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

{{Adams
| number = ML12037A067
| issue date = 02/01/2012
| title = Vermont, Submittal of Inservice Inspection, Repair and Replacement for 2011
| author name = Wanczyk R
| author affiliation = Entergy Nuclear Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000271
| license number = DPR-028
| contact person = 
| case reference number = BVY 12-010
| document type = Inservice/Preservice Inspection and Test Report, Letter type:BVY
| page count = 7
}}

=Text=
{{#Wiki_filter: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'\&deg;'\ 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_
           ------ 1&#xfd;

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}}