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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML17229A7101998-04-30030 April 1998
Analysis of Capsule 263 from FPL St Lucie Unit 2 Reactor Vessel Radiation Surveillance Program.
ML17229A5711997-10-31031 October 1997
Criticality Safety Analysis for Spent Fuel Storage Rack Using Soluble Boron Credit.
ML17229A0421996-09-30030 September 1996
Rev 1 to CEN-405-NP, Application of Reactor Vessel Surveillance Data for Embrittlement Mgt.
ML17228B2261995-06-30030 June 1995
Generic Upper Shelf Values for Linde 1092,124 & 0091 Reactor Vessel Welds, Final Rept
ML17228B1901995-05-31031 May 1995
Joint Applications Rept for Safety Injection Tank Aot/Sti Extension.
ML17228B1831995-05-31031 May 1995
Joint Applications Rept for LPSI Sys AOT Extension.
ML17228B1801995-05-31031 May 1995
Joint Applications Rept for EDGs AOT Extension.
ML17228B4991993-07-31031 July 1993
Nonproprietary Version of Application of Reactor Vessel Surveillance Data for Embrittlement Mgt.
ML17228A4591991-09-30030 September 1991
Suppl 1 to Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis St Lucie Nuclear Power Plant Unit 1.
ML17228A4581991-09-30030 September 1991
Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis St Lucie Power Plant Unit 1.
ML20011F4981989-11-30030 November 1989
Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for St Lucie Unit 2.
ML20153G0921988-09-0101 September 1988
Boric Acid Concentration Reduction
ML17221A5971988-01-22022 January 1988
Concentration Reduction Effort,Technical Bases & Operational Analysis.
ML17221A5881987-03-31031 March 1987
Rev 0 to Criticality Safety Analysis St Lucie New Fuel Storage Vault W/4.5% Enriched 14x14 Fuel Assemblies.
ML17219A2621986-10-31031 October 1986
I Steam Generator Allowable Tube Wall Degradation.
ML20238F2591986-08-31031 August 1986
Tube Burst & Leakage Testing of Intergranular Attack & IGSCC Defects Representative of Those Found in St Lucie Unit One Steam Generators
ML20155B1281986-03-20020 March 1986
Loca/Eccs Analysis W/11% Steam Generator Tube Plugging
ML17216A6161986-02-28028 February 1986
Rev 1 to St Lucie Unit 1:New & Spent Fuel Storage Criticality Safety Evaluation for Natural U Axial Blanket Fuel.
ML20140E1961985-12-31031 December 1985
Suppl 1 to St Lucie Unit 1 Revised LOCA-ECCS Analysis W/15% Steam Generator Tube Plugging Break Spectrum & Exposure Results
ML17216A3461985-11-0505 November 1985
Revised LOCA-ECCS Analysis W/15% Steam Generator Tube Plugging.
ML17346B1711985-07-31031 July 1985
Retran Code Transient Analysis Model Qualification.
ML17215A3691984-04-30030 April 1984
Nonproprietary Conservatism of Axial Shape Index DNB Limiting Condition for Operation Below 30% Power.
ML20085H5511983-08-16016 August 1983
Core Support Barrel Insp,Repair & Analysis & Thermal Shield Removal
ML20083N2661983-01-0707 January 1983
Plant Transient Analysis for St Lucie Unit 1
ML20083N2481983-01-0707 January 1983
Rev 1 to St Lucie Unit 1 Cycle 6 Sar
ML20083N2091982-12-20020 December 1982
LOCA Analysis Using Exem/Pwr ECCS Model
ML20039F8671981-12-31031 December 1981
Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for St Lucie 1 & 2 Reactor Vessels.
