ML16033A471

Millstone, Unit 2 - Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 23

ML16033A471
Person / Time
Site:	Millstone
Issue date:	01/22/2016
From:	Stanley B L Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
16-005
Download: ML16033A471 (8)

Text

~Dominion Dominion Nuclear Connecticut, Inc.Rope Ferry Rd., Waterford, CT 06385Mailing Address:

P.O. Box 128Waterford, CT 06385dora. cornJAN 2 2 2015U.S. Nuclear Regulatory Commission Attention:

Document Control DeskWashington, DC 20555Serial No.NSS&L/MLC Docket No.License No.16-005R050-336DPR-65DOMINION NUCLEAR CONNECTICUT.

INC.MILLSTONE POWER STATION UNIT 2INSERVICE INSPECTION PROGRAM -OWNER'S ACTIVITY REPORT, REFUELING OUTAGE 23Dominion Nuclear Connecticut, Inc. hereby submits the American Society of Mechanical Engineers (AS ME),Section XI, Form OAR-I, Owner's Activity Report for the periodfrom May 19, 2014 through Refueling Outage 23, completed on November 7, 2015, forMillstone Power Station Unit 2. The enclosure is in accordance with the requirements ofASME Code Case N-532-4.If you have any questions or require additional information, please contact Mr. ThomasCleary at (860) 444-4377.

Sincerely, B. L. StanleyDirector, Nuclear Station Safety and Licensing

Enclosure:

1. Millstone Power Station Unit 2, Owner's Activity Report -Refueling Outage 23Commitments made in this letter: None.

Serial No. 16-005Owner's Activity Report, 2R23Docket No. 50-336Page 2 of 2cc: U.S. Nuclear Regulatory Commission Region I2100 Renaissance BlvdSuite 100King of Prussia, PA 19406-2713 R. V. GuzmanNRC Senior Project ManagerU.S. Nuclear Regulatory Commission, Mail Stop 08 C2One White Flint North11555 Rockville PikeRockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Serial No.Docket No.16-00550-336ENCLOSURE1I INSERVICE INSPECTION PROGRAM -OWNER'S ACTIVITY REPORTREFUELING OUTAGE 23MILLSTONE POWER STATION UNIT 2DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATIONUNIT NO. 2OWNER'S ACTIVITY REPORTREFUELING OUTAGE 23Revision 0Contents:

OAR-i Renort Number: MP2-2R23Table 1: Items with Flaws or Relevant Conditions That RequiredEvaluation for Continued Service.Table 2: Abstract of Repairs/Replacement Activities Required for Continued ServicePrepared By:Reviewed By:Reviewed By:/ IS OwnerIndependent ReviewDate: e' a 6,Date: eo,2,Authorized Nuec1ir Inserviee

.Inspector n~niForm OAR-I Owner's Activity ReportA 1 !-5[I k [ S1';iReport Number:_MP2-2R23PlantMillstone Nuclear Power Station.

Rope Ferry Road, Waterford, Connecticut 06385Unit No. 2(if applicable)

Current inspection interval 4thCurrent inspection period 2ndCommercial service date 12126/1975 Refueling outage no. 23(1st, 2nd, 3rd, 4tf, other)(1st, 2nd, 3rd)Edition and Addenda of Section Xl applicable to the inspection plans 2004 Edition.

No AddendaDate and revision of inspection plans 06/15/i5 Revision

3. Chancqe 3-008Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plansN/ACode Cases used: N-460, N-532-4, N-566-2.

N-722-1.

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 Planas required by the ASME Code, Section Xl; and (c) the repair/replacement activities and evaluations supporting thecompletion of 2R23 conform to the requirements of Section XI.(refueling outage number)Signedk~

SI Proaram O~wnerDate 01/05/2016 SOwner or

..-......-

.....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 The Hartford Steam Boiler Inspection andInsurance Company of Connecticut of Hartford.

Connecticut have inspected the items described in this Owner'sActivity 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 hisemployer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from orconnected with this inspection.

