L-16-122, Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation
| ML16176A244 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/24/2016 |
| From: | Boles B FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CAC MF0960, EA-12-051, L-16-122 | |
| Download: ML16176A244 (34) | |
Text
{{#Wiki_filter:FENOC* qr 5501 North Stateflaute 2 FirstEnergyNuclear@rating Company Oak Harbon Ohio 4&149 Brbn D. Bo,8 419-321-7676 Vice President, Fax:419-321-7582 Nuclear June24,2016 L-16-122 10cFR2.202 ATTN: Document ControlDesk U.S.NuclearRegulatory Commission Washington, DC20555-001
SUBJECT:
Davis-Besse NuclearPowerStation DocketNo.50-346,LirenseNo.NPF-3 Qgmpletion of Required Aclignbv NRCOrderEA-12-051. ReliablgSpentFuelPool Instrumentation (.CACNo. MF0960) On March12,2A12, the NuclearRegulatory Commission (NRC)issuedOrder EA-12-051 , OrdetModifying LicenseswithRegardto Reliable$pentFuelPool Instrumentation, to FirstEnergyNuclearOperating Company(FENOC).ThisOrderwas effectiveimmediately and directedFENOCto havea reliableindicationof the water levelin associated spentfuel storagepoolsfor the Davis-Besse NuclearPowerStation (DBNPS)as outlinedin Attachment 2 ol the Order.Thisletter,alongwithits attachments, providesthe notificationrequiredby SectionlV.C.3of the Orderthatfull compliance withthe requirements describedin Attachment 2 of the Orderhasbeen achievedfor DBNPS. This lettercontainsno newregulatorycommitments.lf you haveany questions regarding thisreport,pleasecontactMr.ThomasA. Lentz,Manager- FleetLicensing, at 330-315-6810. I declaregnderpenaltyof perjurythatthe foregoingis trueand correct.Executedon June 4t/ ,2016. Respectful ly submitted, BrianD. Boles
Davis-Besse NuclearPowerStation L-16-122 Page2 Attachments.
- 1. Compliance withOrderEA-12-051
- 2. NRCRequests for Information cc. Director,Officeof NuclearReactorRegulation(NRR)
NRCRegionlll Administrator NRCResidentInspector NRCProjectManager Ms.LisaM. Regner, NRR/JLD/PMB, NRC Mr.BlakeA. Purnell, NRR/JLD/PMB, NRC UtilityRadiologicalSafetyBoard(withoutAttachments)
Attachment1 L-16-122 Compliance withOrderEA-12-051 Page1 of 4 BACKGROUND On March12,2012,theNuclearRegulatory Commission (NRC)issuedOrder EA-12-051, OrderModifying Licenses withRegardto ReliableSpentFuelPool Instrumentation (Reference 1),to FirstEnergy NuclearOperating Company(FENOC). ThisOrderwaseffectiveimmediately anddirectedFENOCto havea reliableindication of thewaterlevelin associated spentfuelstoragepoolsfor the Davis-Besse Nuclear PowerStation(DBNPS)as outlinedin Attachment 2 of the Order.The Orderrequired compliance priorto plantstartupfromthe secondrefueling outagefollowingsubmittal of theoverallintegrated plan(OlP),or by December 31,2016,whichever comesfirst.The compliance datefor DBNPSwas May7,2016. TheNRCstaffrequested thatthe compliance reportbe submitted within60 daysof the compliance date. The information providedhereindocuments fullcompliance for DBNPSin responseto the Order. COMPLIANGE FENOChasinstalled two independent fullscalelevelmonitorson the spentfuelpool (SFP)at DBNPSin response to Reference 1. ThisSFPinstrumentation wassupplied andqualified by Westinghouse, LLC(Westinghouse). DBNPSdischarges irradiated fuelto a singlespentfuelstoragepool. Withthe exception of limitedtimeperiodsfor maintenance or non-refuelingoperations, administrative controlsmaintaingatesin the openpositionbetweenthe followingpools:SFP,fueltransfercanal,andcaskloading pit. Thus,thesepoolsare normallyinter-connected andat the samewaterlevelwhen thewaterlevelin the SFPis greaterthan1 footabovethetop of storedfuelseatedin the storageracks.Thesepoolsaretreatedas one SFPwithregardto Reference 1. FENOCsubmitted the DBNPSOIPby letterdated February 27,2013(Reference 2). By letterdatedDecember11,2013(Reference 3),the NRCprovidedits interimstaff evaluation and requested additional information necessary for completion of the review. Theinformation requested by the NRCis includedin Attachment2of thissubmittal. Reference 1 requiredsubmission of an initialstatusreport60 daysfollowingissuanceof thefinalinterimstaffguidanceandstatusreportsat six-month following intervals submittal of the OlP. FENOCprovided the initialstatusreportforDBNPSby letter datedOctober26,2012(Reference 4). Thefirst,second,third,fourth,fifth,andsixth six-month statusreportsfor DBNPSwereprovidedby lettersdatedAugust26,2013, February 27, 2014,August28,2A14,February 26,2015,August18,2015,and February 9,2016,respectively (References 5, 6, 7,8,9, and 10.) L-16-122 Page2 of 4 Compliance withOrderEA-12-051 wasachieved usingthe guidance in NuclearEnergy (NEI)document Institute NEI 12-02,Revision 1 (Reference 11),whichhasbeen endorsedbythe NRC(Reference 12)withexceptions Asummaryof and clarifications. the compliance elementsis provided below. ldentification of Levelsof RequiredMonitorino FENOChasidentified the threerequiredlevelsfor monitoring SFPlevelin compliance with Reference1. Theselevelshavebeenintegratedintothe siteprocesses for monitoringSFPlevelduringbeyond-design-basis externalevents(BDBEES) and responding to lossof SFPinventory Instrumentation DesignFeatures FENOChasinstalledSFPinstrumentation consisting of permanently mounted, fixed primaryandbackupinstrument channels at DBNPS.ThisSFPinstrumentation was suppliedandqualifiedby Westinghouse. Thedesignof the SFPinstrumentation system complieswiththe requirements specifiedin Reference 1 and Reference 11. TheSFP instrumentation hasbeeninstalled in accordance withthe sitedesigncontrolprocess. The instruments havebeenarrangedto providereasonable protection againstmissiles (airborneobjects).Eachchannelconsistsof a levelsensor,an electronics unit,andan indicator.Thesensorsare mountedon the oppositeendsof the SFPas far apartas practicalwithinthe constraints of the existingpoolgeometryandequipment andas closeto the adjacentcornersas possibleto minimizethe possibility of a singleeventor missiledamaging bothchannels.Thesensorarrangement alsolimitsinterference with existingequipment in or aroundthe SFP. Thisdesigndoesnot posea potentialhazard to personnel workingaroundthe poolor on the SFPlevelinstrumentation itself. The instruments havebeenmountedto retaindesignconfiguration duringandfollowing the maximumexpectedgroundmotionconsidered in the designof the SFPstructure. The instruments will be reliableduringexpectedenvironmental andradiological conditionswhenthe SFPis at saturation for extendedperiods.The instruments are independent of eachotherandhaveseparateanddiverse power supplies. The instruments will maintaintheirdesignedaccuracyfollowinga powerinterruption andare designedto allowfor routinetestingandcalibration. Theinstrument displayis readilyaccessible duringpostulated BDBEEsandallowsfor SFPlevelinformation to be promptlyavailable. L-16-122 Page3 of 4 ProgramFeatures Thesystematic approach to trainingwas utilizedto developand implement training. Traininghasbeenprovidedfor applicable personnel in the useof, and provision of alternatepowerto, primaryand backupinstrument channels. Procedures and useof the primaryandbackupSFP for the testing,calibration, instrumentchannelshavebeenestablished and integrated withexistingprocedures. Preventivemaintenance taskshavealsobeenestablished andscheduled to ensurethe instrumentsare maintained at theirdesignaccuracy. REFERENCES
- 1. NuclearRegulatory Commission (NRC)OrderNumberEA-12-051 , Order Modifying Licenses withRegardto ReliableSpentFuel Pool Instrumentation, dated March12,2012.
