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| | number = ML16214A243 | | | number = ML16214A243 |
| | issue date = 07/25/2016 | | | issue date = 07/25/2016 |
| | title = Millstone Power Station, Unit 3 - Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 17 | | | title = Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 17 |
| | 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 = |
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| =Text= | | =Text= |
| {{#Wiki_filter:I .. Dominion Nuclear Connecticut, Inc. Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 <lorn.com JUL 2 5 2016 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 NUCllEAR MILLSTONE POWER UNIT 3 . Serial No. NSSL/MLC Docket No. license No. fPROGRAM.:... OWNIER1S RIEfPORT, REFUJEUNG OUTAGE 16-254 RO 50-423 NPF-49 Dominion Nuclear Connecticut, Inc. (DNC) hereby submits the American Society of Mechanical Engineers (ASME), Section XI, Form OAR-1, Owner's Activity Report, for the period from November 18, 2014 through Refueling Outage 17, completed on May 13, 2016 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 Jeffry A. Langan at (860) 444-5544. Sincerely, B. L. Stanley Director, Nuclear Safety and Licensing -Millstone | | {{#Wiki_filter:I -.~ .. |
| | Dominion Nuclear Connecticut, Inc. |
| | Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 |
| | <lorn.com JUL 2 5 2016 U.S. Nuclear Regulatory Commission Serial No. 16-254 Attention: Document Control Desk NSSL/MLC RO Washington, DC 20555 Docket No. 50-423 license No. NPF-49 DOM~NION NUCllEAR CONNECl~CUl, ~NC. |
| | MILLSTONE POWER SlAl~ON UNIT 3 . |
| | INSERV~CE ~NSPlECT~ON fPROGRAM.:... OWNIER S ACT~V~lY RIEfPORT, 1 |
| | REFUJEUNG OUTAGE ~7 Dominion Nuclear Connecticut, Inc. (DNC) hereby submits the American Society of Mechanical Engineers (ASME), Section XI, Form OAR-1, Owner's Activity Report, for the period from November 18, 2014 through Refueling Outage 17, completed on May 13, 2016 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 Jeffry A. |
| | Langan at (860) 444-5544. |
| | Sincerely, |
| | ~~ |
| | B. L. Stanley Director, Nuclear Safety and Licensing - Millstone |
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| |
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| ==Enclosure:== | | ==Enclosure:== |
| 1. Owner's Activity Report, Refueling Outage 17, Revision 0. | | : 1. Owner's Activity Report, Refueling Outage 17, Revision 0. |
| * Commitments made in this letter: None cc: U. S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Serial No. 16-254 MPS3 Owner's Activity Report Docket No. 50-423 Page 2 of 2 Senior Project Manager -Millstone Power Station U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station ENCLOSURE 1 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 17 Revision 0 DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3 Serial No. 16-254 Docket No. 50-423 MILLSTONE POWER STATION UNIT NO. 3 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 17 Revision 0 Contents: OAR-1 Report Number: MP3-3R17 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 " 7;{/;& Prepared By: Date: I I 74--<i 7 /17-//£ I Reviewed By: Date: Independent Review Reviewed By: .. /yDatE'.: ila&. ( | | * Commitments made in this letter: None |
| Form OAR-1 Owner's Activity Report ReportNumber:. __ Plant _____ ______ _ Unit No._-=3 ______ _ Commercial service date Aoril 26. 1986 Refueling outage no. __,_1-'-7 __ _ (if applicable) Current inspection interval (15, 2°, 3r, 4 , other) Current inspection period (15\ 2° , 3r ) Edition and Addenda of Section XI applicable to the inspection plans 2004 Edition No Addenda Date and revision of inspection plans 05/05/2016 Revision 2, Change 04-003 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-133. N-460. N-504-4, N-532-4. N-566-2. N-722-1. N-729-1, N-740-2. 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 3R17 conform to the requirements of Section XI. (refueling outage number) Date 07/11/2016 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 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/.£ ,fttl/ 07-/ff A/r,dh ?f .z+ C..:L. Al) National Board, State, Province and Endorsements Da'f!!_.,)uf 121 W'? | | |
