ML12046A836

Inservice Inspection Program - Owners Activity Report

ML12046A836
Person / Time
Site:	Millstone
Issue date:	01/31/2012
From:	Scace S Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
12-043
Download: ML12046A836 (10)

Text

Dominion-Dominion Nuclear Connecticut, Inc.

Millstone Power Station Rope Ferry Road Waterford, CT 06385 JAN 31 2012 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.

NSSUMLC Docket No.

License No.12-043 RO 50-423 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT 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 19, 2010 through Refueling Outage 14, completed on November 23, 2011 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 Mr.

William Bartron at (860) 444-4301.

Sincerely, Stphfý SaceU Site Vice President - Millstone

Enclosure:

1. Inservice Inspection Program - Owner's Activity Report, Refueling Outage 14.

Commitments made in this letter:

None A-W7

Serial No.12-043 MPS3 Owner's Activity Report Docket No. 50-423 Page 2 of 2 cc:

U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 C. J. Sanders Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08-B3 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.12-043 Docket No. 50-423 ENCLOSURE I INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT REFUELING OUTAGE 14 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

MILLSTONE POWER STATION UNIT NO. 3 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 14 Revision 0 Contents:

OAR-1 Report Number: MP3-3R14 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:

ISI Program Owner, Independent Review Date:

,/9.-

Date:

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Auth~ed Nuc4 Inservi/e/tspecfione:

~PmnIniW Form OAR-I Owner's Activity Report Attcmn 1,

E-AA-II-0 Pag If D

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MilI.*tnne Nujr.Ipnr Power Station.

Rone Fern, Road. Waterford. Connecticut 06385 I*l II Millstone Nuclear Power Station Rone Ferrv Road Waterford Connecticut 06385 Unit No.

3 Commercial service date April 26, 1986 Refueling outage no.

14 (if applicable)

Current inspection interval 3rd Current inspection period 1st (1s', 2fl, 3ra, 4

, other)

(1st, 2 no, 3 rd)

Edition and Addenda of Section XI applicable to the inspection plans 2004 Edition, No Addenda Date and revision of inspection plans 05/23/11 Revision 2, Change 01-006 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, 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 3R14 conform to the requirements of Section XI.

(refueling outage number)

Signed y74%

x ISI Proqram Owner Date 01/18/2012 Owner 6r Owner's Designe,'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 CT 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 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 personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_z Commissions _

___Z_ ___ ____

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_/__-___

Ndtiotal Boartd, State, Pr6vince and Endorsements

ý? einionW Form OAR-1 Owner's Activity Report I

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Table 1: Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number F-A / F1.30D Pipe Support Incomplete thread engagement. The 3-SWP-6-PSST058 support condition has been evaluated by Engineering and found to be acceptable with the support performing its intended design function.

C-B / C2.31 Weld 03-073-005 Surface indication evaluated as acceptable in accordance with ASME Section X1, IWB 3514.

F-A I F1.20C Pipe Support Evaluation of support spring load setting.

3-FWS-1-PSSH017 The support condition has been evaluated by Engineering and found to be acceptable with the support performing its intended design function.

F-A I F1.20C Pipe Support Evaluation of support spring load setting.

3-FWS-1-PSSH005 The support condition has been evaluated by Engineering and found to be acceptable with the support performing its intended design function.

F-A I F1.20C Pipe Support Evaluation of support spring load setting 3-FWS-1-PSSHO11 and a loose lock nut at threaded rod to eye bolt connection. The support condition has been evaluated by Engineering and found to be acceptable with the support performing its intended design function. Loose lock nut tightened to restore support to its design condition.

F-A I F1.20C Pipe Support Evaluation of support spring load setting 3-FWS-1-PSSH023 and a loose lock nut at threaded rod to eye bolt connection. The support condition has been evaluated by Engineering and found to be acceptable with the support performing its intended design function. Loose lock nut tightened to restore support to its design condition.

B-A/ B1.40 Weld 101-101 Surface indication evaluated as acceptable in accordance with ASME Section XI, IWB 3514.

B-A/ B1.22 Weld 101-104D Subsurface indications evaluated as acceptable in accordance with ASME Section XI, IWB 3510.

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Form OAR-1 Owner's Activity Report I-tah et1 E-AA ISI-0 Pag 3

.f Table 1: Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number C-H / C7.10 Valve 3RHS*V8701A 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 (ETE-MP-2011-1098).