ML17208A8921980-07-31031 July 1980
RCS Asymmetric Loads Evaluation,Numerical Results - Evaluation of C-E Fuel, App A,Nonproprietary Version
ML17208A8931980-07-31031 July 1980
RCS Asymmetric Loads Evaluation,Eccs Analysis Approach W/Reduced Area Coolant Channels in Peripheral Assemblies, App B
ML19310A2331980-02-29029 February 1980
Statistical Combination of Uncertainties Methodology,Part 3:C-E Calculated Departure from Nucleate Boiling & Linear Heat Rate Limiting Conditions for Operation for St Lucie Unit 1, Nonproprietary Version
ML19310A2241980-01-31031 January 1980
Ceaw:Method of Analyzing Sequential Control Element Assembly Group Withdrawal Event for Analog Protected Sys, Nonproprietary Version
ML19310A2311980-01-31031 January 1980
Statistical Combination of Uncertainties Methodology,Part 2:Combination of Sys Parameter Uncertainties in Thermal Margin Analyses for St Lucie Unit 1, Nonproprietary Version
ML19310A2271979-12-31031 December 1979
Statistical Combination of Uncertainties Methodology,Part 1:C-E Calculated Local Power Density & Thermal Margin/Low Pressure LSSS for St Lucie Unit 1, Nonproprietary Version
ML19310A2261979-11-30030 November 1979
Fiesta:One Dimensional,Two Group Space-Time Kinetics Code for Calculating PWR Scram Activities.
1998-04-30
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17241A4891999-10-0707 October 1999
LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr
ML17241A4951999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for St Lucie,Units 1 & 2.With 991014 Ltr
ML17241A4741999-08-31031 August 1999
Rev 1 to PCM 99016, St Lucie Unit 1,Cycle 16 Colr.
ML17241A4591999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for St Lucie,Units 1 & 2.With 990913 Ltr
ML17241A4301999-07-31031 July 1999
Monthly Operating Repts for Jul 1999 for St Lucie Units 1 & 2.With 990805 Ltr
ML17241A4111999-07-16016 July 1999
LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr
ML17241A4031999-07-0606 July 1999
LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr
ML17241A4041999-07-0606 July 1999
LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr
ML17241A4091999-06-30030 June 1999
Monthly Operating Repts for June 1999 for St Lucie,Units 1 & 2.With 990712 Ltr
ML17241A3941999-06-30030 June 1999
LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr
ML17355A3681999-06-30030 June 1999
Revised Update to Topical QA Rept, Dtd June 1999
ML17241A3551999-06-0404 June 1999
LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr
ML17241A3631999-05-31031 May 1999
Monthly Operating Repts for May 1999 for St Lucie Units 1 & 2.With 990610 Ltr
ML17241A3321999-05-17017 May 1999
LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11
ML17241A3271999-05-0606 May 1999
LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr
ML17241A3331999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for St Lucie,Units 1 & 2.With 990517 Ltr
ML17229B0801999-04-0707 April 1999
LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr
ML17229B0841999-04-0707 April 1999
Rev 2 to PSL-ENG-SEMS-98-102, Engineering Evaluation of ECCS Suction Lines.
ML17229B0791999-04-0707 April 1999
LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr
ML17229B0961999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for St Lucie,Units 1 & 2.With 990408 Ltr
ML17229B0541999-03-10010 March 1999
LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr
ML17229B0461999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for St Lucie,Units 1 & 2.With 990310 Ltr
ML17229B0051999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for St Lucie,Units 1 & 2.With 990211 Ltr
ML17229A9901999-01-20020 January 1999
LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr
ML17229A9961999-01-14014 January 1999
SG Tube Inservice Insp Special Rept.
ML17229A9821999-01-0404 January 1999
LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr
ML17229A9831998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for St Lucie,Units 1 & 2.With 990111 Ltr
ML17229A9611998-12-22022 December 1998
LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr
ML17229A9561998-12-15015 December 1998
LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr
ML17241A3581998-12-0909 December 1998
Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period of 970526-981209.
