TMI-16-023, T1R21 Refueling Outage Inservice Inspection (Isli) Owner'S Activity Report and Attachments

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 Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TMI-16-023
Download: ML16055A115 (5)

Text

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

Subject:

Three Mile Island Nuclear Station, Unit 1 Ti1R21 Refueling Outage Inservice Inspection (ISlI) Owner's Activity Report and Attachments The purpose of this letter is to provide the Three Mile Island Nuclear Station Owner's Activity Report (OAR-i) for Inservice Inspections as required by the American Society of Mechanical Engineers (ASME) Code,Section XI, 2004 Edition with no Addenda and ASME Code Case N-532-5 Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission - Section Xl, Division 1. is the ISI Owner's Activity Report covering ISl activities associated with Ti R2i Refueling Outage which started on October 30, 20i5, and was the ist outage of the 2 nd period of the 4 th 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. Callan Site Vice President, Three Mile Island Unit i Exelon Generation Co., LLC ,

Enclosures:

- ISI Owner's Activity Report - Ti R21 Outage Cc: USNRC, Regional Administrator, Region I USNRC, Senior Project Manager, NRR USNRC, Senior Resident Inspector Gary Gustofson, Hartford Steam Boiler I&l Co. of CT

TIR21 Refueling Outage Inservice Inspection (ISI)

Owner's Activity Report Page 2 Attachment 1 ISI Owner's Activity Report - Ti R21 Outage

I I II I II I FORM OAR-i OWNER'S ACTIVITY REPORT Report Number: T1R21 Plant: Three Mile Island Nuclear Station. 2625 River Road. Middietown, PA 17057 Unit No: 1 Commercial service date: September 2. 1.974 Refueling Outage No: TIR21 (if applikable)

Current Inspection Interval: ISI = 4* / CISI =2n 41,*-*

d, other)

Current inspection period: IS1I2 nd ClSl = 2nd Edition and Addenda of Section Xi applicable to the inspection plans: 2004 Edition with No Addenda Date and revision of inspection plans: 8/29/2014 Rev. 3 and 10/27/2015 Rev. 3A Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code 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 .

(hfapptkable, Inr.ludinB cases mn~difled by N-532 and later resisions)

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 Xl; and (c] the repair/replacement activities and evaluations supporting the completion of TIR21 conform to the requirements of Section XI.

(refueling outage number Signed, Michael Grimm.,151 Program Date____________________________/gf/

Owner or Owner's Designee, Title-CERTIFICATE OF INSERVIlCE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors and employed by The Hartford Stea~m Boiler Inspection and Insurance Company of Connecticut 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 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 the inspector nor his employer shall be liable in any manner for any personnel injury or property damage or a loss of any kind arising from7*cn e with this Inspection.

.ayGustofson. , - ommission 1]3855 ANIC PA 3036

'i~sp~~a~gture(National Board Number and Endorsementi

Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Category Item Description Evaluation Description and Item Number C-H, C7.10 Make-Up Pump Suction Pressure Previously identified valve packing indications Test with existing BACC Evaluations.

C-H, C7.10 Decay Heat Removal System Previously identified, new packing, new bonnet to Pressure Test bolting (dry), and one fitting outside of ISI boundary. All have received BACC Evaluation and are acceptable for service. No leakage is excess of TMI limits.

C-H, C7.10 Decay Heat System Pressure Test Packing leak previously accepted with existing BACC evaluation. Leakage at BWST Main Flange, J one bolt removed inspected and replaced (see table 2).

C-H, C7.10 Building Spray Train B3System Previously identified mechanical leaks addressed Pressure 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 and accepted under the BACC Program D-B, D2.10 Nuclear River System Pressure Test Minor corrosion previously evaluated and accepted under the External Surfaces Monitoring Program D-B, D2.10 Decay River B Train Piping Applied Code Case N-513-3 for acceptance of

_________________thinned pipe wall until T1R21 F-A, F1.40 NR-P-1C Anchorage Corrosion evaluated as acceptable per TMI

_________________procedures F-A, F1.30C IP-E-1 Support Corrosion evaluated as acceptable per TMI procedures B-N-2, B13.60 Reactor Vessel Interior Alignment Cracked seal welds evaluated as acceptable for Keys continued service. Welds do not perform a support function and will not result in corrosion of the Reactor Vessel.

Table 2 Abstract of Repair/Replacement Activities Required for Continued Service code class Item Description Description of Work Date completed Repair/Replacement Plan Number 2 BWST Flanges Replace gasket and 11/22/15 C2033726 bolting on flanges 3 Nuclear River Code Case N-789 06/04/15 C2034615 Backwash Piping Patch Plate Repair 3 Nuclear River Removed patch plate 11/19/15 C2034624 Backwash Piping and replaced piping 3 Decay River A Code Case N-789 06/19/15 C2034682 Train Piping Patch Plate Repair 3 Decay River A Removed patch plate 11/18/15 C2034692 Train Piping and replaced piping 3 Decay River B Replaced piping 11/15/15 C2035 194 Train Piping 1 RC-H-1B Plugged and 11/24/15 R2235505

______________Stabilized tubes 2 MS-V-8A Install Furmanite 04/16/ 14 M2351960 Clamp to Valve Bonnet 2 MS-V-8A Removed Furmanite 11/25/15 C2032189 Clamp and repaired bonnet leakage 2 BWST 24" Flange Removed, inspected, 06/26/14 C2032417 and replaced one bolt ________

1 Reactor Vessel Removed and 11/22/15 C2034392 Internals Vent replaced Vent Valve Valve 2 MU-V-1034 Ground out weld 07/23/14 N/A, less than 1 inch (repaired Socket Weld flaw and re-welded under C2032503) 2 FW-V-12A Repair Bonnet Stud 11/24/15 R2207964

