L-15-012, Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation
| ML15154B199 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/02/2015 |
| From: | Harkness E FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EA-12-051, L-15-0128, TAC MF0802 | |
| Download: ML15154B199 (29) | |
Text
{{#Wiki_filter:FENOC' ~ Perry Nuclear Power Plant PO. Box 97 10 Center Road FirstEnergy Nuclear Operating Company Perry, Ohio 44081 Ernest J. Harkness 440-280-5382 Vice President Fax: 440-280-8029 June 2, 2015 L-15-128 10 CFR 2.202 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-001
SUBJECT:
Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Completion of Required Action by NRC Order EA-12-051. Reliable Spent Fuel Pool Instrumentation (TAC No. MF0802) On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, to FirstEnergy Nuclear Operating Company (FENOC). This Order was effective immediately and directed FENOC to have a reliable indication of the water level in associated spent fuel storage pools for the Perry Nuclear Power Plant (PNPP) as outlined in Attachment 2 of the Order. This letter, along with its attachments, provides the notification required by Section IV.C.3 of the Order that full compliance with the requirements described in Attachment 2 of the Order has been achieved for PNPP. This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at 330-315-681 0. I declare under penalty of perjury that the foregoing is true and correct. Executed on June Z- , 2015.
PerryNuclearPowerPlant L-15-',129 Page2 Attachments:
- 1. Compliance withOrderEA-12-051
- 2. NRCRequestsfor Information cc: Director,Officeof NuclearReactorRegulation(NRR)
NRCRegionlll Administrator NRCResidentInspector NRCProjectManager Ms.LisaM. Regner,NRR/JLD/PMB, NRC Mr.BlakeA. Purnell,NRR/JLD/PMB, NRC
Attachment1 L-15-128 Compliance withOrderEA-12-051 Page1 of 4 BACKGROUND On March12,2012,the NuclearRegulatory Commission (NRC)issuedOrder EA-12-051, OrderModifying LicenseswithRegardto ReliableSpentFuelPool Instrumentation (Reference 1),to FirstEnergy NuclearOperating Company(FENOC). ThisOrderwas effectiveimmediately anddirectedFENOCto havea reliableindication of the waterlevelin associated spentfuel storagepoolsfor the PerryNuclearPower Plant(PNPP)as outlinedin Attachment 2 of the Order.The Orderrequiredcompliance priorto plantstartupfromthe secondrefuelingoutagefollowingsubmittalof the overall integrated plan(OlP),or by December 31,2016,whichever comesfirst. The compliance datefor PNPPwasApril 18,2015.The NRCstaffrequested thatthe compliance reportbe submitted within60 daysof the compliance date. The information providedhereindocumentsfull compliance for PNPP in responseto the Order. COMPLIANCE FENOChasinstalled two independent fullscalelevelmonitorson the spentfuelpool (SFP)at PNPPin response to Reference 1. ThisSFPinstrumentation was supplied andqualifiedby Westinghouse, LLC(Westinghouse). PNPPdischarges irradiated fuel to a singlespentfuel storagepool. Withthe exceptionof limitedtime periods for maintenance or non-refuelingoperations, administrativecontrolsmaintaingatesin the openpositionbetweenthe followingpools:fuelstorageandpreparation pool,fuel transferpool,spentfuelstoragepool,andcaskpit. Thus,thesepoolsare normally inter-connected andat the samewaterlevelwhenthe waterlevelin the spentfuel pool is greaterthan 3.5feetabovethe top of storedfuel seatedin the storageracks. These poolsare treatedas one SFPwith regardto Reference1. FENOCsubmitted the PNPPOIPby letterdatedFebruary27,2013(Reference 2). By letterdatedDecember11,2013 (Reference 3),the NRCprovidedits interimstaff evaluationand requestedadditionalinformation necessaryfor completion of the review. The information requested by the NRCis includedin Attachment 2 of thissubmittal. Reference1 requiredsubmission of an initialstatusreport60 daysfollowingissuanceof the finalinterimstaffguidanceandstatusreportsat six-monthintervalsfollowing submittalof the OlP. FENOCprovidedthe initialstatusreportfor PNPPby letterdated October26,2012(Reference 4). Thefirst,second,third,andfourthsix-month status reportsfor PNPPwere provided by lettersdatedAugust26,2013,February 27,2014, August28,2014,andFebruary 26,2015,respectively (References 5,6,7, and8.) Compliance withOrderEA-12-051 was achievedusingthe guidancein NuclearEnergy Institute(NEl)documentNEI 12-02,Revision1 (Reference 9),whichhasbeen endorsedby the NRC(Reference 10)withexceptions andclarifications.A summaryof the compliance elementsis providedbelow. L-15-128 Page2 of 4 ldentification of Levelsof RequiredMonitorino FENOChasidentified the threerequiredlevelsfor monitoring SFPlevelin compliance with Reference1. Theselevelshavebeenintegratedintothe siteprocessesfor monitoring SFPlevelduringbeyond-design-basis externalevents(BDBEES) and responding to lossof SFPinventory. The designof the fueltransferpooland its gatesis suchthatthereis an approximate 3.5footgap betweenthe top of the fuel racksin the two poolscontainingspentfuel (the fuel storageand preparation poolandthe spentfuel storagepool)andthe top of the fuel transferpoolgateseat. As a result,the top of the fueltransferpoolgateseatis usedas Level3. Thissettingis in compliance with Reference1; however,it represents a minor deviationto Reference9. This is a conservative decisionand ensuresthat actionsare takento preventthe spentfuelfrombeinguncovered. Instrumentation DesiqnFeatures FENOChasinstalledSFPinstrumentation consisting of permanently mounted,fixed primaryand backupinstrument channelsat PNPP.ThisSFPinstrumentation was suppliedandqualifiedby Westinghouse. Thedesignof the SFPinstrumentation system installedcomplieswiththe requirements specifiedin Reference 1 and Reference 9. The SFPinstrumentation hasbeeninstalledin accordance withthe sitedesigncontrol process. The instruments havebeenarrangedto providereasonable protectionagainstmissiles (airborne objects).Eachchannelconsistsof a levelsensor,an electronics unit,andan indicator.The sensorsare mountedat the westernend of the SFP (thefuel preparation andstoragepool),as closeto the adjacentcornersas possibleto minimizethe possibility of a singleeventor missiledamagingbothchannels.The sensor arrangement alsolimitsinterference withexistingequipmentin or aroundthe SFP. This designis in compliance withReference 1; however,it doesrepresent a minordeviation from Reference9. Thisdesignalsodoesnot posea potentialhazardto personnel workingaroundthe poolor on the SFPlevelinstrumentation itself. The instruments havebeenmountedto retaindesignconfiguration duringandfollowing the maximumexpectedgroundmotionconsidered in the designof the SFPstructure. The instruments willbe reliableduringexpectedenvironmental and radiological conditions whenthe SFP is at saturation for extended periods. The instruments are independent of eachotherand haveseparateanddiversepowersupplies.The instruments willmaintaintheirdesignedaccuracyfollowinga powerinterruption andare designedto allowfor routinetestingandcalibration. The instrument displayis readilyaccessible duringpostulated BDBEEsandallowsfor SFPlevelinformation to be promptlyavailable to decisionmakers. L-15-128 Page3 of 4 ProgramFeatures The Systematic Approachto Trainingwas utilizedto developand implement training. Traininghasbeenprovidedfor applicable personnel in the useof, and provision of alternatepowerto, primaryand backupinstrument channels. Procedures for the testing,calibration,and useof the primaryand backupSFP instrumentchannelshavebeenestablished and integrated withexistingprocedures. Preventivemaintenance taskshavealsobeenestablished and scheduled to ensurethe instrumentsare maintained at theirdesignaccuracy. REFERENCES
- 1. NuclearRegulatory Commission (NRC)OrderNumberEA-12-051, OrderModifying LicenseswithRegardto ReliableSpentFuelPoolInstrumentation, dated March12,2012.
