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| {{#Wiki_filter:CATEGORYREGULAT55f INFORMATION DISTRIBUTIO YSTEM(RIDS)ACCESSION NBR:9703270101 DOC."DATE: | | {{#Wiki_filter:CATEGORY REGULAT55f INFORMATION DISTRIBUTIO YSTEM (RIDS)ACCESSION NBR:9703270101 DOC."DATE: |
| 97/03/21NOTARIZED: | | 97/03/21 NOTARIZED: |
| NOFACILSO-'33'5St.LuciePlant,Unit1,FloridaPower6Light.Co.AUTH.NAMEAUTHORAFFILIATION DIETZ,R.L.
| | NO FACIL SO-'33'5 St.Lucie Plant, Unit 1, Florida Power 6 Light.Co.AUTH.NAME AUTHOR AFFILIATION DIETZ,R.L. |
| FloridaPoweraLightCo.STALL,J.A.
| | Florida Power a Light Co.STALL,J.A. |
| FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION "DOCKET05000335
| | Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION"DOCKET 05000335 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER97-002-00:on 970221,operation inexcessofmaxRatedThermalPoweroccurredy failuretoimplement effective configuration forDigitalDataProcessing SyscomputerDZSTRZBUTZON CODE:ZE22TCOPZESRECEZUED:LTR
| | LER 97-002-00:on 970221,operation in excess of max Rated Thermal Power occurredy failure to implement effective configuration for Digital Data Processing Sys computer DZSTRZBUTZON CODE: ZE22T COPZES RECEZUED:LTR |
| )ENCLtSZZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:RECIPIENT IDCODE/NAME PD2-3PDINTERNAL: | | )ENCL t SZZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD2-3 PD INTERNAL: ACRS AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB EXTERNAL: L ST LOBBY WARD NOAC POOREPW.NRC PDR COPIES, LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1~-1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME WIENSPL.B IL CENTER N NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN2 FILE 01 LITCO BRYCE,J H.NOAC QUEENERPDS NUDOCS FULL TXT COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 N NOTE TO ALL"RIDS" RECIPIENTS: |
| ACRSAEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB EXTERNAL:
| | PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25 a Florida Power&Light Company, 6501 South Ocean Drive, Jensen Beach, FL34957 APL MAR 2)1997 L-97-081 10 CFR 50.73 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Re: St.Lucie Unit 1 Docket 50-335 Reportable Event: 97-002 Date of Event: February 21, 1997 Operation in Excess of Maximum Rated Thermal Power The attached Licensee Event Report is a voluntary report submitted to provide notification of the subject event.Very truly yours,'I J.A.Stall Vice President St.Lucie Plant JAS/RLD Attachment cc: Regional Administrator, USNRC Region II Senior Resident Inspector, USNRC, St.I.ucie Plant'703270iOi 97032X PDR ADGCK 05000335 8 PDR lllgttlllElllPiHillttltl an FPL Group company NRC FORM 366 (4-as)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters for each block)APPROVED SY OMS NO.S)50%105 EXPIRES 05QOISS ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MAHDAT INFORMATION COILECTIOH REQUEST: 50.0 HRS.REPORTED LESSON LEARNED ARE INCORPORATED INTO THE UCENSINO PROCESS AND SACK TO SE)USIRY.FORWAIE)COMM BITS REOARDIHO BURDEN ESTIMA TO THE INFORMATION AND RECORDS MANAOEMEHT BRANCH IT%F33)UW NUCLEAR REOIAATORY COMMISSION, WASHINOTON, DC 20555400)AND TO THE PAPERWORK REDUCTION PROJECT 131500)04), OFHCE 0 MANAOEMENT AND BUDGET, WASHIHOTON, DC 20503.PAcIUTY NAME l1)TITlE Ia)ST.LUCIE UNIT 1 DocKET NLssBER l2)05000335 PAOE IS)1 OF 5 Operation in Excess of Maximum Rated Thermal Power Due to Digital Data Processor Calorimetric Error MONTH DAY SEQUENTIAL REV)SION NUMBER NUMBER MONTH DAY YEAR FACIUTY NAME NIA DOCKET NUMBER 02 21 OPERATING MODE (9)LEVEL (10)97 97-002-00 20.2201 (b)20.2203(a)(2)(I) 20.2203(a)(2)(ill)20.2203(e)(2)(iv) 03 21 97 20.2203(e)(2)(v)20.2203(a)(3)(ii) 50.3B(o)(1) 60.3B(c)(2) |
| LSTLOBBYWARDNOACPOOREPW.NRCPDRCOPIES,LTTRENCL11111111111111111~-1111111RECIPIENT IDCODE/NAME WIENSPL.BILCENTERNNRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN2FILE01LITCOBRYCE,JH.NOACQUEENERPDS NUDOCSFULLTXTCOPIESLTTRENCL112211111111111111111111NNOTETOALL"RIDS"RECIPIENTS:
| | FACIUTY NAME NIA 50.73(e)(2)(I)50.73(a)(2)(ill) 50.73(e)(2)(v) 50.73(a)(2)(vli)DOCKET NUMBER 50.73(e)(2)(vlii) 73.71 OTHER Specify In Abstract below or In NRC Form 3SSA NAME R,L.DIETZ, Licensing Engineer TELEPHONE NUMBER Onckde Arse Code)(561)467-7157 cAusE SYSTEM COMPONENT MANUFACTURER To NPRDS CAUSE SYSTEM COMPONENT MANUFACTURER To NPRDS YES (If yes, complete EXPECTED SUBMISSION DATE): X No MONTH DAY YEAR SUBMISSION DATE (16)ABSTRACT (L(mit to 1400 spaces, I.e., approximately 15 single-spaced typewritten lines)(16)This LER is a voluntary report.On February 21, 1997, St.Lucie Unit 1 was operating at a steady-state power level of 100%Rated Thermal Power (RTP)as determined from the Digital Data Processing System (DDPS)display.While performing a feed water flow instrument loop calibration, maintenance personnel determined that proper scaling constants were not being used for the feed water flow input signals to the DDPS.This condition caused the DDPS calorimetric calculation of reactor core thermal power to be non-conservative in that facility steady-state operation with the DDPS indicating 100%RTP resulted in actual reactor power at 100A3%RTP.Plant operation was limited to not more than 99%RTP (indicated) while the problem was thoroughly investigated and corrected. |
| PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
| | On March 1, 1997, St.Lucie Unit 1 was returned to 100%RTP.The cause of this event was failure to implement effective configuration controls for the DDPS computer software.Corrective actions include: 1)Acceptable performance of all critical DDPS functions was verified prior to restoration of full power operations. |
| LTTR25ENCL25 aFloridaPower&LightCompany,6501SouthOceanDrive,JensenBeach,FL34957APLMAR2)1997L-97-08110CFR50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit1Docket50-335Reportable Event:97-002DateofEvent:February21,1997Operation inExcessofMaximumRatedThermalPowerTheattachedLicenseeEventReportisavoluntary reportsubmitted toprovidenotification ofthesubjectevent.Verytrulyyours,'IJ.A.StallVicePresident St.LuciePlantJAS/RLDAttachment cc:RegionalAdministrator, USNRCRegionIISeniorResidentInspector, USNRC,St.I.uciePlant'703270iOi 97032XPDRADGCK050003358PDRlllgttlllElllPiHillttltl anFPLGroupcompany NRCFORM366(4-as)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/characters foreachblock)APPROVEDSYOMSNO.S)50%105EXPIRES05QOISSESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISMAHDATINFORMATION COILECTIOH REQUEST:50.0HRS.REPORTEDLESSONLEARNEDAREINCORPORATED INTOTHEUCENSINOPROCESSANDSACKTOSE)USIRY.
