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| {{#Wiki_filter:ACCEIERDDOCUMENTDISIBVTIONSYSTEMREGULRYINFORMATION DISTRIBUT SYSTEM(RIDS)ACCESSION NBR:9302110293 DOC.DATE: | | {{#Wiki_filter:ACCEI ER D DOCUMENT DIS IBVTION SYSTEM REGUL RY INFORMATION DISTRIBUT SYSTEM (RIDS)ACCESSION NBR:9302110293 DOC.DATE: 93/02/05 NOTARIZED: |
| 93/02/05NOTARIZED: | | NO FACIL:50-389 St.Lucie Plant, Unit 2, Florida Power&Light Co.AUTH.NAME AUTHOR AFFILIATION HURCHALLA,J.A. |
| NOFACIL:50-389 St.LuciePlant,Unit2,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIATION HURCHALLA,J.A.
| | Florida Power E Light Co.SAGER,D.A. |
| FloridaPowerELightCo.SAGER,D.A.
| | -Florida Power 6 Light Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000389 |
| -FloridaPower6LightCo.RECIP.NAME RECIPIENT AFFILIATION DOCKET05000389 | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER93-001-00:on 930108,chemistry technician failedtosamplethirdSItank6samplingofSItank2A1notperformed withinTSrequiredintervalafterfillingtank.Causedbypersonnel error.Personnel counseled.W/930205 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR gENCLgSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER)-,IncidentRpt,etc.NOTES:RECiPIENT IDCODE/NAME PD2-2LANORRIS,JINTERNAL:
| | LER 93-001-00:on 930108,chemistry technician failed to sample third SI tank 6 sampling of SI tank 2A1 not performed within TS required interval after filling tank.Caused by personnel error.Personnel counseled.W/930205 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR g ENCL g SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER)-, Incident Rpt, etc.NOTES: RECiPIENT ID CODE/NAME PD2-2 LA NORRIS,J INTERNAL: ACNW AEOD/DOA.AEOD/ROAB/DSP NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8D NR~SPLB8Dl REG FILE 02 GN2~LE 01 EXTERNAL: EGErG BRYCE,J.H NRC PDR NSIC POORE,W.COPIES LTTR ENCL 1 1 1 1 2 2 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2 PD ACRS AEOD/DSP/TPAB NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB8H3 NRR/DST/SRXB 8E RES/DSIR/EIB L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT COPIES LTTR ENCL 1-1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 R NOTE TO ALL"RIDS" RECIPIENTS: |
| ACNWAEOD/DOA.
| | PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!L S FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 P.O.Box 128, Ft.Pierce, FL 3o954-0128 February 5, 1993 L-'93-30 10 CFR 50.73 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Re: St.Lucie Unit 2 Docket No.50-389 Reportable Event: 93-001 Date of Event: January 8, 1993 Missed Surveillance for Safety In ection Tank Sam lin Due to Personnel Error The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.Very truly yours, D.A.S Vice P St.Lu ger sident e Plant DAS/JWH/kw Attachment cc: Stewart D.Ebneter, Regional Administrator, USNRC Region II.Senior Resident, Inspector, USNRC, St.Lucie Plant DAS/PSL N857-93 3.00042 9302110293 930205 PDR ADOCK 050003B9 8 PDR an FPL Group company~/gJ I FPL Fscsirriis oi NRC Form S68 (e.es)V S.NLCL EAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)APPITCYT 0 CNS ISA$1 50 010l EXP'.l 1500 t EST NEED NATCE N 005 PESPONSE To COWL Y WITH THE PPOISAATION COL LEC TON INOLEST150 ll 550$, TONWAAO CONMENTS PECAIEANO 55505tH 5STNAA TE TO TIE PECOPOSANC INPCTTTSIIANAOENENT TTLFNCH(P~LLS, IACLENLINQAATOIY CONLPSSCFL WANANCTCN. |
