ML16033A471: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| (2 intermediate revisions by the same user not shown) | |||
| Line 2: | Line 2: | ||
| number = ML16033A471 | | number = ML16033A471 | ||
| issue date = 01/22/2016 | | issue date = 01/22/2016 | ||
| title = | | title = Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 23 | ||
| author name = Stanley B | | author name = Stanley B | ||
| author affiliation = Dominion Nuclear Connecticut, Inc | | author affiliation = Dominion Nuclear Connecticut, Inc | ||
| addressee name = | | addressee name = | ||
| Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#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. | ||
Document Control Desk | 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. | ||
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 | If you have any questions or require additional information, please contact Mr. Thomas Cleary at (860) 444-4377. | ||
Sincerely, B. L. Stanley Director, Nuclear Station Safety and Licensing | |||
==Enclosure:== | ==Enclosure:== | ||
: 1. Millstone Power Station Unit 2, Owner's Activity Report -Refueling Outage 23 Commitments made in this letter: None. | : 1. Millstone Power Station Unit 2, Owner's Activity Report - Refueling Outage 23 Commitments made in this letter: None. | ||
Serial No. 16-005 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.Docket No. | |||
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: | 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 | ||
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~ | 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. | ||
SI Proaram O~wner Date 01/05/2016 SOwner or ..-......- | |||
.....CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Connecticut and employed by The Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford. | MILLSTONE POWER STATION UNIT NO. 2 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 23 Revision 0 Contents: | ||
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. | 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 | |||
F-A/ F1.20C Pipe Support 401021 Support spring load setting evaluated by Engineering as acceptable for continued service as documented in UIR MP2 | |||
F-A/ | 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) | ||
F-A/ F1.20C Pipe Support 312009 Support spring load selling evaluated by Engineering as acceptable for continued service as documented in UIR MP2 | Current inspection interval 4th | ||
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 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 | ( 1 st, 2 nd, 3rd, 4 tf, other) | ||
.......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 | Current inspection period 2nd (1st, 2nd, 3rd) | ||
Note: This 0/821 | 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. | ||
Replace section of 3Pipe Spool Service Water piping on 01/25/2015 53102808407 | (refueling outage number) | ||
_____________ | Signed k~ *."**;*"7**,_. SI Proaram O~wner Date 01/05/2016 SOwner or Owner's*Designee*ftle" ..-......- ..... | ||
~~~line 3"-HUD-32____________ | 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. | ||
Replace pressure 3Valve retaining parts of Service 08/05/2015 53102864670 | 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," | ||
~~Water valve 2-SW-i178B | *.*--*fCommissions A4,, ** 6"r/R/- ,, z-- c'_:, | ||
___________ | Inspect s'*ignatu e "National Bo'ard, State, Province and Endorsements Date 6O/.//. £Z-O/,, | ||
Replace section of 3Pipe Spool Service Water piping on 08/07/2015 53102865581 | |||
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. | |||
line 2-1/2"-HUD-1 12 Replace section of 3Pipe Spool Service Water piping on 10/17/2015 53102867864 | 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. | ||
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 | 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. | |||
Document Control Desk | 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. | ||
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 | F-A/ Fl.20A Pipe Support 310021 Support strut barrel thread engagement evaluated by Engineering as acceptable for continued service. Support adjusted to restore to original design condition as documented in UIR MP2-15-008. | ||
C-H / C7.10 Valve 2-SI-470 Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1103 C-H / C7.10 Valve 2-SI-411 Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-201 5-1103 | |||
In,*ioo, Form OAR-I Owner's Activity Report Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number C-H / C7.10 Pump 2-SI-P41B Suction Evidence of leakage at bolted connection Flange evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1 103 C-H I C7.10 .Valve 2-SI-460 Evidence of leakage at bolted connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2015-1153 | |||
....... Form OAR-I Owner's Activity Report Table 2 Abstract of RepairlReplacement Activities Required for Continued Service Code Class Item Description Description of Work Date RepairlReplacement Completed Plan Number Replace section of Feedwater piping on line 2 ~~~~~ | |||
