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| {{#Wiki_filter:~CA.TEGORYREGULATORY INFORMATION DISTRIBUTION SYSTEM(RZDS)ACCESSION NBR:9812140132 DOC.DATE: | | {{#Wiki_filter:~CA.TE GORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RZDS)ACCESSION NBR:9812140132 DOC.DATE: 98/12/08 NOTARIZED: |
| 98/12/08NOTARIZED: | | NO FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M AUTH.NAME AUTHOR AFFILIATION WEBER,L.Indiana Michigan Power Co.SAMPSON,'J.R. |
| NOFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaMAUTH.NAMEAUTHORAFFILIATION WEBER,L.IndianaMichiganPowerCo.SAMPSON,'J.R.
| | Indiana Michigan Power Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000315 |
| IndianaMichiganPowerCo.RECIP.NAME RECIPIENT AFFILIATION DOCKET05000315
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER98-039-01 reEOPstepconflicts withsmallbreakLOCAanalysis.LER 98-039-00 hasbeencanceled.
| | LER 98-039-01 re EOP step conflicts with small break LOCA analysis.LER 98-039-00 has been canceled.With 981208 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL J SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD3-3 PD INTERNAL: AEOD D RAB FILE CE NRR DE EELB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RGN3 FILE 01 COPIES LTTR ENCL 1 1 2'1 1 1 1.1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME STANG,J AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HOHB NRR/DRPM/PECB RES/DET/EIB COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR 1 1 1 1 1 1 LITCO BRYCE,J H NOAC QUEENER,DS NUDOCS FULL TXT 1 1'1 1 1 D NOTE TO ALL"RIDS" RECIPIENTS: |
| With981208ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR IENCLJSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:RECIPIENT IDCODE/NAME PD3-3PDINTERNAL:
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| AEODDRABFILECENRRDEEELBNRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RGN3FILE01COPIESLTTRENCL112'1111.11111111RECIPIENT IDCODE/NAME STANG,JAEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HOHB NRR/DRPM/PECB RES/DET/EIB COPIESLTTRENCL11111111111111EXTERNAL:
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| LSTLOBBYWARDNOACPOORE,W.NRCPDR111111LITCOBRYCE,JHNOACQUEENER,DS NUDOCSFULLTXT11'111DNOTETOALL"RIDS"RECIPIENTS:
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| PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROZDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
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| IndianaMichiganPowerCompanyCowNuaew~~~Ran~M).ecioa616MN)lZINDIANANICHIGANIaOWKRDecember8,1998UnitedStatesNuclearRegulatory Commission DocumentControlDeskWashington, DC20555Operating LicenseDPR-58DocketNo.50-315DocumentControlManager:Inaccordance withthecriteriaestablished by10CFR50.73entitledLicenseeEventLER315/98-039-01, "Retraction
| | Indiana Michigan Power Company Cow Nuaew~~~Ran~M).e cioa 616 M N)l Z INDIANA NICHIGAN IaOWKR December 8, 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating License DPR-58 Docket No.50-315 Document Control Manager: In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event LER 315/98-039-01,"Retraction |
| -Emergency Operation Procedure StepConflicts withSmallBreakLOCAAnalysis". | | -Emergency Operation Procedure Step Conflicts with Small Break LOCA Analysis". |
| Nocommitments wereidentified inthisdocument.
