ML102430462
| ML102430462 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/30/2010 |
| From: | Hartz L N Dominion, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 10-122A | |
| Download: ML102430462 (17) | |
Text
10CFR50.90 VIRGI NI A ELECTRICAND POWE R COMPANY RICH MOND, VIRGINIA 232 61August30,2010U.S.NuclearRegulatoryCommissionAttention:DocumentControlDesk Washington
,D.C.20555SerialNo.10-122A NL&OS/ETS RODocketNos.50-338/339LicenseNos.NPF-4/7 VIRGINIA ELECTRICANDPOWER COMPANY (DOMINION)NORTHANNAPOWER STATIONUNITS1AND2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PROPOSED LICENSE AMENDMENTREQUESTREGARDING RISK-INFORMED JUSTIFICATIONFORTHE RELOCATIONOFSPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTSTOALICENSEE CONTROLLED PROGRAM (ADOPTION OF TSTF-425,REVISION3)InaMarch30,2010letter(SerialNO.10-050),Dominionrequestedamendments,intheformofchangestotheTechnicalSpecifications(TS)toFacilityOperatingLicenseNumbersNPF-4andNPF-7,forNorthAnnaPowerStationUnits1and2,respectively.TheproposedamendmentswouldmodifyNorthAnnaTSbyrelocatingspecificsurveillancefrequenciestoa licensee-controlledprogramwiththeimplementationofNuclearEnergyInstitute(NEI)04-10,"Risk-InformedTechnical Specifications Initiative5b,Risk-InformedMethodforControlofSurveillanceFrequencies."InanAugust6,2010e-mailfromDr.V.Sreenivas,theNRCrequestedadditionalinformationtocompletethereviewofthelicenseamendmentrequest.The attachmenttothisletterprovidestheinformationrequestedintheAugust6,2010e-mail.Theinformationprovidedinthisletterdoesnotaffecttheconclusionofthesignificant hazards considerationdiscussionprovidedinDominionletterdatedMarch30,2010(SerialNO.10-050)forNorthAnna.DominioncontinuestorequestapprovaloftheproposedlicenseamendmentsbyApril1,2011 ,withtheamendmentsbeingimplementedwithin120days.Inaccordancewith10CFR50.91,"NoticeforPublicComment;StateConsultation,"acopyofthisresponse,withattachments,isbeingprovidedtothedesignatedState Officials.
SerialNo.10-122ADocketNos.50
-338/339LAR-Relocate Surveillance FrequenciesfromTSPage2of3Ifyouhaveanyquestionsorrequireadditional
.information,pleasecontactMr.ThomasShaubat(804)273-2763.
Sincerely,VicePresident-NuclearSupportServices Attachments:1.ResponseToRequestForAdditionalInformation-PRAQualityConcerns2.ResponseToRequestForAdditionalInformation-RevisedInsertforTSBases ChangesCommitmentsmadeinthisletter:DominionwillassessthePRAmodelgapsforeachsurveillancefrequencychangeuntilthePRAmodelofrecordisupdated.
COMMONWEALTHOFVIRGINIA COUNTY OF HENRICOTheforegoing document was acknowledgedbeforeme ,inandforthe County and Commonwealth aforesaid,todaybyLeslieN.Hartz,whoisVice President-Nuclear SupportServices,ofVirginiaElectricandPowerCompany.Shehasaffirmedbeforemethatsheisdulyauthorizedtoexecuteandfiletheforegoing documentinbehalfofthatCompany,andthatthe statementsinthe documentaretruetothebestofherknowledgeandbelief.
Acknowledged beforemethis df)7l'day of d (just ,2010.My Commission Expires: 9 31, dO 1'1-.,;[...Icl L (.X,\.j..}U.QQ_NotaryPublic V1CKll.HUll fCotary Public Commonwtallt of VIrgilIa 140542.., ConInIiAion ExpIrn Mar 31.2014 cc:U.S.Nuclear Regulatory CommissionRegionII Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, Georgia 30303-1257Mr.J.E.Reasor,Jr.
Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.Suite 300GlenAllen, Virginia 23060 State Health Commissioner Virginia DepartmentofHealth James Madison Building-7th floor 109 Governor StreetSuite730 Richmond, Virginia 23219 NRC Senior Resident Inspector North Anna Power StationMs.K.R.Cotton NRC Project Manager U.S.Nuclear Regulatory Commission One WhiteFlintNorthMailStop 08 G9A 11555 Rockville Pike Rockville, Maryland 20852Dr.V.Sreenivas NRC Project ManagerU.S.Nuclear Regulatory Commission One WhiteFlintNorthMailStop 08 G9A 11555 Rockville Pike Rockville, Maryland 20852SerialNo.10-122ADocketNos.50-338/339LAR-Relocate Surveillance FrequenciesfromTSPage3of3 SerialNo.10-122ADocketNos.50-338/339ResponseToRequestForAdditionalInformationLAR-Relocate Surveillance FrequenciesfromTS ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PROPOSED LICENSE AMENDMENT REQUEST REGARDING RISK-INFORMED JUSTIFICATIONFORTHE RELOCATIONOFSPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTSTOA LICENSEE CONTROLLED PROGRAM PRA QUALITY CONCERNS VIRGINIA ELECTRICANDPOWER COMPANY (DOMINION)NORTHANNA POWER STATIONUNITS1AND2 SerialNo.10-122ADocketNos.50-338/339ResponseToRequestForAdditionalInformation LAR-Relocate Surveillance FrequenciesfromTSPage1of11 NRC Question1and2Table1ofAttachment2hasbeenupdatedtoaddresstheNRC'sRequestforAdditionalInformation.Specifically,questions1and2:
.1.InTable1ofAttachment2ofthesubmittal,theimportanceofeachgaptothisapplicationinmanyinstancesisdispositionedsimplybyreferringtotheNuclearEnergyInstitute(NEI)04-10requirementtoassessdeficiencieswithsensitivityanalyses.Thisstatementaloneisinsufficientforthestafftofindtheprobabilisticriskassessment(PRA)modeladequatetosupporttheapplication.Thelicenseeisrequestedtoprovideitsassessmentofthesignificanceofeachgaptothecalculationofriskincreasesassociatedwithchangestosurveillancefrequency.ThisisrequestedforthefollowingitemsinTable1:#1,#2,#3(1),#4(1),#5,#7,#9,#10,and#17.2.InTable1ofAttachment2ofthesubmittal,severalgaps(#3,#4(1),#5,#7,#9)identifymissinglogicinthePRAmodel(inadequatescope).ItisnotcleartothestaffhowmissingscopeinaPRAcanbeaddressedbysensitivityanalyses.Thelicenseeisrequestedtodiscusshowitwouldconductsuchanalysesforthisapplication.ThisisrequestedforthefollowingitemsinTable1:#3,#4(1),#5,#7,and#9.
Dominion ResponseTable1hasbeenrevisedtoaddresstheaboveRAls.Therevisionsareincludedincolumntitled, Importance to Application.Specifically,theresponsestoquestion
- 1 startoffwith"Significance"andtheresponsestoquestion#2beginwith"InadequateScope."Foreachsurveillancetestintervalchange,missinglogicgaps(inadequatescope)willbeaddressedviatheuseofsensitivitystudies.ThemodelusedforthesensitivitystudywillaccountforthespecificlogicgapsasshowninTable1.Inaddition,thePRAinputtotheexpertpanelwillincludeadocumenteddiscussiononeachoftheaforementionedgaps.TheuseofgapsensitivitystudieswillnolongerberequiredoncethegapshavebeenincorporatedintotheNAPSPRAmodelofrecord.TheDominionPRAmodelsareusuallyupdatedaroundevery3to5years
- SerialNo.10-122ADocketNos.
