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| | issue date = 11/26/1997 | | | issue date = 11/26/1997 |
| | title = 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 | | | title = 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 |
| | author name = REVELL J, STALL J A | | | author name = Revell J, Stall J |
| | author affiliation = FLORIDA POWER & LIGHT CO. | | | author affiliation = FLORIDA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:CATEGORY1SREGULATEYINFORMATION DISTRIBUTION STEM(RIDS)ACCESSION NBR:9712030199 | | {{#Wiki_filter:CATEGORY 1 S |
| ,DOC.DATE: | | REGULATE Y INFORMATION DISTRIBUTION STEM (RIDS) |
| 97/11/26NOTARIZED: | | ACCESSION NBR:9712030199 , DOC.DATE: 97/11/26 NOTARIZED: NO DOCKET ¹ FACXL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 AUTH. NAME AUTHOR AFFILIATION REVELL,J. Florida Power & Light Co. |
| NOFACXL:50-335 St.LuciePlant,Unit1,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIATION REVELL,J.
| | STALL,J.A. Florida Power & Light Co. |
| FloridaPower&LightCo.STALL,J.A.
| | RECIP.NAME RECIPIENT AFFILIATION |
| FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DOCKET¹05000335
| |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER97-010-00:on 971027,inadvertant corealteration prohibited byTSoccurred.
| | 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 UGS move.W/971126 ltr. |
| CausedbyCEAfailuretodetachfromUGS.Safety evaluation wasperformed
| | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR i ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| &procedural revmadetocontinueUGSmove.W/971126 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR iENCLSIZE:l5TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:ERECIPIENT IDCODE/NAME PD2-3PDINTERNAL: | | SIZE: l5 E |
| ACRSAEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB EXTERNAL:
| | NOTES: |
| LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL111111111111111111111111RECIPIENT IDCODE/NAME WIENS,L.ILECENTNRRNRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN2FXLE01LITCOBRYCE,JHNOACQUEENER,DS NUDOCSFULLTXTCOPIESLTTRENCL1122111111111111'111111110D0UNOTETOALL"RIDS"RECZPZENTS PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
| | RECIPIENT COPIES RECIPIENT COPIES 0 ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3 PD 1 1 WIENS,L. 1 1 INTERNAL: ACRS 1 1 2 2 AEOD/SPD/RRAB 1 1 ILE CENT 1 1 NRR/DE/ECGB 1 1 NRR 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DET/EIB 1 1 RGN2 FXLE 01 '1 1 D EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 0 |
| LTTR25ENCL25 FloridaPower&LightCompany,650tSouthOceanDrive,JensenBeach,FL34957FPLNovember26,1997L-97-29710CFR50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit1DocketNo.50-335Reportable Event:97-010DateofEvent:October27,1997Inadvertant CoreAlteration Prohibited byTechnical Specifications DuetoStuckControlElementAssemblCEATheattachedLicenseeEventReportisbeingsubmitted pursuanttotherequirements of10CFR50.73toprovidenotification ofthesubjectevent.Verytrulyyours,J.A.StallVicePresident St.LuciePlantJAS/JWRAttachment cc:RegionalAdministrator, USNRC,RegionIISeniorResidentInspector, USNRC,St.LuciePlant,ijc4/97i2030i'tt9 97ii26PDRADQCK050003358PDRlbltttliltjtlllttltajiNI anFPLGroupcompany NRCFORM366(4.95)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER){Seereverseforrequirednumberofdigits/characters foreachblock)APPROVEDBYOMBNo.31604I104 EXRRES04I30/SSESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISMANDATORINFORMATION COLLECTION REQUEST:60.0HRS.REPORTEDLESSONLEARNEDAREINCORPORATED INTOTHEUCENSINGPROCESSANDFEBACKTOINDUSTRY.
| | 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 U |
| FORWARDCOMMINTSREGARDING BURDENESTIMATTOTHEINFORMATION ANDRECORDSMANAGEMENT BRANCHIT.SF33)US.NUCLEARREGIAATORY COMMISSION.
| | NOTE TO ALL "RIDS" RECZPZENTS PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT LISTS THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25 |
| WASHINGTON. | | |
| DC206664001 ANDTOTHEPAPERWORK REDUCTION PROJECT13160%1041, OFFICEOIMANAGEMENT ANDBUDGET.WASHINGTON.