| | 2)Review of accountabilities for software modifications and identification of program improvements. |
| FORWAIE)COMMBITSREOARDIHO BURDENESTIMATOTHEINFORMATION ANDRECORDSMANAOEMEHT BRANCHIT%F33)UWNUCLEARREOIAATORY COMMISSION, WASHINOTON, DC20555400) | | 3)Development of verification and validation requirements that challenge all critical attributes for software changes within the DDPS.4)Development of controlled operating procedures to address DDPS operation. |
| ANDTOTHEPAPERWORK REDUCTION PROJECT131500)04),
| | 5)Use of the St.Lucie Total Equipment Data Base or controlled procedures to ensure configuration control of critical DDPS constants. |
| OFHCE0MANAOEMENT ANDBUDGET,WASHIHOTON, DC20503.PAcIUTYNAMEl1)TITlEIa)ST.LUCIEUNIT1DocKETNLssBERl2)05000335PAOEIS)1OF5Operation inExcessofMaximumRatedThermalPowerDuetoDigitalDataProcessor Calorimetric ErrorMONTHDAYSEQUENTIAL REV)SIONNUMBERNUMBERMONTHDAYYEARFACIUTYNAMENIADOCKETNUMBER0221OPERATING MODE(9)LEVEL(10)9797-002-0020.2201(b)20.2203(a)(2)(I) 20.2203(a)(2)
| | 6)Modification of the software vendor blanket purchase order to clarify that compliance with FPL administrative procedures is required.NRC FORM 3SS (4.SS) |
| (ill)20.2203(e)(2)(iv) 03219720.2203(e)(2) | |
| (v)20.2203(a)(3)(ii) 50.3B(o)(1) 60.3B(c)(2) | |
| FACIUTYNAMENIA50.73(e)(2)
| |
| (I)50.73(a)(2)(ill) 50.73(e)(2)(v) 50.73(a)(2)(vli)DOCKETNUMBER50.73(e)(2)(vlii) 73.71OTHERSpecifyInAbstractbeloworInNRCForm3SSANAMER,L.DIETZ,Licensing EngineerTELEPHONE NUMBEROnckdeArseCode)(561)467-7157cAusESYSTEMCOMPONENT MANUFACTURER ToNPRDSCAUSESYSTEMCOMPONENT MANUFACTURER ToNPRDSYES(Ifyes,completeEXPECTEDSUBMISSION DATE):XNoMONTHDAYYEARSUBMISSION DATE(16)ABSTRACT(L(mitto1400spaces,I.e.,approximately 15single-spaced typewritten lines)(16)ThisLERisavoluntary report.OnFebruary21,1997,St.LucieUnit1wasoperating atasteady-state powerlevelof100%RatedThermalPower(RTP)asdetermined fromtheDigitalDataProcessing System(DDPS)display.Whileperforming afeedwaterflowinstrument loopcalibration, maintenance personnel determined thatproperscalingconstants werenotbeingusedforthefeedwaterflowinputsignalstotheDDPS.Thiscondition causedtheDDPScalorimetric calculation ofreactorcorethermalpowertobenon-conservative inthatfacilitysteady-state operation withtheDDPSindicating 100%RTPresultedinactualreactorpowerat100A3%RTP.Plantoperation waslimitedtonotmorethan99%RTP(indicated) whiletheproblemwasthoroughly investigated andcorrected. | |
| OnMarch1,1997,St.LucieUnit1wasreturnedto100%RTP.Thecauseofthiseventwasfailuretoimplement effective configuration controlsfortheDDPScomputersoftware.
| |
| Corrective actionsinclude:1)Acceptable performance ofallcriticalDDPSfunctions wasverifiedpriortorestoration offullpoweroperations. | |
| 2)Reviewofaccountabilities forsoftwaremodifications andidentification ofprogramimprovements. | |
| 3)Development ofverification andvalidation requirements thatchallenge allcriticalattributes forsoftwarechangeswithintheDDPS.4)Development ofcontrolled operating procedures toaddressDDPSoperation. | |
| 5)UseoftheSt.LucieTotalEquipment DataBaseorcontrolled procedures toensureconfiguration controlofcriticalDDPSconstants. | |
| 6)Modification ofthesoftwarevendorblanketpurchaseordertoclarifythatcompliance withFPLadministrative procedures isrequired. | |
| NRCFORM3SS(4.SS)
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| NRCFORM388AI4.9SILICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO ST.LUCIEUNIT105000335YEARSEQUENTIAL REVISION97-002-002OF5TEXTiifmorespaceisrequired, useadditional copiesofNRCArm3684Il17IOnFebruary21,1997,St.LucieUnit1wasoperating atasteady-state powerlevelof100%RatedThermalPower(RTP)asdetermined fromtheDigitalDataProcessing System(DDPS)[EIIS:IO]
| | NRC FORM 388A I4.9SI LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSIO ST.LUCIE UNIT 1 05000335 YEAR SEQUENTIAL REVISION 97-002-00 2 OF 5 TEXT iif more space is required, use additional copies of NRC Arm 3684I l17I On February 21, 1997, St.Lucie Unit 1 was operating at a steady-state power level of 100%Rated Thermal Power (RTP)as determined from the Digital Data Processing System (DDPS)[EIIS:IO]display.Utility Instrumentation and Control (ILC)personnel were performing a feed water flow instrument loop calibration following maintenance on a feed water flow transmitter |
| display.UtilityInstrumentation andControl(ILC)personnel wereperforming afeedwaterflowinstrument loopcalibration following maintenance onafeedwaterflowtransmitter | |
| [EIIS:SJ:PDT]. | | [EIIS:SJ:PDT]. |
| Duringthiscalibration, itwasdiscovered thatscalingconstants forallsixofthefeedwaterflowinputsignalstotheDDPScomputer[EIIS:IO:CPU]
| | During this calibration, it was discovered that scaling constants for all six of the feed water flow input signals to the DDPS computer[EIIS:IO:CPU] |
| wereincorrect, i.e.,theinputsignalrangeof4-20milliamperes corresponded toaflowventuri[EIIS:SJ:FE]
| | were incorrect, i.e., the input signal range of 4-20 milliamperes corresponded to a flow venturi[EIIS:SJ:FE] |
| differential pressurespanofapproximately 0-790inchesofwaterratherthanthecorrectspanof0-800inchesofwater.SincetheDDPSusesthefeedwaterflowparameter incalorimetric calculations ofreactor[EIIS:RCT] | | differential pressure span of approximately 0-790 inches of water rather than the correct span of 0-800 inches of water.Since the DDPS uses the feed water flow parameter in calorimetric calculations of reactor[EIIS:RCT] |
| corethermalpower,thisdiscrepancy wasnon-conservative inthatscalingconstants corresponding tolessthanthefullrangeofflowventuridifferential pressures resultinacalculated valueofpowerthatislessthantheactualreactoroutput.Controlroomoperators werenotifiedbyILCpersonnel thatthereactorwasoperating atacorethermalpowerlevelapproximately 0.6%RTPgreaterthanthevaluedisplayed ontheDDPS,andactionwaspromptlyinitiated toreducepower.At17:55ESTonFebruary21,1997,St.LucieUnit1wasstabilized ataconservative valueof99%RTP(indicated).
| | core thermal power, this discrepancy was non-conservative in that scaling constants corresponding to less than the full range of flow venturi differential pressures result in a calculated value of power that is less than the actual reactor output.Control room operators were notified by ILC personnel that the reactor was operating at a core thermal power level approximately 0.6%RTP greater than the value displayed on the DDPS, and action was promptly initiated to reduce power.At 17:55 EST on February 21, 1997, St.Lucie Unit 1 was stabilized at a conservative value of 99%RTP (indicated). |
| Theunitwasreturnedto100%RTPat05:45ESTonMarch1,1997.InJune,1994,feedwaterflowscalingconstants wererevisedinaccordance withapprovedplantprocedures.