| Form OAR-1 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 Loose pipe clamp evaluated by Engineering and found to be acceptable F-A/F1.10A Pipe Support for continued service as documented in 3-CHS-1-PSST739 UIR MP3-16-001 I CR1034512. Clamp tightened to restore support to original desif:}n condition. Support spring load setting evaluated by F-A/ F1.10C Pipe Support Engineering and found to be acceptable 3-RCS-1-PSSH506 for continued service as documented in UIR MP3-16-002 I CR1035831. Evidence of leakage detected at bolted connection evaluated in accordance with 0-B I 02.10 Valve 3CHS*V993 ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR581790 and ETE-MP-2015-1072. Evidence of leakage detected at bolted connection evaluated in accordance with 0-B I 02.10 Spool Piece 3-CHS-49-4-2-3 ASME Code Case N-566-2 and found to Upstream Flange be acceptable for continued service as documented in CR581778 and ETE-MP-2015-1072. Evidence of leakage detected at bolted connection evaluated in accordance with 0-B I 02.10 Spool Piece 3-CHS-49-4-2-3 ASME Code Case N-566-2 and found to Downstream Flange be acceptable for continued service as documented in CR581784 and ETE-MP-2015-1072. Evidence of leakage detected at bolted connection evaluated in accordance with C-H/C7.10 Valve 3QSS*AOV28 ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR576423 and ETE-MP-2015-1049. Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Heat Exchanger 3RHS*E1A ASME Code Case N-566-2 and found to Lower Flange be acceptable for continued service as documented in CR576427 and ETE-CME-2013-1011 Rev. 0 thru Rev. 2. Evidence of leakage detected at bolted connection evaluated in accordance with : C-H I C7.10 Pump 3RHS*P1A Main ASME Code Case N-566-2 and found to Flange be acceptable for continued service as documented in CR576437 and ETE-MP-2015-1049.
| | Serial No. 16-254 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 R. V. Guzman Senior Project Manager - Millstone Power Station U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station |
| Form OAR-1 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 Evidence of leakage detected at bolted connection evaluated in accordance C-H I Cl.10 3QSS*P3A Inlet I Suction with ASME Code Case N-566-2 and Flange found to be acceptable for continued service as documented in CR576444 and ETE-MP-2015-1049. Evidence of leakage detected at bolted connection evaluated in accordance C-H/C7.10 Pump 3RHS*P1 B Main with ASME Code Case N-566-2 and Flange found to be acceptable for continued service as documented in CR577429 and ETE-MP-2012-1252. Evidence of leakage detected at bolted connection evaluated in accordance C-H/C7.10 Pump 3RHS*P1B Inlet/ with ASME Code Case N-566-2 and Suction Flange found to be acceptable for continued service as documented in CR577 444 and ETE-MP-2015-1058. Evidence of leakage detected at bolted connection evaluated in accordance C-H I Cl.10 Spool Piece 3-RHS-503-1-4-2 with ASME Code Case N-566-2 and Downstream Flange found to be acceptable for continued service as documented in CR577 444 and ETE-MP-2015-1058. Evidence of leakage detected at bolted connection evaluated in accordance C-H/C7.10 3RSS*E1 B Inlet Flange with ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR578142 and ETE-MP-2015-1053. Evidence of leakage detected at bolted connection evaluated in accordance C-H I Cl.10 Pump 3RHS*P1 B Main with ASME Code Case N-566-2 and Flange found to be acceptable for continued service as documented in CR1031685 and ETE-MP-2016-1035. Evidence of leakage detected at bolted connection evaluated in accordance C-H I Cl.10 Valve 3RHS*HCV607 with ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR1031691 and ETE-MP-2016-1035. Evidence of leakage detected at bolted connection evaluated in accordance C-H I Cl.10 Heat Exchanger 3RHS*E1 B with ASME Code Case N-566-2 and Flange found to be acceptable for continued service as documented in CR1031701 and ETE-CME-2013-1011 Rev. 2.
