SVP-14-057, Owner'S Activity Report Submittal Fifth 10 Year Interval 2014 Refueling Outage Activities: Difference between revisions

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{{#Wiki_filter:SVP-14-0871, 2014 U. a Nucar Reuloy Comission ATTN: Document Control Desk Wasi .oDC 20555M001 Ouad Cities Nuclear Power Motion, Units 1 and 2 R wd Facty Operatg" Licenee Nos. "-29 and DP-0 Suet .Owners ActMty Rep t Subme(FMilh 10-Year 2014 Refueling Outage Activities Reerncs:1)
{{#Wiki_filter:SVP-14-087 AUgt* 1, 2014 U.a Nucar Reuloy Comission ATTN: Document Control Desk Wasi         .oDC 20555M001 Ouad Cities Nuclear Power Motion, Units 1 and 2 R     wd Facty Operatg" Licenee Nos. "-29           and DP-0 Suet           .OwnersActMty Rep t Subme(
Letter from T. Tals, (USNRC) to K. Pacillio (Exelon).  
FMilh 10-Year kfe*al 2014 Refueling Outage Activities Reerncs:1) Letter from T.Tals,(USNRC) to K.Pacillio (Exelon). %QuadCities Nuclear Power Station, Units I and 2- Saty Evaluation inSuppor of Request for Relief Associated with the Filth 10 Yea Interval Inservice Inspection Progrmn, dded Septene 30, 201
%Quad Cities Nuclear Power Station, Units I and 2- Saty Evaluation in Suppor of Request for Relief Associated with the Filth 10 Yea Interval Inservice Inspection Progrmn, dded Septene 30, 201 2) Letter from T. tarly (Exelon) to USNG, V*0-ay Post Outa 181 LeW, dated July 5, 2013 This lWater saf s the Owner's Activity Report (Le.. Forto OAR-i) and Inveesel Visual Irspecon (IWi) Report for the Oud Ciies Nuclear Power Station (0CNS) Unit 2 ruing outage (Q2R22) which began on Aprll 7, 2014, and wea ompleted on May 7,2014. This Is the first reuln ouage, conduced in the frst ispecdon period of the ffth 10-year mevce inspection Innil for QCNPS Unit 2. A copy of the Owners Activity Report and IWI Report a provided as anen I and 2 to Ofts letter.This Ownsers Activity Repor is submitted in accodance with Amnerican Society of Mechanica Enginer* (ASME) Boi and Pressure vessel Code Casn N-534, Repeir/Replaosment Activity DocIUMentaIOn Requirementsm and inservics, Summary Repor Prepwaraon and Subnm ,* and the Relfeence I NRC Safety Evaluation, which authorized use of Code Can N-M32-4 at QCNPS (Le., Relief Request ISR-00). Code Cas N-532-4 require an Ownses Ac*ty Report Form OAR-i to be prepared and certified upon completio of each refuein outage. In accordance with the condiions of Code Cae N-*M3-4, thi OAR-1 form is bein within ninety days of the completion of the refueling outage.The I-I results are, provided to repot completed vessel internal Inspections mid to document B-N-I and S-N-2 reele request exam completion.
: 2) Letter from T. tarly (Exelon) to USNG, V*0-ay Post Outa 181 LeW, dated July 5, 2013 This lWater saf s the Owner's Activity Report (Le.. Forto OAR-i) and Inveesel Visual Irspecon (IWi) Report for the Oud Ciies Nuclear Power Station (0CNS) Unit 2 ruing outage (Q2R22) which began on Aprll 7, 2014, and wea ompleted on May 7,2014. This Is the first reuln ouage, conduced inthe frstispecdon period of the ffth 10-year mevce inspection Innil for QCNPS Unit 2. A copy of the Owners Activity Report and IWI Report a provided as anen I and 2 to Ofts letter.
Additlonafly, no wefte were reclassified or-hne statu within the 108C prora this outage.
This Ownsers Activity Repor issubmitted inaccodance with Amnerican Society of Mechanica Enginer* (ASME) Boi       and Pressure vessel Code Casn N-534, Repeir/Replaosment Activity DocIUMentaIOn Requirementsm and inservics,Summary Repor Prepwaraon and Subnm ,*and the Relfeence I NRC Safety Evaluation, which authorized use of Code Can N-M32-4 at QCNPS (Le., Relief Request ISR-00). Code Cas N-532-4 require an Ownses Ac*ty Report Form OAR-i to be prepared and certified upon completio of each refuein outage. In accordance with the condiions of Code Cae N-*M3-4, thi OAR-1 form is bein su*mitted within ninety days of the completion of the refueling outage.
August 1, 2014 U.S. fOuclew Regulatory Commission Page2 Finaly, Attadvcent 3 indcldes a convrcted NIS-2 (from the fouth -10yjer inservie ksection interv) that was pmviously  
The I-I results are, provided to repot completed vessel internal Inspections mid to document B-N-I and S-N-2 reele request exam completion. Additlonafly, no wefte were reclassified or
*u&Moted in Refemnce 2.Shok you have wy questions concerning ft lter, plae wta A. Way amck, Fegulaory Aiswance Manager, at (309) 227-2e00.Rin cariny, Sit Veice Predn Quad Ces Nuclear Power Station A~mdwtntM-.
    -hne statu within the 108C prora this outage.
: 1. Ownes Activity Repoit Form OAR-I 2. tuwes Vu ktsdkon Report 3. RvlWd form NIS-2 OWr-s Report of Repir or R from 4 k*rm cc: Regional ftefto- Region NI NRC Senito Reedert Irnpeclor.
 