| | The unit was returned to 100%RTP at 05:45 EST on March 1, 1997.In June, 1994, feed water flow scaling constants were revised in accordance with approved plant procedures. |
| Thesescalingconstants wereproperlyinstalled intotheoperating DDPSsoftware, butwerenotupdatedinthecontrolroomDDPSdatareference manual.In1996,thesoftwarewasmodifiedbythevendorusingthevendor'sversionofthesourcecodetoaccommodate installation ofanewcoreperformance monitorthatinterfaces withtheDDPS.Whenthismodification wasloadedintotheDDPScomputerduringthe1996refueling outage,theproperscalingconstants wereoverwritten andreplacedwiththepre-1994valuesbasedonthecontrolroomDDPSdatareference manual.Thiscondition wasnotdiscovered untiltheinstrument loopcalibration wasperformed onFebruary21,1997.Thecauseofthiseventwasfailuretoimplement effective configuration controlsfortheDDPScomputersoftware.
| | These scaling constants were properly installed into the operating DDPS software, but were not updated in the control room DDPS data reference manual.In 1996, the software was modified by the vendor using the vendor's version of the source code to accommodate installation of a new core performance monitor that interfaces with the DDPS.When this modification was loaded into the DDPS computer during the 1996 refueling outage, the proper scaling constants were overwritten and replaced with the pre-1994 values based on the control room DDPS data reference manual.This condition was not discovered until the instrument loop calibration was performed on February 21, 1997.The cause of this event was failure to implement effective configuration controls for the DDPS computer software.ln June 1994, a change to the span/static shift adjustment for each of the six DDPS feed water flow transmitters was implemented in accordance with an approved plant work order.To be compatible with the span adjustments, the existing feed water flow scaling constants corresponding to a span of 0-790.6 inches of water'differential pressure were revised to correspond to a span of 0-800 inches of water differential pressure.The new scaling constants were loaded into the correct DDPS operating software locations, but were not recorded in the control room DDPS data reference manual which is maintained at the DDPS console.NRC FORM mA Ii-95I |
| lnJune1994,achangetothespan/static shiftadjustment foreachofthesixDDPSfeedwaterflowtransmitters wasimplemented inaccordance withanapprovedplantworkorder.Tobecompatible withthespanadjustments, theexistingfeedwaterflowscalingconstants corresponding toaspanof0-790.6inchesofwater'differential pressurewererevisedtocorrespond toaspanof0-800inchesofwaterdifferential pressure.
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| Thenewscalingconstants wereloadedintothecorrectDDPSoperating softwarelocations, butwerenotrecordedinthecontrolroomDDPSdatareference manualwhichismaintained attheDDPSconsole.NRCFORMmAIi-95I
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| NRCFORM386AI4.96)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREOULATORY COMMISSIO ST.LUCIEUNIT105000335YEARSEQUENTIAL REVISION97-002-003OF5TEXT/ifmorespecsisreriuired, useedditionel copiesofNRC.cform36EAII17)TheDDPSsoftwareisconsidered qualityrelated.Atthetimethe1994revisionwasmadetothefeedwaterflowscalingconstants, Ql2-PR/PSL-3, Revision0,ControlofComputerSoftware, providedgenericadministrative controlsforcomputersoftwareinwhichtheoutputisusedforsafetyrelatedandqualityrelatedpurposes.
| | NRC FORM 386A I4.96)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REOULATORY COMMISSIO ST.LUCIE UNIT 1 05000335 YEAR SEQUENTIAL REVISION 97-002-00 3 OF 5 TEXT/if more specs is reriuired, use edditionel copies of NRC.cform 36EAI I 17)The DDPS software is considered quality related.At the time the 1994 revision was made to the feed water flow scaling constants, Ql 2-PR/PSL-3, Revision 0, Control of Computer Software, provided generic administrative controls for computer software in which the output is used for safety related and quality related purposes.Significant revisions to strengthen this procedure have been made since 1994.During the refueling outage of April-July, 1996, an on-line core'performance monitoring system which interfaces with the DDPS was installed in accordance with an approved Plant Change/Modification (PC/M).The DDPS software changes needed to accommodate this new installation were developed by the vendor using the vendor's version of the source code (which did not contain the 1994 revised scaling constants). |
| Significant revisions tostrengthen thisprocedure havebeenmadesince1994.Duringtherefueling outageofApril-July,1996,anon-linecore'performance monitoring systemwhichinterfaces withtheDDPSwasinstalled inaccordance withanapprovedPlantChange/Modification (PC/M).TheDDPSsoftwarechangesneededtoaccommodate thisnewinstallation weredeveloped bythevendorusingthevendor'sversionofthesourcecode(whichdidnotcontainthe1994revisedscalingconstants). | | Upon loading the modified software into the DDPS computer, the correct feed water flow constants were overwritten with those corresponding to a range of 0-790.6 inches of water differential pressure.Administrative Procedure (AP)4000060, Maintenance Departmental Control of Computer Software, was implemented February 26, 1996, to provide the methodology by which the maintenance department and support groups control the procurement, development, and revision of software to comply with Ql 2-PR/PSL-3.The validation and verification (V&V)method that was used to confirm the DDPS proper software configuration following modifications to accommodate the 1996 PC/M was selected from this procedure, but did not V&V other functions of the software, such as the calorimetric calculation, that were not related to the modification. |
| UponloadingthemodifiedsoftwareintotheDDPScomputer, thecorrectfeedwaterflowconstants wereoverwritten withthosecorresponding toarangeof0-790.6inchesofwaterdifferential pressure.
| | During post modification testing (PMT)for the 1996 PC/M, the control room copy of the DDPS data reference manual was used to perform a verification of each DDPS input constant.However, this manual is not a controlled document and had not been updated to reflect the 1994 revision to the feed water flow scaling constants. |
| Administrative Procedure (AP)4000060,Maintenance Departmental ControlofComputerSoftware, wasimplemented February26,1996,toprovidethemethodology bywhichthemaintenance department andsupportgroupscontroltheprocurement, development, andrevisionofsoftwaretocomplywithQl2-PR/PSL-3. | | This prevented discovery of the problem at that time, i.e., the values used to verify the feed water flow scaling constants were the same pre-1994 values as those residing in the software that had been loaded into the DDPS computer from the vendor source code, The feed water flow scaling constant error was determined to be.non-conservative by 0.6348 RTP.Two additional discrepancies, unrelated to the 1996 modification, were also discovered in the calorimetric calibration and were determined to result in a combined conservative error of 0.2%RTP.Therefore, the net calorimetric error was 0.43%non-conservative. |
| Thevalidation andverification (V&V)methodthatwasusedtoconfirmtheDDPSpropersoftwareconfiguration following modifications toaccommodate the1996PC/Mwasselectedfromthisprocedure, butdidnotV&Votherfunctions ofthesoftware, suchasthecalorimetric calculation, thatwerenotrelatedtothemodification.
| | An operability assessment was performed which determined that the feed water flow scaling discrepancy combined with the calorimetric measurement un ertainty was less than the required overall calorimetric accuracy requirement of 2%at maximum rated thermal power.In addition, reactor protection, core physics, and reactor fuel parameters impacted by the calorimetric error were evaluated to ensure that assumptions made in the plant safety analysis provided sufficient margin to bound this event.This evaluation concluded that the existing plant safety analysis remains valid.Therefore, the health and safety of the public were not adi>>ely affected by this event.NRC FoRM 388A (4-96I NRC FORM 3SBA I4-96)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSI ST.LUCIE UNIT 1 05000335 YEAR SEQUENTIAL REVISION 9 7-002-00 4 OF 5 TEXT (if more speceis required, use edditionel copies of IVRC Form 368Ai I17)Facility operation was limited to a conservative value of 99%RTP until the problem was thoroughly investigated and corrected. |
| Duringpostmodification testing(PMT)forthe1996PC/M,thecontrolroomcopyoftheDDPSdatareference manualwasusedtoperformaverification ofeachDDPSinputconstant.
