ML17187A136

Millstone, Unit 2 - Inservice Inspection Program, Owner'S Activity Report, Refueling Outage 24

ML17187A136
Person / Time
Site:	Millstone
Issue date:	06/27/2017
From:	Stanley B L Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
17-271
Download: ML17187A136 (10)

Text

Dominion Nuclear Connecticut, Inc. Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 dam.com JUN 2 7 2017 U.S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, DC 20555 DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 2 Serial No. NSS&L/MLC Docket No. License No.17-271 RO 50-336 DPR-65 INSERVICE INSPECTION PROGRAM -OWNERJS ACTIVITY REPORT, REFUELING OUTAGE 24 Dominion Nuclear Connecticut, Inc. hereby submits the American Society of Mechanical Engineers (ASME),Section XI, Form OAR-1, Owner's Activity Report for the period from November 8, 2015 through Refueling Outage 24, completed on May 5, 2017, 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 Jeff Langan at (860) 444-5544.

Sincerely,

8. L. Stanley Director, Nuclear Station Safety and Licensing

Enclosure:

Millstone Power Station Unit 2, Owner's Activity Report -Refueling Outage 24 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 NRC Senior Project Manager Serial No.17-271 Owner's Activity Report, 2R24 Docket No. 50-336 Page 2 of 2 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.17-271 Docket No. 50-336 ENCLOSURE INSERVICE INSPECTION PROGRAM -OWNER'S ACTIVITY REPORT REFUELING OUTAGE 24 MILLSTONE POWER STATION UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT NO. 2 OWNER'S ACTIVITY REPORT REFUELING OUTAGE 24 Revision 0 Contents:.

OAR-1 Report Number: MP2-2R24 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 ISIProgram Reviewed By:

Date: 6t.o-/1z/2011-'

1 I Reviewed By: W Date:*

I Form OAR-1 Owner's Activity Report Attachment 1, ER-AA-ISl-100 Page 1 of 6 ReportNumber:.

__

Plant _____

Unit No .. _ (if applicable)

Commercial service date 12/26/1975 Refueling outage no. ----=2._.4

__ _ Current inspection interval (15 , 2" , 3r , 4 , other) Current inspection period (15', 2° I 3') Edition and Addenda of Section XI applicable to the inspection plans 2004 Edition, No Addenda Date and revision of inspection plans 03/20/17 Revision 3, Change 4-004 Edition and Addenda of 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-729-1, N-770-1 (if applicable)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made iii 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 2R24 conform to the requirements of Section XI. (refueling outage number) Date 06/08/2017 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 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.

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1. ,.fkZ;/ /1c£o/ LJ(cl( lnseci()r'i Si atUre National Board, State, Province and Endorsements 4 Z2 ¢ I I L__ __ Form OAR-1 Owner's Activity Report Attachment 1, ER-AA-151-100 Page 2 of 6 Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number F-A/ F1.308 Pipe Support413122 Bolting thread engagement evaluated by Engineering as acceptable for continued service as documented in UIR MP2-17-001, CR1061880 F-A/ F1.20 Pipe Support 410077 Bolting thread engagement evaluated by Engineering as acceptable for continued service as documented in UIR MP2-17-002, CR1062470 F-A/ F1.20C Pipe Support 302027 Bolting thread engagement evaluated by Engineering as acceptable for continued service as documented in UIR MP2-17-003, CR1063534 F-A/ F1.30G Pipe Support 413153 Bolting thread engagement evaluated by Engineering as acceptable for continued service as documented in UIR MP2-17-004, CR1064227 F-A/ F1.10E Pipe Support 410032 Bolting thread engagement evaluated by Engineering as acceptable for continued service as documented in UIR MP2-17-005, CR1064652 F-A/ F1.10B Pipe Support 510016-A Bolting thread engagement evaluated by Engineering as acceptable for continued service as documented in UIR MP2-17-006, CR1064730 F-A I F1.1DH Pipe support 402113-L Missing washer from snubber support end paddle evaluated by Engineering as acceptable for continued service as documented in UIR-MP2-17-008, CR 1065024. Corrective action scheduled for washer replacement to restore support to design condition.