- 2. FirstEnergy NuclearOperating Company's (FENOC's) OverallIntegrated Planin Response to March12,2012Commission Orderlssuanceof Orderto Modify LicenseswithRegardto Reliable SpentFuelPoolInstrumentation (OrderNumber EA-12-A51),datedFebruary27, 2013.
- 3. NRCLetter,Davis-Besse NuclearPowerPlantUnitNo. 1 - InterimStaffEvaluation and Requestfor Additional Information Regarding the OverallIntegrated Planfor lmplementation of OrderEA-12-051, Reliable SpentFuelPoolInstrumentation, datedDecember 11,2013.
- 4. FirstEnergy NuclearOperating Company's (FENOC's) InitialStatusReportin Response to March12,2012,Commission OrderModifying Licenses withRegard to Requirements for ReliableSpentFuelPoolInstrumentation (Order Number EA-12-051),datedOctober26, 2012.
- 5. FirstEnergy NuclearOperating Company's (FENOC's) FirstSix-Month Status Reportin Response to March12,2012Commission Order Modifying Licenses with Regardto 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 27,2414.
- 7. FirstEnergy NuclearOperating Company's (FENOC's) ThirdSix-Month Status Reportin Response to March12,2012Commission OrderModifying Licenses with L-16-122 Page4 of 4 Regardto ReliableSpentFuelPoolInstrumentation (OrderNumberEA-12-051)
(TACNos.MF0799,MF0800,MF0960, andMF0802), datedAugust28,2014.
- 8. FirstEnergy NuclearOperating Company's (FENOC's) FourthSix-Month Status Reportin Response to March12,2012Commission OrderModifying Licenseswith Regardto ReliableSpentFuelPoolInstrumentation (OrderNumberEA-12-051)
(TACNos.MF0799,MF0800,MF0960, andMF0802), datedFebruary 26,2415.
- 9. FirstEnergy NuclearOperating Company's (FENOC's) FifthSix-MonthStatus Reportin Response to March12,2012Commission OrderModifying Licenseswith Regardto ReliableSpentFuelPoolInstrumentation (OrderNumberEA-12-051)
(TACNos.MF0800andMF0960), datedAugust18,2015. 1 0 . FirstEnergy NuclearOperating Company's (FENOC's) SixthSix-Month Status Reportin Response to March12,2012Commission OrderModifying Licenseswith Regardto ReliableSpentFuelPoolInstrumentation (OrderNumberEA-12-051) (TACNo.MF0960), datedFebruary9, 2016. 1 1 . NEIDocument, NEI12-02,Industry Guidance for Compliance withNRCOrder EA-12-051,"ToModifyLicenses withRegardto Reliable SpentFuelPool fnstrumentation," Revision1,datedAugust2A12.
- 12. NRCJapanLessons-Learned ProjectDirectorateInterimStaffGuidance, JLD-fSG-2012-03,Compliance withOrderEA-12-051, ReliableSpentFuelPool fnstrumentation, datedAugust29,2012.
Attachment2 L-16-122 NRCRequests for Information Page1 of 28 By letterdatedDecember 11,2013,the NuclearRegulatory Commission (NRC)issued an interimstaffevaluation (lSE)and requestfor additional information (RAl)regarding the Davis-Besse NuclearPowerStation(DBNPS)overallintegrated for plan implementation of NRCOrderEA-12-051 , ReliableSpentFuelPoolInstrumentation. Subsequently, by letterdatedMarch26,2014,the NRCstafftransitioned to an audit-basedreviewprocessthatallowedthe useof the licensee's ePortalto provide responses to the RAlsto supportthe staffsreview process. FirstEnergyNuclear Operating Company(FENOC)utilizedthe ePortalto providethe majorityof RAI responses for DBNPS.The responses to thefollowingRAlswerepreviously provided to the NRCviathe FENOCePortal:RAl4(b)schematic, RAI-S,RAI-7,RAI-8, RAI-10(b), RAI-11, RAI-12,RAI-13,RAI-14,andRAI-15.Thepreviously docketed RAI responses to RAI-2,RAI-3,and RAI-4(c), havebeenamended.RAIresponses to RAI-S,RAI-7,RAI-8,RAI-11(a),RAI-12(b), andRAI-13havebeenamendedon the ePortal.The responses are providedin the tensethatwas applicable whenpresented on the ePortal,andthereforemaynot reflectthefinalcompleted status.The NRCstaff questionis presented in boldtype,followedby the FENOCresponse.Following the RAI responses is a copyof the bridgingdocumentthatwas previously providedto the NRC viathe FENOCePortal. RAI.I: Pleasespecifyfor Levelt how the identifiedlocationrepresentsthe higherof the two points describedin the NEI[NuclearEnergyInstitute]12-02guidancefor this level.
