ML102150071

Inservice Inspection Program - Owner'S Activity Report

ML102150071
Person / Time
Site:	Millstone
Issue date:	07/25/2010
From:	Jordan A Dominion, Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
10-430, FOIA/PA-2011-0115
Download: ML102150071 (12)

Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station 9Dominion-Rope Ferry Road Waterford, CT 06385

,"JUL 2 5 2010 U.S. Nuclear Regulatory Commission Serial No.10-430 Attention: Document Control Desk NSSL/MLC RO Washington, DC 20555 Docket No. 50-423 License No. 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 November 25, 2008 through Refueling Outage 13, completed on May18,-2010 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, Site President - Millstone

Enclosure:

1. Inservice Inspection Program - Owners Activity Report, Refueling Outage 13.

Commitments made in this letter: None

Serial No.10-430 MPS3 Owner's Activity Report Docket No.'50-423 2 Page 2 of 2

,cc: VU.S. Nuclear RegulatoryCommission

'Region I

• 475 Allendale Road King of Prissia, PA-1.9406-14-15 C. J. Sanders

• Project Manager ý-lMillstqne PowerStation U.S. Nuclear Regulatory-Commission One White Flint North 1;1555 Rockville Pike Mail Stop O-8B3 Rockville, MD-20852V2738 NRC Senior Resident lnspector

,Millstone Power Station

Serial No.10-430 Docket No.'50-423 ENCLOSURE 1

,INSERVICE.INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT REFUELING OUTAGE .1.3 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

MILLSTONE POWER STATION UNIT NO. 3 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 13 Revision 0 Contents:

OAR-1 Report Number: MP3-3R13 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: o716 /,V ISI Progra, wner Reviewed By: Date: v7 1i71ZOID independent Review Reviewed By: Date: i Audo ze7d Nug ar Inservice Inspector

Form OAR-I Owner's Activity Report VftviniaW Afahet1 RAA4it Page 1 of8 Report Ih1. 1,mh RAD'IJJ-ID41 IN IIIIJEV18 I.

0l f Milktnnp Nizc~l~~ar PAwAr St~tiAn RAnA FAin, Road W~tArford ConnAr~ticIJt 0R385 Rone Ferrv Road Waterford Connecticut 06385 IU I Millstone Nuclear Power Station Unit No. 3 Commercial service date April 26,1986 Refueling outage no. 13 (if applicable)

Current inspection interval 3rd (1s', 2n 3 WA , other)

Current inspection period 1st (11$,2 n d,3 r)

Edition and Addenda of Section Xl applicable to the inspection plans 2004 Edition, No Addenda Date and revision of inspection plans 09/10/09 Revision 2. Change 1 Edition and Addenda of Section Xl applicable to repair/replacement activities, ifdifferent than the inspection plans N/A Code Cases used: N-460. N-532-4. N-566-2. N-722, N-729-1 (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 Xl; and (c) the repair/replacement activities and evaluations supporting the completion of 3R1 3 conform to the requirements of Section XI.

(refueling outage number)

Signed ISI Program Owner Date 07/07/2010 Owner& Owners D90'nee, 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 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 _ '7/. ,-,z"C Inspect InpD s Signa SgnJ, dre u /e Nadonal Board, State, Province and Endorsements

Form OAR-I Owner 'sA ti' ity Report 2FO~iniWr Attcm n 1,E- *6 ~ rd - PaeZSf8 Table I Items with Flaws orRelevantConditions That-Required Evaluation forContinued Service Examination Item Description ""Evaluation Description Category and Item Number C-F-2 /C5.51 Weld FW-S-1 1-FW-7-BM Linear surface indication, evaluated as acceptable in accordance with ASME

,__ _Section Xl, IWB 3514 (UIR MP3-10-002).

C-F-1 /C5.11 Weld SIL-504-FW-1 5 Linear surface indication, evaluated as acceptable in accordance withASME SectionXl, IWB.35,14 (,UIR MP3-10-003).

F-A / FI.20A 'Pipe support Spherical bearing partially dislodged.

3-*FWS-4-PSR064 The support condition has been evaluated by Engineering and .found to be acceptable with supportperforming its

'intended design function

'(UIR MP3-10-004).. Rework performed to reposition bearing to restore support

.back to original design condition.

F-A IFl .20A Pipe support 'Pipe clamp out of alignment with support S3--FWS-4-PSR0111 strut. The support condition has been evaluated by Engineering and found to be acceptable with support performing.its intended design function (UIR MP3-10-005). Rework.performed to ,realign clamp to restore support back to original design condition.

,tF-A/lFI.20A Pipe support Loose locking nut on strut assembly.

3-SIL-1-PSST493 The support condition has been evaluated by Engineering and found to be acceptable with support performing its intended design function (UIR.MP3 006). Rework performed to tighten locking nut to restore support back to

__original design condition.

F-A/F1.10C Pipe support Spring can setting outside its tolerance.

3-RCS-1-PSSH127 The support condition 'has been evaluated by Engineering and found to be acceptable with the spring can functioning within its working-range and design value (UIR MP3-10-007).

