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| {{#Wiki_filter:CATEGORY1REGULATINFORMATION DISTRIBUTION STEM(RIDS)!'CCFSS.'fON NBR:9612270073 DOC.DATE: | | {{#Wiki_filter:CATEGORY 1 REGULAT INFORMATION DISTRIBUTION STEM (RIDS)!'CCFSS.'fON NBR:9612270073 DOC.DATE: 96/12/20 NOTARIZED: |
| 96/12/20NOTARIZED: | | NO k'ACIL:50-335 St.Lucie Plant, Unit 1, Florida Power 6 Light Co.AUTH, NAME AUTHOR AFFILIATION STALL,J.A. |
| NOk'ACIL:50-335 St.LuciePlant,Unit1,FloridaPower6LightCo.AUTH,NAMEAUTHORAFFILIATION STALL,J.A.
| | Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)DOCKET 05000335 |
| FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKET05000335
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendtolicenseDP$-67,requesting deletionoffootnotereTS2.1.1,"ReactorCoreSafetyLimits."CDISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal: | | Application for amend to license DP$-67,requesting deletion of footnote re TS 2.1.1,"Reactor Core Safety Limits." C DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal: |
| GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD2-3LAWIENS,L.INTERNAL:
| | General Distribution NOTES: RECIPIENT ID CODE/NAME PD2-3 LA WIENS,L.INTERNAL: ACRS NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 COPIES RECIPIENT.LTTR ENCL ID CODE/NAME 1 1 PD2-3 PD 1 1 1 1 F1LE CENTER~01 1 1 NRR/DE/EMCB 1 1 NRR/DSSA/SPLB 1 1 NUDOCS-ABSTRACT 1 0 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D NOTE TO ALL"RIDS" RECIPIENTS: |
| ACRSNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3COPIESRECIPIENT
| | PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK/ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL,'.13 C ew't I r,>l C*('I December 20, 1996 Florida Power 8t Light Company, P.O.Box 128, Fort Pierce, FL 34954-0128 L-96-333 10 CFR 50.90 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Re: St.Lucie Unit 1 Docket No.50-335 Proposed License Amendment. |
| .LTTRENCLIDCODE/NAME 11PD2-3PD1111F1LECENTER~01 11NRR/DE/EMCB 11NRR/DSSA/SPLB 11NUDOCS-ABSTRACT 10COPIESLTTRENCL1111111111EXTERNAL: | | Reactor Core Safet Limit Pursuant to 10 CFR 50.90, Florida Power&Light Company (FPL)requests to amend Facility Operating License DPR-67 for St.Lucie Unit 1 by incorporating the attached Technical Specifications (TS)revision.The amendment will delete a footnote associated with TS 2.1.1,"Reactor Core Safety Limits," which requires reactor thermal power to be limited to 90%of 2700 Megawatts thermal for Cycle 14 operation beyond 7000 Effective Full Power Hours.It is requested that the proposed amendment, if approved, be issued prior to May 15, 1997 to permit continued operation of St.Lucie Unit 1 at full power.Attachment 1 is an evaluation of the proposed TS change.Attachment 2 is the"Determination of No Significant Hazards Consideration." Attachment 3 contains a copy of the affected TS page marked-up to show the proposed changes.Enclosed with this submittal is a copy of report EMF-96-176,"St.Lucie Unit 1 Small Break LOCA Analysis with 30%Steam Generator Tube.Plugging," Siemens Power Corporation, Revision 1, December 1996.The proposed amendment has been reviewed by the St.Lucie Facility Review Group and the Florida Power 8.Light Company Nuclear Review Board.In accordance with 10 CFR 50.91 (b)(1), a copy of the proposed amendment is being forwarded to the State Designee for the State of Florida.Please contact us if there are any questions about this submittal. |
| NOAC11NRCPDR11DNOTETOALL"RIDS"RECIPIENTS:
| | Very truly yours, J.A.Stall Vice President St.Lucie Plant JAS/RLD Attachments 9hi2270073 9hi220 PDR, ADQCK 05000335 P PDR POD((Stewart D.Ebnctcr, Regional Administrator, Region II, USNRC.Senior Resident Inspector, USNRC, St.Lucic Plant.Mr.W.A.Passctti, Florida Dcpartmcnt of Health and Rchabilitativc Scrviccs.an FPL Group company 0r<t 4 St.Lucie Unit 1 Docket No.50-335 Proposed License Amendment Reactor Core Safet Limit STATE OF FLORIDA))ss.COUNTY OF ST.LUCIE)J.A.Stall being first duly sworn, deposes and says: That he is Vice President, St.Lucie Plant, for the Nuclear Division of Florida Power Ec 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.A.Stall STATE OF FLORIDA COUNTY OF ST.~uc<<Sworn to and subscribed before me this~~day of DKCFwR8R 19+k by J.A.Stall, who is personally known to me.(''DScA Signature of Notary Public-State of Florida o~pSs~sg~~ii~01%C,hnrtcs'D.>df Name of Notary Public (Print, Type, or Stamgiig (7''sjj8~,ii"'>llillla'l>> |
| PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK/ROOMOWFNSD-5(EXT.
| | t l I 4 I I 1~~'>f e>~'k 4 St.Lucie Unit 1 Docket No.50-335 Proposed License Amendment Reactor Core Safet Limit ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES l I (I j h V 4 L-96-333 Attachment 1 P~ae I EVALUATION OF PROPOSED TS CHANGES Introduction The proposed amendment to Facility Operating License DPR-67 for St.Lucie Unit 1 will delete a footnote associated with Technical Specification (TS)2.1.1,"Reactor Core Safety Limits," which requires thermal power to be limited to less than or equal to 90%of 2700 Megawatts thermal (MWth)for Cycle 14 operation beyond 7000 Effective Full Power Hours (EFPH).The thermal power constraint was imposed in lieu of performing a Small Break Loss of Coolant Accident (SBLOCA)re-analysis for full power operation that demonstrates acceptable results using input assumptions corresponding to 30%(average)of all steam generator tubes plugged (SGTP).That analysis has been completed, and a report of analysis results is enclosed with this submittal. |
| 415-2083) | | Descri tion of Pro osed Chan e TS 2 1 1 Pa e 2-1: Delete the asterisk following"THERMAL POWER," and delete footnote"*" shown at the bottom of page 2-1.A copy of TS Page 2-1, marked-up to show the proposed changes, is contained in Attachment 3.Back round Amendment No.145 to Facility Operating License No.DPR-67 (L.A.Wiens (NRC)to T.F.Plunkett (FPL): ST.LUCIE UNIT 1-ISSUANCE OF AMENDMENT RE: THERIVfAL MARGIN AND REACTOR COOLANT SYSTEM FLOW LIMITS (TAC NO.M95472), July 9, 1996)was issued to permit plant operation with up to 30%(average)SGTP and 345,000 gpm minimum Reactor Coolant System (RCS)flow.In support of this amendment, FPL had determined that conservatism in the existing SBLOCA analysis, which had previously been performed for conditions corresponding to 25%SGTP and 355,000 gpm RCS flow, would offset any adverse effects due to the increased SGTP and decreased reactor coolant system flow for full power operation up to 7000 EFPH.To offset any adverse effects for operation beyond 7000 EFPH, it was determined that limiting core thermal power to 90%of rated thermal power would provide sufficient margin to ensure 10 CFR 50.46 conformity for the remainder of operating Cycle 14.Subsequent to issuance of Amendment No.145, a re-analysis of the SBLOCA has been completed using input assumptions corresponding to 30%(average)SGTP and 345,000 gpm RCS flow.The results of that analysis are briefly discussed in this evaluation, and data is provided in greater detail in the enclosed Siemens Power Corporation-Nuclear Division Report EMF-96-176,"St.Lucie Unit 1 Small Break LOCA Analysis with 30%Steam Generator Tube Plugging," Revision 1, December 1996. |
| TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
| | L-96-333 Attachment 1 P~ee 2 Bases for TS Chan e By Amendment No.145, the NRC approved a license amendment to reduce the RCS flow from 355,000 gpm to 345,000 gpm and the low flow trip setpoint from 95%to 93%of design RCS flow.This amendment supported a SGTP level of 30%+7%, with a requirement to derate to 90%of 2700 MWth prior to exceeding 7000 EFPH of Cycle 14 operation. |
| LTTR14ENCL,'.13 Cew'tIr,>lC*('I December20,1996FloridaPower8tLightCompany,P.O.Box128,FortPierce,FL34954-0128 L-96-33310CFR50.90U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment.