Response
The responseto thisRAIwas providedby FENOCletterdatedFebruary27,2014. RAI.2: Pleaseprovidea clearlylabeledsketch depictingthe elevationview of the proposedtypical mountingarrangementfor the portionsof the instrument channelconsistingof permanentmeasurement channelequipment(e.9.,fixed levelsensorsand/orstillingwells,and mountingbrackets).Indicateon this sketchthe datumvaluesrepresentingLevel1, Level2, and Level3nas well as the top of the fuel racks. Indicateon this sketchthe portionof the levelsensor measurementrangethat is sensitiveto measurementof the fuel pool level,with respectto the Level1, Level2, and Level3, datum points. (This information uyaspreviously requesfedas RAI-lb in fhe IVRCletter dated July 17, 2013.) L-16-122 Page2 of 28
Response
Theresponse to thisRAIwas provided by FENOCletterdatedFebruary 27,2014. Subsequently, morerefinedmeasurements wereobtainedfor the top of fuelrackand bottomof measurement range.An updatedsketchis providedbelow. D$hlp$CriticalLevelEfevations andMeasr*retn*ni Rang*
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Response
Theresponse to thisRAIwas provided by FENOCletterdatedFebruary 27,2A14.The locationof the backuplevelsensor,DB-LE48018, to be on the south was indicated deckof the southeast cornerof the SFP. Thefinallocationof the backuplevelsensoris on the southdeckof the southwest cornerof the SFP. Updatedsketchesfor the locationof DB-LE4801B are provided below,depictinggeneralconfiguration.
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L-16-122 Page6 of 28 RAI4: Pleaseprovidethe following: (a)The designcriteriathat will be used to estimatethe total loadingon the mountingdevice(s),includingstaticweightloadsand dynamicloads. Describe the methodologythat will be usedto estimatethe total loading,inclusiveof designbasismaximumseismicloadsand the hydrodynamicloadsthat could resultfrom pool sloshingor other effectsthat could accompanysuch seismic forces. (b) A descriptionof the mannerin which the levelsensor(andstillingwell,if appropriate)will be attachedto the refuelingfloor and/orother supportstructures for each plannedpoint of attachmentof the probeassembly. Indicatein a schematicthe portionsof the levelsensorthat will serveas points of attachment for mechanical/mounting or electricalconnections. (c)A descriptionof the mannerby which the mechanicalconnectionswill aftach the level instrumentto permanentSFPstructuresso as to support the level sensorassembly. (This information vyaspreviously requestedas RAI-3in IVRClefter dated July 17, 2013.)
Response
The response to part(a) of this RAIwas providedby FENOCletterdated February 27,2014. Withthe exception of providing a schematic,a response to part(b)of this RAIwas provided by FENOCletterdatedFebruary 27,2A14.Therequested schematic contains vendorproprietary information. Westinghouse, LLC(Westinghouse) drawing1006693, Revision1, providesdetailsof the mechanical andelectricalconnections for the mounting of the levelsensorin thefuelhandling areaof theAuxiliaryBuilding.The drawingwas madeavailable to the NRCstafffor review. The response to part(c)of this RAIwas providedby FENOCletterdated February 27,2A14.Part(c) hassubsequently beenamendedas follows: (c) The attachment of the seismically qualifiedbracketto the pooldeckwill be through permanently installedanchors.With permanently installedanchors,the bracket pedestalwillbe securedto the poolsidedeckwithadequate washersand bolts. Thefollowingresultsof the responsespectraanalysisarecontainedin Westinghouse calculation CN-PEUS-13-25, Revision1, Seismic Analysisof the SFPMounting Bracket at Davis-Besse and BeaverValleyNuclearStations.The GTSTRUDL modelandoutput considers self-weight,deadloadof the instrumentation, hydrodynamic loadsdueto L-16-122 Page7 of 28 seismiceffects,andseismicloadon the bracket.All memberspassedcodecheckwith interaction ratiosbelowthe allowable limitusingthe applicable requirements per AmericanInstitute of SteelConstruction (AISC)7thEdition.Considering all of the loads andloadcombinations, all membersof the bracketare acceptable.All weldsandbolts areacceptable whencompared to theirapplicable allowable values.Thiscalculation, whichcontainsvendorproprietary information, was madeavailable for NRCreview. RAI.5: For FIAIa(a)above,pleaseprovidethe resultsof the analysesusedto verify the designcriteriaand methodologyfor seismictesting of the SFPinstrumentation and the electronicsunits,including,designbasismaximumseismicloadsand the hydrodynamicloadsthat could resultfrom pool sloshingor other effectsthat could accompanysuch seismicforces. Response. The parameters usedandanalytical resultsarecontained in Westinghouse calculation CN-PEUS-13-25, Revision 1, Seismic Analysisof the SFPMounting Bracketat Davis-Besseand BeaverValleyNuclearStations.The resultsareobtainedfromthe GTSTRUDL modelandare in accordance withsitedesignrequirements andAISC7th Edition.Considering allof theapplicable loadsandloadcombinations, all members of the bracketare acceptable.All weldsand boltsare acceptable whencompared to their applicableallowable values.The resultsof the analysisrepresent allthe appliedloads andloadcombinations thatwereapplied.TheGTSTRUDL modelandoutputconsiders self-weight, deadloadof the instrumentation, hydrodynamic effectsof the SFPwater, andseismicloadon the bracket.All memberspassedcodecheckwithinteraction ratios belowthe allowable limitusingthe applicable requirements per AISC 7th Edition. Considering all of the loadsand loadcombinations, all membersof the bracketare acceptable.All weldsand boltsareacceptable whencompared to theirapplicable values. CalculationsareC-CSS-070.01-007, SFPLIEnclosure andTransmitter Mounting, and C-CSS-070.01-008, SFPLISensorMounting.Thevendortechnical manualis M-024-00030, Davis-Besse SpentFuelPoolLevelInstrumentation. Thesedocuments demonstrate thatthe designfor the mountingof electronic components andconduits wascompleted in accordance withthe endorsedguidancein Institute of Electrical and ElectronicsEngineers, Inc.(IEEE)Standard 344-2004, "IEEERecommended Practice for SeismicQualification of Class1E Equipment for NuclearPowerGenerating Stations." BecauseBeaverValleyPowerStationand Davis-Besse NuclearPowerStation (DBNPS) sharea bracketdesignandbecauseDBNPS a largerpool,thesloshing has analysisperformed in CN-PEUS-13-25 is boundedby DBNPS.Thesitespecific seismicanalysis of the DBNPSpool-side bracketdocumented in CN-PEUS-13-25, Section4.8,showsthatthe heightof thewavedueto sloshingis 2.65feetmaximum, whichis lowerthanthe 5 feetconsidered in the genericanalysisperformed by L-16-122 Page8 of 28 Westinghouse (LTR-SEE-Il-1 3-47).Therefore, the evaluation performed in LTR-SEE-Il-1 3-47remainsbounding.The DBNPSspecific distance fromthe nominal waterlevelto the bracketis approximately 15.125inches,whichis greaterthanthe 12 inchesusedin LTR-SEE-l\-1347. However, the freeboard assumedin the analysis for CN-PEUS-1 3-25wasapproximately 15 inches.In Engineering Evaluation Request 601009784, FENOCengineering personnel haveassessed the DBNPSspecific parameters by estimating the changein postulated hydrodynamic loadon the level sensorcombined withthedesignloadsresulting in an estimated maximum anchor tensionof 531pounds.Reviewof the postulated loadhas confirmed that it remains withinthe allowable limitsfor the 3/8 inchanchors,affirming the generalconclusions of LTR-SEE-ll-13-047 thatthe resultingloadson the levelsensorprobewill notresultin probeejectionor potentialimpactof the instrument on the sidewalls. Thefollowingdocuments weremadeavailable for NRCreview:
. Engineering Evaluation Request601009784, SFPLevelBracketDesign o Calculation C-CSS-070.01-007, SFPLIEnclosure andTransmitter Mounting o Calculation C-CSS-070.01-008, SFPLISensorMounting . VendorManualM-024-00030, Davis-Besse SpentFuelPoolLevel Instrumentation RAI.6:
For each of the mountingattachmentsrequiredto attachSFPlevelequipmentto plantstructures,pleasedescribethe design inputs,and the methodologythat was used to qualify the structural integrityof the affectedstructures/equipment.