| AEOD/ROAB/DSP NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8DNR~SPLB8DlREGFILE02GN2~LE01EXTERNAL: | | CC t05NL AIO TO THE PAPENFICFIA FETACTCN PNCVECT Ol 50 010PA CF 5 IcE oF NANAEE LENT No NAxft.wASFNIOTIPL oc t05NL FACILITY NAME (1)DOCKET NUMBER (2)St.Lucie Unit 2 A 050003891 0 3 T'TLE{)Missed Surveillance for Safety Injection Tank Sampling Due to Personnel Error EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (8)0 1 DAY 0 8 YEAR 9 3 YEAR 9 3 ,.'IAL 0 0 1 gR 0 0 0 2 DAY YEAR 0 5 9 3 FACILITY NAMES N/A N/A DOCKET NUMBER(S)050 0 05000 OPERATING MODE (9)POWER LEVEL (10)1 0 0;Cgjl r 20.402(b)20.405(a)(1)(i) 20.405(c)50.36(c)(1) 20A05(a)(1)(II) 50.36(c)(2) 20.405(a)(1)(iii) 20.405(a)(1)(iv) 20.405(a)(1)(v) 50.73(a)(2)(I)50.73(a)(2)(ii) 50.73(a)(2)(iii)LICENSEE CONTACT FOR THIS LER 12 50.73(a)(2)(iv) 50.73(a){2){v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x) |
| EGErGBRYCE,J.H NRCPDRNSICPOORE,W.COPIESLTTRENCL1111221122111111111111221111RECIPIENT IDCODE/NAME PD2-2PDACRSAEOD/DSP/TPAB NRR/DET/EMEB 7ENRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB8H3 NRR/DST/SRXB 8ERES/DSIR/EIB LSTLOBBYWARDNSICMURPHY,G.A NUDOCSFULLTXTCOPIESLTTRENCL1-12211111122111111111111RNOTETOALL"RIDS"RECIPIENTS:
| | THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR: Check one or more of the followin, (11)73.71(b)73;71{c)OTHER (Specify in Abstract below and in Text NRC Form 366A)NAME James A.Hurchalla, Shift Technical Advisor TELEP ONE NUMBER AREACODE 4 0 7 465-3550 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 CAUSE SYSTEM COMPONENT REPORTABLE TO NPRDS SYSTEM COMPONENT MANUFAC REPORTABLE TURER TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 YES (If yes, complete EXPECTED SUBMISSION DATE)X NO I I I EXPECTED MONTH DAY YEAR SUBMISSION DATE (15)ABSTRACT'(Limit to 1400 spaces.i.e. |
| PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.504-2065)
| | approximately fifteen single-space typewritten lines)(16)On January 8, at 0500 a Reactor Control Operator (RCO)filled the 2A1, 2A2, and 2B2 Safety tnjection Tanks'SITs) and subsequently notified Chemistry. |
| TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!LSFULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
| | A Chemistry technician sampted two of the SITs per the required surveillance but faited to sample the third.On January 8,1993, at 2300 the Unit 2 Assistant Nuclear Plant Supervisor discovered that the sampling of the 2A1 Safety Injection Tank had not been performed by Chemistry within the required time interval atter filling the tank.Using, the 25%maximum allowable extension permitted by.Technical Specification (TS)4.0.2, the latest time at which the sampling could have been performed on time was January 8, at 1230.The root cause of the event was personnel error by a Chemistry technician responsible for the sampling.When informed by Operations that specific SITs have been filled it is the responsibility of the Chemistry department personnel on shift to sample these SITs for the required boron concentration per TS 4.5.1.1.b. |
| LTTR31ENCL31 P.O.Box128,Ft.Pierce,FL3o954-0128 February5,1993L-'93-3010CFR50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit2DocketNo.50-389Reportable Event:93-001DateofEvent:January8,1993MissedSurveillance forSafetyInectionTankSamlinDuetoPersonnel ErrorTheattachedLicenseeEventReportisbeingsubmitted pursuanttotherequirements of10CFR50.73toprovidenotification ofthesubjectevent.Verytrulyyours,D.A.SVicePSt.LugersidentePlantDAS/JWH/kw Attachment cc:StewartD.Ebneter,RegionalAdministrator, USNRCRegionII.SeniorResident, Inspector, USNRC,St.LuciePlantDAS/PSLN857-933.000429302110293 930205PDRADOCK050003B98PDRanFPLGroupcompany~/gJI FPLFscsirriis oiNRCFormS68(e.es)VS.NLCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)APPITCYT0CNSISA$150010lEXP'.l1500tESTNEEDNATCEN005PESPONSEToCOWLYWITHTHEPPOISAATION COLLECTONINOLEST150 ll550$,TONWAAOCONMENTSPECAIEANO 55505tH5STNAATETOTIEPECOPOSANC INPCTTTSIIANAOENENT TTLFNCH(P~LLS, IACLENLINQAATOIY CONLPSSCFL WANANCTCN.