ML17229A9421998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for St Lucie,Units 1 & 2.With 981215 Ltr
ML17229A9301998-11-25025 November 1998
LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage
ML17229A9021998-11-0404 November 1998
LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr
ML17241A4931998-11-0101 November 1998
Statement of Account for Period of 981101-990930 for Suntrust Bank,As Trustee for Florida Municipal Power Agency Nuclear Decommissioning Trust (St Lucie Project).
ML17229A9051998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for St Lucie,Units 1 & 2.With 981110 Ltr
ML17229A8871998-10-19019 October 1998
Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1 Which Was Machined with Improper Length.C/A Includes Insp Equipment That Will 100% Identify Short Length
ML17229A8781998-10-19019 October 1998
Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1,which Was Machined with Improper Length.Insp Equipment That Will 100% Identify Short Length
ML17229A8771998-10-14014 October 1998
LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr
ML17229A8761998-10-14014 October 1998
LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr
ML17229A8721998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for St Lucie Units 1 & 2.With 981009 Ltr
ML17229A8511998-09-0202 September 1998
LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr
ML17229A8611998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for St Lucie,Units 1 & 2.With 980911 Ltr
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML17229A8481998-08-0707 August 1998
Rev 1 to PSL-ENG-SEFJ-98-013, St Lucie Unit 2,Cycle 10 Colr.
ML17229A9461998-08-0707 August 1998
Rev 0 to PCM 98016, St Lucie Unit 2,Cycle 11 Colr.
ML17229A8301998-07-31031 July 1998
Monthly Operating Repts for July 1998 for St Lucie,Units 1 & 2.W/980814 Ltr
ML17229A8201998-07-29029 July 1998
LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr
ML17229A7981998-06-30030 June 1998
Monthly Operating Repts for June 1998 for St Lucie,Units 1 & 2.W/980713 Ltr
ML17229A7701998-05-31031 May 1998
Monthly Operating Repts for May 1998 for St Lucie,Units 1 & 2.W/980612 Ltr
ML17229A7411998-05-28028 May 1998
LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr
1999-09-30
[Table view] |
Text
SUPPLEMENT 1TOBORICACIDCONCENTOTIONREDUCTION EFFORTCEN-353(P)
TECHNICAL BASESANDOPERATIONAL ANALYSISSAINTLUCIENUCLEARPOWERPLANTUNIT1PREPAREDFORFLORIDAPOWER&.LIGHTCOMPANYBYABBCOMBUSTION ENGINEERING NUCLEARSERVICES9403070179 940222PDRADOCKOS00033S~P..PDR BoricAcidConcentration Reduction Eort.Sul.lTABLEOFCONTENTSCEN-353F1.02.03.040PURPOSEANDSCOPESUMMARYOFRESULTSTECHNICAL BASESFORREVISIONS 3.1REVISEDBAMTVOLUMEREQUIREMENTS 3.2REVISEDBASESSECTION3/4.
1.2REFERENCES
1012TABLESTABLE3-1BAMTBORATIONVOLUMETABLE3-2REQUIREDBAMTSTORAGEVOLUMEFIGURESFIG.3-1ST.LUCIE1MINIMUMBAMTVOLUMEvs.STOREDBAMTCONCENTRATION APPENDIXATECHNICAL SPECIFICATION INPUTFORST.LUCIEUNIT1A-1ABBCombustion Engineering NuclearServicesPage2of12 BoricAcidConcentration Reduction Eort.Sul.1CEN-353(F 1.0PurposeandScopeThepurposeofthisSupplement totheBoricAcidConcentration Reduction (BACR)reportis.toprovideanadjustment totheBoricAcidMakeupTank(BAMT)Volumeandconcentration requirements fortheSt.LucieUnit1Technical Specifications Section3.1.2.8.Thisadjustment isdueonlytorevisinganassumption thatwasmadeintheBACRReport,CEN-353(F),
Rev03.Thissupplement modifiesanoriginalassumption thattheBAMTwouldbeneededasthesourceoffluidfordepressurization oftheRCSfrom2200psiatotheHighPressureSafetyInjection (HPSI)pumpshutoffhead.Thedepressurization wouldrequireadditional inventory ifthemotoroperatedvalvebetweentheRefueling WaterTank(RWT)andthechargingpumpsuction,V2504,failedtoopenautomatically,and couldnotbeopenedmanually.
