BVY 12-010, Vermont, Submittal of Inservice Inspection, Repair and Replacement for 2011

Vermont, Submittal of Inservice Inspection, Repair and Replacement for 2011

ML12037A067
Person / Time
Site:	Vermont Yankee
Issue date:	02/01/2012
From:	Wanczyk R Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 12-010
Download: ML12037A067 (7)

Text

Entergy Nuclear Operations, Inc.

Vermont Yankee 320 Governor Hunt Road SEn tergy Vernon, VT 05354 Tel 802 257 7711 Robert J. Wanczyk Licensing Manager BVY 12-010 February 1,2012 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Vermont Yankee 2011 Summary Report -

Inservice Inspection and Repair and Replacement Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28

Dear Sir or Madam:

In accordance with IWA-4000 and ASME Code Case N-532-4, this letter provides a copy of the Inservice Inspection Summary Report for activities performed at the Vermont Yankee Nuclear Power Station for the period May 30, 2010 to November 2, 2011.

Vermont Yankee hereby submits 2011 Form OAR-i, Owner Activity Report for Inservice Inspections. Vermont Yankee's fourth ten year Inservice Inspection interval began September 1, 2003.

There are no new regulatory commitments being made in this submittal.

If you have any questions concerning this submittal, please contact me at (802) 451-3166.

Sincerely,

[RJW/JTM]

Attachment:

OAR-i, Owner Activity Report Through RFO 29 (5 pages) cc listing (next page) 04 -7 "94

BVY 12-010 / page 2 of 2 cc: William M. Dean, Region 1 Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 USNRC Resident Inspector Vermont Yankee Nuclear Power Station 320 Governor Hunt Road Vernon, VT 05354 Ms. Elizabeth Miller, Commissioner VT Department of Public Service 112 State Street, Drawer 20 Montpelier, VT 05620-2601

~EntergyY Entergy Nuclear Vermont Yankee OAR-1 Owner Activity Report Through RFO 29 May/, 0, 2010 through November 2, 2C)11 Reviewed By: Date: I'P !/_-

InservictInrspection / air Replac ent Program Owner Reviewed By:__ Date: / 23/1 Supervisor, Code Programs Approved By: 4 n Date: 113,1Z.

Engineerfig P o"Ms om1;ponents Manager

Form OAR-1 Owner's Activity Report Report Number: 11-01-01 Plant: Entergy Nuclear Vermont Yankee Unit No.: I Commercial service date: 11/30/1972 Refueling Outage no.: RFO 29 Current inspection interval: Fourth (4 h)

(I", 2 nd, 3 rd 4th, other)

Current inspection period: Third ( 3 d)

(I st 2 nd, 3 rd)

Edition and Addenda of Section XI applicable to the inspection plans: 1998 Edition, through 2000 Addenda Date and revision of inspection plans: SEP-ISI-VTY-001 VTY Fourth Ten-Year Interval Inservice Inspection (ISI)

Program Plan, Revision 5, 6/20/2011 Edition and Addenda of Section XI applicable to repair/replacement activities if different than the inspection nlans: 2001 Edition. throug~h 2003 Addenda for Renair & Renlacement and Pressure Test Program Code Cases used: ASME Code Case N-532-4 (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 RFO 29 conform to the requirements of Section XI.

(refueling outage numbe)

Signed: Norman L. Rademacher Director of Engineering Date: I 1'\°'\ 2o\2" Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Vermont and employed by Hartford Steam Boiler of CT 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 fromod oinspection. with is Curt Hanson / Commissions ,V6, //9 , ,4461 VIT 087 Inspector's Signature National Board, State, Province, and Endorsements nntp- / O/2 .. O / 2_

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1ý

OAR-1 Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service

-Examination Category and Item Description Evaluation Description S Item Number ',.."

F-A Turbine Building Main Steam line CR-VTY-2011-4903: During an operator walkdown, two D support MSH-110 restraints on support MSH-112 (CR-VTY-2011-4758) found to have pulled out of a wall and off an overhead beam were repaired. Since turbine building main steam supports are part of an augmented ISI program the expanded scope included a VT-3 inspection of MSH-1 10.

This support was found to have a 1/2" indication on the attachment weld to an overhead beam. Engineering evaluated this to leave as is.

C-C CS-HD58A, Saddle to pipe weld CR-VTY-2011-4029: There were several indications MT indication found on some of the tack welds attaching the saddle of support CS-HD58A to the pipe. These indications were determined to not affect the tack weld function to hold the saddle in place relative to the pipe, therefore could be left as is.

F-A HPCI-HD35C, Hanger support rod CR-VTY-2011-4120: The vertical support rod on hanger in contact with cable tray HPCI-HD35C was originally routed through a cable tray, requiring an opening to be created in the cable tray to allow for this configuration. The rod was found to be in contact with the cable tray but was evaluated as acceptable to leave as is based on no loss of material or wear on the rod.

F-A RHR-H 129, Restraint strut CR-VTY-2011-4121: The spherical bearing connection spherical bearing lacking freedom of support RHR-H129 was observed to be restricting the of movement movement of the strut which was connected to the Page I of 2

OAR-1 Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Examination Category and  : Item Description " Evaluation Description '.

Item Number __________________

adjacent wall. Engineering determined that the expected movement of this connection, taking thermal growth into account, allowed for enough movement for full functionality of this support.

Page 2 of 2

Table 2 ABSTRACT OF REPAIRS, REPLACEMENTS OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Code Item Description Description of Work Date Completed Repair/Replacement Class Plan Number 3 "A"Diesel Generator, DG-1-1A Weld repair of Service Water outlet bellows 7/10/2010 242589-01 3 3"SW-37A Replaced piping spool piece 2/11/2011 177469-01 3 Valve V70-169A Disc and stem replacement 10/13/2011 174904-01 3 Valve V70-169B Disc and stem replacement 10/13/2011 174902-01 3 Pump P-85-1A Replaced HPCI Lube Oil Pump 5/24/2011 51070740-01 Replaced valve internals and tack welded body to 2 Valve VG-23 bonnet 10/28/2011 52295388-08 3 Valve SCH-1 -2 Replaced compressor 6/8/2011 275838-01 3 Valve V70-206 Replaced valve 10/18/2011 243555-01 Replaced due to flow restrictions inside valve 3 Valve V70-317B causing surveillance failure 9/3/2011 289267-01 1 Snubber S/N 33787 (RR-2) Replaced block valve and rod bushing 9/21/2011 175813-02 Snubber S/N- ADH-301-1597 (HPCI-2 HD103GN) Replaced scored cylinder tube 9/21/2011 239011-02