- 2. FirstEnergy NuclearOperating Company's (FENOC's) OverallIntegrated Planin Response to March12,20'12Commission Orderlssuanceof Orderto Modify LicenseswithRegardto ReliableSpentFuelPoolInstrumentation (OrderNumber EA-12-051),datedFebruary27, 2013.
- 3. NRCLetter,PerryNuclearPowerPlant,Unit1, - InterimStaffEvaluation and Requestfor AdditionalInformation Regarding the OverallIntegrated Planfor lmplementation of OrderEA-12-051, ReliableSpentFuelPoolInstrumentation, datedDecember 11,2013.
- 4. FirstEnergy NuclearOperating Company's (FENOC's)InitialStatusReportin Response to March12,2012,Commission OrderModifyingLicenses withRegardto Requirements for ReliableSpentFuelPoolInstrumentation (OrderNumber EA-12-051),datedOctober26,2A12.
- 5. FirstEnergy NuclearOperating Company's (FENOC's) FirstSix-Month StatusReport in Response to March12,2012Commission OrderModifyingLicenses withRegard to ReliableSpentFuelPoolInstrumentation (OrderNumberEA-12-051) (TACNos.
MF0799,MF0800,MF0960, andMF0802), datedAugust26,2013.
- 6. FirstEnergy NuclearOperating Company's (FENOC's) SecondSix-Month Status Reportin Response to March12,2012Commission OrderModifying Licenses with Regardto ReliableSpentFuelPoolInstrumentation (OrderNumberEA-12-051)
(TACNos.MF0799,MF0800,MF0960,andMF0802), datedFebruary 27,2014.
- 7. FirstEnergy NuclearOperating Company's (FENOC's) ThirdSix-Month Status Reportin Response to March12,2012Commission OrderModifying Licenses with L-15-128 Page4 of 4 Regardto ReliableSpentFuelPoolInstrumentation (OrderNumberEA-12-451)
(TACNos.MF0799,MF0800,MF0960,andMF0802), datedAugust28,20'14. 8 . FirstEnergy NuclearOperating Company's (FENOC's) FourthSix-MonthStatus Reportin Response to March12,2012Commission OrderModifyingLicenseswith Regardto ReliableSpentFuelPoolInstrumentation (OrderNumberEA-12-051) (TACNos.MF0799,MF0800,MF0960,andMF0802), datedFebruary26,2015. 9 . NEfDocument, NEI12-02,Industry Guidance for Compliance withNRCOrder EA-12-051,"ToModifyLicenseswithRegardto ReliableSpentFuelPool fnstrumentation," Revision1, datedAugust2012. 10.NRCJapanLessons-Learned ProjectDirectorateInterimStaffGuidance, JLD-ISG-2012-03,Compliance withOrderEA-12-051,ReliableSpentFuelPool fnstrumentation, datedAugust29,2012.
Attachment2 L-15-128 NRCRequests for Information Page1 of 23 By letterdatedDecember11,2013,the NuclearRegulatory Commission (NRC)issued an interimstaffevaluation (lSE)and requestfor additional information(RAl)regarding the PerryNuclearPowerPlant(PNPP)overallintegrated planfor implementation of NRCOrderEA-12-051,ReliableSpentFuelPoolInstrumentation. Subsequently, by fetterdatedMarch26,2014,the NRCstafftransitioned to an audit-based review processthatallowedthe use of the licensee'sePortalto provideresponsesto the RAls to supportthe staff'sreviewprocess.FirstEnergy NuclearOperatingCompany (FENOC)utilizedthe ePortalto providethe majorityof RAIresponses for PNPP.The ISE RAlsare providedbelow. The responses to the followingRAlswerepreviously providedto the NRCvia the FENOCePortal:RAI-3(b)schematic, RAI-4,RAI-6,RAI-7, RAI-9(b), RAI-10,RAI-11, RAI-12,RAI-13,andRAI-14.Of theseRAls,responses to RAl4, RAI-7,RAI-11, and RAI-12havebeenamendedsincethe siteaudit. The responsesare providedin the tensethatwas applicable whenpresentedon the ePortal, andthereforemay not reflectthe finalcompletedstatus.The NRCstaffquestionis presentedin boldtype,followedby the FENOCresponse.Followingthe RAIresponses is a copyof the bridgingdocumentthatwas previously providedto the NRCviathe FENOCePortal. RAI.I: Pleaseprovidea clearlylabeledsketchdepictingthe elevationview of the proposedtypical mountingarrangementfor the portionsof the instrument channelconsistingof permanentmeasurementchannelequipment(e.9.,fixed levelsensorsand/orstilling wells,and mountingbrackets).Indicateon this sketch the datum values representingLevel 1, Level2, and Level 3, as well as the top of the fuel racks. lndicateon this sketch the portion of the level sensor measurementrangethat is sensitiveto measurementof the fuel pool level,with respectto the Level 1, Level 2, and Level3, datum points. (This information uyaspreviously requesfedas RAI-1[c]in the AlRCletter dated June 10, 2013.)
