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| number = ML16033A471
| number = ML16033A471
| issue date = 01/22/2016
| issue date = 01/22/2016
| title = Millstone, Unit 2 - Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 23
| title = Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 23
| author name = Stanley B L
| author name = Stanley B
| author affiliation = Dominion Nuclear Connecticut, Inc
| author affiliation = Dominion Nuclear Connecticut, Inc
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:~DominionDominion Nuclear Connecticut, Inc.Rope Ferry Rd., Waterford, CT 06385Mailing Address: P.O. Box 128Waterford, CT 06385dora. cornJAN 2 2 2015U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, DC 20555Serial No.NSS&L/MLCDocket No.License No.16-005R050-336DPR-65DOMINION NUCLEAR CONNECTICUT. INC.MILLSTONE POWER STATION UNIT 2INSERVICE INSPECTION PROGRAM -OWNER'S ACTIVITY REPORT, REFUELINGOUTAGE 23Dominion Nuclear Connecticut, Inc. hereby submits the American Society of MechanicalEngineers (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
{{#Wiki_filter:Dominion Nuclear Connecticut, Inc.                             ~Dominion Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 dora. corn JAN 2 2 2015 U.S. Nuclear Regulatory Commission                          Serial No.      16-005 Attention: Document Control Desk                            NSS&L/MLC      R0 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 23 Dominion Nuclear Connecticut, Inc. hereby submits the American Society of Mechanical Engineers (AS ME), Section XI, Form OAR-I, Owner's Activity Report for the period from May 19, 2014 through Refueling Outage 23, completed on November 7, 2015, 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. Thomas Cleary at (860) 444-4377.
Sincerely, B. L. Stanley Director, Nuclear Station Safety and Licensing


==Enclosure:==
==Enclosure:==
: 1. Millstone Power Station Unit 2, Owner's Activity Report -Refueling Outage 23Commitments made in this letter: None.
: 1. Millstone Power Station Unit 2, Owner's Activity Report - Refueling Outage 23 Commitments made in this letter: None.
Serial No. 16-005Owner's Activity Report, 2R23Docket No. 50-336Page 2 of 2cc: U.S. Nuclear Regulatory CommissionRegion I2100 Renaissance BlvdSuite 100King of Prussia, PA 19406-2713R. V. GuzmanNRC Senior Project ManagerU.S. Nuclear Regulatory Commission, Mail Stop 08 C2One White Flint North11555 Rockville PikeRockville, MD 20852-2738NRC Senior Resident InspectorMillstone Power Station Serial No.Docket No.16-00550-336ENCLOSURE1IINSERVICE 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 ContinuedServicePrepared 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 CONFORMANCEI 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 01/05/2016SOwner or ..-......- .....CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectorsand 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 activitiesrepresented 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, concerningthe 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 EndorsementsDate 6O/.//. £Z-O/,,
Serial No. 16-005 Owner's Activity Report, 2R23 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 R. V. Guzman NRC Senior Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08 C2 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
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 DescriptionCategory and Item NumberF-A / F1 .30G Pipe Support 405633 Anchor bolt thread engagementevaluated by Engineering as acceptablefor continued service as documented inUIR MP2-15-001.F-A/ F1.20C Pipe Support 401021 Support spring load setting evaluated byEngineering as acceptable for continuedservice as documented in UIR MP2-15-002.F-A / Fl1.20B Pipe Support 401022 Support spring load setting evaluated byEngineering as acceptable for continuedservice 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 continuedservice 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 continuedservice as documented in UIR MP2-15-007.F-A/ Fl.20A Pipe Support 310021 Support strut barrel thread engagementevaluated by Engineering as acceptablefor 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 connectionevaluated in accordance with ASMECode Case N-566-2 as acceptable forcontinued service as documented inETE MP-2015-1103C-H / C7.10 Valve 2-SI-411 Evidence of leakage at bolted connectionevaluated 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 DescriptionCategory and Item NumberC-H / C7.10 Pump 2-SI-P41B Suction Evidence of leakage at bolted connectionFlange 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 connectionevaluated 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 RepairlReplacementCompleted 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 5310280195818"-EBD-8 at valve2-FW-5BReplace section of2Pipe Spool Feedwater piping on line 10/30/20 15 531028858931 8"-EBB-6 at valve________2-FW-5AReplace section of2 Pipe Spool ~~Feedwater piping on line 1/021 30842Pipe spool 18"-EBB-6 inside 1/021 30842containment
Serial No. 16-005 Docket No. 50-336 ENCLOSURE1I INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT REFUELING OUTAGE 23 MILLSTONE POWER STATION UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC.
~DominionDominion Nuclear Connecticut, Inc.Rope Ferry Rd., Waterford, CT 06385Mailing Address: P.O. Box 128Waterford, CT 06385dora. cornJAN 2 2 2015U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, DC 20555Serial No.NSS&L/MLCDocket No.License No.16-005R050-336DPR-65DOMINION NUCLEAR CONNECTICUT. INC.MILLSTONE POWER STATION UNIT 2INSERVICE INSPECTION PROGRAM -OWNER'S ACTIVITY REPORT, REFUELINGOUTAGE 23Dominion Nuclear Connecticut, Inc. hereby submits the American Society of MechanicalEngineers (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
 
