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| Line 33: |
Line 33: |
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| Justificationtouestion6:RG&EconductedanextensivereviewofmaintenanceandtestproceduresaspartofourresponsetoInspectionReport90-031datedFebruary8,1991.Proceduresthatarestillbeingreviewedareinquarantinependingreviewcompletion.Proceduresfor1Aand1BBatterySystemMaintenanceandRepairverifyoperabilityoftheredundantbatterysystemasaninitialcondition.However,atpresentthereisnospecificprohibitioninallmaintenanceprocedures.ItisRG&Espolicytoprohibitmaintenanceortestingonredundantdcdivisionsatthesametime.RG&Ewillinvestigatetheneedtoplacemorespecificprohibitioninallapplicableprocedurestoensuretheintegrityofthedcsystem.Justificationtouestion7a:Duringtheperformanceofplanttours,normallytwicepershift,thespecifiedbatteryparametersaremonitoredtoensurenormaloperation.AlsoinaccordancewithRegulatoryGuide1.129,"Maintenance,TestingandReplacementofLargeLeadStorageBatteriesforNuclearPowerPlants",monthlyinspectionsareperformedperIEEE-450,"LargeLeadStorageBatteriesforGeneratingStations".Allthespecifiedbatteryparametersareverifiedtobewithinacceptablelimits.Justificationtouestion7b.4:Plantproceduresarecurrentlybeingrevisedtoincludeacceptablelimitsfortheaverageelectrolytetemperature.Presentlytheaverageelectrolytetemperatureiscalculatedforthepurposeof-.calculatingthespecificgravity.Justificationtouestion7b.6:InaccordancewithIEEE-450,"LargeLeadStorageBatteriesforGeneratingStations",celltocellterminalconnectionresistanceisverifiedtobewithinacceptablelimitsduringtheyearlytest.However,monthlytheterminalsarevisuallyinspectedforanyevidenceofcorrosion.Theconnectorsatthedcbusarenotsubjectedtothesamecorrosiveelementsascellterminalconnectionsandthereforearenotvisuallyinspectedmonthly. | | Justificationtouestion6:RG&EconductedanextensivereviewofmaintenanceandtestproceduresaspartofourresponsetoInspectionReport90-031datedFebruary8,1991.Proceduresthatarestillbeingreviewedareinquarantinependingreviewcompletion.Proceduresfor1Aand1BBatterySystemMaintenanceandRepairverifyoperabilityoftheredundantbatterysystemasaninitialcondition.However,atpresentthereisnospecificprohibitioninallmaintenanceprocedures.ItisRG&Espolicytoprohibitmaintenanceortestingonredundantdcdivisionsatthesametime.RG&Ewillinvestigatetheneedtoplacemorespecificprohibitioninallapplicableprocedurestoensuretheintegrityofthedcsystem.Justificationtouestion7a:Duringtheperformanceofplanttours,normallytwicepershift,thespecifiedbatteryparametersaremonitoredtoensurenormaloperation.AlsoinaccordancewithRegulatoryGuide1.129,"Maintenance,TestingandReplacementofLargeLeadStorageBatteriesforNuclearPowerPlants",monthlyinspectionsareperformedperIEEE-450,"LargeLeadStorageBatteriesforGeneratingStations".Allthespecifiedbatteryparametersareverifiedtobewithinacceptablelimits.Justificationtouestion7b.4:Plantproceduresarecurrentlybeingrevisedtoincludeacceptablelimitsfortheaverageelectrolytetemperature.Presentlytheaverageelectrolytetemperatureiscalculatedforthepurposeof-.calculatingthespecificgravity.Justificationtouestion7b.6:InaccordancewithIEEE-450,"LargeLeadStorageBatteriesforGeneratingStations",celltocellterminalconnectionresistanceisverifiedtobewithinacceptablelimitsduringtheyearlytest.However,monthlytheterminalsarevisuallyinspectedforanyevidenceofcorrosion.Theconnectorsatthedcbusarenotsubjectedtothesamecorrosiveelementsascellterminalconnectionsandthereforearenotvisuallyinspectedmonthly. |
| -rvrCmawt-Justificationtouestion7c.3:Plantproceduresarecurrentlybeingrevisedtoincludetestingofthechargerstoensuretheycandelivertheirratedampereoutput.Theplantprocedurewillberevisedpriortotheperformanceofthenextannualbatteryservicetest.andthechargercapabilitywillbeverifiedduringtheservicetest.Justificationtouestion7c.5:Plantproceduresarecurrentlybeingrevisedtoincludemonitoringofeachcellvoltageduringtheannualservicetesttoensurethattheyremainwithinacceptablelimits.Theplantprocedurewillberevisedpriortotheperformanceofthenextannualbatteryservicetest.*Note:Forquestionsinvolvingsupportingtypeinformation(questionnumbers5and9)insteadofdevelopingandsupplyingtheinformationinresponsetothisletter,youmaycommittofurtherevaluatetheneedforsuchprovisionsduringtheperformanceofyourindividualplantexaminationforsevereaccidentvulnerabilities(IPE).Ifyouselectthisoption,youarerequiredto:(1)Sostateinresponsetothesequestions,and(2)Committoexplicitlyaddressquestions5and9inyourIPEsubmittalpertheguidelinesoutlinedinNUREG-1335(Section2.1.6,Subitem7),"IndividualPlantExamination:SubmittalGuidance." | | -rvrCmawt-Justificationtouestion7c.3:Plantproceduresarecurrentlybeingrevisedtoincludetestingofthechargerstoensuretheycandelivertheirratedampereoutput.Theplantprocedurewillberevisedpriortotheperformanceofthenextannualbatteryservicetest.andthechargercapabilitywillbeverifiedduringtheservicetest.Justificationtouestion7c.5:Plantproceduresarecurrentlybeingrevisedtoincludemonitoringofeachcellvoltageduringtheannualservicetesttoensurethattheyremainwithinacceptablelimits.Theplantprocedurewillberevisedpriortotheperformanceofthenextannualbatteryservicetest.