Quad CitiWam Station Attachment 1 Owners Activity Report, Form OAR-1 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number Plant Unit No. 2 (if applicable)
August 1, 2014 U.S.
Current Inspection Interval Current Inspection Period Refueling Outage Q2R22 OAR-1 Quad Cities Nuclear Power Station, 22710 206t" Ave. North, Cordova, IL 61242 Commercial Service Date 03/10/1973 Refueling Outage Number Q2R22 5P' Inspection Interval (ISI), 214 Inspection Interval (Containment)
Page2 fOuclew Regulatory Commission Finaly, Attadvcent 3 indcldes a convrcted NIS-2 (from the fouth -10yjer inservie ksection interv) that was pmviously *u&Moted in Refemnce 2.
(1", 2ý', 3Y, 4h, other)15ý Inspection Period (ISI), 2"d Inspection Period (Containment)(I", 2", 3")2007 Edition with 2008 Addenda (ISI), Edition and Addenda of Section XI applicable to the Inspection Plans 2001 Edition with 2003 Addenda (Containment)
Shok you have wy questions concerning ft lter, plae wta A. Way amck, Fegulaory Aiswance Manager, at (309) 227-2e00.
Date / Revision of Inspection Plans 9/19/12/Revision 0 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-532-4 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, Sectionr XI; and (c) the repair/replacement activities and evaluations supporting the completion of Q2R22 conform to the requirements of Section XI (refueling outage number)Signed Z e-. I Coordinator Date 7/.,2&/s-Towner or Owner's desgnee. TItle)I 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 Illinois and employed by HSB Global Standards 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
Rin cariny, Sit Veice Predn Quad Ces Nuclear Power Station A~mdwtntM-. 1.Ownes Activity Repoit Form OAR-I
....___/-_ _ Commissions IL 2211; NB13175 A, N, I f -(Inspector's Signature)
: 2. tuwes Vu ktsdkon Report
National Board, State, Province, and Endorsements Date z i -. \4 A#Mmwi Omwne AM" Pprt Form OAR-1 TOME I-IO1 wwu MOGRWaRO COuuMMI WWmPi QtW citft "~ 2 bftimut *uzi 3-Gomo WW L" PFsw eA*99Wc (Docane*Ift N.32-W215236-002)
: 3. RvlWd form NIS-2 OWr-s Report of Repir or R             from 4 k*rm cc:     Regional       ftefto- Region NI NRC Senito Reedert Irnpeclor. Quad CitiWam Station
O-P, 615.10 Ppv water **vel borumet Penetration-2r Um"i Pope sin Rd ML 140SM22 -Quid itles Nu'Jem Powr Sati, t**1 2- Saftty Emuko~n Rqepwln RMW Requet ISR-11 For Relie________________________________________________For Pendration N-1i 8 ftevulr (T-AC NO. PF1462)
 
