RS-12-203, Supplement to Quad Cities Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-01

Supplement to Quad Cities Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-01

ML12333A262
Person / Time
Site:	Quad Cities
Issue date:	11/28/2012
From:	Simpson P Exelon Generation Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
RS-12-203
Download: ML12333A262 (4)

Text

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RS-12-203 RS-12-203 10 10 CFR CFR 50.55a 50.55a November28, November 28, 2012 2012 u.s.

U.S. Nuclear Regulatory Regulatory Commission Commission ATTN:

A Document Control TIN: Document Control Desk Washington,DC Washington, DC 20555-0001 Quad Cities Quad Cities Nuclear Power Station, Units 1 and 2 Station, Units Renewed FacilityFacility Operating Operating License License Nos. DPR-29 DPR -29 and DPR-30 NRC Docket Nos. Nos. 50-254 and 50-265 50-265

Subject:

Supplement to Quad Quad Cities Cities Nuclear NuclearPowerPowerStation StationFifth FifthInservice InserviceInspection Inspection Interval Interval Relief Request 15R-01 I5R-01

Reference:

Letter from D.

Letter from D. M.M. Gullott Gullott (Exelon (Exelon Generation Company, Company, LLC) to U.S. U.S. NRC, NRC, "Quad "Quad Cities Nuclear Nuclear PowerPower Station, Station,Units Units11and and2,2,Fifth FifthInterval Intervallnservice Inspection Inservice Inspection Program Program Plan Plan andand Relief Relief Requests,"

Requests," dated dated September 28, 2012 2012 In In the referenced letter, letter, Exelon Exelon Generation GenerationCompany, Company,LLC LLC (EGC)

(EGC) submitted submitted relief relief requests requests associated with the fifth inservice associated with the fifth inserviceinspection inspection(ISI)(lSI)interval interval for for Quad Quad Cities Cities Nuclear NuclearPower PowerStation Station (QCNPS), Units Units 11 and and 2.2. Upon Uponfurther furtherreview review of of Relief Relief Request Request15R-01, 15R-01, itit became becameapparent apparentthat that 10 10 CFR CFR 50.55a(a)(3) 50.55a(a)(3)(ii)(ii) isisthe theappropriate appropriaterelief reliefcriterion criterion for for this request.

request. Therefore, Therefore,EGCEGC requests requests toto supersede supersedethe theversion versionofof15R-01 15R-01ininthe thereferenced referencedletter letterwith with the the version version in in the the attachment attachment to to this thisletter letterin inits itsentirety.

entirety.

There There are are no no regulatory regulatory commitmen commitments ts contained in in this letter.

letter. Should Should youyou have haveany anyquestions questions concerning concerning this letter, please pleasecontact contactMr.Mr. Kenneth Kenneth M. M. Nicely at (630) 657-2803.

657-2803.

Respectfully, Patrick R. Simpson Manager - Licensing Attachment

Attachment:

10 10CFRCFR50.55a 50.55aRequest RequestNumber Number 15R-01,Revision 15R-01, Revision1 1 cc:

cc: NRC NRCRegional RegionalAdministrat Administrator, or, Region RegionIIIIII NRC NRCSenior SeniorResident ResidentInspector, Inspector,QuadQuadCities CitiesNuclear NuclearPower PowerStation Station

ATTACHMENT ATTACHMENT 10CFR 10 CFR SO.SSa 50.55a Relief Request Request 15R-01ISR-01 Revision Revision 1 (Page 11 of (Page of 3) 3)

Request for Request for Relief Relief for for Inspection Inspection of Standby Standby Liquid Liquid Control Nozzle Inner Radius Radius In Accordance In Accordance with 10 10 CFR SO.SSa(a)(3)(ii) 50.55a(a)(3)(ii)

Hardshipor Hardship orUnusual Unusual Difficulty Difficultywithout withoutCompensating Compensating Increase in Level of Quality Increase Quality and and Safety 1.

1. ASME Code Component(s)

ASME Component(s) Affected:

Code Class:

Code Class: 11

Reference:

IWB-2500, Table IWB-2500-1 IWB-2500, IWB-2500-1 Examination Category:

Examination B-D B-D Item Number:

Item B3.100 B3.100

Description:

Inspection of Inspection of Standby Liquid Control Nozzle Inner Radius Component Number:

Component Unit 1:

Unit 1: N10 Unit 2:

Unit 2: N10 Drawing Number:

Drawing Unit 1: M~3106 M73106 Sh. 11 Unit 2: M-3116 Sh. 11 Applicable

2. Code

2. Edition Applicable Code andEditionAddendand Addenda: a:

The Inservice Inspection Program is based based on onthe theAmerican American SocietySocietyof of Mechanical Mechanical Engineers (ASME) Boiler and Engineers (ASME) Boiler and PressureVessel Pressure Vessel(B&PV)

(B&PV) Code, Code, Section SectionXI, XI, 2007 2007Edition Edition through the 2008 Addenda.

Addenda.

Applicable 3.

3. Code Requir Applicable ement:

Code Requirement:

IWB-2500 states that components shall be be examined examined and and tested tested asasspecified specifiedinin Table Table IWB-2500-1 IWB-2500-1..

Table Table IWB-2500-1 IWB-2500-1 requires requires aa volumetric volumetric examination examination to to be beperformed performedon onthetheinner innerradius radius section section ofof all reactor pressure pressure vessel vesselnozzles nozzleseacheachinspection inspectioninterval.

interval.