*Note:Forquestionsinvolvingsupportingtypeinformation(questionnumbers5and9)insteadofdevelopingandsupplyingtheinformationinresponsetothisletter,youmaycommittofurtherevaluatetheneedforsuchprovisionsduringtheperformanceofyourindividualplantexaminationforsevereaccidentvulnerabilities(IPE).Ifyouselectthisoption,youarerequiredto:(1)Sostateinresponsetothesequestions,and(2)Committoexplicitlyaddressquestions5and9inyourIPEsubmittalpertheguidelinesoutlinedinNUREG-1335(Section2.1.6,Subitem7),"IndividualPlantExamination:SubmittalGuidance."}} |
| }} | |
Forwards Response to Generic Ltr 91-06, Resolution of Generic Issue A-30, 'Adequacy of Safety-Related DC Power Supplies.' Advises That Specific Action Planned in Response to Questions 6,7.b.4,7.c.3 & 7.c.5| ML17262A636 |
| Person / Time |
|---|
| Site: |
Ginna  |
|---|
| Issue date: |
10/28/1991 |
|---|
| From: |
MECREDY R C
ROCHESTER GAS & ELECTRIC CORP. |
|---|
| To: |
JOHNSON A R
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
|---|
| References |
|---|
| REF-GTECI-A-30, REF-GTECI-EL, TASK-A-30, TASK-OR GL-91-06, GL-91-6, NUDOCS 9111050285 |
| Download: ML17262A636 (13) |
|
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|---|
Category:CORRESPONDENCE-LETTERS
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Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated
IR 05000244/19990081999-10-14014 October 1999
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ML17265A7651999-10-0808 October 1999
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ML17265A7631999-10-0505 October 1999
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ML20212J3561999-09-30030 September 1999
Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21
ML20212J3801999-09-30030 September 1999
Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21
IR 05000244/19990051999-09-24024 September 1999
Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
ML17265A7571999-09-24024 September 1999
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IR 05000244/19992011999-09-24024 September 1999
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ML17265A7401999-08-26026 August 1999
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Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future
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Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
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Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
ML17265A6671999-06-0101 June 1999
Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301
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Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested
ML17265A6611999-05-24024 May 1999
Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730
ML20206U0921999-05-13013 May 1999
Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21
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ML17265A6411999-05-12012 May 1999
Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630
ML20206E7221999-04-29029 April 1999
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ML20206H6911999-04-22022 April 1999
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ML17265A5671999-03-0101 March 1999
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ML17265A5551999-02-25025 February 1999
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ML17265A5561999-02-22022 February 1999
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ML17265A5451999-02-12012 February 1999
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Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
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ML17265A5361999-02-0202 February 1999
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ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
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Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated
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ML17265A7631999-10-0505 October 1999
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ML17265A7641999-10-0505 October 1999
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IR 05000244/19990051999-09-24024 September 1999