| | Florida Power & Light Company, 650t South Ocean Drive, Jensen Beach, FL 34957 November 26, 1997 L-97-297 FPL 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Reportable Event: 97-010 Date of Event: October 27, 1997 Inadvertant Core Alteration Prohibited by Technical Specifications Due to Stuck Control Element Assembl CEA The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event. |
| DC20603.FACIUTYNAMEHiSTLUCIEUNIT1DOCKETNUMBER12105000335PAGE1311OF4TITLE(41Inadvertant CoreAlteration Prohibited byTechnical Specifications DuetoStuckControlElementAssembly(CEA)MONTHDAY1027OPERATING MODE(9)POWERLEVEL{10)97000SEQUENTIAL REVISIONNUMBERNUMBER97-010-0020.2201(b)20.2203(0)(2)(I)20.2203(a)
| | Very truly yours, J. A. Stall Vice President St. Lucie Plant JAS/JWR Attachment cc: Regional Administrator, USNRC, Region II |
| (2)(iii)20.2203(0)(2)(iv)MONTHOAY112620.2203{a)(2)(v) 20.2203(a) | | ,ij Senior Resident Inspector, USNRC, St. Lucie Plant c |
| (3)(ii)50.36(c)(1) 50.36(c)(2) | | /4 97i2030i'tt9 97ii26 PDR ADQCK 05000335 8 PDR lbltttliltjtlllttltajiNI an FPL Group company |
| YEAR97FACILIlYNAMEFACILITYNAME50.73(a)(2)(i)50.73(a)(2)(iii) 50.73(a)(2)(v)50.73(a)(2)(vii)
| | |
| DOCKETNUMBER DOCKETNUMBER 50.73(a)(2)(viii)73.71OTHERSpecifyinAbstractbefoworinNRCForm366ANAMEJackRevell,Licensing EngineerTELEPHONE NUMBERSncludeAreaCode)(561)467-7169CAUSESYSTEM.COMPONENT MANUFACTURER REPORTABLE TONPRDSCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TONPRDSACRCTC490XYES{Ifyes,completeEXPECTEDSUBMISSION DATE).NoEXPECTEDSUBMISSION DATE{15)MONTHOAYYEAR020498ABSTRACT(Limitto1400spaces,i.e.,approximately 15single-spaced typewritten lines){16)OnOctober27,1997,St.LucieUnit1wasinMode6withthereactorheadremovedinpreparation fordefueling.
| | NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB No. 31604I104 (4.95) EXRRES 04I30/SS ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATOR INFORMATION COLLECTION REQUEST: 60.0 HRS. REPORTED LESSON LEARNED ARE INCORPORATED INTO THE UCENSING PROCESS AND FE LICENSEE EVENT REPORT (LER) BACK TO INDUSTRY. FORWARD COMMINTS REGARDING BURDEN ESTIMAT TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH IT.S F33) |
| Thecontainment equipment hatchandpersonnel accessairlockwereopen,asallowedbyTechnical Specifications.
| | US.NUCLEARREGIAATORY COMMISSION. WASHINGTON. DC 206664001 AND TO THE PAPERWORK REDUCTION PROJECT 13160%1041, OFFICE OI |
| Personnel commenced UpperGuideStructure (UGS)withdrawal fromthereactorvesselinaccordance withprocedures. | | {See reverse for required number of MANAGEMENTAND BUDGET. WASHINGTON. DC 20603. |
| AstheUGSclearedthealignment pins,aControlElementAssembly(CEA)wasdiscovered attachedtotheUGS,andhadbeenunexpectedly withdrawn fromthecore.Thisconstituted acorealteration withoutthecontainment penetration statusrequiredbyTechnical Specifications.
| | digits/characters for each block) |
| Containment integrity wassetwithinabout20minutesofdiscovery ofthestuckCEA.ThecauseoftheCEAremaining attachedtotheUGScouldnotimmediately bedetermined. | | FACIUTY NAME Hi DOCKET NUMBER 121 PAGE 131 ST LUCIE UNIT 1 05000335 1 OF4 TITLE (41 Inadvertant Core Alteration Prohibited by Technical Specifications Due to Stuck Control Element Assembly (CEA) |
| Asafetyevaluation wasperformed andaprocedural revisionmadetocontinuetheUGSmove.Reactorcavitywaterlevelwasraisedtoincreaseshielding.
| | SEQUENTIAL REVISION FACILIlYNAME DOCKETNUMBER MONTH DAY MONTH OAY YEAR NUMBER NUMBER FACILITYNAME DOCKETNUMBER 10 27 97 97 010 00 11 26 97 OPERATING MODE (9) 20.2201 (b) 20.2203{a)(2)(v) 50.73(a) (2) (i) 50.73(a) (2) (viii) |
| Anticipating elevatedcontainment radiation levels,theContainment Isolation System(CIS)wasmanuallyactuatedpriortocontinuing thelift.TheUGSliftrecommenced onOctober28.AremotecamerasituatedbeneaththeUGSmonitored theprogress, andtheCEAremainedattachedthroughout thetransit.Oncethetransittotherefueling cavitywascompleted, theCEAwasrecovered fromtheUGS.Therootcauseoftheeventisstillunderinvestigation. | | POWER LEVEL {10) 000 20.2203 (0) (2) (I) 20.2203(a) (3) (ii) 50.73(a)(2)(iii) 73.71 OTHER 20.2203(a) (2)(iii) 50.36(c)(1) 50.73(a) (2)(v) Specify in Abstract befow or in NRC Form 366A 20.2203 (0) (2) (iv) 50.36(c)(2) 50.73(a)(2)(vii) |
| Furthercorrective actionswillbeidentified oncetherootcauseisdetermined.