F-A / F1.20C Pipe support . Spring can setting outside its tolerance.

3-FWS-1-PSSH002 The support condition has been evaluated by Engineering and found to be acceptable with the spring can functioning within its working range and

• __ _ __ _ _ _ design

_ _ value (UIR MP3-10-008).-

Formý OAR-1 Owner's Activity Report DatninieW -

. I c AfahAet1 EAA SI Pa o'0' 3 of, Table 1 Items with Flaws or Relevant ConditionsThat.Required;Evaluation.forContinued Service Examination Item Description 'Evaluation ýDescription

-Category and Item Number F-A Fl.10A 'Pipe support. Spherical bushing partially dislodged and 3-RCS-1-PSR';68 looselocking nut on strut assembly. The

-support condition'has been eyaluated by Engineering and found to be acceptable with support performing its intended design function (UIR MP3-10-009).

Rework performed to tighten loose lock nut to restore support back to its original design condition.

C-H Cc7.10 Restricting orifice Evidence of leakage detected at bolted 3ýRSS*R039B1. connection. Evaluated in accordance with.ASMECode Case N-'566&2 and found to be acceptable for continued service (M3-EV-10-0021).

C-H /C7. 10 Valve'3SlH*AV8889A '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 (M3-EV-10-0022).

B-P I B15.10 Valve 3RCS*AVS036D 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 (M3-EV-10-0019).

B-P BI15.10 Valve .3RCS*V147 Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found tobe acceptable for continued

_ _ _service (M3-EV-1.0-0019).

B-P / B15.1.0 '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 (M3-EV-10-0019).

B-P / B15.10 *Valve 3SlL*V017 Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case NW566-2 and found to be acceptable for continued service (M3-EV-10-0019).

B-P/ B.15.10 Valve 3RCS*V026ý, Evidence of leakage detected at bolted cc-,nnection. Evaluated in accordance wi*h ASME Code Case 'N-566-2 and, found to.be acceptable for continued

"_ _service (M3-EV-10-0019).

Form OAR-1 Owner's Activity Report WManiniow Atdh 1 E-Agfb-i Pe-4 of 8

'Table -i Items with"Flaws-or Relevant Conditions ThatRequired .Evaluation for-Continued Service Examination :ltem"Description Evaluation Description

-Category and Item Number B-P / B15.10 Valve 3RCS*V031. Evidence of leakage detected at bolted

.connection. Evaluated in accordance with.,ASME Code Case N7566-2 and found to be acceptable for-continued service (M3-EV-10-0019).

B-P / B15.10 Valve 3RCS*MV8003A Evidence of leakage detected at bolted connection. Evaluated in accordance

'withASME Code Case'N-566-2 and found to be acceptable for continued service (M3-EV-10-0019).

B-P I B15.10 Valve 3RCS*MV80,3C Evidence of leakage detected at bolted connection. Evaluated in accqrdance withASME Code Case'N-566-2 and found to be acceptable for continued service (M3-EV-10-00,19).

C-H /C7.10 Valve 3SIL-V987 Evidence of leakage detected at bolted connection. Evaluated in accordance with.ASME Code CaseN-566-2 and found to be acceptable for continued service (M3-EV-1 0-0019).

B-P / B15.10 Valve 3SIL*V015 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 (M3-EV-10-0019).

B-P 1B15.10 Valve 3RHS*MV8701'A 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 (M3-EV-10-0019).

C-H / C7.10 'Valve 3SIL*V012 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.(M3-EV-1 0-0019).

C-H I C7.10 Valve 3SIL*V013 Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code CaseN-566-2 and found to be acceptable for continued

,__ __ __ service (I3-EV-10-0019).

B-P I B15.10 Valve 3RHS*MV8702B 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 (M3-EV-10-0019).

Form OAR-1 Owner's Activity Report PDm~inieWu A - - A' .~ 0 Table1 Items with Flaws or Relevant Conditions That Required -Evaluation. or ,oLtinied Service Examination Item Description Evaluation ,Description

.-Category and Item Number

.C-H I C7.10 '/alv6'3SIL*y006 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 (M3-EV-10-0019).

C-H / C7.10 Valve 3SIL*V007 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 (M3-EV-10-0019).

B-P /B15.10 Valve 3RCS*AV8037C Evidence of leakage detected at bolted connection. Evaluated in accordance with AsmME Code Case N-566-2,and found to be acceptable for continued service (M3-EV-10-0019).

B-P /.B135.10 Valve 3RCS*VI08 ..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 (M3-EV-10-0019).

B-P B1.5.10 Valve 3RCS*V102 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 (M3-EV-1 0-00,19).

B-P I B15.10 Valve&3RCS*AV8153 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 (M3-EV-10-0019.).

B-P /B15.10 Valve 3RCS*LC459 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 (M3-EV-10-0019).

C-H C7.10 Valve 3CHS*AV8146 Evidence of leakage detected atbolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable forcontinued

__service (M3-EV-10-0019).

C-H I C7.10 Valve 3CHS*AV8147 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 (M3-EV-10-0019).

Fcrm OAR-1 Owner's Activity Report pDallin-ior A'

A* -6 A'cr~nA,,E -- .; I a -6 8.

