View source for TMI-12-016, T1R19 Refueling Outage Inservice Inspection (ISI) Owner'S Activity Report and Attachments

{{Adams
| number = ML12054A689
| issue date = 02/20/2012
| title = T1R19 Refueling Outage Inservice Inspection (ISI) Owner'S Activity Report and Attachments
| author name = Libra R
| author affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000289
| license number = DPR-050
| contact person = 
| case reference number = T1R19, TMI-12-016
| document type = Inservice/Preservice Inspection and Test Report, Letter type:TMI
| page count = 5
}}

=Text=
{{#Wiki_filter:Exekln@
Three Mile Island Unit 1                  Telephone 717-948-8000 Nuclear Route 441 South, P.O. Box 480 Middletown, PA 17057 ASME Code, Section XI February 20,            2012                                                            10CFR50.55a TMI-12-016 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 T1R19 Refueling Outage Inservice Inspection (ISI) 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, 1995 Edition with 1996 Addenda, ASME 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 XI, Division 1. is the ISI Owner's Activity Report covering ISI activities associated with T1 R1 9 Refueling Outage which started on October 24, 2011, and was the last outage of the third period of the 3rd ISI inspection interval and the first outage of the first period of the 4th ISI inspection interval.
If you should have any questions, please contact the Three Mile Island ISI Coordinator, Gene Navratil at 717-948-8716.
Sincerely, R. W. Libra Site Vice President, Three Mile Island Unit 1 Exelon Generation Co., LLC

==Enclosures:==
  - ISI Owner's Activity Report - T1 R1 9 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
                                                                                                     'd/