| | NAME TELEPHONE NUMBER Snclude Area Code) |
| NRCFORM366(4-95)
| | Jack Revell, Licensing Engineer (561) 467-7169 CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE REPORTABLE TO NPRDS CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS AC RCT C490 MONTH OAY YEAR EXPECTED YES SUBMISSION X {If yes, complete EXPECTED SUBMISSION DATE). No DATE {15) 02 04 98 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) {16) |
| NRCFORM366A(4.95)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO STLUCIEUNIT105000335YEARSEQUENTIAL REVISION97-010-002OF4TEXTilfmorespeceisrequired, useeddnionel copiesofNRCForm366A/I17IDESCRIPTION OFTHEEVENTOnOctober27,1997,St.LucieUnit1wasinMode6withthereactorhead[EIIS:AB:RCT]
| | On October 27, 1997, St. Lucie Unit 1 was in Mode 6 with the reactor head removed in preparation for defueling. The containment equipment hatch and personnel access airlock were open, as allowed by Technical Specifications. Personnel commenced Upper Guide Structure (UGS) withdrawal from the reactor vessel in accordance with procedures. As the UGS cleared the alignment pins, a Control Element Assembly (CEA) was discovered attached to the UGS, and had been unexpectedly withdrawn from the core. This constituted a core alteration without the containment penetration status required by Technical Specifications. Containment integrity was set within about 20 minutes of discovery of the stuck CEA. |
| removedinpreparation forreactordefueling.
| | The cause of the CEA remaining attached to the UGS could not immediately be determined. A safety evaluation was performed and a procedural revision made to continue the UGS move. Reactor cavity water level was raised to increase shielding. Anticipating elevated containment radiation levels, the Containment Isolation System (CIS) was manually actuated prior to continuing the lift. |
| Thecontainment equipment hatchandpersonnel accessairlock[EIIS:NH]
| | The UGS lift recommenced on October 28. A remote camera situated beneath the UGS monitored the progress, and the CEA remained attached throughout the transit. Once the transit to the refueling cavity was completed, the CEA was recovered from the UGS. The root cause of the event is still under investigation. Further corrective actions will be identified once the root cause is determined. |
| wereopen,asallowedbyTechnical Specifications.
| | NRC FORM 366 (4-95) |
| ControlElementAssemblies (CEAs)[EIIS:AA]
| | |
| hadbeenunlatched bypersonnel inaccordance withprocedure OP1-0110022,
| | NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSIO (4.95) |
| 'Coupling'and Uncoupling ofCEAExtension Shafts'.Atapproximately 1510,thereactorcavitywaterlevelwasraisedto55feet6inchestomaintainadequateshielding inpreparation forliftingtheUpperGuideStructure (UGS)[EIIS:AC]. | | LICENSEE EVENT REPORT (LER) |
| Normallyduringthelift,onlytheUGSliftrigisraisedabovethesurfaceofthewater.Atapproximately 1658,contractpersonnel commenced UGSwithdrawal fromthereactorvesselinaccordance withprocedure 1-M-0015,
| | TEXT CONTINUATION YEAR SEQUENTIAL REVISION ST LUCIE UNIT 1 05000335 2 OF 4 97 010 00 TEXT ilfmore speceis required, use eddnionel copies of NRC Form 366A/ I17I DESCRIPTION OF THE EVENT On October 27, 1997, St. Lucie Unit 1 was in Mode 6 with the reactor head [EIIS:AB:RCT] removed in preparation for reactor defueling. The containment equipment hatch and personnel access airlock [EIIS:NH] were open, as allowed by Technical Specifications. Control Element Assemblies (CEAs) [EIIS:AA]had been unlatched by personnel in accordance with procedure OP1-0110022, 'Coupling'and Uncoupling of CEA Extension Shafts'. |
| 'ReactorVesselMaintenance | | At approximately 1510, the reactor cavity water level was raised to 55 feet 6 inches to maintain adequate shielding in preparation for lifting the Upper Guide Structure (UGS) [EIIS:AC]. Normally during the lift, only the UGS lift rig is raised above the surface of the water. |
| -SequenceofOperations'. | | At approximately 1658, contract personnel commenced UGS withdrawal from the reactor vessel in accordance with procedure 1-M-0015, 'Reactor Vessel Maintenance - Sequence of Operations'. During the evolution, a camera mounted at the reactor vessel flange level was used to verify lift alignment and clearance. At approximately 1744, as the UGS cleared the alignment pins, a CEA was discovered attached to the UGS, and had been unexpectedly withdrawn from the core. Operations ordered containment integrity to be set, and this was achieved by 1805. |
| Duringtheevolution, acameramountedatthereactorvesselflangelevelwasusedtoverifyliftalignment andclearance.
