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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
MONTHYEARNMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds NMP2L2880, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, 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 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines 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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 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 ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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) 2024-09-04
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~,,,§? Exelon Generation 10 CFR 50.55a NMP1 L3406 June 28, 2021 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-63 Docket No. 50-220
Subject:
Fifth lnservice Inspection Interval, First lnservice Inspection Period 2021 Owner's Activity Report for RFO-26 lnservice Examinations Pursuant to 10 CFR 50.55a, Nine Mile Point Nuclear Station, LLC (NMPNS) hereby submits the attached Fifth lnservice Inspection Interval, First lnservice Inspection Period, 2021 Owner's Activity Report for RFO-26 lnservice Examinations, for Nine Mile Point Unit 1 (NMP1).
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, Mgr. Site Regulatory Assurance at (315) 349-7012.
Sincerely,
[:\Digitally signed by Rocks, Joshua F Roe-ks 1 JOs h U a 17...:sate: 2021.06.30 08:07:04 -04'00' Joshua Rocks for Alexander D. Sterio Engineering Director, Nine Mile Point Nuclear Station Exelon Generation Company, LLC ADS/BKS
Attachment:
Fifth lnservice Inspection Interval, First lnservice Inspection Period 2021 Owner's Activity Report for RFO-26 lnservice Examinations cc: Regional Administrator, Region I, USNRC Project Manager, USNRC Resident Inspector, USNRC
Attachment Fifth lnservice Inspection Interval, First lnservice Inspection Period 2021 Owner's Activity Report for RFO-26 lnservice Examinations
............ Exelon
~**,
Generation.
FIFTH INSERVICE. fNSPECTION INTERVAL FIRST INSERVICE INSPECTION PERIOD 2021 OWNER'S ACTIVITY REPORT FOR RFO-26 INSERVICE EXAMINATIONS Prepared For Nine Mile Point Nuclear*Station Unit 1 P.O. Box 63, Lake Road Lycoming, New York 13093
- Commercial Service Date: December 01, 1969 NRC Docket Number: 50-220 Document Number: NMP1-0AR-00o-026 Revision Number: 00 Date: June 21*t, 2021
Nine Mile Point Nuclear Station Unit 1 NMP1-OAR-005-26
,,:,, Exelon Generation
. FIFTH INSERVICE INSPECTION INTERVAL 2021 OWNER'S ACTIVITY REPORT FOR Rev . 00 Date: June 21st, 2021 INSERVICE EXAMINATIONS Page 2 of 9 TABLE OF CONTENTS Table of Contents ................................................................................................................................................ 2 Record of Revision ...............................................................................................................................................3 Abstract ..........................................................................................................................................-...................... 4 Form OAR-1 Owner's Activity Report for ASME Section XI Inspection & Testing Plans .................................. 6 Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service .................. 7 Table 2 Abstract of Repairs, Replacements, or Corrective Measures Required for Continued Service ............ 8
I Nine Mile Point Nuclear Station Unit 1 NMP1-OAR-005-26 FIFTH INSERVICE INSPECTION INTERVAL Rev. 00
,::, Exelon 2021 OWNER'S ACTIVITY REPORT Generation. FOR Date: June 21 5 \ 2021 INSERVICE EXAMINATIONS Page 3 of 9 00 June 17th , 2021 Entire
- Initial issue of Owner's Activity Report for ASME Document Section XI lnservice Inspection, Containment lnservice Examinations, 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 1 NMP1-OAR-005-26
..,,,..,. FIFTH INSERVICE INSPECTION INTERVAL Rev. 00
~ Exelon 2021 OWNER'S ACTIVITY REPORT Generation, FOR Date: June 21 st, 2021 INSERVICE EXAMINATIONS Page 4 of 9 ABSTRACT ASME Section XI Code Case N-532-5 requires submission of the Owner's Activity Report to the regulatory and enforcement authorities having jurisdiction at the plant site within 90 calendar days of the completion of each refueling outage.