| | The requirement to derate was based on the SBLOCA analysis, which supported a full power operation up to 7000 EFPH and 90%power level beyond 7000 EFPH.Except for the SBLOCA, acceptable results were shown within the applicable safety limits for all the safety and setpoint analyses at 100%power operation at the amended conditions and a SGTP level of 30%+7%.The SBLOCA was evaluated at 100%of rated power up to 7000 EFPH and at 90%power level beyond 7000 EFPH.To support Cycle 14 operation at 2700 MWth to end-of-cycle required a reanalysis of SBLOCA with the limiting end-of-cycle conditions. |
| ReactorCoreSafetLimitPursuantto10CFR50.90,FloridaPower&LightCompany(FPL)requeststoamendFacilityOperating LicenseDPR-67forSt.LucieUnit1byincorporating theattachedTechnical Specifications (TS)revision.
| | The SBLOCA has been reanalyzed to support Cycle 14 operation at 100%power for the entire operating cycle.The analysis, included as the enclosure to this proposed license amendment, demonstrates acceptable results in compliance with 10 CFR 50.46 criteria.The peak cladding temperature (PCT)was calculated to be 1804'F, well below the acceptance criteria of 2200'F.This analysis was performed by Siemens Power Corporation (SPC), using an NRC-approved SBLOCA evaluation model.The reanalysis was done with changes to input assumptions with respect to the loop seal clearing and the location of cold leg injection point.The loop seals in the broken loop and one of the intact loops were biased to remain plugged.In the current analysis of record, the loop seal in the broken loop did not stay plugged.Also the safety injection point was moved a node away from the reactor coolant pump to represent a more realistic configuration. |
| Theamendment willdeleteafootnoteassociated withTS2.1.1,"ReactorCoreSafetyLimits,"whichrequiresreactorthermalpowertobelimitedto90%of2700Megawatts thermalforCycle14operation beyond7000Effective FullPowerHours.Itisrequested thattheproposedamendment, ifapproved, beissuedpriortoMay15,1997topermitcontinued operation ofSt.LucieUnit1atfullpower.Attachment 1isanevaluation oftheproposedTSchange.Attachment 2isthe"Determination ofNoSignificant HazardsConsideration."
| | Overall these changes remove some of the conservatism as compared to the analysis of record for 25%tube plugging level (EMF-92-148,"St.Lucie Unit 1 Small Break LOCA Analysis," Siemens Power Corporation, May 1994).Conclusion The SBLOCA reanalysis, along with the analyses addressed in Amendment No.145, support operation of St.Lucie Unit 1 at 100%of RATED THERMAL POWER for the entire Cycle 14.The proposed change supports the reduced RCS flow of 345,000 gpm corresponding to a SGTP level of 30%+7%approved in Amendment No.145. |
| Attachment 3containsacopyoftheaffectedTSpagemarked-up toshowtheproposedchanges.Enclosedwiththissubmittal isacopyofreportEMF-96-176,"St.LucieUnit1SmallBreakLOCAAnalysiswith30%SteamGenerator Tube.Plugging," | | ATTACHMENT 2 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION L-96-333 Attachment 2 P~ae I DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION Description of amendment request: The proposed amendment will delete a footnote associated with Technical Specification 2.1.1,"Reactor Core Safety Limits," which requires thermal power to be limited to 90%of 2700 Megawatts thermal (MWth)for Cycle 14 operation beyond 7000 Effective Full Power Hours.Pursuant to 10 CFR 50.92, a determination may be made that a proposed license amendment involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not: (1)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.Each standard is discussed as follows: (1)Operation of the facility in accordance with the proposed amendment would not involve a signiTicant increase in the probability or consequences of an accident previously evaluated. |
| SiemensPowerCorporation, Revision1,December1996.Theproposedamendment hasbeenreviewedbytheSt.LucieFacilityReviewGroupandtheFloridaPower8.LightCompanyNuclearReviewBoard.Inaccordance with10CFR50.91(b)(1),acopyoftheproposedamendment isbeingforwarded totheStateDesigneefortheStateofFlorida.Pleasecontactusifthereareanyquestions aboutthissubmittal.
| | The proposed change will allow full Cycle 14 operation at 100%of rated power (2700 MWth), by deleting the requirement to derate to 90%of rated power prior to exceeding 7000 EFPH.This restriction was imposed in the NRC transmittal letter for License Amendment 145 for SBLOCA considerations when considering the increased SGTP level of 30%+7%.All Final Safety Analysis Report (FSAR)events, other than SBLOCA were evaluated at 100%of rated thermal power and showed no significant increases in the probability or consequences of accidents previously evaluated. |
| Verytrulyyours,J.A.StallVicePresident St.LuciePlantJAS/RLDAttachments 9hi2270073 9hi220PDR,ADQCK05000335PPDRPOD((StewartD.Ebnctcr,RegionalAdministrator, RegionII,USNRC.SeniorResidentInspector, USNRC,St.LucicPlant.Mr.W.A.Passctti, FloridaDcpartmcnt ofHealthandRchabilitativc Scrviccs.
| | The SBLOCA was reanalyzed to demonstrate continued compliance with 10 CFR 50.46 criteria.There is no impact of the proposed change on any FSAR accident initiator. |
| anFPLGroupcompany 0r<t4 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment ReactorCoreSafetLimitSTATEOFFLORIDA))ss.COUNTYOFST.LUCIE)J.A.Stallbeingfirstdulysworn,deposesandsays:ThatheisVicePresident, St.LuciePlant,fortheNuclearDivisionofFloridaPowerEcLightCompany,theLicenseeherein;Thathehasexecutedtheforegoing document; thatthestatements madeinthisdocumentaretrueandcorrecttothebestofhisknowledge, information andbelief,andthatheisauthorized toexecutethedocumentonbehalfofsaidLicensee.
