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| {{#Wiki_filter:ATTACHMENT ICHANGESTOTECHNICAL SPECIFICATIONS ST.LUCIEUNITIDPR-67+5072~0~~ | | {{#Wiki_filter:ATTACHMENT I CHANGES TO TECHNICAL SPECIFICATIONS ST.LUCIE UNIT I DPR-67+5072~0~~pg()p0335,:, i".)q.85O7>~PDR PDOCK.;'PD P e |
| pg()p0335,:, | | TABLE 3.3-11 ACCIDENT NON ITORING INSTRUHENTATION n'INSTRUHENT 1.Pressurizer Mater Level 2.Auxiliary Feedwater Flow Rate 3.RCS Subcooling Hargin Honitor 4.PORV Position Indicator Acoustic Flow Honitor 5.PORV Block Valve Position Indicator TOTAL NO.OF CIIANNI:LS |
| i".)q.85O7>~PDRPDOCK.;'PDP e | | ~3 1/pump 1/valve 1/valve HINIHUH ,CIIANNELS 01'LIIABLE 1/pump 1/valve 1/valve ACTION 6.Safety Valve Position Indicator 7.~co~T HERNocGo ply&8.Cou~ai~~aer Su<p~M LC.&(porrou)RA+ge)'R.CDQTFg&pierur Sv~p~M+"c~(~>~Ryan)1/valve 1/val ve.3 q/cora re Weceng.c~c'~~Aeachoc'g~.) |
| TABLE3.3-11ACCIDENTNONITORINGINSTRUHENTATION n'INSTRUHENT 1.Pressurizer MaterLevel2.Auxiliary Feedwater FlowRate3.RCSSubcooling HarginHonitor4.PORVPositionIndicator AcousticFlowHonitor5.PORVBlockValvePositionIndicator TOTALNO.OFCIIANNI:LS
| | Leva(Meo'hcioq Qe4u QOL77ht OvletJ7 Ppc85u~~~e NOW-mP~@WCe.Co~ieamem Su~P (Qck~g~+t (IMP{7~'Nay Se SoS n7om~DoR<AT<<oF~"~a: A CRadtJEL lS GQfhP~P C4 (8 j K(Qkk SCPScrcS lD.I'~S~>SF 43H>c.H (9)gou~sensa~eooar~&peep,S<a. |
| ~31/pump1/valve1/valveHINIHUH,CIIANNELS 01'LIIABLE 1/pump1/valve1/valveACTION6.SafetyValvePositionIndicator 7.~co~THERNocGoply&8.Cou~ai~~aer Su<p~MLC.&(porrou)RA+ge)'R.CDQTFg&pierur Sv~p~M+"c~(~>~Ryan)1/valve1/valve.3q/corareWeceng.c~c'~~Aeachoc'g~.) | |
| Leva(Meo'hcioq Qe4uQOL77htOvletJ7Ppc85u~~~eNOW-mP~@WCe.Co~ieamem Su~P(Qck~g~+t(IMP{7~'Nay SeSoSn7om~DoR<AT<<oF~"~a:ACRadtJELlSGQfhP~PC4(8jK(QkkSCPScrcSlD.I'~S~>SF43H>c.H(9)gou~sensa~eooar~&peep,S<a. | |
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| TABLE3.3-II(Continued)
| | TABLE 3.3-I I (Continued) |
| ACTIONSTATEMENTS ACTIONI-WiththenumberofOPERABLEchannelslessthanrequiredbyTable3.3-II,eitherrestoretheinoperable channel(s) toOPERABLEstatuswithin30daysorbeinHOTSTANDBYwithinthenextl2hours.ACTION2-Withpositionindication inoperable, restoretheinoperable indicator toOPERABLEstatusorclosetheassociated PORVblockvalveandremovepowerfromitsoperatorwithin48hoursorbeinHOTSTANDBYwithinthenext6hours.ACTION3-ACTION4-ACTION5-Withanyindividual valvepositionindicator inoperable, obtainquenchtanktemperature, levelandpressureinformation oncepershifttodetermine valveposition.