Response
Theresponse to thisRAIwas provided by FENOCletterdatedFebruary 27,2014. RAI.7: Pleaseprovidethe following: (a)A descriptionof the specificmethodor combinationof methodsthat will be appliedto demonstratethe reliabilityof the permanentlyinstalledequipment under BDB [beyond-desig n-basis]ambienttemperature,humidity, shock, vibration,and radiationconditions. (b) A descriptionof the testingand/oranalysesthat will be conductedto provide assurancethat the equipmentwill performreliablyunderthe worst-casecredible designbasisloadingat the locationwherethe equipmentwill be mounted. Includea discussionof this seismicreliabilitydemonstration as it appliesto (a) the levelsensormountedin the SFParea,and (b) any control boxes,electronics, or read-outand re-transmittingdevicesthat will be employedto conveythe level L-16-122 Page9 of 28 informationfrom the levelsensorto the plant operatorsor emergency responders. (c) A descriptionof the specificmethodor combinationof methodsthat will be usedto confirmthe reliabilityof the permanentlyinstalledequipmentsuch that followinga seismiceventthe instrumentwill maintainits requiredaccuracy. (This information was previously requesfedas RAI-4in the NRCletter dated July 17, 2013.)
Response
The NRCstaffauditedWestinghouse SFPinstrumentation designverification analyses andperformance testresultsin supportof its reviewof Tennessee ValleyAuthority's (TVA's)overallintegrated planfor the WattsBar NuclearPlant(WBN)facility(ADAMS AccessionNo.ML14211A346) for compliance to EA-12-051.The NRCstafffoundthe SFPinstrumentation designandqualification processreasonable. Westinghouse methodologies for demonstrating of the installedSFPlevel the reliability instrumentation systemare described in Westinghouse reportEQ-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 of with Institute ElectricalandElectronics Engineers, Inc.(IEEE)Std.323-2003, andelectromagnetic (EMC)qualification compatibility testingwas performed in accordance withthe technicalrequirements of Regulatory Guide1.180. Temperature and Humidity - Thermalagingandsteamtestingwereperformed on the coaxialcablesandcouplersusinga thermalagingovenat a temperature of 212"Fforthe calculated ageduration of 311hoursplus10 percentmargin,or 343hoursand at219'Ffor 206.5hoursplusa 10 percentmargin,or 228hours.The coaxialcablesandcouplerswerecoiledandset on separateracksin the thermal oven. Thecouplerwasrequiredto be threadedintothe non-preconditioned endof the cableandagedas oneassembly.Steamtestingwas performed in accordance withIEEEStd.323-2003.Thetestspecimen wasexposedto 212'F (+l- 1.8'F),
-2 100percentsaturated(*0, percent)for a durationincluding10 percentmarginof 185hours.In addition, the connectors weresplashtestedto determine the appropriatetorquelevelandsealing.
Thermalagingwas performed withinthe requiredtemperature parameters andfor the requireddurationanda post-thermal agingfunctional testwas successfully performed.Duringsteamtesting,functional testswereperformed, whichverified thatthe testequipment wasfunctioning withinthe requiredaccuracv, as wellas L-16-122 Page10of28 confirmed thatthe enclosure displaycorrectlyidentified the simulated poollevel. Acceptable functional testresultswereobtainedduringfunctional testing.Post-test baselinetestingwasconducted uponcompletion of environmental testingwith successful functional results. Westinghouse concluded thatthe probe,coaxialcable,90 degreeandstraight connector, andstainlesssteelcouplerareableto performin abnormalconditions in the SFPareafor up to sevendays. In addition, Westinghouse testsdemonstrated thatthe levelsensorelectronics withthe couplerandthe coaxialcableattached performsaccurately whenthe probe,coupler,andcoaxialcableareexposedto a temperature rangeof 10to 100'C(50to 212"F)andup to 100percentrelative humidity. Regarding components outsidethe SFP area,Westinghouse concluded the aggregate of the environmental verification for activities the SFPIdemonstrate that the instrumentation operatesreliablyin accordance withthe serviceenvironmental requirements specified for boththe harshandoutsideSFP areaconditions.The levelsensorelectronics housingwas alsoverifiedto meetlP67ratingper EPSILON 08 TEST2373,whichwillpreventwater ingressandwithstand 100percenthumidity. In addition, Westinghouse completed their10-yearagingtest. Thepurposeof the testingwasto extendthe existingqualifiedlifefrom15 monthsto 10years.The systemwiththe 90 degreeconnector passedthetestand is nowqualified to a 10-yearlife. TheDBNPSdesignusesthe 90 degreeconnector. Theexpectedtemperature of the SFPareain beyond-design-basis externalevent (BDBEE)conditions is212F. Theexpected humidity is 100percent.Thismatches the designhumidity of 100percent. Thecomponents outsideof the SFPareaare requiredto operatereliablyper"mild environment conditions," whichoccurduringnormalplantoperation, including an abnormaloperating An occurrence. abnormal operating occurrence would be a loss of heating, ventilating, andairconditioning (HVAC)in the installed equipment location.Forequipment locatedin a mildenvironment, seismicis theonly postulated consequential event. No BDBEEconditions weredefinedfor mild environment equipment. Thetransmitter is locatedin the controlroom. Thetemperature and humiditylevels in thisareawillremainmildduringbothnormalandBDBEEconditions. Theresults arethatit is belowthedesigntemperature of 140'Fandwithinthe designrangeof 0-95percenthumidity. It is requiredthatthe operators be ableto accessthe electronics enclosures located in the controlroomin the eventof the BDBEE.Thetemperature and humiditylevels in thisareawillremainmildduringthe