| | The plant configuration and systems remain unchanged. |
| J.A.StallSTATEOFFLORIDACOUNTYOFST.~uc<<Sworntoandsubscribed beforemethis~~dayofDKCFwR8R19+kbyJ.A.Stall,whoispersonally knowntome.(''DScASignature ofNotaryPublic-State ofFloridao~pSs~sg~~ii~01%C,hnrtcs'D.>dfNameofNotaryPublic(Print,Type,orStamgiig(7''sjj8~,ii"'>llillla'l>> | | Therefore, operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated. |
| tlI4II1~~'>fe>~'k4 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment ReactorCoreSafetLimitATTACHMENT 1EVALUATION OFPROPOSEDCHANGES lI(IjhV4 L-96-333Attachment 1P~aeIEVALUATION OFPROPOSEDTSCHANGESIntroduction Theproposedamendment toFacilityOperating LicenseDPR-67forSt.LucieUnit1willdeleteafootnoteassociated withTechnical Specification (TS)2.1.1,"Reactor CoreSafetyLimits,"whichrequiresthermalpowertobelimitedtolessthanorequalto90%of2700Megawatts thermal(MWth)forCycle14operation beyond7000Effective FullPowerHours(EFPH).Thethermalpowerconstraint wasimposedinlieuofperforming aSmallBreakLossofCoolantAccident(SBLOCA)re-analysis forfullpoweroperation thatdemonstrates acceptable resultsusinginputassumptions corresponding to30%(average) ofallsteamgenerator tubesplugged(SGTP).Thatanalysishasbeencompleted, andareportofanalysisresultsisenclosedwiththissubmittal.
| | (2)Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated. |
| DescritionofProosedChaneTS211Pae2-1:Deletetheasteriskfollowing "THERMALPOWER,"anddeletefootnote"*"shownatthebottomofpage2-1.AcopyofTSPage2-1,marked-up toshowtheproposedchanges,iscontained inAttachment 3.BackroundAmendment No.145toFacilityOperating LicenseNo.DPR-67(L.A.Wiens(NRC)toT.F.Plunkett(FPL):ST.LUCIEUNIT1-ISSUANCEOFAMENDMENT RE:THERIVfAL MARGINANDREACTORCOOLANTSYSTEMFLOWLIMITS(TACNO.M95472),July9,1996)wasissuedtopermitplantoperation withupto30%(average)
| | This proposed amendment removes the requirement in the Technical Specifications to derate to 90%of 2700 MWth for Cycle 14 operation beyond 7000 EFPH.There will be L-96-333 Attachment 2 P~ae 2 no change to the modes of operation of the plant.The plant configuration and the design functions of all the safety systems remain unchanged. |
| SGTPand345,000gpmminimumReactorCoolantSystem(RCS)flow.Insupportofthisamendment, FPLhaddetermined thatconservatism intheexistingSBLOCAanalysis, whichhadpreviously beenperformed forconditions corresponding to25%SGTPand355,000gpmRCSflow,wouldoffsetanyadverseeffectsduetotheincreased SGTPanddecreased reactorcoolantsystemflowforfullpoweroperation upto7000EFPH.Tooffsetanyadverseeffectsforoperation beyond7000EFPH,itwasdetermined thatlimitingcorethermalpowerto90%ofratedthermalpowerwouldprovidesufficient margintoensure10CFR50.46conformity fortheremainder ofoperating Cycle14.Subsequent toissuanceofAmendment No.145,are-analysis oftheSBLOCAhasbeencompleted usinginputassumptions corresponding to30%(average)
| | The proposed amendment will not change the physical plant or the modes of operation defined in the facility license.The changes do not involve the addition of new equipment or the modification of existing equipment, nor do they alter the design of St.Lucie plant systems.Therefore, operation of the facility in accordance with the proposed amendment would not create the possibility of a new or difFerent kind of accident from any accident previously evaluated. |
| SGTPand345,000gpmRCSflow.Theresultsofthatanalysisarebrieflydiscussed inthisevaluation, anddataisprovidedingreaterdetailintheenclosedSiemensPowerCorporation-Nuclear DivisionReportEMF-96-176, "St.LucieUnit1SmallBreakLOCAAnalysiswith30%SteamGenerator TubePlugging,"
| | (3)Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.The impact of the proposed change on'available margin to the acceptance criteria for Specified Acceptable Fuel Design Limits (SAFDL), primary and secondary over-pressurization, peak containment pressure, potential radioactive releases, 10 CFR 50.46 requirements for the large break LOCA, and existing limiting conditions for operation has been evaluated and addressed in the reduced RCS flow operating license Amendment No.145.A requirement to derate to 90%of 2700 MWth was imposed based on the SBLOCA analysis.The small break LOCA analysis with 30%+7%SGTP supported operation up to 7000 EFPH at 100%of-rated thermal power.A reanalysis of SBLOCA with the limiting end-of-cycle conditions at 100%of rated power, demonstrates continued compliance with 10 CFR 50.46 criteria.Therefore, operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.Based on the discussion presented above and on the supporting Evaluation of Proposed TS~Changes, FPL has concluded that this proposed license amendment involves no significant hazards consideration.}} |
| Revision1,December1996.
| |
| L-96-333Attachment 1P~ee2BasesforTSChaneByAmendment No.145,theNRCapprovedalicenseamendment toreducetheRCSflowfrom355,000gpmto345,000gpmandthelowflowtripsetpointfrom95%to93%ofdesignRCSflow.Thisamendment supported aSGTPlevelof30%+7%,witharequirement toderateto90%of2700MWthpriortoexceeding 7000EFPHofCycle14operation. | |
| Therequirement toderatewasbasedontheSBLOCAanalysis, whichsupported afullpoweroperation upto7000EFPHand90%powerlevelbeyond7000EFPH.ExceptfortheSBLOCA,acceptable resultswereshownwithintheapplicable safetylimitsforallthesafetyandsetpointanalysesat100%poweroperation attheamendedconditions andaSGTPlevelof30%+7%.TheSBLOCAwasevaluated at100%ofratedpowerupto7000EFPHandat90%powerlevelbeyond7000EFPH.TosupportCycle14operation at2700MWthtoend-of-cyclerequiredareanalysis ofSBLOCAwiththelimitingend-of-cycle conditions.
| |
| TheSBLOCAhasbeenreanalyzed tosupportCycle14operation at100%powerfortheentireoperating cycle.Theanalysis, includedastheenclosure tothisproposedlicenseamendment, demonstrates acceptable resultsincompliance with10CFR50.46criteria.
| |
| Thepeakcladdingtemperature (PCT)wascalculated tobe1804'F,wellbelowtheacceptance criteriaof2200'F.Thisanalysiswasperformed bySiemensPowerCorporation (SPC),usinganNRC-approved SBLOCAevaluation model.Thereanalysis wasdonewithchangestoinputassumptions withrespecttotheloopsealclearingandthelocationofcoldleginjection point.Theloopsealsinthebrokenloopandoneoftheintactloopswerebiasedtoremainplugged.Inthecurrentanalysisofrecord,theloopsealinthebrokenloopdidnotstayplugged.Alsothesafetyinjection pointwasmovedanodeawayfromthereactorcoolantpumptorepresent amorerealistic configuration.
