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| number = ML13233A318
| number = ML13233A318
| issue date = 08/01/2013
| issue date = 08/01/2013
| title = Millstone, Unit 3 - Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 15
| title = Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 15
| author name = Scace S E
| author name = Scace S
| author affiliation = Dominion, Dominion Nuclear Connecticut, Inc
| author affiliation = Dominion, Dominion Nuclear Connecticut, Inc
| addressee name =  
| addressee name =  
Line 14: Line 14:
| page count = 9
| page count = 9
}}
}}
=Text=
{{#Wiki_filter:Dominion Nuclear Connecticut, Inc.
Millstone Power Station
                                                                    ~Dominioni Rope Ferry Road, Waterford, CT 06385 AUG 1 213 U.S. Nuclear Regulatory Commission                            Serial No. 13-421 Attention: Document Control Desk                              NSSL/MLC RO Washington, DC 20555                                          Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT, REFUELING OUTAGE 15 Dominion Nuclear Connecticut, Inc. (DNC) hereby submits the American Society of Mechanical Engineers (ASME), Section XI, Form OAR-I, Owner's Activity Report, for the period from November 24, 2011 through Refueling Outage 15, completed on May 19, 2013 for Millstone Power Station Unit 3. The enclosure is in accordance with the requirements of ASME Code Case N-532-4.
If you have any questions or require additional information, please contact William D. Bartron at (860) 444-4301.
Sincerely, Site Vice President - Millstone
==Enclosure:==
: 1. Owner's Activity Report, Refueling Outage 15, Revision 0.
Commitments made in this letter: None AU-17
Serial No. 13-421 MPS3 Owner's Activity Report Docket No. 50-423 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 James S. Kim Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No. 13-421 Docket No. 50-423 ENCLOSURE 1 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 15 Revision 0 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
MILLSTONE POWER STATION UNIT NO. 3 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 15 Revision 0 Contents:
OAR-1 Report Number: MP3-3R15 Table 1: Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service.
Table 2: Abstract of Repairs/Replacement Activities Required for Continued Service Prepared By:                                            Date: 7/P/1/7 1§1 Prograw  wner Reviewed By:                                            Date:
Independent Review Reviewed By:                                            Date:
Autýhd NfucleInservice Inspection
I Form OAR-1 Owner's Activity Report W-DominioW I-tah        et1        E-AA          ISI10                              Page  1*f5' Report Numb er:              MP3-3R15 er:
Plant                      Millstone Power Station.          Rope Fernr Road. Waterford. Connecticut 06385 Unit No.        3                        Commercial service date              April 26, 1986        Refueling outage no. 15 (if applicable)
Current inspection interval          3rd (1 st, 2 d, 3 rd, 4 t , other)
Current inspection period            2nd (1st, 2nd,  3  rd)
Edition and Addenda of Section XI applicable to the inspection plans                        2004 Edition, No Addenda Date and revision of inspection plans                03/27/2013 Revision 2. Chanqe 02-004 Edition and Addenda of Section Xl 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-729-1. 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 XI; and (c) the repair/replacement activities and evaluations supporting the completion of                3R15                          conform to the requirements of Section Xl.
(refueling outage number)
Signed                            7                                    ISI Program Owner                      Date 07/08/2013 Owner or Ownertiesignee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of                Connecticut                  and employed by HSB CT                  of Hartford, Connecticut                  have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
__________________Commissions                                              A,,*9,*,/        rVA*//,4'        Z ,1-.ZC Naiional Board, State, Prgvince and Endorsements
Form OAR-1 Owner's Activity Report
  ,Dominion'                I-tah      et1      E-AA-    SI-0                            Page  2.f5' Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination                    Item Description                    Evaluation Description Category and Item Number C-C / C3.10                RHR Heat Exchanger          Surface indication, evaluated as Lower Shell to Skirt Weld    acceptable in accordance with ASME 03-073-009          Section XI, IWB 3514.
F-A / F1 .1A                      Pipe Support          Support strut could not be rotated by hand 3-RCS-1-PSR33            to verify freedom of motion. The support condition has been evaluated by Engineering and found to be acceptable with the support performing its intended design function.
F-A/ F1.10A                        Pipe Support          Support strut could not be rotated by hand 3-RCS-1-PSR40            to verify freedom of motion. The support condition has been evaluated by Engineering and found to be acceptable with the support performing its intended design function.
F-A / F .1OC                      Pipe Support          Evaluation of support spring load setting.
3-RCS-1-PSSH003            The support condition has been evaluated by Engineering and found to be acceptable with the support performing its intended design function.
C-H / C7.10                  Valve 3CHS*AV8149B          Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10                  Valve 3CHS*AV8149C          Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10                  Valve 3CHS*V047            Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10              Heat Exchanger 3RHS*E1A        Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10              Heat Exchanger 3RHS*E1B        Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10                Valve 3RHS*MV8701B          Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service
