GNRO-2015/00005, Entergy'S Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Lnstrumentation (Order Number EA-12-051)
| ML15049A273 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 02/18/2015 |
| From: | Mulligan K J Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EA-12-051, GNRO-2015/00005 | |
| Download: ML15049A273 (25) | |
Text
GNRO-2015/00005February18,2015 u.s.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,DC20555-0001 Entergy Operations, Inc.P.O.Box756PortGibson,MS39150 Kevin J.MulliganSiteVice PresidentGrandGulf Nuclear StationTel.(601)437-7500
SUBJECT:
Entergy'sFourthSix-MonthStatusReportinResponsetoMarch12,2012CommissionOrderModifyingLicenseswithRegardtoReliableSpentFuelPoollnstrurnentation(OrderNumberEA-12-051)GrandGulfNuclearStation,Unit1DocketNo.50-416LicenseNo.NPF-29
REFERENCES:
1.NRCOrderNumberEA-12-051, Order to Modify Licenses with Regard to Reliable SpentFuelPool(SFP)
Instrumentation, dated March 12,2012(ML12054A682)2.EntergyLettertoNRC, Overall IntegratedPlanin Response to March 12, 2012, Commission Order ModifyingLicensewith RegardtoReliable SpentFuelPool Instrumentation (Order Number EA-12-051),datedFebruary 26,20132013/00016,ML13064A417)3.EntergyLettertoNRC, Entergy's First Six-Month Status Report in ResponsetoMarch 12, 2012 Commission Order Modifying License with Regard to Reliable SpentFuelPool Instrumentation (Order Number EA-12-051),datedAugust 28,20132013/00061
)4.EntergyLettertoNRC, Entergy's Second Six-Month Status Report in ResponsetoMarch 12, 2012 Commission Order Modifying License with Regard to Reliable Spent Fue!Pool Instrumentation (Order Number EA-12-051),datedFebruary 28,2014 (GNRO-2014/00013)
.5.EntergyLettertoNRC, Entergy's Third Six-Month Status Report in ResponsetoMarch 12, 2012 Commission Order Modifying License with Regard to Reliable SpentFuelPool Instrumentation (Order Number EA-12-051),datedAugust 27,20142014/00055)
GNRO-2015/00005Page2of2
DearSirorMadam:
OnMarch12,2012,theU.S.
Nuclear Regulatory Commission(NRC)issuedanorder (Reference1)to Entergy Operations,Inc.(Entergy).
Reference1was immediatelyeffectiveand directsEntergytoinstallreliablespentfuelpoollevel instrumentation.
Reference1requires submissionofastatusreportat six-month intervals followingsubmittaloftheoverall integrated plan (Reference2).Thepurposeofthisletteristoprovidethefourth six-monthstatusreport pursuanttoSectionIV, ConditionC.2,of Reference1,that delineates progressmadein implementing the requirements of Reference1.The attached report providesanupdateof milestone accomplishmentssincethelaststatusreport,includingany changestothe compliancemethod,schedule,orneedforreliefandthebasis,ifany.Thisletter containsnonew regulatory commitments.Shouldyouhaveany questionsregardingthissubmittal,please contact Mr.JamesJ.Nadeau, Regulatory AssuranceManager,at(601) 437-2103.Ideclare underpenaltyofperjurythatthe foregoingistrueandcorrect; executed on February18,2015.Sincerely, KJM/tmc
Attachment:
GrandGulfNuclearStation'sFourthSix M62tusReportforthe Implementation of Order EA-12-051, Order ModifyingLicenseswithRegardto RequirementsforReliableSpentFuelPool Instrumentationcc:U.S.Nuclear Regulatory Commission AnN: Kriss KennedyDeputyRegional Administrator,RegionIV1600EastLamar BoulevardArlington,TX76011-4511U.S.Nuclear Regulatory CommissionAttn:Director,Officeof Nuclear Reactor Regulation Washington,DC20555-0001U.S.Nuclear Regulatory Commission AnN:Mr.AlanWang, NRR/DORLMailStop OWFN/8B1 Washington,DC20555-0001 NRC Senior Resident Inspector Grand Gulf Nuclear StationPortGibson,MS39150 Attachment to GNRO-2015/00005 Grand Gulf Nuclear Station's Fourth Six Month Status Report for the Implementation of Order EA-12-051, Order Modifying licenses with Regard to Requirements for Reliable SpentFuelPool Instrumentation GNRO-2015/00005Page1of22 Grand Gulf Nuclear Station's Fourth Six Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Requirements for Reliable SpentFuelPool Instrumentation 1 IntroductionGrandGulf NuclearStation(GGNS) developedanOverall Integrated Plan (Reference1inSection8), documenting the requirementstoinstallreliablespentfuelpoollevel instrumentation(SFPI),inresponseto Reference2.This attachment providesanupdateof milestone accomplishmentssincethelaststatusreport, including any changestothe compliance method,schedule,orneedfor relief/relaxationandthebasis,ifany.
2 Milestone AccomplishmentsThefollowing milestone(s)havebeen completedsinceJuly 31,2014andare currentasof January 31,2015.*RespondtoISERequestfor Additional Information (received November 25,2013)Complete with submissionofthis documentplannedfor February 2015.3 Milestone Schedule StatusThefollowing providesanupdatetothe schedule identifiedinSection2oftheOverall IntegratedPlan.Itprovidesthe activity statusofeachitem,and whether the expected completiondatehaschanged.Thedatesareplanningdates subjecttochangeasdesignand implementation detailsaredeveloped.