| | ACTION STATEMENTS ACTION I-With the number of OPERABLE channels less than required by Table 3.3-I I, either restore the inoperable channel(s) to OPERABLE status within 30 days or be in HOT STANDBY within the next l2 hours.ACTION 2-With position indication inoperable, restore the inoperable indicator to OPERABLE status or close the associated PORV block valve and remove power from its operator within 48 hours or be in HOT STANDBY within the next 6 hours.ACTION 3-ACTION 4-ACTION 5-With any individual valve position indicator inoperable, obtain quench tank temperature, level and pressure information once per shift to determine valve position.With the number of OPERABLE Channels one less than the Total Number of Channels shown in Table 3.3-I I, either restore the inoperable channel to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the commission pursuant to the specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirements of Table 3.3-I I, either restore the inoperable channel(s) to OPERABLE status within 48 hours if repairs are feasible without shutting down or: I.Initiate an alternate method of monitoring the reactor vessel inventory; and 2.Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status;and 3.Restore the Channel to OPERABLE status at the next scheduled re fueling.St.Lucie'-Unit I 3/4 3-43 I C m C INSTRUMENT 1.Pressurizer Hater Level 2.Auxiliary Feedwater Flow Rate CkNNNEL CHECK CNANNEL CALIBRATION TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS 3.Reactor Coolant System Subcooling Hargin Monitor.4.PORV Positio'n Indicator 5.PORV Block Valve Position Indicator 6.Safety Valve Postition Indicator 7,+~g~T BQ.~O CAD 0 p IC,g Q, Co a)TAr Q one.~Su mp~~R~Yc.l (V~~e~Pg~qa,')9>>~&~AIL)Mzhtf+~~p 4LkL~P~Y~1 lQ-Re~c&m Y~~t Levzg~oHoci+Sqs&~l~.~~[~+~p~~yvv z.R' |
| WiththenumberofOPERABLEChannelsonelessthantheTotalNumberofChannelsshowninTable3.3-II,eitherrestoretheinoperable channeltoOPERABLEstatuswithin7daysifrepairsarefeasiblewithoutshuttingdownorprepareandsubmitaSpecialReporttothecommission pursuanttothespecification 6.9.2within30daysfollowing theeventoutlining theactiontaken,thecauseoftheinoperability andtheplansandscheduleforrestoring thesystemtoOPERABLEstatus.WiththenumberofOPERABLEChannelslessthantheMinimumChannelsOPERABLErequirements ofTable3.3-II,eitherrestoretheinoperable channel(s) toOPERABLEstatuswithin48hoursifrepairsarefeasiblewithoutshuttingdownor:I.Initiateanalternate methodofmonitoring thereactorvesselinventory; and2.PrepareandsubmitaSpecialReporttotheCommission pursuanttoSpecification 6.9.2within30daysfollowing theeventoutlining theactiontaken,thecauseoftheinoperability andtheplansandscheduleforrestoring thesystemtoOPERABLEstatus;and3.RestoretheChanneltoOPERABLEstatusatthenextscheduled refueling.St.Lucie'-UnitI3/43-43 ICmCINSTRUMENT 1.Pressurizer HaterLevel2.Auxiliary Feedwater FlowRateCkNNNELCHECKCNANNELCALIBRATION TABLE4.3-7ACCIDENTMONITORING INSTRUMENTATION SURVEILLANCE REUIREHENTS 3.ReactorCoolantSystemSubcooling HarginMonitor.4.PORVPositio'n Indicator 5.PORVBlockValvePositionIndicator 6.SafetyValvePostition Indicator 7,+~g~TBQ.~OCAD0pIC,gQ,Coa)TArQone.~Sump~~R~Yc.l(V~~e~Pg~qa,')9>>~&~AIL)Mzhtf+~~p4LkL~P~Y~1lQ-Re~c&mY~~tLevzg~oHoci+Sqs&~l~.~~[~+~p~~yvvz.R'
| | 'C~g 1 y |
| 'C~g1y | | ~~ATTACHMENT 2 CHANGES TO TECHNICAL SPECIFICATIONS ST.LUCIE UNIT 2-NPF-I 6 |
| ~~ATTACHMENT 2CHANGESTOTECHNICAL SPECIFICATIONS ST.LUCIEUNIT2-NPF-I6 | | ~~INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.APPLICABILITY: |
| ~~INSTRUMENTATION ACCIDENTMONITORING INSTRUMENTATION LIMITINGCONDITION FOROPERATION 3.3.3.6Theaccidentmonitoring instrumentation channelsshowninTable3.3-10shallbeOPERABLE. | | MODES 1, 2 and 3.ACTION: a.With the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-10, either restore the inoperable channel to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours.b.With the number of OPERABLE accident monitoring channels less than'k the Minimum Channels OPERABLE requirements of Table 3.3-10;either Add A<4<o~~restore the inoperable channel(s) to OPERABLE status within 48 hours+)or be$n at'least HOT SHUTOOHN within the next 13 hours..The provisions of Specification 3.0.4 are not applicable. |
| APPLICABILITY: | | SURVEILLANCE RE UIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.w Ac<a c sw~e,+vs m xov APPL.y'c gepcvotz,'hs~)Le,vc)wioarroa.~gq ay5TanA>QauTAubnae>>T Su~P~asar L<<l (nlnaan~aaua5)aalto e'k CosrTssitssnentr sunup Loa4ar Lowe((sw><<l3ouqa)ltl5T4ulnow'T& |
| MODES1,2and3.ACTION:a.WiththenumberofOPERABLEaccidentmonitoring channelslessthantheRequiredNumberofChannelsshowninTable3.3-10,eitherrestoretheinoperable channeltoOPERABLEstatuswithin7days,orbeinHOTSHUTDOWNwithinthenext12hours.b.WiththenumberofOPERABLEaccidentmonitoring channelslessthan'ktheMinimumChannelsOPERABLErequirements ofTable3.3-10;eitherAddA<4<o~~restoretheinoperable channel(s) toOPERABLEstatuswithin48hours+)orbe$nat'leastHOTSHUTOOHNwithinthenext13hours..Theprovisions ofSpecification 3.0.4arenotapplicable.