Form OAR-1 Owner's Activity Report
-~  Dominiow Attachmn-t 1, E -1        II10e-0*                          P      3 of-5 Table I Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination                  Item Description                  Evaluation Description Category and Item Number B-P 1B15.10              Valve 3RHS*MV8701C          Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H/ C7.10              Pump RHS*P1B Casing          Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10            Pump 3QSS*P3A Outlet          Evidence of leakage detected at bolted Flange              connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10              Pump 3QSS*P3A Inlet        Evidence of leakage detected at bolted Flange              connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10            Pump 3QSS*P3A Casing          Evidence of leakage detected at bolted "
connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10              Pump 3QSS*P3B Outlet        Evidence of leakage detected at bolted Flange              connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10            Heat Exchanger 3RSS*EIA        Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10                  Pump 3SIH*PIA            Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10                Valve 3SIH*V013          Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10                Valve 3SIL*AV8879B        Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10                  Valve 3SIL*V017          Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service
M-Wh1h                      Form OAR-1 Owner's Activity Report F-Z-2.ý iiiýDamini*W I tahet1          E-A-S10                              Pag  4~. of5' Table I Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination                      Item Description            Evaluation Description Category and Item Number B-P / B15.10                    Valve 3SIL*V985    Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service B-P / B15.10              Flow Element 3RCS*FE438  Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service B-P / B15.10              Flow Element 3RCS*FE448  Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service B-P / B135.10                  Valve 3RCS*AV8037B  Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service B-P / B15.10                  Valve 3RCS*AV8037C  Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service B-P / B1 5.10                  Valve 3RCS*MV8003A  Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service B-P / B15.10                  Valve 3RCS*MV8003C  Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for clntineced service B-Pt B/15.10                  Valve 3RCS*MV8003D  Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service 13-13/1315.10                  Valve 3RCS*V026    Evidence of leakage detected at bolfted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to Ibe acceptable for continued service
Form OAR-1 Owner's Activity Report AF' .(*mimi[ai1
                                            -      i  1,  -'-,*l.]5[        ~                    .6.  -'*:~
[
Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Class      Item Description          Description of Work                    Date  Repair/Replacement Completed    Plan Number 1            Steam Generator          Install mechanical tube              4/27/2013    53102347234 Plugs              plug for 3RCS*SG1B.
Steam Generator          Install mechanical tube              4/27/2013    53102347236 Plugs              plug for 3RCS*SG1D.
2                  Valve            Replace Feedwater valve                5/10/2013    53102622642 3FWS*FCV540 Weld repair build-up of 3            Heat Exchanger        the divider plate cover on            12/20/2011    53102486686 3CCP*EIC Replace Service Water 3                Pipe Spool          valve 3SWP*V873 with                  2/15/2013    53102587638 pipe spool Replace sections of 3                Pipe Spool                Service Water line                1/25/2013    53102592710 3-SWP-003-276-3.
Replace Service Water 3                Pipe Spool              piping flange for line              3/6/2013    53102606210 3-SWP-003-324-3 Replace Service Water 3                Pipe Spool                pipe spool on line                5/6/2013    53102618055 3-SWP-003-248-3 Replace section of 3                Pipe Spool                  Feedwater line                  5/10/2013    53102618749 3-FWS-018-086-2 Repair Service Water Pipe Spool        pipe spool 3-SWP-21-6A-                  4/29/2013    53M30707417 3        _2-3                                  Outlet flange.
Replace flange bolting for Service Water 3                  Bolting                            Wate        .Servic  4/29/2013    53M30707417 3SWP*RO12OB and pipe spool 3-SWP-21-6A-2-3 3                  Valve            Install replacement valve                5/6/2013    53102600802 for 3SWP*V658 3                  Valve            Install replacement valve                5/6/2013    53102601733 for 3SWP*V659 3                  Valve            Install replacement valve              4/28/2013    53102601735 for 3SWP*V661 3                  Valve            Install replacement valve                5/6/2013    53102601745 for 3SWP*V663 3                  Valve            Install replacement valve              4/29/2013    53102601746 for 3SWP*V664 3                  Valve            Install replacement valve              4/29/2013    53102601747 for 3SWP*V665 3                  Valve            Install replacement valve              4/29/2013    53102601737 for 3SWP*V668}}