Target Revised Activity Target Milestone Completion Status Completion Date DateSpring2016InstallreliableSFPI Refueling Planned N/A OutageRespondtoNRCRAls(receivedJuly August 29, Submitted August29,N/A 30,2013)2013 2013 SubmittalRespondtoISERAls(received September30,plannedfor N/A November25,2013)2015 February 27, 2015 GNRO-2015/00005Page2of22 4 Changes to Compliance MethodSection3oftheOIP definesthewaterlevelforLevel1as 204'-8" (Reference1).Per NEI12-02,Revision1 (Reference9),Level1isthe higherofthefollowingtwopoints:1)the Ibvelatwhichreliablesuctionlossoccursdueto uncoveringofthe coolantinletpipe,weir,or vacuum/siphon breaker(dependingonthedesign);or2)ThelevelatwhichthenormalfuelpoolcoolingpumpsloserequiredNPSH assuming saturated conditionsinthepool.AtGGNS,the anti-siphon ventholesarelocatedatelevation204'-8".However,theFPCCsystem configurationconsistsofadraintankandSFP skimmers and scuppersthatmaintainthewaterlevelatthenormalpoollevelelevation.TherequiredNPSHfortheFPCC pumpswouldbelostiftheSFPremainsbelowthelevelofthe skimmers and scuppersasthe volumeinthedraintankispumpeddownuntiltheFPCCpumpstripduetoalowdraintanklevel.Normalpoolleveliselevation 10".Therefore,basedonthehigherofthetwolevels,Level1atGGNS correspondsto207'-10".5Need for Relief/Relaxation and Basis for the Relief/RelaxationGGNSexpectstocomplywiththeorder implementationdateandno relief/relaxationisrequiredatthistime.6Open Items from Overall IntegratedPlanand Interim Staff EvaluationGGNShasreceivedanInterimStaffEvaluationthat includes19RAls.ResponsestotheRAlsaredueby September 30,2015andareprovidedinSection9ofthis six-monthstatusreport.Thefollowingtable providesastatusofanyRAls documentedintheInterimStaffEvaluation.
RAI#Response Status1SeeSection92SeeSection9 3SeeSection9 4SeeSection9 5SeeSection96SeeSection9 7SeeSection9 8SeeSection9 9SeeSection910SeeSection911SeeSection9 12SeeSection9 13SeeSection9 14SeeSection9 15SeeSection9 16SeeSection9 17SeeSection9 18SeeSection9 19SeeSection9 GNRO-2015/00005Page3of22 7 Potential InterimEvaluationImpactsTherearenopotential impactstotheInterimStaffEvaluation identifiedatthistimeexceptforthoseidentifiedinSection4and6.8ReferencesThefollowing references support the updatestotheOverall Integrated Plan describedinthis Attachment.1."Overall IntegratedPlanin ResponsetoMarch12,2012, CommissionOrderModifyingLicensewithRegardtoReliableSpentFuelPool Instrumentation (Order Number051),"dated February 26,2013 (GNRO-2013/00016, ML 13059A316).2.NRC Order Number EA-12-051,"Order ModifyingLicenseswithRegardtoReliableSpentFuelPool Instrumentation,"datedMarch12,2012(ML 12054A679).3."GrandGulf NuclearStation,Unit1-InterimStaffEvaluationandRequestforAdditional Information Regarding Overall IntegratedPlanforReliableSpentFuelPool Instrumentation (Order Number EA-12-051)(TACNO.MF0955)," dated November 25,2013(ML 133168986).
4."Summaryofthe November26,2013,PublicMeetingto Discuss Industry Responses toStaffInterim EvaluationsforSpentFuelPool Instrumentation," dated December 26,2013(ML 133478030).
5."Request for Additional Information Regarding Overall IntegratedPlanforReliableSpentFuelPool Instrumentation(OrderEA-12-051),"datedJuly30,2013 (GNRI-2013/00129).6.EntergyLettertoNRC,Entergy'sFirst Six-MonthStatusReportinResponsetoMarch12,2012 Commission Order ModifyingLicensewithRegardtoReliableSpentFuelPool Instrumentation (Order Number EA-12-051),datedAugust 28,20132013/00061)7.EntergyLettertoNRC,Entergy's Second Six-MonthStatusReportinResponsetoMarch12,2012 Commission Order ModifyingLicensewithRegardtoReliableSpentFuelPool Instrumentation (Order Number EA-12-051), dated February 28,20132014/00013)8.EntergyLettertoNRC,Entergy'sThird Six-MonthStatusReportinResponsetoMarch12,2012 Commission Order ModifyingLicensewithRegardtoReliableSpentFuelPool Instrumentation (Order Number EA-12-051), dated August 27,20142014/00055)9.NEI12-02, Industry Guidance for CompliancewithNRC OrderEA-12-051,"ToModifyLicenseswithRegardtoReliableSpentFuelPool Instrumentation,"Revision1,datedAugust2012(ML 12240A307)
GNRO-2015/00005Page4of22 9 Responses to the Interim Staff Evaluation Requests for Additional Information RAI#1 Please provide information on specific procedures controlling irradiated hardware stored in the SFP.Include details of any analysis performed to determine the projected dose rate impact and the appropriateLevel2 elevationasa result of dose from irradiated material stored in the SFP.ResponsetothisRAIwas providedinthe3rd Six-MonthStatusReport.RAI#2 Please provide a clearly labeled sketch or marked-up plant drawing depicting the proposed routing of the cables that will extend from the SFP sensors toward the location of the read-out/display device in the computer and control panel room.ResponsetothisRAIwas providedinthe3rd Six-MonthStatusReport.
RAI#3 Please provide the results of the analyses used to verify thedesigncriteria and methodology for seismic testing of the SFP instrumentation and the electronics units, including design basis maximum seismic loads and the hydrodynamic loads that could result from pool sloshing or other effects that could accompany such seismic forces.Seebridging documentTopic#8,9,12,&13(Section10).