MILLSTONE POWER STATION UNIT NO. 2 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 23 Revision 0 Contents:
OAR-i Renort Number: MP2-2R23 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:       / IS Progr* Owner                      Date: e' a     6, Reviewed By:                                              Date: eo,2, Independent Review Reviewed By:
Authorized Nuec1ir Inserviee .Inspector
 
Form OAR-I Owner's Activity Report n~ni                        A              -i.[*:,:1i  1     ,*_-' k    !-5[I                                       [ S1';i Report Number:_            MP2-2R23 Plant                      Millstone Nuclear Power Station.                     Rope Ferry Road, Waterford, Connecticut 06385 Unit No.       2                         Commercial service date                     12126/1975             Refueling outage no. 23 (if applicable)
Current inspection interval        4th
( 1 st, 2 nd, 3rd, 4 tf,   other)
Current inspection period          2nd (1st, 2nd, 3rd)
Edition and Addenda of Section Xl applicable to the inspection plans                               2004 Edition. No Addenda Date and revision of inspection plans                 06/15/i5 Revision 3. Chancqe 3-008 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-722-1. 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 Xl; and (c) the repair/replacement activities and evaluations supporting the completion of               2R23                             conform to the requirements of Section XI.
(refueling outage number)
Signed    k~                               *."**;*"7**,_.                  SI Proaram O~wner Date  01/05/2016 SOwner or Owner's*Designee*ftle"                        ..-......-           .....
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 and Insurance Company of Connecticut 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.
                  ,,--*.**"*Z,"
                        *.*--*fCommissions                                          A4,, **              6"r/R/-         ,,   z-- c'_:,
Inspect     s'*ignatu e "National                                                               Bo'ard, State, Province and Endorsements Date 6O/.//.         £Z-O/,,
 
Form OAR-I Owner's Activity Report m~nksn~
A        -       -       II                               .6~     S 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 .30G         Pipe Support 405633         Anchor bolt thread engagement evaluated by Engineering as acceptable for continued service as documented in UIR MP2-15-001.
F-A/ F1.20C           Pipe Support 401021         Support spring load setting evaluated by Engineering as acceptable for continued service as documented in UIR MP2                                                           002.
F-A / Fl1.20B         Pipe Support 401022         Support spring load setting evaluated by Engineering as acceptable for continued service as documented in UIR MP2                                                           003.
F-A / FlI.30A         Pipe Support 405875         Corrosion evaluated by Engineering as acceptable for continued service as documented in UIR MP2-15-004.
F F-A/ F.20A             Pipe Support 402116         Skewed base plate bolting evaluated by Engineering as acceptable for continued service as documented in UIR MP2                                                           005.
F-A / FI .40F         Pipe Support               Grout and coating degradation at support CAR-X-35A-1-S-B             base evaluated by Engineering as acceptable for continued service as documented in UIR MP2-15-006.
F-A/ F1.20C           Pipe Support 312009         Support spring load selling evaluated by Engineering as acceptable for continued service as documented in UIR MP2                                                           007.
F-A/ Fl.20A           Pipe Support 310021         Support strut barrel thread engagement evaluated by Engineering as acceptable for continued service. Support adjusted to restore to original design condition as documented in UIR MP2-15-008.
C-H / C7.10           Valve 2-SI-470             Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1103 C-H / C7.10           Valve 2-SI-411             Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-201 5-1103
 
In,*ioo,          Form OAR-I Owner's Activity Report 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             Pump 2-SI-P41B Suction     Evidence of leakage at bolted connection Flange                    evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1 103 C-H I C7.10           .Valve 2-SI-460             Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1153
 