F-A/ F1.10C Pipe Support 310049 Support rod in contact with conduit evaluated by Engineering as acceptable for continued service as documented in UIR-MP2-17-009, CR1065325.

Corrective action scheduled for support rod adjustment to restore support to ; design condition.

Support load setting evaluated by Engineering as acceptable for continued service as documented in UIR-MP2-17-013, CR1065491 F-A/ F1.20E Pipe Support412010 Bolting thread engagement evaluated by Engineering as acceptable for continued service as documented in UIR MP2-17-014, CR1065914 Form '0AR-1 Owner's Activity Report Attachment 1, ER-AA-151-100 Page 3 of 6 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 I C7.10 Valve 2-CH-037 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-2015-1189 and ETE MP-2017-1036 C-H I C7.10 Valve 2-CH-184 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-2015-1189

' C-H/C7.10 Valve 2-CH-193 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-2015-1189 C-H I C7.10

• Valve 2-81-470 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-2017-1045 C-H I C7.10 Pump P41 B suction elbow Evidence of leakage at bolted flange connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2017-1043 C-H I C7.10 Pump P41 B casing to Evidence of leakage at bolted stuffing box cover connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2017-1019 C-H I C7.10 Valve 2-CH-514 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-2017-1036 C-H I C7.10 Pump P43A casing to Evidence of leakage at bolted stuffing box cover connection evaluated in accordance

• with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE MP-2017-1028 C-H/C7.10 Valve 2-CS-28 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-2017-1013 Form OAR-1 Owner's Activity Report Attachment 1, ER-AA-151-100 Page 4 of 6 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 I C7.10 Pump P438 casing to Evidence of leakage at bolted stuffing box cover connection evaluated in accordance with ASME Code Case N-566-2 as acceptable for continued service as documented in ETE'MP-2017-1012 C-H /C7.10 Valve 2-Sl-625 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-2017-1046 C-H I C7.10 Pump P198 Stuffing box Through wall leakage identified in pump cover. stuffing box cover as documented in CR1061230 and CR1061348.

Alternative Request RR-04-26 (Dominion letter S/N 17-187), dated 4/28/17, Accession No ML 17123A043, submitted to NRG to request approval of a proposed alternative to keep the pump available for service with the identified indications until a replacement part can be procured and a permanent code repair can be made. NRC approval granted by letter dated 5/3/17, Accession No. ML 17122A374.

Code Case N-722-1 I 815.205 Loop 28 Cold Leg Visual examination identified staining on Instrument Tap cold leg instrument tap nozzle. M2TE-122CD Condition evaluated by Engineering as acceptable for continued service. Staining was determined not to be the result of reactor coolant leakage. Reference CR 1064672 Form OAR-1 Owner's Activity Report Attachment 1, ER-AA-181-100 Page 5 of 6 Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service -Examination Item Description Evaluation Description Category and Item Number Code Case N-729-1/ 84.30 Reactor Vessel Head Visual examination identified area of Penetrations white residue located at CEDM housing numbers 26, 38 and 42. Condition evaluated by Engineering as acceptable for continued services.

Residue was determined to not be the result to reactor head penetration leakage. Residue at GEOM penetration 26 and 42 were found to be caused by leakage from a horizontal piping flange above, that when disassembled during the outage, overflow had dripped down to the area on the vessel head. Residue on CEDM housing 38 was analyzed and found to be foreign material that did not contain reactor coolant. The subject areas have been cleaned and visually inspected with no material degradation identified.

Reference.

CRs 1065275, 1065281 and 1065498.

Form OAR-1 Owner's Activity Report Attachment 1, ER-AA-ISl-100 Page 6 of 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 Mechanical Replace damaged thrust 11/30/2015 53102483719 Snubber bearing assembly Mechanical Replace degraded 1 Snubber bearing retaining nut 01/04/2016 53102579825 Removal of surface indications on Safety 2 Pipe Spool Injection line 03/17/2016 53102831249 6-GCB-10 3 Pipe Spool Replace Service Water 04/25/2017 53103064542 Pipe Spool SK-905A