RAI#4Foreachof the mounting attachments required to fasten SFP level equipment to plant structures, please describe the design inputs, and the methodology that was used to qualify the structural integrity of the affected structures/equipment.Seebridging document Topic#8,9,12&13(Section10).
RAt#5 Please provide further information describing how other material stored in the SFP will not create adverse interaction with theSFPlevel instruments.TheSFPand AuxiliaryBuildingare Seismic Category 1 Structures.Asapartofthe EngineeringChange(EC) processforGGNS, interferences(Le.RefuelingGroup equipment,tools,controlblades,etc.)inthepoolshallberemovedorrelocatedtomakeroomforthenew instruments.Additionally,thisECmarksa3.5ft exclusion zone surroundingtheprobesto ensurenoadverse GNRO-2015/00005Page5of22 radiological, personnel, EMI/RFI (electromagnetic interference) or seismic 1111 interactions with the.probe instrument.
RAI#6 Please provide analysis of the maximum expected radiological conditions (doserateand total integrated dose)to which the sensor electronics (including power boxes, signal processors, and display panels)will be exposed.Provide documentation indicating the maximum total integrated dose the sensor electronics can withstand and howitwas determined.
Discuss the time period over which the analyzed total integrated dose was applied.Seebridging document Topic#3(Section10).RAI#7 Please provide information indicating (a)the temperature ratings and whether the temperature ratings for the system electronics are continuous duty ratings;and(b)the maximum expected ambient temperature in the rooms in which the system electronics will be located under BOB conditions, which includenoAC power available to run Heating, Ventilation, and Air Conditioning (HVAC)systems.Seebridging document Topic#3(Section10).RAI#8 Please provide information indicating the maximum expected relative humidity in the room in which the sensor electronics will be located under BOB conditions, in which thereisnoac power available torunHVAC systems, and whether the sensor electronics I is capable of continuously performing required functions under this expected humidity condition.Seebridging document Topic#3(Section10).
RAI#9 Please provide a description of the specific method or combination of methods to be applied to demonstrate the reliability of the permanently installed equipment under BOB shock and vibration conditions.Thefollowing response was updatedfromthe3rd Six-Month StatusReportto include changesbasedon issuanceoftheNRCAuditReportfortheSFPI vendor (MOHR).Seebridging document Topic#14 (Section 10).
GNRO-2015/00005Page6of22RAI#10ForRAI#9 above, please provide the results for the selected methods, tests, and analyses used to demonstrate the qualification and reliability of the installed equipment in accordance with the Order requirements.
The following response was updatedfromthe3rd Six-Month Status Reporttoinclude changesbasedon issuanceoftheNRCAudit ReportfortheSFPI vendor (MOHR).Seebridging document Topic#14(Section10).
RAI#11 Please provide analysis of the vendor analysis and seismic testing results to show that instrument performance reliability, following exposure to simulated seismic conditions representative of the environment anticipated for the SFP structuresatGGNS,hasbeen adequately demonstrated.Seebridging document Topics#8,9,12,&13(Section10).RAI#12 Please provide the NRC staff with the final configuration of the power supply source for each channel so the staff may conclude the two channels are independent from a power supply assignment perspective.
Each instrumentation channel is independently poweredbya different electricalbusand sourceofpowerthanthe other channel.Powerforthenew instrumentation is suppliedfrom120VACpanels1P199and1L143.120VAC power for Channel-A is supplied from powerpanel1P199(throughnew breaker#18),whichis supplied from transformer1X199 poweredfrom480VAC'BOPMCC13B12.120VAC power for Channel-B is supplied from lightingpanel1L143(through breaker#5),whichis supplied from lighting transformer 1X143 poweredfrom480VACBOPMCC14B21.RAI#13 Please provide the results of the calculation depicting battery backup duty cycle requirements, demonstrating that battery capacity is sufficient to maintain the level indication function until offsite resource availability is reasonably assured.Thefollowing response was updatedfromthe3rd Six-Month StatusReporttoinclude changesbasedon issuanceoftheNRCAuditReportfortheSFPI vendor (MOHR).Seebridging document Topic#18 (Section 10).
GNRO-2015/00005Page7of22RAI#14Pleaseprovide analysis verifying the proposed instrument performance is consistentwiththese estimated accuracy normalandBOB values.Demonstratethatthe channelswillretain theseaccuracyperformance values followingalossofpowerand subsequent restorationofpower.Thefollowingresponsewas updatedfromthe3rd Six-MonthStatusReporttoincludechangesbasedon issuanceoftheNRCAuditReportfortheSFPI vendor (MOHR).Seebridging document Topics#16,17and18(Section10).RAI#15Pleaseprovidea descriptionofthe methodology thatwillbeusedfor determining the maximum allowed deviationfromthe instrument channel design accuracy under normal operating conditions.TheNRCstaff understands this allowed deviationwillserveasan acceptance criterionfora calibration proceduretoalert operators and technicians thatthechannel requires adjustmenttowithinnormal design accuracy.Thefollowing response was updatedfromthe3rd Six-MonthStatusReporttoincludechangesbasedon issuanceoftheNRCAuditReportfortheSFPI vendor (MOHR).Ingeneralrelativetonormal operating conditions, any applicable calibration procedure tolerances (or acceptancecriterion)willbe establishedbasedonthe vendor manual's stated/recommended reference accuracy(ordesign accuracy).
The methodologyusedwillbebasedonthe vendor manuals and capturedinplant procedures and/or programs.Seebridging documentTopic#20(Section10).
.RAI#16 Please provide a descriptionofthein-situ calibration processattheSFP location thatwillresultinthe channel calibration being maintainedatits design accuracy.Thefollowing response was updatedfromthe3rd Six-MonthStatusReporttoincludechangesbasedon issuanceoftheNRCAuditReportfortheSFPI vendor (MOHR).Theprocesswillbe capturedinEntergy procedures establishedbasedon manufacturer's recommendationsandEntergy processes and procedures.