| | The cause of the CEA remaining attached to the UGS could not immediately be determined. A safety evaluation was performed which concluded that there would be no adverse impact on plant safety or operation should the CEA fall onto the core while completing the UGS move. Procedure 1-M-0015, 'Reactor Vessel Maintenance-Sequence of Operations', was revised to accommodate movement of the UGS with a CEA attached. Since the UGS and lift rig were to be lifted much higher than normal, reactor cavity water level was adjusted to 60 feet to increase shielding. This action was completed at approximately 2222 hours. |
| Atapproximately 1744,astheUGSclearedthealignment pins,aCEAwasdiscovered attachedtotheUGS,andhadbeenunexpectedly withdrawn fromthecore.Operations orderedcontainment integrity tobeset,andthiswasachievedby1805.ThecauseoftheCEAremaining attachedtotheUGScouldnotimmediately bedetermined.
| | In anticipation of receiving high enough containment radiation levels to initiate a Containment Isolation Actuation Signal (CIAS), unnecessary personnel leA containment and the Containment Isolation System (CIS) [EIIS:JM] |
| Asafetyevaluation wasperformed whichconcluded thattherewouldbenoadverseimpactonplantsafetyoroperation shouldtheCEAfallontothecorewhilecompleting theUGSmove.Procedure 1-M-0015,
| | was manually actuated at approximately 0253 on October 28. This was a preplanned actuation performed in accordance with procedure OP1-1600023, 'Refueling Sequencing Guidelines'. |
| 'ReactorVesselMaintenance-SequenceofOperations', | | NAC FOAM 366A I4.95) |
| wasrevisedtoaccommodate movementoftheUGSwithaCEAattached.
| | |
| SincetheUGSandliftrigweretobeliftedmuchhigherthannormal,reactorcavitywaterlevelwasadjustedto60feettoincreaseshielding.
| | NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSIO I4.96) |
| Thisactionwascompleted atapproximately 2222hours.Inanticipation ofreceiving highenoughcontainment radiation levelstoinitiateaContainment Isolation Actuation Signal(CIAS),unnecessary personnel leAcontainment andtheContainment Isolation System(CIS)[EIIS:JM]
| | LICENSEE EVENT REPORT (LER) |
| wasmanuallyactuatedatapproximately 0253onOctober28.Thiswasapreplanned actuation performed inaccordance withprocedure OP1-1600023,
| | TEXT CONTINUATION YEAR SEQUENTIAL REVISION ST LUCIE UNIT 1 05000335 3 OF 4 97 010 00 TEXT flfmore speceis required, use edditionel copies of NRC Form 366A/ I17) |
| 'Refueling Sequencing Guidelines'. | | The UGS lift recommenced at approximately 0320 with only essential personnel in containment. A remote camera situated beneath the UGS monitored the progress, and the CEA remained firmly attached throughout the transit. |
| NACFOAM366AI4.95)
| | At approximately 0324, CIAS channels indicated that containment radiation levels had reached the CIAS initiation threshold. Channel MD, with the most direct exposure to the UGS, registered an area radiation rate of approximately 7 REM per hour, while the other three channels indicated approximately 100 millirem per hour. |
| NRCFORM366AI4.96)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO STLUCIEUNIT105000335YEARSEQUENTIAL REVISION97-010-003OF4TEXTflfmorespeceisrequired, useedditionel copiesofNRCForm366A/I17)TheUGSliftrecommenced atapproximately 0320withonlyessential personnel incontainment.
| | CIS actuates automatically with two channels greater than or equal to 90 millirem per hour. |
| AremotecamerasituatedbeneaththeUGSmonitored theprogress, andtheCEAremainedfirmlyattachedthroughout thetransit.Atapproximately 0324,CIASchannelsindicated thatcontainment radiation levelshadreachedtheCIASinitiation threshold.
| | Once the transit to the refueling cavity was completed, attempts were made to free the CEA but were initially unsuccessful. Subsequently, the CEA was disengaged by operating personnel. The CEA was retrieved and moved to the spent fuel pool for storage. It was identified as CEA 24, a Type 1, full length CEA manufactured by Combustion Engineering. |
| ChannelMD,withthemostdirectexposuretotheUGS,registered anarearadiation rateofapproximately 7REMperhour,whiletheotherthreechannelsindicated approximately 100milliremperhour.CISactuatesautomatically withtwochannelsgreaterthanorequalto90milliremperhour.Oncethetransittotherefueling cavitywascompleted, attemptsweremadetofreetheCEAbutwereinitially unsuccessful.