AdaohmtI 1 Ownwe A FvityRom.
Attachment 1 Owners Activity Report, Form OAR-1 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number                                                           Refueling Outage Q2R22 OAR-1 Plant                                    Quad Cities Nuclear Power Station, 22710 206t" Ave. North, Cordova, IL 61242 Unit No.                2              Commercial Service Date               03/10/1973                 Refueling Outage Number               Q2R22 (if applicable)
Form OAR-1 T#AIL 2 qm d --. ..... .. ..A~ (WM loller 3 N" M own (IR. WO 14S447 -New hwS whcts e m, 2/19/13 RWP 12-047, 12-147036S) prior to pttn kft 074, 12-068 3 2-5746-A -2A RHR ROOM COOLER "HAS WO 1671617 -and weld .epa. 2A RR 9/11/13 RRP 13-081 TU8ESHEET CORROSiON THAT NEEDS REPAIR room cooler tbewshetand Iw k l tb~epl... ...... ..... .... .. .....(.IR 01556124)
Current Inspection Interval                              5P' Inspection Interval (ISI), 214 Inspection Interval (Containment)
_ _ _ _ _ _ _ _ _ _ __ _ _ __._ _ _ _ _ __ _ _ _ _ _ _ _ _ _3 Leek found o LINE 2-1011 S. to the 25 WO 1710206 -29 ARSW Cubide Cooler pipe 2/7/14 RRP 14-010 RHRtSW Cubicle Cooler (It 1617892) replacemeat mC Ara of X-2 .... et"iS..........d.
(1", 2ý', 3Y,4h, other)
WO 1730517 -Reaced Mm Bter 4/2514 RR0 14-027......... .... " dnc --r f IR 1 4,7 16) .... ...... ............
Current Inspection Period                                  15ý Inspection Period (ISI), 2"d Inspection Period (Containment)
_ _ _ _ __.... ........ ._
(I", 2", 3")
Attahent 2 The ASME Section XI inspections credited during 02R22 IVVI activities include the once-per-period 8-N-1 Inspection of the reactor vessel Interior and B.N-2 inspections of reactor vessel erior attachment Credt Is beg taken for the BWRVIP examninations in place of the BN-1 and *N-2 examinations in acco ,ace wth Quad Ciies Station Relief Request 15R-06, 'Request for Re"ef for the Use of BWRVIP Guidelines In Lieu of Specifi ASME Code Requirements on Reacor Vessel oW nals , Comnponents inspection In Acoordame with I0CFRS0.55a(&)(3)(l)
2007 Edition with 2008 Addenda (ISI),
Alternative Provides Acceptbl e Level of Quality and Sfetw.To iniplement thO requireomoes of th Boiling Watr Reactor Vessel Internals Program (BWRVIP), GE was contracted to perform the In-Vesel Visual Inspections (IWV). The following components and assemnbies were examined: " Visual Inspections of the Stem Dryer wall support hip" Visual inspections of Core Shroud Vertical welds V5, V6, VT, V26, V27, and V28" Visual Inspection of Inshument Nozzle Upper and Lower RPV interior surfaces To irnplement the requi ments of the Boi Water Reactor Vessel Internals PrgI (BWAVIP), GE was contacted to perform the In-Vessel Visua Inspectins (IVVI. The followhing o -mponets and assemblies wower amned:* 42 comnponts on jet pump assembles, including UT on 20 jet pump bams, in accordance with the BWRVIP-41 Rev. 3, BWR Jet P"mp Assweby Inspecton and Flew Evaluation Guideles'.
Edition and Addenda of Section XI applicable to the Inspection Plans                     2001 Edition with 2003 Addenda (Containment)
* 36 core spray piping welds in accordance with the BWRVIP-18 Revision I-A,"BWR Core Spray Intnals Inspect and Flaw Evalkuion Guidi'.* AN of the woe spray sparger bracets 50% of the sparger nozzle weldse, andl all of the sparge pipe end cop welfs In accorda with WRVIP-1 8 Revision 1-A. 1BWR Core Spray Internals Inspection and Flaw Evaluation Guideline'.
Date / Revision of Inspection Plans                                                     9/19/12/Revision 0 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used:                                                                     N-532-4 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, Sectionr XI; and (c) the repair/replacement activities and evaluations supporting the completion of                         Q2R22 conform to the requirements of Section XI                                                                                     (refueling outage number)
* 6 core shroud vertical welds in accordance with 8WRVP-.76 Revision 1, BWR Core Shroud Inspectio and Flaw Ev*aui Guidelines.
Signed       Z       e-.                       I Coordinator                                     Date         7/.,2&/s I
* 4 Attachment welds for the steam dryer support lugs in sccordance with BWRVIP-48-A, "Vesel ID Attachlment Weld Inspection and Flaw Evaluation Guidelles¶.
                                  -Towner or Owner's desgnee. TItle)
* Steam dryer examinations of the tee to cap doubler welcls. Dryer inspections were perfomned in ordance with BWRVIP-1 30-A, "Stemm Dryer Inspection and Flaw Evaluation Guidelinsl'.
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                 Illinois             and employed by         HSB Global Standards             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/
Attacvin 2 Inve" Vwual I k Report In addition to the BWRVIP inspection guidance, the following augmented examinations were also pertormed as part of the M2R22 IWI activities:
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
* 48 jet pump component not requred by BWRVIP41 Rev. 3, *BWR Jet Pump Assweml It and Flaw Evaluation Guldelines" per progWammat req"irements.
    ....                     ___/-_                 _           Commissions                       IL 2211; NB13175 A, N, I f     -       (Inspector's Signature)                                   National Board, State, Province, and Endorsements Date       zi    -. \4
* Selected cas audtenntc sainles stee coomponents (CASS) In acooa*nce woh Nkow" renewal coml nme&tL* .,Accessbile Intlor sufaoes on fomu trumen nozfes p Or p requrenenfts Se of mech a damage t 3 stm seperator locations per* Rirpecton of mehanical d age at 3 ~tam dyr loc.atins per Multple indications (goges and rub ma ) were Ieie on all four of the Stawm Dryer wall support us. These iiao were pmrviouy oberved In (R1. A comparlson of the inspection reults from Q2FI to 02R22 fumnd no apparent chage to the pvAous indications and no new Indications were Idenrfied.
 