| | No commitments were identified in this document.Sincerely, J.R.Sampson Site Vice President Imbd Attachment J.'L.Caldwell (Acting), Region III R.P.Powers P.A.Barrett J.B.Kingseed R.-Whale D.Hahn Records Center, INPONRC Resident Inspector 9812140132 981208 PDR ADQCK 05000315 S PDR NRC,Form 366 U.S.NUCLEAR REGULATORY COMMISSION (6-1998)LICENSEE EVENT REPORT (LER)(See.reverse for required number of digits/characters for each block)APPROVED BY OM8 NO.31604104 EXPIRES 06/30/2001 KSTSIATKD BURDEN PKR RESPONSE TO COMPLY WITH TIBS MANDATORY INFORMATlON COLLKCTCN RKOLJKST'. |
| Sincerely, J.R.SampsonSiteVicePresident ImbdAttachment J.'L.Caldwell(Acting), | | $0.0 HRS.REPORTED LESSONS LEARNED ARE NCORPORATKO erTO THK LJCKNSLNO PROCESS ANO FKO BACK TO INOLJSTRY. |
| RegionIIIR.P.PowersP.A.BarrettJ.B.KingseedR.-WhaleD.HahnRecordsCenter,INPONRCResidentInspector 9812140132 981208PDRADQCK05000315SPDR NRC,Form366U.S.NUCLEARREGULATORY COMMISSION (6-1998)LICENSEEEVENTREPORT(LER)(See.reverse forrequirednumberofdigits/characters foreachblock)APPROVEDBYOM8NO.31604104EXPIRES06/30/2001 KSTSIATKD BURDENPKRRESPONSETOCOMPLYWITHTIBSMANDATORY INFORMATlON COLLKCTCN RKOLJKST'.
| | FCRWARO COMMENTS RKCAROLNO BLIOKN KSTSIATK TO THK~ORMATION ANO RECORDS IMNACKMKNT BRANCH IT4 FS)).U.S.NUCLEAR RKGLAATORY COMMISSION. |
| $0.0HRS.REPORTEDLESSONSLEARNEDARENCORPORATKO erTOTHKLJCKNSLNO PROCESSANOFKOBACKTOINOLJSTRY. | |
| FCRWAROCOMMENTSRKCAROLNO BLIOKNKSTSIATKTOTHK~ORMATION ANORECORDSIMNACKMKNT BRANCHIT4FS)).U.S.NUCLEARRKGLAATORY COMMISSION.
| |
| WASH)NOTCH. | | WASH)NOTCH. |
| DC2055%001, ANOTOTHKP~RKOLJCTNtr PROJECTL5)5001LH).
| | DC 2055%001, ANO TO THK P~RKOLJCTNtr PROJECT L5)5001LH). |
| OFFlCKOFIlAWCKMKNTANOBLJOCKT,WAS)eNOTOJL OCFACIUTYNAMEII)TITLE<<)CookNuclearPlantUnit1DOCKETNUMBER(2)05000-315 PAGEP)1of2Retraction
| | OFFlCK OF IlAW CKMKNT ANO BLJOCKT, WAS)eNOTOJL OC FACIUTY NAME II)TITLE<<)Cook Nuclear Plant Unit 1 DOCKET NUMBER (2)05000-315 PAGE P)1 of 2 Retraction |
| -Emergency Operating Procedure StepConflicts withSmallBreakLOCAAnalysisEVENTDATE(5)LERNUMBER(6)REPORTDATE(7)OTHERFACILITIES INVOLVED(8)MONTHDAY0824YEARYEARSEQUENTIAL NUMBERREVISIONNUMBER19981998-039-01MONTH12DAY081998AILINAMCookUnit2AILINUMB05000-316 DNUMOPERATING MODE(9)50.73(a)(2)(viii) 5o.73(a)(2)(i) 20.2203(a)(2)(v) 20.2201(b)THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFRg:(Checkoneormore)(11)POWERLEVEL(10)00O'P~P~F%"k~ | | -Emergency Operating Procedure Step Conflicts with Small Break LOCA Analysis EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (8)MONTH DAY 08 24 YEAR YEAR SEQUENTIAL NUMBER REVISION NUMBER 1998 1998-039-01 MONTH 12 DAY 08 1998 A ILI NAM Cook Unit 2 A ILI NUMB 05000-316 D NUM OPERATING MODE (9)50.73(a)(2)(viii) 5o.73(a)(2)(i) 20.2203(a)(2)(v) 20.2201 (b)THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR g: (Check one or more)(11)POWER LEVEL (10)00 O'P~P~F%"k~ |
| 'ti45'NE623J('~820.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2) | | 'ti45'N E 623 J ('~8 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2) |
| LICENSEECONTACTFORTHISLER(12)50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(x) 73.71OTHERSPeoifyhAbelraclbe)orrornNRCForllr 368AMr.LarryWeber,Operations ManagerTELEPHONE NUMBER(B)etudeAreaCode)616/465-5901 X2443COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT(13)CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TOEPIXCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TOEPIXSUPPLEMENTAL REPORTEXPECTED(14)YES(IfYes,completeEXPECTEDSUBMISSION DATEXNOEXPECTEDSUBMISSION DATE15MONTHDAYAbstract(Limitto1400spaces,l.e.,approximately 15single-spaced typewritten lines)(16)OnAugust24,1998,withbothunitsinColdShutdown, areviewofthecurrentrevisionofEmergency Operating Procedure (EOP),"Transfer toColdLegRecirculation,"
