ML11207A464
| ML11207A464 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 07/18/2011 |
| From: | Macmanus R Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 11-396 | |
| Download: ML11207A464 (8) | |
Text
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@mini@w Dominion Nuclear Connecticut, Inc.
Millstone Power Station Rope Ferry Road Waterford, CT 06385 JUL 18 2011 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.
NSS&L/MLC Docket No.
License No.11-396 RO 50-336 DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT, REFUELING OUTAGE 20 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 November 19, 2009 through Refueling Outage 20, completed on May 3,2011, 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.
Very truly yours, R. K. MacManus Director, Nuclear Station Safety and Licensing
Enclosure:
- 1. Millstone Power Station Unit 2, Owner's Activity Report - Refueling Outage 20 Commitments made in this letter: None.
43(0(47
Serial No.11-396 Owner's Activity Report, 2R20 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 U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08B3 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No.
Docket No.11-396 50-336 ENCLOSURE1 INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT REFUELING OUTAGE 20 MILLSTONE POWER STATION UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT NO. 2 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 20 Revision 0 Contents:
OAR-1 Report Number: MP2-2R20 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:
ISfProgram OW9%f Independent Review Auth zed-Nucl&r Inservice inSpetor Date:
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Date:
"7tS*2.oII Date: vZ'//gQr-
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InIkk WDOMiniW Form OAR-1 Owner's Activity Report IAttcmn 1,
E-AA-S-0 Page 1
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rf. KI' knHa KAD'I 9WN1 DIoII Mill~tnnA NIu'~lA~ar Pnw~r ~t~tinn Rnn~ FAin, Rn~rI W~tArfArd flnnnA~tk'It flR~RF~
I Millstone Nuclear Power Station Rnnp Ferrv Road Waterford Connecticut 06385 Unit No.
2 Commercial service date 12/26/1975 Refueling outage no.
20 (if applicable)
Current inspection interval 4th Current inspection period 1st (1$', 2fno 3,T 4m, other)
(I st 2 no, 3rd)
Edition and Addenda of Section Xl applicable to the inspection plans 2004 Edition, No Addenda Date and revision of inspection plans 06/10/10 Revision 3.
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 (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 Xl; and (c) the repair/replacement activities and evaluations supporting the completion of 2R20 conform to the requirements of Section Xl.
(refueling outage number)
Signed ISI Program Owner Date 07/05/2011 Owner orOwners De~ heeTit e 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 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.
.,--r Commissions
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7-/A7, Inspep.trs Sigpatfure Naf'ona( Board, State, Provin ce and Endorsements Date
IC'77 Form OAR-1 Owner's Activity Report Atahmn 1,t-A-S1 00 Pag
- 2.
f Table I Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number F-A / F1.30 Pipe Support 329020 Support member corrosion evaluated by Engineering as acceptable for continued service.
F-A / F1.30 Pipe Support 329020A Support member corrosion evaluated by
.Engineering as acceptable for continued service.
F-A / F1.30 Pipe Support 329048 Support member corrosion evaluated by Engineering as acceptable for continued service.
F-A / F1.20 Pipe Support 304029 Bolting thread engagement evaluated by Engineering as acceptable for continued service.
F-A / F1.30 Pipe Support 427110 Separation gap between support wall plate and wall evaluated by Engineering as acceptable for continued service.
F-A / F1.20 Pipe Support 301126 Spring can setting evaluated by Engineering as acceptable for continued service.
F-A / F1.10 Pipe Support 408014 Spring can setting evaluated by Engineering as acceptable for continued service.
F-A/ F1.10 Pipe Support 408017D Spring can setting and bolting thread engagement evaluated by Engineering as acceptable for continued service.
B-G-2 / B7.70 Valve 2-SI-245 Bolting Minor bolting thread damage evaluated by Engineering as acceptable for continued service.
F-A/ F1.20 Pipe Support 312012 Spring can setting evaluated by Engineering as acceptable for continued service.
C-H / C7.10 Valve 2-CH-192 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-CS-091 Evidence of leakage at bolted connection evaluated in accordance with Code Case N-566-2 as acceptable for continued service.
B-P I B15.10 Valve 2-RC-35A 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-073 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 Attachent 1,ER-AA.I[S 0 0*
3 of 4 Examination Item Description Evaluation Description Category and Item Number 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-432 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-434 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 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.
C-H I C7.10 SDC heat exchanger X23A Evidence of leakage at bolted connection channel head cover evaluated in accordance with Code Case N-566-2 as acceptable for continued service.
Form OAR-1 Owner's Activity Report Attc 1
I Pe 4
Table 2 Abstract of Repair/Replacement Activities Required forContinued Service Code Class Item Description Description of Work Date Repair/Replacement Completed Plan Number Replace section of line 3
PipeSpool Y3"-HUD-130 between 2-0811/2010
'53M20808003 Pipe Spool SW-1 78A and,2-SW-179A.
Replace a section of inlet 3 Pipe Spool piping M2X183 due to erosion at elbow, 2"-
07/29/2010 53102186593 HUD-113.
Weld repair the 3
Pipe Flange degraded outlet flange 10/28/2009 53102292843 on spool SK-4256A.
3 Pipe Spool Replace portion of line 04/08/2011 53102358019 4"-EBD (B)-25.
Fabricate and install 3
Pipe Spool
- cooling piping for P40CM 04/26/2011 53M208051335 replacement motor.
"Fabricate replacement pipe spool SK-3650 for 3
Pipe Spool line 8-inch JGD-7 lAW 01/05/2011 53102403014 DCN MP2-10-01196-000.
1 Valves Replace drain valves 2-04/13/2011 53102288546 SI-024A and 2-SI-024B.
Rework corroded areas 3
Pipe Spool on spools for line 6-inch 04/15/2011 53102187069 JGD-4 per attachment 8 of CM-AA-NWP-101.
Pipe support M2HGR-2 Support 412016 - Remove 04/23/2011 53102429523 indications found by an ISI examination.
Replace 2 X 3/4-inch 3
reducing bushing on 04/24/2011 53102432023 Pipe Fitting X18A upstream of valve 2-SW-92A.
Replace section of line 3
PipeSpool 3"-HUD-130 between 2-08/11/2010 53M20808003 Pipe Spool SW-1 78A and 2-SW-179A.
Replace a section of inlet 3
Pipe Spool piping M2X183 due to erosion at elbow, 2"-
07/29/2010
-53102186593 HUD-113.
Weld repair the 3
Pipe Flange degraded outlet flange 10/28/2009 53102292843 on spool SK-4256A.
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