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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARNMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations NMP1L3517, Proposed Alternative Associated with a Weld Overlay Repair to the Torus2023-03-29029 March 2023 Proposed Alternative Associated with a Weld Overlay Repair to the Torus NMP2L2811, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owner'S Activity Report for RFO-18 Inservice Examinations2022-05-13013 May 2022 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owner'S Activity Report for RFO-18 Inservice Examinations ML21189A0262021-06-28028 June 2021 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2021 Owner'S Activity Report for RFO-26 Inservice Examinations NMP1L3356, Relief Requests Associated with Pump Periodic Verification Tests for the Fifth Ten-Year Inservice Test Interval2020-10-0808 October 2020 Relief Requests Associated with Pump Periodic Verification Tests for the Fifth Ten-Year Inservice Test Interval NMP2L2755, Fourth Inservice Inspection Interval, First Inservice Inspection Period, 2020 Owner'S Activity Report for RFO17 Inservice Examinations2020-01-0808 January 2020 Fourth Inservice Inspection Interval, First Inservice Inspection Period, 2020 Owner'S Activity Report for RFO17 Inservice Examinations NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 ML19267A0242019-09-24024 September 2019 End of Interval Relief Associated with the Third Ten-Year Inservice Inspection (ISI) Interval NMP1L3309, Submittal of the Snubber IST Program Plan for the Unit 1 Fifth 10-Year Interval and the Unit 2 Fourth 10-Year Interval2019-09-0606 September 2019 Submittal of the Snubber IST Program Plan for the Unit 1 Fifth 10-Year Interval and the Unit 2 Fourth 10-Year Interval NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants2019-04-30030 April 2019 Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants ML18207A4062018-07-17017 July 2018 Third Inservice Inspection Interval, Third Iservice Inspection Period 2018 Owner'S Activity Report for RF0-16 Lnservice Examinations ML18018A9622018-01-18018 January 2018 Preservice Inspection Plan - Preservice Testing - Component Supports ML18018A9612018-01-18018 January 2018 Preservice Inspection Plan ML17164A1812017-06-0606 June 2017 Fourth Inservice Inspection Interval, Third Inservice Inspection Period 2017 Owner'S Activity Report for RF0-24 Inservice Examinations NMP2L2620, Submittal of Post Extended Power Uprate Steam Dryer Inspection Results and Long-term Steam Dryer Inspection Plan in Accordance with Operating License Conditions 2.C.(20)(f), 2.C.(20)(g) and 2.C.(20)(h)2016-08-0101 August 2016 Submittal of Post Extended Power Uprate Steam Dryer Inspection Results and Long-term Steam Dryer Inspection Plan in Accordance with Operating License Conditions 2.C.(20)(f), 2.C.(20)(g) and 2.C.(20)(h) ML16216A1492016-07-25025 July 2016 Third Inservice Inspection Interval, Second Inservice Inspection Period 2016 Owner'S Activity Report for RFO-15 Inservice Examinations ML15191A3852015-07-0909 July 2015 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2015 Owner'S Activity Report for RFO-23 Inservice Examinations ML15155A5912015-06-0303 June 2015 End of Interval Relief Request Associated with the Second 10- Year Risk Informed ISI Inspections ML14203A0082014-07-16016 July 2014 Third Inservice Inspection Interval, Second Inservice Inspection Period 2014 Owner'S Activity Report for RFO14 Inservice Examinations ML13261A2882013-09-0606 September 2013 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for Implementation of a Risk-Informed, Safety-Based Inservice Inspection Program Based on ASME Code Case N-716 - Response to Nrc. ML13231A1862013-08-0909 August 2013 Fourth Inservice Inspection Interval, Second Inservice Inspection Period, 2013 Owner'S Activity Report for RFO-22 Inservice Examinations ML12335A2882012-11-20020 November 2012 Corrected Copy of 2012 Owner'S Activity Report for Refueling Outage 13 Inservice Examinations ML12242A2362012-08-16016 August 2012 Owner'S Activity Report for Refueling Outage 13 Inservice Examinations ML1012700232010-04-29029 April 2010 American Society of Mechanical Engineers Code, Section XI, Inservice Inspection Program for Third Ten-Year Inservice Inspection Interval - 10 CFR 50.55a