                  .......               Form OAR-I Owner's Activity Report Table 2 Abstract of RepairlReplacement Activities Required for Continued Service Code Class       Item Description           Description of Work             Date       RepairlReplacement Completed            Plan Number Replace section of Feedwater piping on line 2                ~~~~~
Pipe Pipe Spool        18"-EBB-6.       Note: This activity was performed      0/821 0/821                   30721 30721 during previous outage 2R22. Ref. CR1010609.                   __________
Replace section of 3Pipe                    Spool       Service Water piping on     01/25/2015             53102808407
_____________                              ~~~line 3"-HUD-32____________
Replace pressure 3Valve                              retaining parts of Service   08/05/2015             53102864670
____________                          ~~Water valve 2-SW-i178B                   ___________
Replace section of 3Pipe                    Spool       Service Water piping on     08/07/2015             53102865581
_______________________                  line 2-1/2"-HUD-1 12 Replace section of 3Pipe                    Spool       Service Water piping on     10/17/2015             53102867864
__________  _____________               line 2-1/2"-HUD-1 12 Replace section of 2Pipe                    Spool       Feedwater piping on line     10/29/2015             53102801958 18"-EBD-8 at valve 2-FW-5B Replace section of 2Pipe                    Spool       Feedwater piping on line     10/30/20 15           53102885893 18"-EBB-6 at valve
________2-FW-5A Replace section of 2          Pipe Spool         ~~Feedwater piping on line     1/021                   30842 Pipe spool       18"-EBB-6 inside       1/021                   30842 containment
 
Dominion Nuclear Connecticut, Inc.                             ~Dominion Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 dora. corn JAN 2 2 2015 U.S. Nuclear Regulatory Commission                          Serial No.      16-005 Attention: Document Control Desk                            NSS&L/MLC      R0 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 23 Dominion Nuclear Connecticut, Inc. hereby submits the American Society of Mechanical Engineers (AS ME), Section XI, Form OAR-I, Owner's Activity Report for the period from May 19, 2014 through Refueling Outage 23, completed on November 7, 2015, 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. Thomas Cleary at (860) 444-4377.
Sincerely, B. L. Stanley Director, Nuclear Station Safety and Licensing


==Enclosure:==
==Enclosure:==
: 1. Millstone Power Station Unit 2, Owner's Activity Report -Refueling Outage 23Commitments made in this letter: None.
: 1. Millstone Power Station Unit 2, Owner's Activity Report - Refueling Outage 23 Commitments made in this letter: None.
Serial No. 16-005Owner's Activity Report, 2R23Docket No. 50-336Page 2 of 2cc: U.S. Nuclear Regulatory CommissionRegion I2100 Renaissance BlvdSuite 100King of Prussia, PA 19406-2713R. V. GuzmanNRC Senior Project ManagerU.S. Nuclear Regulatory Commission, Mail Stop 08 C2One White Flint North11555 Rockville PikeRockville, MD 20852-2738NRC Senior Resident InspectorMillstone Power Station Serial No.Docket No.16-00550-336ENCLOSURE1IINSERVICE 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 ContinuedServicePrepared 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 CONFORMANCEI 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 01/05/2016SOwner or ..-......- .....CERTIFICATE OF INSERVICE INSPECTIONI, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectorsand 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 activitiesrepresented 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, concerningthe 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 EndorsementsDate 6O/.//. £Z-O/,,
Serial No. 16-005 Owner's Activity Report, 2R23 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 R. V. Guzman NRC Senior Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08 C2 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
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 DescriptionCategory and Item NumberF-A / F1 .30G Pipe Support 405633 Anchor bolt thread engagementevaluated by Engineering as acceptablefor continued service as documented inUIR MP2-15-001.F-A/ F1.20C Pipe Support 401021 Support spring load setting evaluated byEngineering as acceptable for continuedservice as documented in UIR MP2-15-002.F-A / Fl1.20B Pipe Support 401022 Support spring load setting evaluated byEngineering as acceptable for continuedservice 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 continuedservice 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 continuedservice as documented in UIR MP2-15-007.F-A/ Fl.20A Pipe Support 310021 Support strut barrel thread engagementevaluated by Engineering as acceptablefor 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 connectionevaluated in accordance with ASMECode Case N-566-2 as acceptable forcontinued service as documented inETE MP-2015-1103C-H / C7.10 Valve 2-SI-411 Evidence of leakage at bolted connectionevaluated 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 DescriptionCategory and Item NumberC-H / C7.10 Pump 2-SI-P41B Suction Evidence of leakage at bolted connectionFlange 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 connectionevaluated 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 RepairlReplacementCompleted 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 5310280195818"-EBD-8 at valve2-FW-5BReplace section of2Pipe Spool Feedwater piping on line 10/30/20 15 531028858931 8"-EBB-6 at valve________2-FW-5AReplace section of2 Pipe Spool ~~Feedwater piping on line 1/021 30842Pipe spool 18"-EBB-6 inside 1/021 30842containment}}
Serial No. 16-005 Docket No. 50-336 ENCLOSURE1I INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT REFUELING OUTAGE 23 MILLSTONE POWER STATION UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC.
 