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Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs
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Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726
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Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded
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Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806
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ML17265A7271999-07-30030 July 1999
Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply
ML17265A7151999-07-23023 July 1999
Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions
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Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations
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Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999
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Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future
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Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603
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Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached
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Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl
ML17265A6841999-06-21021 June 1999
Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
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Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification
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Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
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Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP
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1999-09-30
[Table view] |
Text
ACCELERATEDDIBUTIONDEMONSTIONSYSTEMREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9111050285DOC.DATE:91/10/28NOTARIZED:YESDOCKETFACIL:50-244RobertEmmetGinnaNuclearPlant,Unit1,RochesterG05000244AUTH.NAMEAUTHORAFFILIATIONMECREDY,R.C.RochesterGas&ElectricCorp.RECIP.NAMERECIPIENTAFFILIATION-JOHNSON,A.R.ProjectDirectorateI-3NIRCTQ
SUBJECT:
ForwardsresponsetoGenericLtr91-06,"ResolutionofGenericIssueA-30,'AdequacyofSafety-RelateddcPowerSupplies.'".AdvisesthatspecificactionplannedinresponsetoQuestions6,7.b.4,7.c.367.c.5.DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionRDNOTES:LicenseExpdateinaccordancewith10CFR2,2.109(9/19/72).05000244ARECIPIENTIDCODE/NAMEPDl-3LAJOHNSON,AINTERNAL:NRR/DET/ECMB7DNRR/DOEA/OTSB11NRR/DST/SELB7ENRR/DST/SRXB8EOC/~LEBRPI'LE0-COPIESLTTRENCL1122111111111011RECIPIENTIDCODE/NAMEPD1-3PDNRR/DET/ESGBNRR/DST8E2NRR/DST/SICB8H7NUDOCS-ABSTRACTOGC/HDS1RES/DSIR/EIBCOPIESLTTRENCL11111111111011DD11EXTERNAL:NRCPDRQ~/v>pSyS73(/4~NSIC11DNOTETOALL"RIDS"RECIPIENTS:ADDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLINISFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR18ENCL16
~giiiiiiiiiiIIIiiIZZiirZi'IrIIIIIIIIIII'Z~'iiiiiiIIIIROCHESTERGASANDELECTRICCORPORATIONo89EASTAVENUE,ROCHESTERN.Y.14649-0001ROBERTC.MECREDYVicePresidentClnnaNuclearProductionOctober28,1991TELEPHONEAREACODE71B646.2700U.S.NuclearRegulatoryCommissionDocumentControlDeskAttn:All'enR.JohnsonProjectDirectorateI-3Washington,D.C.20555
Subject:
ResolutionofGenericIssueA-30,AdequacyofSafety-Related.DCPowerSupplies(GenericLetter91-06)dated,April29,1991R.E.GinnaNuclearPowerPlantDocketNo.50-244
DearMr.Johnson:
GenericLetter91-06requestedawrittenresponsewithin180daystospecificquestionsasrelatedtoGenericIssue(GI)A-30,SafetyRelatedDCPowerSystems.ThequestionsandourresponsesareprovidedinATTACHMENT1.Specificactionsareplannedinresponsetoquestions6,7.b.4,7.c.3,and.7.c.5.Verytrulyyours,GAL/192AttachmentsRobertC.MecredySubscribedandsworntobeforemeonth'dayofOctober,1991SAMUELkBROWNBMTAAYPUBUC,SnaedNewYot1tRegIatrationNsL4917041Chal'fatdinMonroeCly.IWayneOy.My~tbphe0eo.28,1'c:Mr.AllenR.Johnson(MailStop14D1)ProjectDirectorateI-3Washington,D.C.20555U.S.NuclearRegulatoryCommissionRegionI475AllendaleRoadKingofPrussia,PA19406GinnaSeniorResidentInspector~riI7PIB//fP9ii10502859ii028PDR--'--'ADGCK05000244PDRP