| | In addition, there was a failure on the part of the control room personnel to realize that one of the three filled SITs had not been sampled when Chemistry notified them that two SITs were within specification. |
| CCt05NLAIOTOTHEPAPENFICFIA FETACTCNPNCVECTOl50010PACF5IcEoFNANAEELENTNoNAxft.wASFNIOTIPL oct05NLFACILITYNAME(1)DOCKETNUMBER(2)St.LucieUnit2A050003891 03T'TLE{)MissedSurveillance forSafetyInjection TankSamplingDuetoPersonnel ErrorEVENTDATE(5)LERNUMBER(6)REPORTDATE(7)OTHERFACILITIES INVOLVED(8)01DAY08YEAR93YEAR93,.'IAL001gR0002DAYYEAR0593FACILITYNAMESN/AN/ADOCKETNUMBER(S) 050005000OPERATING MODE(9)POWERLEVEL(10)100;Cgjlr20.402(b) 20.405(a)(1)(i) 20.405(c) 50.36(c)(1) 20A05(a)(1)(II) 50.36(c)(2) 20.405(a)(1)(iii) 20.405(a)(1)(iv) 20.405(a)(1)(v) 50.73(a)(2)(I)50.73(a)(2)(ii) 50.73(a)(2)
| | Corrective actions were;1)Perform the 2A1 SIT sutveiltance. |
| (iii)LICENSEECONTACTFORTHISLER1250.73(a)(2)(iv) 50.73(a){2){v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x) | | 2)Create a status board by which Chemistry can insure that the appropriate SITs have been sampled.3)The Chemistry personnel involved were counselled. |
| THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFR:Checkoneormoreofthefollowin, (11)73.71(b)73;71{c)OTHER(SpecifyinAbstractbelowandinTextNRCForm366A)NAMEJamesA.Hurchalla, ShiftTechnical AdvisorTELEPONENUMBERAREACODE407465-3550COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEMCOMPONENT REPORTABLE TONPRDSSYSTEMCOMPONENT MANUFACREPORTABLE TURERTONPRDSSUPPLEMENTAL REPORTEXPECTED14YES(Ifyes,completeEXPECTEDSUBMISSION DATE)XNOIIIEXPECTEDMONTHDAYYEARSUBMISSION DATE(15)ABSTRACT'(Limitto1400spaces.i.e.
| | 4)Operations personnel have been counselled. |
| approximately fifteensingle-space typewritten lines)(16)OnJanuary8,at0500aReactorControlOperator(RCO)filledthe2A1,2A2,and2B2Safetytnjection Tanks'SITs) andsubsequently notifiedChemistry. | | 5)A Human Performance Evaluation System evaluation was subsequently conducted whose findings agree with this report.FPL Facsimile of NRC Form 366 (6-89) |
| AChemistry technician samptedtwooftheSITspertherequiredsurveillance butfaitedtosamplethethird.OnJanuary8,1993,at2300theUnit2Assistant NuclearPlantSupervisor discovered thatthesamplingofthe2A1SafetyInjection Tankhadnotbeenperformed byChemistry withintherequiredtimeintervalatterfillingthetank.Using,the25%maximumallowable extension permitted by.Technical Specification (TS)4.0.2,thelatesttimeatwhichthesamplingcouldhavebeenperformed ontimewasJanuary8,at1230.Therootcauseoftheeventwaspersonnel errorbyaChemistry technician responsible forthesampling.
| | PPL PSCSIITTle Ot NRC FOTm&OSl6 89)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATlON |
| WheninformedbyOperations thatspecificSITshavebeenfilleditistheresponsibility oftheChemistry department personnel onshifttosampletheseSITsfortherequiredboronconcentration perTS4.5.1.1.b.
| | 'APPROITOCAAT KLSITCSIPA l splpaa ACGIT TSTPAATTOIMICTNPTRRTSPONSl TOOOINTTWITH TIPSPPOISAAOCNCOIlf CTON RTOUT ST I ISA IPTS IORNNO CCANRNT 0 RTGARTNIC TAPSXN TSTINATl TOPIC RTCORCS AICI IS PORTS N ANAGT AS NT SRANCH TP 000A U 0, IAICI 0 AIT Rl OIAA TORY OAA+CSSN70 WANTNCTON,OCT000S NAPTOTIR PAPTRWOPNRTOVCTIONPRORCTI'TIICCISPAOIIICC OP NANAK NTNT AM)TANCTT.WAN SNCTOIA OC PPNO FACILITY NAME (1)St.Lucie Unit 2 DOCKET NUMBER (2)YEAR EQUENTIAL NUMBER."T',." REVISION vl NUMBER LER NUMBER (6)PAGE (3)0 500 0389 TEXT (If more spaceis reqoired, tjse additional NRC Form 366A's)(17)9 3 0 0 0 0 0 2 0 3 Operations fills Safety Injection Tanks (SIT)(EIIS: |
| Inaddition, therewasafailureonthepartofthecontrolroompersonnel torealizethatoneofthethreefilledSITshadnotbeensampledwhenChemistry notifiedthemthattwoSITswerewithinspecification.