MILLSTONE POWER STATION UNIT NO. 2 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 23 Revision 0 Contents:
OAR-i Renort Number: MP2-2R23 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:       / IS Progr* Owner                      Date: e' a     6, Reviewed By:                                              Date: eo,2, Independent Review Reviewed By:
Authorized Nuec1ir Inserviee .Inspector
 
Form OAR-I Owner's Activity Report n~ni                        A              -i.[*:,:1i  1     ,*_-' k    !-5[I                                       [ S1';i Report Number:_            MP2-2R23 Plant                      Millstone Nuclear Power Station.                     Rope Ferry Road, Waterford, Connecticut 06385 Unit No.       2                         Commercial service date                     12126/1975             Refueling outage no. 23 (if applicable)
Current inspection interval        4th
( 1 st, 2 nd, 3rd, 4 tf,   other)
Current inspection period          2nd (1st, 2nd, 3rd)
Edition and Addenda of Section Xl applicable to the inspection plans                               2004 Edition. No Addenda Date and revision of inspection plans                 06/15/i5 Revision 3. Chancqe 3-008 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-722-1. 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 Xl; and (c) the repair/replacement activities and evaluations supporting the completion of               2R23                             conform to the requirements of Section XI.
(refueling outage number)
Signed    k~                               *."**;*"7**,_.                  SI Proaram O~wner Date  01/05/2016 SOwner or Owner's*Designee*ftle"                        ..-......-           .....
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 and Insurance Company of Connecticut 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.
                  ,,--*.**"*Z,"
                        *.*--*fCommissions                                          A4,, **              6"r/R/-         ,,   z-- c'_:,
Inspect     s'*ignatu e "National                                                               Bo'ard, State, Province and Endorsements Date 6O/.//.         £Z-O/,,
 
Form OAR-I Owner's Activity Report m~nksn~
A        -       -       II                               .6~     S 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 .30G         Pipe Support 405633         Anchor bolt thread engagement evaluated by Engineering as acceptable for continued service as documented in UIR MP2-15-001.
F-A/ F1.20C           Pipe Support 401021         Support spring load setting evaluated by Engineering as acceptable for continued service as documented in UIR MP2                                                           002.
F-A / Fl1.20B         Pipe Support 401022         Support spring load setting evaluated by Engineering as acceptable for continued service as documented in UIR MP2                                                           003.
F-A / FlI.30A         Pipe Support 405875         Corrosion evaluated by Engineering as acceptable for continued service as documented in UIR MP2-15-004.
F F-A/ F.20A             Pipe Support 402116         Skewed base plate bolting evaluated by Engineering as acceptable for continued service as documented in UIR MP2                                                           005.
F-A / FI .40F         Pipe Support               Grout and coating degradation at support CAR-X-35A-1-S-B             base evaluated by Engineering as acceptable for continued service as documented in UIR MP2-15-006.
F-A/ F1.20C           Pipe Support 312009         Support spring load selling evaluated by Engineering as acceptable for continued service as documented in UIR MP2                                                           007.
F-A/ Fl.20A           Pipe Support 310021         Support strut barrel thread engagement evaluated by Engineering as acceptable for continued service. Support adjusted to restore to original design condition as documented in UIR MP2-15-008.
C-H / C7.10           Valve 2-SI-470             Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1103 C-H / C7.10           Valve 2-SI-411             Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-201 5-1103
 
In,*ioo,          Form OAR-I Owner's Activity Report 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             Pump 2-SI-P41B Suction     Evidence of leakage at bolted connection Flange                    evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1 103 C-H I C7.10           .Valve 2-SI-460             Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1153
 