| | |
| Form OAR-1 Owner's Activity Report Table 1 items with Flaws or Relevant Co01di1l:ions That ReqQJlired Evalua11:ion for Continued Service Examination Item Description Evaluation Description Category and Item Number Evidence of leakage detected at bolted connection evaluated in accordance with B-P I 815.20 Valve 3RHS*MV8702B AJ'.>ME Code Case N-566-2 and found to be acceptable for continued service as documented in CR1034435 and ETE-MP-2016-1058. Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Heat Exchanger 3RSS*E1 B ASME Code Case N-566-2 and found to Inlet Flange be acceptable for continued service as documented in CR1036848 and ETE-MP-2016-1081. Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Heat Exchanger 3RSS*E1 B ASME Code Case N-566-2 and found to Outlet Flange be acceptable for continued service as documented in CR1036860 and ETE-MP-2016-1081. Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Valve 3SIH*V017 ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR1029017 and ETE-MP-2016-1006. Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Valve 3SIH*MV8802B ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR1036511 and ETE-MP-2016-1079. Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Valve 3SIH*MV8821A ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR1036483 and ETE-MP-2016-1079. Evidence of leakage detected at bolted connection evaluated in accordance with B-P I B15.20 Valve 3SI L *V985 ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR1034279 and ETE-MP-2016-1048. Evidence of leakage detected at bolted connection evaluated in accordance with B-P I B15.20 Valve 3RCS*SV8095B ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR1037278 and ETE-MP-2016-1084.
| | Serial No. 16-254 Docket No. 50-423 ENCLOSURE 1 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 17 Revision 0 DOMINION NUCLEAR CONNECTICUT, INC. |
| Form OAR-1 Owner's Activity Report Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Servoce Examination Item Description Evaluation Description Category and Item Number Evidence of leakage detected at bolted connection evaluated in accordance with B-P I 815.20 Valve 3RCS* AV8037C ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR1034041 and ETE-MP-2016-1048. Evidence of leakage detected at bolted connection evaluated in accordance with B-P I 815.20 Valve 3RCS*AV80378 ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR1033846 and ETE-MP-2016-1048. Evidence of leakage detected at bolted connection evaluated in accordance with B-P I 815.20 Valve 3RCS*V107 ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR1034039 and ETE-MP-2016-1048 Evidence of leakage detected at bolted connection evaluated in accordance with B-P I 815.20 Valve 3RCS*MV8003A ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR1034272and ETE-MP-2016-1058. Evidence of leakage detected at bolted connection evaluated in accordance with B-P I 815.20 Valve 3RCS*MV8003C ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR1034275 and ETE-MP-2016-1058. Evidence of leakage detected at bolted connection evaluated in accordance with 8-P I 815.20 Valve 3RCS*MV8003D ASME Code Case N-566-2 and found to be acceptable for continued service as documented in CR1034281 and ETE-MP-2016-1058.
| | MILLSTONE POWER STATION UNIT 3 |
| Form OAR-1 Owner's Activity Report Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Repair/Replacement Completed Plan Number Replace section of 3 Pipe Spool Service Water line 02/03/2015 53102801095 3-SWP-003-324-3. Replace section of 3 Pipe Spool Service Water line 12/16/2015 53102874177 3-SWP-003-276-3. Replace section of 53102957056 3 Pipe Spool Service Water line 04/25/2016 53102797777 3-SWP-018-82-3.