Response
By fetterdatedFebruary27,2014,FENOCprovideda sketchdepicting the requested datumvalues.Subsequently, by FENOCletterdatedAugust28,2014,Level2 was changed.An updatedsketchis providedbelow. L-15-128 Page2 of 23 LaunchPlate- -El-.6e0'l0* {WEC Dws10066fS8} 12" . 630'6' dead tu$ARF*sS,r-9$h 4) band EL.619'10"- (L-14-024) EL,G.lg'6' LevefI {L-14-CI44} Measurable Range EL.6l{'S" 339"{28'3') Level I 355"t29'r',) EL.591'7\ EL"5g{'6',
--T- -\ - ToB of the Gats $s*t t\ Level 3 4" dead
{USAR Pg.e"1-18} band EL.5gl'2' Top of the Raek {Mearurtd?114#0f4} El-.575'* 1* (USAR Ps.e"1-18) L-15-128 Page3 of 23
RAI-2
Pleaseprovidea clearlylabeledsketch or marked-upplantdrawingof the plan view of the SFP[spentfuel pool] area,depictingthe SFPinsidedimensions,the plannedlocations/placement of the primaryand back-upSFPlevelsensor,and the proposed routing of the cablesthat will extendfrom these sensors toward the locationof the read-ouUdisplay device. (This information was previously requesfedas RAI-Zin the NRCletter dated June 10, 2013.) Response. The response to thisRAIwas providedby FENOCletterdatedFebruary27,2014.
RAI-3
Pleaseprovidethe following: (a)The designcriteriathat will be used to estimatethe total loadingon the mountingdevice(s),includingstatic weight loadsand dynamicloads. Describe the methodologythat will be usedto estimatethe total loading,inclusiveof design basis maximumseismic loadsand the hydrodynamicloadsthat could resultfrom pool sloshingor other effectsthat could accompanysuch seismic forces. (b) A descriptionof the mannerin which the levelsensor(andstilling well, if appropriate)will be attachedto the refuelingfloor and/or other support structures for each plannedpoint of attachmentof the probeassembly. Indicatein a schematicthe portions of the level sensor that will serve as points of attachment for mechanical/mounting or electricalconnections. (c) A descriptionof the mannerby which the mechanicalconnectionswill attach the level instrumentto permanentSFPstructuresso as to support the level sensorassembly. (This information u/as previously requestedas RAI-3in the NRC letter dated June 10, 2013.)
Response
The responseto parts(a) and (c) of this RAIwas providedby FENOCletterdated February 27,2014. Withthe exceptionof providinga schematic,a responseto part(b) of this RAIwas providedby FENOCletterdatedFebruary27,2014. The requested schematic contains vendorproprietary information. Westinghouse, LLC(Westinghouse) drawing L-15-128 Page4 of 23 10066E88, Revision2, providesdetailsof the mechanical connections andelectrical for the mountingof the levelsensorin the FuelHandlingBuilding.Thedrawingwas made availableto the NRCstafffor review. RAI4: For RAI 3(a)above,pleaseprovidethe resulb of the analysesused to verify the designcriteriaand methodologyfor seismictesting of the SFPinstrumentation and the electronicsunitsnincluding,designbasismaximumseismicloadsand the hydrodynamicloadsthat could resultfrom pool sloshingor other effectsthat could accompanysuch seismicforces.
Response
The resultsof the analysisand the parametersusedare containedin Westinghouse cafculation CN-PEUS-1 3-27, Revision2, SeismicAnalysisof the SFPMountingBracket at PerryNuclearPowerPlant.The resultsare obtainedfromthe GTSTRUDL model and are in accordance withsitedesignrequirements andAmericanInstituteof Steel Construction (AISC)7thEdition.Considering all of the applicable loadsandload combinations, all membersof the bracketareacceptable.All weldsand boltsare acceptable whencompared to theirapplicable allowable values.The resultsof the analysisrepresent all the appliedloadsand loadcombinations thatwereapplied.The GTSTRUDL modelandoutputconsiders self-weight, deadloadof the instrumentation, hydrodynamic effectsof the SFPwater,and seismicloadon the bracket.All members passedcodecheckwithinteraction ratiosbelowthe allowablelimitusingthe applicable requirements perAISC7thEdition.Considering all of the loadsandloadcombinations, all membersof the bracketare acceptable.All weldsand boltsare acceptable when comparedto theirapplicable values.Thiscalculation, whichcontainsvendorproprietary information, was madeavailable for NRCreview. The seismic-related documents for the evaluation for the mountingof the electronic components andconduitsweremadeavailable for NRCreview.Thesedocuments included:Engineering ChangePackage(ECP)12-0835-000, Reference Documents - Fukushima SpentFuelPoolLevelInstrumentation Design,ECP12-0835-A02, Primary Channelwiring,cables,conduits, trays,supportsandequipment fromthe SFPareaand to the MainControlRoom(MCR),ECP12-0835-005, BackupChannel wiring,cables, conduits, trays,supportsandequipment fromthe SFPareaandto the MCR; Calcufations 7:24.000, SpentFuelPoolLevelInstrumentation Equipment Mounting, 0P42-0111, SelfWeightExcitationReviewof Hangersfor Emergency ClosedCooling System,and 5:18.000, SpentFuelPoolLevelInstrumentation Mounting Anchor Qualification;VendorTechnicalInformation; VendorManual 1440; Qualification Reports;and Drawings.Thesedocuments demonstrate thatthe designfor the mountingof electronic components andconduitswas completed in accordance withthe endorsedguidancein Institute of Electrical and Electronics Engineers,Inc.(IEEE) Standard344-2004,"IEEERecommended Practicefor SeismicQualification of Class 1E Equipment for NuclearPowerGenerating Stations." L-15-128 Page5 of 23 The PNPPspecificwaveheightdueto sloshingis 4.45feetmaximum.Thisvalueis documented in CN-PEUS-1 3-27,Section4.5.2.3,andis basedon TID-7024.This 4.45feetvalueis boundby the 5-footvalueconsidered in the genericqualitative anafysisperformed for the levelsensingprobedocumented in LTR-SEE-l!-1347 . The PNPPspecificvaluefor the distancefromthe bracketto the nominalwaterlevelis 16 inches,whichis greaterthanthe 12 inchesusedin the genericanalysisperformed by Westinghouse (LTR-SEE-Il-13-47). Westinghouse and PNPPengineering have assessedthe PNPPspecific parameters by estimatingthe change in the postulated hydrodynamic loadon the levelsensorcombinedwiththe designloadsresultingin an estimatedmaximumanchortensionof approximately 1530pounds(lbs). Reviewof the postulatedloadhasconfirmedthat it remainswithinthe allowablelimitof 2000lbsfor the 112inchanchors,affirming the generalconclusions of LTR-SEE-I/-13-047 thatthe resultingloadson the levelsensorprobewillnot resultin probeejectionor potential impactof the instrument on the sidewalls.
