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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
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 IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 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) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 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 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans 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 IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs 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 ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration 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 ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) 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 . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 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 ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval 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 ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations 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) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
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CENGSM a joint venture of Constellation e.gy" eDF SEnergy10 NINE MILE POINT NUCLEAR STATION August 9, 2013 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Nine Mile Point Nuclear Station Unit 1 Renewed Facility Operating License No. DPR 63 Docket No. 50-220 Fourth Inservice Inspection Interval, Second Inservice Inspection Period, 2013 Owner's Activity Report for RFO-22 Inservice Examinations Pursuant to 10 CFR 50.55a, Nine Mile Point Nuclear Station, LLC (NMPNS) is submitting Attachment 1, Fourth Inservice Inspection Interval, Second Inservice Inspection Period, 2013 Owner's Activity Report for RFO-22 Inservice Examinations, for Nine Mile Point Unit 1 (NMP1). This report summarizes the results of examinations performed during the last refueling outage (RFO-22) of the Second Inservice Inspection Period of the Fourth Ten-Year Inspection Interval (August 23, 2009 through August 22, 2019).
This activity report meets the requirements of the American Society of Mechanical Engineers (ASME),
Code Case N-532-4, "Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice 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, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1." , Nine Mile Point Unit I Steam Dryer Support Bracket Flaw Evaluation, delineates the flaw evaluation performed for the indications identified in the NMP1 steam dryer support brackets during RFO-22. Attachment 2 was prepared by Structural Integrity Associates, Inc.
Nine Mile Point Nuclear Station, LLC P.O. Box 63, Lycoming, NY 13093
Document Control Desk August 9, 2013 Page 2 Should you have any questions regarding the information in this submittal, please contact Theresa Darling, acting Director - Licensing, at (315) 349-5219.
Sincerely, Paul M. Swift Manager Engineering Services PMS/BTV Attachments: (1) Fourth Inservice Inspection Interval, Second Inservice Inspection Period, 2013 Owner's Activity Report for RFO-22 Inservice Examinations (2) Nine Mile Point Unit I Steam Dryer Support Bracket Flaw Evaluation cc: NRC Regional Administrator, Region I NRC Project Manager NRC Senior Resident Inspector
ATTACHMENT (1)
FOURTH INSERVICE INSPECTION INTERVAL SECOND INSERVICE INSPECTION PERIOD 2013 OWNER'S ACTIVITY REPORT FOR RFO-22 INSERVICE EXAMINATIONS Nine Mile Point Nuclear Station, LLC August 9, 2013
0 Energy Group C(onste,,7o1n Nine Mile Point Nuclear Station FOURTH INSERVICE INSPECTION INTERVAL SECOND INSERVICE INSPECTION PERIOD 2013 OWNER'S ACTIVITY REPORT FOR RFO-22 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 26, 1969 NRC Docket Number: 50-220 Document Number: NMP1-OAR-004-022 Revision Number: 00 Date: May 20, 2013 Prepared by: ý-a ý Ronald P. Fabiny(1PNS IS15 Owner (in-training)
Approved by: 1( L*K Todd L. Davis - NMPNTISI Program Owner Approved by:
Ronald P. Fabiny - NMPN Test Program Owner (in-training)
Approved by: 6C7 L Carlo McClay - NMP Repair & Replacement Program Owner Approved by:
Tim ldfl -NMP S Senior Engineering Analyst/NDE Level III Approved by:
o iorenza, neral Supe fe gineering Programs
Nine Mile Point Nuclear Station Unit I CNG-NMP1-OAR-004-22 O Constellation Energy Group FOURTH INSERVICE INSPECTION Rev. 00 Nine Mile Point INTERVAL Nudear Station 2013 OWNER'S ACTIVITY REPORT Date: MAY 20, 2013 FOR INSERVICE EXAMINATIONS Page 2 of 9 TABLE OF CONTENTS T a b le o f C o n te n ts .................................................................................................................................................... 2 R e c o rd of R e v is io n ..................................................................................................................................................... 3 A b s trac t ....................................................................................................................................................................... 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
Nine Mile Point Nuclear Station Unit I CNG-NMP1-OAR-004-22 Constellation Energy Group FOURTH INSERVICE INSPECTION Rev. 00 Nine Mile Point INTERVAL Nuclear Station 2013 OWNER'S ACTIVITY REPORT Date: MAY 20, 2013 FOR INSERVICE EXAMINATIONS Page 3 of 9 RECORD OF REVISION REVISION " DATE AFFECTED REASON FOR REVISION No. PAGES 00 MAY 20,2013 Entire Initial issue of Owner's Activity Report for ASME Document Section Xl Inservice Inspection, Containment Inservice Examinations, and Pressure Tests and Alternate Risk-Informed Inspection in accordance with the requirements of ASME Code Case N-532-4.