| | |
| }} | | MILLSTONE POWER STATION UNIT NO. 3 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 17 Revision 0 Contents: |
| | OAR-1 Report Number: MP3-3R17 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;{/;& |
| | I I Reviewed By: ~ 74--<i Independent Review Date: 7/17-//£ I Reviewed By: ../yDatE'.: ( |
| | ~fl* ila&. |
| | |
| | Form OAR-1 Owner's Activity Report ReportNumber:._ _~M~P~3~-3~R~1~7~----------------------------- |
| | Plant _ _ _ _ __,_,_M=il=ls=to=n=e~P~o=w~e=r~S=t=a=ti=o~n.~R~o~o~e"-'--F=e~rrvJ-'-R=o=a=d~,~VV~a~te=rf~o=r=d~.=C=o~n~ne=c=t=ic=u~t~0=6=3=8=5_ _ _ _ _ __ |
| | Unit No._-=3_ _ _ _ _ __ Commercial service date Aoril 26. 1986 Refueling outage no. __,_1-'-7_ __ |
| | (if applicable) |
| | Current inspection interval _3=r~d~---=,----=----,,,r--=----------------------- |
| | (15, 2°, 3r, 4 , other) |
| | Current inspection period _~3~rd~--~-r------------------------ |
| | (15\ 2° , 3r ) |
| | Edition and Addenda of Section XI applicable to the inspection plans 2004 Edition No Addenda Date and revision of inspection plans 05/05/2016 Revision 2, Change 04-003 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-133. N-460. N-504-4, N-532-4. N-566-2. N-722-1. N-729-1, N-740-2. 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 3R17 conform to the requirements of Section XI. |
| | (refueling outage number) |
| | Date 07/11/2016 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 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. |
| | _,~""-+J'4'.d:;~~~~"""'°'""IZ..."'--'K:~----- Commissions A/.£,fttl/ 07-/ff A/r,dh ?f .z+ C..:L. Al) ln~OT'SSfaTiature National Board, State, Province and Endorsements Da'f!!_.,)uf 121 W'? |
| | |
| | Form OAR-1 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 Loose pipe clamp evaluated by Engineering and found to be acceptable Pipe Support for continued service as documented in F-A/F1.10A 3-CHS-1-PSST739 UIR MP3-16-001 I CR1034512. Clamp tightened to restore support to original desif:}n condition. |
| | Support spring load setting evaluated by Pipe Support Engineering and found to be acceptable F-A/ F1.10C 3-RCS-1-PSSH506 for continued service as documented in UIR MP3-16-002 I CR1035831. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to 0-B I 02.10 Valve 3CHS*V993 be acceptable for continued service as documented in CR581790 and ETE-MP-2015-1072. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with 0-B I 02.10 Spool Piece 3-CHS-49-4-2-3 ASME Code Case N-566-2 and found to Upstream Flange be acceptable for continued service as documented in CR581778 and ETE-MP-2015-1072. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with 0-B I 02.10 Spool Piece 3-CHS-49-4-2-3 ASME Code Case N-566-2 and found to Downstream Flange be acceptable for continued service as documented in CR581784 and ETE-MP-2015-1072. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to C-H/C7.10 Valve 3QSS*AOV28 be acceptable for continued service as documented in CR576423 and ETE-MP-2015-1049. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Heat Exchanger 3RHS*E1A ASME Code Case N-566-2 and found to Lower Flange be acceptable for continued service as documented in CR576427 and ETE-CME-2013-1011 Rev. 0 thru Rev. 2. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Pump 3RHS*P1A Main ASME Code Case N-566-2 and found to Flange be acceptable for continued service as documented in CR576437 and ETE-MP-2015-1049. |
| | |
| | Form OAR-1 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 Evidence of leakage detected at bolted connection evaluated in accordance C-H I Cl.10 3QSS*P3A Inlet I Suction with ASME Code Case N-566-2 and Flange found to be acceptable for continued service as documented in CR576444 and ETE-MP-2015-1049. |
| | Evidence of leakage detected at bolted connection evaluated in accordance C-H/C7.10 Pump 3RHS*P1 B Main with ASME Code Case N-566-2 and Flange found to be acceptable for continued service as documented in CR577429 and ETE-MP-2012-1252. |
| | Evidence of leakage detected at bolted connection evaluated in accordance C-H/C7.10 Pump 3RHS*P1B Inlet/ with ASME Code Case N-566-2 and Suction Flange found to be acceptable for continued service as documented in CR577444 and ETE-MP-2015-1058. |
| | Evidence of leakage detected at bolted connection evaluated in accordance C-H I Cl.10 Spool Piece 3-RHS-503-1-4-2 with ASME Code Case N-566-2 and Downstream Flange found to be acceptable for continued service as documented in CR577444 and ETE-MP-2015-1058. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and C-H/C7.10 3RSS*E1 B Inlet Flange found to be acceptable for continued service as documented in CR578142 and ETE-MP-2015-1053. |