Oncethedepressurization
- occurred, thecooldowncouldbecontinued usingfluidfromtheRWT.ThisrevisionnowassumesthatV2504canbeopenedmanually, therefore, theBAMTinventory neededtodepressurize totheHPSIpumpshutoffheadisnolongerrequired.
ThisresultsinrevisionoftherequiredBAMTborationvolumesandtheTechnical Specification BAMTstoragerequirements.
ThisSupplement isapplicable toSt.LucieUnit1only.RevisionoftheBAMTVolumerequirements willalsoresultinachangetotheBAMTvolumeslistedintheTechnical Specification BASESSection3/4.1.2.ThellBASESvalueswerepresented onpages32and33ofthereport.Inthereport,thetextoftheBasesinsertusedtheexactBAMTborationvolume,ratherthantheABBCombustion Engineering NuclearServicesPage3ofl2 BoricrlcidConcelurntion Reduction Eorr.Sul.iCEJV-353IF requiredstoragevolume.TheBASEStextwasrevisedtocorrespond totherequiredstoragevolumes,whichwereconservative.
Sincetheassumption changeofthiscalculation revisesthevolumeadjustment betweentheBAMTborationvolumeandtherequiredstoragevolume,theBASESinsertwillberevised.2.0SummarofResultsTheproposedTechnical Specification inputsforSt.LucieUnit1forSection3.1.2.8andBASESSection3/4.1.2arecontained inAppendixA.TherevisedvaluessuppliedinAppendixAarederivedinSection3.1and3.2below.3.0Technical BasesforRevisions 3.1RevisedBAMTVolumeRequirements Asstatedabove,thepurposeofthissupplement istodocumenttherevisionoftheadjustment betweentheBAMTborationvolumesandtheTechnical Specification BAMTstoragerequirements.
Inthepreviousrevisiontothisreport,manualoperation ofV2504(themotoroperatedvalvebetweentheRWTandthechargingpumpsuction)wasnotassumedforapostulated failuretoopenautomatically.
SinceRWTwaterwouldberiBBColnbustion Engineering nuclearServicesPnge4of12 BoricAcidConcentration Reduction Eort.Sul.1CEN-353(F unavailable throughtheCVCSforcooldownwithV2504'closed, additional waterinventory requirements wereimposedontheBAMTstoallowfordepressurization oftheRCSdowntoHPSIshutoffhead(1200psia)usingauxiliary spray.Avolumeadjustment of1000gallonswasused,tocoverthe905.9gallonsrequiredforthedepressurization (CEN-353(F),
Rev.03,Page29).Theborationvolumeswereadjustedbyroundinguptothenext50gallonsandthenadding1000gallonstocoverthedepressurization volume.Manualhandwheel operation ofmotoroperatedvalveV2504isacceptable forSt.LucieUnit1cooldownscenarios.
Revisingthisassumption willmaketheSt.LucieUnit1analysisagreewiththeUnit2analysisforthisassumption.
Withmanualoperation ofV2504,adjustment oftheborationvolumetoincludethevolumefordepressurization willnolongerberequired.
