TMI-14-029, T1R20 Refueling Outage Inservice Inspection (ISI) Owner'S Activity Report and Attachments

T1R20 Refueling Outage Inservice Inspection (ISI) Owner'S Activity Report and Attachments

ML14063A064
Person / Time
Site:	Three Mile Island
Issue date:	02/25/2014
From:	Libra R Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TMI-14-029
Download: ML14063A064 (6)

Text

""WExelon Generation Three Mile Island Unit 1 Route 441 South, P.O. Box 480 Middletown, PA 17057 Telephone 717-948-8000 February 25, 2014 TMI-14-029 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289

Subject:

Three Mile Island Nuclear Station, Unit 1 T1 R20 Refueling Outage Inservice Inspection (IS3) 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-532-4 Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission - Section Xl, Division 1. is the ISI Owner's Activity Report covering ISI activities associated with T1 R20 Refueling Outage which started on October 28, 2013, and was the 2 nd outage of the 1st period of the 4 1h ISI inspection interval.

If you should have any questions, please contact the Three Mile Island ISI Coordinator, Michael Grimm at 717-948-8306.

Sincerely, Richard Libra Site Vice President, Three Mile Island Unit 1 Exelon Generation Co., LLC

Enclosures:

- ISI Owner's Activity Report - T1 R20 Outage cc: USNRC, Regional Administrator, Region I USNRC, Senior Project Manager, NRR USNRC, Senior Resident Inspector Gary Gustofson, Hartford Steam Boiler I&I Co. of CT

/ALC7

T1 R20 Refueling Outage Inservice Inspection (ISI)

Owner's Activity Report Page 2 Attachment 1 ISI Owner's Activity Report - T1 R20 Outage Page 1 of 4 Three Mile Island, Unit No. 1 - Ti R20 OAR REPORT FORM OAR-I OWNER'S ACTIVITY REPORT Report Number T1 R20 Plant: Three Mile Island Nuclear Station, 2625 River Road, Middletown, PA 17057 Unit No: 1 Commercial Service Date: September 2,1974 Refueling Outage No: Ti R20 Current Inspection Interval: 151 = 4'"' / CISI=2n Current Inspection Period: ISI = 1i" CISI = 1" Edition and Addenda of Section Xl Applicable to the inspection plans: 2004 Edition with no Addenda for ISI and CISI Date and revision of inspection plan 12/12/12, Rev 2 for 4 M ISI Interval and 2nd CISI Interval Edition & Addenda of Section XI applicable to repairs and replacements, if different than the inspection plans:

N/A Code Cases used: N-432-1, N-460, N-504-2. N-513-3, N-516-3. N-517-1. N-526. N-528-1. N-532-4. N-552, N-557-1, N-566-2. Nm569-1. N-586-1. N-593, N-597-2. N-600. N-613-1. N-624, N-629. N-638-4. N-639, N-641. N-643-2. N-648-1. N-651.N-661-1. N-665, N-666. N-686-1. N-705. N-706. N-706-1. N-722-1. N-729-1.

N-731, N-733. N-735, N-739, N-740-2*. N-751, N-753, N-770-1. N-789,

• N-740-2 was aporoved for FSWOL in TMI RR-12-02 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; and (c) the repair/replacement activities supporting the completion of 1,R2 conform toQhe requirements of Section XI.

Signed ned Michael Grimm, ISI Program Owner Date 2.,&/S//

Owner or Owner's Designee, Title 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 Pennsylvania and employed by HSB Global Standards of Connecticut have inspected the items described in this Owners 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 anyfind arisin* from or connected with this Inspection.

a IRCommissions: 13855 ANIC PA 3036 e ]U1tesoSignature National Board, State, Province, and Endorsements Date: ZtI4.4 -

Page 2 of 4 Three Mile Island, Unit No. 1 - T1 R20 OAR REPORT TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Examination Item Description Evaluation Description Category Item Number Found shim gap of 1 inch (average of

-- L-B--.-F l2,30-- H24-22 Shim Gap 0.5 inches). Eyaluated as acceptable under IR 1567897 Found shim gap of 1 inch (average of L-B L.2.30 D-143 Shim Gap 0.5 Inches). Evaluated as acceptable

_under IR 1569980 Found shim gap of 1 inch (average of L.B 1.2.30 H13-08 Shim Gap 0.5 inches). Evaluated as acceptable under IR 1579266 Lift-off was not performed on both ends L-B 1..2.10 H13-03 Lift-Off of H13-03. Evaluated as an acceptable lift-off under IR 1587456 0V-136 Missing Missing buttonhead on tendon V-136 L-B3 L2.10 iButtonhead evaluated as acceptable under IR 1567224 D143 146 and 237 Grease voids exceeding the acceptance L-B 12.40 grease voids under 10%, evaluated as acceptable criteriaIRof 1585403