| | BP)as necessary to maintain the required Technical Specification (TS)level.Subsequently these SITs must be sampled in accordance with-Chemistry Operating Procedure 2-C-60 within 6 hours to ensure that the required TS boron concentration has been maintained. |
| Corrective actionswere;1)Performthe2A1SITsutveiltance. | | On January 8, 1993, at 0500 a Reactor Control Operator (RCO)filled the 2A1, 2A2, and 2B2 SITs.At 0530 he notified the onshift Chemistry technician. |
| 2)CreateastatusboardbywhichChemistry caninsurethattheappropriate SITshavebeensampled.3)TheChemistry personnel involvedwerecounselled. | | The Chemistry technician who received the call turned the sampling responsibility over to an oncoming technician on the next shift.This technician received the appropriate verbal instructions of which SITs to check but only sampled the 2A2 and 2B2 SITs.At 0830 he notified the control room that these SITs were satisfactory wilh respect to boron concentration. |
| 4)Operations personnel havebeencounselled. | | Operations personnel received the call and failed to notice that one of the SITs had not been sampled.At 2314 the oncoming Assistant Nuclear Plant Supervisor was reviewing the RCO chronological log and discovered the 2A1 SIT had not been sampled.The SIT was administratively declared out of service and Chemistry was notified to sample it.The sample showed satisfactory boron concentration and the 2A1 SIT was declared back in service at 2345.V The root cause of the event is cognitive personnel error by a utility Chemistry technician by failing to ensure the sampling of the appropriate SITs.A contributing factor is that there was no method other than verbal request turnover between Chemistry technicians to insure that the correct SITs are sampled.This places the full responsibility for the correctness and timeliness of this TS surveillance on verbal communication with no recorded information for the Chemistry technician to reference. |
| 5)AHumanPerformance Evaluation Systemevaluation wassubsequently conducted whosefindingsagreewiththisreport.FPLFacsimile ofNRCForm366(6-89) | | In addition, there was a failure on the part of control room personnel to realize that one of the three SITs had not been sampled when Chemistry notified them that two SITs were within specification. |
| PPLPSCSIITTle OtNRCFOTm&OSl689)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATlON
| | There were no unusual characteristics of the work location which contributed to this event.T V This event is reportable under 10 CFR 50.73.a.2.i.b, as a missed surveillance required by Technical Specifications. |
| 'APPROITOCAAT KLSITCSIPA lsplpaaACGITTSTPAATTOIMICTNPTRRTSPONSl TOOOINTTWITH TIPSPPOISAAOCNCOIlf CTONRTOUTSTIISAIPTSIORNNOCCANRNT0RTGARTNIC TAPSXNTSTINATlTOPICRTCORCSAICIISPORTSNANAGTASNTSRANCHTP000AU0,IAICI0AITRlOIAATORYOAA+CSSN70 WANTNCTON,OCT000S NAPTOTIRPAPTRWOPNRTOVCTIONPRORCTI'TIICCISPAOIIICC OPNANAKNTNTAM)TANCTT.WANSNCTOIAOCPPNOFACILITYNAME(1)St.LucieUnit2DOCKETNUMBER(2)YEAREQUENTIAL NUMBER."T',."REVISIONvlNUMBERLERNUMBER(6)PAGE(3)05000389TEXT(Ifmorespaceisreqoired, tjseadditional NRCForm366A's)(17)9300000203Operations fillsSafetyInjection Tanks(SIT)(EIIS: | | Technical Specification 4.5.1.1.b states that each Safety Injection Tank shall be demonstrated operable within 6 hours after each solution volume increase greater than or equal to 1%of tank volume by verifying the boron concentration of the solution.The purpose of this sampling is to provide assurance that the boron concentration of the SITs has not been changed to a value-outside the band of the Technical Specification requirements. |
| BP)asnecessary tomaintaintherequiredTechnical Specification (TS)level.Subsequently theseSITsmustbesampledinaccordance with-Chemistry Operating Procedure 2-C-60within6hourstoensurethattherequiredTSboronconcentration hasbeenmaintained. | | This assures that the assumptions used for the SITs in the Final Updated Safety Analysis Report (FUSAR)are valid.The surveillance of the 2A1 SIT was completed at 2340, or 12 hours and 40 minutes past the required Technical Specification sample time.FPL Facsimile of NRC Form 366 (6-89) |
| OnJanuary8,1993,at0500aReactorControlOperator(RCO)filledthe2A1,2A2,and2B2SITs.At0530henotifiedtheonshiftChemistry technician.
| | F PL Facsimro ot r NRC Form 666 (669t.U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATlON APPAOVTOCallNCI 0ll00IOI 000TIES.0000 0 00TAAATTO nvexNPT frfE0PONTE ToCOAWlvvATN TI0000aNAAOONCcuTCTEPI IEOIE 00 I 000 0000 f CTIWATEr CCANE NT 0 IE CAN ONC TAPCTN 00TINAT K To OE TE COII0 Ala fEPTNTCNANACTAENTCPlANCNIP0000ua IAcTTArl TEaAATONT~ |
| TheChemistry technician whoreceivedthecallturnedthesamplingresponsibility overtoanoncomingtechnician onthenextshift.Thistechnician receivedtheappropriate verbalinstructions ofwhichSITstocheckbutonlysampledthe2A2and2B2SITs.At0830henotifiedthecontrolroomthattheseSITsweresatisfactory wilhrespecttoboronconcentration.