RAI-5
For each of the mountingattachmentsrequiredto attach SFP Levelequipmentto plantstructures,pleasedescribethe design inputs,and the methodologythat will be used to qualify the structural integrity of the affectedstructures/equipment.
Response
The responseto this RAIwas providedby FENOCletterdatedFebruary 27,2014. RAI.6: Pleaseprovidethe following: (a)A descriptionof the specificmethodor combinationof methodsthat will be appliedto demonstratethe reliabilityof the permanentlyinstalledequipment under BDB [beyond-design-basisl ambienttemperature,humidity,shock, vibration,and radiationconditions. (b) A descriptionof the testing and/or analysesthat will be conductedto provide assurancethat the equipmentwill performreliablyunderthe worct-casecredible design basis loadingat the locationwherethe equipmentwill be mounted. lncludea discussionof this seismicreliabilitydemonstrationas it appliesto (a) the levelsensor mountedin the SFParea,and (b) any control boxes,electronics, or read-outand re-transmiftingdevicesthat will be employedto conveythe level informationfrom the levelsensor to the plant operatorsor emergency responders. (c) A descriptionof the specificmethodor combinationof methodsthat will be used to confirmthe reliabilityof the permanentlyinstalledequipmentsuch that followinga seismiceventthe instrumentwill maintainits requiredaccuracy. L-15-128 Page6 of 23 (This information was previously requestedas RAI-4 in the NRC letter dated June 10, 2013.)
Response
The NRCstaffauditedthe Westinghouse SFPinstrumentation designverification analysesand performance test resultsin supportof its reviewof TennesseeValley Authority's(TVA's)overallintegratedplanfor the WattsBar NuclearPlantWBN) facility (ADAMSAccessionNo. ML14211A346) for compliance to EA-12-051.The NRCstaff foundthe SFPinstrumentation designandqualification processreasonable. Westinghouse methodologies for demonstrating the reliabilityof the installedSFPlevel instrumentation systemaredescribedin Westinghouse report EQ-QR-269, Revision1, DesignVerification TestingSummaryReportfor the SpentFuelPoolInstrumentation SystemandWestinghouse reportEQ-QR-264, Revision0, Equipment Qualification Abbreviated SummaryReportfor the SpentFuelPoolInstrumentation System.These reports,whichcontainvendorproprietary information, weremadeavailable for NRC review. (a) Environmental qualification testingwas performed in accordance with IEEEStd. 323-2003and electromagnetic compatibility(EMC)qualification testingwas performed in accordance withthe technicalrequirements of Regulatory Guide1.180. Temperature and Humidity- Thermalagingand steamtestingwereperformed on the coaxialcablesandcouplersusinga thermalagingovenat a temperature of 212"Fforthe calculated agedurationof 31t hours plus 10 percent margin, or 343hoursandat 219"Ffor 206.5hoursplusa 10 percentmargin,or 228hours.The coaxialcablesand couplerswerecoiledand set on separateracksin the thermal oven. The couplerwas requiredto be threadedintothe non-preconditioned endof the cableand agedas one assembly.Steamtesting was performed in accordance withIEEEStd.323-2003.Thetestspecimen was exposedto 212"F(+l- 1.8'F), 100percentsaturated(*0, -2 percent)for a durationincluding10 percentmarginof 185hours. In addition, the connectors weresplashtestedto determine the appropriate torquelevelandsealing. Radiation - The coaxialcableandcouplerunderwent radiationagingin accordance with IEEEStd.323-2003for servicein post-accident radiationconditions.Test specimens wererequiredto be exposedto a minimumof 11 Mradof Co60gamma raysat a doserateminimumof 0.2- 0.5 Mrad/hour. EMC- Susceptibility, emissions and harmonics testingwas performed andthe guidance andlimitsprovided in Regulatory Guide1.180wereused. Continuous monitoring was performed to monitorthe performance duringthe application of EMC susceptibilitytesting. Performance Criterionfor this systemis determined to be CriterionB. L-15-128 Page7 of 23 (b) Seismicqualification testingwas performedin accordance with IEEEStd. 344-2004, whichis endorsedby NRCRegulatory Guide1.100,Revision 3, andIEEEStd. 323-2003.The electronics enclosurewas mountedto the testfixturewithfour 3/8-inchGrade5 bolts,lockwashers,flatwashers,and nutstorquedsnugtight. The sensorheadunitmountingbracketwas mountedto the fixturewithfour 3/8-inch Grade5 bolts,lockwashers,andflatwasherstorquedsnugtight. The sensorhead unitwas mountedto the sensorheadunitmountingbracketwithtwo 114inch-2O boltsand lockwasherstorquedto 75 in-lbs.The coaxialcouplerwastorquedhand tight. The launchplatewas mountedto thefixturewithfour5/16-inch Grade5 bolts and lockwasherstorquedsnugtight. Thesensorheadunitmountingbracketwas mountedto the couplerusingthe integralthreadsin the probeanda lockwasherto snugtight. Terminalblockattachments withinthe rearof the sensorheadunitwere torquedto 8 in-lbs. Seismictestingwas performedon a 4x4-footindependent triaxialtesttableusing random,multi-frequency accelerationtime historyinputs. Accelerometers were mountedon the testtableandequipment undertest. Thetabledrivesignalwas appliedseparately andsimultaneously in boththe horizontal andverticaldirections for a durationof 30 secondswitha minimumof 20 secondsof strongmotion.The responsefromthe tableandthe responseaccelerometers wereanalyzedat 5 percentcriticaldampening for eachoperatingbasisearthquake(OBE)and safe shutdownearthquake(SSE)testandwereplottedat one twelfthoctaveintervals overthe frequencyrangeof 1 to 100Hz. Seismictestingof the instrumentation was performed in accordance withIEEE 344-2004.The requiredresponsespectra(RRS)includeda 10 percentmargin recommended by IEEE323-2003.Seismictestingwas performed to the defined