InCEN-353(F),
Rev.03,theBAMTborationvolumesforeachcombination ofBAMTandRWTconcentrations wasprovidedinTable2-34onpage73.ThesevaluesarerepeatedinTable3-1below.ABBCotnbustion Engineering NuclearServicesPage5of12 BoricAcidConcentration Reduction Eort,Sul.iTABLE3-1CEJV-353FBORICACIDMAKEUPTANKMINIMUMBORATIONVOLUMESVSSTOREDBORICACIDCONCENTRATION FORMODES1,2,3AND4MINIMUMVOLUME(GALLONS)
BAMTatwt%17201850RWTatRWTatRWTat2000RWTatRWTat21502300ppmppmppmppmppm2.502.753.003.253.508194.57703.9.6966.86607.96185.45689.85406.05065.44887.74535.67221.16129.95235.24594.04130.16714.56019.35577.74946.84769.94187.74130.13650.93713.23213.1DuringtheSt.LucieUnit2BACRanalysis, 500gallonswereaddedtotheBAMTborationvolumesforconservatism.
Tobeconsistent withUnit2,500gallonswillbeaddedtotheSt.LucieUnit1BAMTborationvolumestodefinetherevisedTechnical Specification BAMTStoragevolumerequirements.
Theborationvolumes;vill beroundeduptothenext50gallons,and500gallonswillbeaddedforconservatism.
Theresulting RequiredBAMTStorageVolumesarecontained inTable3-2andareplottedinFigure3-1.Figure3-1providestherevisedstoragerequirements toreplaceFigure2-6onpage82ofthemainreport.ABBCombustion Engineering NuclearServicesPage6ofl2
BoricAcidConcentration Reduction Eort.SuI.lCEN-353/'F TABLE3-2MINIMUMBORICACIDMAKEUPTANKVOLUMEVS.STOREDBORICACIDMAKEUPTANKCONCENTRATION MINIMUMVOLUME(GALLONS)
BAMTatwt,%172018502000RWTatRWTatRWTatRWTat2150RWSTat2300ppmppmppmppmppm2.50870082507750725065502.75750071506650610054503.00670062005750530047003.253.505950540056005100505046504650425042003750FP&Lcurrently requeststhatonlyonecurvebepresented intheRequiredBAMTVolumecurve,Technical Specification Figure3.1-1,ratherthanthefamilyofcurvesforvariousRWTconcentrations.
FP&LrequeststhatonlythecurvefortheRWTat1720ppmbeprovided.
ThenewTechnical Specification Figure3.1-1iscontained inAppendixA.ABBCotnbustion Engineering NttclearServicesPage7of12 BoricAcidConcentration Reduction Eort.Sul.lCEN-353(F SincethenewRequiredBAMTvolumescanbecontained inonetankforthefullrangeofboricacidconcentrations, someofthetextforTechnical Specification Section3.1.2.8canbedeleted.Whenthevolumerequirement forthefullrangeofconcentrations couldnotfitinonetank,thecurrentspecification requiredaboricacidconcentration between3.2-3.5weightpercent.Therevisedspecification iscontained inAppendixA.ABBCombustion Engineering NuclearServicesPage8of12 BoricAcidConcentration Reduction EortSu>~l.ICEN-353FFIGURE3-1ST,LUCIE1IVIINBAMTVOLUMEvsSTOREDBAMTCONCENTRATION Q7g~60~52.62.83.03.2STOREDBAMTCONC(wt%boricacid)3.43.6~1720PPM~1850PPM~2000PPM~2150PPM~2300PPMIHRWTINRWTINRWTINRWTIHRWTABBCombustion Engineering NuclertrSetvicesPage9ofl2 BoricAcidConcentration Reduction Eort.Sul.lCEN-353(F 3.2Technical Secification BASESSection3/4.1.2TheTechnical Specification BASESSection3/4.1.2wasoriginally presented onpages32and33ofCEN-353(F),
Rev.03.Thepurposeofthatsectionwastodetermine thenewBAMTandRWTvolumevaluesfortheTechnical Specification BASESsection.ThesectionusedtheBAMTborationvolumesasinputstodetermine therequiredRWTvolumeforthecooldowndepending ontheBAMTconcentration used.Italsodetermined theRWTvolumerequiredifnoBAMTvolumewasused.WhiletheactualBAMTBorationVolumevalueswereusedinthesection,therevisedtextoftheBASESSectionshouldreporttheBAMTStorageVolumeRequirements asthevolumeused.SincetheBAMTStorageVolumeRequirements aregreater,thisisconservative.