| |
| Overallthesechangesremovesomeoftheconservatism ascomparedtotheanalysisofrecordfor25%tubeplugginglevel(EMF-92-148, "St.LucieUnit1SmallBreakLOCAAnalysis,"
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| SiemensPowerCorporation, May1994).Conclusion TheSBLOCAreanalysis, alongwiththeanalysesaddressed inAmendment No.145,supportoperation ofSt.LucieUnit1at100%ofRATEDTHERMALPOWERfortheentireCycle14.TheproposedchangesupportsthereducedRCSflowof345,000gpmcorresponding toaSGTPlevelof30%+7%approvedinAmendment No.145.
| |
| ATTACHMENT 2DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION L-96-333Attachment 2P~aeIDETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION Description ofamendment request:Theproposedamendment willdeleteafootnoteassociated withTechnical Specification 2.1.1,"Reactor CoreSafetyLimits,"whichrequiresthermalpowertobelimitedto90%of2700Megawatts thermal(MWth)forCycle14operation beyond7000Effective FullPowerHours.Pursuantto10CFR50.92,adetermination maybemadethataproposedlicenseamendment involvesnosignificant hazardsconsideration ifoperation ofthefacilityinaccordance withtheproposedamendment wouldnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or(2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated; or(3)involveasignificant reduction inamarginofsafety.Eachstandardisdiscussed asfollows:(1)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasigniTicant increaseintheprobability orconsequences ofanaccidentpreviously evaluated. | |
| TheproposedchangewillallowfullCycle14operation at100%ofratedpower(2700MWth),bydeletingtherequirement toderateto90%ofratedpowerpriortoexceeding 7000EFPH.Thisrestriction wasimposedintheNRCtransmittal letterforLicenseAmendment 145forSBLOCAconsiderations whenconsidering theincreased SGTPlevelof30%+7%.AllFinalSafetyAnalysisReport(FSAR)events,otherthanSBLOCAwereevaluated at100%ofratedthermalpowerandshowednosignificant increases intheprobability orconsequences ofaccidents previously evaluated.
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| TheSBLOCAwasreanalyzed todemonstrate continued compliance with10CFR50.46criteria.
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| ThereisnoimpactoftheproposedchangeonanyFSARaccidentinitiator.
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| Theplantconfiguration andsystemsremainunchanged.
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| Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated. | |
| (2)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated. | |
| Thisproposedamendment removestherequirement intheTechnical Specifications toderateto90%of2700MWthforCycle14operation beyond7000EFPH.Therewillbe L-96-333Attachment 2P~ae2nochangetothemodesofoperation oftheplant.Theplantconfiguration andthedesignfunctions ofallthesafetysystemsremainunchanged.
| |
| Theproposedamendment willnotchangethephysicalplantorthemodesofoperation definedinthefacilitylicense.Thechangesdonotinvolvetheadditionofnewequipment orthemodification ofexistingequipment, nordotheyalterthedesignofSt.Lucieplantsystems.Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifFerent kindofaccidentfromanyaccidentpreviously evaluated.
| |
| (3)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Theimpactoftheproposedchangeon'available margintotheacceptance criteriaforSpecified Acceptable FuelDesignLimits(SAFDL),primaryandsecondary over-pressurization, peakcontainment | |
| : pressure, potential radioactive
| |
| : releases, 10CFR50.46requirements forthelargebreakLOCA,andexistinglimitingconditions foroperation hasbeenevaluated andaddressed inthereducedRCSflowoperating licenseAmendment No.145.Arequirement toderateto90%of2700MWthwasimposedbasedontheSBLOCAanalysis.
| |
| ThesmallbreakLOCAanalysiswith30%+7%SGTPsupported operation upto7000EFPHat100%of-ratedthermalpower.Areanalysis ofSBLOCAwiththelimitingend-of-cycle conditions at100%ofratedpower,demonstrates continued compliance with10CFR50.46criteria.
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| Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Basedonthediscussion presented aboveandonthesupporting Evaluation ofProposedTS~Changes,FPLhasconcluded thatthisproposedlicenseamendment involvesnosignificant hazardsconsideration.}} | |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17241A4441999-08-18018 August 1999 Application for Amend to License NPF-16,to Change Required Surveillance Frequency for Cycling Steam Valves in Turbine Overspeed Protection Sys from Once Per Month to Once Per Quarter (92 Days).Proprietary Encls Withheld ML17241A3521999-06-0101 June 1999 Application for Amends to Licenses DPR-67 & NPF-16,revising TS 3.5.2 to Allow Up to 7 Days to Restore Inoperable LPSI Train to Operable Status ML17241A3431999-05-24024 May 1999 Application for Amend to License NPF-16,revising Unit 2 TS 3/4.5.1, Safety Injection Tanks, by Clarifying Nonconservative Wording of Surveillance 4.5.1.1.d.1 to Align Surveillance with Intent & Design Bases Requirements ML17229B0181999-02-23023 February 1999 Application for Amend to License NPF-16,removing Redundant Concentration Monitoring Requirements Specified for Modes 3 Through 6 by Deleting TS 3/4.1.2.9, Reactivity Control Sys- Boron Dilution. ML17229A9541998-12-16016 December 1998 Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position ML17229A9221998-11-22022 November 1998 Application for Amend to License DPR-67,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 ML17229A9111998-11-19019 November 1998 Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position ML17229A8421998-08-24024 August 1998 Application for Amends to Licenses DPR-67 & NPF-16,removing Obsolete License Conditions & Incorporating Attached TS Revs ML17229A7581998-06-0303 June 1998 Application for Amends to Licenses DPR-67 & NPF-16 to Incorporate Attached TS Revs.Proposed Amends Are Administrative in Nature & Will Modify Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 ML17229A7461998-05-27027 May 1998 Application for Amend to License NPF-16,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions ML17229A7491998-05-27027 May 1998 Application for Amends to Licenses DPR-67 & NPF-16,revising TS 6.2.2.f to Allow Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews ML17229A7421998-05-27027 May 1998 Supplemental Application to 961031 Proposed Amend to Licenses DPR-67 & NPF-16,providing for More Efficient Use of on-site Mgt Personnel in Review & Approval Process for Plant Procedures ML17229A6481998-03-0303 March 1998 Application for Amend to License NPF-16,revising Applicability of TS 3.4.7 Re RCS Chemistry,Consistent W/ Corresponding Specification for Unit 1 ML17309A9161997-12-31031 December 1997 Application for Amend to License NPF-16 by Incorporating Attached TS Rev.Amend Will Modify TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity ML17309A9111997-12-29029 December 1997 Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17229A5471997-12-0101 December 1997 Application for Amends to Licenses DPR-67 & NPF-16,revising EPP Section 4, Environ Conditions & Section 5, Administrative Procedures, to Incorporate Proposed Terms & Conditions of Incidental Take Statement ML17229A4601997-08-22022 August 1997 Application for Amends to Licenses DPR-67 & NPF-16,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 Controls Section ML17229A4321997-08-0101 August 1997 Application for Amend to License NPF-16,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 ML17229A4211997-07-22022 July 1997 Application for Amend to License DPR-67,incorporating Recent Evaluation of Postulated Inadvertent Opening of MSSV Into Current Licensing Basis ML17229A3581997-05-29029 May 1997 Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Administrative Changes That Will Improve Consistency Throughout TSs & Related Bases ML17229A1811996-12-20020 December 1996 Application for Amend to License DPR-67,requesting Deletion of Footnote Re TS 2.1.1, Reactor Core Safety Limits. ML17229A1591996-12-0909 December 1996 Application for Amend to License DPR-67,requesting Mod for Selected cycle-specific Reactor Physics Parameters to Refer to COLR for Limiting Values ML17229A1171996-10-31031 October 1996 Application for Amends to Licenses DPR-67 & NPF-16, Requesting Revisions to 6.5.1 Re Facility Review Group & 6.8 Re Procedures & Programs ML17339A0431996-10-30030 October 1996 Application for Amends to Licenses DPR-67 & NPF-16, Requesting to Revise TS 3/4.9.9 Re Refueling Requirements & TS 3/4.9.10 Re Refueling Operations,Water level-reactor Vessel ML17229A1071996-10-28028 October 1996 Application for Amend to License NPF-16,modifying TS to Implement 10CFR50,App J,Option B,To Revise TS to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17229A1041996-10-28028 October 1996 Application for Amend to License DPR-67,requesting to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17228B5621996-07-15015 July 1996 Application for Amends to Licenses DPR-67 & NPF-16 Revising Core Alteration Definition ML17228B5021996-06-0101 June 1996 Application for Exigent Amend to License DPR-67,revising TS Re Thermal Margin & RCS Flow Limits.Siemens Power Corp Rept EMF-96-135, St Lucie Unit 1 Chapter 15 Event Review & Analysis for 30% SG Tube Plugging Encl ML17228B3741996-01-0404 January 1996 Application for Amends to Licenses DPR-67 & NPF-16 Revising TS 3.5.3 to Rectify Discrepancy for Each St Lucie Unit & to Provide Assurance That Admin Controls for Hpsip Remain Effective in Lower Operational Modes ML17228B3341995-11-22022 November 1995 Application for Amends to Licenses DPR-67 & NPF-16,amending TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation by Adapting STS for C-E Plants (NUREG-1432),Spec 3.4.15 for Facilities ML17228B2861995-10-0505 October 1995 Application for Amends to Licenses DPR-67 & NPF-16,removing SR Re Dune & Mangrove Surveys from TS ML17228B2401995-08-16016 August 1995 Application for Amends to Licenses DPR-67 & NPF-16, Relocating Selected TS Requirements Re Instrumentation,Per Final Policy Statement on TS Improvements & Relocating TS Re Emergency & Security Plan Review Process Per GL 93-07 ML17228B2431995-08-16016 August 1995 Application for Amend to License NPF-16,modifying Spec 3.6.6.1, Sbvs to More Effectively Address Design Functions Performed by Sbvs for Shield Bldg & Fuel Handling Bldg,Per NUREG-1432 ML17228B1871995-06-21021 June 1995 Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Revise Action Statements & Certain Surveillances of TS 3/4.5.1 Re Safety Injection Tanks ML17228B1771995-06-21021 June 1995 Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Extend Allowed Outage Time for Inoperable EDGs ML17309A7921995-06-21021 June 1995 Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Allow Up to Seven Days to Restore an Inoperable LPSI Train to Operable Status ML17228B1451995-05-17017 May 1995 Application for Amend to License DPR-67,extending Applicability of Current RCS Pressure/Temp Limits & Maximum Allowed RCS Heatup & Cooldown Rates to 23.6 Effective Full Power Yrs of Operation ML17228B1421995-05-17017 May 1995 Application for Amends to Licenses DPR-67 & NPF-16 Re Administrative & Conforming Update ML17228B0881995-04-0303 April 1995 Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Incorporate line-item TS Improvements to TSs 3/4.8.1 & 4.8.1.2.2 ML17228B0571995-02-27027 February 1995 Application for Amend to License NPF-16,modifying Surveillance Requirement 4.9.8.1 & 4.9.8.2 to Allow Reduction in Required Min Shutdown Cooling Flow Rate Under Certain Conditions During Operational Mode 6 ML17228B0501995-02-27027 February 1995 Application for Amend to License NPF-16,revising TS Tables 3.3-3 & 3.3-4 to Accommodate Improved Coincidence Logic & Relay Replacement for 4.16 Kv Loss of Voltage Relay ML17228B0311995-02-22022 February 1995 Application for Amends to Licenses DPR-67 & NPF-16,deleting Refs to Automatic Tester for Containment Personnel Air Lock from TS 4.6.1.3 ML17228A9901995-01-20020 January 1995 Application for Amends to Licenses DPR-67 & NPF-16, Relocating Operability Requirements for Incore Detectors (TS 3/4.3.3.2) to Updated FSAR & Revising Lhr Surveillance 4.2.1.4 & Special Test Exceptions Surveillances ML17352B0001995-01-17017 January 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.9.1.7, COLR, Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters.Fpl Topical Rept NF-TR-95-01, Nuclear Physics Methodology... Encl ML17228A9011994-11-0202 November 1994 Application for Amends to Licenses DPR-67 & NPF-16,upgrading TS 3/4.6.2.1 & 3/4.6.2.3 by Adapting Combined Spec for Containment Spray & Cooling Sys Contained in Std TS for C-E Plants ML17309A7511994-10-27027 October 1994 Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Encl Administrative Changes ML17228A6501994-07-28028 July 1994 Application for Amends to Licenses DPR-67,revising TS 3/4.4.13 to Incorporate LTOP Requirements Similar to LTOP Requirements Recommended by NRC Via GL 90-06,in Accordance W/Resolution of Generic Issue 94 ML17228A6571994-07-25025 July 1994 Application for Amends to Licenses DPR-67 & NPF-16,revising Ts,Implementing Enhancements Recommended by GL 93-05 Re line-item TS Improvements to Reduce SR for Testing During Power Operation. ML17228A6541994-07-25025 July 1994 Application for Amend to License NPF-16,proposing TS Upgrading TS 3/4.7.1.6 for Main Feedwater Line Isolation Valves to Be Consistent w/NUREG-1432,standard TS for C-E Plants ML17228A5751994-05-23023 May 1994 Application for Amend to License DPR-67,revising TS 3.5.2 for ECCS by Removing Option That Allows HPSI Pump 1C to Be Used as Alternative to Preferred Pump for Subsystem Operability 1999-08-18