Nine Mile Point Nuclear Station Unit I CNG-NMPI-OAR-004-22 0Constellation Energy Group FOURTH INSERVICE INSPECTION Rev. 00 Nine Mile Point INTERVAL Nuclear Station 2013 OWNER'S ACTIVITY REPORT Date: MAY 20, 2013 FOR INSERVICE EXAMINATIONS Page 4 of 9 ABSTRACT ASME Section XI Code Case N-532-4 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-Two (RFO-22), from April 15, 2013 through May 15, 2013, and the First outage of the Second In-service Inspection Period that started on August 23, 2012 and is scheduled to end on August 22, 2016.
The attached Table 1 and 2 include flaws and conditions (those meeting the requirements of Code Case N-532-
- 4) identified since the last Owner's Activity Report following Refueling Outage RFO-21.
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-532-4, 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 16, approved ASME Code Case N-532-4 for use. This Report complies with the requirements of Code Case N-532-4 and the conditions identified in RG 1.147.
OWNER'S ACTIVITY REPORTS - FORM OAR-1 Owner's Activity Reports Form OAR-I's were prepared and certified upon completion of the Nine Mile Point Unit 1, 2013 refueling outage (RFO-22) examination activity in accordance with the following NMPNS inspection plans and schedules:
CNG-NMP1-ISI-004, Fourth Ten-Year In-service Inspection Plan and Implementing Schedule, (includes the Alternate Risk-Informed Inspection Program CNG-NMP1-CISI-002, Second Containment In-service Inspection Plan and Implementing Schedule.
NMP1-PT-003, Inservice Pressure Testing Program Plan In addition to the Owner's Activity Report, Form OAR-i, 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).
Nine Mile Point Nuclear Station Unit 1 CNG-NMPI-OAR-004-22 0 Constellation Energy Group FOURTH INSERVICE INSPECTION Rev. 00 Nine Mile Point INTERVAL Nuclear Station 2013 OWNER'S ACTIVITY REPORT Date: MAY 20, 2013 FOR INSERVICE EXAMINATIONS Page 5 of 9
- 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.
In accordance with ASME Section Xl, IWB-2412(a), IWC-2412, IWD-2412 IWE-2412(a), and IWF-2410(b) 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 completed for the First In-service Inspection Period in accordance with Tables IWB-2412-1, IWC-2412-1, IWD-2412-1, IWE-2412-1, and IWF-2410-2.
Nine Mile Point Nuclear Station Unit I CNG-NMP1-OAR-004-22 0 Constellation Energy Group FOURTH INSERVICE INSPECTION Rev. 00 Nine Mile Point INTERVAL Nuclear Station 2013 OWNER'S ACTIVITY REPORT Date: MAY 20, 2013 FOR INSERVICE EXAMINATIONS Page 6 of 9 FORM OAR-1 OWNER'S ACTIVITY REPORT As required by the provisions of the ASME Code Case N-532-4 Report Number: NMP1-OAR-004-022 Plant Nine Mile Point Nuclear Station. P. 0. Box 63. Lvcomina. New York 13093 (Name and Address of Plant)
Plant Unit 1 Commercial Service Date December 26, 1969 Refueling Outage Number RFO-22 Current Inspection Interval 4th Interval for ISI & PT. 2 nd Interval for CISI Auqust 23, 2009 to August 22, 2019 (1st, 2nd, 3rd, 4th, Other)
Current Inspection Period Second In-service Inspection Period August 23, 2012 to August 22, 2016 (1st, 2nd, 3rd)
Edition and Addenda of Section Xl applicable to the Inspection Plans 2004 Edition, No Addenda Date and Revision of Inspection Plans CNG-NMP1-ISI-004, Revision 01, December 31, 2010 (ISI), CNG-NMPI-CISI-002, Revision 01, December 31, 2010 (Containment ISI), NMPI-PT-003 Revision 04, March 15, 2011 (Pressure Test)
Edition and Addenda of ASME Section XI applicable to Repair/Replacement activities, if different than the Inspection Plan N/A (same Code Edition/Addenda)
(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: e de, Section Xl; and (c) the repair/replacement activities and evaluations supporting the completi of RFO- conform to the requirements of Section XI.