| | Primary system manual calorimetric calculations were performed to verify reactor power remained below 100%RTP.2)The correct feed water flow scaling constants were entered into both the on-line and the back-up DDPS computers, and other calorimetric constants were verified to be correct using information fro the plant Total Equipment Data Base (TEDB).The increase in calculated calorimetric power shown on the DDPS display was verified to be as predicted. |
| However,thismanualisnotacontrolled documentandhadnotbeenupdatedtoreflectthe1994revisiontothefeedwaterflowscalingconstants. | | A primary system manual calorimetric calculation was performed and results were within 0.2%of DDPS indicated power.3)The correct feed water flow scaling constants were documented, and master/backup copies of the upgraded system were filed in accordance with an approved St..Lucie Plant Software Configuration/Change Control, Computer Software Change Request (Administrative Procedure 4000060, Revision 2).Acceptable performance of other critical DDPS functions was verified to ensure that other inadvertent software changes had not been made, and surveillances were performed for other plant systems whose calibrations can be influenced by DDPS calculated calorimetric power to ensure that these system calibrations had not been compromised. |
| Thisprevented discovery oftheproblematthattime,i.e.,thevaluesusedtoverifythefeedwaterflowscalingconstants werethesamepre-1994valuesasthoseresidinginthesoftwarethathadbeenloadedintotheDDPScomputerfromthevendorsourcecode,Thefeedwaterflowscalingconstanterrorwasdetermined tobe.non-conservative by0.6348RTP.Twoadditional discrepancies, unrelated tothe1996modification, werealsodiscovered inthecalorimetric calibration andweredetermined toresultinacombinedconservative errorof0.2%RTP.Therefore, thenetcalorimetric errorwas0.43%non-conservative.
| | 5)I&C performed a three point calibration of all DDPS calorimetric inputs to verify the proper scaling constants and input circuit operation. |
| Anoperability assessment wasperformed whichdetermined thatthefeedwaterflowscalingdiscrepancy combinedwiththecalorimetric measurement unertaintywaslessthantherequiredoverallcalorimetric accuracyrequirement of2%atmaximumratedthermalpower.Inaddition, reactorprotection, corephysics,andreactorfuelparameters impactedbythecalorimetric errorwereevaluated toensurethatassumptions madeintheplantsafetyanalysisprovidedsufficient margintoboundthisevent.Thisevaluation concluded thattheexistingplantsafetyanalysisremainsvalid.Therefore, thehealthandsafetyofthepublicwerenotadi>>elyaffectedbythisevent.NRCFoRM388A(4-96I NRCFORM3SBAI4-96)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIST.LUCIEUNIT105000335YEARSEQUENTIAL REVISION97-002-004OF5TEXT(ifmorespeceisrequired, useedditionel copiesofIVRCForm368AiI17)Facilityoperation waslimitedtoaconservative valueof99%RTPuntiltheproblemwasthoroughly investigated andcorrected.
| | Minor discrepancies were identified in the feed water Resistance Temperature Detector and Reactor Coolant Pump KW scaling curves that were not related to the event reported in this LER.Engineering determined that these discrepancies accounted for a combined conservative error of 0.2%.FPL will revise the software to correct these errors in the St.Lucie Unit 1 DDPS.The scaling curves for these components were also verified in the St.Lucie Unit 2 DDPS to ensure that similar discrepancies did not exist.6)To ensure adequate post modification testing is performed, FPL will review software modification accountabilities and identify program improvements to be made.7)FPL will develop generic V&V requirements to challenge all critical attributes within both St.Lucie Unit 1 and Unit 2 DDPS for all software changes.8)Controlled operating procedures will be developed to address both St.Lucie Unit 1 and Unit 2 DDPS operation and identify specific point identification and locations. |
| Primarysystemmanualcalorimetric calculations wereperformed toverifyreactorpowerremainedbelow100%RTP.2)Thecorrectfeedwaterflowscalingconstants wereenteredintoboththeon-lineandtheback-upDDPScomputers, andothercalorimetric constants wereverifiedtobecorrectusinginformation frotheplantTotalEquipment DataBase(TEDB).Theincreaseincalculated calorimetric powershownontheDDPSdisplaywasverifiedtobeaspredicted.
| | 9)FPL will ensure configuration control for all critical St.Lucie Unit 1 and Unit 2 DDPS constants by entering them into the TEDB or ensuring they are documented in a controlled procedure. |
| Aprimarysystemmanualcalorimetric calculation wasperformed andresultswerewithin0.2%ofDDPSindicated power.3)Thecorrectfeedwaterflowscalingconstants weredocumented, andmaster/backup copiesoftheupgradedsystemwerefiledinaccordance withanapprovedSt..LuciePlantSoftwareConfiguration/Change Control,ComputerSoftwareChangeRequest(Administrative Procedure 4000060,Revision2).Acceptable performance ofothercriticalDDPSfunctions wasverifiedtoensurethatotherinadvertent softwarechangeshadnotbeenmade,andsurveillances wereperformed forotherplantsystemswhosecalibrations canbeinfluenced byDDPScalculated calorimetric powertoensurethatthesesystemcalibrations hadnotbeencompromised.
| | 10)FPL's blanket purchase order with the software rendor has been modified to clarify that development of new software and upgrading/changing existing software shall be per FPL's Administrative Procedure AP-4000060. |
| 5)I&Cperformed athreepointcalibration ofallDDPScalorimetric inputstoverifytheproperscalingconstants andinputcircuitoperation. | | NAC FORM 388A I4-96I NRC FORIN 388A I4-95),LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUcLEAR REGULATORY colNMISSIO ST.LUCIE UNIT 1 YEAR SEQUENTIAL REVISION 05000335 97-002-00 5 OF 5 TEXT (If more space is required, use additional copies of NRC Form 366AI l17I None LER 335/86-005, St.Lucie Unit 1, Technical Specification Deviation Due to Personnel Error, 07/21/86.LER 389/92-008, St.Lucie Unit 2, Digital Data Process System Calorimetric Error due to Instrument Calibration Error, Revision 1, 03/31/93.NAC FoAM 388A I4-96) |
| Minordiscrepancies wereidentified inthefeedwaterResistance Temperature DetectorandReactorCoolantPumpKWscalingcurvesthatwerenotrelatedtotheeventreportedinthisLER.Engineering determined thatthesediscrepancies accounted foracombinedconservative errorof0.2%.FPLwillrevisethesoftwaretocorrecttheseerrorsintheSt.LucieUnit1DDPS.Thescalingcurvesforthesecomponents werealsoverifiedintheSt.LucieUnit2DDPStoensurethatsimilardiscrepancies didnotexist.6)Toensureadequatepostmodification testingisperformed, FPLwillreviewsoftwaremodification accountabilities andidentifyprogramimprovements tobemade.7)FPLwilldevelopgenericV&Vrequirements tochallenge allcriticalattributes withinbothSt.LucieUnit1andUnit2DDPSforallsoftwarechanges.8)Controlled operating procedures willbedeveloped toaddressbothSt.LucieUnit1andUnit2DDPSoperation andidentifyspecificpointidentification andlocations.
| |
| 9)FPLwillensureconfiguration controlforallcriticalSt.LucieUnit1andUnit2DDPSconstants byenteringthemintotheTEDBorensuringtheyaredocumented inacontrolled procedure. | |
| 10)FPL'sblanketpurchaseorderwiththesoftwarerendorhasbeenmodifiedtoclarifythatdevelopment ofnewsoftwareandupgrading/changing existingsoftwareshallbeperFPL'sAdministrative Procedure AP-4000060. | |
| NACFORM388AI4-96I NRCFORIN388AI4-95),LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUcLEARREGULATORY colNMISSIO ST.LUCIEUNIT1YEARSEQUENTIAL REVISION0500033597-002-005OF5TEXT(Ifmorespaceisrequired, useadditional copiesofNRCForm366AIl17INoneLER335/86-005, St.LucieUnit1,Technical Specification Deviation DuetoPersonnel Error,07/21/86.