The instrument automatically monitors the integrityofitslevel measurementsystemusingin-situcapability.Deviationofmeasuredtest parameters from manufactured or as-installed configurationvaluesbeyonda configurable threshold-tolerable limit prompts operator intervention.Seebridging documentTopic#20.(Section10).
GNRO-2015/00005Page8of2RAI#17 Please describe the evaluation used to validate that the display locationcanbe accessed without unreasonable delay followingaBOB event.Include the time available for personnel to access the display as credited in the evaluation, as well as the actual time(e.g.,basedon walk-throughs) that it will take for personnel to access the display.Additionally, include a description of the radiological and environmental conditions on the paths personnel might take.Describe whether the display location remains habitable for radiological, heat and humidity, and other environmental conditions followingaBOB event.Describe whether personnel are continuously stationed at the display or monitor the display periodically.Thedisplayswillbelocatedinthe LowerCableRoomwhichisintheControlBuilding,onefloorbelowtheControlRoom.Thisroomis accessiblefromtheControlRoomviatwo stairwellsina Category One Structure(oneeachontheeastandwestwalls)and thereforecanbeaccessed without unreasonabledelayfollowingaBOBevent.
Therefore, an evaluationofthetimeittakestoaccessthe displayisnotrequired.Thefollowing response was updatedfromthe3rd Six-MonthStatusReporttoincludechangesbasedon issuanceoftheNRC AuditReportfortheSFPI vendor (MOHR).Thestairwaystothe displaylocationandthe LowerCableRoomaremildradiation environments.
Habitabilitywillbe assuredbyheatstress countermeasuresandrotationofpersonnel.Personnelarenot typically continuously stationedatthedisplay,itwillbe monitoredperiodically.ThesiteFLEX Support Guidelineswillprovide guidanceforpersonneltoevaluatetheroom temperatureandtakeactionsas necessary.Inaddition,site proceduresalreadyusepassivecooling technologies for response personnel.Ifnecessary,portableradioswillbeusedto communicate with decision makers.RAI#18 Please provide a list of the procedures addressing operation (both normal and abnormal response), calibration, test, maintenance, and inspection that will be developed for use oftheSFP instrumentation.
The licensee is requested to include a brief description of the specific technical objectives to be achieved within each procedure.Thefollowing response was updatedfromthe3rd Six-Month Status Reporttoincludechangesbasedon issuanceoftheNRC AuditReportfortheSFPI' vendor (MOHR).The calibrationandtest proceduresareprovidedinthe technical manuals developedbyMOHR.Seebridging document Topics#10,19,and20.The objectivesareto measure system performance, determineifthereisa deviationfromnormal tolerances,andreturnthesystemtonormaltolerances.
Diagnostic procedures developedbyMOHRareprovidedas automated and semi-automatedroutinesinthesystem softwarealertingthe operator to abnormal deviationinselectedsystem parameterssuchasbatteryvoltage,loopcontinuity,andTOR waveformofthe transmissioncable.The technical objectiveofthe diagnostic proceduresisto identify system conditions that GNRO-2015/00005Page9of22 require operator attention to ensure continuedreliableliquidlevel measurement.
Manual diagnostic proceduresarealso providedintheeventthat further workup is determinedtobe necessary.
<, Maintenance procedures developedbyMOHRare providedinthe technicalmanual.Theseallowa techniciantrainedinEFP-ILsystem maintenancetoensurethatsystem functionality is maintained.Anoperation procedurewillprovide sufficient instructions for operationanduseofthesystem.
Entergy procedureswillbe developed in accordancewiththe vendor manualsprovidedbyMOHRand Entergy procedures and processes.FLEXSupport Guidelineswillprovide sufficient instructionsforuseoftheSFPIfollowingaBeyondDesignBasisexternalevent.RAI#19 Please provide further information describing the maintenance and testing program the licensee will establish and implement to ensure that regular testing and calibration is performed and verified by inspection and audit to demonstrate conformance with design and system readiness requirements.
Include a description of plans to ensure necessary channel checks, functional tests, periodic calibration, and maintenance will be conducted for the level measurement system and its supporting equipment.Thefollowing response was updatedfromthe3rd Six-MonthStatusReporttoincludechangesbasedon issuanceoftheNRCAuditReportfortheSFPI vendor (MOHR).SFPI channel/equipment maintenance/preventative maintenanceandtestingprogram requirementstoensuredesignandsystem readinesswillbe established in accordance with Entergy's processes and proceduresandin consideration of vendor recommendations toensurethat appropriateregulartesting, channel checks, functionaltests,periodiccalibration, and maintenance are performed (and available for inspectionandaudit).Seebridging document Topics#10and20(Section10).
GNRO-2015/00005Page10of22 10 GGNS Bridging DocumentBetweenVendor Technical Information and LicenseeUseBasedonNRC Staff Requests for Additional Information(RAls)andNRCVendorAudit
- Topic Parameter Vendor AdditionalTestor Licensee Evaluation Summary Reference Comment Analysis Document Results#1 Design SFPI References Evaluationofthe vendor information is within the Specification Requirements4-13,23, scope of engineering change package EC-50286.derived fromand27-29 References 1,2,and3.2Test Strategy Per References The equipment testing performedfortheSFPIhas Requirements 4,6-13,23, been foundtobe acceptable basedonthe current in Referencesand27-29 design requirements.
