ML16055A115

Three Mile Island, Unit 1 - T1R21 Refueling Outage Inservice Inspection (Isli) Owner'S Activity Report and Attachments

ML16055A115
Person / Time
Site:	Three Mile Island
Issue date:	02/22/2016
From:	Callan E W Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TMI-16-023
Download: ML16055A115 (5)

Text

~Exe!.on GenerationThree Mile Island Unit 1Route 441 South, P.O. Box 480Middletown, PA 17057Telephone 717-948-8000TMI-16-023February 22, 2016U.S. Nuclear Regulatory CommissionATTN. Document Control DeskWashington, DC 20555Three Mile Island Nuclear Station, Unit 1Renewed Facility Operation License No. DPR-50NRC Docket No. 50-289

Subject:

Three Mile Island Nuclear Station, Unit 1 Ti1R21 Refueling Outage InserviceInspection (ISlI) Owner's Activity Report and AttachmentsThe purpose of this letter is to provide the Three Mile Island Nuclear Station Owner's ActivityReport (OAR-i) for Inservice Inspections as required by the American Society of MechanicalEngineers (ASME) Code,Section XI, 2004 Edition with no Addenda and ASME Code CaseN-532-5 Repair/Replacement Activity Documentation Requirements and Inservice SummaryReport Preparation and Submission -Section Xl, Division 1.Attachment 1 is the ISI Owner's Activity Report covering ISl activities associated with Ti R2iRefueling Outage which started on October 30, 20i5, and was the ist outage of the 2ndperiod of the 4th ISI inspection interval.If you should have any questions, please contact the Three Mile Island ISl Coordinator,Michael Grimm at 717-686-7134.Sincerely,E. W. CallanSite Vice President, Three Mile Island Unit iExelon Generation Co., LLC ,

Enclosures:

Attachment 1 -ISI Owner's Activity Report -Ti R21 OutageCc: USNRC, Regional Administrator, Region IUSNRC, Senior Project Manager, NRRUSNRC, Senior Resident InspectorGary Gustofson, Hartford Steam Boiler I&l Co. of CT TIR21 Refueling OutageInservice Inspection (ISI)Owner's Activity ReportPage 2Attachment 1ISI Owner's Activity Report -Ti R21 Outage I I II I II IFORM OAR-i OWNER'S ACTIVITY REPORTReport Number: T1R21Plant: Three Mile Island Nuclear Station. 2625 River Road. Middietown, PA 17057Unit No: 1 Commercial service date: September 2. 1.974 Refueling Outage No: TIR21(if applikable)Current Inspection Interval: ISI = / CISI =2nd, other)Current inspection period: IS1I 2nd ClSl = 2ndEdition and Addenda of Section Xi applicable to the inspection plans: 2004 Edition with No AddendaDate and revision of inspection plans: 8/29/2014 Rev. 3 and 10/27/2015 Rev. 3AEdition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plansN/ACode Cases used for inspection and evaluation: N-432-1. N-460. N-504,-4. N-508-4. N-513-3. N-516-3. N-517-1. N-526. N-528-1. N-532-4. N-532-5. N-552. N-557-1. N-561-2, N-562-2, N-566-2, N-569-1. N-586-1, N-593. N-597-2. N-600. N-613-1. N-619, N-624, N-638-4, N-639, N-641,,N-643-2, N-648-1, N-651. N-661-1. N-661-2. N-665. N-666, N-686-1, N-695. N-696, N-705. N-706-1, .N-722-1, N-729-1, N-731. N-733, N-735. N-739, N-739-1, N-751. N-753. N-770-1. N-786, and N-789 .(hf apptkable, Inr.ludinB cases mn~difled by N-532 and later resisions)CERTIFICATE OF CONFORMANCEI certify that (a) the statements made in this report are correct; (b) the examinations and tests meet theInspection Plan as required by the ASME Code, Section Xl; and (c] the repair/replacement activities and evaluationssupporting the completion of TIR21 conform to the requirements of Section XI.(refueling outage numberSigned, Michael Grimm.,151 Program Date____________________________/gf/Owner or Owner's Designee, Title-CERTIFICATE OF INSERVIlCE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vesselinspectors and employed by The Hartford Stea~m Boiler Inspection and Insurance Company of Connecticut haveinspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge andbelief, the Owner has performed all activities represented by this report in accordance with the requirements ofSection Xl.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 theinspector nor his employer shall be liable in any manner for any personnel injury or property damage or a loss ofany kind arising e with this Inspection..ayGustofson. , -ommission 1]3855 ANIC PA 3036'i~sp~~a~gture(National Board Number and Endorsementi Table 1Items with Flaws or Relevant Conditions That Required Evaluation for Continued ServiceExamination Category Item Description Evaluation Descriptionand Item NumberC-H, C7.10 Make-Up Pump Suction Pressure Previously identified valve packing indicationsTest with existing BACC Evaluations.C-H, C7.10 Decay Heat Removal System Previously identified, new packing, new bonnet toPressure Test bolting (dry), and one fitting outside of ISIboundary. All have received BACC Evaluation andare acceptable for service. No leakage is excess ofTMI limits.C-H, C7.10 Decay Heat System Pressure Test Packing leak previously accepted with existingBACC evaluation. Leakage at BWST Main Flange,J one bolt removed inspected and replaced (seetable 2).C-H, C7.10 Building Spray Train B3 System Previously identified mechanical leaks addressedPressure Test under the BACC program.C-H, C7.10 Make-Up System Pressure Test Previously identified packing leak evaluated as_________________acceptable under the BACC program.D-B, D2.10 EF-P-1 System Pressure Test Leaking bonnet connections evaluated andaccepted under the BACC ProgramD-B, D2.10 Nuclear River System Pressure Test Minor corrosion previously evaluated andaccepted under the External Surfaces MonitoringProgramD-B, D2.10 Decay River B Train Piping Applied Code Case N-513-3 for acceptance of_________________thinned pipe wall until T1R21F-A, F1.40 NR-P-1C Anchorage Corrosion evaluated as acceptable per TMI_________________proceduresF-A, F1.30C IP-E-1 Support Corrosion evaluated as acceptable per TMIproceduresB-N-2, B13.60 Reactor Vessel Interior Alignment Cracked seal welds evaluated as acceptable forKeys continued service. Welds do not perform asupport function and will not result in corrosion ofthe Reactor Vessel.

