ML15049A293
| ML15049A293 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/09/2015 |
| From: | Daugherty J Dominion, Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 15-024 | |
| Download: ML15049A293 (10) | |
Text
A kh
~Domi nionll Dominion Nuclear Connecticut, Inc.
Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 dorn.corn FEB 09 2015 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.
NSSL/MLC Docket No.
License No.15-024 RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT, REFUELING OUTAGE 16 Dominion Nuclear Connecticut, Inc. (DNC) hereby submits the American Society of Mechanical Engineers (ASME),Section XI, Form OAR-i, Owner's Activity Report, for the period from May 20, 2013 through Refueling Outage 16, completed on November 17, 2014 for Millstone Power Station Unit 3. The enclosure is in accordance with the requirements of ASME Code Case N-532-4.
If you have any questions or require additional information, please contact William D. Bartron at (860) 444-4301.
Sincerely, Site Vice President - Millstone
Enclosure:
- 1. Owner's Activity Report, Refueling Outage 16, Revision 0.
Commitments made in this letter:
None A04-7
Serial No.15-024 MPS3 Owner's Activity Report Docket No. 50-423 Page 2 of 2 cc:
U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Mohan C. Thadani Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 B1 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No.15-024 Docket No. 50-423 ENCLOSURE 1 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 16 Revision 0 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
MILLSTONE POWER STATION UNIT NO. 3 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 16 Revision 0 Contents:
OAR-I Report Number: MP3-3R1 6 Table 1:
Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service.
Table 2:
Abstract of Repairs/Replacement Activities Required for Continued Service Prepared By:
Reviewed By:
Reviewed By:
fSI Program wner Independent Review Authoriz ucle anservice Inspection Date:
C!'
-71Aor Date:
a
,l0 Date:,14*/
0-2 DQr1nion' Form OAR-1 Owner's Activity Report I tah et1 E-AA ISI-00~
S i
aeIo Renort Number:
MP3-3R1 6 Plant Millstone Power Station, Rope Ferry Road, Waterford, Connecticut 06385 Unit No.
3 (if applicable)
Commercial service date APril 26, 1986 Refueling outage no.
16 Current inspection interval 3rd Current inspection period 2nd (I st 2 L1, 3r, 4
, other)
(1 st, 2 nd, 3rd)
Edition and Addenda of Section XI applicable to the inspection plans 2004 Edition, No Addenda Date and revision of inspection plans 10/14/2014 Revision 2, Change 03-004 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-460. N-532-4. N-566-2. N-722-1. N-729-1. N-770-1 (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 by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of 3R16 conform to the requirements of Section XI.
(refueling outage number)
Signed
/
'/
7A
-4 ISI Program Owner Date 01/07/2015 Owner or Ownebesignee, 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 Connecticut and employed by HSB Global Standards of Hartford, 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 any kind arising from or connected with this inspection.
Commissions o,1/<
/,".//
SA'*C_
lnspect~ Si~nafLK'e Date auz4s-Z5 National Board, St-te, Proiince and Endorsements
AWDOnIiniow Form OAR-1 Owner's Activity Report Atah et1 E-A AIS10 II-Pae2o Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number Support spring load setting evaluated by F-A F1.30C Pipe Support Engineering and found to be acceptable 3-CCP-2-PSSH091 for continued service as documented in UIR MP3-14-001.
Support thread engagement evaluated F-Al F1.20A Pipe Support by Engineering and found to be 3-FWS-4-PSR01 5 acceptable for continued service as documented in UIR MP3-14-002.
Support Loose Jam nut evaluated by Engineering and found to be acceptable F-A / FI.10E Pipe Support for continued service. Rework 3-RCS-1-PSSP147 performed to tighten loose nut to restore support to original design condition as documented in UIR MP3-14-003.
Support Loose Jam nuts evaluated by Engineering and found to be acceptable Pipe Support for continued service. Rework F-Al F1.20B21 3-FWA-1-PSR001 performed to tighten loose nuts to restore support to original design condition as documented in UIR MP3-14-004.
Support spring load setting evaluated by F-A / F1.OC Pipe Support Engineering and found to be acceptable 3-RCS-1-PSSH003 for continued service as documented in UIR MP3-14-005.
Evidence of leakage detected at bolted connection evaluated in accordance with C-H / C7.10 Valve 3CHS*V046 ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR560676 and ETE-MP-2014-1199.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to C-H /0C7.10 Valve 3CHS*V910 be acceptable for continued service as documented in CR560687 and ETE-MP-2014-1199.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR560611 and ETE-MP-2014-1199.