This Owner's Activity Report summarizes the results of the Nine Mile Point Nuclear Station (NMPNS), Unit 1, American Society of Mechanical Engineers (ASME)Section XI In-service Inspection, Risk-Informed Inspection, Containment In-service Examinations, and Pressure Tests performed during Refueling Outage Twenty-Six (RFO-26), from March 22, 2021 through April 11, 2021, and the first outage of the 1st In-service Inspection Period that started on August 23, 2019 and is currently scheduled to end on August 22, 2022.
The attached Table 1 and 2 include flaws and conditions (those meeting the requirements of Code Case N-532-
- 5) identified since the last Owner's Activity Report following Refueling Outage RFO-25.
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 XI, Division 1". Regulatory Guide 1.147, Revision 18, approved ASME Code Case N-532-5 for use. This Report complies with the requirements of Code Case N-532-5 and the conditions identified in RG 1.147.
OWNER'S ACTIVITY REPORTS - FORM OAR-1 Owner's Activity Reports Form OAR-1 's were prepared and certified upon completion of the Nine Mile Point Unit 1, 2021 refueling outage (RFO-26) examination activity in accordance with the following NMPNS inspection plans and schedules:
- ER-NM-330-1001, Fifth Ten-Year In-service Inspection Plan and Implementing Schedule, [includes the Alternate Risk-Informed Inspection Program, Pressure Testing (PT) Program, and Containment (CISI) lnservice Inspection Program]
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 item(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 criteria shall be provided with the information and format of Table 2. This information is required even if 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 criterion for a particular item 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 1 NMP1-OAR-005-26 FIFTH INSERVICE INSPECTION INTERVAL Rev. 00
,=, Exelon 2021 OWNER'S ACTIVITY REPORT Generation. FOR Date: June 21 st , 2021 INSERVICE EXAMINATIONS Page 5 of 9 In accordance with ASME Section XI, IWB-2411, IWC-2411, IWD-2411, IWE-2411, and IWF-2410 and with the exception of the examinations that may be deferred until the end of the inspection interval as specified in Table IWB-2500-1; IWC-2500-1, IWD-2500-1, IWF-2500-1 and IWE-2500-1, including those examinations which NMPNS has requested and received approval in the-form of relief request, the required examinations in each examination category have been scheduled in accordance with Tables IWB-2411-1, IWC-2411-1, IWD-2411-1, IWE-2411-1, and IWF-2410-1.
Nine Mile Point Nuclear Station Unit 1 NMP1-OAR-005-26 AIIW' FIFTH INSERVICE INSPECTION INTERVAL Rev. 00
_.. Exelon 2021 OWNER'S ACTIVITY REPORT Generation. FOR Date: June 21 st , 2021 INSERVICE EXAMINATIONS Page 6 of 9 FORM OAR-1 OWNER'S ACTIVITY REPORT As required by the provisions of the ASME Code Case N-532-5 Report Number: NMP1-OAR-005-26 Plant -------~N=in=e~M=ile~P=oi~n~t~N=uc=le=a=r-,;S;c..t=at=io~n~.~P"""."'=O""'.,=;B=ox~63=.'='L='y""c=om~in__q~.~N=ew~Y~o~rk~13~0=9~3'-------
(Name and Address of Plant)
Plant Unit -~1_ _ Commercial Service Date December 01. 1969 Refueling Outage Number RFO-26 Current Inspection Interval 5th Interval for ISi & PT. 3rd Interval for GISI August 23. 2019 to August 22. 2029 (1st. 2nd. 3rd, 4th. Other)
Current Inspection Period First In-service Inspection Period August 23. 2019 to August 22. 2022 (1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the Inspection Plans 2013 Edition. No Addenda Date and Revision of Inspection Plans ER-NM-330-1001. Revision 00. August 23. 2019 {ISi}
Edition and Addenda of ASME Section XI applicable to Repair/Replacement activities, if different than the Inspection Plan NIA {same Code Edition/Addenda)
Code Cases used: ~N~-5~3=2~-~5---------....,,....-....,,--,-,---,----------
{if applicable)
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 RFO-26 conform to the requirements of Section XI.