Request Number ISI-25, Response to NRC Request for Additional Information ML1003200522010-01-28028 January 2010 American Society of Mechanical Engineers Code, Section XI, Inservice Inspection Program for Fourth Ten-Year Inservice Inspection Interval & Associated 10 CFR 50.55a Requests - Additional Supplemental Information Relating to Relief Request 1 ML0933505232009-11-24024 November 2009 American Society of Mechanical Engineers Code, Section XI, Inservice Inspection Program for the Third Ten-Year Inservice Inspection Interval - 10 CFR 50.55a Request Number ISI-25 ML0924001492009-08-25025 August 2009 Third 10-Year Inservice Testing Program - Request for Alternative Number MSS-VR-02 Regarding Testing of Main Steam Safety Relief Valves ML0919503072009-07-0606 July 2009 Third Inservice Inspection Interval Third Inservice Inspection Period 2009 Owner'S Activity Report for RFO-20 Inservice Examinations ML0918300492009-06-25025 June 2009 Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for the Repair & Inservice Inspection of Control Rod Drive Stub Tubes for the License Renewal Period of Extended Operation - Response. ML0908608602009-03-16016 March 2009 Submittal of American Society of Mechanical Engineers (ASME) Code, Section XI, Inservice Inspection Program for the Fourth Ten-Year Inservice Inspection Interval and Associated 10 CFR 50.55a Requests ML0832305122008-11-13013 November 2008 Transmittal of Inservice Testing (IST) Program Update and Associated 10 CFR 50.55a Requests - Response to NRC Request for Additional Information ML0826711202008-09-16016 September 2008 Extension of Permanent Relief from Inservice Inspection Requirements of 10 CFR 50.55a(g) for the Volumetric Examination of Reactor Pressure Vessel Shell Circumferential Welds for the License Renewal Period of Extended Operation ML0819309652008-07-11011 July 2008 Second Inservice Inspection Interval 2008 Owners' Activity Report for Inservice Examinations ML0818400222008-06-30030 June 2008 American Society of Mechanical Engineers Code, Section XI, Inservice Inspection Program for Third Ten-Year Inservice Inspection Interval & Associated 10 CFR 50.55a Requests - Response to NRC Requests for Additional Information ML0819005682008-06-30030 June 2008 Inservice Testing Program Update and Associated 10 CFR 50.55a Requests for the Next Ten-Year IST Intervals ML0802504102008-01-25025 January 2008 American Society of Mechanical Engineers (ASME) Code, Section XI, Inservice Inspection Program for the Third Ten-Year Inservice Inspection Interval and Associated 10 CFR 50.55a Requests - Replacement of Appendix H, Relief Requests / Alterna ML0713702302007-05-10010 May 2007 Request for Use of Later Edition to ASME Code, Section XI for Inservice Inspection Program ML0620101392006-07-13013 July 2006 Owner'S Activity Report for Inservice Examinations ML0522104362005-07-26026 July 2005 Owner'S Activity Report for Inservice Examinations ML0323104382003-08-0808 August 2003 Relief, Request for Relief from Qualification Requirements for Dissimilar Metal Piping Welds ML0321101322003-07-23023 July 2003 Submittal of Inservice Inspection Owners Activity Reports ML0307704482003-03-0606 March 2003 Inservice Inspection Relief Requests Regarding Inner Radius Examination of Class I Reactor Pressure Vessel Nozzles ML0037349602000-07-18018 July 2000 Inservice Inspection (ISI) Summary Report ML18018B0531999-10-15015 October 1999 Third Inservice Inspection Interval - Ten-Year Inservice Inspection Plan and Schedule ML18018B0521999-09-27027 September 1999 Third Inservice Inspection Interval ML18018B0131986-07-29029 July 1986 Preservice Inspection Plan for Nuclear Piping Systems and the Reactor Pressure Vessel Vol. 2 2023-07-14
[Table view] Category:Letter type:NMP