| | LICENSEE CONTACT FOR THIS LER (12)50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(x) 73.71 OTHER SPeoify h Abelracl be)orr or nNRCForllr 368A Mr.Larry Weber, Operations Manager TELEPHONE NUMBER (B)etude Area Code)616/465-5901 X2443 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX SUPPLEMENTAL REPORT EXPECTED (14)YES (If Yes, complete EXPECTED SUBMISSION DATE X NO EXPECTED SUBMISSION DATE 15 MONTH DAY Abstract (Limit to 1400 spaces, l.e., approximately 15 single-spaced typewritten lines)(16)On August 24, 1998, with both units in Cold Shutdown, a review of the current revision of Emergency Operating Procedure (EOP),"Transfer to Cold Leg Recirculation," identified a step that did not appear to satisfy an assumption in the Westinghouse Small Break Loss of Coolant Accident (SBLOCA)analysis at the point in time when high head safety injection (Sl)pump flow would be delivered to the reactor coolant system (RCS).The EOP step required the Sl pumps to be turned off if RCS pressure exceeded 1250 psig (1000 psig for adverse containment condition) after isolation of the pump minimum flow line returning SI pump flow to the refueling water storage tank (RWST).The Sl pumps would be turned off to prevent pump damage due to inadequate pump minimum flow.This would leave only the centrifugal charging pumps injecting to the RCS during a SBLOCA with high RCS pressure.The Westinghouse analysis assumes SI pump injection to the RCS whenever RCS pressure is less than 1350 psig.When RCS pressure instrument uncertainty was applied, the EOP step to terminate Sl was considered capable of placing the plant in a condition outside of the safety analysis during a SBLOCA that allowed RCS pressure to remain high but less than 1350 psig.An ENS notification was made on August 24, 1998, at 1705 hours EDT in accordance with 10CFR50.72(b)(2)(i). |
| identified astepthatdidnotappeartosatisfyanassumption intheWestinghouse SmallBreakLossofCoolantAccident(SBLOCA)analysisatthepointintimewhenhighheadsafetyinjection (Sl)pumpflowwouldbedelivered tothereactorcoolantsystem(RCS).TheEOPsteprequiredtheSlpumpstobeturnedoffifRCSpressureexceeded1250psig(1000psigforadversecontainment condition) afterisolation ofthepumpminimumflowlinereturning SIpumpflowtotherefueling waterstoragetank(RWST).TheSlpumpswouldbeturnedofftopreventpumpdamageduetoinadequate pumpminimumflow.Thiswouldleaveonlythecentrifugal chargingpumpsinjecting totheRCSduringaSBLOCAwithhighRCSpressure. | | An interim LER was submitted on September 22, 1998, in accordance with 10CFR50.73(a)(2)(ii). |
| TheWestinghouse analysisassumesSIpumpinjection totheRCSwheneverRCSpressureislessthan1350psig.WhenRCSpressureinstrument uncertainty wasapplied,theEOPsteptoterminate Slwasconsidered capableofplacingtheplantinacondition outsideofthesafetyanalysisduringaSBLOCAthatallowedRCSpressuretoremainhighbutlessthan1350psig.AnENSnotification wasmadeonAugust24,1998,at1705hoursEDTinaccordance with10CFR50.72(b)(2)(i).
| | Operations provided Westinghouse with details of the use of the EOP step and requested an analysis of the significance of the condition. |
| AninterimLERwassubmitted onSeptember 22,1998,inaccordance with10CFR50.73(a)(2)(ii).