| | CAUSE OF THE EVENT The cause of the event was failure of the CEA to detach from the UGS. It is currently undetermined whether the CEA was partially latched or friction fit to the CEA Extension Shaft. The root cause is still under investigation. |
| Subsequently, theCEAwasdisengaged byoperating personnel. | | A supplement to this LER will be issued describing the findings of root cause evaluation for the stuck CEA. |
| TheCEAwasretrieved andmovedtothespentfuelpoolforstorage.Itwasidentified asCEA24,aType1,fulllengthCEAmanufactured byCombustion Engineering.
| | ANALYSIS OF THE EVENT This event is reportable under 10 CFR 50.73 (a)(2)(i)(B) as "Any operation or condition prohibited by the plant's Technical Specifications." The Technical Specification violated is Unit 1 Technical Specification 3.9.4: |
| CAUSEOFTHEEVENTThecauseoftheeventwasfailureoftheCEAtodetachfromtheUGS.Itiscurrently undetermined whethertheCEAwaspartially latchedorfrictionfittotheCEAExtension Shaft.Therootcauseisstillunderinvestigation.
| | "The containment penetrations shall be in the following status: |
| Asupplement tothisLERwillbeissueddescribing thefindingsofrootcauseevaluation forthestuckCEA.ANALYSISOFTHEEVENTThiseventisreportable under10CFR50.73(a)(2)(i)(B) as"Anyoperation orcondition prohibited bytheplant'sTechnical Specifications."
| | : a. The equipment door closed and held in place by a minimum of four bolts, |
| TheTechnical Specification violatedisUnit1Technical Specification 3.9.4:"Thecontainment penetrations shallbeinthefollowing status:a.Theequipment doorclosedandheldinplacebyaminimumoffourbolts,b.Aminimumofonedoorineachairlockisclosed,andC.Eachpenetration providing directaccessfromthecontainment atmosphere totheoutsideatmosphere shallbe...(severalconfigurations given).APPLICABILITY:
| | : b. A minimum of one door in each airlock is closed, and C. Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be... (several configurations given). |
| DuringCOREALTERATIONS ormovementofirradiated fuelwithinthecontainment."
| | APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment." |
| NRCFORM366AI4.96)
| | NRC FORM 366A I4.96) |
| NRCFORM366AI4-95)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO STLUCIEUNIT105000335YEARSEQUENTIAL REVISION97-010-004OF4TEXTllfmorespaceisrequired, useadditional copiesofNRCForm366A/I17ITheTechnical Specifications define"corealteration" as"movement ormanipulation ofanyfuel,sources,reactivit controlcomponents, orothercomponents affecting reactivity withinthereactorvesselwiththevesselheadremovedandfuelinthevessel."Normally, liftingaUGSisnotacorealteration, sincetheUGSdoesnotcontainfuel,sources,orcomponents thatcontroloraffectreactivity.
| | |
| However,sinceareactivity controlcomponent (aCEA)wasmovedwiththeUGSinthisevent,acorealteration wasperformed. | | NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSIO I4-95) |
| : Moreover, thecorealteration wasperformed withoutthecontainment penetration statusrequiredbytheTechnical Specification.
| | LICENSEE EVENT REPORT (LER) |
| Penetrations wereplacedintherequiredstatewithinapproximately 20minutesofdiscovery ofthestuckCEA.TheCISactuation wasnotreportable under10CFR50.72,sincetheactuation waspartofapreplanned sequenceaddressed byprocedure. | | TEXT CONTINUATION YEAR SEQUENTIAL REVISION ST LUCIE UNIT 1 05000335 4 OF 4 97 010 00 TEXT llfmore space is required, use additional copies of NRC Form 366A/ I 17I The Technical Specifications define "core alteration" as "movement or manipulation of any fuel, sources, reactivit control components, or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel." Normally, lifting a UGS is not a core alteration, since the UGS does not contain fuel, sources, or components that control or affect reactivity. However, since a reactivity control component (a CEA) was moved with the UGS in this event, a core alteration was performed. Moreover, the core alteration was performed without the containment penetration status required by the Technical Specification. Penetrations were placed in the required state within approximately 20 minutes of discovery of the stuck CEA. |
| TheCISisdesignedtomitigatetheconsequences ofaccidents whichreleaselargeamountsofenergywithinthecontainment structure.