1,2,and3.3 Environmental 65-104°F Reference 4 14-131°F As discussed in GGNS SFPI EC50286, the primary Qualificationfor.(References and backup SFPI channel displays for GGNS are electronics 1,2,&37)locatedinthe Lower Cable Room (Reference 38).enclosure with The Lower CableRoomisinthe Control Building.Display The Control Building Cooling Subsystem is not operational following a BDBEE.M3.10.001 (Reference 37)states that the Lower Cable Roomcanbe maintained at 104°F without cooling due to the heat loads thatarelostto surrounding rooms (Reference 37);therefore, following a BDBEE, the Lower CableRoomwill remain below the maximum design temperaturedueto overall reduction in heatloadfrom powered equipment.
There is sufficient cooling margin within the Lower Cable Room, due to the flow of heat to surrounding rooms, to dissipate the minimal heat additionoftheSFPI equipment.
The SFPI vendor, MOHR, has successfully tested its system electronicstoa nominal temperature range GNRO-2015/00005Page11of22of14°Fto131°F.The sensor electronics is capable of continuously performingitsrequired functionunderthe expected temperature conditions.
Resultsofthe vendortestingare available in proprietaryMOHRReport1-0410-1 (Reference4),MOHREFP-ILSFPISystem Temperature and Humidity Report.5-950/0 RHReference4 5-95%RHTheSFPIvendor,MOHR,has successfully tested its system electronics to operateina humidityrangeof 5%to 95%relativehumidity.Resultsofthe vendortestingare available in proprietary MOHR Report 1-0410-1,MOHREFP-ILSFPISystem Temperature and Humidity Report (Reference 4).HumidityintheLowerCableRoomis regulated by the non-safetyrelatedControlBuilding CoolingSubsystem;normal operationbetween10and60 percent RH (Reference35).Duringan extended lossofACpower,the non-safetyrelatedControl BuildingHVACsystemisnolongeravailable.
Assuming theControlBuildingdoorsremainclosed,the temperature increaseintheLowerCableRoomis primarilydueto sensibleheatfrom electrical cablesandequipment.Eveniftheupperlimitsofthe humidity and temperature occur simultaneously, the maximum temperatureconditionof104°Fand60 percent RH (Reference35)isboundedbythe47°C(116.6°F)and71 percentRHtestcase presented inMOHRReport
- 1-0410-1 (Reference 4).Intheeventthatoutsideairis introducedtotheLowerCableRoomduetoopendoorsorHVAC system connections to other rooms, ASHRAE definesthe0.4 percent dehumidification condition tobe84°F dry-bulbwith77 percentRHfor Jackson, I Mississippi (Reference36).Similarly,90 ofDB,with GNRO-2015/00005Page12of22
-66°fc,RHisdefinedfora 0.4%evaporationcondition,ThemaximumRHinLowerCableRoomisboundedbytheoutside conditionswiththe assumptionthattheControlBuilding doors areopened.Themaximum humidity conditionof77 percentRHis boundedbythe32°C(89.6°F)and96
-percentRHtestcase presentedinMOHRReport
- 1-0410-1 (Reference4).Hence,the operational humidityrangeof 5-95 percent encompasses all expected conditionsfortheLowerCableRoomand the sensor electronics are capable of continuously performingtheirrequired function under the expected humidity conditions.NoRadiation N/A Accordingtothe Environmental Parameters for EffectsGGNS(E100.0,Reference35),theradiationdoseratesandtotal integrateddoseare identicalfortheControlRoom (OC503)andtheLowerCableRoom (OC402).Therefore this environment is acceptableandno additionaltestingisrequiredperNRC AuditReportforMOHR (Reference 30).RadiationlevelsintheLowerCableRoomarenot impactedbyareductionin SpentFuelPool water level.4 Environmental 65-212°FReference5RADTIDis480°Flong-TheNRCAuditReportforMOHR (Reference 30)TestingforLevel (Referencesthetotal40yrtermfor concludesthattheSFP-1probeis suitable for Sensor 1,2,and18)doseplusthePEEK operationintheSFP environment.
components in7dayworst InsulatorsSFParea-SubmergedReference5 case accident PEEKTheSFPis expectedtoremainatorabovethe Submerged Componentdoseatthe Insulators minimum ambient temperature(65°F)as called.outPortionofProbe (References 1lowestspacercapableofintheUFSAR (Reference18)Section 9.4.2.1.2.
Bodyand2)locationonlongterm Maximum accident conditionofthe spentfuelpoolistheProbe submergenctakentobe 212°F boiling water/steam at body e atmospheric pressure.Basedonthe vendor analysisresults,thesensitive materialsintheprobebodywill GNRO-2015/00005Page13of22notbe challenged under the required conditions of References 1,2,and18,andare acceptable.
3.67E+08 rad Reference 510GradforTheNRCAudit ReportforMOHR (Reference 30)TID PEEK concludesthattheSFP-1 probe is suitable for (References Insulators operationintheSFP environment.
1,2,&32)CalculationXC-N1 FLEX-14002 (Reference 32)defines a worstcasedoseof approximately 3.67E+ORradtotheprobeviathe applicable requirements of References1and2.As such, the PEEK spacers are suitableforthe application.
5 Environmental 65-212°F Reference 5RadTIDis PEEK: 480°FTheNRC Audit ReportforMOHR (Reference 30)TestingforLevel (Referencesthetotal40yrlongterm concludesthattheSFP-1 probe is suitable for Sensor 1,2,and18)doseplusthe operationintheSFP environment.
Electronics7day worst EPDM: Housing-Probe case accident 194°F long-TheSFP area is expectedtoremainator above the Head locateddoseattheterm,500 minimum ambient temperature(65°F)as called outAbovetheSFP location days@inthe UFSAR (Reference 18).Maximum accident232°F,12 condition temperature and humidity directly above days@the spentfuelpoolistakentobea condensing 311°F steam environment which conservativelywillbeno Sylgard 170: greater than 212°F, the temperature of boiling water 392°F long-at atmospheric pressure.Basedonthe vendor term analysis results the sensitive materialsinthe probeheadwillnotbe challenged under the required conditions of References1,2,and18,andare acceptable.
