BVY 10-049, Summary Report - Inservice Inspection and Repair and Replacement

Summary Report - Inservice Inspection and Repair and Replacement

ML102380102
Person / Time
Site:	Vermont Yankee
Issue date:	08/23/2010
From:	Wanczyk R Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 10-049
Download: ML102380102 (9)

Text

Entergy Nuclear Operations, Inc.

Vermont Yankee

--En tergy 320 Governor Hunt Road Vernon, VT 05354 Tel 802 257 7711 Robert J. Wanczyk Licensing Manager BVY 10-049 August 23, 2010 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Vermont Yankee 2010 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:

This letter, in accordance with IWA-4000, IWA-6000 and ASME Code Case N-532-4, provides a copy of the Inservice Inspection Summary Report for activities performed at the Vermont Yankee Nuclear Power Station for the period November 11, 2008 to May 29, 2010. Vermont Yankee hereby submits 2010 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.

Sincerel

[RJW/JTM]

Attachment:

OAR-1 Owner Activity Report for Inservice Inspections (7 pages) cc listing (next page)

BVY 10-049 / page 2 of 2 cc: 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 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street, Drawer 20 Montpelier, VT 05620-2601

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-- Entergy Entergy Nuclear Vermont Yankee OAR-1 Owner Activity Report Through RFO 28 November 11, 2008 through May 29,2010 Reviewed By: Date: E/-L//O Insdvice

{Inspection Pro 0riOler Reviewed By: Date: Z['lqLo Re'pair/Replacement Program Owner Approved By: Pgm& o nn e Date: *L/,odc' Programs & Components Manager

Form OAR-1 Owner's Activity Report Report Number: 10-01-01 Plant: Entergy Nuclear Vermont Yankee Unit No.: 1 Commercial service date: 11/30/1972 Refueling Outage no.: RFO 28 Current inspection interval: Fourth (01)

( Ist, 2 n1 3 rd, 4 th, other)

Current inspection period: _ Second ( 2fld)

(1st, 2na, 3rd)

Edition and Addenda of Section XI applicable to the inspection plans: 1998 Edition, through 2000 Addenda Date and revision of inspection plans: PP7015 Vermont Yankee Inservice Inspection Program. Revision 10, 1/3/2008 Edition and Addenda of Section XI applicable to repair/replacement activities if different than the inspection plans: 2001 Edition, through 2003 Addenda for Repair & Replacement and Pressure Test Program Code Cases used: ASME Code Case N-513-2 (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 28 conform to the requirements of Section XI.

(refueling o e number)

Signed: Norman L. Rademacher %/ NaX ector of Engineering Date:

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 I 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 from o nnectedit hhis inspection.

Curt Hanson/ Commissions& -&¢2 /11 A 61V'I.11 ""

Inspect r's Sig ature National Board, State, Province, and Endorsements Date:* 1O Z-00

OAR-1 Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Exa~i51iiatioji Categ~o~ry"" antemi Descripto I~autOicription 1:ek Number.__________________________

D-B Service Water (SW) Piping Lines CR-VTY-2009-00238: During operator rounds, a leak 8"SW-800, 8"SW-801, and 6"SW- was discovered in SW piping. An ASME Code Case N-801B 513 structural evaluation was performed. The N-513 evaluation demonstrated that the indications detected in the four welds are structurally acceptable for all design basis loadings on a temporary basis and not exceeding the time to the next scheduled plant outage.

D-B "A" Emergency Diesel Generator CR-VTY-2009-03376: During operator rounds, a pinhole (DG-1-1-A) Aftercooler Stationary leak was discovered in the DG-1-1A aftercooler wall. The Head leak was approximately lOmL every 5 minutes. An Engineering evaluation concluded the DG was inoperable. Tech Spec LCO was entered for repairs.

D-B SW/CW (Circulating Water) CR-VTY-2009-02093: During operator rounds, a leak traveling screen backwash header was discovered on the traveling screen backwash header of approximately several drops per minute from-the header section going to the "B" SW traveling screen.

While assessing the affected piping for possible Ultrasonic (UT) examination the corroded area failed when touched with a hand tool. Tech Spec LCO was entered for repairs.

F-A Core Spray (CS) Pipe Support CS- CR-VTY-2010-01557: During ISI VT-3 examination, a HD-57C loose jam nut on CS-HD-57C pipe support threaded connection was discovered. Engineering evaluation concluded that the condition was acceptable since the spring can setting had not changed.