| | A4-nOQ KTAKNGNTS 4PPL'f QN<y VO Rea<70a.'(4 SSC,)Le.Vel.HOSO nO~iQ(Tj Ooonw&mslJT Su~uoa4sr LCM(va~~Gauge)ouo L'owraio~os |
| SURVEILLANCE REUIREMENTS 4.3.3.6Eachaccidentmonitoring instrumentation channelshallbedemonstrated OPERABLEbyperformance oftheCHANNELCHECKandCHANNELCALIBRATION operations atthefrequencies showninTable4.3-7.wAc<acsw~e,+vsmxovAPPL.y'cgepcvotz, | | '5uw p k)sbw.ST.LOCI/-WIIT 3~,3/4 3-41 t |
| 'hs~)Le,vc)wioarroa.~gq ay5TanA>QauTAubnae>>T Su~P~asarL<<l(nlnaan~aaua5)aaltoe'kCosrTssitssnentr sunupLoa4arLowe((sw><<l3ouqa)ltl5T4ulnow'T& | |
| A4-nOQKTAKNGNTS 4PPL'fQN<yVORea<70a.'(4SSC,)Le.Vel.HOSOnO~iQ(TjOoonw&mslJT Su~uoa4srLCM(va~~Gauge)ouoL'owraio~os | |
| '5uwpk)sbw.ST.LOCI/-WIIT3~,3/43-41 t | |
| Sw&~lv)KAJc& | | Sw&~lv)KAJc& |
| TDgk5WiththenumberofOPERABLEChannelsonelessthantheTotalNumberofChannelsshowninTable3.3-II,eitherrestoretheinoperable channeltoOPERABLEstatuswithin7daysifrepairsarefeasiblewithoutshuttingdownorprepareandsubmitaSpecialReporttothecommission pursuanttothespecification 6.9.2within30'daysfollowing theeventoutlining theactiontaken,thecauseoftheinoperability andtheplansandscheduleforrestoring thesystemtoOPERABLEstatus.WiththenumberofOPERABLEChannelslessthantheMinimumChannelsOPERABLErequirements ofTable3.3-II,eitherrestoretheinoperable channel(s) toOPERABLEstatuswithin48hoursifrepairsarefeasiblewithoutshuttingdownor:I.Initiateanalternate methodofmonitoring thereactorvesselinventory; and2.PrepareandsubmitaSpecialReporttotheCommission pursuanttoSpecification 6.9.2within30daysfollowing theeventoutlining theactiontaken,the.causeoftheinoperability andtheplansandscheduleforrestoring thesystemtoOPERABLEstatus;and3.RestoretheChanneltoOPERABLEstatusatthenextscheduled refueling.
| | TD g k 5 With the number of OPERABLE Channels one less than the Total Number of Channels shown in Table 3.3-I I, either restore the inoperable channel to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the commission pursuant to the specification 6.9.2 within 30'days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirements of Table 3.3-I I, either restore the inoperable channel(s) to OPERABLE status within 48 hours if repairs are feasible without shutting down or: I.Initiate an alternate method of monitoring the reactor vessel inventory; and 2.Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the.cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status;and 3.Restore the Channel to OPERABLE status at the next scheduled refueling. |
| TABLE3.3-10ACCIDENTNHITORIHG IHSTRNENTATIOH IMhiEAREAIItOIHSTRNENT REQUIREOHUHOEROFCHANNELSHIHINHCHANNELSOPERABLEl.1'/steaagenerator 1/steaagenerator
| | TABLE 3.3-10 ACCIDENT NHITORIHG IHSTRNENTATIOH I M hi EAR EAI I tO IHSTRNENT REQUIREO HUHOER OF CHANNELS HIHINH CHANNELS OPERABLE l.1'/steaa generator 1/steaa generator]/steaa generator" 1 1 1/valve~*]/valve~e]/yal vere~]*ASS 1 2/core quadrant t,0+4'*~Containaent Pressure.-2 1 2.Reactor Coolant Outlet Teaperature |
| ]/steaagenerator" 111/valve~*]/valve~e | | -THot (Harrow'ange)2 1 3.Reactor.Coolant Inlet Teaperature |
| ]/yalvere~]*ASS12/corequadrantt,0+4'*~Containaent Pressure.-212.ReactorCoolantOutletTeaperature | | -TCold (Mide Range)2 1 4.Reactor Coolant Pressure-Mide Atange.2 S.Pressurizer Mater Level 2 6.Steaa Generator Pressure 2/steaa generator~7.Steaa Generator Mater Level-Harrow Range]/steaa generator 8./team Generator Mater level-Mide Range]/steaa generators S.Refueling Mater Storage Tank Mater Level 2]O.Auxiliary feedwater Flow Rate (Each puap)]/PuePA]].Reactor Cooling System Subcooling Hargin Honitor 2 12.PORV Position/F low Indicator 2/valve*~13.PORV Block Valve Position Indicator]/valve*"]4.Safety Valve Position/Flow Indicator/val ye*RA~]S.'Containment Sump Mater Level (Harrow Range)~]@@*A 16.Containment Mater level (Mide Range)2 D..Incore Theraocouples 4/core quadrant l 3.ReAcvoa Vessel Lc.ve I These corresponding instruaents aay be substituted for each other.""Hot required if.the POAV block valve is shut and power is removed froa the operator.If not available, eonitor the quench tank pressure, level and teeperature, and each safety valve/PORV discharge piping teaperature at least once every 12 hours."~"~The non-safety grade containment sump'water level instrument say be substituted. |
| -THot(Harrow'ange)213.Reactor.CoolantInletTeaperature | | A~~+~op@(c'ore L~<L~u<C Cna Sme Ov(83'>gm~g~n gg g~)<<ahL<('f3 f'oov-~~says~op>~~~~pig. |
| -TCold(MideRange)214.ReactorCoolantPressure-MideAtange.2S.Pressurizer MaterLevel26.SteaaGenerator Pressure2/steaagenerator | | I C n M Ill INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION TABLE 4.3-7 ACCIOENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS Cal CQ D~04 24 3.5.6.7.8.9.10.12.13.14.16.16.Containment Pressure=Reactor Coolant Outlet Temperature |