SSEand hardrockhighfrequency(HRHF)spectra.The OBERRSat 5 percent criticaldampingwas at least70 percentof the respectiveSSEseismiclevel. At a minimum,five successfulOBEleveltestswererequired,followedby two successful SSEleveltestsandonesuccessful HRHFleveltest. In addition,staticpulltests wereperformedon the Radiallconnectors(straightand 90 degree)to address seismicqualification of the connectors. (c) The equipment undertest(EUT)was poweredon duringOBEseismictestruns,but was notelectrically monitored duringthetestruns. Functional testingwas performedbeforeand afterthe fivesuccessfulOBEtest runs. The system maintained accuracyafterfive successfulOBEleveltestsand no lossof powerwas notedduringthe test runs. The EUTwas poweredon duringall SSEand HRHF seismictestruns,butwas notelectrically monitored duringthetestruns. Functional testingwas alsoperformedbeforeand aftereachsuccessfulSSEand HRHFtest run. The systemmaintained accuracyafterall SSEand HRHFleveltestsandno lossof powerwas notedduringthe test runs. Duringthe SSE2, the alternating current(AC)powerwas removedfromthe system approximately 15 secondsintothe run. Thisoperation was performed to ensurethat the uninterruptiblepowersupply(UPS)was ableto switchfrom line power to battery L-15-128 Page8 of 23 powerduringa seismicevent.The systemperformed withoutissue.The EUTmet all of the requiredperformance and acceptance criteriaand maintained structural integrity duringall acceptable OBEtestruns,acceptable SSEtest runs,andthe acceptable HRHFtestrunto the RRS. Acceptable of the EUTwas functionality confirmeduponcompletionof seismictesting.The post-testinspectionperformed uponcompletion of all seismictestsrevealedno majorstructural issuesor damage to the EUT.
RAI-7
For RAI 6 abovenpleaseprovidethe resultsfrom the selectedmethods,tests and analysesusedto demonstratethe qualificationand reliabilityof the installed equipmentin accordancewith the Orderrequirements.
Response
The NRCstaffauditedthe Westinghouse SFPinstrumentation designverification analysesand performance test resultsin supportof its reviewof TVA'soverall integratedplanfor the WBNfacility(ADAMSAccessionNo. ML14211A346) for compliance to EA-12-051.The NRCstafffoundthe SFPinstrumentation designand qualification processreasonable. Westinghouse test resultsfor the SFP levelinstrumentation systemare describedin Westinghouse reportEQ-QR-269, Revision1, DesignVerification TestingSummary Reportfor the SpentFuelPoolInstrumentation SystemandWestinghouse report EQ-QR-264, Revision0, Equipment Qualification Abbreviated SummaryReportfor the SpentFuelPoolInstrumentation System.Thesereports,whichcontainvendor proprietary information, weremadeavailablefor NRCreview. Temperature and Humidity - Thermalagingwas performed withinthe required temperature parameters andfor the requireddurationand a post-thermal aging functionaltestwas successfully performed. Duringsteamtesting,functionaltestswere performed, whichverifiedthatthe testequipment wasfunctioning withinthe required accuracy,as wellas confirmedthatthe enclosuredisplaycorrectlyidentifiedthe simulated poollevel.Acceptable functional testresultswereobtainedduringfunctional testing.Post-testbaselinetestingwas conducteduponcompletion of environmental testingwithsuccessful functionalresults. Westinghouse concluded thatthe probe,coaxialcable,90 degreeandstraight connector, andstainlesssteelcouplerare ableto performin abnormalconditions in the SFPareafor up to sevendays. In addition,Westinghouse testsdemonstrated thatthe levelsensorelectronics withthe couplerandthe coaxialcableattachedperforms accurately whenthe probe,coupler,and coaxialcableare exposedto a temperature rangeof 10to 100'C(50-212'F) andup to 100percentrelativehumidity (RH). Regarding components outsidethe SFParea,Westinghouse concluded the aggregate of the environmental verification activitiesfor the SFPinstrumentation demonstrate that L-15-128 PageI of 23 the instrumentation operatesreliablyin accordance withthe serviceenvironmental requirements specifiedfor boththe harshand outsideSFP areaconditions.The level sensorelectronics housingwas alsoverifiedto meetlP67ratingper EPSILON08 TEST 2373,whichwillpreventwateringressandwithstand100percenthumidity. In addition,Westinghouse completed their10-yearagingtest. The purposeof the testingwasto extendthe existingqualifiedlifefrom 15 monthsto 10 years. The system withthe 90 degreeconnector passedthetestand is nowqualifiedto a 1O-year life. The systemwiththe straightconnectorperformedduringthe 7 daysof steamtesting,but functionalitywas lostduringthe finalrampdownat the end of the 7 days. The PNPP designusesthe straightconnector.Westinghouse recommended thatthoseplants usingthe straightconnector continuewithinstallationsincethe connectoris qualified for 15 months.Westinghouse issuedCAPAL100045159 and FENOCissuedCondition Report2014-14616 in theirrespective correctiveactionprogramsto trackresolutionof thisissue. In December2014,Westinghouse notifiedFENOCthata follow-uptestwas performed, andthe straightconnector passed the testwith Raychemadded. Raychem willbe addedto the PNPPstraightconnector.The straightconnector is nowqualified for 10 years. ShockandVibration- Seismictestingconsistedof five successfulOBEtests,two successful SSEtests,andonesuccessful HRHFtest. Duringthe secondsuccessful SSEleveltest (281SSE2), AC powerwas cut off to the SFP instrumentation systemto ensurethatthe UPSwouldreliablyswitchduringa seismicevent. No equipment failureswerenotedas a resultof the seismictest runs. Westinghouse performed functionaltestingof the equipment beforeandaftereachSSEand HRHFruns,andthe equipment maintained itsfunctionality. Westinghouse