A4,, 6"r/R/- ,, z-- c'_:,Inspect s' e "National Bo'ard, State, Province and Endorsements Date 6O/.//. £Z-O/,,

m~nksn~Form OAR-I Owner's Activity ReportA --II .6~ STable I Items with Flaws or Relevant Conditions That Required Evaluation for Continued ServiceExamination Item Description Evaluation Description Category and Item NumberF-A / F1 .30G Pipe Support 405633 Anchor bolt thread engagement evaluated by Engineering as acceptable for continued service as documented inUIR MP2-15-001.

F-A/ F1.20C Pipe Support 401021 Support spring load setting evaluated byEngineering as acceptable for continued service as documented in UIR MP2-15-002.F-A / Fl1.20B Pipe Support 401022 Support spring load setting evaluated byEngineering as acceptable for continued service as documented in UIR MP2-15-003.F-A / FlI.30A Pipe Support 405875 Corrosion evaluated by Engineering asacceptable for continued service asdocumented in UIR MP2-15-004.

F-A/ F F.20A Pipe Support 402116 Skewed base plate bolting evaluated byEngineering as acceptable for continued service as documented in UIR MP2-15-005.F-A / FI .40F Pipe Support Grout and coating degradation at supportCAR-X-35A-1-S-B base evaluated by Engineering asacceptable for continued service asdocumented in UIR MP2-15-006.

F-A/ F1.20C Pipe Support 312009 Support spring load selling evaluated byEngineering as acceptable for continued service as documented in UIR MP2-15-007.F-A/ Fl.20A Pipe Support 310021 Support strut barrel thread engagement evaluated by Engineering as acceptable for continued service.

Support adjustedto restore to original design condition asdocumented in UIR MP2-15-008.

C-H / C7.10 Valve 2-SI-470 Evidence of leakage at bolted connection evaluated in accordance with ASMECode Case N-566-2 as acceptable forcontinued service as documented inETE MP-2015-1103 C-H / C7.10 Valve 2-SI-411 Evidence of leakage at bolted connection evaluated in accordance with ASMECode Case N-566-2 as acceptable forcontinued service as documented in ETEMP-201 5-1103 Form OAR-I Owner's Activity ReportTable 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued ServiceExamination Item Description Evaluation Description Category and Item NumberC-H / C7.10 Pump 2-SI-P41B Suction Evidence of leakage at bolted connection Flange evaluated in accordance with ASMECode Case N-566-2 as acceptable forcontinued service as documented in ETEMP-2015-1 103C-H I C7.10 .Valve 2-SI-460 Evidence of leakage at bolted connection evaluated in accordance with ASMECode Case N-566-2 as acceptable forcontinued service as documented inETE MP-2015-1153

.......Form OAR-I Owner's Activity ReportTable 2 Abstract of RepairlReplacement Activities Required for Continued ServiceCode Class Item Description Description of Work Date RepairlReplacement Completed Plan NumberReplace section ofFeedwater piping on line2 Pipe ~~~~~ 18"-EBB-6.

Note: This 0/821 30721Pipe Spool activity was performed 0/821 30721during previous outage2R22. Ref. CR1010609.