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3523, Annual Radioactive Environmental Operating Report2023-05-12012 May 2023 Annual Radioactive Environmental Operating Report NMP1L3522, Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report2023-04-30030 April 2023 Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report NMP1L3525, Core Operating Limits Report2023-04-19019 April 2023 Core Operating Limits Report NMP1L3526, Submittal of Emergency Relief Request I5R-14 Concerning a Proposed Alternative Associated with N2E Safe End-to-Nozzle Dissimilar Metal Weld Repair with Laminar Indication2023-04-13013 April 2023 Submittal of Emergency Relief Request I5R-14 Concerning a Proposed Alternative Associated with N2E Safe End-to-Nozzle Dissimilar Metal Weld Repair with Laminar Indication NMP1L3520, Supplemental Information for License Amendment Request Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 22023-04-0404 April 2023 Supplemental Information for License Amendment Request Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2 NMP1L3519, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-30030 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3516, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-29029 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3517, Proposed Alternative Associated with a Weld Overlay Repair to the Torus2023-03-29029 March 2023 Proposed Alternative Associated with a Weld Overlay Repair to the Torus NMP1L3518, Proposed Alternative to Utilize Specific Provisions of Code Case N-716-3, Alternative Classification and Examination Requirements Section XI, Division 12023-03-29029 March 2023 Proposed Alternative to Utilize Specific Provisions of Code Case N-716-3, Alternative Classification and Examination Requirements Section XI, Division 1 NMP1L3515, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-27027 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3513, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-24024 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3499, CFR 50.46 Annual Report2023-01-27027 January 2023 CFR 50.46 Annual Report NMP1L3482, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-12-15015 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3486, Radiological Emergency Plan Document Revision2022-12-15015 December 2022 Radiological Emergency Plan Document Revision NMP1L3484, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-15015 December 2022 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Reatment of Structures, Systems and Components for Nuclear Power Reactors NMP1L3485, Proposed Alternative Associated with a Weld Overlay Repair to the Torus2022-12-0808 December 2022 Proposed Alternative Associated with a Weld Overlay Repair to the Torus NMP2L2823, Supplemental Information for License Amendment Request Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators2022-10-28028 October 2022 Supplemental Information for License Amendment Request Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators NMP1L3481, Constellation Energy Generation, LLC, 10 CFR 50, Appendix E - Development of Evacuation Time Estimates2022-09-15015 September 2022 Constellation Energy Generation, LLC, 10 CFR 50, Appendix E - Development of Evacuation Time Estimates NMP1L3477, License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise.2022-08-12012 August 2022 License Amendment Request - Application to Partially Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2, to Revise. NMP1L3478, Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-08-0505 August 2022 Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits NMP1L3467, License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage2022-06-29029 June 2022 License Amendment Request - Revision to Alternative Source Term Calculation for Main Steam Isolation Valve (MSIV) Leakage and Non-MSIV Leakage NMP1L3465, Independent Spent Fuel Storage Installation - General License 30-day Cask Registration Notifications2022-06-17017 June 2022 Independent Spent Fuel Storage Installation - General License 30-day Cask Registration Notifications NMP1L3462, Independent Spent Fuel Storage Installation, General License 30-day Cask Registration Notifications2022-06-0909 June 2022 Independent Spent Fuel Storage Installation, General License 30-day Cask Registration Notifications NMP2L2799, License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators2022-05-24024 May 2022 License Amendment Request - Revise Surveillance Requirements to Reduce Excessive Fast Starting of Emergency Diesel Generators NMP2L2811, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owner'S Activity Report for RFO-18 Inservice Examinations2022-05-13013 May 2022 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2022 Owner'S Activity Report for RFO-18 Inservice Examinations NMP1L3459, 2021 Annual Radiological Environmental