In addition, inspected the equipment afterthe seismictestingand no damagewasfound.Westinghouse concluded thatthe systemmetall requirements, maintained structural during integrity andafterall OBEs,SSEsand HRHFtests. Radiation - The coaxialsignalcableandcouplerweresubjected to thermaland radiationagingpriorto seismictesting.Twosetsof identicalspecimens wereaged,and the components performedto the limitsof 2.5 yearsfor thennalagingand 10 MRad+ 10 percentmarginfor radiation aging.Thecoaxialcableand couplerwere visuallyinspectedafterradiationresting.lt was identifiedthat a lockwasherwas missingfromthe probeattachmentpointof the coupler.Westinghouse notedthatthe absenceof this lockwasherhad no effecton the thermalor radiationagingperformed, andthatthe inspection did not revealanynoticeable degradation. A baselinefunctional testwas performedanddid not showany changein performance as a resultof the radiationagingperformed. EMC- The systemmetall of the identifiedperformance requirements before,during andaftereachEMCsusceptibility testanddemonstrated compliant emissionlevels.No modifications or deviations wererequiredto achievecompliance during EMCtesting. L-15-128 Page10 of 23
RAI-8
Pleaseprovidethe following: (a)A descriptionof how the two channelsof the proposedlevelmeasurement system meet this requirementso that the potentialfor a common cause event to adverselyaffect both channelsis minimizedto the extent pacticable. (b) Furtherinformationdescribingthe designand installationof each level measurementsystem,consistingof levelsensor electronics,cabling,and read-out devices. Pleaseaddresshow independenceof thesecomponentsof the primaryand back-upchannelsis achievedthroughthe applicationof independent powersources,physicaland spatialseparation,independenceof signalssent to the location(s)of the readoutdevices,and the independenceof the displays. (This information was previously requesfedas RAI-5 in fhe AlRCletter dated June 10, 2013.)
Response
The responseto this RAIwas providedby FENOCletterdatedFebruary 27,2014.
RAI-9
Pleaseprovidethe following: (a) A descriptionof the electricalac power sources and capabilitiesfor the primaryand backupchannels. (b) Pleaseprovidethe results of the calculationdepictingthe batterybackupduty cycle requirementsdemonstratingthat its capacityis sufficient to maintainthe level indicationfunctionuntil offsite resourceavailabilityis reasonablyassured. (This information was previously requesfedas RAI-Gin the NRC letter dated June 10, 2013. However,basedon feedbackfrom the licensees,it was revr.sedas above.)
Response
The responseto part(a)of this RAIwas providedby FENOCletterdated February 27,2014. (b) The back-upbatteryis designedto lasta minimumof 72 hours.Thevendor's calculationhasdetermined thatthe batterywill lastfroma full chargefor greaterthan 100hoursperSection5.2.1of Westinghouse calculation WNA-CN-00300-GEN, Revision0, SpentFuelPoolInstrumentation SystemPowerConsumption. L-15-128 Page11of 23 RAr-l0: Pleaseprovidethe following: (a) An estimateof the expectedinstrumentchannelaccuracyperformance(e.9., in percentof span)underboth (a) normalSFPlevelconditions(approximately Level1 or higher)and (b) at the BDB conditions(i.e.,radiation,temperaturen humidity,post-seismicand post-shockconditions)that would be presentif the SFP levelwere at the Level 2 and Level 3 datum points. (b) A descriptionof the methodologythat will be usedfor determiningthe maximumalloweddeviationfrom the instrumentchanneldesignaccuracythat will be employedunder normaloperatingconditionsas an acceptancecriterion for a calibrationprocedureto flag to operatorsand to techniciansthat the channelrequiresadjustmentto within the normalconditiondesignaccuracy. (This information was previously requestedas F/./.I-T in fhe l\lRC letter dated June 10, 2013.)
Response
(a)The designaccuracyis 3 inchesor lessfor bothnormaland BDBconditions andthe calculatedaccuracyfor PNPPof 1.83inchesis withinthe designrange.The calculatedaccuracyof the instrumentation is 0.54percentandthe calculated accuracyof the controlroomremoteindicatoris 0.7082percent. (b)A periodiccalibration verificationwill be performedwithin60 daysof a refueling outageconsidering normaltestingscheduling allowances (forexample,25percent). Calibration will not be requiredto be performedmorethanonceper verification 12 months.Thesecalibration requirements areconsistent withthe guidance providedin NuclearEnergyInstitute(NEl)12-02,Section4.3. PerWestinghouse procedures, shouldthe calibration verificationindicatethatthe instrument is out of toleranceby morethanthe designed3-inchtolerance, o recalibrationwillbe performed. RAt-l1: Pleaseprovidethe following: (a)A descriptionof the capabilityand provisionsthe proposedlevelsensing equipmentwill haveto enableperiodictestingand calibration,includinghow this capabilityenablesthe equipmentto be testedin-situ. (b) A descriptionof how such testingand calibrationwill enablethe conductof regularchannelchecksof each independentchannelagainstthe other,and againstany other permanently-installed SFPlevelinstrumentation. L-15-128 Page12 of 23 (c) A descriptionof how calibrationtests and functionalcheckswill be performed, and the frequencyat which they will be conducted. Discusshow these surveillanceswill be incorporatedinto the plant surveillanceprogram. (d) A descriptionof the preventivemaintenancetasks requiredto be performed during normaloperation,and the plannedmaximumsurveillanceintervalthat is necessaryto ensurethat the channelsare fully conditionedto accuratelyand reliablyperformtheir functionswhen needed. (This information was previously requesfedas RAI-8in the NRC letter dated June 10,2013.)