These indications are documnted In IR 1648006 and evalualted for continued service under EC 3 .ud Cities wi contnue to montor th condition in isccorýldance wit the Reaclor kinteas Program.
A#Mmwi Omwne AM" Pprt Form OAR-1 TOME I
Attachment 3 Revised form NIS-2 Owners Report of Repair or Replacement from 4th Interval PMSM0Wft JMPmS ai XP MWAU(ORmACMWr As beqund by 6w Pvoswim. 4ASWE Ca& Sio 91 Milo0 2OW Ave. MaO,* Cmdowa H, fi342 3. W4*% iwby: OW- wfmi w amu WOAim I'm c -k9n"%A-nm m"O.;NA (b) Appm a fScio5UgV3 VXWufm *s or 3.ammm Zd~ i dof MU 0 j:0 9 l-mi,, -CR"AW (W CNw --Tvcui of CA* -W tagi lb___________t u _________(XW~~tm~wpfn V*SCM. hWmmqe by OIaCM f~twv b vEalbr pmjvtu l~SW*vSWru
                                          -IO1     wwu MOGRWaRO             COuuMMI WWmPi QtW citft "~ 2 bftimut *uzi 3-Gomo WW L" PFsw eA*99Wc (Docane*IftN.32-W215236-002)
_ LEM mdv, hyd~ 4_ mIM~"ift tv *"o tr~t*emmee is *s4 WW' Pap"h-hww,"e*
O-P, 615.10             Ppv water **vel borumet Penetration- 2r Um"i Pope sin         Rd ML 140SM22 - Quid itles Nu'Jem Powr Sati, t**1 2- Saftty Emuko~n Rqepwln RMW Requet ISR-11 For Relie
lmac mools 4~ vlez AAW tki iwap~m toin ax~p waý or PNWY a"13 Oratwl ff2m}}
________________________________________________For                                  Pendration N-1i 8 ftevulr (T-AC NO. PF1462)
 