| | WASHNC TON, OC 00000 APAT To TIE 0 APT frWONA TE COCTION PNOE C'0 fll 00 0 I Ol 0 0Ãf ICT Of NANACTIENT AIO TANCET.WACIIAOT000 OC 00NO.FACILITY NAME{1)St.LUCie Unit 2 DOCKET NUMBER (2)YEAR LER NUMBER{6)EQUENTIAL NUMBER REVISION NUMBER PAGE (3)0 500 0389 9 3 TEXT (If more spaceis required, use additional NRC Form 366A's)(17)0 0 1 0 0 0 3 0 0 3 The results of the chemistry sample showed the boron concentration to be within Technical Specification 3.5.1.c.The 2A1 Safety Injection Tank was capable of performing its intended safety function as set forth in the assumptions of the FUSAR, sections 6.3.2.2.1 and 6.3.3.4.3.f. |
| Operations personnel receivedthecallandfailedtonoticethatoneoftheSITshadnotbeensampled.At2314theoncomingAssistant NuclearPlantSupervisor wasreviewing theRCOchronological loganddiscovered the2A1SIThadnotbeensampled.TheSITwasadministratively declaredoutofserviceandChemistry wasnotifiedtosampleit.Thesampleshowedsatisfactory boronconcentration andthe2A1SITwasdeclaredbackinserviceat2345.VTherootcauseoftheeventiscognitive personnel errorbyautilityChemistry technician byfailingtoensurethesamplingoftheappropriate SITs.Acontributing factoristhattherewasnomethodotherthanverbalrequestturnoverbetweenChemistry technicians toinsurethatthecorrectSITsaresampled.Thisplacesthefullresponsibility forthecorrectness andtimeliness ofthisTSsurveillance onverbalcommunication withnorecordedinformation fortheChemistry technician toreference. | | TI;erefore, lhe health and safety of the public was not affected by this event.1)The 2A1 Safety Injection Tank (SIT)Chemistry Surveillance was performed with satisfactory results January 8, 1993 at 2340 hours.2)The Chemistry department now uses a status board to track regulatory required surveillances that are not periodically scheduled.. |
| Inaddition, therewasafailureonthepartofcontrolroompersonnel torealizethatoneofthethreeSITshadnotbeensampledwhenChemistry notifiedthemthattwoSITswerewithinspecification.
| | 3)The personnel involved in this event have been counselled by the Chemistry supervisor on the importance of meeting surveillance requirements. |
| Therewerenounusualcharacteristics oftheworklocationwhichcontributed tothisevent.TVThiseventisreportable under10CFR50.73.a.2.i.b, asamissedsurveillance requiredbyTechnical Specifications.
| | -4)The Operations supervisor has issued a Night Order on this event which emphasizes the need for operators to track surveillances such as the one described in the LER via the operator turnover sheet, and the need for the oncoming crews to carefully review the chronological log.5)A Human Performance Enhancement System (HPES)evaluation was performed. |
| Technical Specification 4.5.1.1.b statesthateachSafetyInjection Tankshallbedemonstrated operablewithin6hoursaftereachsolutionvolumeincreasegreaterthanorequalto1%oftankvolumebyverifying theboronconcentration ofthesolution. | | The results agree with the conclusions of this Licensee Event Report.ITI NA F n n F il There were no component failures involved in this event.VI A previous similar event is described in LER 389-89-008, which describes a missed surveillance for Safety Injection Loop Header valves following the filling of two SITs.FPL Facsimile of NRC Form 366 (6.89)}} |
| Thepurposeofthissamplingistoprovideassurance thattheboronconcentration oftheSITshasnotbeenchangedtoavalue-outsidethebandoftheTechnical Specification requirements.