| | The CIS actuation was not reportable under 10 CFR 50.72, since the actuation was part of a preplanned sequence addressed by procedure. The CIS is designed to mitigate the consequences of accidents which release large amounts of energy within the containment structure. There was no such accident in this case, and the CIS actuation was intentional rather than the result of accident conditions. |
| Therewasnosuchaccidentinthiscase,andtheCISactuation wasintentional ratherthantheresultofaccidentconditions.
| | Withdrawal of the stuck CEA from the reactor core did not place the plant in an unanalyzed condition, nor did it place the plant in a condition outside its design basis. Plant procedures address the case of a single CEA not inserted in the core, and substantial shutdown margin was maintained during the course of this event. |
| Withdrawal ofthestuckCEAfromthereactorcoredidnotplacetheplantinanunanalyzed condition, nordiditplacetheplantinacondition outsideitsdesignbasis.Plantprocedures addressthecaseofasingleCEAnotinsertedinthecore,andsubstantial shutdownmarginwasmaintained duringthecourseofthisevent.LER97-001-00 forSt.LucieUnit2documented aneventwithradiological conditions similartothisevent.IntheUnit2event,anexpectedCISactuation occurredastheUGSwaswithdrawn fromthereactor.Theelevatedradiation levelswerecausedbyirradiated incoreinstrumentation segments[EIIS:IG] | | LER 97-001-00 for St. Lucie Unit 2 documented an event with radiological conditions similar to this event. In the Unit 2 event, an expected CIS actuation occurred as the UGS was withdrawn from the reactor. The elevated radiation levels were caused by irradiated incore instrumentation segments [EIIS:IG] which had broken during removal of incores. The Unit 2 event, however, was unlike this event in that there was no core alteration. |
| whichhadbrokenduringremovalofincores.TheUnit2event,however,wasunlikethiseventinthattherewasnocorealteration.
| | I CORRECTIVE ACTIONS Immediate corrective actions included stopping the UGS lift and evaluating dose rates. A condition report was issued and a team was designated to determine the cause of the stuck CEA. The team reviewed potential failure modes and related industry experience, but has not had access to the CEA's extension shaft for evaluation. The unlatch procedure was also reviewed and verified to have been properly performed. Further corrective actions for the stuck CEA will be identified in a supplement to this LER once the root cause has been determined. |
| ICORRECTIVE ACTIONSImmediate corrective actionsincludedstoppingtheUGSliftandevaluating doserates.Acondition reportwasissuedandateamwasdesignated todetermine thecauseofthestuckCEA.Theteamreviewedpotential failuremodesandrelatedindustryexperience, buthasnothadaccesstotheCEA'sextension shaftforevaluation.
| | NAC FOAM 366A I4.95)}} |
| Theunlatchprocedure wasalsoreviewedandverifiedtohavebeenproperlyperformed.
| |
| Furthercorrective actionsforthestuckCEAwillbeidentified inasupplement tothisLERoncetherootcausehasbeendetermined.
| |
| NACFOAM366AI4.95)}}
| |
|
|---|
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 1 S
REGULATE Y INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR:9712030199 , DOC.DATE: 97/11/26 NOTARIZED: NO DOCKET ¹ FACXL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 AUTH. NAME AUTHOR AFFILIATION REVELL,J. Florida Power & Light Co.
STALL,J.A. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
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 UGS move.W/971126 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR i ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
SIZE: l5 E
NOTES:
RECIPIENT COPIES RECIPIENT COPIES 0 ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3 PD 1 1 WIENS,L. 1 1 INTERNAL: ACRS 1 1 2 2 AEOD/SPD/RRAB 1 1 ILE CENT 1 1 NRR/DE/ECGB 1 1 NRR 1 1 NRR/DE/EMEB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DET/EIB 1 1 RGN2 FXLE 01 '1 1 D EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 0
1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 U
NOTE TO ALL "RIDS" RECZPZENTS PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT LISTS THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25
Florida Power & Light Company, 650t South Ocean Drive, Jensen Beach, FL 34957 November 26, 1997 L-97-297 FPL 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Reportable Event: 97-010 Date of Event: October 27, 1997 Inadvertant Core Alteration Prohibited by Technical Specifications Due to Stuck Control Element Assembl CEA 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, J. A. Stall Vice President St. Lucie Plant JAS/JWR Attachment cc: Regional Administrator, USNRC, Region II
,ij Senior Resident Inspector, USNRC, St. Lucie Plant c
/4 97i2030i'tt9 97ii26 PDR ADQCK 05000335 8 PDR lbltttliltjtlllttltajiNI an FPL Group company
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB No. 31604I104 (4.95) EXRRES 04I30/SS ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATOR INFORMATION COLLECTION REQUEST: 60.0 HRS. REPORTED LESSON LEARNED ARE INCORPORATED INTO THE UCENSING PROCESS AND FE LICENSEE EVENT REPORT (LER) BACK TO INDUSTRY. FORWARD COMMINTS REGARDING BURDEN ESTIMAT TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH IT.S F33)
US.NUCLEARREGIAATORY COMMISSION. WASHINGTON. DC 206664001 AND TO THE PAPERWORK REDUCTION PROJECT 13160%1041, OFFICE OI
{See reverse for required number of MANAGEMENTAND BUDGET. WASHINGTON. DC 20603.