Pipe Pipe Spool 18"-EBB-6. Note: This activity was performed 0/821 0/821 30721 30721 during previous outage 2R22. Ref. CR1010609. __________ | |||
Replace section of 3Pipe Spool Service Water piping on 01/25/2015 53102808407 | |||
_____________ ~~~line 3"-HUD-32____________ | |||
Replace pressure 3Valve retaining parts of Service 08/05/2015 53102864670 | |||
____________ ~~Water valve 2-SW-i178B ___________ | |||
Replace section of 3Pipe Spool Service Water piping on 08/07/2015 53102865581 | |||
_______________________ line 2-1/2"-HUD-1 12 Replace section of 3Pipe Spool Service Water piping on 10/17/2015 53102867864 | |||
__________ _____________ line 2-1/2"-HUD-1 12 Replace section of 2Pipe Spool Feedwater piping on line 10/29/2015 53102801958 18"-EBD-8 at valve 2-FW-5B Replace section of 2Pipe Spool Feedwater piping on line 10/30/20 15 53102885893 18"-EBB-6 at valve | |||
________2-FW-5A Replace section of 2 Pipe Spool ~~Feedwater piping on line 1/021 30842 Pipe spool 18"-EBB-6 inside 1/021 30842 containment | |||
Dominion Nuclear Connecticut, Inc. ~Dominion Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 dora. corn JAN 2 2 2015 U.S. Nuclear Regulatory Commission Serial No. 16-005 Attention: Document Control Desk NSS&L/MLC R0 Washington, DC 20555 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT. INC. | |||
MILLSTONE POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM - OWNER'S ACTIVITY REPORT, REFUELING OUTAGE 23 Dominion Nuclear Connecticut, Inc. hereby submits the American Society of Mechanical Engineers (AS ME), Section XI, Form OAR-I, Owner's Activity Report for the period from May 19, 2014 through Refueling Outage 23, completed on November 7, 2015, for Millstone Power Station Unit 2. The enclosure is in accordance with the requirements of ASME Code Case N-532-4. | |||
If you have any questions or require additional information, please contact Mr. Thomas Cleary at (860) 444-4377. | |||
Sincerely, B. L. Stanley Director, Nuclear Station Safety and Licensing | |||
==Enclosure:== | ==Enclosure:== | ||
: 1. Millstone Power Station Unit 2, Owner's Activity Report -Refueling Outage 23 Commitments made in this letter: None. | : 1. Millstone Power Station Unit 2, Owner's Activity Report - Refueling Outage 23 Commitments made in this letter: None. | ||
Serial No. 16-005 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.Docket No. | |||
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: | 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 | ||
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~ | 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. | ||
SI Proaram O~wner Date 01/05/2016 SOwner or ..-......- | |||
.....CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Connecticut and employed by The Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford. | MILLSTONE POWER STATION UNIT NO. 2 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 23 Revision 0 Contents: | ||
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. | 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 | |||
F-A/ F1.20C Pipe Support 401021 Support spring load setting evaluated by Engineering as acceptable for continued service as documented in UIR MP2 | |||
F-A/ | 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) | ||
F-A/ F1.20C Pipe Support 312009 Support spring load selling evaluated by Engineering as acceptable for continued service as documented in UIR MP2 | Current inspection interval 4th | ||
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 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 | ( 1 st, 2 nd, 3rd, 4 tf, other) | ||
.......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 | Current inspection period 2nd (1st, 2nd, 3rd) | ||
Note: This 0/821 | 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. | ||
Replace section of 3Pipe Spool Service Water piping on 01/25/2015 53102808407 | (refueling outage number) | ||
_____________ | Signed k~ *."**;*"7**,_. SI Proaram O~wner Date 01/05/2016 SOwner or Owner's*Designee*ftle" ..-......- ..... | ||
~~~line 3"-HUD-32____________ | 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. | ||
Replace pressure 3Valve retaining parts of Service 08/05/2015 53102864670 | 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," | ||
~~Water valve 2-SW-i178B | *.*--*fCommissions A4,, ** 6"r/R/- ,, z-- c'_:, | ||
___________ | Inspect s'*ignatu e "National Bo'ard, State, Province and Endorsements Date 6O/.//. £Z-O/,, | ||
Replace section of 3Pipe Spool Service Water piping on 08/07/2015 53102865581 | |||
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. | |||
line 2-1/2"-HUD-1 12 Replace section of 3Pipe Spool Service Water piping on 10/17/2015 53102867864 | 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. | ||
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 | 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
| ML16033A471 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| 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