Response
(a)A periodiccalibration will be performedin-situto verifythatthe verification transmitteris in calibration usinga calibrationverification tool providedby the manufacturer and in accordance withthe plantprocedures and manufacturer's recommendations (Reference RAI14 responsefor moredetail).Shouldthe calibration verificationindicatethatthe transmitter is out of calibration,a full-range calibration adjustment willbe completed usinga calibration testkit. The portable test kit is composedof a replicateprobe,couplerand launchplateequivalent to thoseinstalled, a replicate coaxialcableof the sameelectrical lengthas installedin the pool,a bracketto holdtheweightend of the probecable,simulated poolliner, anda moveablemetaltarget.To perform the calibration, the installedSFP instrumentation systemcoaxialcableis disconnected fromthe sensorandthe replicatetest kit coaxialcableis connected.A metaltargetis usedto measure severalpointsalongthe lengthof the probeto performthefull-range calibration. The readingsdisplayed on the outputdisplayat each point alongthe probewillbe comparedto the physicaldistancemeasuredalongthe lengthof the probecableto determinecalibration acceptance.Eachcomponent in the instrument channelcan be replaced(transmitter included)to restorethe instrumentloopto servicein the eventa component failureoccurs. (b)A channelcheckis conducted as partof lCl-B01-012, ABBIK-TEK MT5000Guided WaveRadarLevelTransmitter Calibration Check,Section5.4,to ensurethat upon completionof the calibration checkor calibration thatthe two channelscompare withinacceptable limits.The SFPlevelindication is locatedin the maincontrol room. To aid in earlydetectionof any"offnormal"readingswhichcouldindicatethat channeladjustment maybe required, a periodicchannelcheckusingthisindication of SFPlevelhasbeenaddedto "ControlRoomPlantEquipment Rounds"and is per conducted OAI-1702, "Operations SectionRoundsSheets,Logs,and Records." The channelcheckis performed dailyand confirmsthatthe two SFPlevel instruments are readingwithinonefootof eachother.As installed, the level instruments typicallyreadwithinapproximately l12footof eachother(t3 inches calibration tolerance for eachinstrument) andthe instrument scalereadingis in l12footincrements, establishingthe basisof one scaleunitdivergence (112foot)for the onefootchannelcheckacceptance criteria.The channelcheckperiodicity and L-15-128 Page13 of 23 acceptance criteriaarecontrolled withinPNPPoperatingprocedures and periodic maintenance programsand maychangebasedon equipment operating experience. Testingto validateinstrument per NEI 12-02,Section4.3,is basedon functionality the instrument calibrationperiodicity as notedin response to RAI-11(c). (c) FENOCwillperformperiodiccalibration verificationsusingperiodicmaintenance procedures andmanufacturer's guidelines.The periodiccalibration verificationwill be performedwithin60 daysof a refuelingoutageconsidering normal testing scheduling allowances (forexample,25 percent).Calibration will not be verification requiredto be performed morethanonce per 12 months. These calibration requirements areconsistent withthe guidanceprovidedin NEI 12-02,Section4.3. (d) Preventive Maintenance (PM)procedures willbe in placefor periodicreplacement of the backupbatteriesbasedon manufacturer recommendations andfor calibration verification. RAt-l2: Pleaseprovidea list of the proceduresaddressingoperation(both normaland abnormalresponse),calibration,test, maintenance,and inspectionthat will be developedfor use of the spent SFP instrumentation.The licenseeis requestedto includea brief descriptionof the specifictechnicalobiectivesto be achieved within each procedure.
Response
The modification reviewprocesswill be usedto ensureall necessaryprocedures are developed for maintaining andoperating the spentfuellevelinstruments upon installation.Theseprocedures willbe developedin accordance withthe FENOC procedural controlprocess. The objectivesof eachprocedural areaare describedbelow: Inspection, Calibration,andTestinq- Guidanceon the performance of periodicvisual inspections, as wellas calibration andtesting,to ensurethateachSFPchannelis operating and indicating levelwithinitsdesignaccuracy. Preventative Maintenance - Guidanceon scheduling of, andperforming, appropriate preventative maintenance activitiesnecessaryto maintainthe instruments in a reliable condition. Maintenance - To specifytroubleshooting and repairactivitiesnecessary to address systemmalfunctions. L-15-128 Page14of 23 Proqrammatic controls- Guidanceon actionsto be takenif oneor morechannelsis out of service. SystemOperations - To provideinstructions for operationand useof the systemby plantstaff. Responseto inadequatelevels- Actionto be takenon observations of levelsbelow normallevelwill be addressedin siteOff Normalprocedures and/orFLEX[Diverseand FlexibleCopingStrategiesl SupportGuidelines (FSGs). Thefollowingprocedureshavebeenidentifiedto date: o EOP-3Chart,Secondary Containment Control(pointsto FSG50.1and FSG50.2) o FSG50.1,FuelPoolFillUsingFireMainor PortablePump
. FSG 50.2,FuelPoolSprayUsingFireMainor PortablePump o FSG50.3,FuelPoolFillUsingEmergency MakeupSystem o FSG90.1,ReadingInstrumentation LocallyDuringStationBlackout o ONI-SPIH-3,Instrumentation AvailableDuringStationBlackout o ONI-SPIJ-1,Maximizing FuelPoolCoolingWaterFlow o ONI-SPIJ-2,Supplying OneFPCCIFuel PoolCoolingandCleanup]HX [Heat Exchanger] with ESW[Emergency ServiceWater]Cooling o ONI-SPIJ-3,Supplying Two FPCCHXsWitha SingleESWCoolingLoop . ONI-SPIJ-4,FuelPoolFillUsingAlternateSources . VLI-G41(FPCC),FuelPoolCoolingandCleanupSystem o TXI-0429,PrimarySpentFuelPoolLevellnstrumentation SystemPower-Upand AcceptanceTesting o TXI-0430,Back-UpSpentFuelPoolLevelInstrumentation SystemPower-Up andAcceptance Testing o lCl-801-012,ABB/K-TEK MT5000GuidedWaveRadarLevelTransmitter Calibration Check o NOP-LP-7300, FLEXProgramfor the PerryNuclearPowerPlant(PNPP)
ThefollowingPMssupportinstallation of the SFPinstrumentation system: o 600925790,PrimaryLevelSensor(transmitter) replacement (6 years) o 600925914, PrimaryLevelSensor(transmitter) (calibrate calibration systemas a loopandthe controlroomanalogmeter)
. 600925793,SecondaryLevelSensor(transmitter) replacement (6 years) o 600925915, Secondary LevelSensor(transmitter) calibration(calibratesystem as a loopandthe control room analog meter) o 600925916, PrimaryElectronicsEnclosure replacement (10years) . 600925917 , Secondary Electronics Enclosurereplacement (10years) o 600927774,PrimaryBatteryreplacement (3 years) o 600927776,SecondaryBatteryreplacement (3 years)
L-15-128 Page15 of 23 l 600927780, PrimaryCoaxialCable,Coupler,and CoaxialConnector replacement (10years) o 600927781, Secondary CoaxialCable,Coupler,and CoaxialConnector replacement (10years) RAt-l3: Pleaseprovidethe following: (a) Furtherinformationdescribingthe maintenanceand testing programthe licenseewill establishand implementto ensurethat regulartestingand calibrationis performedand verifiedby inspectionand audit to demonstrate conformancewith designand systemreadinessrequirements.Includea descriptionof plans to ensure necessarychannelchecks,functionaltests, periodiccalibration,and maintenancewill be conductedfor the level measurementsystemand its supportingequipment. (b) A descriptionof FENOC'sprocedure/process to implementthe guidancein NEI12-02Section4.3 on compensatoryactionsfor one or both non-functioning channels. (c) A descriptionof the compensatoryactions to be taken in the eventthat one of the instrumentchannelscannotbe restoredto functionalstatuswithin 90 days. (This information was previously requesfedas RAI-11 in the NRC letter dated June 10, 2013.)