| ~7.SteaaGenerator MaterLevel-HarrowRange]/steaagenerator 8./teamGenerator Materlevel-MideRange]/steaagenerators S.Refueling MaterStorageTankMaterLevel2]O.Auxiliary feedwater FlowRate(Eachpuap)]/PuePA]].ReactorCoolingSystemSubcooling HarginHonitor212.PORVPosition/F lowIndicator 2/valve*~ | | -TH t (Narrow Range)Reactor Coolant Inlet Telperature-TC ld (Wide Range)Reactor Coolant Pressure-Wide Range Pressurizer Water Level'.Steam Generator Pressure Steam Generator Water Level-Narrow Range Steam Generator Water Level-,Wide Range Refueling Mater Storage Tank Mater Level Auxiliary Feedwater Flow Rate (Each pump)Reactor Coolant System Subcooling Hargin Honitor PORV Position/Flow Indicator PORV Block Valve Position Indicator Safety Valve Position/FLow Indicator Containment Sump Mater Level (Narrow Range)Containment Mater Level (Mide Range)Incore Thermocouples Q>c'woe)j~ej 4've f 8<<~~>~~<~Sq~zz~H H H H H H H H H H H H H H H H H R R R R R R R R R R R R R R.R R R ATTACHMENT 3 NO S IGNIF I CANT HAZARDS CONSIDERATIONS Introduction The requested amendment to the St.Lucie Units I and 2 operciting licenses adds plant instrumentation currently installed and operational to the Technical Specifications. |
| 13.PORVBlockValvePositionIndicator | | This addition will provide a higher degree of control and operational readiness for these instrument channels by requiring operability and monthly surveil lances of accuracy.Evaluation The three criteria for a determination of whether a no significant hazards consideration exists, from IO CFR 50.92(c), are: I)Involve a significant increase in the probability or consequences of an accident previously evaluated, or 2)create the possibility of a new or different kind of accident from any accident previously evaluated; or 3)involve a significant reduction in a margin of safety.A.With respect to the first of the above criteria, the requested license amendment does not increase the probability or.consequences of accidents previously analyzed.The plant hardware and normal operating conditions are not affected by the proposed change since this equipment was previously installed and operating. |
| ]/valve*" | | Addition of monthly surveil lances on these instrument channels will not involve any significant increase in the probability or consequences of an accident previously evaluated but will assure accurate output from these instrument channels.B.With respect to the second criteria, plant hardware and basic plant operation are not affected by the proposed.license amendment. |
| ]4.SafetyValvePosition/Flow Indicator | | Therefore, the possibility for a new or different type of accident is not created.C.With respect to the third criteria, since the consequences of accidents are not increased and new or different types of accidents are not introduced by this amendment, all margins of safety will be maintained. |
| /valye*RA~]S.'Containment SumpMaterLevel(HarrowRange)~]@@*A16.Containment Materlevel(MideRange)2D..IncoreTheraocouples 4/corequadrantl3.ReAcvoaVesselLc.veIThesecorresponding instruaents aaybesubstituted foreachother.""Hotrequiredif.thePOAVblockvalveisshutandpowerisremovedfroatheoperator. | | It is concluded from the above evaluation that this amendment involves no significant hazards considerations. |
| Ifnotavailable, eonitorthequenchtankpressure, levelandteeperature, andeachsafetyvalve/PORV discharge pipingteaperature atleastonceevery12hours."~"~Thenon-safety gradecontainment sump'water levelinstrument saybesubstituted.
| | Furthermore, the proposed amendment is similar to example (I I)of the Commissions examples of amendments that are considered not likely to involve significant hazards considerations in that, it is a change that'onstitutes an additional limitation, restriction or control not presently in the technical specifications. |
| A~~+~op@(c'oreL~<L~u<CCnaSmeOv(83'>gm | | STATE OF FLORIDA COUNTY OF DADE J.W.Williams Jr.being first duly sworn, deposes and says: That he is a Grou Vice President of Florida Power&Light Company, the Licensee herein;That he has executed the foregoing document;that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.J.W.Williams, Jr.Subscribed and sworn to before me this NOTA'RY PUBLIC, in and for the County'f, Dade, S'tate of Florida My Commission expires: |
| ~g~nggg~)<<ahL<('f3f'oov-~~says~op>~~~~pig. | | A)E\r C>'-8'p P<>I~1gq(~<l111}} |
| ICnMIllINSTRUMENT CHANNELCHECKCHANNELCALIBRATION TABLE4.3-7ACCIOENTMONITORING INSTRUMENTATION SURVEILLANCE REUIREHENTS CalCQD~04243.5.6.7.8.9.10.12.13.14.16.16.Containment Pressure=
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| ReactorCoolantOutletTemperature
| |
| -THt(NarrowRange)ReactorCoolantInletTelperature | |
| -TCld(WideRange)ReactorCoolantPressure-WideRangePressurizer WaterLevel'.SteamGenerator PressureSteamGenerator WaterLevel-NarrowRangeSteamGenerator WaterLevel-,WideRangeRefueling MaterStorageTankMaterLevelAuxiliary Feedwater FlowRate(Eachpump)ReactorCoolantSystemSubcooling HarginHonitorPORVPosition/Flow Indicator PORVBlockValvePositionIndicator SafetyValvePosition/FLow Indicator Containment SumpMaterLevel(NarrowRange)Containment MaterLevel(MideRange)IncoreThermocouples Q>c'woe)j~ej4'vef8<<~~>~~<~Sq~zz~HHHHHHHHHHHHHHHHHRRRRRRRRRRRRRR.RRR ATTACHMENT 3NOSIGNIFICANTHAZARDSCONSIDERATIONS Introduction Therequested amendment totheSt.LucieUnitsIand2operciting licensesaddsplantinstrumentation currently installed andoperational totheTechnical Specifications. | |
| Thisadditionwillprovideahigherdegreeofcontrolandoperational readiness fortheseinstrument channelsbyrequiring operability andmonthlysurveillancesofaccuracy.