| |
| Thisassuresthattheassumptions usedfortheSITsintheFinalUpdatedSafetyAnalysisReport(FUSAR)arevalid.Thesurveillance ofthe2A1SITwascompleted at2340,or12hoursand40minutespasttherequiredTechnical Specification sampletime.FPLFacsimile ofNRCForm366(6-89)
| |
| FPLFacsimrootrNRCForm666(669t.U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATlON APPAOVTOCallNCI 0ll00IOI000TIES.0000000TAAATTO nvexNPTfrfE0PONTE ToCOAWlvvATN TI0000aNAAOONCcuTCTEPI IEOIE00I0000000fCTIWATErCCANENT0IECANONCTAPCTN00TINATKToOETECOII0AlafEPTNTCNANACTAENTCPlANCNIP0000ua IAcTTArlTEaAATONT~
| |
| WASHNCTON,OC00000APATToTIE0APTfrWONATECOCTIONPNOEC'0fll000IOl00ÃfICTOfNANACTIENT AIOTANCET.WACIIAOT000 OC00NO.FACILITYNAME{1)St.LUCieUnit2DOCKETNUMBER(2)YEARLERNUMBER{6)EQUENTIAL NUMBERREVISIONNUMBERPAGE(3)0500038993TEXT(Ifmorespaceisrequired, useadditional NRCForm366A's)(17)0010003003Theresultsofthechemistry sampleshowedtheboronconcentration tobewithinTechnical Specification 3.5.1.c.The2A1SafetyInjection Tankwascapableofperforming itsintendedsafetyfunctionassetforthintheassumptions oftheFUSAR,sections6.3.2.2.1 and6.3.3.4.3.f.
| |
| TI;erefore, lhehealthandsafetyofthepublicwasnotaffectedbythisevent.1)The2A1SafetyInjection Tank(SIT)Chemistry Surveillance wasperformed withsatisfactory resultsJanuary8,1993at2340hours.2)TheChemistry department nowusesastatusboardtotrackregulatory requiredsurveillances thatarenotperiodically scheduled.. | |
| 3)Thepersonnel involvedinthiseventhavebeencounselled bytheChemistry supervisor ontheimportance ofmeetingsurveillance requirements. | |
| -4)TheOperations supervisor hasissuedaNightOrderonthiseventwhichemphasizes theneedforoperators totracksurveillances suchastheonedescribed intheLERviatheoperatorturnoversheet,andtheneedfortheoncomingcrewstocarefully reviewthechronological log.5)AHumanPerformance Enhancement System(HPES)evaluation wasperformed. | |
| Theresultsagreewiththeconclusions ofthisLicenseeEventReport.ITINAFnnFilTherewerenocomponent failuresinvolvedinthisevent.VIAprevioussimilareventisdescribed inLER389-89-008, whichdescribes amissedsurveillance forSafetyInjection LoopHeadervalvesfollowing thefillingoftwoSITs.FPLFacsimile ofNRCForm366(6.89)}}
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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
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Text
ACCEI ER D DOCUMENT DIS IBVTION SYSTEM REGUL RY INFORMATION DISTRIBUT SYSTEM (RIDS)ACCESSION NBR:9302110293 DOC.DATE: 93/02/05 NOTARIZED:
NO FACIL:50-389 St.Lucie Plant, Unit 2, Florida Power&Light Co.AUTH.NAME AUTHOR AFFILIATION HURCHALLA,J.A.
Florida Power E Light Co.SAGER,D.A.
-Florida Power 6 Light Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000389
SUBJECT:
LER 93-001-00:on 930108,chemistry technician failed to sample third SI tank 6 sampling of SI tank 2A1 not performed within TS required interval after filling tank.Caused by personnel error.Personnel counseled.W/930205 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR g ENCL g SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER)-, Incident Rpt, etc.NOTES: RECiPIENT ID CODE/NAME PD2-2 LA NORRIS,J INTERNAL: ACNW AEOD/DOA.AEOD/ROAB/DSP NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8D NR~SPLB8Dl REG FILE 02 GN2~LE 01 EXTERNAL: EGErG BRYCE,J.H NRC PDR NSIC POORE,W.COPIES LTTR ENCL 1 1 1 1 2 2 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2 PD ACRS AEOD/DSP/TPAB NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB8H3 NRR/DST/SRXB 8E RES/DSIR/EIB L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT COPIES LTTR ENCL 1-1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 R NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!L S FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 P.O.Box 128, Ft.Pierce, FL 3o954-0128 February 5, 1993 L-'93-30 10 CFR 50.73 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Re: St.Lucie Unit 2 Docket No.50-389 Reportable Event: 93-001 Date of Event: January 8, 1993 Missed Surveillance for Safety In ection Tank Sam lin Due to Personnel Error The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.Very truly yours, D.A.S Vice P St.Lu ger sident e Plant DAS/JWH/kw Attachment cc: Stewart D.Ebneter, Regional Administrator, USNRC Region II.Senior Resident, Inspector, USNRC, St.Lucie Plant DAS/PSL N857-93 3.00042 9302110293 930205 PDR ADOCK 050003B9 8 PDR an FPL Group company~/gJ I FPL Fscsirriis oi NRC Form S68 (e.es)V S.NLCL EAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)APPITCYT 0 CNS ISA$1 50 010l EXP'.l 1500 t EST NEED NATCE N 005 PESPONSE To COWL Y WITH THE PPOISAATION COL LEC TON INOLEST150 ll 550$, TONWAAO CONMENTS PECAIEANO 55505tH 5STNAA TE TO TIE PECOPOSANC INPCTTTSIIANAOENENT TTLFNCH(P~LLS, IACLENLINQAATOIY CONLPSSCFL WANANCTCN.
