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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 13: Line 13:
| document type = Inservice/Preservice Inspection and Test Report, Letter
| document type = Inservice/Preservice Inspection and Test Report, Letter
| page count = 8
| page count = 8
| revision = 0
}}
}}
=Text=
{{#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:==
: 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}}

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