~~3NVeOAOJ)33VMAR&4V~RIO~.~,~~>47ggtKitCa.~.Nr.+O.(C~Vl.~i"'gCt>Mcr;<..~=.."..Oy~3 ResonseToGenericLetter91-06uestions:Thefollowinginformationistobeprovidedforeachunitateachsite:UnitR.E.GinnaNuclearPlant2~a~ThenumberofindependentredundantdivisionsofClass1Eorsafety-relateddcpowerforthisplantis2(IncludinganyseparateClass1Eorsafety-relateddc,suchasanydcdedicatedtothedieselgenerators.)b.Thenumberoffunctionalsafety-relateddivisionsofdcpowernecessarytoattainsafeshutdownforthisunitis1~3~Doesthecontrolroomatthisunithavethefollowingseparate,independentlyannunciatedalarmsandindicationsforeachdivisionofdcpower?a~alarms1~2.Batterydisconnectorcircuitbreakeropen?NOBatterychargerdisconnectorcircuitbreakeropen(bothinputacoroutputdc)?NO3~dcsystemground?NO4~5.dcbusundervoltage?NOdcbusovervoltage?NODCsystemovervoltageismeasuredatthebatteryterminals.6.Batterychargerfailure?NO7~Batterydischarge?NOb.Indications1~2~Batteryfloatchargecurrent?YESBatterycircuitoutputcurrent?YES3~4~Batterydischarge?YESBusVoltage?YES Thebatterymonitoringsystemprovideslocalandcontrolroomindicationofbatterydischargeandthedischargecurrent,batteryfloatchargecurrentandbatteryvoltage.Thereisalsoaseparatemeterinthecontrolroomprovidingindicationfordcsystembusvoltage.c.Doestheunithavewrittenproceduresforresponsetotheabovealarmsandindications?YES4~Doesthisunithaveindicationofbypassedandinoperablestatusofcircuitbreakersorotherdevicesthatcanbeusedtodisconnectthebatteryandbatterychargerfromitsdcbusandthebatterychargerfromitsacpowersourceduringmaintenanceortesting?YESAbatterymonitoringsystemprovidescontrolroomannunciationuponalossofbatterychargingcurrent.Thereforeindicationofthedisconnectionofthebatteryfromthedcsystemisprovided.Indicationisalsoprovidedinthecontrolroomforthedisconnectionofeachbatterychargerfromthedcsystemorfromitsacpowersource.5.Iftheanswertoanypartofquestion3or4isno,thenprovideinformationjustifyingtheexistingdesignfeaturesofthefacility'ssafety-relateddcsystems.*Seenotebelow.Justificationforuestion3Thereisannunciationinthecontrolroomforallthealarmfunctionsidentifiedinquestion3,butcircuitsforbothtrainsareannunciated'tcommonannunciatorwindows.Therefore,thecontrolroomdoesnothaveseparate,independentlyannunciatedalarmsforbothdivisionofdcpower.Thisisacceptablebecauseifaproblemis'identified,ononebatterydivision,theoperatorsareinstructedbyprocedureand/ortrainingtoperiodicallymonitortheotherDCdivision.Separateindicationsareinthecontrolroomforbothdivisions,thereforemonitoringoftheunaffecteddivisioncanbeaccomplishedfromthecontrolroom.6.(1)Haveyouconductedareviewofmaintenanceandtestingactivitiestominimizepotentialforhumanerrorcausingmorethanonedcdivisiontobeunavailable?YESand(2)doplantproceduresprohibitmaintenanceortestingonredundantdcdivisionsatthesametime?NO
IfthefacilityTechnicalSpecificationshaveprovisionsequivalenttothosefoundintheWestinghouseandCombustionEngineeringStandardTechnicalSpecificationsformaintenanceandsurveillance,thenquestion7maybeskippedandastatementtothateffectmaybeinsertedhere.NotEuivalent7~Aremaintenance,surveillanceandtestproceduresregardingstationbatteriesconductedroutinelyatthisplant?Specifically:a0Atleastonceper7daysarethefollowingverifiedtobewithinacceptablelimits:2.Pilotcellelectrolytelevel?YESSpecificgravityorchargingcurrent?NO3.FloatVoltage?NOTotalbusvoltageonfloatcharge?NO5.Physicalconditionofallcells?YESb.Atleastonce.per92days,orwithin7daysafterabatterydischarge,overcharge,orifthepilotcellreadingsareoutsidethe7-daysurveillancerequirementsarethefollowingverifiedtobewithinacceptablelimits:Thefollowingparametersareverifiedtobewithinacceptablelimitseverquarter:2.3.Electrolytelevelofeachcell?YESTheaveragespecificgravityofallcells?YESThespecificgravityofeachcell?YES4~Theaverageelectrolytetemperatureofarepresentativenumberofcells?NO5.Thefloatvoltageofeachcell?YES6.Visuallyinspectormeasureresistanceofterminalsandconnectors(includingtheconnectorsatthedcbus)?NO tIf c~Atleastevery18months'arethefollowingverified:1~Lowresistanceofeachconnection(bytest)?YES2~Physicalconditionofthebattery?YES3.4~Batterychargercapabilitytodeliverratedampereoutputtothedcbus?NOThecapabilityofthebatterytodeliveritsdesigndutycycletothedcbus?YESEachindividualcellvoltageiswithinacceptablelimitsduringtheservicetest?NOd.Atleastevery60months,iscapacityofeachbatteryverifiedbyperformanceofadischargetest?YESe.Atleastannually,isthebatterycapacityverifiedbyperformancedischargetest,ifthebatteryshowssignsofdegradationorhasreached85%oftheexpectedservicelife?YESDoesthisplanthaveoperationalfeaturessuchthatfollowinglossofonesafety-relateddcpowersupplyorbus:a0b.Capabilityismaintainedforensuringcontinuedandadequatereactorcooling?YESReactorcoolantsystemintegrityandisolationcapabilityaremaintained?YESc~Operatingprocedure,instrumentation(includingindicatorsandannunciators),andcontrolfunctionsareadequatetoinitiatesystemsasrequiredtomaintainadequatecorecooling?YESIftheanswertoanypartofquestion6,7or8isno,thenprovideyourbasisfornotperformingthemaintenance,surveillanceandtestproceduresdescribedand/orthebasesfornotincludingtheoperationalfeaturescited.*Seenotebelow.