digits/characters for each block)
FACIUTY NAME Hi DOCKET NUMBER 121 PAGE 131 ST LUCIE UNIT 1 05000335 1 OF4 TITLE (41 Inadvertant Core Alteration Prohibited by Technical Specifications Due to Stuck Control Element Assembly (CEA)
SEQUENTIAL REVISION FACILIlYNAME DOCKETNUMBER MONTH DAY MONTH OAY YEAR NUMBER NUMBER FACILITYNAME DOCKETNUMBER 10 27 97 97 010 00 11 26 97 OPERATING MODE (9) 20.2201 (b) 20.2203{a)(2)(v) 50.73(a) (2) (i) 50.73(a) (2) (viii)
POWER LEVEL {10) 000 20.2203 (0) (2) (I) 20.2203(a) (3) (ii) 50.73(a)(2)(iii) 73.71 OTHER 20.2203(a) (2)(iii) 50.36(c)(1) 50.73(a) (2)(v) Specify in Abstract befow or in NRC Form 366A 20.2203 (0) (2) (iv) 50.36(c)(2) 50.73(a)(2)(vii)
NAME TELEPHONE NUMBER Snclude Area Code)
Jack Revell, Licensing Engineer (561) 467-7169 CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE REPORTABLE TO NPRDS CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS AC RCT C490 MONTH OAY YEAR EXPECTED YES SUBMISSION X {If yes, complete EXPECTED SUBMISSION DATE). No DATE {15) 02 04 98 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) {16)
On October 27, 1997, St. Lucie Unit 1 was in Mode 6 with the reactor head removed in preparation for defueling. The containment equipment hatch and personnel access airlock were open, as allowed by Technical Specifications. Personnel commenced Upper Guide Structure (UGS) withdrawal from the reactor vessel in accordance with procedures. As the UGS cleared the alignment pins, a Control Element Assembly (CEA) was discovered attached to the UGS, and had been unexpectedly withdrawn from the core. This constituted a core alteration without the containment penetration status required by Technical Specifications. Containment integrity was set within about 20 minutes of discovery of the stuck CEA.
The cause of the CEA remaining attached to the UGS could not immediately be determined. A safety evaluation was performed and a procedural revision made to continue the UGS move. Reactor cavity water level was raised to increase shielding. Anticipating elevated containment radiation levels, the Containment Isolation System (CIS) was manually actuated prior to continuing the lift.
The UGS lift recommenced on October 28. A remote camera situated beneath the UGS monitored the progress, and the CEA remained attached throughout the transit. Once the transit to the refueling cavity was completed, the CEA was recovered from the UGS. The root cause of the event is still under investigation. Further corrective actions will be identified once the root cause is determined.
NRC FORM 366 (4-95)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSIO (4.95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION YEAR SEQUENTIAL REVISION ST LUCIE UNIT 1 05000335 2 OF 4 97 010 00 TEXT ilfmore speceis required, use eddnionel copies of NRC Form 366A/ I17I DESCRIPTION OF THE EVENT On October 27, 1997, St. Lucie Unit 1 was in Mode 6 with the reactor head [EIIS:AB:RCT] removed in preparation for reactor defueling. The containment equipment hatch and personnel access airlock [EIIS:NH] were open, as allowed by Technical Specifications. Control Element Assemblies (CEAs) [EIIS:AA]had been unlatched by personnel in accordance with procedure OP1-0110022, 'Coupling'and Uncoupling of CEA Extension Shafts'.
At approximately 1510, the reactor cavity water level was raised to 55 feet 6 inches to maintain adequate shielding in preparation for lifting the Upper Guide Structure (UGS) [EIIS:AC]. Normally during the lift, only the UGS lift rig is raised above the surface of the water.
At approximately 1658, contract personnel commenced UGS withdrawal from the reactor vessel in accordance with procedure 1-M-0015, 'Reactor Vessel Maintenance - Sequence of Operations'. During the evolution, a camera mounted at the reactor vessel flange level was used to verify lift alignment and clearance. At approximately 1744, as the UGS cleared the alignment pins, a CEA was discovered attached to the UGS, and had been unexpectedly withdrawn from the core. Operations ordered containment integrity to be set, and this was achieved by 1805.