                  .......               Form OAR-I Owner's Activity Report Table 2 Abstract of RepairlReplacement Activities Required for Continued Service Code Class       Item Description           Description of Work             Date       RepairlReplacement Completed            Plan Number Replace section of Feedwater piping on line 2                ~~~~~
Pipe Pipe Spool        18"-EBB-6.       Note: This activity was performed      0/821 0/821                   30721 30721 during previous outage 2R22. Ref. CR1010609.                   __________
Replace section of 3Pipe                    Spool       Service Water piping on     01/25/2015             53102808407
_____________                              ~~~line 3"-HUD-32____________
Replace pressure 3Valve                              retaining parts of Service   08/05/2015             53102864670
____________                          ~~Water valve 2-SW-i178B                   ___________
Replace section of 3Pipe                    Spool       Service Water piping on     08/07/2015             53102865581
_______________________                  line 2-1/2"-HUD-1 12 Replace section of 3Pipe                    Spool       Service Water piping on     10/17/2015             53102867864
__________  _____________               line 2-1/2"-HUD-1 12 Replace section of 2Pipe                    Spool       Feedwater piping on line     10/29/2015             53102801958 18"-EBD-8 at valve 2-FW-5B Replace section of 2Pipe                    Spool       Feedwater piping on line     10/30/20 15           53102885893 18"-EBB-6 at valve
________2-FW-5A Replace section of 2          Pipe Spool         ~~Feedwater piping on line     1/021                   30842 Pipe spool       18"-EBB-6 inside       1/021                   30842 containment}}

Latest revision as of 02:12, 31 October 2019

Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 23
ML16033A471
Person / Time
Site: Millstone Dominion icon.png
Issue date: 01/22/2016
From: Stanley B
Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
16-005
Download: ML16033A471 (8)


Text

Dominion Nuclear Connecticut, Inc. ~Dominion Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 dora. corn JAN 2 2 2015 U.S. Nuclear Regulatory Commission Serial No.16-005 Attention: Document Control Desk NSS&L/MLC R0 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 23 Dominion Nuclear Connecticut, Inc. hereby submits the American Society of Mechanical Engineers (AS ME),Section XI, Form OAR-I, Owner's Activity Report for the period from May 19, 2014 through Refueling Outage 23, completed on November 7, 2015, 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. Thomas Cleary at (860) 444-4377.

Sincerely, B. L. Stanley Director, Nuclear Station Safety and Licensing

Enclosure:

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

Serial No.16-005 Owner's Activity Report, 2R23 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 R. V. Guzman NRC Senior Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08 C2 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.16-005 Docket No. 50-336 ENCLOSURE1I INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT REFUELING OUTAGE 23 MILLSTONE POWER STATION UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT NO. 2 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 23 Revision 0 Contents:

OAR-i Renort Number: MP2-2R23 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: / IS Progr* Owner Date: e' a 6, Reviewed By: Date: eo,2, Independent Review Reviewed By:

Authorized Nuec1ir Inserviee .Inspector

Form OAR-I Owner's Activity Report n~ni A -i.[*:,:1i 1 ,*_-' k  !-5[I [ S1';i Report Number:_ MP2-2R23 Plant Millstone Nuclear Power Station. Rope Ferry Road, Waterford, Connecticut 06385 Unit No. 2 Commercial service date 12126/1975 Refueling outage no. 23 (if applicable)

Current inspection interval 4th

( 1 st, 2 nd, 3rd, 4 tf, other)

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

Edition and Addenda of Section Xl applicable to the inspection plans 2004 Edition. No Addenda Date and revision of inspection plans 06/15/i5 Revision 3. Chancqe 3-008 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-722-1. 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 Xl; and (c) the repair/replacement activities and evaluations supporting the completion of 2R23 conform to the requirements of Section XI.

(refueling outage number)

Signed k~ *."**;*"7**,_. SI Proaram O~wner Date 01/05/2016 SOwner or Owner's*Designee*ftle" ..-......- .....

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 and Insurance Company of Connecticut 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.

,,--*.**"*Z,"

  • .*--*fCommissions A4,, ** 6"r/R/- ,, z-- c'_:,

Inspect s'*ignatu e "National Bo'ard, State, Province and Endorsements Date 6O/.//. £Z-O/,,

Form OAR-I Owner's Activity Report m~nksn~

A - - II .6~ S 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 .30G Pipe Support 405633 Anchor bolt thread engagement evaluated by Engineering as acceptable for continued service as documented in UIR MP2-15-001.