~~
Justificationtouestion6:RG&EconductedanextensivereviewofmaintenanceandtestproceduresaspartofourresponsetoInspectionReport90-031datedFebruary8,1991.Proceduresthatarestillbeingreviewedareinquarantinependingreviewcompletion.Proceduresfor1Aand1BBatterySystemMaintenanceandRepairverifyoperabilityoftheredundantbatterysystemasaninitialcondition.However,atpresentthereisnospecificprohibitioninallmaintenanceprocedures.ItisRG&Espolicytoprohibitmaintenanceortestingonredundantdcdivisionsatthesametime.RG&Ewillinvestigatetheneedtoplacemorespecificprohibitioninallapplicableprocedurestoensuretheintegrityofthedcsystem.Justificationtouestion7a:Duringtheperformanceofplanttours,normallytwicepershift,thespecifiedbatteryparametersaremonitoredtoensurenormaloperation.AlsoinaccordancewithRegulatoryGuide1.129,"Maintenance,TestingandReplacementofLargeLeadStorageBatteriesforNuclearPowerPlants",monthlyinspectionsareperformedperIEEE-450,"LargeLeadStorageBatteriesforGeneratingStations".Allthespecifiedbatteryparametersareverifiedtobewithinacceptablelimits.Justificationtouestion7b.4:Plantproceduresarecurrentlybeingrevisedtoincludeacceptablelimitsfortheaverageelectrolytetemperature.Presentlytheaverageelectrolytetemperatureiscalculatedforthepurposeof-.calculatingthespecificgravity.Justificationtouestion7b.6:InaccordancewithIEEE-450,"LargeLeadStorageBatteriesforGeneratingStations",celltocellterminalconnectionresistanceisverifiedtobewithinacceptablelimitsduringtheyearlytest.However,monthlytheterminalsarevisuallyinspectedforanyevidenceofcorrosion.Theconnectorsatthedcbusarenotsubjectedtothesamecorrosiveelementsascellterminalconnectionsandthereforearenotvisuallyinspectedmonthly.
-rvrCmawt-Justificationtouestion7c.3:Plantproceduresarecurrentlybeingrevisedtoincludetestingofthechargerstoensuretheycandelivertheirratedampereoutput.Theplantprocedurewillberevisedpriortotheperformanceofthenextannualbatteryservicetest.andthechargercapabilitywillbeverifiedduringtheservicetest.Justificationtouestion7c.5:Plantproceduresarecurrentlybeingrevisedtoincludemonitoringofeachcellvoltageduringtheannualservicetesttoensurethattheyremainwithinacceptablelimits.Theplantprocedurewillberevisedpriortotheperformanceofthenextannualbatteryservicetest.*Note:Forquestionsinvolvingsupportingtypeinformation(questionnumbers5and9)insteadofdevelopingandsupplyingtheinformationinresponsetothisletter,youmaycommittofurtherevaluatetheneedforsuchprovisionsduringtheperformanceofyourindividualplantexaminationforsevereaccidentvulnerabilities(IPE).Ifyouselectthisoption,youarerequiredto:(1)Sostateinresponsetothesequestions,and(2)Committoexplicitlyaddressquestions5and9inyourIPEsubmittalpertheguidelinesoutlinedinNUREG-1335(Section2.1.6,Subitem7),"IndividualPlantExamination:SubmittalGuidance."