50-338/339Page2of11Table1StatusofidentifiedGapstoNEI00-02and CapabilityCategoryIIoftheASMEPRAStandard Title DescriptionNEIElement ICurrentStatus I Comment Importance to Application ASMESRGap#1A TWS modelingofAS-9 , ATWSFailureRelief Probability is Conservative modelingofthe A1VVS Failure potentially dominate QU-11, conservatively modeledbasedon Probabilities
'Nillbeaddressedby sensitivities per NEI dominant sequences ST-13aUET (UnfavorableExposure0410
,Revision1ifapplioabletothe speoific STIanddata traceabilityTime)of27%
.evaluation
.Significance:TheNAPSATWSmodelusesa conservative simplification that assumesthatpressurereliefisalways insufficient whenevertheunitisintheUETperiod,whichis assumedtobe27%.Thisisa conservativebiassincethereisa probability thatpressurereliefis successfulgiventhe availabilityofthe pressurizer PORVs ,safetiesandAFW.The sensitivitystudieswillincludeanATWS assessment in accordance with WCAP-15831, WOG Risk-Informed A TWS Assessment and Licensing Implementation Processusingthe generic methodologyandvalues.Gap#2 For initiatingeventIE-C8ThecurrentNAPS system-level Support system level initiating eventfaulttreeswillbe fault-tree modeling, initiatingeventfaulttreesusesaaddressedby sensitivities per NEI0410 ,Revision1ifcaptureallrelevant 365*Capacity Factor multiplierinapplioabletothespeoifio STI evaluation.
combinationsofeventsallofthe initiatingeventfaulttrees, involvingtheannualwhichneedstobereplacedw ith Significance:Thisissueis importantforany potential frequencyofonethenew methodology described in SurveillanceTestInterval(STI)change impacting component failure EPRI TR-1013490,"Supportsupportsystem initiating events.Therefore, the combinedwiththeSystemInitiatingEvents:
system-level initiatingeventswillberevisedusingthe unavailability of other Identification and Quantification methodologyinEPRITR-1013490 methodology.
components Guideline", EPRI , December 2006.
SerialNo.10-122A Docket Nos.50-338/339Page3of11Table1StatusofidentifiedGapstoNEI00-02and Capability CategoryIIoftheASMEPRAStandard Title DescriptionNEIElement I Current Status I Comment Importance to Application ASMESRGap#3Forkey safety functions AS-A4SRisNOTMETuntil
- 1)anHEPis 1)HEPforrestoringof EGGSduringSBOwillbe (e.g., poweraddedtotheSBOnodesfor addressed by sensitivities per NEI0410,Revision1if restoration) identifyrestoringtheEGGS functions; and appl ioabletothespeoifioSTI evaluation
.operator actions to 2)textinseotion 2.3.3.1isthe achievethedefined accident sequence documentation Significance:
Non-considerationofthis operator actionsuccesscriteria.needstoberevisedtoclarifytheresultsinasmall non-conservatisminthe Stationneedfor operatoractiontorestart Black-Out (SBO)accident sequencesresults.The EGGS functions.overallimpactontheresultsissmall.
Inadequate Scope:AnHumanError Probability(HEP)willbeaddedtothe sensitivityPRAmodelwhen quantifyingtheeffectofaproposed individual STIrevisionfor comparison to acceptance criteriainNEI04-10.Rev ision 1.2)None.Thisis judgedtobea documentation considerationonlyanddoesnot affect the technical adequacyofthePRAmodel.
Serial No."10-122A Docket Nos.50-338/339Page4of11 Table 1 Status of identified Gaps toNEI00-02 and Capability Category II of the ASME PRA Standard Title Description NEI Element I Current Status I Comment Importance to Application ASME SRGap#4 Delineate accident AS-A?SRisNOT METuntil:1)inclusion 1)ConsequentiallossofRCPseal cooling for sequence (e.g.,Lossof of consequentiallossofRCPseal transients will be addressed by sensitivities per NEI 04RCPseal cooling)for cooling for transients
,and2)10, Revision1if applicabletothe specific STI each initiating event documentation enhancement of evaluation
.(e.g., transients).theU1-RCPSL nodes.Significance:
ConsequentiallossofRCPseal coolingisnot specifically consideredinthe eventtrees,asboththeCCandCH systems would needtofail within the24hoursofan initiating event.The model does include consequential pressurizer PORV failing to reclose ,whichis transferredtothesmall LOCA event tree.The consequential PORV LOCAhasa relativelylowrisk importance
.The consequentiallossofRCPseal cooling i s expected to have a comparable or lower risk impact.Inadeguate Scope: A consequentiallossofRCPseal cooling for transientswillbe addressed in sensitivity studies when quant ifying the effectofa proposed individualSTIrevisionfor comparison to acceptance criteriainNEI 04-10, Revision 1.2)None.This is judgedtobea documentation considerationonlyanddoesnot affect the technical adequacyofthePRA model.