Page 1 of 2

OAR-1 Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Exmiaio ategory and 4ti~srpi fDe~scri-ption vluation

<ItemiNumber F-A Primary Containment Torus CR-VTY-2010-01638: During ISI VT-3 examination, Support NB-H1951-TSS10 Torus Support NB-H1951-TSSIO column anchor bolt was discovered cut-off. Engineering evaluation determined that this support bolt is abandoned equipment and that drawing had not been updated.

F-A Residual Heat Removal Service CR-VTY-2010-01395: During a walk-down of the Water (RHRSW) Spring Can Service Water pipe trench, RHRSW pipe supports were Supports identified as being in a degraded condition (exfoliation of the support surface due to general corrosion resulting from exposure to flooding in the pit). This condition was previously identified in 2005' In both instances an engineering evaluation concluded the degraded condition did not prevent the supports from performing their design function.

C-C Feedwater (FDW) Anchor Piping CR-VTY-2010-01942: During an owner elected Support Integral Attachment Weld Penetrant Test (PT) exam, an approximate 1/2" long FDW-HD39 indication was discovered. The indication is located in the previously excavated area and is bounded by previous engineering evaluation supporting functionality and I operability.

Page 2 of 2

OAR-1 Table 2 Abstract of Repair/Replacement Activities Required for Continued Service

~Repair, Replaceinent, P

Modcaiton 'Rep,,orted Code 'or Corrective' Comiplete Plan lss

.. Measure, , ItemDescriptigo -' - D

Desc-.ltlonioflork ,Date Numbe 3 Replacement Pipe Line 8" SW-801B Thru wall leak in 8" SW-801B was 2/21/2009 180338-06 (Standby Fuel Pool repaired by installation of pre-fabricated Cooling Service Water) Tee.

3 Replacement Pipe Line 3" SW-5 Thru wall leak in 3" SW-5 piping was 8/17/2009 197972-01 (Service Water supply to repaired by replacement.

traveling screens) 3 Replacement Pipe Line SW-5 (Service All SW-5 piping outside and inside 8/17/2009 197972-23 Water supply to traveling intake structure was repaired by screens) replacement (prefabrication of piping).

3 Replacement Standby Fuel Pool Cooling Thru wall leak in Standby Fuel Pool 2/1/2010 202414-01 Service Water Piping per, Cooling Service Water Piping was Engineering Change, EC repaired by replacement per EC 16328.

16328 3 Replacement Standby Fuel Pool Cooling Standby Fuel Pool Cooling Service 2/1/2010 202414-19 Service Water Piping per Water Pipe was replaced (Pre-fab).

Engineering Change, EC 16328 1 1 Page 1 of 3

OAR-1 Table 2 Abstract of Repair/Replacement Activities Required for Continued Service riping upstream or 6 wV-6uu was repiacea upstream or Standby Fuel Pool Cooling V70-261 Per ECN-18983.

Service Water valve V70-261 (Engineering Change Notice, ECN-18983) on line 8"SW-800 3 Repair 12"X12"X8" Pipe Tee on 8"SW-800 was repaired by weld build- 2/1/2010 202414-44 Pipe Line 8"SW-800 up on existing 12"X12"X8" Tee.

(Standby Fuel Pool Cooling Service Water) 3 Replacement "Alpha" Emergency Diesel Pinhole leak on DG- 1-1A Aftercooler 2/8/2010 209099-01 Generator, DG-1-1A, was repaired by replacement.

Aftercooler 3 Replacement "Alpha" Service Water P-7-1A Packing Gland was replaced due 11/2/2009 212301-01 Pump P-7-1A Packing to thru-wall leak on the stuffing box.

Gland 3 Replacement "Alpha" Emergency Diesel Replace Stationary Control Side 1/7/2010 213217-01 Generator, DG- 1-1A, Aftercooler head on DG- 1-1A("Alpha" Stationary Control Side Emergency Diesel Generator)

Aftercooler Channel Head II_ I Page 2 of 3

OAR-1 Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Repair,>

Replacmen4i$,

Modif.ictionpV.. Reported Code ~or Cori-etive Co'mplete Plan

>Clas~s ~Measiir-e 4PmI~n Description ,Description of>Work Date Number 3 Repair "Alpha" Emergency Diesel Thru wall leak on DG-1-IA Control 1/7/2010 213217-12 Generator, DG-I-1A, Side Channel Head wall damage was Control Side Channel repaired by weld buildup from ID.

Head 3 Replacement "Alpha" Emergency Diesel New DG-I-IA Aftercooler Heat 1/7/2010 213217-13 Generator, DG- 1-1 A, Exchanger Stationary Channel Flange Aftercooler Heat was modified to facilitate replacement.

Exchanger Stationary Channel Flange Page 3 of 3