| |
| LER389/92-008, St.LucieUnit2,DigitalDataProcessSystemCalorimetric ErrorduetoInstrument Calibration Error,Revision1,03/31/93.
| |
| NACFoAM388AI4-96)
| |
| I}} | | I}} |
|
|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
ML17229A7381998-05-21021 May 1998
LER 98-006-00:on 980421,missed EDG Fuel Oil Sample Surveillance Was Noted.Caused by Personnel Error.Revised Fuel Oil Sampling Service Purchase Order & Revised Site procedure.W/980521 Ltr
ML17229A7011998-04-27027 April 1998
LER 98-003-00:on 980326,discovered Containment Pressure Instrumentation Design Single Failure Vulnerability.Caused by Inadequate Design by Personnel Error.Removed RPS & ESFAS Containment Pressure Bypass Keys immediately.W/980427 Ltr
ML17229A6761998-04-0202 April 1998
LER 98-005-00:on 980305,identified Two Conditions That Were Outside App R Design Bases.Caused by Design Oversight During Development of Original App R Safe SD Design.Established 30 Minute Roving Fire Watches & Provided training.W/980402 Ltr
ML17229A6731998-03-26026 March 1998
LER 98-002-00:on 980224,radiation Monitor Surveillance Inadequacies Led to Operating of Facility Prohibited by Tss. Caused by Congnitive Personnel Error.Permanent Procedure Changes Were implemented.W/980326 Ltr
ML17229A6551998-03-0505 March 1998
LER 98-001-00:on 980206,high/low Pressure Shutdown Cooling Interface Was Noted Outside App R Design Bases.Caused by Personnel Error.Addl Guidance Was Provided to Engineering Dept personnel.W/980305 Ltr
ML17229A6281998-02-19019 February 1998
LER 98-004-00:on 980121,emergency Lighting Outside App R Design Bases Occurred.Caused by Congnitive Personnel Error During Translation of App R Section Iii.Procedures Onop 1 & 2 ONP-100.01 Were Issued for Use on 980206.W/980219 Ltr
ML17229A6211998-02-0909 February 1998
LER 98-003-00:on 980110,manual Rt Due to DEH Leak at Turbine Test Block Was Noted.Caused by o-ring Extrusion.Shortened Bolts by About 0.125 & Reinstalled at Correct Torque values.W/980209 Ltr
ML17229A6191998-02-0404 February 1998
LER 98-002-00:on 980105,CIS Bistable in Bypass Resulted in Condition Prohibited by Tss.Caused by Personnel Error. Radiation Monitor Was Restored to service.W/980204 Ltr
ML17229A6161998-02-0303 February 1998
LER 98-001-00:on 980104,inadvertent RPS Actuation Occurred Due to Personnel Error.Caused by Procedural Inadequacies & Inadequate self-checking by Licensed Utility Personnel. Placards Have Been Placed in CRs.W/980203 Ltr
ML17229A6051998-01-27027 January 1998
LER 97-010-01:on 971027,inadvertent Core Alteration Prohibited by TSs Were Noted Due to Stuck Cea.Caused by Personnel Error.Cea #24 Was Dislodged & Transferred to Spent Pool for insp.W/980127 Ltr
ML17229A5501997-12-0505 December 1997
LER 97-008-00:on 971107,inadequate CR Ventilation Surveillance Resulted in Condition Prohibited by Ts.Caused by non-cognitive Personnel Error.Operating Procedure 2-1900050 Was revised.W/971205 Ltr
ML17309A9091997-12-0202 December 1997
LER 97-011-00:on 971102,non-conservative RAS Set Point Resulted in Operation Prohibited by Ts.Caused by Inadequate Set Point & Instrument Loop Scaling Process.Revised ESFAS Functional Tp W/Proper Set point.W/971202 Ltr
ML17229A5391997-11-26026 November 1997
LER 97-010-00:on 971027,inadvertant Core Alteration Prohibited by TS Occurred.Caused by CEA Failure to Detach from Ugs.Safety Evaluation Was Performed & Procedural Rev Made to Continue Upper Guide Structure move.W/971126 Ltr
ML17229A5151997-11-0707 November 1997
LER 97-007-00:on 971008,inoperable Containment Cooling Fan Resulted in Operation of Facility Outside Design Basis. Caused by non-cognitive Personnel Error.Ccs Operation Was Revised & Issued on 971013.W/971107 Ltr
ML17229A4991997-10-17017 October 1997
LER 97-009-00:on 970917,inoperable PORV Block Valve Resulted in Operation Prohibited by Tech Specs Occurred.Caused by Plant GL 89-10 Program Plan to Review Plant Manager Action Item Sys.Porv Block Valve V-1403 restored.W/971017 Ltr
ML17309A9011997-08-27027 August 1997
LER 97-008-00:on 970728,mechanical Fire Penetrations Were Inoperable & Outside App R Design Bases.Caused by Seal Mfg Not Providing Formal Documentation for Installed Seals. Modified Inoperable Fire penetrations.W/970827 Ltr
ML17229A4311997-07-29029 July 1997
LER 97-006-00:on 970630,discovered Inadequate Testing of Engineered Safety Features Subgroup Relays.Caused by Inadequacy in Implementing TS Requirements in Surveillance Procedures.Revised Surveillance procedures.W/970729 Ltr
ML17229A4241997-07-25025 July 1997
LER 97-005-00:on 970625,discovered That Hot Shutdown Control Panel Shutdown Cooling Flow indicator,FI-3306 Inoperable. Caused by Weakness in Work Order & Procedure Used to Repair FI-3306.Section Meeting W/I&C Planners held.W/970725 Ltr
ML17229A3971997-07-11011 July 1997
LER 97-004-00:on 970611,discovered Incorrect Original Cable Tray Fire Stop Assembly Installation Was Outside App R Design Basis.Caused by Personnel Error.Hourly Fire Watch Patrols Will Be posted.W/970711 Ltr
ML17229A3871997-06-19019 June 1997
LER 97-003-00:on 970521,determined Required Post Maint Open Stroke Test for Valve V3245,2B2 SIT Discharge Check Valve, Had Not Been Performed.Caused by Personnel Error.Procedure revised.W/970619 Ltr
ML17229A3841997-06-17017 June 1997
LER 97-002-00:on 970518,containment Sump Debris Screen Was Not IAW Design Due to Gaps in Screen Encl.Performed SER to Document Containment Sump Design requirements.W/970617 Ltr
ML17229A3751997-06-0202 June 1997
LER 97-006-00:on 970501,operation Was Prohibited by TS Due to Inadequately Tested Degraded Voltage Sys.Revised Unit 1 ESFAS Surveillance Test procedure.W/970602 Ltr
ML17229A3611997-05-29029 May 1997
LER 97-007-00:on 970502,reactor Coolant Pump Oil Collection Sys Was Outside App R Design Bases.Identified Leak Sites Were Repaired & Mods to RCP Oil Collection Sys to Capture Any Future Leakage from areas.W/970529 Ltr
ML17229A3491997-05-21021 May 1997
LER 97-001-00:on 970423,containment Isolation Actuation Occurred.Caused by Increased Radiation Levels During Removal of Upper Guide Structure.Proper Actuation of Containment Isolation Components Was verified.W/970521 Ltr
ML17229A3441997-05-13013 May 1997
LER 97-005-00:on 970419,reactor Was Shutdown Due to Reactor Coolant Pressure Boundary Leakage.Hot Cracking Was Caused by Weld Contamination.Repairs to RCPB Were Completed & 1A SDC Train Was Restored to Svc
ML17229A3141997-04-30030 April 1997
LER 97-004-00:on 970402,refueling Machine Was Operating in Manner Prohibited by TS Due to Original Design of Refueling Machine Bypass Feature Conflicting W/Ts Requirements. Eliminated Overload Cut Off Limit bypass.W/970430 Ltr
ML17229A2951997-03-31031 March 1997
LER 97-003-00:on 970304,automatic Rt Resulted from Loss of Electrical Power to 1A2 Rc Pump.Rcp Breaker Was Replaced & Pump Was Returned to svc.W/970331 Ltr
ML17229A2721997-03-21021 March 1997
LER 97-002-00:on 970221,operation in Excess of Max Rated Thermal Power Occurred Due to Digital Data Processing Sys (Ddps) Calorimetric Error.Verified Acceptable Performance of Ddps Functions & Reviewed Software mods.W/970321 Ltr
1999-07-06
[Table view]
Category:RO)
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