Serial No.10-122A Docket Nos.50-338/339 Page5of11Table1StatusofidentifiedGapstoNEI00-02and CapabilityCategoryIIoftheASMEPRAStandardTitleDescriptionNEIElement ICurrentStatus I Comment Importance to ApplicationASMESRGap#5 Define and model plant AS-B5a Cross-tie unavailabilityduetoCrosstie electrioal bus unavailabilityduetorefuel ing configurations and outages is accountedforwiththe outageswillbe addressed by sensitiv ities per NEI 04 alignmentsthatreflect exception of electrical buses where 10, Revision1if applioabletothe specific STI dependencies.
the unavailability during at power evaluation.
operation is essentially 0 versusoneortwodays during refueling Significance:
Significancewillbe addressed by outages.modeling electrical bus cross-tie unavailability for each sensitivity study.Inadequate Scope: The sensitivity studies will address the electrical bus cross-tie unavailability before quantifying the effectofa proposed individual STIrevisionfor comparison to acceptance criteriainNEI 04-10, Revision 1.Gap#6 Include a discussion of SC-A6 Someofthe success crite ria None.ThisisjUdgedtobea documentation operator actions discussion includes general consideration only and does not affect the technical assumedaspartofthe operator actions,butthe adequacyofthePRA model.success criteria discussiondoesnot include development
,andhow proceduresandnotall event tree those actions are sections contain the discussion consistent with plant procedures and practices SerialNo.10-122A Docket Nos.50-338/339Page6of11 Table 1 Status of identified Gaps toNEI00-02 and Capability Category II of the ASME PRA Standard Title Description NEI Element/Current Status/Comment Importance to Application ASME SRGap#7 IncorporatetheeffectofSY-A11Theou rrentNAPSPRAdoesnot Inadvertent SI Aotuation will be addressed by variable success SY-A13 inolude inadvertent SI Aotuation.sensitivitiesperNEI 04 10 , Revis ion 1 i f applioable to criteria (i.e., success Inadvertent Safety Injection(SI)thespeoifioSTI evaluation.
criteria that change as Actuationhasbeen includedintheafunctionofplantNAPSPRAmodelofrecord, Significance:TheNAPSPRA model,N009A.has status)intothesystem N009Aa.beenupdatedsincetheRITS5bsubm ittal and before modeling.Include receivingtheRequestfor Additional Informat ion.The considerationofalllatestNAPSPRAmodel,N009Aa, includes Inadvertent failure modes, SI Actuation , Significancehasbeen addressed by cons istent with incorporatingtheissueintothePRA model o f record , availabledataand N009Aa.modellevelofdetail Inadeauate Scope:Asstated above, Inadvertent SI Actuat ion was integratedintothelatestNAPSPRAmodel,N009Aa.
Gap#8Useresultsofplant SY-A2TheDom inionPRAstaffhas Not Significant.
This i s judgedtobea documentation walkdownsandplantSY-A4 performed many system conside rationonlyanddoesnot affect the technical personnel interviews SY-B8 walkdowns dur ing the adequacyofthePRAmodel.(system engineersandSY-C1 development and maintenance of operators)asasourcethemodels.In addition , Dominion of information forPRAstaffworks closelywithNorth modelingtheas-built, Anna system engineers and as-operated plant.operators on nearly a daily basis while supporting the various risk informed programs.However, no formal documentationexistsatthistimetoallowclosureoftheseSRs.ItisNOT anticipatedthatnot meeting this requirementwillhave a siqnificantimpactonthemodel.
SerialNo.10-122ADocketNos.
50-338/339Page7of11Table1StatusofidentifiedGapstoNEI00-02and CapabilityCategoryIIoftheASMEPRAStandard Title DescriptionNEIElement
/CurrentStatus/
Comment Importance to ApplicationASMESRGap#9IdentifySSCsthatmaySY-B15Currently, theNAPSPRAmodelPZRPORVsfailingtoreoloseon waterreliefwillbeberequiredtooperatedoesnot distinguishbetweenPZRaddressedby sensitivities per NEI0410,Revision1ifinconditionsbeyondPORVsfailingtorecloseonwaterapplioabletothespeoifioSTIevaluation.
their environmentalreliefandsteam qualifications.