BDBEE.Therefore, theareaconditions are considered habitable by the operator. L-16-122 Page11of 28 Radiation - Thecoaxialcableandcouplerundennrent radiation agingin accordance with IEEEStd.323-2003 for servicein post-accident radiation conditions.Test specimens wererequiredto be exposedto a minimumof 11 Mradof Co60gamma raysat a doserateminimumof 0.2- 0.5Mrad/hour. The bounding dosefor locationof the transmitters andelectronic enclosures TID 1E3radswitha 1,000raddesignlimit.Thebounding dosefor the level sensorswasdetermined to be lessthan1l Mradwithan 11 Mraddesignlimit.The boundingdosefor the locationof the electronics enclosures wasdetermined to be 1.1 rad(controlroom),whichis wellwithinthe designlimitsfor the transmitter and enclosure.PerC-NSA-070.01-005, SpentFuelPoolInstrumentation Dose Calculation, radiation to the probeis <.06Mrad/hr.Thiscorresponds to 10.08Mrad overtheseven-day period,whichis lessthanthe bounded valueof 11 Mrad. 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 thissystemis determined to be CriterionB. Thetransmitter andelectronics enclosure locations arealreadyestablished exclusion zones.Thereare no motorsin the vicinityof the equipment thatcould interfere withthe operation of the equipment.A radioexclusion zonewas established aroundtheequipment in the SFP. (b) Seismictestingconsisted of fivesuccessful operating basisearthquake (OBE)tests, two successful safeshutdownearthquake (SSE)tests,andonesuccessful hardrock highfrequency (HRHF)test. Duringthe secondsuccessful SSEleveltest,AC powerwas cut offto the SFPinstrumentation systemto ensurethatthe uninterruptiblepowersupplywouldreliably switchduringa seismicevent.No equipment failureswerenotedas a resultof the seismictestruns. Westinghouse performed functionaltestingof the equipment beforeandaftereachSSEand HRHF runs,andtheequipment maintained itsfunctionality. In addition, Westinghouse inspected theequipment afterthe seismictesting, and no damage wasfound. Westinghouse concluded thatthe systemmetall requirements, maintained structural integrity duringandafterall OBEs,SSEs,andHRHFtests. Seismicqualification testingwas performed in accordance withIEEEStd.344-2004, whichis endorsed by NRCRegulatory Guide1.100,Revision 3, andIEEEStd. 323-2003.Theelectronics enclosure was mountedto the testfixturewithfour 3/8-inchGrade5 bolts,lockwashers,flatwashers,and nutstorquedsnugtight. The sensorheadunitmountingbracketwas mountedto thefixturewithfour3/8-inch Grade5 bolts,lockwashers,andflatwasherstorquedsnugtight. Thesensorhead unitwasmounted to the sensorheadunitmounting bracketwith two 1/4inch-2O boltsandlockwasherstorquedto 75 inch-pounds. Thecoaxialcouplerwastorqued handtight. The launchplatewas mountedto the fixturewithfour5/16-inch Grade5 boltsandlockwasherstorquedsnugtight. Thesensorheadunitmountingbracket L-16-122 Page12of 28 was mountedto the couplerusingthe integralthreadsin the probeanda lock washerto snugtight. Terminalblockattachments withinthe rearof the sensorhead unitweretorquedto 8 inch-pounds. Seismictestingwas performed on a 4x4-tootindependent triaxialtesttableusing random,multi-frequency acceleration timehistoryinputs.Accelerometers were mountedon thetesttableandequipment undertest. Thetabledrivesignalwas appliedseparately andsimultaneously in boththe horizontal andverticaldirections for a durationof 30 secondswitha minimumof 20 secondsof strongmotion.The responsefromthe tableandthe responseaccelerometers were analyzedat 5 percentcriticaldampening for eachOBEand SSEtestandwereplottedat one-twelfth octaveintervals overthe frequencyrangeof 1 to 100Hz. Seismictestingof the instrumentation was performed in accordance withIEEE 344-2004.The requiredresponsespectra(RRS)includeda 10 percent margin recommended by IEEE323-2003.Seismictestingwas performed to the defined SSEand HRHFspectra.TheOBERRSat 5 percent criticaldampingwas at least 70 percentof the respective SSEseismiclevel.At a minimum, fivesuccessful OBE leveltestswere required,followedby two successfulSSE leveltestsandone successful HRHFleveltest. In addition, staticpulltestswereperformed on the radialconnectors (straightand90 degree)to addressseismicqualification of the connectors. (c) Theequipment undertest(EUT)was poweredon duringOBEseismictestrunsbut was notelectrically monitored duringthe testruns. Functional testingwas performedbeforeand afterthe fivesuccessfulOBEtest runs. The system maintained accuracyafterfivesuccessful OBEleveltests,andno lossof powerwas notedduringthe testruns. The EUTwas poweredon duringall SSEand HRHF seismictestruns,butwas notelectrically monitored duringthe testruns. Functional testingwas also performed beforeandaftereachsuccessful SSEand HRHFtest run. Thesystemmaintained accuracyafterall SSEand HRHFleveltests,and no lossof power was notedduringthe testruns. Duringthe SSE2, the alternating current(AC)powerwas removedfromthe system approximately 15 secondsintothe run. Thisoperation was performed to ensurethat the uninterruptible powersupply(UPS)was ableto switchfromlinepowerto battery powerduringa seismicevent.Thesystemperformed withoutissue.The EUTmet all of the requiredperformance andacceptance criteriaand maintained structural integrity duringall acceptable OBEtestruns,acceptable SSEtestruns,andthe acceptable HRHFtestrunto the RRS. Acceptable functionalityof the EUTwas confirmed uponcompletion of seismictesting.The post-testinspection performed uponcompletion of all seismictestsrevealedno majorstructural issuesor damage to the EUT. L-16-122 Page13of 28 RAI.8: For RAI 7 above,pleaseprovidethe 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 qualificationprocessreasonable. Westinghouse