Latest revision as of 14:30, 4 November 2019

Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 15
ML13233A318
Person / Time
Site: Millstone Dominion icon.png
Issue date: 08/01/2013
From: Scace S
Dominion, Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
13-421
Download: ML13233A318 (9)


Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station

~Dominioni Rope Ferry Road, Waterford, CT 06385 AUG 1 213 U.S. Nuclear Regulatory Commission Serial No.13-421 Attention: Document Control Desk NSSL/MLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT, REFUELING OUTAGE 15 Dominion Nuclear Connecticut, Inc. (DNC) hereby submits the American Society of Mechanical Engineers (ASME),Section XI, Form OAR-I, Owner's Activity Report, for the period from November 24, 2011 through Refueling Outage 15, completed on May 19, 2013 for Millstone Power Station Unit 3. The enclosure is in accordance with the requirements of ASME Code Case N-532-4.

If you have any questions or require additional information, please contact William D. Bartron at (860) 444-4301.

Sincerely, Site Vice President - Millstone

Enclosure:

1. Owner's Activity Report, Refueling Outage 15, Revision 0.

Commitments made in this letter: None AU-17

Serial No.13-421 MPS3 Owner's Activity Report Docket No. 50-423 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 James S. Kim Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.13-421 Docket No. 50-423 ENCLOSURE 1 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 15 Revision 0 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

MILLSTONE POWER STATION UNIT NO. 3 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 15 Revision 0 Contents:

OAR-1 Report Number: MP3-3R15 Table 1: Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service.

Table 2: Abstract of Repairs/Replacement Activities Required for Continued Service Prepared By: Date: 7/P/1/7 1§1 Prograw wner Reviewed By: Date:

Independent Review Reviewed By: Date:

Autýhd NfucleInservice Inspection

I Form OAR-1 Owner's Activity Report W-DominioW I-tah et1 E-AA ISI10 Page 1*f5' Report Numb er: MP3-3R15 er:

Plant Millstone Power Station. Rope Fernr Road. Waterford. Connecticut 06385 Unit No. 3 Commercial service date April 26, 1986 Refueling outage no. 15 (if applicable)

Current inspection interval 3rd (1 st, 2 d, 3 rd, 4 t , other)

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

Edition and Addenda of Section XI applicable to the inspection plans 2004 Edition, No Addenda Date and revision of inspection plans 03/27/2013 Revision 2. Chanqe 02-004 Edition and Addenda of Section Xl 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-729-1. 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 XI; and (c) the repair/replacement activities and evaluations supporting the completion of 3R15 conform to the requirements of Section Xl.

(refueling outage number)

Signed 7 ISI Program Owner Date 07/08/2013 Owner or Ownertiesignee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Connecticut and employed by HSB CT of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

__________________Commissions A,,*9,*,/ rVA*//,4' Z ,1-.ZC Naiional Board, State, Prgvince and Endorsements

Form OAR-1 Owner's Activity Report

,Dominion' I-tah et1 E-AA- SI-0 Page 2.f5' Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number C-C / C3.10 RHR Heat Exchanger Surface indication, evaluated as Lower Shell to Skirt Weld acceptable in accordance with ASME 03-073-009 Section XI, IWB 3514.

F-A / F1 .1A Pipe Support Support strut could not be rotated by hand 3-RCS-1-PSR33 to verify freedom of motion. The support condition has been evaluated by Engineering and found to be acceptable with the support performing its intended design function.

F-A/ F1.10A Pipe Support Support strut could not be rotated by hand 3-RCS-1-PSR40 to verify freedom of motion. The support condition has been evaluated by Engineering and found to be acceptable with the support performing its intended design function.

F-A / F .1OC Pipe Support Evaluation of support spring load setting.