Significance:Currently,theNAPSPRAmodeldoes not distinguishbetweenPZRPORVsfailingtorecloseonsteamorwaterrelief.EPRI TR-1011047
'ProbabilityofSafetyValve Failure-to-Reseat FollowingSteamandLiquidRelief'provides guidance for evaluatingtheincreaseinfailure probability associatedwithpassingwater.
Significancewillbeaddressedby incorporatingtheissueintothe sensitivitystudymodel.
Inadequate Scope: ProbabilityofPZRPORVfailingtorecloseonwaterreliefwillbeaddressedinthe sensitivityPRAmodelwhen quantifyingtheeffectofaproposedindividualSTIrevisionforcomparisonto acceotancecriteriainNEI04-10Revision1.Gap#10BasethetimeavailableHR-G4TimewindowsforsuccessfulSeveralHEP M/\APrunsneedtobeupdatedand,tocompleteactionsoncompletionofactionsinsometherefore,these'Nillbeaddressedby sensitivities per appropriate realisticinstancesmayneedtobeupdated NEI0410 ,Revision1ifapplioabletothespeoifioSTIgenericthermal-(forexample,thosethatarebased evaluation.
NotenotallneoessaryMAAPruns
'Nere hydraulicanalyses,or on estimatesmadefortheIPE)updatedfor N009/\model.simulationfromsimilar plants Significance:Thisgapisnotconsidered significantsincemostoftheNAPStimewindowsare similartotheSurryPowerStation(SPS)timewindows,whicharebasedonupdatedMAAPruns.NAPSandSPSsystemsare similarenoughthatthetimingsaren'texpectedtobesignif icantlydifferent.ForthoseHEPsthatdon'thaveNAPS-specificMAAPanalyses(whichismostofthem),theHEP probabilitieswillbeincreasedbv factorof2.
SerialNo.10-122ADocketNos.50-338/339Page8of11Table1Statusof identifiedGapstoNEI00-02and CapabilityCategoryIIoftheASMEPRAStandardTitleDescriptionNEIElement
/Current Status I Comment Importance to ApplicationASMESRGap#11Basetherequiredt ime HR-G5Noformal documentationcurrentlyNotSignificant.Thisisjudgedtobea documentationtocompleteactionsforexistsandthisSRwillremainNOTconsiderationonlyanddoesnotaffectthetechnical significantHFEsonMET.Asafootno tethetimingsadequacyofthePRAmodel.actiontimearenotexpectedtochange measurementsineither significantlyastheyarebasedon walkthroughsortalk-comparisons with similaractionsatthroughsofthe Surry.procedu res or simulator observations.Gap#12Checkthe consistency HR-G6DocumentareviewoftheHFEsNotSignificant.This isjudgedtobea documentationofpost-initiator HEPs.andtheirfinalHEPsrelativetoconsiderationonlyanddoesnotaffectthetechnicaleachothertoconfirm theiradequacyofthePRAmodel.
reasonablenessgiventhescenariocontext,planthistory
, procedures, operational p ractices, and experienceGap#13Whenusingexpert DA-D2 DocumentationneedstobeNotSignificant.Thisisjudgedtobea documentat ion judgmentdocumenttheenhancedfortheseveralcasesconsiderationonlyanddoesnotaffectthetechn icalrationalebehindthewhereexpertopinionisused.TheadequacyofthePRAmodelchoiceof parameterexpertopinionisreasonableand values.shouldnotchance.Gap#14Identify method-specific QU-B1 A lthough key assumptionsareNotSignificant.Thisisjudgedtobea documentationlimitationsandfeaturesQU-F5 documented
,thesedonotincludeconsiderationonlyanddoesnotaffectthetechnicalthatcould impact the limitationsofthe quantificationadequacyofthePRAmodel.resultsandmethodorfeaturesthatimpact applications.results(asidefromreferencestocodelimitations,guidance documentsandprocedures)
.Gap#15IdentifykeysourcesofQU-E1EachPRAelementnotebook(IE,NotSignificant.ThePRA documentationhasidentifiedmodeluncertainty.
AS ,SC ,SY ,DA ,HR,LE)haspotentialsourcesof modelinguncertainty.The identifiedpotentialsourcesofpotentialsourcesof uncertaintywillbeaddressedbymodeluncerta inty.A sensitivitiesperNEI04-10
, Revision1if applicable to characterizationofthosesourcesthespecificSTIevaluation.
of uncertaintyandevaluationofthegenericsourcesof uncertainty hasnotyetbeencompletedhowever.