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17241A4441999-08-18018 August 1999 Application for Amend to License NPF-16,to Change Required Surveillance Frequency for Cycling Steam Valves in Turbine Overspeed Protection Sys from Once Per Month to Once Per Quarter (92 Days).Proprietary Encls Withheld ML17241A3521999-06-0101 June 1999 Application for Amends to Licenses DPR-67 & NPF-16,revising TS 3.5.2 to Allow Up to 7 Days to Restore Inoperable LPSI Train to Operable Status ML17241A3431999-05-24024 May 1999 Application for Amend to License NPF-16,revising Unit 2 TS 3/4.5.1, Safety Injection Tanks, by Clarifying Nonconservative Wording of Surveillance 4.5.1.1.d.1 to Align Surveillance with Intent & Design Bases Requirements ML17229B0181999-02-23023 February 1999 Application for Amend to License NPF-16,removing Redundant Concentration Monitoring Requirements Specified for Modes 3 Through 6 by Deleting TS 3/4.1.2.9, Reactivity Control Sys- Boron Dilution. ML17229A9541998-12-16016 December 1998 Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position ML17229A9221998-11-22022 November 1998 Application for Amend to License DPR-67,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 ML17229A9111998-11-19019 November 1998 Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position ML17229A8421998-08-24024 August 1998 Application for Amends to Licenses DPR-67 & NPF-16,removing Obsolete License Conditions & Incorporating Attached TS Revs ML17229A7581998-06-0303 June 1998 Application for Amends to Licenses DPR-67 & NPF-16 to Incorporate Attached TS Revs.Proposed Amends Are Administrative in Nature & Will Modify Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 ML17229A7461998-05-27027 May 1998 Application for Amend to License NPF-16,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions ML17229A7491998-05-27027 May 1998 Application for Amends to Licenses DPR-67 & NPF-16,revising TS 6.2.2.f to Allow Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews ML17229A7421998-05-27027 May 1998 Supplemental Application to 961031 Proposed Amend to Licenses DPR-67 & NPF-16,providing for More Efficient Use of on-site Mgt Personnel in Review & Approval Process for Plant Procedures ML17229A6481998-03-0303 March 1998 Application for Amend to License NPF-16,revising Applicability of TS 3.4.7 Re RCS Chemistry,Consistent W/ Corresponding Specification for Unit 1 ML17309A9161997-12-31031 December 1997 Application for Amend to License NPF-16 by Incorporating Attached TS Rev.Amend Will Modify TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity ML17309A9111997-12-29029 December 1997 Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17229A5471997-12-0101 December 1997 Application for Amends to Licenses DPR-67 & NPF-16,revising EPP Section 4, Environ Conditions & Section 5, Administrative Procedures, to Incorporate Proposed Terms & Conditions of Incidental Take Statement ML17229A4601997-08-22022 August 1997 Application for Amends to Licenses DPR-67 & NPF-16,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 Controls Section ML17229A4321997-08-0101 August 1997 Application for Amend to License NPF-16,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 ML17229A4211997-07-22022 July 1997 Application for Amend to License DPR-67,incorporating Recent Evaluation of Postulated Inadvertent Opening of MSSV Into Current Licensing Basis ML17229A3581997-05-29029 May 1997 Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Administrative Changes That Will Improve Consistency Throughout TSs & Related Bases ML17229A1811996-12-20020 December 1996 Application for Amend to License DPR-67,requesting Deletion of Footnote Re TS 2.1.1, Reactor Core Safety Limits. ML17229A1591996-12-0909 December 1996 Application for Amend to License DPR-67,requesting Mod for Selected cycle-specific Reactor Physics Parameters to Refer to COLR for Limiting Values ML17229A1171996-10-31031 October 1996 Application for Amends to Licenses DPR-67 & NPF-16, Requesting Revisions to 6.5.1 Re Facility Review Group & 6.8 Re Procedures & Programs ML17339A0431996-10-30030 October 1996 Application for Amends to Licenses DPR-67 & NPF-16, Requesting to Revise TS 3/4.9.9 Re Refueling Requirements & TS 3/4.9.10 Re Refueling Operations,Water level-reactor Vessel ML17229A1071996-10-28028 October 1996 Application for Amend to License NPF-16,modifying TS to Implement 10CFR50,App J,Option B,To Revise TS to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17229A1041996-10-28028 October 1996 Application for Amend to License DPR-67,requesting to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17228B5621996-07-15015 July 1996 Application for Amends to Licenses DPR-67 & NPF-16 Revising Core Alteration Definition ML17228B5021996-06-0101 June 1996 Application for Exigent Amend to License DPR-67,revising TS Re Thermal Margin & RCS Flow Limits.Siemens Power Corp Rept EMF-96-135, St Lucie Unit 1 Chapter 15 Event Review & Analysis for 30% SG Tube Plugging Encl ML17228B3741996-01-0404 January 1996 Application for Amends to Licenses DPR-67 & NPF-16 Revising TS 3.5.3 to Rectify Discrepancy for Each St Lucie Unit & to Provide Assurance That Admin Controls for Hpsip Remain Effective in Lower Operational Modes ML17228B3341995-11-22022 November 1995 Application for Amends to Licenses DPR-67 & NPF-16,amending TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation by Adapting STS for C-E Plants (NUREG-1432),Spec 3.4.15 for Facilities ML17228B2861995-10-0505 October 1995 Application for Amends to Licenses DPR-67 & NPF-16,removing SR Re Dune & Mangrove Surveys from TS ML17228B2401995-08-16016 August 1995 Application for Amends to Licenses DPR-67 & NPF-16, Relocating Selected TS Requirements Re Instrumentation,Per Final Policy Statement on TS Improvements & Relocating TS Re Emergency & Security Plan Review Process Per GL 93-07 ML17228B2431995-08-16016 August 1995 Application for Amend to License NPF-16,modifying Spec 3.6.6.1, Sbvs to More Effectively Address Design Functions Performed by Sbvs for Shield Bldg & Fuel Handling Bldg,Per NUREG-1432 ML17228B1871995-06-21021 June 1995 Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Revise Action Statements & Certain Surveillances of TS 3/4.5.1 Re Safety Injection Tanks ML17228B1771995-06-21021 June 1995 Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Extend Allowed Outage Time for Inoperable EDGs ML17309A7921995-06-21021 June 1995 Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Allow Up to Seven Days to Restore an Inoperable LPSI Train to Operable Status ML17228B1451995-05-17017 May 1995 Application for Amend to License DPR-67,extending Applicability of Current RCS Pressure/Temp Limits & Maximum Allowed RCS Heatup & Cooldown Rates to 23.6 Effective Full Power Yrs of Operation ML17228B1421995-05-17017 May 1995 Application for Amends to Licenses DPR-67 & NPF-16 Re Administrative & Conforming Update ML17228B0881995-04-0303 April 1995 Application for Amends to Licenses DPR-67 & NPF-16.Amends