| | Evidence of leakage detected at bolted connection evaluated in accordance C-H I Cl.10 Pump 3RHS*P1 B Main with ASME Code Case N-566-2 and Flange found to be acceptable for continued service as documented in CR1031685 and ETE-MP-2016-1035. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and C-H I Cl.10 Valve 3RHS*HCV607 found to be acceptable for continued service as documented in CR1031691 and ETE-MP-2016-1035. |
| | Evidence of leakage detected at bolted connection evaluated in accordance C-H I Cl.10 Heat Exchanger 3RHS*E1 B with ASME Code Case N-566-2 and Flange found to be acceptable for continued service as documented in CR1031701 and ETE-CME-2013-1011 Rev. 2. |
| | |
| | Form OAR-1 Owner's Activity Report Table 1 items with Flaws or Relevant Co01di1l:ions That ReqQJlired Evalua11:ion for Continued Service Examination Item Description Evaluation Description Category and Item Number Evidence of leakage detected at bolted connection evaluated in accordance with AJ'.>ME Code Case N-566-2 and found to B-P I 815.20 Valve 3RHS*MV8702B be acceptable for continued service as documented in CR1034435 and ETE-MP-2016-1058. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Heat Exchanger 3RSS*E1 B ASME Code Case N-566-2 and found to Inlet Flange be acceptable for continued service as documented in CR1036848 and ETE-MP-2016-1081. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Heat Exchanger 3RSS*E1 B ASME Code Case N-566-2 and found to Outlet Flange be acceptable for continued service as documented in CR1036860 and ETE-MP-2016-1081. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to C-H I C7.10 Valve 3SIH*V017 be acceptable for continued service as documented in CR1029017 and ETE-MP-2016-1006. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to C-H I C7.10 Valve 3SIH*MV8802B be acceptable for continued service as documented in CR1036511 and ETE-MP-2016-1079. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to C-H I C7.10 Valve 3SIH*MV8821A be acceptable for continued service as documented in CR1036483 and ETE-MP-2016-1079. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I B15.20 Valve 3SI L*V985 be acceptable for continued service as documented in CR1034279 and ETE-MP-2016-1048. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I B15.20 Valve 3RCS*SV8095B be acceptable for continued service as documented in CR1037278 and ETE-MP-2016-1084. |
| | |
| | Form OAR-1 Owner's Activity Report Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Servoce Examination Item Description Evaluation Description Category and Item Number Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS* AV8037C be acceptable for continued service as documented in CR1034041 and ETE-MP-2016-1048. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS*AV80378 be acceptable for continued service as documented in CR1033846 and ETE-MP-2016-1048. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS*V107 be acceptable for continued service as documented in CR1034039 and ETE-MP-2016-1048 Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS*MV8003A be acceptable for continued service as documented in CR1034272and ETE-MP-2016-1058. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS*MV8003C be acceptable for continued service as documented in CR1034275 and ETE-MP-2016-1058. |
| | Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to 8-P I 815.20 Valve 3RCS*MV8003D be acceptable for continued service as documented in CR1034281 and ETE-MP-2016-1058. |
| | |
| | Form OAR-1 Owner's Activity Report Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Repair/Replacement Completed Plan Number Replace section of 3 Pipe Spool Service Water line 02/03/2015 53102801095 3-SWP-003-324-3. |
| | Replace section of 3 Pipe Spool Service Water line 12/16/2015 53102874177 3-SWP-003-276-3. |
| | Replace section of 53102957056 3 Pipe Spool Service Water line 04/25/2016 53102797777 3-SWP-018-82-3.}} |
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Alternate Request RR-05-06 - Inspection Interval Extension for Steam Generator Pressure Retaining Welds and Full-Penetration Welded Nozzles
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Alternative Request IR-4-03 for Use of an Alternative Non-Code Methodology to Demonstrate Structural Integrity of Class 3 Moderate-Energy Piping
ML20049A0882020-02-17017 February 2020
ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Second Period of the Third 10-Year Inspection Interval
ML20048A0062020-02-11011 February 2020
ASME Section XI Inservice Inspection Program: Relief Request for Limited Coverage Examinations Performed in the Second Period of the Fourth 10-Year Inspection Interval
ML19275D2542019-09-19019 September 2019
End of Cycle 19 Steam Generator Tube Inspection Report