ML17229A7381998-05-21021 May 1998
LER 98-006-00:on 980421,missed EDG Fuel Oil Sample Surveillance Was Noted.Caused by Personnel Error.Revised Fuel Oil Sampling Service Purchase Order & Revised Site procedure.W/980521 Ltr
ML17229A7011998-04-27027 April 1998
LER 98-003-00:on 980326,discovered Containment Pressure Instrumentation Design Single Failure Vulnerability.Caused by Inadequate Design by Personnel Error.Removed RPS & ESFAS Containment Pressure Bypass Keys immediately.W/980427 Ltr
ML17229A6761998-04-0202 April 1998
LER 98-005-00:on 980305,identified Two Conditions That Were Outside App R Design Bases.Caused by Design Oversight During Development of Original App R Safe SD Design.Established 30 Minute Roving Fire Watches & Provided training.W/980402 Ltr
ML17229A6731998-03-26026 March 1998
LER 98-002-00:on 980224,radiation Monitor Surveillance Inadequacies Led to Operating of Facility Prohibited by Tss. Caused by Congnitive Personnel Error.Permanent Procedure Changes Were implemented.W/980326 Ltr
ML17229A6551998-03-0505 March 1998
LER 98-001-00:on 980206,high/low Pressure Shutdown Cooling Interface Was Noted Outside App R Design Bases.Caused by Personnel Error.Addl Guidance Was Provided to Engineering Dept personnel.W/980305 Ltr
ML17229A6281998-02-19019 February 1998
LER 98-004-00:on 980121,emergency Lighting Outside App R Design Bases Occurred.Caused by Congnitive Personnel Error During Translation of App R Section Iii.Procedures Onop 1 & 2 ONP-100.01 Were Issued for Use on 980206.W/980219 Ltr
ML17229A6211998-02-0909 February 1998
LER 98-003-00:on 980110,manual Rt Due to DEH Leak at Turbine Test Block Was Noted.Caused by o-ring Extrusion.Shortened Bolts by About 0.125 & Reinstalled at Correct Torque values.W/980209 Ltr
ML17229A6191998-02-0404 February 1998
LER 98-002-00:on 980105,CIS Bistable in Bypass Resulted in Condition Prohibited by Tss.Caused by Personnel Error. Radiation Monitor Was Restored to service.W/980204 Ltr
ML17229A6161998-02-0303 February 1998
LER 98-001-00:on 980104,inadvertent RPS Actuation Occurred Due to Personnel Error.Caused by Procedural Inadequacies & Inadequate self-checking by Licensed Utility Personnel. Placards Have Been Placed in CRs.W/980203 Ltr
ML17229A6051998-01-27027 January 1998
LER 97-010-01:on 971027,inadvertent Core Alteration Prohibited by TSs Were Noted Due to Stuck Cea.Caused by Personnel Error.Cea #24 Was Dislodged & Transferred to Spent Pool for insp.W/980127 Ltr
ML17229A5501997-12-0505 December 1997
LER 97-008-00:on 971107,inadequate CR Ventilation Surveillance Resulted in Condition Prohibited by Ts.Caused by non-cognitive Personnel Error.Operating Procedure 2-1900050 Was revised.W/971205 Ltr
ML17309A9091997-12-0202 December 1997
LER 97-011-00:on 971102,non-conservative RAS Set Point Resulted in Operation Prohibited by Ts.Caused by Inadequate Set Point & Instrument Loop Scaling Process.Revised ESFAS Functional Tp W/Proper Set point.W/971202 Ltr
ML17229A5391997-11-26026 November 1997
LER 97-010-00:on 971027,inadvertant Core Alteration Prohibited by TS Occurred.Caused by CEA Failure to Detach from Ugs.Safety Evaluation Was Performed & Procedural Rev Made to Continue Upper Guide Structure move.W/971126 Ltr
ML17229A5151997-11-0707 November 1997
LER 97-007-00:on 971008,inoperable Containment Cooling Fan Resulted in Operation of Facility Outside Design Basis. Caused by non-cognitive Personnel Error.Ccs Operation Was Revised & Issued on 971013.W/971107 Ltr
ML17229A4991997-10-17017 October 1997
LER 97-009-00:on 970917,inoperable PORV Block Valve Resulted in Operation Prohibited by Tech Specs Occurred.Caused by Plant GL 89-10 Program Plan to Review Plant Manager Action Item Sys.Porv Block Valve V-1403 restored.W/971017 Ltr
ML17309A9011997-08-27027 August 1997
LER 97-008-00:on 970728,mechanical Fire Penetrations Were Inoperable & Outside App R Design Bases.Caused by Seal Mfg Not Providing Formal Documentation for Installed Seals. Modified Inoperable Fire penetrations.W/970827 Ltr
ML17229A4311997-07-29029 July 1997
LER 97-006-00:on 970630,discovered Inadequate Testing of Engineered Safety Features Subgroup Relays.Caused by Inadequacy in Implementing TS Requirements in Surveillance Procedures.Revised Surveillance procedures.W/970729 Ltr
ML17229A4241997-07-25025 July 1997
LER 97-005-00:on 970625,discovered That Hot Shutdown Control Panel Shutdown Cooling Flow indicator,FI-3306 Inoperable. Caused by Weakness in Work Order & Procedure Used to Repair FI-3306.Section Meeting W/I&C Planners held.W/970725 Ltr
ML17229A3971997-07-11011 July 1997
LER 97-004-00:on 970611,discovered Incorrect Original Cable Tray Fire Stop Assembly Installation Was Outside App R Design Basis.Caused by Personnel Error.Hourly Fire Watch Patrols Will Be posted.W/970711 Ltr
ML17229A3871997-06-19019 June 1997
LER 97-003-00:on 970521,determined Required Post Maint Open Stroke Test for Valve V3245,2B2 SIT Discharge Check Valve, Had Not Been Performed.Caused by Personnel Error.Procedure revised.W/970619 Ltr
ML17229A3841997-06-17017 June 1997
LER 97-002-00:on 970518,containment Sump Debris Screen Was Not IAW Design Due to Gaps in Screen Encl.Performed SER to Document Containment Sump Design requirements.W/970617 Ltr
ML17229A3751997-06-0202 June 1997
LER 97-006-00:on 970501,operation Was Prohibited by TS Due to Inadequately Tested Degraded Voltage Sys.Revised Unit 1 ESFAS Surveillance Test procedure.W/970602 Ltr
ML17229A3611997-05-29029 May 1997
LER 97-007-00:on 970502,reactor Coolant Pump Oil Collection Sys Was Outside App R Design Bases.Identified Leak Sites Were Repaired & Mods to RCP Oil Collection Sys to Capture Any Future Leakage from areas.W/970529 Ltr
ML17229A3491997-05-21021 May 1997
LER 97-001-00:on 970423,containment Isolation Actuation Occurred.Caused by Increased Radiation Levels During Removal of Upper Guide Structure.Proper Actuation of Containment Isolation Components Was verified.W/970521 Ltr
ML17229A3441997-05-13013 May 1997
LER 97-005-00:on 970419,reactor Was Shutdown Due to Reactor Coolant Pressure Boundary Leakage.Hot Cracking Was Caused by Weld Contamination.Repairs to RCPB Were Completed & 1A SDC Train Was Restored to Svc
ML17229A3141997-04-30030 April 1997
LER 97-004-00:on 970402,refueling Machine Was Operating in Manner Prohibited by TS Due to Original Design of Refueling Machine Bypass Feature Conflicting W/Ts Requirements. Eliminated Overload Cut Off Limit bypass.W/970430 Ltr
ML17229A2951997-03-31031 March 1997
LER 97-003-00:on 970304,automatic Rt Resulted from Loss of Electrical Power to 1A2 Rc Pump.Rcp Breaker Was Replaced & Pump Was Returned to svc.W/970331 Ltr
ML17229A2721997-03-21021 March 1997
LER 97-002-00:on 970221,operation in Excess of Max Rated Thermal Power Occurred Due to Digital Data Processing Sys (Ddps) Calorimetric Error.Verified Acceptable Performance of Ddps Functions & Reviewed Software mods.W/970321 Ltr
1999-07-06
[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
CATEGORY REGULAT55f INFORMATION DISTRIBUTIO YSTEM (RIDS)ACCESSION NBR:9703270101 DOC."DATE:
97/03/21 NOTARIZED:
NO FACIL SO-'33'5 St.Lucie Plant, Unit 1, Florida Power 6 Light.Co.AUTH.NAME AUTHOR AFFILIATION DIETZ,R.L.