__________

Replace section of3Pipe Spool Service Water piping on 01/25/2015 53102808407

_____________

~~~line 3"-HUD-32____________

Replace pressure3Valve retaining parts of Service 08/05/2015 53102864670

____________

~~Water valve 2-SW-i178B

___________

Replace section of3Pipe Spool Service Water piping on 08/07/2015 53102865581

__________

_____________

line 2-1/2"-HUD-1 12Replace section of3Pipe Spool Service Water piping on 10/17/2015 53102867864

__________

_____________

line 2-1/2"-HUD-1 12Replace section of2Pipe Spool Feedwater piping on line 10/29/2015 53102801958 18"-EBD-8 at valve2-FW-5BReplace section of2Pipe Spool Feedwater piping on line 10/30/20 15 53102885893 1 8"-EBB-6 at valve________2-FW-5A Replace section of2 Pipe Spool ~~Feedwater piping on line 1/021 30842Pipe spool 18"-EBB-6 inside 1/021 30842containment

~Dominion Dominion Nuclear Connecticut, Inc.Rope Ferry Rd., Waterford, CT 06385Mailing Address:

P.O. Box 128Waterford, CT 06385dora. cornJAN 2 2 2015U.S. Nuclear Regulatory Commission Attention:

Document Control DeskWashington, DC 20555Serial No.NSS&L/MLC Docket No.License No.16-005R050-336DPR-65DOMINION NUCLEAR CONNECTICUT.

INC.MILLSTONE POWER STATION UNIT 2INSERVICE INSPECTION PROGRAM -OWNER'S ACTIVITY REPORT, REFUELING OUTAGE 23Dominion Nuclear Connecticut, Inc. hereby submits the American Society of Mechanical Engineers (AS ME),Section XI, Form OAR-I, Owner's Activity Report for the periodfrom May 19, 2014 through Refueling Outage 23, completed on November 7, 2015, forMillstone Power Station Unit 2. The enclosure is in accordance with the requirements ofASME Code Case N-532-4.If you have any questions or require additional information, please contact Mr. ThomasCleary at (860) 444-4377.

Sincerely, B. L. StanleyDirector, Nuclear Station Safety and Licensing

Enclosure:

1. Millstone Power Station Unit 2, Owner's Activity Report -Refueling Outage 23Commitments made in this letter: None.

Serial No. 16-005Owner's Activity Report, 2R23Docket No. 50-336Page 2 of 2cc: U.S. Nuclear Regulatory Commission Region I2100 Renaissance BlvdSuite 100King of Prussia, PA 19406-2713 R. V. GuzmanNRC Senior Project ManagerU.S. Nuclear Regulatory Commission, Mail Stop 08 C2One White Flint North11555 Rockville PikeRockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Serial No.Docket No.16-00550-336ENCLOSURE1I INSERVICE INSPECTION PROGRAM -OWNER'S ACTIVITY REPORTREFUELING OUTAGE 23MILLSTONE POWER STATION UNIT 2DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATIONUNIT NO. 2OWNER'S ACTIVITY REPORTREFUELING OUTAGE 23Revision 0Contents:

OAR-i Renort Number: MP2-2R23Table 1: Items with Flaws or Relevant Conditions That RequiredEvaluation for Continued Service.Table 2: Abstract of Repairs/Replacement Activities Required for Continued ServicePrepared By:Reviewed By:Reviewed By:/ IS OwnerIndependent ReviewDate: e' a 6,Date: eo,2,Authorized Nuec1ir Inserviee

.Inspector n~niForm OAR-I Owner's Activity ReportA 1 !-5[I k [ S1';iReport Number:_MP2-2R23PlantMillstone Nuclear Power Station.

Rope Ferry Road, Waterford, Connecticut 06385Unit No. 2(if applicable)

Current inspection interval 4thCurrent inspection period 2ndCommercial service date 12126/1975 Refueling outage no. 23(1st, 2nd, 3rd, 4tf, other)(1st, 2nd, 3rd)Edition and Addenda of Section Xl applicable to the inspection plans 2004 Edition.

No AddendaDate and revision of inspection plans 06/15/i5 Revision

3. Chancqe 3-008Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plansN/ACode Cases used: N-460, N-532-4, N-566-2.

N-722-1.

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 Planas required by the ASME Code, Section Xl; and (c) the repair/replacement activities and evaluations supporting thecompletion of 2R23 conform to the requirements of Section XI.(refueling outage number)Signedk~

SI Proaram O~wnerDate 01/05/2016 SOwner or

..-......-

.....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 The Hartford Steam Boiler Inspection andInsurance Company of Connecticut of Hartford.