CC t05NL AIO TO THE PAPENFICFIA FETACTCN PNCVECT Ol 50 010PA CF 5 IcE oF NANAEE LENT No NAxft.wASFNIOTIPL oc t05NL FACILITY NAME (1)DOCKET NUMBER (2)St.Lucie Unit 2 A 050003891 0 3 T'TLE{)Missed Surveillance for Safety Injection Tank Sampling Due to Personnel Error EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (8)0 1 DAY 0 8 YEAR 9 3 YEAR 9 3 ,.'IAL 0 0 1 gR 0 0 0 2 DAY YEAR 0 5 9 3 FACILITY NAMES N/A N/A DOCKET NUMBER(S)050 0 05000 OPERATING MODE (9)POWER LEVEL (10)1 0 0;Cgjl r 20.402(b)20.405(a)(1)(i) 20.405(c)50.36(c)(1) 20A05(a)(1)(II) 50.36(c)(2) 20.405(a)(1)(iii) 20.405(a)(1)(iv) 20.405(a)(1)(v) 50.73(a)(2)(I)50.73(a)(2)(ii) 50.73(a)(2)(iii)LICENSEE CONTACT FOR THIS LER 12 50.73(a)(2)(iv) 50.73(a){2){v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x)
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR: Check one or more of the followin, (11)73.71(b)73;71{c)OTHER (Specify in Abstract below and in Text NRC Form 366A)NAME James A.Hurchalla, Shift Technical Advisor TELEP ONE NUMBER AREACODE 4 0 7 465-3550 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 CAUSE SYSTEM COMPONENT REPORTABLE TO NPRDS SYSTEM COMPONENT MANUFAC REPORTABLE TURER TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 YES (If yes, complete EXPECTED SUBMISSION DATE)X NO I I I EXPECTED MONTH DAY YEAR SUBMISSION DATE (15)ABSTRACT'(Limit to 1400 spaces.i.e.
approximately fifteen single-space typewritten lines)(16)On January 8, at 0500 a Reactor Control Operator (RCO)filled the 2A1, 2A2, and 2B2 Safety tnjection Tanks'SITs) and subsequently notified Chemistry.
A Chemistry technician sampted two of the SITs per the required surveillance but faited to sample the third.On January 8,1993, at 2300 the Unit 2 Assistant Nuclear Plant Supervisor discovered that the sampling of the 2A1 Safety Injection Tank had not been performed by Chemistry within the required time interval atter filling the tank.Using, the 25%maximum allowable extension permitted by.Technical Specification (TS)4.0.2, the latest time at which the sampling could have been performed on time was January 8, at 1230.The root cause of the event was personnel error by a Chemistry technician responsible for the sampling.When informed by Operations that specific SITs have been filled it is the responsibility of the Chemistry department personnel on shift to sample these SITs for the required boron concentration per TS 4.5.1.1.b.
In addition, there was a failure on the part of the control room personnel to realize that one of the three filled SITs had not been sampled when Chemistry notified them that two SITs were within specification.
Corrective actions were;1)Perform the 2A1 SIT sutveiltance.
2)Create a status board by which Chemistry can insure that the appropriate SITs have been sampled.3)The Chemistry personnel involved were counselled.
4)Operations personnel have been counselled.
5)A Human Performance Evaluation System evaluation was subsequently conducted whose findings agree with this report.FPL Facsimile of NRC Form 366 (6-89)
PPL PSCSIITTle Ot NRC FOTm&OSl6 89)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATlON
'APPROITOCAAT KLSITCSIPA l splpaa ACGIT TSTPAATTOIMICTNPTRRTSPONSl TOOOINTTWITH TIPSPPOISAAOCNCOIlf CTON RTOUT ST I ISA IPTS IORNNO CCANRNT 0 RTGARTNIC TAPSXN TSTINATl TOPIC RTCORCS AICI IS PORTS N ANAGT AS NT SRANCH TP 000A U 0, IAICI 0 AIT Rl OIAA TORY OAA+CSSN70 WANTNCTON,OCT000S NAPTOTIR PAPTRWOPNRTOVCTIONPRORCTI'TIICCISPAOIIICC OP NANAK NTNT AM)TANCTT.WAN SNCTOIA OC PPNO FACILITY NAME (1)St.Lucie Unit 2 DOCKET NUMBER (2)YEAR EQUENTIAL NUMBER."T',." REVISION vl NUMBER LER NUMBER (6)PAGE (3)0 500 0389 TEXT (If more spaceis reqoired, tjse additional NRC Form 366A's)(17)9 3 0 0 0 0 0 2 0 3 Operations fills Safety Injection Tanks (SIT)(EIIS:
BP)as necessary to maintain the required Technical Specification (TS)level.Subsequently these SITs must be sampled in accordance with-Chemistry Operating Procedure 2-C-60 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to ensure that the required TS boron concentration has been maintained.