AdaohmtI1 Ownwe         A             FvityRom. Form OAR-1 T#AIL 2
    *-       ....                                       A~ (WM                                  loller                                                                  .. qm d I--*ofotC        --.     ...
3           N"
* M                         own             (IR. WO 14S447 - New hwS                   whcts             e       m,       2/19/13     RWP 12-047, 12-147036S)                                                     prior to pttn kft swer*ve.                                          074, 12-068 3                 2-5746-A -2A RHR ROOM COOLER "HAS                                       WO 1671617           - Excv*ate and weld           2A RR .epa.       9/11/13         RRP 13-081
...  ...... . .
TU8ESHEET
                  . ..       .... ..
CORROSiON THAT NEEDS REPAIR
                                            . .... (.IR 01556124)                                 _
room      cooler tbewshetand
_ _ _ _ _ _ _ _ _               __
k _ l_ tb~epl Iw      __._           _ _ _ _   __ _ _ _ _ _ _   _ _ _
3              Leek found o LINE 2-1011 S. -*Dto the 25                                       WO 1710206 - 29 ARSW Cubide Cooler pipe                               2/7/14         RRP 14-010 RHRtSW Cubicle Cooler (It 1617892)                                                               replacemeat mC                 Ara of X-2                               et"iS..........d.
                                                                    &*oftd*        ....              WO 1730517 - Reaced               Mm     Bter                   4/2514         RR0 14-027
            .     .     .......       ....       "   dnc
* f r--IR1 4,7 16) . ... ...... ............   ........   ._                            _ _ _ _ __....
 
Attahent 2 The ASME Section XI inspections credited during 02R22 IVVI activities include the once-per-period 8-N-1 Inspection of the reactor vessel Interior and B.N-2 inspections of reactor vessel erior attachment Credt Is beg taken for the BWRVIP examninations in place of the BN-1 and *N-2 examinations in acco       ,acewth Quad Ciies Station Relief Request 15R-06, 'Request for Re"ef for the Use of BWRVIP Guidelines In Lieu of Specifi ASME Code Requirements on Reacor Vessel   oW nals   ,       Comnponents inspection InAcoordame with I0CFRS0.55a(&)(3)(l) Alternative Provides Acceptbl e Level of Quality and Sfetw.
To iniplement thO requireomoes of th Boiling Watr Reactor Vessel Internals Program (BWRVIP), GE was contracted to perform the In-Vesel Visual Inspections (IWV). The following components and assemnbies were examined:
      " Visual Inspections of the Stem Dryer wall support hip
      " Visual inspections of Core Shroud Vertical welds V5, V6, VT, V26, V27, and V28
      " Visual Inspection of Inshument Nozzle Upper and Lower RPV interior surfaces To irnplement the requi   ments of the Boi     Water Reactor Vessel Internals PrgI (BWAVIP), GE was contacted to perform the In-Vessel Visua Inspectins (IVVI. The followhing o -mponets     and assemblies woweramned:
* 42 comnponts on jet pump assembles, including UT on 20 jet pump bams, in accordance with the BWRVIP-41 Rev. 3, BWR Jet P"mp Assweby Inspecton and Flew Evaluation Guideles'.
* 36 core spray piping welds in accordance with the BWRVIP-18 Revision I-A, "BWR Core Spray Intnals Inspect and Flaw Evalkuion Guidi'.
* AN of the woe spray sparger bracets 50% of the sparger nozzle weldse, andl all of the sparge pipe end cop welfs In accorda     with th* WRVIP-1 8 Revision 1-A. 1BWR Core Spray Internals Inspection and Flaw Evaluation Guideline'.
* 6 core shroud vertical welds in accordance with 8WRVP-.76 Revision 1, BWR Core Shroud Inspectio and Flaw Ev*aui           Guidelines.
* 4 Attachment welds for the steam dryer support lugs in sccordance with BWRVIP-48-A, "Vesel IDAttachlment Weld Inspection and Flaw Evaluation Guidelles¶.
* Steam dryer examinations of the tee to cap doubler welcls. Dryer inspections were perfomned in     ordance with BWRVIP-1 30-A, "Stemm Dryer Inspection and Flaw Evaluation Guidelinsl'.
 