Table 1 Itemswith'Flaws or Relevant Conditions That RequiredEvaiuation for 'Continued Service Examination Item "Description Evaluation 'DezcrOption Category and Item Number C-H / C7.10 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 <M3-EV-1 0-0019).

B-P I B'I5.10 'Valve 3SIH*V887 Evidence of leakage detected at bolted connection. Evaluated in accordance

'with ASME Code Case N--566-2 and

-foundto be acceptable for continued service (M3-EV-1,0-00,19).

C-H/ C7. 1,0 Valve 3RHS*V021 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 (M3-EV-1 0-0008).

C-H./ 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 (M3-EV-10-0014).

C-H / 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 (M3-EV-05-0016 'Rev. 3).

C-H / C7. 10 'Heat exchanger 3RHS*EI 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 service (M3-EV-05-0016 Rev. 3).

C-H / C7.10 'Valve 3RHS*V029 ' 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 (M3-EV-05-001 3).

C-H / C7.10 Spectacle flange" Evidence of leakage detected at bolted 3RHS*FLS1iB . connection. Evaluated in accordance with ASME Code Case 'N-566-2 and found to be acceptable for continued service (M3-EV-10-0013).

C-H/ C7.10 Pump 3RHS*P1B Evidence of leakage detected at bolted I- , connection. Evaluated in accordance I,,with ASME Code Case NW566-2 and found to.be acceptable for continued service (M3-EV-10-0013).

Form OAR-1 Owner's Activity Report Table 2 Abstract of.Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Repair/Replacement Completed Plan Number 3 Pipe Spool Replace piping at the 04/19/2010 53102322014 CCE Heat Exchanger.

3 Pipe Spool Fabricate and install 10/28/2008 53M30517833 replacement inlet and outlet channel head (workcompleted

• *flanges for heat' during previous period)

____ __exchanger 3EGS*E2A. _

2 Valve 3CHS*CV8152 Replace. body to bonnet 02/27/2009 53102234037 fasteners on 3CHS*CV8152.

3 Pipe Spool ., Coatings and Cladding 03/21/2009 53102195579 repair of the Inlet/Outlet Channel Head Flange for Heat Exchanger

__ _3CCP*ElC.

3 . Pipe Spool Replace a.portion of line 03/26/2009 53102188990

__ _ _ _ _ _ 3-SWP-002-383-3. "

3 Valve 3SWP*V696 Replace~plug valve 03/28/2009 53102241929 3SWP*V696.

3 Valve 3SWP*V866 Replace flange bolting for 06/01/2009 53102203933 valve 3SWP*V866.

3 Valve 3SWP*V867 Replace Flange Bolting 06/01/2009 53102203934 for Valve 3SWP*V867.

3 Pipe Spool Replace brazed pipe line' 07/22/2009 '53102268587 3-SWP-003-101-3 with butt welds lAW DM3 0076-08.

3 Pump 3CCP*P1B Replacecasing studs'and 10/31/2009 53102292101 nuts on pump 3CCP*P1B.

,3 Pipe Spool -Replace a portion of Line 12/28/2009 53102313861 3-SWP-003-59-3 in the ESF building.

3, Pipe' Spool Replaceza portion on 01/19/2010 53102318157 3SWP-150-103-3(A-) due:

to a pinhole leak.

Valves Replace reactor head Valvesvent valves 1 3RCS*SV8095A and vent 5Aand 04/02/2010 53102334985 3RCS*SV8096A 3RCS*SV8095A and

.3RCS*SV8096A.

Replace a portion of line 3 Pipe Spool on 3SWP-150-61-3 and 04/18/2010 53102317914 3SWP-150-064-03(B-).

Rework / remove unacceptable surface 04/19/2010

.2 Pipe Spool indications located on line 53102341108 3-FWS-018-86-2.

Form OAR-I Own~er's NA-ivity Report I'm C ce- ct*

t,- f, a .E .*A4 Table 2 Abstract of.Repair/Repgacement Activities Required for Continued Service CodDate RepairIReplacement Codelass .ItemDescription Description. -of Work -Completed Plan Number 3 Pipe Spool Replace pipe on line 3-' 04/21/2010 53M30709070 3__ Pipe_Spool _ SWP-006-50-3.. -

Install replacement tube

.3 HeatrExchanger assembly in diesel

_3EGS*E1B generator intercooler heat 04/23/2010 53M30709271 exchanger 3EGS*E1 B.

Snubber 'Replace pivot pin on 2 3-MSS-1-PSSP0450 snubber for pipe support 04/25/2010 53102261,798 3-MSS-1-PSSP0450. __

Snubber -Replace snubber for pipe 3-RCS-1 -PSSP0928 support 3-RCS 04/28/2010 53102262076

___________ 3SPSSP0928.

Replace a portion of line .

• 3 Pipe Spool 3-SWP-150-72-3, Outlet 05/07/20,10 53102347647

_line from 3CCI*E1A. J _

Remove arc-strike on line 2 Pipe Spool 3-CHS-003-072-.2 lAW 05/08/2010 533102351290 CRIED CR380222.