| |
| Evaluation Thethreecriteriaforadetermination ofwhetheranosignificant hazardsconsideration exists,fromIOCFR50.92(c), | |
| are:I)Involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, or2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated; or3)involveasignificant reduction inamarginofsafety.A.Withrespecttothefirstoftheabovecriteria, therequested licenseamendment doesnotincreasetheprobability or.consequences ofaccidents previously analyzed. | |
| Theplanthardwareandnormaloperating conditions arenotaffectedbytheproposedchangesincethisequipment waspreviously installed andoperating.
| |
| Additionofmonthlysurveillancesontheseinstrument channelswillnotinvolveanysignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated butwillassureaccurateoutputfromtheseinstrument channels.
| |
| B.Withrespecttothesecondcriteria, planthardwareandbasicplantoperation arenotaffectedbytheproposed. | |
| licenseamendment.
| |
| Therefore, thepossibility foranewordifferent typeofaccidentisnotcreated.C.Withrespecttothethirdcriteria, sincetheconsequences ofaccidents arenotincreased andnewordifferent typesofaccidents arenotintroduced bythisamendment, allmarginsofsafetywillbemaintained. | |
| Itisconcluded fromtheaboveevaluation thatthisamendment involvesnosignificant hazardsconsiderations.
| |
| Furthermore, theproposedamendment issimilartoexample(II)oftheCommissions examplesofamendments thatareconsidered notlikelytoinvolvesignificant hazardsconsiderations inthat,itisachangethat'onstitutes anadditional limitation, restriction orcontrolnotpresently inthetechnical specifications. | |
| STATEOFFLORIDACOUNTYOFDADEJ.W.WilliamsJr.beingfirstdulysworn,deposesandsays:ThatheisaGrouVicePresident ofFloridaPower&LightCompany,theLicenseeherein;Thathehasexecutedtheforegoing document; thatthestatements madeinthisdocumentaretrueandcorrecttothebestofhisknowledge, information, andbelief,andthatheisauthorized toexecutethedocumentonbehalfofsaidLicensee.
| |
| J.W.Williams, Jr.Subscribed andsworntobeforemethisNOTA'RYPUBLIC,inandfortheCounty'f,Dade,S'tateofFloridaMyCommission expires: | |
| A)E\rC>'-8'pP<>I~1gq(~<l111}} | |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17241A3541999-06-0101 June 1999 Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status ML17241A3451999-05-24024 May 1999 Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks ML17229B0711999-03-19019 March 1999 Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit ML17229B0201999-02-23023 February 1999 Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution ML17229A9551998-12-16016 December 1998 Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position ML17229A9161998-11-25025 November 1998 Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases ML17229A9251998-11-22022 November 1998 Proposed Tech Specs Revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1 ML17229A9131998-11-19019 November 1998 Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position ML20155C3061998-10-29029 October 1998 Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses ML17229A8441998-08-24024 August 1998 Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal ML17229A7731998-06-15015 June 1998 Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b ML17229A7601998-06-0303 June 1998 Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank ML17229A7511998-05-27027 May 1998 Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews ML17229A7481998-05-27027 May 1998 Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions ML17229A7441998-05-27027 May 1998 Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures ML17229A6501998-03-0303 March 1998 Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls ML17229A5691997-12-31031 December 1997 Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity ML17309A9131997-12-29029 December 1997 Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17229A5491997-12-0101 December 1997 Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion ML17229A4621997-08-22022 August 1997 Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8 ML17229A4341997-08-0101 August 1997 Proposed Tech Specs,Extending semi-annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996 & Associated SE ML17229A3601997-05-29029 May 1997 Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases ML17229A1831996-12-20020 December 1996 Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings ML17229A1611996-12-0909 December 1996 Proposed Tech Specs 1.9a Re Core Operating Limits Rept ML17229A1191996-10-31031 October 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML17229A1111996-10-30030 October 1996 Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel ML17229A1091996-10-28028 October 1996 Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17229A1061996-10-28028 October 1996 Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel ML17228B5641996-07-15015 July 1996 Revised Tech Specs Re Core Alteration Definition ML17228B5041996-06-0101 June 1996 Proposed Tech Specs Re Thermal Margin & RCS Flow Limits ML17228B3761996-01-0404 January 1996 Proposed Tech Specs Rectifying Discrepancy for Each St Lucie Unit & Providing Assurance That Admin Controls for Hpsip Remain Effective in Lower Operational Modes ML17228B3361995-11-22022 November 1995 Proposed TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation,Adapting STS for C-E Plants (NUREG-1432) Spec 3.4.15 ML17228B2451995-08-16016 August 1995 Proposed TS 3.6.6.1, Sbvs. ML17228B2421995-08-16016 August 1995 Proposed Ts,Reflecting Relocation of Selected TS Requirements Re Instrumentation & Emergency & Security Plan Review Process,Per GL 93-07 ML17228B1891995-06-21021 June 1995 Proposed Tech Specs Re Safety Injection Tank Surveillances ML17228B1811995-06-21021 