(,nedrefueingouteumber)
SignedI Date 7/.--
(General Supervisor - Engineering Prodramsýýý CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid copImission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of , ye and employed by h%6c'e1 of//42,fl-4 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 con t d t inspection.
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V Inspector's Signature National Board, State, Province, and Endorsements Dnite
Nine Mile Point Nuclear Station Unit I CNG-NMPI-OAR-004-22 0 ConstemkWon Energy Group FOURTH INSERVICE INSPECTION Rev. 00 Nine Mile Point INTERVAL Nuclear Station 2013 OWNER'S ACTIVITY REPORT Date: MAY 20, 2013 FOR 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-532-4 EVALUATION DESCRIPTION EXAMINATION ITEM ITEM CATEGORY NUMBER DESCRIPTION F-A F1.20B Seismic Restraint Condition Report CR-2013-003241 documents that during Inservice Inspection of seismic restraint 81-SC-46, it was identified that clearances are not as identified on as-built drawing B81-SC-46, SH 2 rev 1. Drawing shows 1/8" typical clearance between pipe and clamshell plates of restraint. No gap exists on top half of pipe; 1/32" gap exists on bottom half of pipe.
Based on a review of the thermal movements in the pipe stress calculation, S14-81P03 the thermal displacements are insignificant.
As such, there is no impact to pipe stress due to the less than 1/8" "normal" gaps at the support 81 -SC-46. There is also no impact on the ability of 81-SC-46 to perform its seismic restraint function.
This condition does not represent a non-conforming condition.
Gaps referenced on drawing B81-SC-46, SH 2 are shown as "nominal". As such minor variations in the gap measurement are expected. Based on the review of the pipe stress calculation the as-found measurements are acceptable and have no impact on the piping analysis.
B-N-2 B13.30 Reactor Vessel Interior Condition Reports CR-2011-002755, CR-2011-002866 and CR-Attachment Weld - 2013-003335 document the identification of a relevant indication Beyond Beltline Region exceeding the acceptance criteria of IWB-3520.2. CENG re-(Steam Dryer Support inspected the four steam dryer support brackets during the Spring Bracket) 2013 refueling outage using EVT-1 and a qualified UT tool and procedure. All four brackets contained reportable indications using UT. Three of the four brackets contained reportable indications using EVT-1.
The UT and EVT-1 inspections performed during RF022 reported flaws larger than reported RFO21 and identified new indications that were not reported in RFO21.
The supporting Engineering Evaluation concluded that the indications are acceptable for continued service for at least one additional operating cycle. In accordance with IWB-3144(b) the engineering evaluation of the exam results is submitted as an attachment to this Owner's Activity Report.
Nine Mile Point Nuclear Station Unit 1 CNG-NMP1-OAR-004-22 0 Coenstellation Energy Group FOURTH INSERVICE INSPECTION Rev. 00 Energy pINTERVAL Nine Mile Point Nuclear Station 2013 OWNER'S ACTIVITY REPORT Date: MAY 20, 2013 FOR INSERVICE EXAMINATIONS Page 8 of 9 TABLE 2 ABSTRACT OF REPAIRIREPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE As required by the provisions of the ASME Code Case N-532-4 REPAIR/REPLACE DESCRIPTION MENT CODE ITEM OF DATE PLAN NUMBER CLASS DESCRIPTION WORK COMPLETED Reactor Water Clean- Replacement of 33-WD- May 1,2013 C92260831 up Weld 33-WD-046 046 due to flaw in weld.
Nine Mile Point Nuclear Station Unit I CNG-NMP1-OAR-004-22 Constellation Energy Group FOURTH INSERVICE INSPECTION Rev. 00 Nine Mile Point INTERVAL Nuctear Station 2013 OWNER'S ACTIVITY REPORT Date: MAY 20, 2013 FOR INSERVICE EXAMINATIONS Page 9 of 9 END OF INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR REFUELING OUTAGE TWENTY-TWO (RFO-22)