T1 R19 Refueling Outage Inservice Inspection (ISI)
Owner's Activity Report Page 2 Attachment 1 ISI Owner's Activity Report - T1 R1 9 Outage Page 1 of 3 Three Mile Island, Unit No. 1 - 1R19 OAR REPORT FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number 1R19 Plant:     Three Mile Island Nuclear Station, 2625 River Road, Middletown, PA 17057 Unit No: 1            Commercial Service Date: September 2, 1974                                     Refueling Outage No: T1 R19 Current Inspection Interval: ISI = 3       d & 4 th / CISI= 1s&& 2 nd            -
Current Inspection Period: ISI         = 3 for 3rd Interval & 1 st for 4th Interval / CISI = 3 rd for 3 rd Interval &151 for 4 th Interval Edition and Addenda of Section XI Applicable to the inspection plans:                      1995 Edition through 1996 Addenda for ISI 3 rd Interval & CISI 1 st Interval. 2004 Edition with no Addenda for the 4th ISI Interval &2nd CISI Interval 11/4/10, Rev9for3rd ISI & 1 SI CISI Interval & 3/11/11, Rev 0 for 4th             IS, Date and revision of inspection plan              Interval and 2 nd CISI Interval Edition & Addenda of Section XI applicable to repairs and replacements, if different than the inspection plans:
1995 Edition with 1996 Addenda through April 19, 2011 & 2004 Edition with no Addenda for 4/20/11 & later.
Code Cases used: N-416-3, N-460, N-491-2, N498-4, N-504-2, N-517-1, N-522, N-523-2, N-526, N-528-1, N-532-4, N-533-1, N-537, N-545, N-546, N-566-2, N-583, N-600, N-613-1, N-624, N-638-1. N-639, N-643, N-643-2, N-652, N-665, N-685, N-695, N-696, N-686, N-686-1, N-700, N-706, N-706-1. N-722, N-729-1. N-731, N-735, N-739, N-751, N-753.
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, T1 R1 9 conform to the requirements of Section XI.
Signed: -                fA               Z               Gene Navratil, ISI Program Owner                    Date     02/02/2012 Owner or Owners 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 Hartford Steam 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 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 an kind aip'ing from or connected with this inspection.
Commissions:               13855 ANI               PA 3036
         -4*Vc*'pector' sSi-gn&#xfd;--arre                                           National Board, State, Province, and Endorsements Date: 02/02/2012 Page 2 of 3 Three Mile Island, Unit No. 1 - 1 R1 9 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 F-A           F1.30          Support COE0007       Pipe in contact with box restraint evaluated as acceptable under IR 1255909.
F-A           F1.20         Snubber SPSE001 0      Loose pipe clamp bolt evaluated as acceptable under IR 1275230.
F-A           F1.20           Support MS0067       Bolt thread engagement evaluated as acceptable under IR 1280879.
F-A           F1.20           Support EF0024       Support travel setting evaluated as acceptable under IR 1282745.
F-A           F1.20           Support EF0025       Support travel setting evaluated as acceptable under IR 1282745.
F-A           F1.20           Snubber MS0214       Snubber piston setting evaluated as acceptable under IR 1285625.
F-A           F1.10          Support MU01 455      Bent hanger rod evaluated as acceptable under IR 1286004.
F-A           F1.10          Snubber MUE0043       Snubber bolt thread engagement evaluated as acceptable under IR 1286507.
F-A           F1.10           Support RC0002       Bent hanger rod evaluated as acceptable under IR 1289704.
F-A           F1.10           Snubber RC0005       Snubber piston setting evaluated as acceptable under IR 1289611.
C-H           C7.10       System Leakage Test In   Boric acid deposits observed at C7.30       Make-Up and Purification mechanical joints and accepted under C7.50         System (Work Order     IR's 238636,1100558, 946760, and C7.70              R2124159)         1139763.
D-B           D2.10 D2.30 D2.50 D2.70 B-P           B15.10      System Leakage Test In   Boric acid deposits observed at C-H           C7.10       Make-Up and Purification mechanical joints and accepted under System (Work Order     IR's 1280461 and 1280462.
R2152126)
C-H           C7.10       System Leakage Test In   Boric acid deposits observed at Make-Up and Purification mechanical joints and accepted under System (Work Order     IR's 1033510 and 1292277.
R2156159)
C-H           C7.10       System Leakage Test in   Boric acid deposit observed at C7.30        Decay Heat Removal      mechanical joint and accepted under IR C7.50         System (R2134124)      1126043.
C7.70 Page 3 of 3 Three Mile Island, Unit No. 1 - 1R19 OAR REPORT TABLE 1 (Continued)
ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination          Examination             Item Description                Evaluation Description Category          Item Number
__-C&#xfd;--I-*I            -C7.-1-0 --- -- System-Leakage-Test-in .. Boric-acid-deposits-observedat Core Flood System       mechanical joints and accepted under (R2138474)          IR's 1280456 and 1280480.
B-P              B15.10           System Leakage Test in     Boric acid deposits observed at Class 1 Components       mechanical joints and accepted under (R2156771)          I R's 1294265, 1294251, 1294252, 1294253,1294254,1294256,1294264, 1294214,1294266,1294258,1294259, 1294261, 1294262, and 1294211.
C-H               C7.30           System Leakage Test in      Leakage observed at mechanical joints C7.70            Nuclear Services Close    and accepted under IR's 987240, D-B               D2.10            Cooling Water System      314570, and 933616.
D2.30                  (R2086383)
D2.50 D2.70 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 3        Strainer CA-S-8B          Installed new cover bolting.              07/15/2010     R2124407 3        Piping fabrication        Installed mechanical pipe clamp.          12/14/2010     C2024596 weld MU57b5 3        Piping fabrication        Replaced piping weld.                     01/25/2012     C2024595 weld MU57b5 2        Relief valve MS-V-        Replaced relief valve.                    01/26/2012     C2026480 21A 1        Snubber RC0102            Replaced snubber.                         01/26/2012     R2043988 2        Relief valve MS-V-        Replaced relief valve.                    01/26/2012     R2002964 18A 1        Steam Generator           Plugged and stabilized tubes.             02/01/2012     R2117327 RC-H-1B         ,__I}}