Connecticut have inspected the items described in this Owner'sActivity 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 hisemployer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from orconnected with this inspection.

A4,, 6"r/R/- ,, z-- c'_:,Inspect s' e "National Bo'ard, State, Province and Endorsements Date 6O/.//. £Z-O/,,

m~nksn~Form OAR-I Owner's Activity ReportA --II .6~ STable I Items with Flaws or Relevant Conditions That Required Evaluation for Continued ServiceExamination Item Description Evaluation Description Category and Item NumberF-A / F1 .30G Pipe Support 405633 Anchor bolt thread engagement evaluated by Engineering as acceptable for continued service as documented inUIR MP2-15-001.

F-A/ F1.20C Pipe Support 401021 Support spring load setting evaluated byEngineering as acceptable for continued service as documented in UIR MP2-15-002.F-A / Fl1.20B Pipe Support 401022 Support spring load setting evaluated byEngineering as acceptable for continued service as documented in UIR MP2-15-003.F-A / FlI.30A Pipe Support 405875 Corrosion evaluated by Engineering asacceptable for continued service asdocumented in UIR MP2-15-004.

F-A/ F F.20A Pipe Support 402116 Skewed base plate bolting evaluated byEngineering as acceptable for continued service as documented in UIR MP2-15-005.F-A / FI .40F Pipe Support Grout and coating degradation at supportCAR-X-35A-1-S-B base evaluated by Engineering asacceptable for continued service asdocumented in UIR MP2-15-006.

F-A/ F1.20C Pipe Support 312009 Support spring load selling evaluated byEngineering as acceptable for continued service as documented in UIR MP2-15-007.F-A/ Fl.20A Pipe Support 310021 Support strut barrel thread engagement evaluated by Engineering as acceptable for continued service.

Support adjustedto restore to original design condition asdocumented in UIR MP2-15-008.

C-H / C7.10 Valve 2-SI-470 Evidence of leakage at bolted connection evaluated in accordance with ASMECode Case N-566-2 as acceptable forcontinued service as documented inETE MP-2015-1103 C-H / C7.10 Valve 2-SI-411 Evidence of leakage at bolted connection evaluated in accordance with ASMECode Case N-566-2 as acceptable forcontinued service as documented in ETEMP-201 5-1103 Form OAR-I Owner's Activity ReportTable 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued ServiceExamination Item Description Evaluation Description Category and Item NumberC-H / C7.10 Pump 2-SI-P41B Suction Evidence of leakage at bolted connection Flange evaluated in accordance with ASMECode Case N-566-2 as acceptable forcontinued service as documented in ETEMP-2015-1 103C-H I C7.10 .Valve 2-SI-460 Evidence of leakage at bolted connection evaluated in accordance with ASMECode Case N-566-2 as acceptable forcontinued service as documented inETE MP-2015-1153

.......Form OAR-I Owner's Activity ReportTable 2 Abstract of RepairlReplacement Activities Required for Continued ServiceCode Class Item Description Description of Work Date RepairlReplacement Completed Plan NumberReplace section ofFeedwater piping on line2 Pipe ~~~~~ 18"-EBB-6.

Note: This 0/821 30721Pipe Spool activity was performed 0/821 30721during previous outage2R22. Ref. CR1010609.

__________

Replace section of3Pipe Spool Service Water piping on 01/25/2015 53102808407

_____________

~~~line 3"-HUD-32____________

Replace pressure3Valve retaining parts of Service 08/05/2015 53102864670

____________

~~Water valve 2-SW-i178B

___________

Replace section of3Pipe Spool Service Water piping on 08/07/2015 53102865581

__________

_____________

line 2-1/2"-HUD-1 12Replace section of3Pipe Spool Service Water piping on 10/17/2015 53102867864

__________

_____________

line 2-1/2"-HUD-1 12Replace section of2Pipe Spool Feedwater piping on line 10/29/2015 53102801958 18"-EBD-8 at valve2-FW-5BReplace section of2Pipe Spool Feedwater piping on line 10/30/20 15 53102885893 1 8"-EBB-6 at valve________2-FW-5A Replace section of2 Pipe Spool ~~Feedwater piping on line 1/021 30842Pipe spool 18"-EBB-6 inside 1/021 30842containment