testresultsfor the SFPlevelinstrumentation systemaredescribedin Westinghouse reportEQ-QR-269, Revision1, DesignVerification TestingSummary Reportfor the SpentFuelPoolInstrumentation SystemandWestinghouse report EQ-QR-264, Revision0, Equipment Qualification Abbreviated Summary Report for the SpentFuelPoolInstrumentation System.Thesereports,whichcontainvendor proprietaryinformation, weremadeavailabbfor NRCreview. Temperature and Humidity - Thermalagingwas performed withinthe required temperature parameters andfor the requireddurationanda post-thermal aging functionaltestwas successfully performed.Duringsteamtesting,functional testswere performed, whichverifiedthatthe testequipment wasfunctioning withinthe required accuracy, as wellas confirmed thatthe enclosure displaycorrectlyidentifiedthe simulated poollevel.Acceptable functional testresultswereobtainedduringfunctional testing.Post-test baselinetestingwas conducted uponcompletion of environmental testingwithsuccessful functional results. Westinghouse concluded thatthe probe,coaxialcable,90 degreeandstraight connector, andstainless steelcouplerare ableto performin abnormalconditions in the SFPareafor up to sevendays. In addition, Westinghouse testsdemonstrated the that levelsensorelectronics withthe couplerandthe coaxialcableattachedperforms accurately whenthe probe, coupler,andcoaxialcableareexposedto a temperature rangeof 10to 100'C(50-212'F) andup to 100percentrelative humidity (RH). Regarding components outsidethe SFParea,Westinghouse concluded the aggregate of the environmental verificationactivitiesfor the SFP instrumentation demonstrate that the instrumentation operatesreliablyin accordance withthe serviceenvironmental requirements specifiedfor boththe harshandoutsideSFPareaconditions.The level sensorelectronics housingwas alsoverifiedto meetlP67ratingper EPSILON08 TEST 2373,whichwill preventwateringressandwithstand100percenthumidity. In addition, Westinghouse completed their10-yearagingtest. Thepurposeof the testingwasto extendthe existingqualifiedlifefrom 15 monthsto 10years.Thesystem L-16-122 Page14 of 28 withthe 90 degreeconnector passedthe testand is nowqualified to a 10-yearlife. The DBNPSdesignusesthe 90 degreeconnector. ShockandVibration - Seismictestingconsisted of fivesuccessful OBEtests,two successful SSEtests,andonesuccessful HRHFtest. Duringthe secondsuccessful SSEleveltest,AC powerwas cutoff to the SFPinstrumentation systemto ensurethat the UPSwouldreliablyswitchduringa seismicevent.No equipment failureswere notedas a resultof the seismictestruns. Westinghouse performed functionaltestingof theequipment beforeandaftereachSSEandHRHFruns,andtheequipment maintained itsfunctionality.In addition,Westinghouse inspected the equipment after theseismictesting,andno damagewasfound.Westinghouse concluded thatthe systemmetall requirements, maintaining structural integrityduringandafterall OBEs, SSEsandHRHFtests. Radiation - Thecoaxialsignalcableandcouplerweresubjected to thermaland radiation agingpriorto seismictesting.Twosetsof identical specimens wereaged,and the components performed to the limitsof 2.5 years forthermalagingand 10 MRad+ 10 percentmarginfor radiation aging.Thecoaxialcableandcouplerwere visuallyinspected afterradiationresting.lt was identified thata lockwasherwas missingfromthe probeattachment pointof the coupler.Westinghouse notedthatthe absenceof thislockwasherhadno effecton thethermalor radiation agingperformed, andthatthe inspection did not revealany noticeable degradation. A baselinefunctional testwas performed anddid notshowanychangein performance as a resultof the radiation agingperformed.PerC-NSA-070.01-005, SpentFuelPoolInstrumentation DoseCalculation, radiationto the probeis <.06Mrad/hr.Thiscorresponds to 10.08Mradoverthesevendayperiod,whichis lessthanthe bounded valueof 1 1M r a d . EMC- Thesystemmetall of the identified performance requirements before,during andaftereachEMCsusceptibility testanddemonstrated compliant emissionlevels.No modifications or deviationswererequiredto achievecompliance duringEMCtesting. The installation hasa tracewirein the conduitattachedto the connectors, which minimizes thesusceptibility,emissions, and harmonics associated with EMC. RAI.9: Pleaseprovidethe following: (a)A descriptionof the mannerthe two channelsof the proposedlevel measurementsystemmeetthe independencerequirementto minimize,to the extentpracticablen the potentialfor a commoncauseeventto adverselyaffect both channels. (b) Furtherinformationdescribingthe designand installationof each level measurementsystem,consistingof levelsensorelectronics,cabling,and readout devices. Pleaseaddresshow independenceof thesecomponentsof the primary L-16-122 Page15of28 and back-upchannelsis achievedthroughthe applicationof independentpower sources,physicaland spatialseparation,independence of signalssent to the location(s)of the readoutdevices,and the independenceof the displays. (This information was previously requesfedas RAI-Sin wRC letter dated July 17, 2013.)
Response
Theresponse to thisRAIwasprovided by FENOCletterdatedFebruary 27,2014. RAI-I0: Pleaseprovidethe following: (a)A descriptionof the electricalac powersourcesand capabilitiesfor the primaryand backupchannels. (b) Pleaseprovidethe resultsof the calculationdepictingthe batterybackupduty cycle requirementsdemonstratingthat its capacityis sufficientto maintainthe levelindicationfunction until offsiteresourceavailabilityis reasonablyassured. (This information was previously requestedas RAI-6in AlRCletter dated July 17, 2013. However, basedon feedbackfrom the licensees,itwas revisedas above.)