SerialNo.10-122ADocketNos.
50-338/339Page9of11Table1StatusofidentifiedGapstoNEI00-02and CapabilityCategoryIIoftheASMEPRAStandard Title DescriptionNEIElement I Current Status I Comment Importance to ApplicationASMESRGap#16ProvideadetailedQU-F3 Significantcontributors(basedonNotSignificant.Thisisjudgedtobea documentationdescriptionofF-VandRAW)havebeen considerationonlyanddoesnotaffectthe technical significant accidentidentifiedandevaluated
.AdetailedadequacyofthePRAmodel.sequencesorfunctional descriptionhasbeenprovidedforfailuregroups.thetop5accidentsequences,butnotforallsignificantaccident sequencesorfunctionalfailure qroups.Gap#17Performrealistic LE-D4 SecondarysideisolationduringaTheeffeatofadditionalreliefvalve demands'""ill besecondarysideSGTRshouldalsoconsidertheaddressedby sensitivitystudiesper NEI0410, revision isolation capabilityadditionalnumberofdemandson 1,ifappliaabletothespeaifiaSTIevaluation.analysisforthethereliefvalvesintheprogression sign ificant accidenttocoredamage.
Significance:ThisisaLevel2issue involving the progression sequencesprogressionofcoredamage.Themodel currently doescausedbySGtubenotconsidertheadditionalsteam generatorreliefvalve release.demandsassociatedwithSGTRresultingincoredamage.ThewaterreliefPORVissuewillbeaddressedinthe sensitivitystudiesbyevaluatingtheimpactontheproposed surveillancetestintervalchange.Therefore, significancewillbeaddressedby incorooratinatheissueintothe sensitivitvstudvmodel.
SerialNo.10-122ADocketNos.50-338
/339Page10of11 NRC Question 3InAttachment1,Section2.2,Item3identifiedadeviationfromTechnicalSpecificationTaskForce-425associatedwiththeproposedBases.
Subsequenttothesubmittal
, theU.S.NuclearRegulatoryCommissionissuedadditionalguidanceonacceptableBases(ADAMSML100990099)whichaddressedthespecificissue.
"TheinsertprovidedinTSF-425toreplacetextintheTSBasesdescribingthebasisforeachfrequencyrelocatedtotheSFCPhasbeenrevisedfrom,'TheSurveillanceFrequency(SF)isbasedonoperatingexperience,equipmentreliability
,andplantriskandiscontrolledundertheSurveillanceFrequencyControlProgram
,'toread'TheFrequencymaybebasedonfactorssuchasoperatingexperience,equipmentreliability,orplantrisk
,andiscontrolledundertheSurveillanceFrequencyControlProgram.
'ThisdeviationisnecessarytoreflecttheNAPSbasisforfrequencieswhichdonot
,inall cases ,basefrequencyonoperatingexperience,equipmentreliabilityandplantrisk.
" TSTF-425 ,Revision3,"RelocateSurveillanceFrequenciestoLicenseeControl-RITSTF Init iative 5b,"(ADAMSAccessionNos
,andML090850640)wasapprovedbyNoticeofAvailabilitypublishedinthe Federal RegisteronJuly6 , 2009.TSTF-425,Rev.3involvestherelocationofmosttime-basedsurveillancefrequenciestoalicenseecontrolledprogram,calledtheSurveillanceFrequencyControlProgram(SFCP),andaddstheSFCPtotheadministrativecontrolssectionofTS.TheSFCPdoesnotincludesurveillancefrequenciesthatareeventdriven,controlledbyanexistingprogram,orarecondition-based.PartoftheTSTF-425changetoNUREGs 1430-1434(StandardTechnicalSpecifications)providesanoptionalinsert(INSERT2)totheexistingTechnicalSpecification(TS)BasestofacilitateadoptionoftheTSTFwhileretainingtheexistingNUREGTSSurveillanceFrequencyTSBasesforlicenseesnotchoosingtoadoptTSTF-425.TheTSTF-425TSBasesINSERT2states:"TheSurveillance Frequency is basedonoperatingexperience
, equipment reliability
, and plant risk and is controlledundertheSurveillance Frequency ControlProgram."SeverallicenseesrequestinglicenseamendmentstoadoptTSTF-425haveidentifiedaneedtodeviatefromthisstatementbecauseitonlyappliestofrequenciesthathavebeenchangedinaccordancewiththeSurveillanceFrequencyControlProgram(SFCP)anddoesnotapplytofrequenciesthatarerelocatedbutnotchanged.TheNRCstaffagreesthattheTSTF-425TSBasesinsertappliesonlytorelocatedSFsthatare subsequentlyevaluatedandchangedinaccordancewiththeSFCP
,andthatthecurrentinsertdoesnotapplytoSFsrelocatedtotheSFCPbutremainunchanged.ForSFsrelocatedtotheSFCPbutnotsubsequentlychangedinaccordancewiththeprogram,theexistingTSBasesdescriptionremainsavalidBasesfortheseSFs.
