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{{Adams
#REDIRECT [[SVP-15-048, Submittal of Owner'S Activity Report Submittal Fifth 10- Tear Interval 2015 Refueling Outage Activities]]
| number = ML15211A557
| issue date = 06/19/2015
| title = Submittal of Owner'S Activity Report Submittal Fifth 10- Tear Interval 2015 Refueling Outage Activities
| author name = Darin S
| author affiliation = Exelon Generation Co, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000254
| license number = DPR-029
| contact person =
| case reference number = SVP-15-048
| package number = ML15211A572
| document type = Fuel Cycle Reload Report, Inservice/Preservice Inspection and Test Report, Letter
| page count = 7
}}
 
=Text=
{{#Wiki_filter:$VP-15-04W June 19, 2015 U. S. Nuclear Regutatory Commission ATTN: Cukent Control Desk Washlngon, DC 205550001 Quad Cities Nuclear Power Station, Unit I Renewed Facility Operating Ucense No. OPR-29 NRC Docket No. 50-254 Subjeot Owner's Ac Report Submittal Ffth 10-Year Interval 2015 Refueling Outage Activities
 
==Reference:==
 
Letter from T. Tate (USNRC) to M. PacWlo (Exelon), Tuad Cities Nuclear Power Stationm Units 1 and 2 -Safety Evaluation In Support of Request for Relief Associated with the FPdh 10 Year Interval InserWce Inspection Program," dated September 30, 2013.This letter the Owner's Activty Report (iLe., Form OAR-I) and Invessel Visual Inspection (IWI) RepoWt for the Quad Cites Nucear Power Station (OCNPS) Unit I refueling outage (QiR23) wh begn on March 2, 2015, and was corpleted on March 23,2015. This Is the f1r1t raeftelngo conducted In the firt inspection period of the fifth 10-year Irservice Inspection Interval for QOCNPS Unit 1. A copyo the Owners Activity Report and the IWI Report ae provided as attachments to this letter.The Owner's Activity Report Is stbmted in accordance with American Society of Mechanical Engfnear (ASME) Soiler and Pressure Vessel Code Case N-5324, 1 Riepar acant Acvity Documentaton Requirements and Inservce Summary Report Preparation and Submission," and the referenced NRC Safety Evaluation, which authoized use of Code Case N-532.4 at QCNPS (i.e., Relief Request ISR-09). Code Case N-532-4 requires an Onmees Activity Report Form OAR-1 to be prepared and certified upon completion of each refueling outage. In accordance with the conditions of Code Case N-532-4, this OAR-1 form is being submitted within ninety days of the completion of the refueling outage.The IVt results ame provided to report cmpleted vessel Internal inspections and to document B-N-1 and B-N-2 relief request exam completion.
Additionally, no welds were reclassified or chagW status within the IG$CC program this outage.
SVP-15-046 U.S. Nuclear Regulatory Commission page 2 Stould you have any questions conmemrng this letter, please contact Mr. Wally Beck, Regulatory Assurance Manager, at (309) 227-2800.Respectfulltv, amaDam Site Vie President Quad Cities Nulear Power Station Attachments:
: 1. Owner's Acdvity Report, Form QA1 2, Invessel Visual Inspadci Report cc: Regional Admnkdstor
-Region III NRC Resident .Inspect, Quad Cities Station Aftachment I Owners Aivity Report, Form OAR-1 RepotNe R.. .. ..efuelfn utm* , 01W mOAR-i.Unit ." Comi m Seovlc a& 1'73 R Ouae l r 0WWR23 Current !nspeceon intevlspck Itra Cb4jwn Inspedb ton POW~eta e14 II ~~to ero Cnanet 2007 Edtn wth 2008 Addenr (IS!), eMon eW AWmnd Sect; Xl opp:WkcAb te twInseon to ......m 1...o 200w3 A:Mde nda ft Dee/ Ivmon of Imspecto Plan. f/14 R .EdWWlo and Addmuba Of Seftion X appfla*e to fep Iakl/mpoamer aactivt it atfexent u"i fth vmectlo pums WA Code WCss uNe64: 9.32., N4 .CBam",'" oF coWmommP1Um I certiy ft (a) thme at"" ma In ath repeot amn com (b) the examM*m, WA teft meet "a Ispetion Plan as sequhrd by te ASI4E Cc&-, %eON XM W4 (C) thme rep/MpWseW PCUWYMS W4d 4V4&UMB SWippft the WffoMW~eI~
of g1W.Somm t the ro emn',ecrin XI (ieem ou-.4e nFe), tme un*dg, hdlhV, a vd oWWMn bMue$ b t Natimona od of 9o0r 8,0 PMeMMe Vessel bnet; and the ae or Me MseCteO tme Item e e i tO m Am stattat W We best o ofmy nmowWe md beW, Owner has peMbonc actf pmretd by tis report In acoda with the eWcgs of SectOn Gy si~ng ths ceiica mer mtm Mspectr m his ema -er nukes any wama expressed or Wpi conor" ft rqzlr/ecm ectMtl.,eS evaklton describ In Wie rept femore neier fme Inspctor nor his enmloyer sAMa be liable In any manner for ny p njury opropeM" dunege or a I= of aW imid arin ftmm or onnWnd vith ft neMo Cor.ns.ons
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AttaChment i Owners Activi* Reprt, Fom OAR-I None. NoneNon Attachment 1 Owners Activity Report, Form OAR-1 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code, Item Description Date Repair/Class Description Of Work Completed Replacement Plan Number MC Areas of X-2 Hatch Moisture Barrier Needs WO 01812660-Replaced Moisture Barrier 3/16/15 RRP 15-035 Replacing (IR 02463927)MC Bolting for the 1-3799-31 check valve was WO 01672243 -Bolting was replaced.
3/16/15 RRP 14-036 damaged during disassembly (02468850).