| | On November 4, 1998, Westinghouse provided an assessment based on its analysis.Our review of the assessment confirmed that by use of the EOPs the plant would not have been placed in a condition where the Sl pump termination criterion would have been reached.Therefore, the plant was within its analyzed basis, and LER 315/98-039-00 is being retracted. |
| Operations providedWestinghouse withdetailsoftheuseoftheEOPstepandrequested ananalysisofthesignificance ofthecondition. | | NRC FORM 366 (6-1998) |
| OnNovember4,1998,Westinghouse providedanassessment basedonitsanalysis.
| | NRC FORM 366A U.S.NUCLEAR REGULATORY COMMISSION (6-1998)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME (1)Cook Nuclear Plant Unit 1 DOCKET NUMBER(2)05000-315 YEAR 1998 LER NUMBER (6)SEQUENTIAL NUMBER 039 REVISION NUMBER 01 PAGE (3)2of2 TEXT (lf moro speceis required, use eddiiional copies or NRC Form (366A)(17)On August 24, 1998, with both units in Cold Shutdown, a review of the current revision, Revision 5, of Emergency Operating Procedure (EOP)01/02-OHP 4023.ES-1.3,"Transfer to Cold Leg Recirculation," identified a step that did not appear to satisfy an assumption in the Westinghouse Small Break Loss of Coolant Accident (SBLOCA)analysis at the time when high head safety injection (Sl)pump flow would be delivered to the reactor coolant system (RCS).The EOP step required the Sl pumps to be turned off if RCS pressure exceeded 1250 pounds per square inch gage (psig), 1000 psig for adverse containment conditions, after isolation of the pump minimum flow line returning Sl pump flow to the refueling water storage tank (RWST).The Sl pumps would be turned off to prevent pump damage due to inadequate pump minimum flow.The normal minimum flow path to the RWST cannot be used during a LOCA because it is undesirable to pump radioactively contaminated water from the containment sump to the RWST.Therefore, prior to switching SI pump suction from the RWST to the containment sump, as directed by the EOP, the Sl pump minimum flow lines to the RWST would be isolated.The Sl pumps would then have to rely on RCS injection flow to satisfy the requirement for adequate pump minimum flow of approximately 70 gallons per minute.This flow rate is determined by actual RCS pressure and the physical characteristics of the pumps.Indicated RCS pressure was chosen as the procedural criterion for operators to determine if the Sl pumps needed to be stopped.Earlier revisions of the procedure had directed the pumps to be stopped at various indicated RCS pressures between 1000 psig and 1630 psig.Some revisions of the procedure also used indicated low Sl flow to direct stopping the pumps.Due to instrument uncertainty the indicated values could have represented higher or lower actual values.During a SBLOCA, pressure in containment could be high enough to have an adverse effect on RCS pressure instruments. |
| Ourreviewoftheassessment confirmed thatbyuseoftheEOPstheplantwouldnothavebeenplacedinacondition wheretheSlpumptermination criterion wouldhavebeenreached.Therefore, theplantwaswithinitsanalyzedbasis,andLER315/98-039-00isbeingretracted.
