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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:Operating Report
MONTHYEARNL-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-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 NL-17-095, 2017 Form OAR-1 Owners Activity Report for Lnservice Inspection and Repairs and Replacements at Indian Point Unit No. 32017-07-26026 July 2017 2017 Form OAR-1 Owners Activity Report for Lnservice Inspection and Repairs and Replacements at Indian Point Unit No. 3 NL-15-052, Revised Core Operating Limits Report for Cycle 192015-04-21021 April 2015 Revised Core Operating Limits Report for Cycle 19 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 ML1029403622010-11-12012 November 2010 October 2010 10 CFR 2.206 Monthly Status Report: Enclosures NL-07-060, Revised Core Operating Limits Report2007-05-15015 May 2007 Revised Core Operating Limits Report 2020-09-01
[Table view] |
Text
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-17-095 July 26, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk \
11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738
Subject:
2017 Form OAR-1 Owners Activity Report for lnservice Inspection and Repairs and Replacements at Indian Point Unit No. 3 Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64
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. 3 herein submits the 2017 "Form OAR-1 Owners Activity Report." This report describes relevant conditions that required evaluation and repairs and replacements to be performed during the period May 2015 through June 2017.
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.
Sincerely, 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 Ms. Alicia Barton, President and CEO, NYSERDA NRC Resident Inspectors
ENCLOSURE TO NL-17-095 Form OAR-1 Owners Activity Report ENTERGY NUCLEAR OPERATIONS, INC.
Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64
FORM OAB-1 OWNERS ACTMTY REPORT Report Number: ~NL~.~-~1~7~-0=9-=-5_ _ _ _ _ __ Page _Lof_3_
Plant: Indian Point Energy Center. Buchanan, New York 10511-0249 Unit No: 3 Comillercial Service Date: -~0~8~/3~0~/1=9~7~6_ _ _Refueling Outage No.: -~3R~l9_ __
(if applicable)
Current Inspection Interva1: _ _ _ _ _ _~4_lh_ _ _ _ _ _ _ _ _ _ _ _ _ _ __
(!st, 2nd, 3rd, 4th, Other)
Current Inspection Period: -------=-3-rd---~------------
(lst, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the Inspection Plans: 2001 Edition, 2003 Addenda Date and Revision oflnspectionPlans: August 2. 2016 I ISI Program Plan. Rev. 4 No. SEP-ISI-IP3-001 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the Inspection Plans:
2001Edition,2003 Addenda Code Cases used for inspection and evaluation: N-513-3, N-532-5, N-716, N-722, N-729-1, N-770 (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 3Rl 9 conform to the requirements of Section XI.
Signed: N'f-LC:.o ~
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 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.
~- Inspector's Signature Commissions: _ _ _N""B~1~00~1~1~1,~N~N""Y~S~3~08~4~-----
(National Board Number and Endorsement)
Date: _ _ ?~0_z~s+-//_"7~--
' I
FORM OAB-1 OWNERS ACTIVITY REPORT Report Number: ~N~L=-~1~7-'-0=9-"-5_ _ _ _ _ __
Page _l__of_3_
Plant: Indian Point Energy Center, Buchanan, New York 10511-0249 Unit No: ,----,-:----.;=,3~_ _Commercial Service Date: --'0""'8"'--/3,,,_0=/-"-1~97""'6"'--_ _.Refueling Outage No.: --=3R=19"----
(if applicable)
TABLEl:
ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Item Description Evaluation Description Category an~
Item Number F-NFl.lOB 1-4102 Sl-H&R-843-5C CR-IP3-2017-01303- Support concrete embedment was cracked.
Engineering evaluated condition and determined that the support was operable in current condition.
F-NF1.30A 3-3410 SW-H-62 CR-IP3-2017-01503-The Spring Can Hanger cold load setting was found out of tolerance. Engineering evaluated condition and determined that the support was operable in current condition.
F-NF1.30A 3-3408 SWN-H-406-7 CR-IP3-2017-01139-The Spring Can Hanger cold load setting was found out of tolerance. Engineering evaluated condition and determined that the support was operable in current condition.
F-NF1.30B 3-3500 AC-H&R-523 CR-IP3-2017-01133- Anchor bolts of the support had a gap between the anchor nut and the base plate of the support.
Engineering evaluated condition and determined that the support was operable in current condition.
F-NF1.30B 3-3500 AC-H&R-528 CR-IP3-2017-01131- Anchor bolts of the support had a gap between the anchor nut and the base plate of the support.
Engineering evaluated condition and determined that the support was operable in current condition.
F-NF1.30B 3-3410 SW-H&R-12C-17 CR-IP3-2017-01502- 1. A gap between a locknut and jam-nut.
Nut tightened. 2. And a gap between the anchor bolt and washer on the base plate. Engineering evaluated condition and determined that the support was operable in current condition.
F-NF1.30B 3-3400 SWN-H&R-1081-6 CR-IP3-2017-01003- Corrosion discovered on support.
Engineering evaluated condition and determined that the support was operable in current condition.
F-NF1.30B 3-3400 SWN-H&R-1082-6 CR-IP3-2017-01004- Corrosion discovered on support.
Engineering evaluated condition and determined that the support was operable in current condition.
F-NF1.30B 3-3400 SWN-H&R-1083-6 CR-IP3-2017-01006- Corrosion discovered on support.
Engineering evaluated condition and determined that the support was operable in current condition.
F-NFl.40 3-1500 31 Support CR-IP3-2017-01601- Degraded coating and corrosion discovered on support. Engineering evaluated condition and determined that the support was operable in current c~ndition.
- FORM OAR-1 OWNERS ACTMTY REPORT Report Number: --"N-'-'L=----"1_,_7__,-0=9-=-5_ _ _ _ _ __
Page _]__of_3_
Plant: Indian Point Energy Center, Buchanan, New York 10511-0249 Unit No: ---=-3_ _ _Commercial Service Date: -~0~8~/3~0~/1~9~7~6_ _ _Refueling Outage No.: -~3R~19~--
TABLE2:
ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Description of Work Date Repair/Replacement Class Comnleted Plan Number 3 14" Pipe Line #108-1 Cut out and replace section of 14" carbon steel 4/4/17 16-3-38 cement-lined pipe (N-513-3) 3 3" Pipe Line #1224 Replace leaking flange and pipe piece (N-513-3) 3/22117 16-3-60 3 18" Pipe Line #405 Replace leaking flange and pipe piece (N-513-3) 3/31/17 17-3-6 3 3" Weld #B297 Weld repair leaking weld (N-513-3) 3/22/17 17-3-8 3 3" Weld #Bl 155 Replace elbow due to pitting at the weld (N-513-3) 4/2/17 17-3-10 3 3" Cap on Pipe Line #406 Cut out leaking fitting to pipe weld and install a blind 4/27/17 17-3-23 flange*
.2 l" Line#525 Cut out and replace l" piping due to pinhole leak at . 5/13/17 NIA socket weld connection