Response
The response to paft(a)of thisRAIwas providedby FENOCletterdated February 27,2014. (b) The back-upbatteryis designedto lasta minimumof 72 hours.Thevendor's calculation hasdetermined thatthe batteryshouldlastfroma fullchargefor greater than100hoursperSection5.2.1of Westinghouse calculationWNA-CN-00300-GEN, Revision 0, SpentFuelPoolInstrumentation SystemPowerConsumption. RAt-l1: Pleaseprovidethe following: (a)An estimateof the expectedinstrumentchannelaccuracyperformance(e.9., in percentof span) underboth (a) normalSFPlevelconditions(approximately LevelI or higher)and (b) at the BDB conditions(i.e.,radiation,temperaturen humidity,post-seismicand post-shockconditions)that would be presentif the SFPlevelwere at the Level2 and Level3 datum points. L-16-122 Page16 of 28 A descriptionof the methodologythat will be usedfor determiningthe maximum alloweddeviationfrom the instrumentchanneldesignaccuracythat will be employedundernormaloperatingconditionsas an acceptancecriterionfor a calibrationprocedureto flag to operatorsand to techniciansthat the channel requiresadjustmentto within the normalconditiondesignaccuracy. (This information was previously requesfedas RAI-7 in AIRCletter dated July 17, 2013,)
Response
(a)Thedesignaccuracyis 3 inchesor lessfor bothnormaland BDBconditions. Westinghouse calculation WNA-CN-00301-GEN providesthe channelaccuracyof a wiredsystemwitha standardmeasurement spanof 296inches.The calculated accuracyof the standardsystemis 0.54percentof spanor 1.60inches.The cable probelengthfor DBNPSis 287.5 inches,whichis lessthantheassumedvaluein WNA-CN-00301-GEN; therefore, the calculatedaccuracyof 0.54percentof spanor 1.60inchesis bounding for DBNPSandwithinthedesignrange. (b)A periodiccalibration will be performed verification within60 daysof a refueling outageconsidering normaltestingscheduling allowances (forexample,25 percent). Calibration verification will notbe requiredto be performed morethanonceper 12 months.Thesecalibration requirements areconsistent withthe guidance providedin NuclearEnergyInstitute(NEl)12-02,Section4.3. PerWestinghouse procedures, shouldthe calibration indicatethatthe instrument verification is out of toleranceby morethanthe designed3-inchtolerance, d will recalibration be performed. RAt-l2: Pleaseprovidethe following: (a)A descriptionof the capabilityand provisionsthe proposedlevelsensing equipmentwill haveto enableperiodictestingand calibration,includinghow this capabilityenablesthe equipmentto be testedin-situ. (b) A descriptionof the testingand calibrationnecessaryto enablethe conductof regularchannelchecksof eachindependent channelagainstthe other,and againstany other permanently-installed SFPlevelinstrumentation. (c) A descriptionof the calibrationtests and functionalchecksprocessesto be performedn and their frequency.Discussthe stepsto be takento ensurethese surveillances will be incorporatedinto the plantsurveillanceprogram. (d) A descriptionof the preventivemaintenancetasks that are requiredto be performedduringnormaloperation,and the plannedmaximumsulveillance L-16-122 Page17ot 28 intervalnecessaryto ensurethat the channelsare fully conditionedto accurately and reliablyperformtheir functionswhen needed. (This information vyaspreviously requesfedas RAI-8in lrRC letter dated July 17, 2013.)
Response
(a)A periodiccalibration verification willbe performed in-situto verifythatthe transmitter is in calibration usinga calibration verification toolprovidedby the manufacturer and in accordance withthe plantprocedures andmanufacturer's recommendations (Reference RAI 15 response for moredetail).Shouldthe calibration verification indicatethatthe transmitter is out of calibration, afull-range calibration adjustment will be completed usinga calibration testkit. The portable testkit is composed of a replicate probe, couplerand launch plateequivalent to thoseinstalled, a replicate coaxialcableof the sameelectrical lengthas installedin the pool,a bracketto holdtheweightendof the probecable,simulatedpoolliner, anda moveablemetaltarget.To performthe calibration, the installedSFP instrumentation systemcoaxialcableis disconnected fromthe sensorandthe replicate testkit coaxialcableis connected.A metaltargetis usedto measure severalpointsalongthe lengthof the probeto performthe full-range calibration. Thereadings displayed on theoutputdisplayat eachpointalongthe probewillbe compared to the physicaldistancemeasured alongthe lengthof the probecableto determine calibration acceptance.Eachcomponent in the instrument channelcan be replaced(transmitter included) to restorethe instrument loopto servicein the eventa component failureoccurs. (b)DBNPSprocedure DB-Ml-05340, Calibrationof FuelPoolLevelTransmitter Model ABB/K-TEK MT5000,was madeeffective.The SFPlevelindication is locatedin the maincontrolroom. To aid in earlydetection of any"offnormal"readings, which couldindicate thatchanneladjustment maybe required, a dailychannelcheckusing thisindication of SFPlevelwillbe addedto OperatorRoundsandenteredin the ShiftOperations Management System(eSOMS) basedon NORM-OP-O104, eSOMS OperatorRoundsModule.Thechannelcheckconfirmsthatthe two SFPlevel instruments are readingwithin6 inchesof eachotherto conformto the system designaccuracy of t3 inchesperchannel.Thechannelcheckperiodicity and acceptance criteriaarecontrolled withinDBNPSoperatingprocedures andperiodic maintenance programsand maychangebasedon equipment operating experience. Testingto validateinstrument per NEI 12-02,Section4.3,is basedon functionality the instrument calibration periodicity as notedin response to RAI-12(c). (c) FENOCwillperformperiodic calibrationverificationsusingperiodicmaintenance procedures andmanufacturer's guidelines.The periodic calibration verification will be performed within60 daysof a refueling outage,considering normaltesting schedufing allowances (forexample,25 percent).Calibration verificationwill notbe requiredto be performed morethanonceper 12 months.Thesecalibration requirements are consistent withthe guidanceprovidedin NEI 12-02,Section4.3. L-16-122 Page18 of 28 (d) Preventive Maintenance (PM)procedures will be in placefor periodicreplacement of the backupbatteriesbasedon manufacturer recommendations andfor calibration verification. RAI-I3: Pleaseprovidea list of the proceduresaddressingoperation(both normaland abnormalresponse),calibration,test, maintenance, and inspectionprocedures that will be developedfor use of the SFPinstrumentation.The licenseeis requestedto includea brief descriptionof the specifictechnicalobjectivesto be achievedwithin each procedure.
Response
The modification reviewprocesswillbe usedto ensureall necessary procedures are developed for maintaining andoperating the spentfuellevel instruments upon installation. Theseprocedures willbe developed in accordance withthe FENOC proceduralcontrolprocess. The objectives of eachprocedural areaaredescribedbelow: Inspection. Calibration,andTesting- Guidance on the performance of periodic visual inspections, as wellas calibrationandtesting,to ensurethateachSFPchannelis operating and indicating levelwithinitsdesignaccuracy. Preventative Maintenance - Guidanceon scheduling of, andperforming, appropriate preventative maintenance activitiesnecessary to maintainthe instruments in a reliable condition. Maintenance - To specifytroubleshooting and repairactivities necessary to address systemmalfunctions. Programmatic controls- Guidance on actionsto be takenif oneor morechannelsis out of service. SystemOperations - To provideinstructions for operation and useof the systemby plantstaff. Response to inadequate levels- Actionto be takenon observations of levelsbelow normallevelwillbe addressed in siteoff normalprocedures and/orFLEX[Diverseand Flexible CopingStrategiesl SupportGuidelines (FSGs). L-16-122 Page19of28 Thefollowingprocedures havebeenidentified: o DB-Ml-05340, Calibration of FuelPoolLevelTransmitter ModelABB/K-TEK MT5000 o DB-OP-02547 , SpentFuelPoolCoolingMalfunctions
. DB-OP-02600, Operational Contingency ResponseActionPlan o DB-OP-06021, SpentFuelPoolOperating Procedure NewPMsarebasedon NORM-ER-3733, FENOCFLEXSpentFuelPoolLevelMonitor.