______________ Holes

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

Subject:

Three Mile Island Nuclear Station, Unit 1 Ti1R21 Refueling Outage Inservice Inspection (ISlI) Owner's Activity Report and Attachments The purpose of this letter is to provide the Three Mile Island Nuclear Station Owner's Activity Report (OAR-i) for Inservice Inspections as required by the American Society of Mechanical Engineers (ASME) Code,Section XI, 2004 Edition with no Addenda and ASME Code Case N-532-5 Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission - Section Xl, Division 1. is the ISI Owner's Activity Report covering ISl activities associated with Ti R2i Refueling Outage which started on October 30, 20i5, and was the ist outage of the 2 nd period of the 4 th 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. Callan Site Vice President, Three Mile Island Unit i Exelon Generation Co., LLC ,

Enclosures:

- ISI Owner's Activity Report - Ti R21 Outage Cc: USNRC, Regional Administrator, Region I USNRC, Senior Project Manager, NRR USNRC, Senior Resident Inspector Gary Gustofson, Hartford Steam Boiler I&l Co. of CT

TIR21 Refueling Outage Inservice Inspection (ISI)

Owner's Activity Report Page 2 Attachment 1 ISI Owner's Activity Report - Ti R21 Outage

I I II I II I FORM OAR-i OWNER'S ACTIVITY REPORT Report Number: T1R21 Plant: Three Mile Island Nuclear Station. 2625 River Road. Middietown, PA 17057 Unit No: 1 Commercial service date: September 2. 1.974 Refueling Outage No: TIR21 (if applikable)

Current Inspection Interval: ISI = 4* / CISI =2n 41,*-*

d, other)

Current inspection period: IS1I2 nd ClSl = 2nd Edition and Addenda of Section Xi applicable to the inspection plans: 2004 Edition with No Addenda Date and revision of inspection plans: 8/29/2014 Rev. 3 and 10/27/2015 Rev. 3A Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code 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 .

(hfapptkable, Inr.ludinB cases mn~difled by N-532 and later resisions)

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 Xl; and (c] the repair/replacement activities and evaluations supporting the completion of TIR21 conform to the requirements of Section XI.

(refueling outage number Signed, Michael Grimm.,151 Program Date____________________________/gf/

Owner or Owner's Designee, Title-CERTIFICATE OF INSERVIlCE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors and employed by The Hartford Stea~m Boiler Inspection and Insurance Company of Connecticut 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 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 the inspector nor his employer shall be liable in any manner for any personnel injury or property damage or a loss of any kind arising from7*cn e with this Inspection.

.ayGustofson. , - ommission 1]3855 ANIC PA 3036

'i~sp~~a~gture(National Board Number and Endorsementi

Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Category Item Description Evaluation Description and Item Number C-H, C7.10 Make-Up Pump Suction Pressure Previously identified valve packing indications Test with existing BACC Evaluations.

C-H, C7.10 Decay Heat Removal System Previously identified, new packing, new bonnet to Pressure Test bolting (dry), and one fitting outside of ISI boundary. All have received BACC Evaluation and are acceptable for service. No leakage is excess of TMI limits.

C-H, C7.10 Decay Heat System Pressure Test Packing leak previously accepted with existing BACC evaluation. Leakage at BWST Main Flange, J one bolt removed inspected and replaced (see table 2).

C-H, C7.10 Building Spray Train B3System Previously identified mechanical leaks addressed Pressure 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 and accepted under the BACC Program D-B, D2.10 Nuclear River System Pressure Test Minor corrosion previously evaluated and accepted under the External Surfaces Monitoring Program D-B, D2.10 Decay River B Train Piping Applied Code Case N-513-3 for acceptance of

_________________thinned pipe wall until T1R21 F-A, F1.40 NR-P-1C Anchorage Corrosion evaluated as acceptable per TMI

_________________procedures F-A, F1.30C IP-E-1 Support Corrosion evaluated as acceptable per TMI procedures B-N-2, B13.60 Reactor Vessel Interior Alignment Cracked seal welds evaluated as acceptable for Keys continued service. Welds do not perform a support function and will not result in corrosion of the Reactor Vessel.

Table 2 Abstract of Repair/Replacement Activities Required for Continued Service code class Item Description Description of Work Date completed Repair/Replacement Plan Number 2 BWST Flanges Replace gasket and 11/22/15 C2033726 bolting on flanges 3 Nuclear River Code Case N-789 06/04/15 C2034615 Backwash Piping Patch Plate Repair 3 Nuclear River Removed patch plate 11/19/15 C2034624 Backwash Piping and replaced piping 3 Decay River A Code Case N-789 06/19/15 C2034682 Train Piping Patch Plate Repair 3 Decay River A Removed patch plate 11/18/15 C2034692 Train Piping and replaced piping 3 Decay River B Replaced piping 11/15/15 C2035 194 Train Piping 1 RC-H-1B Plugged and 11/24/15 R2235505

______________Stabilized tubes 2 MS-V-8A Install Furmanite 04/16/ 14 M2351960 Clamp to Valve Bonnet 2 MS-V-8A Removed Furmanite 11/25/15 C2032189 Clamp and repaired bonnet leakage 2 BWST 24" Flange Removed, inspected, 06/26/14 C2032417 and replaced one bolt ________

1 Reactor Vessel Removed and 11/22/15 C2034392 Internals Vent replaced Vent Valve Valve 2 MU-V-1034 Ground out weld 07/23/14 N/A, less than 1 inch (repaired Socket Weld flaw and re-welded under C2032503) 2 FW-V-12A Repair Bonnet Stud 11/24/15 R2207964

______________ Holes