Thereareno electronics in the probe head located above the SFP.See Topic#3 for discussion of electronics enclosure with display.Forcoaxial transmission cable beyond the Probe ,Head,MOHRuses Class1E Nuclear Safety Related RSCC Wire&CableRSS-6-11OAiLEwhich meets the requirements of Institute of Electrical and GNRO-2015/00005Page14of22 Electronic Engineers (IEEE)383-1974, IIIEEE Standard for Type Test of Class1E Electric Cables, c: Field Splices, and Connections for Nuclear Power Generating Stations"andisacceptable(Reference 30).0-100%RH Reference5.0-100%RHTheNRC Audit Report for MOHR (Reference 30)CondensingforPEEK, concludesthattheSFP-1 probe is suitable for (References 1 EPDM and operationintheSFP environment.and2)Sylgard 170 100%non-condensingRHisa conservative humidityrangefor normal operating conditions.
Basedonthe vendor analysisresults,the sensitive materialsinthe probeheadwillnotbe challenged under the required conditions of References1and2,andare acceptable.
3.46E+07 rad Reference 5PEEK:10TheNRC Audit Report for MOHR (Reference 30)TID Grad concludesthattheSFP-1 probe is suitable for (ReferencesEPDM:2 operationintheSFP environment.
1,2,&32)Grad Sylgard 170: CalculationXC-N1 FLEX-14002 (Reference 32)200Mrad defines a worst case dose of approximately 3.46E+07radtothe area abovetheSFP.Based on the vendor analysisresults,the sensitive materials in the probeheadwillnotbe challenged under the required conditions of References 1,2,and32and are acceptable.
6 Thermal&See Topics#4 Reference 5 See above Acceptable, vendor test/analysis bound licensee Radiation Aging-and5 above Topics#4 parameters, see discussion above in Topics#4and organicand55.components inSFParea7BasisforDose References1N/A Entergy Calculation Procedure EN-DC-126 Requirementand2 (Reference19)wasusedto develop calculations XC-N1 FLEX-14001 (Reference31)and XC-N1 FLEX-14002 (Reference 32)basedonthe GNRO-2015/00005Page15of22 requirementsofNEI12-02 (Reference2)andEA 051 (Reference1).The calculations determine conservativesourcetermsanddoseratesatkey instrumentlocations,forbotha7day accident scenarioand40yearTID.
8 SeismicSeismicClass References Seismic Acceptable,MOHRhas preparedaseriesof generic Qualification I (References8and11Class1 seismic qualificationreportsfortheSFPlevel1,2,3and18) instrumentwhichbound GGNS's seismic criteria.The qualificationreportsenvelopall components ofthenewSFPlevel instrumentationrequiredtobe operationalfollowingaBDBEEand post-event.
These documentsareMOHRReports 1-0410-6 (Reference8)and1-0410-9 (Reference 11).Calculation CC-N1G41-14001 (Reference 33)accountsforseismicloadsandshowsthattheSFPIProbeMountingBracketis structurally adequate and seismically qualifiedasall Interaction Ratios(IR)arelessthanone(1.0).ReferenceTopic#9for discussion of seismicallyinducedsloshingaffectwhichisincluded.
9 SloshingWaterinduced ReferencesSeeTopic#8 Acceptable,theMOHR genericseismicqualificationmotionfrom 8,11,27, reports (References8and11)in combination withseismiceventand28NAIReports NAI-1725-003 and NAI-1725-004doesnot (References27and28)adequatelyboundthe cause hydrodynamic loads associated with sloshing for equipment GGNS.structural failure Calculation CC-N1G41-14001 (Reference 33)accountsforsloshingandshowsthattheSFPIProbeMountingBracketis structurally adequate and seismically qualifiedasall InteractionRatios(lR)arelessthanone(1.0).Reference33is availableonthee-portalforreview.
GNRO-20 15/00005Page16of22 10SpentFuelPoolSystemmust ReferencesThesystem features on board electrical diagnostics.
Instrumentationallowfor14,15,and SFPI channel/equipment maintenance/preventative Systemroutine,insitu 16 maintenance and testing program requirements to Functionalityfunctionality ensuredesignandsystem readinesswillbe established in accordance with Entergy's processes and proceduresandin consideration of vendor recommendations to ensure that appropriate regular testing, channel checks, functional tests, periodic calibration, and maintenance are performed (and available for inspectionandaudit).The instrument automatically monitors the integrityofitslevel measurementsystemusingin-situ capability.11BoronBuild-UpBuildup Reference Boron Acceptable,MOHRReport 1-0410-8 (Reference 10)cannot 10buildupcan concludesthatthe presence of borated water and/or produce error produce aboricacid depositswillnot significantly impair the greater than l'maximumabilityoftheMOHR EFP-ILSFPIsystemto including allerrorof2.5 accurately measure waterlevelintheSFP other error inches environment.
Regardlessofthese findings, GGNS is source termsaBWRanddoesnotuse borated water in their SFP.(References 1and2)12Pool-sideBracket Seismic Class ReferenceSeeTopic#8 Seismic Calculation CC-N1G41-14001 (Reference 33)showsSeismicAnalysis I (References 11ClassIthattheSFPIProbe Mounting Bracket is structurally (References1,2, 1,2,and18)adequate and seismically qualifiedasall Interactionand18)Ratios(IR)arelessthanone(1.0).
Reference33is availableonthee-portalforreview.