Attacvin 2 Inve"   Vwual I     k Report In addition to the BWRVIP inspection guidance, the following augmented examinations were also pertormed as part of the M2R22 IWI activities:
* 48 jet pump component not requred by BWRVIP41 Rev. 3, *BWR Jet Pump Assweml It           and Flaw Evaluation Guldelines" per progWammat req"irements.
* Selected cas audtenntc sainles stee coomponents (CASS) In acooa*nce woh Nkow" renewal coml nme&tL
    * .,Accessbile Intlor sufaoes on fomu trumen nozfes p           pOr requrenenfts Se               of mech     a damage t 3 stm seperator locations per
* Rirpecton of mehanical d age at 3 ~tam dyr loc.atins per Multple indications (goges and rub ma ) were Ieie on all four of the Stawm Dryer wall support us. These iiao           were pmrviouy oberved In(R1. A comparlson of the inspection reults from Q2FI to 02R22 fumnd no apparent chage to the pvAous indications and no new Indications were Idenrfied. These indications are documnted InIR 1648006 and evalualted for continued service under EC 3         . ud Cities wi contnue to montor th       condition in isccorýldance wit the Reaclor kinteas Program.
 
Attachment 3 Revised form NIS-2 Owners Report of Repair or Replacement from 4th Interval
 
PMSM0Wft JMPmS     ai         XP MWAU(ORmACMWr As beqund by 6w Pvoswim.4ASWE Ca& Sio 91 amu      WOAim Milo0 2OW Ave. MaO,*Cmdowa H,fi342
: 3. W4*% iwby:           OW-     wfmi       w I'm c A-nm m"O.;
                                                                              -k9n"%
NA (b) Appm         a   fScio5UgV3 VXWufm     *s   or 3.ammm       Zd~   i   MU dof   j:0 0
9 l-mi,,     -
CR"AW (W CNw                                                 --
Tvcui of CA*   -W tagi lb___________t                                         u     _________
(XW~~tm~wpfn hWmmqe V*SCM.             by OIaCM   bf~twv vEalbr   pmjvtu   l
~SW*vSWru     _ LEM     mdv,     hyd~     4_       mIM~"ift       tv *"o                     tr~t
    *emmee is*s4 WW'             Pap"h-hww,"e*       lmac   moolsvlez  4~ AAWtki  iwap~m toinax~p     waý or PNWY Oratwl a"13 ff2m}}

Revision as of 01:35, 4 November 2019

Owner'S Activity Report Submittal Fifth 10 Year Interval 2014 Refueling Outage Activities
ML14224A005
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 08/01/2014
From: Darin S
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
SVP-14-057
Download: ML14224A005 (9)


Text

SVP-14-087 AUgt* 1, 2014 U.a Nucar Reuloy Comission ATTN: Document Control Desk Wasi .oDC 20555M001 Ouad Cities Nuclear Power Motion, Units 1 and 2 R wd Facty Operatg" Licenee Nos. "-29 and DP-0 Suet .OwnersActMty Rep t Subme(