F-A/ F1.20C Pipe Support 401021 Support spring load setting evaluated by Engineering as acceptable for continued service as documented in UIR MP2 002.

F-A / Fl1.20B Pipe Support 401022 Support spring load setting evaluated by Engineering as acceptable for continued service as documented in UIR MP2 003.

F-A / FlI.30A Pipe Support 405875 Corrosion evaluated by Engineering as acceptable for continued service as documented in UIR MP2-15-004.

F F-A/ F.20A Pipe Support 402116 Skewed base plate bolting evaluated by Engineering as acceptable for continued service as documented in UIR MP2 005.

F-A / FI .40F Pipe Support Grout and coating degradation at support CAR-X-35A-1-S-B base evaluated by Engineering as acceptable for continued service as documented in UIR MP2-15-006.

F-A/ F1.20C Pipe Support 312009 Support spring load selling evaluated by Engineering as acceptable for continued service as documented in UIR MP2 007.

F-A/ Fl.20A Pipe Support 310021 Support strut barrel thread engagement evaluated by Engineering as acceptable for continued service. Support adjusted to restore to original design condition as documented in UIR MP2-15-008.

C-H / C7.10 Valve 2-SI-470 Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1103 C-H / C7.10 Valve 2-SI-411 Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-201 5-1103

In,*ioo, Form OAR-I Owner's Activity Report 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 Pump 2-SI-P41B Suction Evidence of leakage at bolted connection Flange evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1 103 C-H I C7.10 .Valve 2-SI-460 Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1153

....... Form OAR-I Owner's Activity Report Table 2 Abstract of RepairlReplacement Activities Required for Continued Service Code Class Item Description Description of Work Date RepairlReplacement Completed Plan Number Replace section of Feedwater piping on line 2 ~~~~~

Pipe Pipe Spool 18"-EBB-6. Note: This activity was performed 0/821 0/821 30721 30721 during previous outage 2R22. Ref. CR1010609. __________

Replace section of 3Pipe Spool Service Water piping on 01/25/2015 53102808407

_____________ ~~~line 3"-HUD-32____________

Replace pressure 3Valve retaining parts of Service 08/05/2015 53102864670

____________ ~~Water valve 2-SW-i178B ___________

Replace section of 3Pipe Spool Service Water piping on 08/07/2015 53102865581

_______________________ line 2-1/2"-HUD-1 12 Replace section of 3Pipe Spool Service Water piping on 10/17/2015 53102867864

__________ _____________ line 2-1/2"-HUD-1 12 Replace section of 2Pipe Spool Feedwater piping on line 10/29/2015 53102801958 18"-EBD-8 at valve 2-FW-5B Replace section of 2Pipe Spool Feedwater piping on line 10/30/20 15 53102885893 18"-EBB-6 at valve

________2-FW-5A Replace section of 2 Pipe Spool ~~Feedwater piping on line 1/021 30842 Pipe spool 18"-EBB-6 inside 1/021 30842 containment

Dominion Nuclear Connecticut, Inc. ~Dominion Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 dora. corn JAN 2 2 2015 U.S. Nuclear Regulatory Commission Serial No.16-005 Attention: Document Control Desk NSS&L/MLC R0 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 23 Dominion Nuclear Connecticut, Inc. hereby submits the American Society of Mechanical Engineers (AS ME),Section XI, Form OAR-I, Owner's Activity Report for the period from May 19, 2014 through Refueling Outage 23, completed on November 7, 2015, 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. Thomas Cleary at (860) 444-4377.

Sincerely, B. L. Stanley Director, Nuclear Station Safety and Licensing

Enclosure:

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

Serial No.16-005 Owner's Activity Report, 2R23 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 R. V. Guzman NRC Senior Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08 C2 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.16-005 Docket No. 50-336 ENCLOSURE1I INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT REFUELING OUTAGE 23 MILLSTONE POWER STATION UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT NO. 2 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 23 Revision 0 Contents:

OAR-i Renort Number: MP2-2R23 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: / IS Progr* Owner Date: e' a 6, Reviewed By: Date: eo,2, Independent Review Reviewed By:

Authorized Nuec1ir Inserviee .Inspector

Form OAR-I Owner's Activity Report n~ni A -i.[*:,:1i 1 ,*_-' k  !-5[I [ S1';i Report Number:_ MP2-2R23 Plant Millstone Nuclear Power Station. Rope Ferry Road, Waterford, Connecticut 06385 Unit No. 2 Commercial service date 12126/1975 Refueling outage no. 23 (if applicable)

Current inspection interval 4th

( 1 st, 2 nd, 3rd, 4 tf, other)

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

Edition and Addenda of Section Xl applicable to the inspection plans 2004 Edition. No Addenda Date and revision of inspection plans 06/15/i5 Revision 3. Chancqe 3-008 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-722-1. 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 Xl; and (c) the repair/replacement activities and evaluations supporting the completion of 2R23 conform to the requirements of Section XI.

(refueling outage number)

Signed k~ *."**;*"7**,_. SI Proaram O~wner Date 01/05/2016 SOwner or Owner's*Designee*ftle" ..-......- .....

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 and Insurance Company of Connecticut 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.

,,--*.**"*Z,"

  • .*--*fCommissions A4,, ** 6"r/R/- ,, z-- c'_:,

Inspect s'*ignatu e "National Bo'ard, State, Province and Endorsements Date 6O/.//. £Z-O/,,

Form OAR-I Owner's Activity Report m~nksn~

A - - II .6~ S 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 .30G Pipe Support 405633 Anchor bolt thread engagement evaluated by Engineering as acceptable for continued service as documented in UIR MP2-15-001.

F-A/ F1.20C Pipe Support 401021 Support spring load setting evaluated by Engineering as acceptable for continued service as documented in UIR MP2 002.

F-A / Fl1.20B Pipe Support 401022 Support spring load setting evaluated by Engineering as acceptable for continued service as documented in UIR MP2 003.

F-A / FlI.30A Pipe Support 405875 Corrosion evaluated by Engineering as acceptable for continued service as documented in UIR MP2-15-004.

F F-A/ F.20A Pipe Support 402116 Skewed base plate bolting evaluated by Engineering as acceptable for continued service as documented in UIR MP2 005.

F-A / FI .40F Pipe Support Grout and coating degradation at support CAR-X-35A-1-S-B base evaluated by Engineering as acceptable for continued service as documented in UIR MP2-15-006.

F-A/ F1.20C Pipe Support 312009 Support spring load selling evaluated by Engineering as acceptable for continued service as documented in UIR MP2 007.

F-A/ Fl.20A Pipe Support 310021 Support strut barrel thread engagement evaluated by Engineering as acceptable for continued service. Support adjusted to restore to original design condition as documented in UIR MP2-15-008.

C-H / C7.10 Valve 2-SI-470 Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1103 C-H / C7.10 Valve 2-SI-411 Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-201 5-1103

In,*ioo, Form OAR-I Owner's Activity Report 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 Pump 2-SI-P41B Suction Evidence of leakage at bolted connection Flange evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1 103 C-H I C7.10 .Valve 2-SI-460 Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1153

....... Form OAR-I Owner's Activity Report Table 2 Abstract of RepairlReplacement Activities Required for Continued Service Code Class Item Description Description of Work Date RepairlReplacement Completed Plan Number Replace section of Feedwater piping on line 2 ~~~~~

Pipe Pipe Spool 18"-EBB-6. Note: This activity was performed 0/821 0/821 30721 30721 during previous outage 2R22. Ref. CR1010609. __________

Replace section of 3Pipe Spool Service Water piping on 01/25/2015 53102808407

_____________ ~~~line 3"-HUD-32____________

Replace pressure 3Valve retaining parts of Service 08/05/2015 53102864670

____________ ~~Water valve 2-SW-i178B ___________

Replace section of 3Pipe Spool Service Water piping on 08/07/2015 53102865581

_______________________ line 2-1/2"-HUD-1 12 Replace section of 3Pipe Spool Service Water piping on 10/17/2015 53102867864

__________ _____________ line 2-1/2"-HUD-1 12 Replace section of 2Pipe Spool Feedwater piping on line 10/29/2015 53102801958 18"-EBD-8 at valve 2-FW-5B Replace section of 2Pipe Spool Feedwater piping on line 10/30/20 15 53102885893 18"-EBB-6 at valve

________2-FW-5A Replace section of 2 Pipe Spool ~~Feedwater piping on line 1/021 30842 Pipe spool 18"-EBB-6 inside 1/021 30842 containment