Florida Power a Light Co.STALL,J.A.
Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION"DOCKET 05000335
SUBJECT:
LER 97-002-00:on 970221,operation in excess of max Rated Thermal Power occurredy failure to implement effective configuration for Digital Data Processing Sys computer DZSTRZBUTZON CODE: ZE22T COPZES RECEZUED:LTR
)ENCL t SZZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD2-3 PD INTERNAL: ACRS AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB EXTERNAL: L ST LOBBY WARD NOAC POOREPW.NRC PDR COPIES, LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1~-1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME WIENSPL.B IL CENTER N NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN2 FILE 01 LITCO BRYCE,J H.NOAC QUEENERPDS NUDOCS FULL TXT COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 N NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25 a Florida Power&Light Company, 6501 South Ocean Drive, Jensen Beach, FL34957 APL MAR 2)1997 L-97-081 10 CFR 50.73 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Re: St.Lucie Unit 1 Docket 50-335 Reportable Event: 97-002 Date of Event: February 21, 1997 Operation in Excess of Maximum Rated Thermal Power The attached Licensee Event Report is a voluntary report submitted to provide notification of the subject event.Very truly yours,'I J.A.Stall Vice President St.Lucie Plant JAS/RLD Attachment cc: Regional Administrator, USNRC Region II Senior Resident Inspector, USNRC, St.I.ucie Plant'703270iOi 97032X PDR ADGCK 05000335 8 PDR lllgttlllElllPiHillttltl an FPL Group company NRC FORM 366 (4-as)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters for each block)APPROVED SY OMS NO.S)50%105 EXPIRES 05QOISS ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MAHDAT INFORMATION COILECTIOH REQUEST: 50.0 HRS.REPORTED LESSON LEARNED ARE INCORPORATED INTO THE UCENSINO PROCESS AND SACK TO SE)USIRY.FORWAIE)COMM BITS REOARDIHO BURDEN ESTIMA TO THE INFORMATION AND RECORDS MANAOEMEHT BRANCH IT%F33)UW NUCLEAR REOIAATORY COMMISSION, WASHINOTON, DC 20555400)AND TO THE PAPERWORK REDUCTION PROJECT 131500)04), OFHCE 0 MANAOEMENT AND BUDGET, WASHIHOTON, DC 20503.PAcIUTY NAME l1)TITlE Ia)ST.LUCIE UNIT 1 DocKET NLssBER l2)05000335 PAOE IS)1 OF 5 Operation in Excess of Maximum Rated Thermal Power Due to Digital Data Processor Calorimetric Error MONTH DAY SEQUENTIAL REV)SION NUMBER NUMBER MONTH DAY YEAR FACIUTY NAME NIA DOCKET NUMBER 02 21 OPERATING MODE (9)LEVEL (10)97 97-002-00 20.2201 (b)20.2203(a)(2)(I) 20.2203(a)(2)(ill)20.2203(e)(2)(iv) 03 21 97 20.2203(e)(2)(v)20.2203(a)(3)(ii) 50.3B(o)(1) 60.3B(c)(2)
FACIUTY NAME NIA 50.73(e)(2)(I)50.73(a)(2)(ill) 50.73(e)(2)(v) 50.73(a)(2)(vli)DOCKET NUMBER 50.73(e)(2)(vlii) 73.71 OTHER Specify In Abstract below or In NRC Form 3SSA NAME R,L.DIETZ, Licensing Engineer TELEPHONE NUMBER Onckde Arse Code)(561)467-7157 cAusE SYSTEM COMPONENT MANUFACTURER To NPRDS CAUSE SYSTEM COMPONENT MANUFACTURER To NPRDS YES (If yes, complete EXPECTED SUBMISSION DATE): X No MONTH DAY YEAR SUBMISSION DATE (16)ABSTRACT (L(mit to 1400 spaces, I.e., approximately 15 single-spaced typewritten lines)(16)This LER is a voluntary report.On February 21, 1997, St.Lucie Unit 1 was operating at a steady-state power level of 100%Rated Thermal Power (RTP)as determined from the Digital Data Processing System (DDPS)display.While performing a feed water flow instrument loop calibration, maintenance personnel determined that proper scaling constants were not being used for the feed water flow input signals to the DDPS.This condition caused the DDPS calorimetric calculation of reactor core thermal power to be non-conservative in that facility steady-state operation with the DDPS indicating 100%RTP resulted in actual reactor power at 100A3%RTP.Plant operation was limited to not more than 99%RTP (indicated) while the problem was thoroughly investigated and corrected.
On March 1, 1997, St.Lucie Unit 1 was returned to 100%RTP.The cause of this event was failure to implement effective configuration controls for the DDPS computer software.Corrective actions include: 1)Acceptable performance of all critical DDPS functions was verified prior to restoration of full power operations.
2)Review of accountabilities for software modifications and identification of program improvements.
3)Development of verification and validation requirements that challenge all critical attributes for software changes within the DDPS.4)Development of controlled operating procedures to address DDPS operation.
5)Use of the St.Lucie Total Equipment Data Base or controlled procedures to ensure configuration control of critical DDPS constants.
6)Modification of the software vendor blanket purchase order to clarify that compliance with FPL administrative procedures is required.NRC FORM 3SS (4.SS)
NRC FORM 388A I4.9SI LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSIO ST.LUCIE UNIT 1 05000335 YEAR SEQUENTIAL REVISION 97-002-00 2 OF 5 TEXT iif more space is required, use additional copies of NRC Arm 3684I l17I On February 21, 1997, St.Lucie Unit 1 was operating at a steady-state power level of 100%Rated Thermal Power (RTP)as determined from the Digital Data Processing System (DDPS)[EIIS:IO]display.Utility Instrumentation and Control (ILC)personnel were performing a feed water flow instrument loop calibration following maintenance on a feed water flow transmitter
[EIIS:SJ:PDT].