Would Incorporate line-item TS Improvements to TSs 3/4.8.1 & 4.8.1.2.2 ML17228B0571995-02-27027 February 1995 Application for Amend to License NPF-16,modifying Surveillance Requirement 4.9.8.1 & 4.9.8.2 to Allow Reduction in Required Min Shutdown Cooling Flow Rate Under Certain Conditions During Operational Mode 6 ML17228B0501995-02-27027 February 1995 Application for Amend to License NPF-16,revising TS Tables 3.3-3 & 3.3-4 to Accommodate Improved Coincidence Logic & Relay Replacement for 4.16 Kv Loss of Voltage Relay ML17228B0311995-02-22022 February 1995 Application for Amends to Licenses DPR-67 & NPF-16,deleting Refs to Automatic Tester for Containment Personnel Air Lock from TS 4.6.1.3 ML17228A9901995-01-20020 January 1995 Application for Amends to Licenses DPR-67 & NPF-16, Relocating Operability Requirements for Incore Detectors (TS 3/4.3.3.2) to Updated FSAR & Revising Lhr Surveillance 4.2.1.4 & Special Test Exceptions Surveillances ML17352B0001995-01-17017 January 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.9.1.7, COLR, Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters.Fpl Topical Rept NF-TR-95-01, Nuclear Physics Methodology... Encl ML17228A9011994-11-0202 November 1994 Application for Amends to Licenses DPR-67 & NPF-16,upgrading TS 3/4.6.2.1 & 3/4.6.2.3 by Adapting Combined Spec for Containment Spray & Cooling Sys Contained in Std TS for C-E Plants ML17309A7511994-10-27027 October 1994 Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Encl Administrative Changes ML17228A6501994-07-28028 July 1994 Application for Amends to Licenses DPR-67,revising TS 3/4.4.13 to Incorporate LTOP Requirements Similar to LTOP Requirements Recommended by NRC Via GL 90-06,in Accordance W/Resolution of Generic Issue 94 ML17228A6571994-07-25025 July 1994 Application for Amends to Licenses DPR-67 & NPF-16,revising Ts,Implementing Enhancements Recommended by GL 93-05 Re line-item TS Improvements to Reduce SR for Testing During Power Operation. ML17228A6541994-07-25025 July 1994 Application for Amend to License NPF-16,proposing TS Upgrading TS 3/4.7.1.6 for Main Feedwater Line Isolation Valves to Be Consistent w/NUREG-1432,standard TS for C-E Plants ML17228A5751994-05-23023 May 1994 Application for Amend to License DPR-67,revising TS 3.5.2 for ECCS by Removing Option That Allows HPSI Pump 1C to Be Used as Alternative to Preferred Pump for Subsystem Operability 1999-08-18
[Table view] |
Text
CATEGORY 1 REGULAT INFORMATION DISTRIBUTION STEM (RIDS)!'CCFSS.'fON NBR:9612270073 DOC.DATE: 96/12/20 NOTARIZED:
NO k'ACIL:50-335 St.Lucie Plant, Unit 1, Florida Power 6 Light Co.AUTH, NAME AUTHOR AFFILIATION STALL,J.A.
Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)DOCKET 05000335
SUBJECT:
Application for amend to license DP$-67,requesting deletion of footnote re TS 2.1.1,"Reactor Core Safety Limits." C DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:
General Distribution NOTES: RECIPIENT ID CODE/NAME PD2-3 LA WIENS,L.INTERNAL: ACRS NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 COPIES RECIPIENT.LTTR ENCL ID CODE/NAME 1 1 PD2-3 PD 1 1 1 1 F1LE CENTER~01 1 1 NRR/DE/EMCB 1 1 NRR/DSSA/SPLB 1 1 NUDOCS-ABSTRACT 1 0 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK/ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL,'.13 C ew't I r,>l C*('I December 20, 1996 Florida Power 8t Light Company, P.O.Box 128, Fort Pierce, FL 34954-0128 L-96-333 10 CFR 50.90 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Re: St.Lucie Unit 1 Docket No.50-335 Proposed License Amendment.
Reactor Core Safet Limit Pursuant to 10 CFR 50.90, Florida Power&Light Company (FPL)requests to amend Facility Operating License DPR-67 for St.Lucie Unit 1 by incorporating the attached Technical Specifications (TS)revision.The amendment will delete a footnote associated with TS 2.1.1,"Reactor Core Safety Limits," which requires reactor thermal power to be limited to 90%of 2700 Megawatts thermal for Cycle 14 operation beyond 7000 Effective Full Power Hours.It is requested that the proposed amendment, if approved, be issued prior to May 15, 1997 to permit continued operation of St.Lucie Unit 1 at full power.Attachment 1 is an evaluation of the proposed TS change.Attachment 2 is the"Determination of No Significant Hazards Consideration." Attachment 3 contains a copy of the affected TS page marked-up to show the proposed changes.Enclosed with this submittal is a copy of report EMF-96-176,"St.Lucie Unit 1 Small Break LOCA Analysis with 30%Steam Generator Tube.Plugging," Siemens Power Corporation, Revision 1, December 1996.The proposed amendment has been reviewed by the St.Lucie Facility Review Group and the Florida Power 8.Light Company Nuclear Review Board.In accordance with 10 CFR 50.91 (b)(1), a copy of the proposed amendment is being forwarded to the State Designee for the State of Florida.Please contact us if there are any questions about this submittal.
Very truly yours, J.A.Stall Vice President St.Lucie Plant JAS/RLD Attachments 9hi2270073 9hi220 PDR, ADQCK 05000335 P PDR POD((Stewart D.Ebnctcr, Regional Administrator, Region II, USNRC.Senior Resident Inspector, USNRC, St.Lucic Plant.Mr.W.A.Passctti, Florida Dcpartmcnt of Health and Rchabilitativc Scrviccs.an FPL Group company 0r<t 4 St.Lucie Unit 1 Docket No.50-335 Proposed License Amendment Reactor Core Safet Limit STATE OF FLORIDA))ss.COUNTY OF ST.LUCIE)J.A.Stall being first duly sworn, deposes and says: That he is Vice President, St.Lucie Plant, for the Nuclear Division of Florida Power Ec 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.A.Stall STATE OF FLORIDA COUNTY OF ST.~uc<<Sworn to and subscribed before me this~~day of DKCFwR8R 19+k by J.A.Stall, who is personally known to me.(DScA Signature of Notary Public-State of Florida o~pSs~sg~~ii~01%C,hnrtcs'D.>df Name of Notary Public (Print, Type, or Stamgiig (7sjj8~,ii"'>llillla'l>>
t l I 4 I I 1~~'>f e>~'k 4 St.Lucie Unit 1 Docket No.50-335 Proposed License Amendment Reactor Core Safet Limit ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES l I (I j h V 4 L-96-333 Attachment 1 P~ae I EVALUATION OF PROPOSED TS CHANGES Introduction The proposed amendment to Facility Operating License DPR-67 for St.Lucie Unit 1 will delete a footnote associated with Technical Specification (TS)2.1.1,"Reactor Core Safety Limits," which requires thermal power to be limited to less than or equal to 90%of 2700 Megawatts thermal (MWth)for Cycle 14 operation beyond 7000 Effective Full Power Hours (EFPH).The thermal power constraint was imposed in lieu of performing a Small Break Loss of Coolant Accident (SBLOCA)re-analysis for full power operation that demonstrates acceptable results using input assumptions corresponding to 30%(average)of all steam generator tubes plugged (SGTP).That analysis has been completed, and a report of analysis results is enclosed with this submittal.