Operating Report2022-05-0808 May 2022 2021 Annual Radiological Environmental Operating Report NMP1L3457, 2021 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 22022-04-30030 April 2022 2021 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2 NMP2L2805, Annual Environmental Operating Report2022-04-23023 April 2022 Annual Environmental Operating Report NMP2L2807, Core Operating Limits Report2022-04-0707 April 2022 Core Operating Limits Report NMP1L3458, Constellation Energy Generation, LLC, Annual Property Insurance Status Report2022-04-0101 April 2022 Constellation Energy Generation, LLC, Annual Property Insurance Status Report NMP1L3454, Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-03-0202 March 2022 Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs NMP1L3444, CFR 50.46 Annual Report2022-01-27027 January 2022 CFR 50.46 Annual Report NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 02022-01-11011 January 2022 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0 NMP2L2793, Supplemental Information - Relief Request Associated with Excess Flow Check Valves2021-12-17017 December 2021 Supplemental Information - Relief Request Associated with Excess Flow Check Valves NMP2L2789, Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-12-16016 December 2021 Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0 2024-02-01
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Text
Exelon Generation~
10 CFR 50.55a NMP2L2755 January 8, 2020 U.S. Nucl~ar Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 Docket No. 50-41 O
Subject:
Fourth lnservice Inspection Interval, First lnservice Inspection Perio_d, 2020 Owner's Activity Report for RFO17 lnservice Examinations Pursuant to 10 CFR 50.55a, Nine Mile Point Unit 2 hereby submits the attached Fourth lnservice Inspection Interval, First lnservice Inspection Period, 2020 Owner's Activity Report for RFO17 lnservice Examinations.
This activity report meets the requirements of the American Society of Mechanical Engineers (ASME), Code Case N-532-5, "Alternative Requirements to Repair and Replacement Documentation Requirements and lnservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000,Section XI, Division 1," as approved for use by Regulatory Guide 1.147, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1."
There are no regulatory commitments contained in this letter.
Should you have any questions regarding the information in this submittal, please contact Brandon Shultz, Manager Site Regulatory Assurance, at (315) 349-7012.
Sincerely, itally signed by Sterio, Sterio, Alexander xander D e: 2021.01.13 08:12:20 -05'00' Alexander D. Sterio Director Site Engineering, Nine Mile Point Nuclear Station Exelon Generation Company, LLC ADS/BKS
Enclosure:
Fourth lnservice Inspection Interval, First lnservice Inspection Period 2020 Owner's Activity Report for RFO17 lnservice Examinations
NMP2 Owner's Activity Report for RFO17 January 8, 2021 Page2 cc: Regional Administrator, Region I, USNRC Project Manager, USNRC Resident Inspector, USNRC
NMP2 Owner's Activity Report for RF017 January 7, 2021 Page 3 bee: P. M. Orphanos AG. Schuennan A D. Sterio
- 8. K. Shultz M. R. Faivus COMMITMENTS IDENTIFIED IN THIS CORRESPONDENCE:
- None Responslble Person/Organization: NA Due Date: NA TSB Revision Required? No NL No.: NA Posting Requirements for Responses - NOV/Order No
Enclosure Fourth lnservice Inspection Interval, First lnservice Inspection Period 2020 Owner's Activity Report for RF017 lnservice Examinations
FOURTH INSERVICE INSPECTION INTERVAL FIRST INSERVICE INSPECTION PERIOD 2020 OWNER'S ACTIVITY REPORT FOR RFO17 INSERVICE EXAMINATIONS Prepared For Nine Mlle Point Nuclear Station Unit 2 P.O. Box 63, Lake Road Lycoming, New York 13093 Commercial Service Date* April 5, 1988 NRC Docket Number: 50-410 Document Number: NM P2-OAR-004-020 Revision Number: 00 Date. December 17, 2020 Mark J. Ferlisi - GSE Tru kDigitally signed by Zhang, Bryan Z h ang, Brya n~~ate: 2020121813:26:16-05'00' Reviewed by. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Bryan Zhang - NMPNS Engineering Programs
. .h d ~~rtally s,gned by F1=, MJch>el R Fa1vus, Mic ae I Ji'~-~"7i';~:;~~-osw Approved by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Mike Faivus - Manager Site Engineenng Programs
.=;- ExelonGeneraUon.