SerialNo.10-122ADocketNos.50-338/339Page11of11Oneoptiontoaddressthisconcernforthoseinstanceswherethelicenseeused425Insert2
,istomodifythewordingusedintheapplicationasfollows:
"TheSurveillance Frequency is controlledundertheSurveillanceFrequencyControl Program"Inaddition,thefollowingstatementshouldbeincludedregardingSFBasesrelocatedtotheSFCP:"TheexistingBasesinformationdescribingthebasisfortheSurveillanceFrequencywillberelocatedtothe licensee-controlledSurveillanceFrequencyControlProgram."ItshouldbenotedthatonlytheBasesfortheSurveillanceFrequencycanberelocatedtotheSFCP.TheBasesfortheTSSurveillancewillremainintheTSBasesandshouldnotberelocatedtotheSFCP.ThelicenseeisrequestedtoprovidearevisiontoitsproposedBaseschangesconsistentwiththisguidance.VEPCO'sapplicationdatedMarch30,2010,includedtheaforementioneddeviationsfromtheproposedlanguageinTSTF-425,Revision3.TheNRCstaffhasreviewedtheproposeddeviationfromTSTF-425andrequeststhatthelicenseemodifythe application
,asdescribedabove,ordevelopanalternateresolutiontotheissuewithInsert2asdescribedinitem3,andincludingappropriatejustifications.
Dominion ResponseDominionwasawareoftheNRCguidanceprovidedintheApril2010letter.Inaddition,totheletter,severaldiscussionshavetakenplacebetweentheNRCandTechnicalSpecificationTaskForce(TSTF)todeveloptheappropriatewordingoftheBases.DominionhasreviewedthisadditionalguidanceandisprovidingarevisiontoitsproposedBaseschangesconsistentthelatestguidancefromtheNRCandTSTF.ThefollowingBaseswordswillbeusedtodiscussthebasisforsurveillancefrequenciesconsistentwiththeNRCguidance:
'TheSurveillance Frequency is controlledundertheSurveillanceFrequencyControlProgram."AcorrectedInsert1fortheBaseschangesisincluded.PleaseusetherevisedInsert1tocompletethereviewoftheproposedMarch30
,2010LARBaseschanges.AfterNRCapprovaloftheLARandaspartoftheLAR implementation
,theexistingNorthAnnaBasesinformationdescribingthebasisfortherelocatedSurveillanceFrequencieswillalsoberelocatedtotheNorthAnnaSurveillanceFrequencyControl Program.
SerialNo.10-122ADocketNos.
50-338/339 ATTACHMENT 2RESPONSETOREQUESTFOR ADDITIONAL INFORMATION PROPOSED LICENSE AMENDMENTREQUESTREGARDING RISK-INFORMED JUSTIFICATIONFORTHE RELOCATIONOFSPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTSTOALICENSEE CONTROLLED PROGRAMREVISEDINSERTFORTSBASESCHANGES VIRGINIA ELECTRICANDPOWER COMPANY (DOMINION)
NORTH ANNA POWER STATIONUNITS1AND2 Ser ialNo.10-122ADocketNos.50
-338/339 REVISED INSERT FOR TECHNICAL SPECIFICATIONS BASESINSERT1 The Surveillance Frequency is controlledunderthe Surveillance Frequency Control Program.