13 AdditionalSeismicClass Reference 8SeeTopic#8 Seismic Calculations 425A.4520and425A.4521 (References Brackets (Sensor I (ReferencesClassI39and40)account.for seismic accelerations and Electronics and1,2,3and18)showthatthe additional brackets and other Electronics applicable supports are seismically qualified.
Enclosure)
References39and40are availableonthe e-portalforreview.14Shock&Vibration (References ReferencesIEC 60068-2-Acceptable,theNRCAuditReportforMOHR 1,2and3)7,11,and27(2008-02)(Reference 30)concludesthatthe shock and 29 (Reference vibrationtestresultswere satisfactory.Thereport GNRO-2015/00005Page17of22 MIL-STD-167-25)also acknowledgesthatthetesting pertormed in 1 (ReferenceIEC60068-2-MOHRReport 1-0410-16 (Reference29)is sufficient20)for6(2007-12)toclosetheopenitemidentifiedduringtheMOHRvibrationand (Reference audit.MIL-S-901D 26)(ReferenceMOHRReport 1-0410-5 (Reference 7)adequately21)forshock addresses the requirementsforgeneral robustnessofthe enclosures.Theprobeand repairable head are essentiallyacoaxcablesystemthatis considered inherentlyresistanttoshockandvibration.Theprobesand repairableheadare evaluatedtobe adequately designed for resilience againstshockandvibration (Reference 29).Thenewprobemounting components and fasteners are seismically qualified and designedasrigid components inherentlyresistantto vibration effects.Theprobeswillbeaffixedtothe bracketusingamachinescrew connection designed with proper thread engagementandlockwashers.
The indicatorandbattery enclosureswillbe mountedintheLowerCableRoom.The equipmentisnotaffixedor adjacenttoanyrotating machinery thatwouldcausevibrationeffectsintheareaofinstallation.Thenew instrument mounting components and fasteners are seismically qualified and designedasrigid components inherentlyresistanttovibrationeffects.Similarly,the effects ofshockonthe supporting fixturesforthe instrumentsarenotacrediblethreat;allexisting equipmentinthevicinityofthenewSFPI equipment is qualified seismicallysuchthatthereareno expected impacts from adjacent objectsduringtheBDBEEor design basis earthquake requirements imposed bvNEI12-GNRO-2015/00005Page18of22 02 (Reference2).Eventhough shock and vibrationisnot credible for LowerCableRoom equipment,itis adequately addressed by vendortestreports.
15 Requirements Software Reference The instrument software Verification and Validation Traceability Traceability 13 was performedbyMOHRperRevision2ofMOHR Matrix MatrixReport1-0410-11 (Reference 13).Requiredfor SoftwareEvaluationof Equipment16Factory MustMOHRFAT Acceptable channel factory acceptance tests have Acceptance Test demonstrate Procedure been completed successfully.
functionality offullEFP-ILandSFP-117Channel+/-1foot References3.0inmax, AppendixAof Reference 14 statesthatthe Accuracy (Reference2)14and17 not including maximum SFPI absolute accuracyis76.2mmor3.0boricacidin,not includingboricacid depositioneffects.Note deposition orGGNSisaBWRanddoesnotuse borated water in boilingtheirSFP.Thiserror complieswiththelimitof+/-1foot effectssetbyNEI12-02 (Reference 2).Additionally,theprobeis designed to produce accurate level indicationinboilingand frothing (multiphase) environments (Reference 17).18Power120VAC,60 References85-264 VAC Acceptable,theNRCAuditReportfor MOHR Consumption Hz (Reference9and1247-63HZ (Reference 30)concludesthatno deficits were 18)11.48W identified with respect to function reliability, accuracy, (average)or calibrationasaresultof power interruption.18.83W (maximum)Thepower requirementsforthe instrumentaremetbythe power supplythatwill provide normal ACpowertotheunits.MOHRReport 1-0410-10 (Reference 12)concludes GNRO-2015/00005Page19of22thatthe accuracyisnot affectedbyan interruption in power.7daybattery Reference 97daybattery Acceptable,theNRCAuditReportforMOHRliferequired life@upto (Reference 30)concludes that battery life capability 15 samples is satisfactory.perhourrate (Suspend The instrument testing demonstrates the batterymode);upto capacity is sufficientforthe maximum duration 30 samples.requiredby References1and2.perhourrate (Minimumpowermode) 19TechnicalManualN/A References Acceptable,thetechnical manualshavebeen15and16providedbythevendor,MOHRin References 15and16.20 CalibrationMustallowfor ReferencesSystemis Acceptable, the manualshavebeen providedbythe in-situ14,15,andcalibratedvendor,MOHRin References14,15,and16.calibration16usingCT-100PreviousTopic#10 already discusses maintenance
/deviceand preventative maintenance requirements beingprocessingof established in consideration of vendorscanfilesby recommendations.vendor.Dryscanfrom Overall calibrationorchannel functional testing original methodology is completedbasedon vendor stated installation accuracyandto incorporate a comparisonofSFPImustbe channelstoactualpoollevelaswellasaSFPIcross maintained channel comparison.
21FailureModes System ReferenceSFPIsystem Acceptable,theFMEAprovided adequatelyandEffectsprovides34willmeet addressesfailuremodesand effectsforthefullAnalysis(FMEA)reliable requirements instrumentchannelwith credittakenfortheuseofindicationof of two redundant channels provided the installationfuelpoollevel, References1meetsall requirements stipulated in References 1 consistentand2whenand2.withtheinstalledas requirements required GNRO-2015/00005Page20of22 of References1and2 22 EmissionsEPRITR-ReferencesEPRITR-Acceptable,MOHRreports 1-0410-4 (Reference 6)Testing102323,Rev.6and23102323,Revand1-0410-4-S1 (Reference 23)demonstrate the 3 (Reference 3 (ReferencenewSFPI satisfiestheEMI/RFI compliance 22)22)guidelinesofRevision3ofEPRITR-1 02323 (Reference22)in accordance with Entergy Engineering Standard EN-IC-S-004-MUL TI (Reference24).As demonstratedinthe MOHRSystemEMCTestReportand Supplemental Information (References6and23),theSFPI system passedtheHigh Frequency Radiated and Conducted Emissions testing.FLEX Support Guidelines (FSG)governingtheuseoftheSFPIare expected to include a cautionary statement to precluderadiousagewithinclose proximitytothe displays.