Nine Mlle Point Nuclear Station Unit 2 FOURTH INSERVICE INSPECTION INTERVAL NMP2-0AR-004-020 Rev. 00 Date: December 17, 2020 2020 OWNER'S ACTIVITY REPORT FOR Page 2 of 8 INSERVICE EXAMINATIONS TABLE OF CONTENTS Table of Contents............... .... . .. . ...................... 2 Record of Revision........... ........ ... ....................... **************** ........ 3 Abstract . ................. ... . ........ ................ .. ..... . ................................................................................. 4 Form OAR-1 Owner's Activity Report ...................... . ....... 5 Table 1 Items wrth Flaws or Relevant Condrt1ons that Required Evaluation for Continued Service .................... 6 Table 2 Abstract of Repair/Replacement Activities Required for Continued Service ........................................... 7 . . . .......... . . . . . . . . . . . . . . . . . ****************************** ... 8
~ ExelonGeneration.
Nine Mile Point Nuclear Station Unit 2 FOURTH INSERVICE INSPECTION INTERVAL NMP2-0AR-004-020 Rev. 00 Date: December 17, 2020 2020 OWNER'S ACTMTY REPORT FOR Page 3 of 8 INSERVICE EXAMINATIONS
@tORI)' Of REVISION
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No. PAGl;S - .. -
00 December 17, 2020 Entire lnrtial issue of Owner's Activity Report for ASME Document Section XI lnservice Inspection, Containment lnservice Examinations, and Pressure Tests and Alternate Risk-Informed Inspection in accordance with.the requirements of ASME Code Case N-532-5.
Nine Mile Point Nuclear Station Unit 2 NMP2-0AR-004--020
~ExelonGeneration. FOURTH INSERVICE INSPECTION Rev. 00 INTERVAL Date: December 17, 2020 2020 OWNER'S ACTIVITY REPORT FOR Page 4 of 8 INSERVICE EXAMINATIONS ABSTRACT ASME Section XI Code Case N-532-5 requires submission of the Owner's Activity Report to the regulatory and enforcement authorrties having jurisdiction at the plant srte within 90 calendar days of the completion of each refueling outage. An alternative to this requirement was authorized by the NRC, as documented in a letter dated April 30, 2020 (Reference ADAMS Accession No. ML20113F041 ), and submittal of this report is compliant with the authonzed alternative.
This Owner's Activity Report summanzes the results of the Nine Mile Point N'uclear Station (NMPNS), Unit 2, American Society of Mechanical Engineers (ASME) Section XJ In-service Inspection, Risk-lnfonned Inspection, Containment In-service Examinations, and Pressure Tests performed since the last report dated June 28, 2018 through Refueling Outage Sixteen (RFO17) ending Apnl 3rd 2020. RFO17 Is the only refueling outage scheduled during the First In-service Inspection Period that started on October 6, 2018 and is scheduled to end on August 22, 2021.
- The attached Table 1 and 2 include flaws and condrtions (those meeting the requirements of Code Case N-532-
- 5) identified since the last Owner's Activity Report following Refueling Outage RFO-16 (Document Number NMP2-0AR-003-018). documents items that did not fully comply with requirements of IWA-4000 or could not be reviewed to confirm compliance with applicable Code requirements. These items have been entered into the site corrective action program, as noted herein.