(refueling outage number) r Signed Zhang, Bryal')t::.":::i~"r~~= Date 6/23/2021 (Programs Manager)
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 of NY and employed by The Hartford Steam Boiler Inspection & Insurance Co. 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 a loss of any kind arising from or connected with this inspection.
Powers. .~Di7_i~allysignedby Commissions NY5570 NB 16158A NI R I'1spector's ~~lilq~~~;:;; ~tional Board, State, Province, and Endorsements Branaon 1.,,/
Date u13-03-04*00*
Nine Mile Point Nuclear Station Unit 1 NMP1 -OAR-005-26
.--* FIFTH INSERVICE INSPECTION INTERVAL Rev. 00
,,::, Exelon 2021 OWNER'S ACTIVITY REPORT Generation. FOR Date: June 21st, 2021 INSERVICE EXAMINATIONS Page 7 of 9 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-5 EXAMINATION ITEM ITEM EVALUATION DESCRIPTION CATEGORY NUMBER DESCRIPTION R-A R1.20 Reactor Vessel Nozzle While performing an Encoded Automated Phased Array on weld N1C Safe End to Elbow 32-WD-085 Nozzle to safe end weld on N1C, two axial indications were recorded with measurable through-wall dimensions. Indication #1 is acceptable, however indication #2 ls unacceptable per table ASME Section XI 2013 Edition Table-3514-1. These flaws are ID connected (inner diameter surface):
These flaws were seen in previously encoded data and were characterized as ID geometry. Since the current technique is far superior (data quality), we can now ascertain a through-wall dimension to generate an a/I (aspect ratio) per the code. The flaws are constrained to the 316NG (Nuclear Grade-Low Carbon) material which is considered sec (stress corrosion cracking) resistant material. These flaws are not service induced. This condition was documented in the site Corrective Action Program (IR#4412326).
R-A R1.20 Reactor Vessel Nozzle While performing an Encoded Automated Ph~sed Array on weld N1 D Nozzle Safe End to 32-WD-125 Nozzle to safe end weld on N1D, thirteen (13) axial Elbow indications were recorded with measurable through-wall dimensions. The results were four (4) acceptable indications and nine (9) unacceptable indications.
Indications #1, '/16, #8, and #11 are acceptable, however indications #2, #3, #4, #5, #7, #9, #10, #12, and #13 are unacceptable per table ASME Section XI 2013 Edition Table-3514-1. All flaws are ID connected (inner diameter surface).
These flaws were seen in previously encoded data and were characterized as ID geometry. Since the current technique is far superior (data quality), we can now ascertain a through-wall dimension to generate an a/I (aspect ratio) per the code. The flaws are constrained to the 316NG (Nuclear Grade-Low Carbon) material which is considered sec (stress corrosion cracking) resistant material. These flaws are not service induced. This condition was documented in the site Corrective Action Program (IR# 04412423).
Nine Mile Point Nuclear Station Unit 1 NMP1-OAR-005-26 FIFTH INSERVICE INSPECTION INTERVAL Rev. 00
,::I::!' Exelon 2021 OWNER'S ACTIVITY REPORT Generation, FOR Date: June 21 st , 2021 INSERVICE EXAMINATIONS Page 8 of 9 TABLE2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-5 CODE CLASS ITEM DESCRIPTION DESCRIPTION OF WORK DATE COMPLETED REPAIR/REPLACEMENT PLAN NUMBER None.
..=-' Exelon Generation.
Nine Mile Point Nuclear Station Unit 1 FIFTH INSERVICE INSPECTION INTERVAL 2021 OWNER'S ACTIVITY REPORT FOR INSERVICE EXAMINATIONS NMP1-OAR-005-26 Rev. 00 Date: June 21 st, 2021 Page 9 of 9 END OF INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR REFUELING OUTAGE TWENTY-SIX (RF0-26)