On January 8, 1993, at 0500 a Reactor Control Operator (RCO)filled the 2A1, 2A2, and 2B2 SITs.At 0530 he notified the onshift Chemistry technician.
The Chemistry technician who received the call turned the sampling responsibility over to an oncoming technician on the next shift.This technician received the appropriate verbal instructions of which SITs to check but only sampled the 2A2 and 2B2 SITs.At 0830 he notified the control room that these SITs were satisfactory wilh respect to boron concentration.
Operations personnel received the call and failed to notice that one of the SITs had not been sampled.At 2314 the oncoming Assistant Nuclear Plant Supervisor was reviewing the RCO chronological log and discovered the 2A1 SIT had not been sampled.The SIT was administratively declared out of service and Chemistry was notified to sample it.The sample showed satisfactory boron concentration and the 2A1 SIT was declared back in service at 2345.V The root cause of the event is cognitive personnel error by a utility Chemistry technician by failing to ensure the sampling of the appropriate SITs.A contributing factor is that there was no method other than verbal request turnover between Chemistry technicians to insure that the correct SITs are sampled.This places the full responsibility for the correctness and timeliness of this TS surveillance on verbal communication with no recorded information for the Chemistry technician to reference.
In addition, there was a failure on the part of control room personnel to realize that one of the three SITs had not been sampled when Chemistry notified them that two SITs were within specification.
There were no unusual characteristics of the work location which contributed to this event.T V This event is reportable under 10 CFR 50.73.a.2.i.b, as a missed surveillance required by Technical Specifications.
Technical Specification 4.5.1.1.b states that each Safety Injection Tank shall be demonstrated operable within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase greater than or equal to 1%of tank volume by verifying the boron concentration of the solution.The purpose of this sampling is to provide assurance that the boron concentration of the SITs has not been changed to a value-outside the band of the Technical Specification requirements.
This assures that the assumptions used for the SITs in the Final Updated Safety Analysis Report (FUSAR)are valid.The surveillance of the 2A1 SIT was completed at 2340, or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and 40 minutes past the required Technical Specification sample time.FPL Facsimile of NRC Form 366 (6-89)
F PL Facsimro ot r NRC Form 666 (669t.U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATlON APPAOVTOCallNCI 0ll00IOI 000TIES.0000 0 00TAAATTO nvexNPT frfE0PONTE ToCOAWlvvATN TI0000aNAAOONCcuTCTEPI IEOIE 00 I 000 0000 f CTIWATEr CCANE NT 0 IE CAN ONC TAPCTN 00TINAT K To OE TE COII0 Ala fEPTNTCNANACTAENTCPlANCNIP0000ua IAcTTArl TEaAATONT~
WASHNC TON, OC 00000 APAT To TIE 0 APT frWONA TE COCTION PNOE C'0 fll 00 0 I Ol 0 0Ãf ICT Of NANACTIENT AIO TANCET.WACIIAOT000 OC 00NO.FACILITY NAME{1)St.LUCie Unit 2 DOCKET NUMBER (2)YEAR LER NUMBER{6)EQUENTIAL NUMBER REVISION NUMBER PAGE (3)0 500 0389 9 3 TEXT (If more spaceis required, use additional NRC Form 366A's)(17)0 0 1 0 0 0 3 0 0 3 The results of the chemistry sample showed the boron concentration to be within Technical Specification 3.5.1.c.The 2A1 Safety Injection Tank was capable of performing its intended safety function as set forth in the assumptions of the FUSAR, sections 6.3.2.2.1 and 6.3.3.4.3.f.
TI;erefore, lhe health and safety of the public was not affected by this event.1)The 2A1 Safety Injection Tank (SIT)Chemistry Surveillance was performed with satisfactory results January 8, 1993 at 2340 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.9037e-4 months <br />.2)The Chemistry department now uses a status board to track regulatory required surveillances that are not periodically scheduled..
3)The personnel involved in this event have been counselled by the Chemistry supervisor on the importance of meeting surveillance requirements.
-4)The Operations supervisor has issued a Night Order on this event which emphasizes the need for operators to track surveillances such as the one described in the LER via the operator turnover sheet, and the need for the oncoming crews to carefully review the chronological log.5)A Human Performance Enhancement System (HPES)evaluation was performed.
The results agree with the conclusions of this Licensee Event Report.ITI NA F n n F il There were no component failures involved in this event.VI A previous similar event is described in LER 389-89-008, which describes a missed surveillance for Safety Injection Loop Header valves following the filling of two SITs.FPL Facsimile of NRC Form 366 (6.89)