As an alternate to the requirements of the ASME, Boiler and Pressure Vessel Code (B&PVC),Section XI, Article IWA-6000, NMPNS is implementing ASME Code Case N-532-5, Alternative Requirements to Repair and Replacement Documentation Requirements and In-service Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000, Section XJ, Division 1. ASME Code Cpse N-532-5 is currently approved for use in Regulatory Guide 1.147, Revision 19, Table 1.
OWNER'S ACTMTY REPORT - FORM OAR-1 The Owner's Activity Report Form OAR-1 was prepared and certified upon completion of the Nine Mile Point Unrt 2, 2020 refueling outage (RFO17) examination activity in accordance with the following NMPNS inspection plans and schedules:
- NMP8743R02U2-04, ISi Program Plan, Fourth Ten-Year Inspection Interval (includes the Alternate Risk-Informed Inspection Program, Containment lnserv1ce Inspection Program, and lnservice Pressure Testing Program)
- ER-NM-330-2003, ISi Selection Document, Fourth Ten-Year Inspection Interval (includes schedules for items selected for examination)
In addition to the Owner's Activity Report, Form OAR-1, the following Tables are also included:
a Items with Flaws or Relevant Conditions that Require Evaluation for Continued Service, Table 1, provides a listing of ltem(s) with flaws or relevant conditions that required evaluation to **determine acceptability for continued service, whether or not the flaw or relevant condition was discovered during a scheduled examination or test, and provides such information as Examination Category, Examination Item Number, Item Description, Flaw Characterization (as required by IWA-3300).
- b. Abstract of Repairs, Replacements or Corrective Measures Required for Continued Service, Table 2, identifies those items containing flaws or relevant conditions that exceeded Division 1 acceptance critena This information Is required even 1f the discovery of the flaw or relevant condition that necessitated the repair/replacement activity did not result from an examination or test required by Division 1. If the acceptance cnterion for a particular rtem Is not specified in Division 1, the provisions of IWA-3100(b) shall be used to determine which repair/replacement activities are required to be included in the abstract.
Nine Mile Point Nuclear Station Unit 2 NMP2-0AR..004-020 Rev. 00
- ~ ExelonGeneration. FOURTH INSERVICE INSPECTION INTERVAL Date: December 17, 2020 2020 OWNER'S ACTIVITY REPORT FOR Page 5 of 8 INSERVICE EXAMINATIONS FORM OAR-1 OWNER'S ACTIVITY REPORT As required by the provisions of the ASME Code Case N-532-5 Report Number: ----------~N~M~P=2-0~A~R~-0~04-0~_2~0_ _ _ _ _ _ _ _ _ _ _ _ _ __
Plant _ _ _ _ _ ____._N,...!ne.,_,.__.M=He'"-'P'-'o=m=t...,_N=u=cle=ar'--'S~tab=o=n,,__,_._P..,...o_B;,.ao"-'x'--'6=3_.,,,, ;,LYr,-=CO=-',"m=m.,.,gu.. .,'--"N=ew,_,__,_Y-"-o'-"rk'-'1...,.3..,._0""'93..___ _ _ _ _ __
(Name and Address of Plant)
Plant Unit -~2~- Commeraal Service Date Aprll 5. 1988 Refueling Outage Number--"--R~F-=O~1~7_ _ _ __
Current Inspection lntervaI _ _~4=th~l=ns=e=rv..ul=ceL..l....,ns~pectj!<,==o~n'-.;l,'--'-nt'!,=e-'-;rv=a"'"'I,.........,=-,=o=ct.;-"o=be=r'-'6..,..-=2=0~18._to~A~u=a=us=t=22~.2=0=2=8_ _ _ __
(1st, 2nd, 3rd, 4th, Other)
Current !1"1$pect100 Perl_op --~Fi=rs=t=ln_._-se~rvl~ce~l~ns~pe~cti~o'="n~P-:-'e'-=n=o-ff-d_~o~ct=o=b=e_._r6~*~2~0~18~to~A~u=g~us=t~2=2,,__.=20=2~1,___ _ __