ML19211B1672019-07-23023 July 2019
Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 19
ML19100A1262019-03-19019 March 2019
Inservice Inspection Program Interval Change
ML19023A0242019-01-11011 January 2019
Submittal of Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 25
ML18114A1052018-04-19019 April 2018
End of Cycle 18 Steam Generator Tube Inspection Report
ML18066A0782018-03-0101 March 2018
In-service Testing Program for Pumps, Valves, & Snubbers Fifth & Fourth 10-Year Interval Updates for Units 2 & 3
ML18031A0932018-01-24024 January 2018
Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 18
ML17269A0302017-09-18018 September 2017
End of Cycle 24 Steam Generator Tube Inspection Report
ML17187A1362017-06-27027 June 2017
Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 24
ML16222A3512016-08-0202 August 2016
Submittal of End of Cycle 17 Steam Generator Tube Inspection Report
ML16214A2432016-07-25025 July 2016
Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 17
ML16033A4712016-01-22022 January 2016
Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 23
ML15356A3752015-12-14014 December 2015
End-of-Cycle 23 Steam Generator Tube Inspection Report
ML15050A0412015-02-0909 February 2015
End of Cycle 16 Steam Generator Tube Inspection Report
ML15049A2932015-02-0909 February 2015
Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 16
ML15033A3732015-01-26026 January 2015
Response to Second Request for Addition Information Regarding Aging Management Program Description: Inservice Inspection - Reactor Vessel Internals, License Renewals Commitment #13
ML14220A0162014-08-0101 August 2014
Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 22
ML14206A8372014-07-21021 July 2014
Response to Request for Additional Information Regarding Aging Management Program Description: Inservice Inspection - Reactor Vessel Internals, License Renewal Commitment #13 (MF3402)
ML14188B1902014-06-26026 June 2014
End of Cycle 22 Steam Generator Tube Inspection Report
ML14143A4082014-05-20020 May 2014
Examination Summary and Coverage Results ASME Section XI Inservice Inspection Program Alternative Request RR-04-15, Limited One-Sided Ultrasonic Examination Technique
ML14051A1092014-02-0707 February 2014
Response to Request for Additional Information Regarding ASME Section XI Inservice Inspection Program Alternative Request RR-04-15, Limited One-Sided Ultrasonic Examination Technique
ML13284A0652013-10-0202 October 2013
End of Cycle 15 Steam Generator Tube Inspection Report
ML13218A2642013-07-31031 July 2013
Information in Support of License Renewal Commitment #13 Program Description for Reactor Vessel Internals Inspections
ML13045A4862013-02-0505 February 2013
Inservice Inspection Program-Owner's Activity Report, Refueling Outage 21
ML12151A3592012-06-0707 June 2012
End of Cycle 20 Steam Generator Tube Inservice Inspection Report Review
ML12109A0442012-04-0606 April 2012
End of Cycle 14 Steam Generator Tube Inspection Report
ML11207A4642011-07-18018 July 2011
Inservice Inspection Program - Owner'S Activity Report, Refueling Outage 20
ML1102502592011-01-20020 January 2011
Request for Additional Information Regarding Relief Requests for Limited Coverage Examinations Performed in the Second 10-Year Inspection Interval
ML1022205272010-08-0505 August 2010
Fourth 10-Year Interval Inservice Inspection Program
ML1025802042010-07-29029 July 2010
Fourth 10-Year Interval Inservice Inspection Program and Associated Proposed Alternatives and Relief Request
ML1021500712010-07-25025 July 2010
Inservice Inspection Program - Owner'S Activity Report
ML1006404562010-03-0505 March 2010
CFR50.55a Relief Request IR-3-14, Update to the Risk-Informed Inservice Inspection Program for the Third 10-Year Inspection Interval
ML1005011632010-02-0404 February 2010
Inservice Inspection Program - Owner'S Activity Report for Refueling Outage 19
ML0913106662009-04-28028 April 2009
Third 10-year Interval Inservice Inspection Program and Associated Proposed Alternatives and Relief Requests
ML0908503442009-03-13013 March 2009
Submittal of End of Cycle 12 Steam Generator Tube Inspection Report
ML0905700482009-02-13013 February 2009
Submittal of Inservice Inspection Program - Owner'S Activity Report for 05/20/07 Through Refueling Outage 12, 11/24/08
ML0824104152008-08-0707 August 2008
Submittal of Inservice Inspection Program - Owner'S Activity Report
ML0811401382008-04-11011 April 2008
Submittal of 2007 Steam Generator Tube Inspection Report
2024-04-30
[Table view]
Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024
Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001
ML24289A0152024-10-21021 October 2024
Review of the Fall 2023 Steam Generator Tube Inspection Report
