ML13045A486

Inservice Inspection Program-Owner's Activity Report, Refueling Outage 21

ML13045A486
Person / Time
Site:	Millstone
Issue date:	02/05/2013
From:	Macmanus R Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
13-069
Download: ML13045A486 (8)

Text

Dominion Nuclear Connecticut,AInc. ODominion-Millstone Power Station Rope Ferry Road Waterford, CT 06385 FEB 5 2013 U.S. Nuclear Regulatory Commission Serial No. "13-069 Attention: Document Control Desk NSS&L/MLC RO Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT, REFUELING OUTAGE 21 Dominion Nuclear Connecticut, Inc. hereby submits the American Society of Mechanical Engineers (ASME),Section XI, Form OAR-i, Owner's Activity Report for the period from May 4, 2011 through Refueling Outage 21, completed on November 23, 2012, for Millstone Power Station Unit 2. 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 D. Bartron at (860) 444-4301.

Sincerely, R. K. MacManus Director, Nuclear Station Safety and Licensing

Enclosure:

1. Millstone Power Station Unit 2, Owner's Activity Report - Refueling Outage 21 Commitments made in this letter: None.

Serial No.13-069 Owner's Activity Report, 2R21 Docket No. 50-336 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 J. S. Kim Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2A Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.13-069 Docket No. 50-336 ENCLOSUREI INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT REFUELING OUTAGE 21 MILLSTONE POWER STATION UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT NO. 2 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 21 Revision 0 Contents:

OAR-1 Report Number: MP2-2R21 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: Date: //7/.0t3

.ISdPr-ogram Oer Reviewed By: Date: l4lzova Independent Review Reviewed By:

Authý NU zed r Inservice In~spetor/ "-

Form OAR-1 Owner's Activity Report Dominion et

_Uýtahen I E~AMS-0 A Report-Number:. MP2-2R21 Plant Millstone Nuclear Power Station RoDe Ferry Road. Waterford. Connecticut 06385 Unit No. 2 Commercial service date 12/26/1975 Refueling outage no. 21 (if applicable)

Current inspection interval 4th (Ist, 2na, 3ra, 4tn, other)

Current inspection period 1st (1st, 2nd, 3rd)

Edition and Addenda of Section Xl applicable to the inspection plans 2004 Edition, No Addenda Date and revision of inspection plans 06/11/12 Revision 3, Chanqe 2-002 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-586-1, 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 2R21 conform to the requirements of Section Xl.

(refueling outage number)

SignedOwne orOwnr ee Title ISI Proqram Owner Date 01/08/2013 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.

Commissions .,i4*19r'*' t/7".,- .4,tiC Inspe or's Sign re NafionafBoard, State, Province and Endorsements Date*.,*,LZ-* /* /--

Form OAR-1 Owner's Activity Report

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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/ F1.10 Pipe Support 491412 Support member corrosion evaluated by Engineering as acceptable. for continued service.

F-A/ F1.10 Pipe Support 410060 Bolting thread engagement evaluated by Engineering as acceptable! for continued service F-A/ F1.20 Pipe Support 402077 Support base plate gap evaluated by Engineering as acceptable for continued service B-P / B15.215 Weld P-4-C-1 Staining at weld area evaluated by Engineering for leakage. Staining determined to be caused by historical pump seal leakage with weld found to be acceptable for continued service.

B-P / B15.10 Pump M2-P40A Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

B-P / B15.10 Pump M2-P40C Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

C-H / C7.10 Valve 2-CH-1 18 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

C-H / C7.10 Valve 2-CH-322 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

C-H / C7.10 Valve 2-SI-411 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

C-H / C7.10 Valve 2-SI-435 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

C-H / C7.10 Valve 2-SI-458 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

C-H / C7.10 Valve 2-SI-615 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

Form OAR-1 Owner's Activity Report Atahet1 E~A- SI-003o4 Examination Item Description Evaluation Description Category and Item Number C-H / C7.10 Valve 2-SI-625 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

C-H / C7.10 Valve 2-SI-635 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

C-H I C7.10 Valve 2-SI-645 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

D-B D 02.10 Valve 2-RW-4B Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

D-B I D2.10 Valve 2-RW-5A Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

D-B / D2.10 Valve 2-RW-14 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

D-B / D2.10 Valve 2-RW-16 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

D-B / D2.10 Valve 2-RW-65 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.

Form OAR-1 Owner's Activity Report Atchm** t 1, ER-AA-IS[-10.0 4o Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Repair/Replacement Completed Plan Number Replace flange downstream of Service 3

Pipe Flange Water valve 2-SW-1 79A 02/2/12 53102372585 on line 3"-HUD-130 Replace degraded section of 24-inch Service 3Pipe Spool Water line JGD-6, piping 12/20/11 53102477243 spool SK-912.

Weld repair 24-inch Service Water line JGD-Pipe Spool 6, piping spools SK-912, 12/22/11 53102485522 SK-913, and SK-913A 1 Valve Replace Reactor Coolant 11/5/12 53102295113 valve 2-RC-037B.

Replace section of 3 Pipe Spool Service Water line, piping 9/12/12 53102555638 spool SK-4256A.

Replace Containment 1 Valve Spray valve 11/7/12 53102437234 2-RC-252.

Replace Containment 1 Valve Spray valve 11/7/12 53102443647 2-RC-253.

Replace flange on 6-inch 3 Pipe Flange Service Water line, piping 10/8/12 53102562516 spoolP18. I