Dom~niauu Form OAR-1 Owner's Activity Report
-hn 1, E R*
A-
[SI-0 Pa-g 3
f 6 Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to C-H / C7.10 Flow Element 3CHS*FE142 be acceptable for continued service as documented in CR560671 and ETE-MP-2014-1199.
Evidence of leakage detected at bolted connection evaluated in accordance with C-H /C7.10 Valve 3CHS*AV8149B ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR562504 and ETE-MP-2014-1216.
Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Heat Exchanger 3RSS*ElC ASME Code Case N-566-2 and found to Outlet Flange be acceptable for continued service as documented in CR563893 and ETE-MP-2014-1227.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to D-B I D2.10 Pump 3SFC*PIA Casing be acceptable for continued service as documented in CR556956 and ETE-MP-2014-1184.
Evidence of leakage detected at bolted connection evaluated in accordance with D-B 1
D2.10 Pump 3SFC*P1A inlet pipe ASME Code Case N-566-2 and found to flange be acceptable for continued service as documented in CR556962 and ETE-MP-2014-1184.
Evidence of leakage detected at bolted connection evaluated in accordance with D-B /D2.10 Pump 3SFC*P1 B Inlet ASME Code Case N-566-2 and found to Flange be acceptable for continued service as documented in CR554383 and ETE-MP-2014-1166.
Evidence of leakage detected at bolted connection evaluated in accordance with D-1 / D2.10 Pump 3SFC*P1 B Outlet ASME Code Case N-566-2 and found to Flange be acceptable for continued service as documented in CR554385 and ETE-MP-2014-1166.
W-3 Dminivn I Form OAR-1 Owner's Activity Report I
Atah et1 E
-A-S 10 11 1
1 ae4o Table I Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR562290 and ETE-MP-2014-1216.
Evidence of leakage detected at bolted connection evaluated in accordance with B-P B 15.20 Valve 3SlL*V987 ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR562414 and ETE-MP-2014-1216.
Evidence of leakage detected at bolted connection evaluated in accordance with B-P B
B15.20 Valve 3SIL*V985 ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR562311 and ETE-MP-2014-1216.
Evidence of leakage detected at bolted connection evaluated in accordance with B-P BI B5.20 Valve 3R CS*SV8095 ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR565315 and ETE-MP-2014-1234.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR561944 and ETE-MP-2014-1218.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P /815.20 Valve 3RCS*MV8001 B be acceptable for continued service as documented in CR562319 and ETE-MP-2014-1218.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR562186 and ETE-MP-2014-1218.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR562698 and ETE-MP-2014-1216.
Do1P",91manioiir Form OAR-1 Owner's Activity Report IAttc m
n 1,
E-A
-S 10 I
Pa-of 6.t Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR562039 and ETE-MP-2014-1218.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR562378 and ETE-MP-2014-1218.
ONn Form OAR-1 Owner's Activity Report Do0minionw A*ahmn 1,
E-AIS10 Pag 6
of.
6 Table 2 Abstract of RepairlReplacement Activities Required for Continued Service Code Class Item Description Description of Work Date Repair/Replacement Completed Plan Number Replace section of piping and perform weld repair 3
Pipe Spool of an existing elbow of 10/23/2014 53102601188 Service Water line 3-SWP-006-35-3(A-).
Replace section of 3
Pipe Spool Service Water line 10/31/2014 53102744549 3-SWP-002-315-3(B-).
Replace section of 3
Pipe Spool Service Water line 07/09/2014 53102750321 3-SWP-010-27-3.
Replace section of 3
Pipe Spool Service Water line 10/21/2014 53102768543 3-SWP-150-104-3.
Replace section of 3
Pipe Spool Service Water line 10/23/2014 53102768932 3-SWP-002-314-3.
Perform weld repair on 3
Pipe Flange flanges of Service Water 10/27/2014 53102779318 spool 3-SWP-20-3-2-3 and 3-SWP-23-3A-2-3.
Perform weld repair on 3
Pipe Flange flange of Service Water 10/26/2014 53102777705 spool 3-SWP-28-5-4-3.
Perform weld repair on 3Pipe Flange flange of Service Water 10/27/2014 53102779361 spool 3-SWP-20-7-2-3.
Perform weld repair on 3
flanges of Service Water 10/27/2014 53102780336 Pipe Flange spool 3SWP-19-4, and 3SWP-19-4A.
Replace section of 3
Pipe Spool Service Water line 10/23/2014 53102743434 3-SWP-006-32-3(A).
Replace Chemical and 2
Valve Volume Control valve 11/04/2014 53102779781 3CHS*V394.
Replace Reactor Coolant valves 3RCS*SV8095A 1
Valve / Pipe Spool and 3RCS*SV8096A, 11/07/2014 53102788967 including head vent pipe spool.