Descri tion of Pro osed Chan e TS 2 1 1 Pa e 2-1: Delete the asterisk following"THERMAL POWER," and delete footnote"*" shown at the bottom of page 2-1.A copy of TS Page 2-1, marked-up to show the proposed changes, is contained in Attachment 3.Back round Amendment No.145 to Facility Operating License No.DPR-67 (L.A.Wiens (NRC)to T.F.Plunkett (FPL): ST.LUCIE UNIT 1-ISSUANCE OF AMENDMENT RE: THERIVfAL MARGIN AND REACTOR COOLANT SYSTEM FLOW LIMITS (TAC NO.M95472), July 9, 1996)was issued to permit plant operation with up to 30%(average)SGTP and 345,000 gpm minimum Reactor Coolant System (RCS)flow.In support of this amendment, FPL had determined that conservatism in the existing SBLOCA analysis, which had previously been performed for conditions corresponding to 25%SGTP and 355,000 gpm RCS flow, would offset any adverse effects due to the increased SGTP and decreased reactor coolant system flow for full power operation up to 7000 EFPH.To offset any adverse effects for operation beyond 7000 EFPH, it was determined that limiting core thermal power to 90%of rated thermal power would provide sufficient margin to ensure 10 CFR 50.46 conformity for the remainder of operating Cycle 14.Subsequent to issuance of Amendment No.145, a re-analysis of the SBLOCA has been completed using input assumptions corresponding to 30%(average)SGTP and 345,000 gpm RCS flow.The results of that analysis are briefly discussed in this evaluation, and data is provided in greater detail in the enclosed Siemens Power Corporation-Nuclear Division Report EMF-96-176,"St.Lucie Unit 1 Small Break LOCA Analysis with 30%Steam Generator Tube Plugging," Revision 1, December 1996.
L-96-333 Attachment 1 P~ee 2 Bases for TS Chan e By Amendment No.145, the NRC approved a license amendment to reduce the RCS flow from 355,000 gpm to 345,000 gpm and the low flow trip setpoint from 95%to 93%of design RCS flow.This amendment supported a SGTP level of 30%+7%, with a requirement to derate to 90%of 2700 MWth prior to exceeding 7000 EFPH of Cycle 14 operation.
The requirement to derate was based on the SBLOCA analysis, which supported a full power operation up to 7000 EFPH and 90%power level beyond 7000 EFPH.Except for the SBLOCA, acceptable results were shown within the applicable safety limits for all the safety and setpoint analyses at 100%power operation at the amended conditions and a SGTP level of 30%+7%.The SBLOCA was evaluated at 100%of rated power up to 7000 EFPH and at 90%power level beyond 7000 EFPH.To support Cycle 14 operation at 2700 MWth to end-of-cycle required a reanalysis of SBLOCA with the limiting end-of-cycle conditions.
The SBLOCA has been reanalyzed to support Cycle 14 operation at 100%power for the entire operating cycle.The analysis, included as the enclosure to this proposed license amendment, demonstrates acceptable results in compliance with 10 CFR 50.46 criteria.The peak cladding temperature (PCT)was calculated to be 1804'F, well below the acceptance criteria of 2200'F.This analysis was performed by Siemens Power Corporation (SPC), using an NRC-approved SBLOCA evaluation model.The reanalysis was done with changes to input assumptions with respect to the loop seal clearing and the location of cold leg injection point.The loop seals in the broken loop and one of the intact loops were biased to remain plugged.In the current analysis of record, the loop seal in the broken loop did not stay plugged.Also the safety injection point was moved a node away from the reactor coolant pump to represent a more realistic configuration.
Overall these changes remove some of the conservatism as compared to the analysis of record for 25%tube plugging level (EMF-92-148,"St.Lucie Unit 1 Small Break LOCA Analysis," Siemens Power Corporation, May 1994).Conclusion The SBLOCA reanalysis, along with the analyses addressed in Amendment No.145, support operation of St.Lucie Unit 1 at 100%of RATED THERMAL POWER for the entire Cycle 14.The proposed change supports the reduced RCS flow of 345,000 gpm corresponding to a SGTP level of 30%+7%approved in Amendment No.145.
ATTACHMENT 2 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION L-96-333 Attachment 2 P~ae I DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION Description of amendment request: The proposed amendment will delete a footnote associated with Technical Specification 2.1.1,"Reactor Core Safety Limits," which requires thermal power to be limited to 90%of 2700 Megawatts thermal (MWth)for Cycle 14 operation beyond 7000 Effective Full Power Hours.Pursuant to 10 CFR 50.92, a determination may be made that a proposed license amendment involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not: (1)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.Each standard is discussed as follows: (1)Operation of the facility in accordance with the proposed amendment would not involve a signiTicant increase in the probability or consequences of an accident previously evaluated.
The proposed change will allow full Cycle 14 operation at 100%of rated power (2700 MWth), by deleting the requirement to derate to 90%of rated power prior to exceeding 7000 EFPH.This restriction was imposed in the NRC transmittal letter for License Amendment 145 for SBLOCA considerations when considering the increased SGTP level of 30%+7%.All Final Safety Analysis Report (FSAR)events, other than SBLOCA were evaluated at 100%of rated thermal power and showed no significant increases in the probability or consequences of accidents previously evaluated.
The SBLOCA was reanalyzed to demonstrate continued compliance with 10 CFR 50.46 criteria.There is no impact of the proposed change on any FSAR accident initiator.
The plant configuration and systems remain unchanged.
Therefore, operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.
(2)Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.
This proposed amendment removes the requirement in the Technical Specifications to derate to 90%of 2700 MWth for Cycle 14 operation beyond 7000 EFPH.There will be L-96-333 Attachment 2 P~ae 2 no change to the modes of operation of the plant.The plant configuration and the design functions of all the safety systems remain unchanged.
The proposed amendment will not change the physical plant or the modes of operation defined in the facility license.The changes do not involve the addition of new equipment or the modification of existing equipment, nor do they alter the design of St.Lucie plant systems.Therefore, operation of the facility in accordance with the proposed amendment would not create the possibility of a new or difFerent kind of accident from any accident previously evaluated.
(3)Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.The impact of the proposed change on'available margin to the acceptance criteria for Specified Acceptable Fuel Design Limits (SAFDL), primary and secondary over-pressurization, peak containment pressure, potential radioactive releases, 10 CFR 50.46 requirements for the large break LOCA, and existing limiting conditions for operation has been evaluated and addressed in the reduced RCS flow operating license Amendment No.145.A requirement to derate to 90%of 2700 MWth was imposed based on the SBLOCA analysis.The small break LOCA analysis with 30%+7%SGTP supported operation up to 7000 EFPH at 100%of-rated thermal power.A reanalysis of SBLOCA with the limiting end-of-cycle conditions at 100%of rated power, demonstrates continued compliance with 10 CFR 50.46 criteria.Therefore, operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.Based on the discussion presented above and on the supporting Evaluation of Proposed TS~Changes, FPL has concluded that this proposed license amendment involves no significant hazards consideration.