ThefollowingPMssupportinstallation of the SFPinstrumentation system: Equipment PM Tvpe Interval Owner PrimaryandSecondary LevelSensor Calibration 1/Cycle Maintenance Transmitter PrimaryandSecondary LevelSensor Cleansing/ 1/Cycle Maintenance Transmitter Inspection PrimaryandSecondary LevelSensor CoaxCable llCycle Maintenance Transmitter ResistanceCheck PrimaryandSecondary Batterv Replacement 3 Years Maintenance PrimaryandSecondary LevelSensor Replacement 6 Years Maintenance Transmitter LevelSensorProbe Replacement 7 Years Maintenance PrimaryandSecondary CoaxialCable, Replacement 10Years Maintenance Coupler, andCoaxConnector PrimaryandSecondary Electronics Replacement 10Years Maintenance Enclosure Components RAt-l4: Pleaseprovidethe following: (a) Furtherinformationdescribingthe maintenanceand testingprogramthe licenseewill establishand implementto ensurethat regulartestingand calibrationis performedand verifiedby inspectionand audit to demonstrate conformancewith designand systemreadinessrequirements.Includea descriptionof your plansfor ensuringthat necessarychannelchecks,functional tests,periodiccalibrationnand maintenancewill be conductedfor the level measurementsystemand its supportingequipment. (b) A descriptionof the approachand processto be used by the licenseeto follow guidancein NEI12-02Section4.3,regardingcompensatory actionsfor one or both non-functioning channels. L-16-122 Page20 of 28 (c) A descriptionof the compensatoryactionsto be taken in the eventthat one of the instrumentchannelscannotbe restoredto functionalstatuswithin 90 days. (This information was previously requesfedas RAI-I1 in ,VRCletter dated July 17, 2013.)
Response
(a) SFPinstrumentation channel/equipment maintenance/preventative maintenance and testingprogramrequirements to ensuredesignandsystemreadiness willbe established in accordance withFENOC'sprocesses and procedures. Thedesign modification processwilltakeintoconsideration the vendorrecommendations to ensurethatappropriate regulartesting,channelchecks,functional tests, periodic calibration, andmaintenance is performed (andavailable for inspection andaudit). Oncethe maintenance andtestingprogramrequirements for the SFPare determined, the requirements willbe documented in maintenance program documents. Performance checks,describedin the vendoroperator's manual,andthe applicable informationwill be contained in plantprocedures.Operatorperformance testswill be performed periodically as recommended by the vendor. Channelfunctional testswithlimitsestablished in consideration of vendorequipment specifications will be performed at appropriate frequencies. Channelcalibration testspermaintenance procedures withlimitsestablished in consideration of vendorequipment specifications are planned to be performed at frequencies established in consideration of vendorrecommendations. (b) BothprimaryandbackupSFPinstrumentation channelsincorporate permanent (with installation no relianceon portable, post-event installation) of simple relatively androbustaugmented qualityequipment.Permanent installation coupledwith stockingof adequate spare parts reasonably diminishes the likelihood thata single channel(andgreatlydiminishes the likelihoodthatbothchannels) is (are)out-of-servicefor an extendedperiodof time. Plannedcompensatory actionsfor unlikely extendedout-of-service eventsare summarized as follows: L-16-122 Page21 of 28 Compensatory Action if RequiredRestoration
# Channel(s) Actionnot completed Out-of-Service RequiredRestoration Action withinSpecified Time Restorechannelto lmmediately initiate functionalstatuswithin actionin accordance with (or 90 days if channel Notebelow restoration not expected within90 days,then proceedto Compensatory Action) 2 lnitiateactionwithin lmmediately initiate 24 hoursto restoreone actionin accordance with channelto functional status Notebelow and restoreonechannelto functionalstatuswithin 72 hours Notes:
- 1. Presenta reportto the on-sitesafetyreviewcommittee withinthe following 14days.Thereportshalloutlinethe plannedalternate methodof monitoring, the causeof the non-functionality, andthe plans andschedulefor restoring the instrumentation channel(s) to functional status.
(c) A conditionreportwillbe initiatedandaddressed throughFENOC'sCorrective ActionProgram.Provisions associated without of service(OOS)or non-functional equipment, includingallowedoutagetimesandcompensatory actions,willbe consistent withtheguidance provided in Section4.3of NEIn-Az. lf oneOOS channelcannotbe restoredto servicewithin90 days,appropriate compensatory actions,includingthe useof alternate suitableequipment, willbe taken. lf both channelsbecomeOOS,actionswouldbe initiated within24 hoursto restoreoneof the channelsto operablestatusandto implement appropriate compensatory actions, including the useof alternatesuitable equipment and/orsupplemental personnel, within72 hours. RAt-l5: Pleaseprovidea descriptionof the in-situcalibrationprocessat the SFPlocation that will resultin the channelcalibrationbeingmaintainedat its designaccuracy. L-16-122 Page22 of 28
Response
Thecalibration verification involvesattaching a slidingplateto theflatsurfaceabovethe launch plate of the fixedbracketandplacinga metaltargetagainstthe probecable abovethe waterlevel.To completethismethod,thewaterlevelmustbe a sufficient distance belowthe100percentlevelmark,whichis nominally 12 inchesbelowthe launchplate.Thedifferences in distancesimpartedby thisstandardcan be physically determined andcompared to the distancedifference observedon the leveldisplayof the sensorelectronics. Thesecondportionof thiscalibration verificationis a visual waveformcheckto verifypropersignaloperation.lf the calibration verificationcheck fallswithinthe requiredcalibration tolerance(t3 inches)andthewaveformcheckmeets the criteriaoutlined, the calibration verificationis successfulandthe equipment maybe returnedto the normaloperating setup. lf an anomalywiththe calibration is observed duringthiscalibration verification,the electronic or calibration verification adjustment is to be followedfor furtherinvestigation. Thisverification shallbe performed on both channels(primaryand backup)of the SFPinstrumentation systemindependently.
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