.L-B 1.2.10 H24-15 Protruding Wires Found 2 protruding wires evaluated as S L1 H 1PounW acceptable under IR 1565440 Found 2 studs with missing threads, Pressurizer Heater evaluated as acceptable under IRs 2Bu Covlag 1581221 and 1581230, and AREVA Bolting CRs 2013-8573 and 2013-8572 Found eroded sections around the Lower Pressurizer Heater lower heater bundle. Evaluated as B-G-1 B6.70 Bundle acceptable under IR 1581714 and AREVA CR 2013-8660 Found stainless steel weld buttering on Middle Pressurizer middle heater bundle was not uniform.

B-G-1 B6.70 Heater Bundld Condition was evaluated under IR 1581684 as acceptable and AREVA CR 2013-8665 System Leakage Test D-B D2.10 Boric Acid Injection Bonnet Leak Observed at CA-V-266 (R2201479) (Acceptable per IR 1550355)

Leakage from fuel transfer tubes, D-B D2.10 Spent Fuel Leakage evaluated as acceptable per IRs IExam (R2140278) 1423559 and 1423659 TABLE 1 (Continued)

Attachment 1 Page 3 of 4 Three Mile Island, Unit No. 1 - T1 R20 OAR REPORT ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Packing Leaks, evaluated as C-H C7.10 Make-up System acceptable under IRs 1440128, D-B P2.10 Leakage Exam 1441416, (R2176437) 1447282, 1441315,1442493,1442796, 1447287, 1447789, and AR A2227146.

Make-up System Dry Boron at mechanical connections,

--- C-H C7.10-- Leakage Test i evaluated and accepted under IRs (R2162679) 1400565,1400572, 1400582,1400587, and AR A2265084 Dry Boron at mechanical connection, Make-up Suction evaluated and accepted under IRs C-H - -C7.10 Leakage Test 1590768, 1590763, 1590773,1590778, (R2192154) 1590782, and ARs A2197588 and A2241558 Core Flood B Leakage White Boron at CF-V-47B Threaded C-H C7.10 Test (R2190498) Test Conneciton evaluated and accepted under IR 1561684 Building Spray Train B Dry Boron at mechanical connections, C-H C7.10 Leakage Test evaluated and accepted under IRs (R2186661) 1537965 and 1537969 Reactor Coolant System Leakage at mechanical connections, R9.eatr Tevaluated and accepted under IRs (R2193436) 1589444, 1589442, 1589443, 1589512, and 1589510 OTSG Secondary System Procedure Test Pressure not met, C-H C7.10 Leakage Test evaluated and accepted under IR (R2156661) 1589478 C-H C7.10 Reactor River Water Leakage at mechanical strainer D-B D2.10 System Leakage Test connections, evaluated and accepted (R2192196) under IR 1583453 and 1583458 Nuclear Services System Leakage at Mechanical Connection, D-B D2.10 Leakage Test evaluated and accepted EDT 936935 1 (R2164419) I I Page 4 of 4 Three Mile Island, Unit No. 1 - T1 R20 OAR REPORT TABLE 2 ABSTRACT OF REPAIR / REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Description of Work Date Repair I Class Completed Replacement Plan Number 1 Elbow to Pipe Weld Replace pipe and elbow 02/06/2014 C2031156 RC0289 R ap new/223 Steam Generator 1 Hand Hole Bolting Replaced bolting due to galled threads 1/16/2014 R2198554 RC-H- 1A Steam Generator 1 Hand Hole Bolting Replaced bolting due to galled threads 1/16/2014 R2198555 RC-H-1 B.

1 RC-H.1A Plugged and Stabilized tubes. 12/2/2013 R2198554 1 RC-H-1B Plugged and Stabilized tubes, 12/2/2013 R2198555 3 Penetration 414 Replaced Bolting due to Galled 02/06/2014 R2198561 3___ Bolting Threads 0__06/2014 _2198561._

NS-C-1C Piping Temporary patch repair under code 3 Elbow. case N-789 2/18/2014 C2030720 3 NS-C-1C piping Replaced elbow 2/16/2014 C2030725

.Elbow__ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

1 RC-T-2 Upper 1 Heater Bundle Replaced Upper Heater Bundle 9/04/2013 C2009463 1 RC-V-18 Install TCCP 11-00593, remove RC-V- 2/16/2014 C2026784 18 and Install pipe caps 1 RC-V-18/44 Leak Replace valves, removes TCCP 11- 02/13/2014 02028261 1 by ____ 00593 02 0 4I I 02