FMilh 10-Year kfe*al 2014 Refueling Outage Activities Reerncs:1) Letter from T.Tals,(USNRC) to K.Pacillio (Exelon). %QuadCities Nuclear Power Station, Units I and 2- Saty Evaluation inSuppor of Request for Relief Associated with the Filth 10 Yea Interval Inservice Inspection Progrmn, dded Septene 30, 201

2) Letter from T. tarly (Exelon) to USNG, V*0-ay Post Outa 181 LeW, dated July 5, 2013 This lWater saf s the Owner's Activity Report (Le.. Forto OAR-i) and Inveesel Visual Irspecon (IWi) Report for the Oud Ciies Nuclear Power Station (0CNS) Unit 2 ruing outage (Q2R22) which began on Aprll 7, 2014, and wea ompleted on May 7,2014. This Is the first reuln ouage, conduced inthe frstispecdon period of the ffth 10-year mevce inspection Innil for QCNPS Unit 2. A copy of the Owners Activity Report and IWI Report a provided as anen I and 2 to Ofts letter.

This Ownsers Activity Repor issubmitted inaccodance with Amnerican Society of Mechanica Enginer* (ASME) Boi and Pressure vessel Code Casn N-534, Repeir/Replaosment Activity DocIUMentaIOn Requirementsm and inservics,Summary Repor Prepwaraon and Subnm ,*and the Relfeence I NRC Safety Evaluation, which authorized use of Code Can N-M32-4 at QCNPS (Le., Relief Request ISR-00). Code Cas N-532-4 require an Ownses Ac*ty Report Form OAR-i to be prepared and certified upon completio of each refuein outage. In accordance with the condiions of Code Cae N-*M3-4, thi OAR-1 form is bein su*mitted within ninety days of the completion of the refueling outage.

The I-I results are, provided to repot completed vessel internal Inspections mid to document B-N-I and S-N-2 reele request exam completion. Additlonafly, no wefte were reclassified or

-hne statu within the 108C prora this outage.

August 1, 2014 U.S.

Page2 fOuclew Regulatory Commission Finaly, Attadvcent 3 indcldes a convrcted NIS-2 (from the fouth -10yjer inservie ksection interv) that was pmviously *u&Moted in Refemnce 2.

Shok you have wy questions concerning ft lter, plae wta A. Way amck, Fegulaory Aiswance Manager, at (309) 227-2e00.

Rin cariny, Sit Veice Predn Quad Ces Nuclear Power Station A~mdwtntM-. 1.Ownes Activity Repoit Form OAR-I

2. tuwes Vu ktsdkon Report
3. RvlWd form NIS-2 OWr-s Report of Repir or R from 4 k*rm cc: Regional ftefto- Region NI NRC Senito Reedert Irnpeclor. Quad CitiWam Station

Attachment 1 Owners Activity Report, Form OAR-1 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number Refueling Outage Q2R22 OAR-1 Plant Quad Cities Nuclear Power Station, 22710 206t" Ave. North, Cordova, IL 61242 Unit No. 2 Commercial Service Date 03/10/1973 Refueling Outage Number Q2R22 (if applicable)

Current Inspection Interval 5P' Inspection Interval (ISI), 214 Inspection Interval (Containment)

(1", 2ý', 3Y,4h, other)

Current Inspection Period 15ý Inspection Period (ISI), 2"d Inspection Period (Containment)

(I", 2", 3")

2007 Edition with 2008 Addenda (ISI),

Edition and Addenda of Section XI applicable to the Inspection Plans 2001 Edition with 2003 Addenda (Containment)

Date / Revision of Inspection Plans 9/19/12/Revision 0 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-532-4 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, Sectionr XI; and (c) the repair/replacement activities and evaluations supporting the completion of Q2R22 conform to the requirements of Section XI (refueling outage number)

Signed Z e-. I Coordinator Date 7/.,2&/s I

-Towner or Owner's desgnee. 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 Illinois and employed by HSB Global Standards 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