June 1995 Proposed Tech Specs Re Time Allowed to Restore Inoperable LPSI Train to Operable Status ML17228B1791995-06-21021 June 1995 Proposed Tech Specs Re Extended Allowed Outage Time for EDGs ML17228B1471995-05-17017 May 1995 Proposed Tech Specs,Extending Applicability of Current RCS Pressure/Temp Limits & Maximum Allowed RCS Heatup & Cooldown Rates to 23.6 Effective Full Power Yrs of Operation ML17228B1441995-05-17017 May 1995 Proposed Tech Specs Re Administrative & Conforming Update ML17228B0901995-04-0303 April 1995 Proposed Tech Specs Re Incorporation of line-item TS Improvements to TSs 3/4.8.1 & 4.8.1.2.2 for Licenses DPR-67 & NPF-16 ML17228B0591995-02-27027 February 1995 Proposed TS Re Sdcs Min Flow Rate Requirements ML17228B0521995-02-27027 February 1995 Proposed Tech Spec Tables 3.3-3 & 3.3-4 to Accommodate Improved Coincidence Logic & Relay Replacement for 4.16 Kv Loss of Voltage Relays ML17228B0331995-02-22022 February 1995 Proposed TS 4.6.1.3,reflecting Deletion of Refs to Automatic Tester for Containment Personnel Air Lock ML17228A9921995-01-20020 January 1995 Proposed Tech Specs,Relocating Operability Requirements for Incore Detectors to (TS 3/4.3.3.2) to Updated FSAR & Revising Lhr Surveillance 4.2.1.4 & Special Test Exceptions Surveillance 4.10.2.2,4.10.4.2 & 4.10.5.2 ML17228A9031994-11-0202 November 1994 Proposed Tech Specs 3/4.6.2.1 & 3/4.6.2.3,adapting Combined Spec for Containment Spray & Cooling Sys Contained in Std TS for C-E Plants ML17228A8911994-10-27027 October 1994 Proposed Tech Specs,Incorporating Administrative Changes ML17228A6521994-07-28028 July 1994 Proposed Tech Specs Re LTOP Requirements for Power Operated Relief Valves,Per GL 90-06 ML17228A6591994-07-25025 July 1994 Proposed Tech Specs Implementing Enhancements Recommended by GL 93-05, Line-Item TS Improvements to Reduce SR for Testing During Power Operation. ML17228A6561994-07-25025 July 1994 Proposed Tech Specs for Main Feedwater Line Isolation Valves to Be Consistent w/NUREG-1432,standard TS for C-E Plants ML17228A5771994-05-23023 May 1994 Proposed Tech Specs Removing Option That Allows HPCI Pump 1C to Be Used as Alternative to Preferred Pump for Subsystem Operability 1999-06-01
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17309A9961999-06-30030 June 1999 Rev 35 to HP-90, Emergency Equipment. ML17309A9941999-06-17017 June 1999 Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples. ML17241A3541999-06-0101 June 1999 Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status ML17309A9951999-05-27027 May 1999 Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples. ML17241A3451999-05-24024 May 1999 Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks ML17229B0711999-03-19019 March 1999 Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit ML17229B0441999-03-0202 March 1999 Cycle 11 Reactor Startup Physics Testing Rept. with 990304 Ltr ML17229B0201999-02-23023 February 1999 Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution ML17229B0361998-12-22022 December 1998 Rev 20 to Procedure C-200, Odcm. ML17229A9551998-12-16016 December 1998 Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position ML17229A9161998-11-25025 November 1998 Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases ML17229A9251998-11-22022 November 1998 Proposed Tech Specs Revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1 ML17229A9131998-11-19019 November 1998 Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position ML20155C3061998-10-29029 October 1998 Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses ML20153G0781998-08-26026 August 1998 Rev 19 to Plstqp, Guard Training & Qualification Plan ML17229A8441998-08-24024 August 1998 Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal ML17229A7731998-06-15015 June 1998 Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b ML17229A7601998-06-0303 June 1998 Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank ML17229A7441998-05-27027 May 1998 Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures ML17229A7481998-05-27027 May 1998 Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions ML17229A7511998-05-27027 May 1998 Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews ML17229A6751998-03-27027 March 1998 Cycle 15 Reactor Startup Physics & Replacement SG Testing Rept. W/980402 Ltr ML17229A6501998-03-0303 March 1998 Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls ML17229A6381998-02-12012 February 1998 Rev 19 to C-200, Offsite Dose Calculation Manual. ML17229A6151998-01-12012 January 1998 Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan. ML17229A6141998-01-12012 January 1998 Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1. ML17229A5691997-12-31031 December 1997 Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity ML17309A9131997-12-29029 December 1997 Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17229A5851997-12-12012 December 1997 Rev 0 to ADM-29.01, IST Program for Pumps & Valves. ML17229A5491997-12-0101 December 1997 Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion ML17309A9171997-11-26026 November 1997 Rev 0 to PSL-ENG-SENS-97-068, Spent Fuel Pool Dilution Analysis. ML17229A5931997-09-26026 September 1997 Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures. ML17229A5921997-09-18018 September 1997 Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening. ML20211Q5841997-09-10010 September 1997 Rev 18 to Training & Qualification Plan ML17229A4621997-08-22022 August 1997 Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8 ML17229A4341997-08-0101 August 1997 Proposed Tech Specs,Extending semi-annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996 & Associated SE ML17309A8951997-06-11011 June 1997 Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project. ML17229A3601997-05-29029 May 1997 Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases ML17229A2981997-03-0606 March 1997 Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A. ML17229A1831996-12-20020 December 1996 Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings ML17229A1611996-12-0909 December 1996 Proposed Tech Specs 1.9a Re Core Operating Limits Rept ML17229A1191996-10-31031 October 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML17229A1111996-10-30030 October 1996 Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel ML17229A1061996-10-28028 October 1996 Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel ML17229A1091996-10-28028 October 1996 Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17229A0951996-10-24024 October 1996 Rev 0 to 00000-OSW-16, In-Situ Pressure Test Results for St Lucie Unit 1 Spring 1996 Outage. ML17229A0861996-10-18018 October 1996 Startup Physics Testing Rept. W/961018 Ltr ML17229A2441996-09-23023 September 1996 Rev 18 to Offsite Dose Calculation Manual (Odcm). ML17228B5641996-07-15015 July 1996 Revised Tech Specs Re Core Alteration Definition ML17229A0961996-06-12012 June 1996 Rev 0 to TR-9419-CSE96-1101, Test Rept - SG Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination. 1999-06-30
[Table view] |
Text
ATTACHMENT I CHANGES TO TECHNICAL SPECIFICATIONS ST.LUCIE UNIT I DPR-67+5072~0~~pg()p0335,:, i".)q.85O7>~PDR PDOCK.;'PD P e
TABLE 3.3-11 ACCIDENT NON ITORING INSTRUHENTATION n'INSTRUHENT 1.Pressurizer Mater Level 2.Auxiliary Feedwater Flow Rate 3.RCS Subcooling Hargin Honitor 4.PORV Position Indicator Acoustic Flow Honitor 5.PORV Block Valve Position Indicator TOTAL NO.OF CIIANNI:LS
~3 1/pump 1/valve 1/valve HINIHUH ,CIIANNELS 01'LIIABLE 1/pump 1/valve 1/valve ACTION 6.Safety Valve Position Indicator 7.~co~T HERNocGo ply&8.Cou~ai~~aer Su<p~M LC.&(porrou)RA+ge)'R.CDQTFg&pierur Sv~p~M+"c~(~>~Ryan)1/valve 1/val ve.3 q/cora re Weceng.c~c'~~Aeachoc'g~.)
Leva(Meo'hcioq Qe4u QOL77ht OvletJ7 Ppc85u~~~e NOW-mP~@WCe.Co~ieamem Su~P (Qck~g~+t (IMP{7~'Nay Se SoS n7om~DoR<AT<<oF~"~a: A CRadtJEL lS GQfhP~P C4 (8 j K(Qkk SCPScrcS lD.I'~S~>SF 43H>c.H (9)gou~sensa~eooar~&peep,S<a.
TABLE 3.3-I I (Continued)
ACTION STATEMENTS ACTION I-With the number of OPERABLE channels less than required by Table 3.3-I I, either restore the inoperable channel(s) to OPERABLE status within 30 days or be in HOT STANDBY within the next l2 hours.ACTION 2-With position indication inoperable, restore the inoperable indicator to OPERABLE status or close the associated PORV block valve and remove power from its operator within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.ACTION 3-ACTION 4-ACTION 5-With any individual valve position indicator inoperable, obtain quench tank temperature, level and pressure information once per shift to determine valve position.With the number of OPERABLE Channels one less than the Total Number of Channels shown in Table 3.3-I I, either restore the inoperable channel to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the commission pursuant to the specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirements of Table 3.3-I I, either restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without shutting down or: I.Initiate an alternate method of monitoring the reactor vessel inventory; and 2.Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status;and 3.Restore the Channel to OPERABLE status at the next scheduled re fueling.St.Lucie'-Unit I 3/4 3-43 I C m C INSTRUMENT 1.Pressurizer Hater Level 2.Auxiliary Feedwater Flow Rate CkNNNEL CHECK CNANNEL CALIBRATION TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS 3.Reactor Coolant System Subcooling Hargin Monitor.4.PORV Positio'n Indicator 5.PORV Block Valve Position Indicator 6.Safety Valve Postition Indicator 7,+~g~T BQ.~O CAD 0 p IC,g Q, Co a)TAr Q one.~Su mp~~R~Yc.l (V~~e~Pg~qa,')9>>~&~AIL)Mzhtf+~~p 4LkL~P~Y~1 lQ-Re~c&m Y~~t Levzg~oHoci+Sqs&~l~.~~[~+~p~~yvv z.R'
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~~ATTACHMENT 2 CHANGES TO TECHNICAL SPECIFICATIONS ST.LUCIE UNIT 2-NPF-I 6
~~INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.APPLICABILITY:
MODES 1, 2 and 3.ACTION: a.With the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-10, either restore the inoperable channel to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.b.With the number of OPERABLE accident monitoring channels less than'k the Minimum Channels OPERABLE requirements of Table 3.3-10;either Add A<4<o~~restore the inoperable channel(s) to OPERABLE status within 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />s+)or be$n at'least HOT SHUTOOHN within the next 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />..The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.w Ac<a c sw~e,+vs m xov APPL.y'c gepcvotz,'hs~)Le,vc)wioarroa.~gq ay5TanA>QauTAubnae>>T Su~P~asar L<<l (nlnaan~aaua5)aalto e'k CosrTssitssnentr sunup Loa4ar Lowe((sw><<l3ouqa)ltl5T4ulnow'T&
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TD g k 5 With the number of OPERABLE Channels one less than the Total Number of Channels shown in Table 3.3-I I, either restore the inoperable channel to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the commission pursuant to the specification 6.9.2 within 30'days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirements of Table 3.3-I I, either restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without shutting down or: I.Initiate an alternate method of monitoring the reactor vessel inventory; and 2.Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the.cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status;and 3.Restore the Channel to OPERABLE status at the next scheduled refueling.