Response
(a) SFP instrumentation channel/equipment maintenance/preventative maintenance and testingprogramrequirements to ensuredesignandsystemreadiness willbe establishedin accordance withFENOC'sprocesses and procedures. Thedesign modificationprocess willtake intoconsideration the vendorrecommendations to ensurethatappropriate regulartesting,channelchecks,functional tests,periodic calibration, and maintenance is performed (andavailable for inspectionandaudit). Oncethe maintenance andtestingprogramrequirements for the SFPare determined, the requirements willbe documented in Maintenance program documents. Performance checks,described in the vendoroperator'smanual,andthe applicable informationwill be containedin plantprocedures.Operatorperformance testswill be performedperiodically as recommended by the vendor. Channelfunctional testswithlimitsestablished in consideration of vendorequipment specificationswill be performedat appropriate frequencies. L-15-128 Page16of 23 Channelcalibration testsper maintenance procedures withlimitsestablished in consideration of vendorequipmentspecifications are plannedto be performedat frequencies established in consideration of vendorrecommendations. (b) Bothprimaryand backupSFPinstrumentation channelsincorporate permanent (withno relianceon portable,post-event installation installation) of relativelysimple and robustaugmented qualityequipment.Permanent installation coupledwith stockingof adequatesparepartsreasonably diminishes the likelihood thata single channel(andgreatlydiminishes the likelihood thatbothchannels)is (are) out-of-servicefor an extendedperiodof time. Plannedcompensatory actionsfor unlikely extendedout-of-service eventsare summarized as follows: Compensatory Action if RequiredRestoration
# Channel(s) Actionnot completed Out-of-Service RequiredRestoration withinSpecified Time Action 1 Restorechannelto lmmediately initiateaction functional statuswithin in accordance with Notes 90 days(or if channel below restorationnot expected within90 days,then proceedto Compensatory Action) 2 Initiateactionwithin lmmediately initiateaction 24 hoursto restoreone in accordance with Notes channelto functional below statusand restoreone channelto functional statuswithin72 hours Notes:
- 1. Presenta reportto the on-sitesafetyreviewcommitteewithinthe following14 days. The reportshalloutlinethe plannedalternate methodof monitoring, the causeof the non-functionality, andthe plans andschedulefor restoring the instrumentation channel(s) to functional status.
- 2. FENOCplansto placecompensatory actionsin NOP-LP-7300, FLEX Programfor the PerryNuclearPowerPlant(PNPP).
(c) A ConditionReportwill be initiatedandaddressed throughFENOC'sCorrective ActionProgram.Provisionsassociated without of service(OOS)or non-functional equipment, includingallowedoutagetimesandcompensatory actions,willbe consistentwiththe guidance provided in Section4.3 of NEI 12-02. lf one OOS L-15-128 Page17of 23 channelcannotbe restoredto servicewithin90 days,appropriate compensatory actions,including the useof alternatesuitableequipment, willbe taken. lf both channelsbecomeOOS,actionswouldbe initiatedwithin24 hoursto restoreone of the channelsto operablestatusandto implement appropriate compensatory actions, includingthe useof alternatesuitableequipment and/orsupplemental personnel, within72 hours. RAt-14: Pleaseprovidea descriptionof the in-situ calibrationprocessat the SFP location that will result in the channelcalibrationbeingmaintainedat its designaccuracy.
Response
The calibration verification involvesattachinga slidingplateto the flat surfaceabovethe launchplateof the fixedbracketand placinga metaltargetagainstthe probecable abovethe waterlevel. To completethis method,the waterlevelmustbe a sufficient distancebelowthe100percentlevelmark,whichis nominally 12 inchesbelowthe launchplate.Thedifferences in distancesimpartedby thisstandardcan be physically determined and comparedto the distancedifferenceobservedon the leveldisplayof the sensorelectronics. Thesecondportionof thiscalibration verificationis a visual waveformcheckto verifypropersignaloperation.lf the calibration verificationcheck fallswithinthe requiredcalibration tolerance(t3 inches)andthe waveformcheckmeets the criteriaoutlined, the calibration is successful verification andthe equipment maybe returnedto the normaloperating is setup. lf an anomalywiththe calibration observed duringthiscalibration verification, the electronic verification or calibrationadjustment is to be followedfor furtherinvestigation. Thisverificationshallbe performed on both channels(primaryand backup)of the SFPinstrumentation systemindependently.
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