3-RCS-1-PSSH003 The support condition has been evaluated by Engineering and found to be acceptable with the support performing its intended design function.

C-H / C7.10 Valve 3CHS*AV8149B Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Valve 3CHS*AV8149C Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Valve 3CHS*V047 Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Heat Exchanger 3RHS*E1A Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Heat Exchanger 3RHS*E1B Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Valve 3RHS*MV8701B Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service

Form OAR-1 Owner's Activity Report

-~ Dominiow Attachmn-t 1, E -1 II10e-0* P 3 of-5 Table I Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number B-P 1B15.10 Valve 3RHS*MV8701C Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H/ C7.10 Pump RHS*P1B Casing Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Pump 3QSS*P3A Outlet Evidence of leakage detected at bolted Flange connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Pump 3QSS*P3A Inlet Evidence of leakage detected at bolted Flange connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Pump 3QSS*P3A Casing Evidence of leakage detected at bolted "

connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Pump 3QSS*P3B Outlet Evidence of leakage detected at bolted Flange connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Heat Exchanger 3RSS*EIA Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Pump 3SIH*PIA Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Valve 3SIH*V013 Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Valve 3SIL*AV8879B Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service C-H / C7.10 Valve 3SIL*V017 Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service

M-Wh1h Form OAR-1 Owner's Activity Report F-Z-2.ý iiiýDamini*W I tahet1 E-A-S10 Pag 4~. of5' Table I Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number B-P / B15.10 Valve 3SIL*V985 Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service B-P / B15.10 Flow Element 3RCS*FE438 Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service B-P / B15.10 Flow Element 3RCS*FE448 Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service B-P / B135.10 Valve 3RCS*AV8037B Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service B-P / B15.10 Valve 3RCS*AV8037C Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service B-P / B1 5.10 Valve 3RCS*MV8003A Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service B-P / B15.10 Valve 3RCS*MV8003C Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for clntineced service B-Pt B/15.10 Valve 3RCS*MV8003D Evidence of leakage detected at bolted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to be acceptable for continued service 13-13/1315.10 Valve 3RCS*V026 Evidence of leakage detected at bolfted connection. Evaluated in accordance with ASME Code Case N-566-2 and found to Ibe acceptable for continued service

Form OAR-1 Owner's Activity Report AF' .(*mimi[ai1

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Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Repair/Replacement Completed Plan Number 1 Steam Generator Install mechanical tube 4/27/2013 53102347234 Plugs plug for 3RCS*SG1B.

Steam Generator Install mechanical tube 4/27/2013 53102347236 Plugs plug for 3RCS*SG1D.

2 Valve Replace Feedwater valve 5/10/2013 53102622642 3FWS*FCV540 Weld repair build-up of 3 Heat Exchanger the divider plate cover on 12/20/2011 53102486686 3CCP*EIC Replace Service Water 3 Pipe Spool valve 3SWP*V873 with 2/15/2013 53102587638 pipe spool Replace sections of 3 Pipe Spool Service Water line 1/25/2013 53102592710 3-SWP-003-276-3.

Replace Service Water 3 Pipe Spool piping flange for line 3/6/2013 53102606210 3-SWP-003-324-3 Replace Service Water 3 Pipe Spool pipe spool on line 5/6/2013 53102618055 3-SWP-003-248-3 Replace section of 3 Pipe Spool Feedwater line 5/10/2013 53102618749 3-FWS-018-086-2 Repair Service Water Pipe Spool pipe spool 3-SWP-21-6A- 4/29/2013 53M30707417 3 _2-3 Outlet flange.

Replace flange bolting for Service Water 3 Bolting Wate .Servic 4/29/2013 53M30707417 3SWP*RO12OB and pipe spool 3-SWP-21-6A-2-3 3 Valve Install replacement valve 5/6/2013 53102600802 for 3SWP*V658 3 Valve Install replacement valve 5/6/2013 53102601733 for 3SWP*V659 3 Valve Install replacement valve 4/28/2013 53102601735 for 3SWP*V661 3 Valve Install replacement valve 5/6/2013 53102601745 for 3SWP*V663 3 Valve Install replacement valve 4/29/2013 53102601746 for 3SWP*V664 3 Valve Install replacement valve 4/29/2013 53102601747 for 3SWP*V665 3 Valve Install replacement valve 4/29/2013 53102601737 for 3SWP*V668