C-H I C7.10 Valve 3RHS*V8701C 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 (ETE-MP-2011-1098).

C-H I C7.10 Valve 3SIL*V987 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 (ETE-MP-2011-1099).

C-H / C7.10 Valve 3SIL*V017 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 (ETE-MP-2011-1099).

B-P I B15.10 Valve 3CHS*AV8149B 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 (ETE-MP-2011-1102).

B-P I B15.10 Valve 3CHS*AV8149C 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 (ETE-MP-2011-1102).

B-P 1 B15.10 Valve 3RCS*AV8037B 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 (ETE-MP-2011-1105).

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Form OAR-1 Owner's Activity Report I tahet1 E-AA ISI-0 Pag 4fT Table 1: Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number B-P / B15.10 Valve 3RCS*AV8037C 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 (ETE-MP-2011-1105).

B-P / B15.10 Valve 3RCS*MV8003A 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 (ETE-MP-2011-1105).

B-P I B15.10 Valve 3RCS*MV8003C 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 (ETE-MP-2011-1105).

C-H / C7.10 Heat Exchanger 3RSS*E1C 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 (ETE-MP-2011-1115).

C-H I C7.10 SFC Flange between Spools Evidence of leakage detected at bolted 3-SFC-520-2-3-3 and 3-connection. Evaluated in accordance SFC-520-5-3-3A with ASME Code Case N-566-2 and found to be acceptable for continued service (ETE-MP-2011-1058).

C-H I C7.10 Valve CHS*V297 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 (ETE-MP-2010-0003).

C-H I C7.10 Flow Element 3RHS*FE618 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 (ETE-MP-2011-1090).

C-H I C7.10 Valve RHS*HCV606 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 (ETE-MP-2011-1090).

C-H / C7.10 Restricting Orifice Evidence of leakage detected at bolted 3RSS*RO39A connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service (ETE-MP-2011-1065).

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Form OAR-1 Owner's Activity Report I

Atahet1 RA-SI0 Page 5

of6 Table 1: Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number C-H / C7.10 Valve 3RSS*MOV38A 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 (ETE-MP-2011-1065).

C-H I C7.10 Heat Exchanger 3RHS*E1A 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 (TE M3-EV-0016 Rev. 3).

C-H I C7.10 Heat Exchanger 3RHS*EIB 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 (TE M3-EV-0016 Rev. 3).

C-H / C7.10 Strainer 3SIH*STRT1 B Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued I service (ETE-MP-2011-1071).

Form OAR-1 Owner's Activity Report 25-Dorninionz Table 2: Abstract of RepairlReplacement Activities Required for Continued Service Code Class Item Description Description of Work Date RepairlReplacement Completed Plan Number Install mechanical 1

Steam Generator expansion tube plugs for 10/24/2011 53102204616 Plugs Steam Generator 3RCS*SG1A.

Weld restore the wall 2

Valve Body thickness of valve body 11/1/2011 53102211323 for 3FWS*FCV520.

Replace Service Water 3

4D Pipe Bend (SWP-4D-10/14/2011 53102335898 Pipe Spool 003-002) on line 3-SWP-003-210-2.

Replace Service Water 3

Pipe Spool pipe spool on line 1/20/2011 53102385728 3-SWP-002-146-3.

3 Valve Replace valve 9/27/2011 53102390508 3SWP*AOV39A Replace lateral piece No.

3 Pipe Spool 152 on line SWP-002-10/15/2011 53102403668 351-3.

Replace Service Water 1/27/2011 53102409766 3

Pipe Spool pipe spool on 3CCI*E1A 3

Valve Replace valve 10/28/2011 53102440496 3SWP*V699 3

Valve Replace valve 5/26/2011 53102440553 3SWP*V18 Replace Service Water 3

Pipe Spool pipe spool on line 3SWP-10/14/2011 53102465058 150-104-3.

Replace degraded 3

Fasteners fasteners - 3SWP*V663 -

10/23/2011 53102469542 Outlet Flange Repair spools 3SWP-20-2A (Inlet Flange) and 3

Pipe Flanges 3SWP-20-3 (Outlet 10/26/2011 53102471152 Flange) to remove corrosion damage.

2 Tank Repair through-wall leak 11/9/2011 53102479236 1

found on 3CHS*TK2