TheBAMTStorageVolumesareusedtomaketheBASESSectionconsistent withtheBAMTStorageVolumescontained inFigure3.1-1andTechnical Specification Section3.1.2.8'.
SincetheTechnical Specification BAMTStorageVolumeRequirements wererevisedinSection3.1above,TheBASESSectionshouldberevisedtocorrespond tothenewBAMTStorageVolumeRequirements.
SincetheBAMTBorationVolumeswereusedtocalculate theRWTvolumerequirements, andtheBAMTBorationVolumeshavenotchanged,thereisnoneedtorevisetheRWTvolumerequirements.
rhBBCombustion Engineering NuclearServicesPage10of12 BoricAcidConcentration Reduction Eort.Sul.lCEN-353FTherevisedtextfortheBASESSectionisasfollows:"Theborationcapability ofeithersystemissufficient toprovideaSHUTDOWNMARGINfromalloperating conditions of2000pcmafterxenondecayandcooldownto200degreesF.Themaximumboration'apability requirement occursatEOLfromfullpowerequilibrium xenonconditions.
Thisrequirement canbemetforarangeofboricacidconcentrations ontheBoricAcidMakeupTanks(BAMTs)andRefueling WaterTank(RWT).Thisrangeisboundedby5400gallonsof3.5weightpercent(6119ppmboron)boricacidfromtheBAMTsand17,000gallonsof1720ppmboratedwaterfromtheRWTto8700gallonsof2.5weightpercent(4371ppmboron)boricacidfromtheBAMTsand13,000gallonsof1720ppmboratedwaterfromtheRWT.Aminimumof45,000gallonsof1720ppmboronisrequiredfromtheRWTifitistobeusedtoboratetheRCSalone."Thistextiscontained inAppendixA.ABBCombustion Engineering NuclearServicesPagellof12 BoricAcidConcentration Reduction Eort.Suol.lCEN-353(F J
4.0REFERENCES
4.1ABB-CECalculation 607784-MPS-1CALC-001, Revision00,"St.LucieUnit1InputtoTechnical Specifications 3.1.2.8and4.1.2.8",
dated9/25/90.4.2ABB-CECalculation F-MPS-CALC-002, Rev.00,"InputtoSt.LucieUnit1Technical Specification SystemBases",dated9/26/91.4.3StLucieUnit1Technical Specifications, throughAmendment 122,dated5/03/93.4.4ABB-CECalculation F-MECH-CALC-016, Rev.00,"FP&LSt.Lucie1RevisionofTechnical Specification Section3.1.2.8andBASES3/4.1.2",
dated10/21/93.
ABBCombustion Engineering NuclearServicesPagel2of12 BoricAcidConcentration Reduction Eort.Sul.lCEN-353(F)
APPENDIXATechnical Specification InputforSt.LucieUnit1ABBCombustion Engineering NuclearServicesPageA-lof5 BoricAcidConcentration Reduction Eurt.Surl.lCEN-353FFIGURE3.1-1ST.LUCIE1lVIINBAMTVOLUMEYSSTOREDBAMTCONCENTRATION 9,000V)O8,000GJCD(8700)ACCEPTABLE OPERATION (7500)~7,000O)I-~e,oooZ'6700)UNACCEPTABLE OPERATION (6960)5,000(6400)2.42.62.833.23.43.6(4646PPM)(5245ppM)(6g44PPM)(4196PPM)(4896PPM)(55g6ppM)(62g4ppM)STOREDBAMTCONC(wt%boricacid)ST.LUCIE-UNITI3/41-1/ABBCombustion Engineering NuclearServicesPageA-2of5
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