June 2007 Inservice Inspection Third Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval ML0707100072007-03-19019 March 2007 Summary of the Staff'S Review of the 2006 Steam Generator Tube Inservice Inspection Reports for Refueling Outrage 17 NL-07-028, Inservice Testing Program Summary for 4th Interval, Revision 02007-02-28028 February 2007 Inservice Testing Program Summary for 4th Interval, Revision 0 NL-07-029, 4th Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan2007-02-28028 February 2007 4th Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan NL-05-088, Inservice Inspection (ISI) Second Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval2005-07-0606 July 2005 Inservice Inspection (ISI) Second Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval NL-05-0211, Inservice Testing Program Summary for the Interval July 1, 1994 Through April 6.2006. Revision 32005-02-22022 February 2005 Inservice Testing Program Summary for the Interval July 1, 1994 Through April 6.2006. Revision 3 ML0506304052005-02-22022 February 2005 Inservice Inspection (ISI) Third Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval JPN-04-010, Request to Use 1998 Edition, 2000 Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code Requirements for Examination of Reactor Vessel Closure Studs2004-04-14014 April 2004 Request to Use 1998 Edition, 2000 Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code Requirements for Examination of Reactor Vessel Closure Studs NL-03-188, Request for Approval for Alternative to Use Code Case N-613-1 for Reactor Vessel Nozzle to Vessel Weld Inspection2003-12-30030 December 2003 Request for Approval for Alternative to Use Code Case N-613-1 for Reactor Vessel Nozzle to Vessel Weld Inspection NL-03-078, Relief Request RR 63, Risk-Informed Inservice Inspection (RI-ISI) Program2003-05-12012 May 2003 Relief Request RR 63, Risk-Informed Inservice Inspection (RI-ISI) Program NL-03-055, Withdrawal of Relief Request RR3-29 for Inservice Inspection Program2003-03-27027 March 2003 Withdrawal of Relief Request RR3-29 for Inservice Inspection Program NL-03-026, Refueling Outage Inservice Inspection (ISI) Program Summary Report - Third Outage, Second Period, Third Interval2003-02-25025 February 2003 Refueling Outage Inservice Inspection (ISI) Program Summary Report - Third Outage, Second Period, Third Interval NL-04-006, St Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval2003-01-20020 January 2003 St Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval ML0209900922002-04-0303 April 2002 Revised Relief Request Nos. 3-12, 3-14, 3-16 & 3-17, Third 10-Year Inservice Inspection Interval Program Plan ML0205803912002-02-0505 February 2002 Relief Request RR 3-28, Risk-Informed Inservice Inspection (RI-ISI) Program 2018-08-13
[Table view] 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
- ===* Entergx Entergy Nuclear Operations. Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 254 6700 Anthony J. Vitale Site Vice President NL-16-096 September 9, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738
Subject:
2016 Form OAR-1 Owners Activity Report for lnservice Inspection and Repairs and Replacements at Indian Point Unit No. 2 Indian Point Nuclear Generating Unit No. 2 Docket No. 50-24 7 License No. DPR-26
Dear Sir or Madam:
In accordance with ASME Section XI, Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission," Indian Point Unit No. 2 herein submits the 2016 "Form OAR-1 Owners Activity Report." This report describes relevant conditions that required evaluation and repairs and replacements to be performed during the period April 2014 through June 2016.
There are no new commitments made by Entergy contained in this letter. If you have any questions, please contact Mr. Robert Walpole, Manager, Regulatory Assurance at (914) 254-6710.
Sincere!~~ '
~ f-* ~. v,?i,k AJV/gd
Enclosure:
Form OAR-1 Owners Activity Report cc: Mr. Daniel H. Dorman, Regional Administrator, NRC Region I Mr. Douglas V. Pickett, Senior Project Manager, NRC NRR DORL Ms. Bridget Frymire, New York State Department of Public Service Mr. John B. Rhodes, President and CEO, NYSERDA NRC Resident Inspectors
ENCLOSURE TO NL-16-096 Form OAR-1 Owners Activity Report ENTERGY NUCLEAR OPERATIONS, INC.
Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 License No. DPR-26
FORM OAR-1 OWNERS ACTMTY REPORT Report Number NL-16-096 Plant Indian Point Energy Center. Buchanan. New York 10511-0249 Unit No. _..,.2_ _ __ Commercial service date -----=0=..::8=/=0..:..:1/c...:1...:::9c.:..7_,_4____ Refueling outage no. 2R22 Current inspection interval ______ 4th_______________ (1st, 2nd, 3rd, 4th, Other)
Current inspection period -----"""3_rd_ _ _ _ _ _ _ _ _ _ _ _ _ _ ___.(1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the inspection plans _ ___,2=0""'0"'"'1'-E=d=iti=o""'n..._.2=0=0=3"-'-A=d=d=e.:...:n=d=a_____
Date and revision of inspection plans: May 11. 2016 / IP2 Fourth Ten-Year ISl/Cll Program Plan. SEP-ISl-IP2-001 Rev 3. June 25, 2012 / IP2 Fourth Ten-Year ISl/Cll Program Plan. SEP-ISl-IP2-002 Rev 1 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans ----'S=A_,,M=E-Code Cases used for inspection and evaluation: N-532-5, N-663, N-513-3, N-722-1, N-729-1, N-770-1 (if applicable, including cases modified by Case N-532 and later revisions)
CERTIFICATE OF CONFORMANCE I certify that (a) the.statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of 2R22 conform to the requirements of Section XI.