, (1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the Inspection Plans -----=2=-01_,_,3'--'E""d,,.jti,,_,*o'--'-'n,___ _ _ _ _ _ _ __
Date and Revision of Inspection Plans NMP8743R02U2-04, Revision 0. October 5, 2018 Editmn and Addenda of ASME Secbon XI appllcable*to Repair/Replacement activities, if different than the Inspection Plan N/A (same Code Edition/Addenda)
Of applicable)
Code Cases used for Inspection and evaluation: Code Cases used at Nine Mile Point. Unit 2 dunng the Fourth lnseTVJce Inspection Interval are identified in Document#ER-AA-330-1007, Revision 0 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 RFO17 confonn to the requirements of Section Xi (refueHng outage number)
Date 12/17/2020 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province ofl:I.Y and employed by The Hartford Steam Boller Inspection and Insurance Company of Hartford. CT have inspected the rtems descnbed in this Owner"s Activity Report and state that to the best of my knowledge and belief, the Owner has perfonned all activibes represented by this report m 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 descnbed in this report Furthennore, neither the Inspector nor hlS employer shall be liable in any manner for any personal mJury or property damage or a loss of any kind arising from or connected wrth this Inspection.
__a_~ ____n,__A_tJ-_~ ______Commisslons ANIR 16158 NY 5570 National Board, State, Province, and Endorsements Inspector's Signature Date 12/18/2020
~ Exelon Generation.
Nine Mlle Point Nuclear Station Unit 2 FOURTH INSERVICE INSPECTION INTERVAL NMP2-0AR-004-020 Rev. 00 Date: December 17, 2020 2020 OWNER'S ACTIVITY REPORT FOR Page 6 of 8 INSERVICE EXAMINATIONS TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the proV1s1ons of the ASME Code Case N-532-5 EXAMINATION ITEM ITEM DESCRIPTION EVALUATION DESCRIPTION CATEGORY NUMBER R-A R116 RPV N2J lnter1or Per UT report N2-ISl-203800 and IR#04327298 from N2R17, during a Surface phased-array UT of reclrc Inlet nozzle DMW 2RPV-KB11 (N2J) an embedded non-service induced Indication was observed. The exam was considered acceptable, but the flaw did not meet tha acceptance crrterla In IWB-3514.4. The flaw was evaluated for continued serv1ce.
Calculations for the projected crack growth determined that the flaw Is acceptable for an evaluation Interval of at least 10 years and shall be reexamined by the end of the evaluabon Interval.
F-A F1.20 Venable Spring Per NOE Report #lSI-VT-20-169 and AR# 04329500, during tha VT-3 Support ID #2ASS- examlnabon of spnng hanger 2ASS-PSSH13284 It was noted that the PSSH132B4 cold setbng of the hanger was outside of the acceptable settings per NMP2-P301 F An evaluabon determined that the current setting ls wrthin the operable range of the spring hanger F-A F1 20 Pipe Restraint ID Par NOE Report #lSI-VT-20-163 and AR #04328693, Pipe Support
- 2RHS-PSR042A2 #2RHS-PSR042A2 did not match design drawing 12177-BZ-71BA-2 (rrusslng and plates). The condrt1on of the support was evaluated as acceptable. An action has been created to update the support drawing to reflect as-bunt condltl ons.
F-A F1.30 Pipe Restraint ID Per NOE Report #ISI-VT-20-102 arid AR #04327396, Snubber Support
- 2SWP-PSR523A3 #2SWP-PSR523A3 did not match the design drawing (m1SS1ng end plates). The condrtlon of the support was evaluated as acceptable An action has been created to update the support drawing to reflect as-bLDlt condrtlons.