05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024
Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary
IR 05000336/20244022024-10-0808 October 2024
Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only)
ML24281A1102024-10-0707 October 2024
Requalification Program Inspection
05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024
Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications
ML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
ML24260A2192024-09-16016 September 2024
Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification
ML24260A1952024-09-16016 September 2024
Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel
ML24248A2272024-09-0404 September 2024
Operator Licensing Examination Approval
ML24240A1532024-09-0303 September 2024
Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel
IR 05000336/20240052024-08-29029 August 2024
Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005
IR 05000336/20240022024-08-13013 August 2024
Integrated Inspection Report 05000336/2024002 and 05000423/2024002
ML24221A2872024-08-0808 August 2024
Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage
IR 05000336/20244412024-08-0606 August 2024
Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only)
ML24212A0742024-08-0505 August 2024
Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification
ML24211A1712024-07-25025 July 2024
Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change
IR 05000336/20244032024-07-22022 July 2024
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403
IR 05000336/20245012024-07-0101 July 2024
Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501
ML24180A0932024-06-28028 June 2024
Readiness for Additional Inspection: EA-23-144
IR 05000336/20240102024-06-26026 June 2024
Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010
ML24178A2422024-06-25025 June 2024
2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46
IR 05000336/20244402024-06-24024 June 2024
Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only)
ML24280A0012024-06-20020 June 2024
Update to the Final Safety Analysis Report (Redacted Version)
ML24177A2792024-06-20020 June 2024
Preparation and Scheduling of Operator Licensing Examinations
ML24176A2622024-06-20020 June 2024
Update to the Final Safety Analysis Report, Revision 37
ML24281A2072024-06-20020 June 2024
Update to the Final Safety Analysis Report, Revision 37 (Redacted Version)
ML24176A1782024-06-20020 June 2024
Update to the Final Safety Analysis Report
ML24170B0532024-06-10010 June 2024
DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code
05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024
Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications
ML24165A1292024-06-0505 June 2024
ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023
ML24128A2772024-06-0404 June 2024
Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary)
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
ML24109A0032024-05-21021 May 2024
Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary)
ML24110A0562024-05-21021 May 2024
Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter)
ML24141A2432024-05-20020 May 2024
Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15
ML24142A0952024-05-20020 May 2024
End of Cycle 22 Steam Generator Tube Inspection Report
05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024
Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications
IR 05000336/20240012024-05-14014 May 2024
Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation
05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024
Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications
ML24123A2042024-05-0202 May 2024
Pre-Decisional Replay to EA-23-144
ML24123A1222024-04-30030 April 2024
Inservice Inspection Program - Owners Activity Report, Refueling Outage 22
IR 05000336/20244012024-04-30030 April 2024
Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only)
ML24116A0452024-04-25025 April 2024
Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only)
ML24114A2662024-04-24024 April 2024
Submittal of 2023 Annual Radioactive Effluent Release Report
ML24116A1742024-04-24024 April 2024
Annual Radiological Environmental Operating Report
ML24103A0202024-04-22022 April 2024
Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits
ML24106A2032024-04-15015 April 2024
2023 Annual Environmental Operating Report
ML24088A3302024-04-0404 April 2024
Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel
ML24093A1022024-04-0101 April 2024
Alternative Request IR-4-13, Proposed Alternative Request to Support Steam Genera Tor Channel Head Drain Modification
2024-09-04
[Table view] |
Text
I -.~ ..
Dominion Nuclear Connecticut, Inc.
Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385
<lorn.com JUL 2 5 2016 U.S. Nuclear Regulatory Commission Serial No.16-254 Attention: Document Control Desk NSSL/MLC RO Washington, DC 20555 Docket No. 50-423 license No. NPF-49 DOM~NION NUCllEAR CONNECl~CUl, ~NC.
MILLSTONE POWER SlAl~ON UNIT 3 .
INSERV~CE ~NSPlECT~ON fPROGRAM.:... OWNIER S ACT~V~lY RIEfPORT, 1
REFUJEUNG OUTAGE ~7 Dominion Nuclear Connecticut, Inc. (DNC) hereby submits the American Society of Mechanical Engineers (ASME),Section XI, Form OAR-1, Owner's Activity Report, for the period from November 18, 2014 through Refueling Outage 17, completed on May 13, 2016 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 Jeffry A.
Langan at (860) 444-5544.
Sincerely,
~~
B. L. Stanley Director, Nuclear Safety and Licensing - Millstone
Enclosure:
- 1. Owner's Activity Report, Refueling Outage 17, Revision 0.
- Commitments made in this letter: None
Serial No.16-254 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 R. V. Guzman Senior Project Manager - Millstone Power Station U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No.16-254 Docket No. 50-423 ENCLOSURE 1 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 17 Revision 0 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
MILLSTONE POWER STATION UNIT NO. 3 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 17 Revision 0 Contents:
OAR-1 Report Number: MP3-3R17 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;{/;&
I I Reviewed By: ~ 74--ME Code Case N-566-2 and found to B-P I 815.20 Valve 3RHS*MV8702B be acceptable for continued service as documented in CR1034435 and ETE-MP-2016-1058.
Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Heat Exchanger 3RSS*E1 B ASME Code Case N-566-2 and found to Inlet Flange be acceptable for continued service as documented in CR1036848 and ETE-MP-2016-1081.
Evidence of leakage detected at bolted connection evaluated in accordance with C-H I C7.10 Heat Exchanger 3RSS*E1 B ASME Code Case N-566-2 and found to Outlet Flange be acceptable for continued service as documented in CR1036860 and ETE-MP-2016-1081.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to C-H I C7.10 Valve 3SIH*V017 be acceptable for continued service as documented in CR1029017 and ETE-MP-2016-1006.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to C-H I C7.10 Valve 3SIH*MV8802B be acceptable for continued service as documented in CR1036511 and ETE-MP-2016-1079.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to C-H I C7.10 Valve 3SIH*MV8821A be acceptable for continued service as documented in CR1036483 and ETE-MP-2016-1079.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I B15.20 Valve 3SI L*V985 be acceptable for continued service as documented in CR1034279 and ETE-MP-2016-1048.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I B15.20 Valve 3RCS*SV8095B be acceptable for continued service as documented in CR1037278 and ETE-MP-2016-1084.
Form OAR-1 Owner's Activity Report Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Servoce Examination Item Description Evaluation Description Category and Item Number Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS* AV8037C be acceptable for continued service as documented in CR1034041 and ETE-MP-2016-1048.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS*AV80378 be acceptable for continued service as documented in CR1033846 and ETE-MP-2016-1048.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS*V107 be acceptable for continued service as documented in CR1034039 and ETE-MP-2016-1048 Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS*MV8003A be acceptable for continued service as documented in CR1034272and ETE-MP-2016-1058.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to B-P I 815.20 Valve 3RCS*MV8003C be acceptable for continued service as documented in CR1034275 and ETE-MP-2016-1058.
Evidence of leakage detected at bolted connection evaluated in accordance with ASME Code Case N-566-2 and found to 8-P I 815.20 Valve 3RCS*MV8003D be acceptable for continued service as documented in CR1034281 and ETE-MP-2016-1058.
Form OAR-1 Owner's Activity Report Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Repair/Replacement Completed Plan Number Replace section of 3 Pipe Spool Service Water line 02/03/2015 53102801095 3-SWP-003-324-3.
Replace section of 3 Pipe Spool Service Water line 12/16/2015 53102874177 3-SWP-003-276-3.
Replace section of 53102957056 3 Pipe Spool Service Water line 04/25/2016 53102797777 3-SWP-018-82-3.