During this calibration, it was discovered that scaling constants for all six of the feed water flow input signals to the DDPS computer[EIIS:IO:CPU]
were incorrect, i.e., the input signal range of 4-20 milliamperes corresponded to a flow venturi[EIIS:SJ:FE]
differential pressure span of approximately 0-790 inches of water rather than the correct span of 0-800 inches of water.Since the DDPS uses the feed water flow parameter in calorimetric calculations of reactor[EIIS:RCT]
core thermal power, this discrepancy was non-conservative in that scaling constants corresponding to less than the full range of flow venturi differential pressures result in a calculated value of power that is less than the actual reactor output.Control room operators were notified by ILC personnel that the reactor was operating at a core thermal power level approximately 0.6%RTP greater than the value displayed on the DDPS, and action was promptly initiated to reduce power.At 17:55 EST on February 21, 1997, St.Lucie Unit 1 was stabilized at a conservative value of 99%RTP (indicated).
The unit was returned to 100%RTP at 05:45 EST on March 1, 1997.In June, 1994, feed water flow scaling constants were revised in accordance with approved plant procedures.
These scaling constants were properly installed into the operating DDPS software, but were not updated in the control room DDPS data reference manual.In 1996, the software was modified by the vendor using the vendor's version of the source code to accommodate installation of a new core performance monitor that interfaces with the DDPS.When this modification was loaded into the DDPS computer during the 1996 refueling outage, the proper scaling constants were overwritten and replaced with the pre-1994 values based on the control room DDPS data reference manual.This condition was not discovered until the instrument loop calibration was performed on February 21, 1997.The cause of this event was failure to implement effective configuration controls for the DDPS computer software.ln June 1994, a change to the span/static shift adjustment for each of the six DDPS feed water flow transmitters was implemented in accordance with an approved plant work order.To be compatible with the span adjustments, the existing feed water flow scaling constants corresponding to a span of 0-790.6 inches of water'differential pressure were revised to correspond to a span of 0-800 inches of water differential pressure.The new scaling constants were loaded into the correct DDPS operating software locations, but were not recorded in the control room DDPS data reference manual which is maintained at the DDPS console.NRC FORM mA Ii-95I
NRC FORM 386A I4.96)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REOULATORY COMMISSIO ST.LUCIE UNIT 1 05000335 YEAR SEQUENTIAL REVISION 97-002-00 3 OF 5 TEXT/if more specs is reriuired, use edditionel copies of NRC.cform 36EAI I 17)The DDPS software is considered quality related.At the time the 1994 revision was made to the feed water flow scaling constants, Ql 2-PR/PSL-3, Revision 0, Control of Computer Software, provided generic administrative controls for computer software in which the output is used for safety related and quality related purposes.Significant revisions to strengthen this procedure have been made since 1994.During the refueling outage of April-July, 1996, an on-line core'performance monitoring system which interfaces with the DDPS was installed in accordance with an approved Plant Change/Modification (PC/M).The DDPS software changes needed to accommodate this new installation were developed by the vendor using the vendor's version of the source code (which did not contain the 1994 revised scaling constants).
Upon loading the modified software into the DDPS computer, the correct feed water flow constants were overwritten with those corresponding to a range of 0-790.6 inches of water differential pressure.Administrative Procedure (AP)4000060, Maintenance Departmental Control of Computer Software, was implemented February 26, 1996, to provide the methodology by which the maintenance department and support groups control the procurement, development, and revision of software to comply with Ql 2-PR/PSL-3.The validation and verification (V&V)method that was used to confirm the DDPS proper software configuration following modifications to accommodate the 1996 PC/M was selected from this procedure, but did not V&V other functions of the software, such as the calorimetric calculation, that were not related to the modification.
During post modification testing (PMT)for the 1996 PC/M, the control room copy of the DDPS data reference manual was used to perform a verification of each DDPS input constant.However, this manual is not a controlled document and had not been updated to reflect the 1994 revision to the feed water flow scaling constants.
This prevented discovery of the problem at that time, i.e., the values used to verify the feed water flow scaling constants were the same pre-1994 values as those residing in the software that had been loaded into the DDPS computer from the vendor source code, The feed water flow scaling constant error was determined to be.non-conservative by 0.6348 RTP.Two additional discrepancies, unrelated to the 1996 modification, were also discovered in the calorimetric calibration and were determined to result in a combined conservative error of 0.2%RTP.Therefore, the net calorimetric error was 0.43%non-conservative.
An operability assessment was performed which determined that the feed water flow scaling discrepancy combined with the calorimetric measurement un ertainty was less than the required overall calorimetric accuracy requirement of 2%at maximum rated thermal power.In addition, reactor protection, core physics, and reactor fuel parameters impacted by the calorimetric error were evaluated to ensure that assumptions made in the plant safety analysis provided sufficient margin to bound this event.This evaluation concluded that the existing plant safety analysis remains valid.Therefore, the health and safety of the public were not adi>>ely affected by this event.NRC FoRM 388A (4-96I NRC FORM 3SBA I4-96)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSI ST.LUCIE UNIT 1 05000335 YEAR SEQUENTIAL REVISION 9 7-002-00 4 OF 5 TEXT (if more speceis required, use edditionel copies of IVRC Form 368Ai I17)Facility operation was limited to a conservative value of 99%RTP until the problem was thoroughly investigated and corrected.
Primary system manual calorimetric calculations were performed to verify reactor power remained below 100%RTP.2)The correct feed water flow scaling constants were entered into both the on-line and the back-up DDPS computers, and other calorimetric constants were verified to be correct using information fro the plant Total Equipment Data Base (TEDB).The increase in calculated calorimetric power shown on the DDPS display was verified to be as predicted.
A primary system manual calorimetric calculation was performed and results were within 0.2%of DDPS indicated power.3)The correct feed water flow scaling constants were documented, and master/backup copies of the upgraded system were filed in accordance with an approved St..Lucie Plant Software Configuration/Change Control, Computer Software Change Request (Administrative Procedure 4000060, Revision 2).Acceptable performance of other critical DDPS functions was verified to ensure that other inadvertent software changes had not been made, and surveillances were performed for other plant systems whose calibrations can be influenced by DDPS calculated calorimetric power to ensure that these system calibrations had not been compromised.
5)I&C performed a three point calibration of all DDPS calorimetric inputs to verify the proper scaling constants and input circuit operation.
Minor discrepancies were identified in the feed water Resistance Temperature Detector and Reactor Coolant Pump KW scaling curves that were not related to the event reported in this LER.Engineering determined that these discrepancies accounted for a combined conservative error of 0.2%.FPL will revise the software to correct these errors in the St.Lucie Unit 1 DDPS.The scaling curves for these components were also verified in the St.Lucie Unit 2 DDPS to ensure that similar discrepancies did not exist.6)To ensure adequate post modification testing is performed, FPL will review software modification accountabilities and identify program improvements to be made.7)FPL will develop generic V&V requirements to challenge all critical attributes within both St.Lucie Unit 1 and Unit 2 DDPS for all software changes.8)Controlled operating procedures will be developed to address both St.Lucie Unit 1 and Unit 2 DDPS operation and identify specific point identification and locations.
9)FPL will ensure configuration control for all critical St.Lucie Unit 1 and Unit 2 DDPS constants by entering them into the TEDB or ensuring they are documented in a controlled procedure.
10)FPL's blanket purchase order with the software rendor has been modified to clarify that development of new software and upgrading/changing existing software shall be per FPL's Administrative Procedure AP-4000060.
NAC FORM 388A I4-96I NRC FORIN 388A I4-95),LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUcLEAR REGULATORY colNMISSIO ST.LUCIE UNIT 1 YEAR SEQUENTIAL REVISION 05000335 97-002-00 5 OF 5 TEXT (If more space is required, use additional copies of NRC Form 366AI l17I None LER 335/86-005, St.Lucie Unit 1, Technical Specification Deviation Due to Personnel Error, 07/21/86.LER 389/92-008, St.Lucie Unit 2, Digital Data Process System Calorimetric Error due to Instrument Calibration Error, Revision 1, 03/31/93.NAC FoAM 388A I4-96)
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