(refueling outage number)
Signed ~ .* J....~ 1/ NUlON M;Ey&>o S\lf-\:~11o~<Toate e( 2.~(1{,
~ ~neror owner' s Deslgnee, Title I ~~c ~.l ---=.>.-----------
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford. CT , have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.
~=~-------_-_:-_-_-_-_-_-_commissions _ _.....N=B--:1=0-=-0"'"'"11...._..l."""N'--'-"N..._YS=--3.-08"""4_,__ __
Inspector's Signature National Board, State, Province, and Endorsements Date_____,qi+-/=-+1 I I l.......,lfe~
2R22 Refueling Outage IP2 Owner Activity Report Third Period Examination Category and !~m Des.crltion Item Number CR-IP2-2016-01323 - The weld attached to the pipe is not fully welded as indicated In the support drawing.
D-AfD1 .20A Class 3 Welded Attachment - One Directional Support I CT 152-W Engineering evaluated the condition and the condition was accepted as is. The design drawing was updated to reflect as-built configuration via an EC.
- CR-IP2-2016-01996- There is a discrepancy between the as-built configuration and the as-built drawing. The drawing indicates anchor bolts on the base plate bracket attached to the concrete wall. The actual as-built F-AfF1 .1 OA Class 1 Piping Supports - One Directional/ RCH 66 configuration is the base plate bracket welded to a concrete embedment plate. Engineering evaluated the condition and the drawing was updated to reflect as-built configuration via an EC.
CR-IP2-2016-02047 - The Spring Can Hanger cold load setting was found out of tolerance. Engineering evaluated F-NF1.10C Class 1 Piping Supports-Thermal Movement/ SIH 179 the condition and the pipe support was readjusted to the cold setting shown in the design drawing.
CR-IP2-2016-01320 - The strut is not rotating due lo corrosion on the bearing and spacer. Engineering evaluated F-A I F1 .20A Class 2 Piping Supports - One Directional/ SR A-9 the condition. The condition was accepted as is.
CR-IP2-2016-01502 - The Spring Can Hanger cold load setting was found out of tolerance. Engineering evaluated F-A/ F1.20C Class 2 Piping Supports-Thermal Movement/ SIH 117 the condition and the spring support is operable and can perform its intended safety function in as found condition.
CR-IP2-2016-01499 - The Spring can hanger cold load setting was found out of tolerance. Engineering evaluated F-A I F1.20C Class 2 Piping Supports -Thermal Movement/ SIH 118 the condition and the pipe support was readjusted to the cold setting shown in the design drawing.
CR-IP2-2016-01306 -The strut is not rotating due to corrosion on the bearing and spacer, and it has a missing F-A I F1 .30A Class 3 Piping Suppcrts - One Directional/ SR 553 cotter pin on the load stud. Engineering evaluated the condition and the strut condition was accepted as Is and the missing cotter pin was replaced for future design configuration.
B/23/2016 OAR-1
2R22 Refueling Outage IP2 Owner Activity Report Third Period i~fili:~'Wfi~~~°kl~f4#ji,@:$ftfff~'t:filt't~Jtitft~t~@£#lM~~~;{tajirt~¥:4:;'..{~*,::~~,:~;~*i:it~ ; .. ' l~\~~~~il§:~~E"\%l!Mi:t@~iW-W.*lf.;;\~~~t1.W1wtti~4ARW:@&t%.msl~
ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE
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Perform a weld overlay IAW ASME CC N-666 upstream of 2 Vent Valve S-50 vent valve 850 2/24/15 15-2-16 3 Condensate Storage Tank Repair local pittinQ corrosion areas on base of CST 3/21/16 15-2-38 Replace sections of pitted 1" SS piping with 6% MoSS 3 Line #1576 material 9/9/15 N/A Replace sections of pitted 2" SS piping with 6% MoSS 3 Line #1579 material 10/4/15 15-2-70 3 Line#497 Reolace corroded elbow on 21 CRFMC SW outlet 12/23/15 15-2-86 3 23 EDG Jacket Water Cooler Repair leak and weld repair HX cover 2/2/16 16-2-3 3 Line#1704 Perform weld repair at elbow upstream of SWN-1142 3/23/16 16-2-7 3 Line #411 Perform weld repair at F-1924 3/19/16 16-2-17 2 SR-48 Repair bent base plate on suonort 4/1/16 16-2-27 1 21 RV Penetration #50 Mechanically remove indications in reactor vessel penetration 3/22/16 16-2-39 2 Valve 728A Cut out and replace drain line due to leakinc weld 4/21/16 N/A 3 496-H-51 Replace bent suooort rod 6/5/16 16-2-66 3 Line #411 Implement EC 65389 6/26/16 16-2-76 8/23/2016 OAR-1