.... ___/-_ _ Commissions IL 2211; NB13175 A, N, I f - (Inspector's Signature) National Board, State, Province, and Endorsements Date zi -. \4

A#Mmwi Omwne AM" Pprt Form OAR-1 TOME I

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Attahent 2 The ASME Section XI inspections credited during 02R22 IVVI activities include the once-per-period 8-N-1 Inspection of the reactor vessel Interior and B.N-2 inspections of reactor vessel erior attachment Credt Is beg taken for the BWRVIP examninations in place of the BN-1 and *N-2 examinations in acco ,acewth Quad Ciies Station Relief Request 15R-06, 'Request for Re"ef for the Use of BWRVIP Guidelines In Lieu of Specifi ASME Code Requirements on Reacor Vessel oW nals , Comnponents inspection InAcoordame with I0CFRS0.55a(&)(3)(l) Alternative Provides Acceptbl e Level of Quality and Sfetw.

To iniplement thO requireomoes of th Boiling Watr Reactor Vessel Internals Program (BWRVIP), GE was contracted to perform the In-Vesel Visual Inspections (IWV). The following components and assemnbies were examined:

" Visual Inspections of the Stem Dryer wall support hip

" Visual inspections of Core Shroud Vertical welds V5, V6, VT, V26, V27, and V28

" Visual Inspection of Inshument Nozzle Upper and Lower RPV interior surfaces To irnplement the requi ments of the Boi Water Reactor Vessel Internals PrgI (BWAVIP), GE was contacted to perform the In-Vessel Visua Inspectins (IVVI. The followhing o -mponets and assemblies woweramned:

  • 42 comnponts on jet pump assembles, including UT on 20 jet pump bams, in accordance with the BWRVIP-41 Rev. 3, BWR Jet P"mp Assweby Inspecton and Flew Evaluation Guideles'.
  • AN of the woe spray sparger bracets 50% of the sparger nozzle weldse, andl all of the sparge pipe end cop welfs In accorda with th* WRVIP-1 8 Revision 1-A. 1BWR Core Spray Internals Inspection and Flaw Evaluation Guideline'.
  • 6 core shroud vertical welds in accordance with 8WRVP-.76 Revision 1, BWR Core Shroud Inspectio and Flaw Ev*aui Guidelines.
  • 4 Attachment welds for the steam dryer support lugs in sccordance with BWRVIP-48-A, "Vesel IDAttachlment Weld Inspection and Flaw Evaluation Guidelles¶.
  • Steam dryer examinations of the tee to cap doubler welcls. Dryer inspections were perfomned in ordance with BWRVIP-1 30-A, "Stemm Dryer Inspection and Flaw Evaluation Guidelinsl'.

Attacvin 2 Inve" Vwual I k Report In addition to the BWRVIP inspection guidance, the following augmented examinations were also pertormed as part of the M2R22 IWI activities:

  • 48 jet pump component not requred by BWRVIP41 Rev. 3, *BWR Jet Pump Assweml It and Flaw Evaluation Guldelines" per progWammat req"irements.
  • Selected cas audtenntc sainles stee coomponents (CASS) In acooa*nce woh Nkow" renewal coml nme&tL
  • .,Accessbile Intlor sufaoes on fomu trumen nozfes p pOr requrenenfts Se of mech a damage t 3 stm seperator locations per
  • Rirpecton of mehanical d age at 3 ~tam dyr loc.atins per Multple indications (goges and rub ma ) were Ieie on all four of the Stawm Dryer wall support us. These iiao were pmrviouy oberved In(R1. A comparlson of the inspection reults from Q2FI to 02R22 fumnd no apparent chage to the pvAous indications and no new Indications were Idenrfied. These indications are documnted InIR 1648006 and evalualted for continued service under EC 3 . ud Cities wi contnue to montor th condition in isccorýldance wit the Reaclor kinteas Program.

Attachment 3 Revised form NIS-2 Owners Report of Repair or Replacement from 4th Interval

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