Table 2Abstract of Repair/Replacement Activities Required for Continued Servicecode class Item Description Description of Work Date completed Repair/Replacement Plan Number2 BWST Flanges Replace gasket and 11/22/15 C2033726bolting on flanges3 Nuclear River Code Case N-789 06/04/15 C2034615Backwash Piping Patch Plate Repair3 Nuclear River Removed patch plate 11/19/15 C2034624Backwash Piping and replaced piping3 Decay River A Code Case N-789 06/19/15 C2034682Train Piping Patch Plate Repair3 Decay River A Removed patch plate 11/18/15 C2034692Train Piping and replaced piping3 Decay River B Replaced piping 11/15/15 C2035 194Train Piping1 RC-H-1B Plugged and 11/24/15 R2235505______________Stabilized tubes2 MS-V-8A Install Furmanite 04/16/ 14 M2351960Clamp to ValveBonnet2 MS-V-8A Removed Furmanite 11/25/15 C2032189Clamp and repairedbonnet leakage2 BWST 24" Flange Removed, inspected, 06/26/14 C2032417and replaced onebolt ________1 Reactor Vessel Removed and 11/22/15 C2034392Internals Vent replaced Vent ValveValve2 MU-V-1034 Ground out weld 07/23/14 N/A, less than 1 inch (repairedSocket Weld flaw and re-welded under C2032503)2 FW-V-12A Repair Bonnet Stud 11/24/15 R2207964________ ______________ Holes

~Exe!.on GenerationThree Mile Island Unit 1Route 441 South, P.O. Box 480Middletown, PA 17057Telephone 717-948-8000TMI-16-023February 22, 2016U.S. Nuclear Regulatory CommissionATTN. Document Control DeskWashington, DC 20555Three Mile Island Nuclear Station, Unit 1Renewed Facility Operation License No. DPR-50NRC Docket No. 50-289

Subject:

Three Mile Island Nuclear Station, Unit 1 Ti1R21 Refueling Outage InserviceInspection (ISlI) Owner's Activity Report and AttachmentsThe purpose of this letter is to provide the Three Mile Island Nuclear Station Owner's ActivityReport (OAR-i) for Inservice Inspections as required by the American Society of MechanicalEngineers (ASME) Code,Section XI, 2004 Edition with no Addenda and ASME Code CaseN-532-5 Repair/Replacement Activity Documentation Requirements and Inservice SummaryReport Preparation and Submission -Section Xl, Division 1.Attachment 1 is the ISI Owner's Activity Report covering ISl activities associated with Ti R2iRefueling Outage which started on October 30, 20i5, and was the ist outage of the 2ndperiod of the 4th ISI inspection interval.If you should have any questions, please contact the Three Mile Island ISl Coordinator,Michael Grimm at 717-686-7134.Sincerely,E. W. CallanSite Vice President, Three Mile Island Unit iExelon Generation Co., LLC ,

Enclosures:

Attachment 1 -ISI Owner's Activity Report -Ti R21 OutageCc: USNRC, Regional Administrator, Region IUSNRC, Senior Project Manager, NRRUSNRC, Senior Resident InspectorGary Gustofson, Hartford Steam Boiler I&l Co. of CT TIR21 Refueling OutageInservice Inspection (ISI)Owner's Activity ReportPage 2Attachment 1ISI Owner's Activity Report -Ti R21 Outage I I II I II IFORM OAR-i OWNER'S ACTIVITY REPORTReport Number: T1R21Plant: Three Mile Island Nuclear Station. 2625 River Road. Middietown, PA 17057Unit No: 1 Commercial service date: September 2. 1.974 Refueling Outage No: TIR21(if applikable)Current Inspection Interval: ISI = / CISI =2nd, other)Current inspection period: IS1I 2nd ClSl = 2ndEdition and Addenda of Section Xi applicable to the inspection plans: 2004 Edition with No AddendaDate and revision of inspection plans: 8/29/2014 Rev. 3 and 10/27/2015 Rev. 3AEdition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plansN/ACode Cases used for inspection and evaluation: N-432-1. N-460. N-504,-4. N-508-4. N-513-3. N-516-3. N-517-1. N-526. N-528-1. N-532-4. N-532-5. N-552. N-557-1. N-561-2, N-562-2, N-566-2, N-569-1. N-586-1, N-593. N-597-2. N-600. N-613-1. N-619, N-624, N-638-4, N-639, N-641,,N-643-2, N-648-1, N-651. N-661-1. N-661-2. N-665. N-666, N-686-1, N-695. N-696, N-705. N-706-1, .N-722-1, N-729-1, N-731. N-733, N-735. N-739, N-739-1, N-751. N-753. N-770-1. N-786, and N-789 .(hf apptkable, Inr.ludinB cases mn~difled by N-532 and later resisions)CERTIFICATE OF CONFORMANCEI certify that (a) the statements made in this report are correct; (b) the examinations and tests meet theInspection Plan as required by the ASME Code, Section Xl; and (c] the repair/replacement activities and evaluationssupporting the completion of TIR21 conform to the requirements of Section XI.(refueling outage numberSigned, Michael Grimm.,151 Program Date____________________________/gf/Owner or Owner's Designee, Title-CERTIFICATE OF INSERVIlCE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vesselinspectors and employed by The Hartford Stea~m Boiler Inspection and Insurance Company of Connecticut haveinspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge andbelief, the Owner has performed all activities represented by this report in accordance with the requirements ofSection Xl.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 theinspector nor his employer shall be liable in any manner for any personnel injury or property damage or a loss ofany kind arising e with this Inspection..ayGustofson. , -ommission 1]3855 ANIC PA 3036'i~sp~~a~gture(National Board Number and Endorsementi Table 1Items with Flaws or Relevant Conditions That Required Evaluation for Continued ServiceExamination Category Item Description Evaluation Descriptionand Item NumberC-H, C7.10 Make-Up Pump Suction Pressure Previously identified valve packing indicationsTest with existing BACC Evaluations.C-H, C7.10 Decay Heat Removal System Previously identified, new packing, new bonnet toPressure Test bolting (dry), and one fitting outside of ISIboundary. All have received BACC Evaluation andare acceptable for service. No leakage is excess ofTMI limits.C-H, C7.10 Decay Heat System Pressure Test Packing leak previously accepted with existingBACC evaluation. Leakage at BWST Main Flange,J one bolt removed inspected and replaced (seetable 2).C-H, C7.10 Building Spray Train B3 System Previously identified mechanical leaks addressedPressure Test under the BACC program.C-H, C7.10 Make-Up System Pressure Test Previously identified packing leak evaluated as_________________acceptable under the BACC program.D-B, D2.10 EF-P-1 System Pressure Test Leaking bonnet connections evaluated andaccepted under the BACC ProgramD-B, D2.10 Nuclear River System Pressure Test Minor corrosion previously evaluated andaccepted under the External Surfaces MonitoringProgramD-B, D2.10 Decay River B Train Piping Applied Code Case N-513-3 for acceptance of_________________thinned pipe wall until T1R21F-A, F1.40 NR-P-1C Anchorage Corrosion evaluated as acceptable per TMI_________________proceduresF-A, F1.30C IP-E-1 Support Corrosion evaluated as acceptable per TMIproceduresB-N-2, B13.60 Reactor Vessel Interior Alignment Cracked seal welds evaluated as acceptable forKeys continued service. Welds do not perform asupport function and will not result in corrosion ofthe Reactor Vessel.

Table 2Abstract of Repair/Replacement Activities Required for Continued Servicecode class Item Description Description of Work Date completed Repair/Replacement Plan Number2 BWST Flanges Replace gasket and 11/22/15 C2033726bolting on flanges3 Nuclear River Code Case N-789 06/04/15 C2034615Backwash Piping Patch Plate Repair3 Nuclear River Removed patch plate 11/19/15 C2034624Backwash Piping and replaced piping3 Decay River A Code Case N-789 06/19/15 C2034682Train Piping Patch Plate Repair3 Decay River A Removed patch plate 11/18/15 C2034692Train Piping and replaced piping3 Decay River B Replaced piping 11/15/15 C2035 194Train Piping1 RC-H-1B Plugged and 11/24/15 R2235505______________Stabilized tubes2 MS-V-8A Install Furmanite 04/16/ 14 M2351960Clamp to ValveBonnet2 MS-V-8A Removed Furmanite 11/25/15 C2032189Clamp and repairedbonnet leakage2 BWST 24" Flange Removed, inspected, 06/26/14 C2032417and replaced onebolt ________1 Reactor Vessel Removed and 11/22/15 C2034392Internals Vent replaced Vent ValveValve2 MU-V-1034 Ground out weld 07/23/14 N/A, less than 1 inch (repairedSocket Weld flaw and re-welded under C2032503)2 FW-V-12A Repair Bonnet Stud 11/24/15 R2207964________ ______________ Holes