GNRO-20 15/00005Page21of22SpentFuelPool Instrumentation Order (EA-12-051)
Bridging Document Between Vendor Technical Information and Licensee UseBasedonNRCStaff Requests for Additional Information(RAls)andNRC Vendor Audit Bridging Document
References:
1.ML 12054A682, NRC Order EA-12-051,"ORDER MODIFYING LICENSES WITH REGARD TO RELIABLE SPENT FUEL POOL INSTRUMENTATION", Nuclear Regulatory Commission, March 12,20122.ML 12240A307,NEI12-02Rev.1,"Industry Guidance for compliancewithNRC Order EA-12-051,'To Modify Licenses withRegardtoReliableSpentFuelPool Instrumentation'"August,2012.3.ML 12221A339,Rev.0, JLD-ISG-2012-03,"Compliance with Order EA-12-051,ReliableSpentFuelPool Instrumentation", August29,2012, Nuclear Regulatory Commission Japan Lessons-Learned Project Directorate.4.1-0410-1"MOHREFP-ILSFPISystem Temperature and Humidity Test Reporf'5.1-0410-2"MOHRSFP-1LevelProbe Assembly Materials Qualification Report" 6.1-0410-4"MOHREFP-ILSFPISystemEMC Test Report" 7.1-0410-5"MOHR EFP-ILSFPISystemShockand Vibration Test Reporf'8.1-0410-6"MOHREFP-ILSFPISystem Seismic Test Reporf'9.1-0410-7"MOHREFP-ILSFPISystemBatteryLife Reporf'10.1-0410-8"MOHR EFP-ILSFPISystemBoricAcid Deposition Report" 11.1-0410-9"MOHRSFP-1LevelProbe Assembly Seismic Analysis Report" 12.1-0410-10"MOHREFP-ILSFPISystemPower Interruption Reporf'13.1-0410-11"MOHREFP-ILSFPISystem Software Verification and Validation" 14.1-0410-12"MOHREFP-ILSignal Processor Operator's Manual" 15.1-0410-13"MOHREFP-ILSignal Processor Technical Manual".16.1-0410-14"MOHRSFP-1LevelProbe Assembly Technical Manual" 17."MOHREFP-ILSFPISystem Uncertainty Analysis"18.UFSAR,Rev10,"GrandGulf NuclearStationUpdatedFinalSafety Analysis Report 19.EN-DC-126,Rev.5,"Engineering Calculation Process"20.MIL-STD-167-1"Mechanical Vibrations of Shipboard Equipment(Type1-EnvironmentallyandTypeII-Internally Excited)"21.MIL-S-901D"ShockTests, H.1.(HighImpact)
Shipboard Machinery, Equipment,andSystems, Requirements for"22.EPRI TR-102323,Rev.3,"Guidelines for Electromagnetic InterferenceofPowerPlant Equipment"23.1-0410-4-S1"MOHR EFP-IL SFPI Supplemental EMC Information" 24.EN-IC-S-004-MULTI,Rev.001,"EMI/RFIDesign Considerations"25.IEC 60068-2-27 (2008-02)"Environmental Testing-Part 2-27: Tests-TestEaand Guidance: Shock"26.IEC 60068-2-6 (2007-12)"Environmental Testing-Part 2-6: Tests-Test Fc: Vibration (sinusoidal)"
GNRO-2015/000Q5 Page22of22 27.NAI-1725-003,Rev.0,"GOTHIC Verification and Sensitivity Studies for Predicting Hydrodynamic Response to Acceleration in RectangularShapedPools" 28.NAI-1725-004,Rev3"Seismic Induced Hydraulic ResponseintheCGSSpentFuelPool" 29.1-0410-16,"MOHRSFP-1LevelProbe AssemblyShockand VibrationTestReport"30.DonaldC.Cook NuclearPlant,Units1and2-ReportfortheOnsiteAuditofMOHR Regarding ImplementationofReliableSpentFuelPool InstrumentationRelatedto OrderEA-12-051(TACNOS.MF0761and MF0762)dated August 27,2014 (ADAMS AccessionNoML 14216A362)31.XC-N1 FLEX-14001, Rev.0.00,"SpentFuelPool InstrumentationSourceTerm Calculation"32.XC-N1 FLEX-14002,Rev.000,"SpentFuelPool Instrumentation Shielding Calculation"33.CC-N1 G41-14001,Rev.000,"SpentFuelPoolProbe Mounting Bracket Qualification" 34.EVAL-194-4812-01,"MOHREFP-ILLiquidLevel MeasurementSystemFailureModesand Effects Analysis (FMEA)"35.E100.0,Rev.007,"Technical Specification for EnvironmentalSafetyRelatedParameter" 36.ASHRAE Fundamentals,2001IPEd.37.M3.10.001,Rev.300,"ControlBuildingHVAC"38.EC50286,"GGNSSpentFuelPoolLevel Instrumentation Upgrade" 39.425A.4520,Rev.000,"SpentFuelPoolDisplayPanel, Battery Enclosure, and Transformer Mounting Qualification forChannelA" 40.425A.4521,Rev.000,"SpentFuelPoolDisplayPanel,Battery Enclosure, and Transformer Mounting Qualification forChannelB"