The cause of the CEA remaining attached to the UGS could not immediately be determined. A safety evaluation was performed which concluded that there would be no adverse impact on plant safety or operation should the CEA fall onto the core while completing the UGS move. Procedure 1-M-0015, 'Reactor Vessel Maintenance-Sequence of Operations', was revised to accommodate movement of the UGS with a CEA attached. Since the UGS and lift rig were to be lifted much higher than normal, reactor cavity water level was adjusted to 60 feet to increase shielding. This action was completed at approximately 2222 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.45471e-4 months <br />.
In anticipation of receiving high enough containment radiation levels to initiate a Containment Isolation Actuation Signal (CIAS), unnecessary personnel leA containment and the Containment Isolation System (CIS) [EIIS:JM]
was manually actuated at approximately 0253 on October 28. This was a preplanned actuation performed in accordance with procedure OP1-1600023, 'Refueling Sequencing Guidelines'.
NAC FOAM 366A I4.95)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSIO I4.96)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION YEAR SEQUENTIAL REVISION ST LUCIE UNIT 1 05000335 3 OF 4 97 010 00 TEXT flfmore speceis required, use edditionel copies of NRC Form 366A/ I17)
The UGS lift recommenced at approximately 0320 with only essential personnel in containment. A remote camera situated beneath the UGS monitored the progress, and the CEA remained firmly attached throughout the transit.
At approximately 0324, CIAS channels indicated that containment radiation levels had reached the CIAS initiation threshold. Channel MD, with the most direct exposure to the UGS, registered an area radiation rate of approximately 7 REM per hour, while the other three channels indicated approximately 100 millirem per hour.
CIS actuates automatically with two channels greater than or equal to 90 millirem per hour.
Once the transit to the refueling cavity was completed, attempts were made to free the CEA but were initially unsuccessful. Subsequently, the CEA was disengaged by operating personnel. The CEA was retrieved and moved to the spent fuel pool for storage. It was identified as CEA 24, a Type 1, full length CEA manufactured by Combustion Engineering.
CAUSE OF THE EVENT The cause of the event was failure of the CEA to detach from the UGS. It is currently undetermined whether the CEA was partially latched or friction fit to the CEA Extension Shaft. The root cause is still under investigation.
A supplement to this LER will be issued describing the findings of root cause evaluation for the stuck CEA.
ANALYSIS OF THE EVENT This event is reportable under 10 CFR 50.73 (a)(2)(i)(B) as "Any operation or condition prohibited by the plant's Technical Specifications." The Technical Specification violated is Unit 1 Technical Specification 3.9.4:
"The containment penetrations shall be in the following status:
- a. The equipment door closed and held in place by a minimum of four bolts,
- b. A minimum of one door in each airlock is closed, and C. Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be... (several configurations given).
APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment."
NRC FORM 366A I4.96)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSIO I4-95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION YEAR SEQUENTIAL REVISION ST LUCIE UNIT 1 05000335 4 OF 4 97 010 00 TEXT llfmore space is required, use additional copies of NRC Form 366A/ I 17I The Technical Specifications define "core alteration" as "movement or manipulation of any fuel, sources, reactivit control components, or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel." Normally, lifting a UGS is not a core alteration, since the UGS does not contain fuel, sources, or components that control or affect reactivity. However, since a reactivity control component (a CEA) was moved with the UGS in this event, a core alteration was performed. Moreover, the core alteration was performed without the containment penetration status required by the Technical Specification. Penetrations were placed in the required state within approximately 20 minutes of discovery of the stuck CEA.
The CIS actuation was not reportable under 10 CFR 50.72, since the actuation was part of a preplanned sequence addressed by procedure. The CIS is designed to mitigate the consequences of accidents which release large amounts of energy within the containment structure. There was no such accident in this case, and the CIS actuation was intentional rather than the result of accident conditions.
Withdrawal of the stuck CEA from the reactor core did not place the plant in an unanalyzed condition, nor did it place the plant in a condition outside its design basis. Plant procedures address the case of a single CEA not inserted in the core, and substantial shutdown margin was maintained during the course of this event.
LER 97-001-00 for St. Lucie Unit 2 documented an event with radiological conditions similar to this event. In the Unit 2 event, an expected CIS actuation occurred as the UGS was withdrawn from the reactor. The elevated radiation levels were caused by irradiated incore instrumentation segments [EIIS:IG] which had broken during removal of incores. The Unit 2 event, however, was unlike this event in that there was no core alteration.
I CORRECTIVE ACTIONS Immediate corrective actions included stopping the UGS lift and evaluating dose rates. A condition report was issued and a team was designated to determine the cause of the stuck CEA. The team reviewed potential failure modes and related industry experience, but has not had access to the CEA's extension shaft for evaluation. The unlatch procedure was also reviewed and verified to have been properly performed. Further corrective actions for the stuck CEA will be identified in a supplement to this LER once the root cause has been determined.
NAC FOAM 366A I4.95)