TABLE 3.3-10 ACCIDENT NHITORIHG IHSTRNENTATIOH I M hi EAR EAI I tO IHSTRNENT REQUIREO HUHOER OF CHANNELS HIHINH CHANNELS OPERABLE l.1'/steaa generator 1/steaa generator]/steaa generator" 1 1 1/valve~*]/valve~e]/yal vere~]*ASS 1 2/core quadrant t,0+4'*~Containaent Pressure.-2 1 2.Reactor Coolant Outlet Teaperature
-THot (Harrow'ange)2 1 3.Reactor.Coolant Inlet Teaperature
-TCold (Mide Range)2 1 4.Reactor Coolant Pressure-Mide Atange.2 S.Pressurizer Mater Level 2 6.Steaa Generator Pressure 2/steaa generator~7.Steaa Generator Mater Level-Harrow Range]/steaa generator 8./team Generator Mater level-Mide Range]/steaa generators S.Refueling Mater Storage Tank Mater Level 2]O.Auxiliary feedwater Flow Rate (Each puap)]/PuePA]].Reactor Cooling System Subcooling Hargin Honitor 2 12.PORV Position/F low Indicator 2/valve*~13.PORV Block Valve Position Indicator]/valve*"]4.Safety Valve Position/Flow Indicator/val ye*RA~]S.'Containment Sump Mater Level (Harrow Range)~]@@*A 16.Containment Mater level (Mide Range)2 D..Incore Theraocouples 4/core quadrant l 3.ReAcvoa Vessel Lc.ve I These corresponding instruaents aay be substituted for each other.""Hot required if.the POAV block valve is shut and power is removed froa the operator.If not available, eonitor the quench tank pressure, level and teeperature, and each safety valve/PORV discharge piping teaperature at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."~"~The non-safety grade containment sump'water level instrument say be substituted.
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I C n M Ill INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION TABLE 4.3-7 ACCIOENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS Cal CQ D~04 24 3.5.6.7.8.9.10.12.13.14.16.16.Containment Pressure=Reactor Coolant Outlet Temperature
-TH t (Narrow Range)Reactor Coolant Inlet Telperature-TC ld (Wide Range)Reactor Coolant Pressure-Wide Range Pressurizer Water Level'.Steam Generator Pressure Steam Generator Water Level-Narrow Range Steam Generator Water Level-,Wide Range Refueling Mater Storage Tank Mater Level Auxiliary Feedwater Flow Rate (Each pump)Reactor Coolant System Subcooling Hargin Honitor PORV Position/Flow Indicator PORV Block Valve Position Indicator Safety Valve Position/FLow Indicator Containment Sump Mater Level (Narrow Range)Containment Mater Level (Mide Range)Incore Thermocouples Q>c'woe)j~ej 4've f 8<<~~>~~<~Sq~zz~H H H H H H H H H H H H H H H H H R R R R R R R R R R R R R R.R R R ATTACHMENT 3 NO S IGNIF I CANT HAZARDS CONSIDERATIONS Introduction The requested amendment to the St.Lucie Units I and 2 operciting licenses adds plant instrumentation currently installed and operational to the Technical Specifications.
This addition will provide a higher degree of control and operational readiness for these instrument channels by requiring operability and monthly surveil lances of accuracy.Evaluation The three criteria for a determination of whether a no significant hazards consideration exists, from IO CFR 50.92(c), are: I)Involve a significant increase in the probability or consequences of an accident previously evaluated, or 2)create the possibility of a new or different kind of accident from any accident previously evaluated; or 3)involve a significant reduction in a margin of safety.A.With respect to the first of the above criteria, the requested license amendment does not increase the probability or.consequences of accidents previously analyzed.The plant hardware and normal operating conditions are not affected by the proposed change since this equipment was previously installed and operating.
Addition of monthly surveil lances on these instrument channels will not involve any significant increase in the probability or consequences of an accident previously evaluated but will assure accurate output from these instrument channels.B.With respect to the second criteria, plant hardware and basic plant operation are not affected by the proposed.license amendment.
Therefore, the possibility for a new or different type of accident is not created.C.With respect to the third criteria, since the consequences of accidents are not increased and new or different types of accidents are not introduced by this amendment, all margins of safety will be maintained.
It is concluded from the above evaluation that this amendment involves no significant hazards considerations.
Furthermore, the proposed amendment is similar to example (I I)of the Commissions examples of amendments that are considered not likely to involve significant hazards considerations in that, it is a change that'onstitutes an additional limitation, restriction or control not presently in the technical specifications.
STATE OF FLORIDA COUNTY OF DADE J.W.Williams Jr.being first duly sworn, deposes and says: That he is a Grou Vice President of Florida Power&Light Company, the Licensee herein;That he has executed the foregoing document;that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.J.W.Williams, Jr.Subscribed and sworn to before me this NOTA'RY PUBLIC, in and for the County'f, Dade, S'tate of Florida My Commission expires:
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