MC Bolting for the DW head was damaged during WO 01672501 -Bolting was replaced.
3/9/15 RRP 15-032 disassembly (IR 02462313).
Attachment 2 Invessel Visual Inspection Report The ASME Section Xl inspections credited during Q1 R23 IVVI activities include the once-per-period B-N-1 inspection of the reactor vessel interior and B-N-2 inspections of reactor vessel interior attachments.
Credit is being taken for the BWRVIP examinations in place of the B-N-1 and B-N-2 examinations in accordance with Quad Cities Station Relief Request 15R-06, "Request for Relief for the Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor Vessel Internals and Components Inspection In Accordance with 1 OCFR50.55a(a)(3)(i)
Alternative Provides Acceptable Level of Quality and Safety".To implement the requirements of the Boiling Water Reactor Vessel Internals Program (BWRVIP), GE-Hitachi (GEH) was contracted to perform the In-Vessel Visual Inspections (IVVI). The following components and assemblies were examined:* Visual inspections of the four Steam Dryer wall support lugs* Visual inspections of two Jet Pump Attachment welds RB-1* Visual inspections of six Upper Sample Bracket Attachments
* Visual inspections of six Lower Sample Bracket Attachments
* Visual inspections of four Upper Guide Rod Support Bracket Attachments
* Visual inspections of two Lower Guide Rod Support Bracket Attachments
* Visual inspections of Core Shroud Vertical welds V6, V29, V30, V31, and V32* RPV interior surfaces in areas near BWRVIP exams in accordance with Relief Request 15R-06.To implement the requirements of the Boiling Water Reactor Vessel Internals Program (BWRVIP), GE-Hitachi (GEH)was contacted to perform the In-Vessel Visual Inspections (IVVI) and Ultrasonic Testing (UT). The following components and assemblies were examined:* 67 components on jet pump assemblies in accordance with the BWRVIP-41 Rev. 3, "BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines".
* 38 core spray piping welds via visual exam in accordance with the BWRVIP-18 Revision i-A, "BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines".
* 16 core spray piping P4 welds via UT exam in accordance with the BWRVIP-18 Revision i-A, "BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines".
0 All 12 core spray sparger brackets, 50% of the sparger nozzle S3a/b welds (on the upper spargers), all 4 core spray sparger T-box cover S1 welds, 2 of 4 core spray lower sparger drain plug $3c welds, all 8 core spray sparger T-box S2 welds and all 8 of the sparger pipe end cap S4 welds in accordance with the BWRVIP-1 8 Revision 1-A, "BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines".
Attachment 2 Invessel Visual Inspection Report* 5 core shroud vertical welds in accordance with BWRVIP-76 Revision 1, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines".
e 4 Attachment welds for the steam dryer support lugs in accordance with BWRVIP-48-A, "Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines".
0 4 Attachment welds for the steam dryer guide rod support bracket in accordance with BWRVIP-48-A, "Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines".
e 2 Attachment welds for the steam separator guide rod support bracket in accordance with BWRVIP-48-A,"Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines".
* 12 Attachment welds for the surveillance sample holder brackets in accordance with BWRVIP-48-A, "Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines".
e Top guide rim weld at 20 cell locations in accordance with BWRVIP-26-A, "BWR Top Guide Inspection and Flaw Evaluation Guidelines".
0 4 top guide aligner assemblies in accordance with BWRVIP-48-A, "Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines".
* Steam dryer examinations of the tee to cap doubler welds. Dryer inspections were performed in accordance with BWRVIP-139-A, "Steam Dryer Inspection and Flaw Evaluation Guidelines".
In addition to the BWRVIP inspection guidance, the following augmented examinations were also performed as part of the Q1 R23 IVVI activities:
* 21 jet pump components not required by BWRVIP-41 Rev. 3, "BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines" per programmatic requirements.
* 2 Nuclear Instrument Dry Tubes in accordance with GEH SIL 409-Rev 4* Welds and flow-holes on 4 feedwater spargers per NUREG 0619* Selected cast austenitic stainless steel components in accordance with license renewal commitments.
* Re-inspection of mechanical damage at 1 steam separator location per programmatic requirements.
Multiple indications (gouges and rub marks) were identified on all four of the Steam Dryer wall support lugs. These indications were previously observed in Q1 R22. A comparison of the inspection results from Q1 R22 to Q1 R23 found no significant change to the previous indications and no new indications were identified.
These indications are documented in IR 2464537 and evaluated for continued service under EC 400050. Quad Cities will continue to monitor these conditions in accordance with the Reactor Internals Program.}}

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