F-A F1 30 Pipe Restraint ID Per NOE Report #ISI-VT-20-144 and AR #04328719, Pipe Support
- 2SWP-PSRB14A3 #2SWP-PSRB14A3 does not match design drawing. Shims are lnstaned between the pipe and the support, but shims are not shown on BZ-19ED-6 The condition of the support was evaluated as acceptable An action has been created to update the support drawing to Identify the use of shim plates F-A F1.30 Sway Strut ID Per NOE Report #ISI-VT-20-158 and AR #04328707, Pipe Support
- 2SWP-PSST401A3 #2SWP-PSST401A3 does not match design drawing 12177-BZ19MB-2 (missing end plate). The condrtlon of the support was evaluated as acceptable. An action has been created to update the support drawing to reflect as-bunt conditions.
E-A E1.11 Examination Zones Per NOE Reports #ISI-VT-20-119 and #lSI-VT-20-120 and AR IWE-DFL-001 and #04327353, Dryv.,ell floor coatings at El. 240' were observed to be IWE-DFL-002 degraded The IVv'E Responsible lndiVldual determined that these conditions have no detnmental effect on the floor and are acceptable BS-IS.
Nina Mila Point Nuclear Station Unit 2 NMP2-0AR-004-020
.;:!fF ExelonGenefatlon. FOURTH INSERVICE INSPECTION Rev. 00 INTERVAL Date: December 17, 2020 2020 OWNER'S ACTIVITY REPORT FOR Page 7 of 8 INSERVICE EXAMINATIONS TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE As required by the proV1s1ons of the ASME Code Case N-532-5 CODE ITEM DESCRIPTION OF VVORK DATE REPAIR/REPLACEMENT PLAN CLASS DESCRIPTION COMPLETED NUMBER 3 2SWP*STR4C Repair piping through-wall leak in strainer 7/9/2019 C93713556 drain line
Nine Mile Point Nuclear Station Unit 2 NMP2-0AR..004-020
~ ExelonGeneration. Rev. 00 FOURTH INSERVICE INSPECTION INTERVAL Date: December 17, 2020 2020 OWNER'S ACTIVITY REPORT FOR Page 8 of 8 INSERVICE EXAMINATIONS Attachment 1 to Form OAR-1, Owner's Activity Report The followfng Work Orders could not be located to confmn whether performed work included activibes that were subject to requirements of the ASME Code, Secbon XI, IWA-4000, and whether any repair/replacement acl.MtJes documented m these Work Orders required hstmg m Table 2 ofth1s report The lack of availab1hty of these Work Orders has been documented In the site Corrective Ac!Jon Program (Reference AR #04389342)
- C93478814 2RCS*P1 B (Reactor Rearculabon Pump B) Pump Seal Replacement
- C93672936 Perform PMT Inspection Durmg RPV Hydro Test - This Work Order was to Perform Post-Reprur/Replacement VT-2 ExBJTIInatlons for Work Orders #C93691143
- C93246066 2SWP*V1 F (Service Water Pump Discharge Check Valve) Replace Valve 2 Non-destrucbve examinations were not performed ImmedIately follOWJng complebon of repair/replacement actlvrtJes documented m the followmg Work Orders Tus has been documented m the srte Corrective Action Program (Reference AR #04389347)
- C93501282 2SvVP*P1A (Service Water Pump A) - No NOE Datasheet for VT-2 Examination A subsequent VT-2 Examination has now been performed
- C93501335 2CCP*RV64A (Spent Fuel Pool HX Over-Pressure Protection Valve) -VT-2 Examination A subsequent VT-2 Examination has now been performed
- C93620715 2SvVP*STR4F (Service Water Self-Cleaning Strainer F)-VT-2 Examination A subsequent VT-2 Examination has now been performed
- C93622504 21AS*SOV166 (Instrument Alr Supply Automatic Isolation Valve) - VT-2 Examination
- C93367012 2MSS*PSV131 (Mam Steam Safety ReliefValve)-VT-1 PSI on Smgle Nut