Reason4. 4. forReason Reque st:

for Request:

Pursuant Pursuantto to1010CFR CFR50.55a(a)(3) 50.55a(a)(3)(ii),(ii), relief relief is is requested requestedon onthethebasis basisthat thatcompliance compliancewith with the Code requirement the Code requirements s impose imposehardship hardshipwithout withoutaacompensatin compensating increaseininthe g increase thelevel levelofof quality quality and and safety.

safety.

The TheStandby StandbyLiquid LiquidControl Control (SBLC)

(SBLC) nozzle, nozzle,as asshown shownininFigureFigure15R-01.1, 15R-01.1 ,isisdesigned designedwith with an anintegral integralsocket sockettotowhich whichthe theboron boroninjection injectionpiping piping isis fillet fillet welded. The TheSBLC SBLCnozzle nozzleisis located located near nearthethebottom bottom of of the the vessel vesselininananarea areawhich whichisisinaccessible inaccessiblefor forultrasonic ultrasonic examination s from the inside surface of the RPV.

examinations from the inside surface of the RPV. Therefore, Therefore,ultrasonic ultrasonicexamination examinations would s would need needtotobe beperformed performedfrom from thetheoutside outsidediameter diameterofofthe theRPV.

RPV.AsAsshown shownininFigure Figure15R-01.1, 15R-01.1, the theultrasonic ultrasonicbeam beamwouldwouldneedneedtototravel travelthrough throughthe thefull full thickness thicknessof ofthe thevessel vesselinto intoaa complex complexcladding/soc cladding/socket ket configuratio configuration. n. These Thesegeometric geometricand andmaterial materialreflectors reflectorsinherent inherentinin the thedesign designprevent preventa ameaningful meaningfulexamination examinationfrom frombeing beingperformed performedon onthe theinner innerradius radiusofof the theSBLC SBLCnozzle.

nozzle.

ATTACHMENT ATTACHMENT 10CFR 10 CFR 50.55a 50.55a Relief Request Request 15R-01 15R-01 Revision 1 Revision (Page (Page 22 of of 3) 3)

InInaddition, addition,the theinner innerradius radiussocket socketattaches attaches to the piping piping which which injects injects boron boron at at locations locations far far removed from the nozzle.

removed from the nozzle. Therefore, Therefore, the SBLC SBLC nozzle nozzle inner inner radius radius is is not not subjected subjected to to turbulentmixing turbulent mixingconditions conditionsthat thatare areaaconcern concern at at other other nozzles.

nozzles.

Compliance with Compliance withthetheapplicable applicableCodeCode requirements requirements wouldwould require require an an ultrasonic examination to be to be performed performed on on the the outside diameter of the the RPV. Geometric and RPV. Geometric and material material reflectors reflectors wouldprevent would preventaa meaningful meaningfulexamination, examination,resulting resultinginininaccurate inaccuratedata.

data. Based on this, the the Code requirements Code requirements impose hardship hardship without without a compensating increasein compensating increase in the the level level of quality quality and safety in accordance and accordance with with 10 10 CFR CFR 50.55a(a)(3) 50.55a(a)(3)(ii).

(ii).

5.

5. Proposed Alternative Proposed Alternative and and Basis for Use:

As an alternate As alternate examination examination, , Exelon ExelonGeneration GenerationCompany, Company,LLC LLCwill willperform performaaVT-2 VT-2visual visual examination of examination of the the subject subject nozzles at at Quad Quad Cities Cities Nuclear Nuclear Power Power Station, Station, Units Units 11 and and 2,2, each refueling outage in conjunction refueling outage conjunction withwiththe theClass Class 11 System System Leakage Test.

Duration 6.

6.

of Propos Duration of ed Alterna Proposed tive:

Alternative:

Relief isis requested Relief requested for the FifthFifth Ten-Year Inspection IntervalInterval Quad Cities Nuclear Power Power Station Units 1 and 2.

Preceden 7.

7. ts:

Precedents:

Quad Cities Cities Nuclear Nuclear Power Power Station, Station, Units Units 11and and2,2,fourth fourthinspection inspectioninterval intervalrelief relief request 14R-01 14R-01 was was authorized authorized in in an an NRC NRC safety evaluation evaluation dated January 28, dated January 28,2004.

2004.

The Fifth Fifth inspection interval interval relief relief request utilizes utilizes aa similar similar approach approach thatthatwas waspreviously previously approved.

Dresden Dresden NuclearNuclear Power PowerStation, Station, Units Units 22and and3,3,fourth fourth inspection inspection interval interval relief relief request request 14R-01 14R-01 was was authorized authorized in in an an NRC NRC safety evaluation dated September September4,4,2003.2003.

ATTACHMENT ATTACHMENT 10CFR 10 CFR50.55a 50.55a Relief Relief Request 15R-01 15R-01 Revision 11 Revision (Page33of (Page of3) 3)

FIGURE 15R-01.1 FIGURE 15R-01.1 22 INCH INCHSTANDBY STANDBY LIQUI LIQUID D CONTROL CONTROL NOZZLE NOZZLE 6 1/4" Cladding Cladding Safe-End Pipe (Stainless Steel) Nozzle Pipe (Stainle ss Stee (Stainless Steel) 1.453" 1/8" Min

/

3/4" R Min 6 3/8"--- 3 3/4"