| | In such an adverse containment condition, instrument uncertainty could be greater.Turning off the high head Sl pumps would leave only the centrifugal charging pumps injecting to the RCS during a SBLOCA with persistent high RCS pressure.The Westinghouse SBLOCA analysis assumes high head Sl pump injection to the RCS whenever RCS pressure is less than approximately 1350 psig during a SBLOCA.When instrument uncertainty was applied, the EOP step to terminate high head Sl was considered capable of placing the plant in a condition outside of the safety analysis during a SBLOCA that allowed RCS pressure to remain high, but less than 1350 psig.An ENS notification was made on August 24, 1998, at 1705 hours EDT in accordance with 10CFR50.72(b)(2)(i). |
| NRCFORM366(6-1998)
| | An interim LER was submitted on September 22, 1998, in accordance with 10CFR50.73 (a)(2)(ii). |
| NRCFORM366AU.S.NUCLEARREGULATORY COMMISSION (6-1998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION FACILITYNAME(1)CookNuclearPlantUnit1DOCKETNUMBER(2) 05000-315 YEAR1998LERNUMBER(6)SEQUENTIAL NUMBER039REVISIONNUMBER01PAGE(3)2of2TEXT(lfmorospeceisrequired, useeddiiional copiesorNRCForm(366A)(17)OnAugust24,1998,withbothunitsinColdShutdown, areviewofthecurrentrevision, Revision5,ofEmergency Operating Procedure (EOP)01/02-OHP 4023.ES-1.3, "Transfer toColdLegRecirculation,"
| | Operations provided Westinghouse with details on the use of the EOP step and requested an analysis of the significance of the condition. |
| identified astepthatdidnotappeartosatisfyanassumption intheWestinghouse SmallBreakLossofCoolantAccident(SBLOCA)analysisatthetimewhenhighheadsafetyinjection (Sl)pumpflowwouldbedelivered tothereactorcoolantsystem(RCS).TheEOPsteprequiredtheSlpumpstobeturnedoffifRCSpressureexceeded1250poundspersquareinchgage(psig),1000psigforadversecontainment conditions, afterisolation ofthepumpminimumflowlinereturning Slpumpflowtotherefueling waterstoragetank(RWST).TheSlpumpswouldbeturnedofftopreventpumpdamageduetoinadequate pumpminimumflow.ThenormalminimumflowpathtotheRWSTcannotbeusedduringaLOCAbecauseitisundesirable topumpradioactively contaminated waterfromthecontainment sumptotheRWST.Therefore, priortoswitching SIpumpsuctionfromtheRWSTtothecontainment sump,asdirectedbytheEOP,theSlpumpminimumflowlinestotheRWSTwouldbeisolated. | | On November 4, 1998, Westinghouse provided its assessment of the condition based on its analysis.The Westinghouse assessment examines whether a design basis SBLOCA for the Cook Nuclear Plant would lead to conditions required by the various revisions of the procedure for Sl termination. |
| TheSlpumpswouldthenhavetorelyonRCSinjection flowtosatisfytherequirement foradequatepumpminimumflowofapproximately 70gallonsperminute.Thisflowrateisdetermined byactualRCSpressureandthephysicalcharacteristics ofthepumps.Indicated RCSpressurewaschosenastheprocedural criterion foroperators todetermine iftheSlpumpsneededtobestopped.Earlierrevisions oftheprocedure haddirectedthepumpstobestoppedatvariousindicated RCSpressures between1000psigand1630psig.Somerevisions oftheprocedure alsousedindicated lowSlflowtodirectstoppingthepumps.Duetoinstrument uncertainty theindicated valuescouldhaverepresented higherorloweractualvalues.DuringaSBLOCA,pressureincontainment couldbehighenoughtohaveanadverseeffectonRCSpressureinstruments.
| | To assess the conditions that could be presented by control room indications following a postulated SBLOCA, design basis simulations using the MAAP4 computer code were used.The effects of plant specific uncertainties were included in the assessment. |
| Insuchanadversecontainment condition, instrument uncertainty couldbegreater.TurningoffthehighheadSlpumpswouldleaveonlythecentrifugal chargingpumpsinjecting totheRCSduringaSBLOCAwithpersistent highRCSpressure.
| | A range of SBLOCA sizes, down to very small breaks that would result in RCS repressurization, was considered. |
| TheWestinghouse SBLOCAanalysisassumeshighheadSlpumpinjection totheRCSwheneverRCSpressureislessthanapproximately 1350psigduringaSBLOCA.Wheninstrument uncertainty wasapplied,theEOPsteptoterminate highheadSlwasconsidered capableofplacingtheplantinacondition outsideofthesafetyanalysisduringaSBLOCAthatallowedRCSpressuretoremainhigh,butlessthan1350psig.AnENSnotification wasmadeonAugust24,1998,at1705hoursEDTinaccordance with10CFR50.72(b)(2)(i).
| | The potential for operation without Sl flow, with RCS pressures as low as 835 pounds per square inch absolute, was considered. |
| AninterimLERwassubmitted onSeptember 22,1998,inaccordance with10CFR50.73 (a)(2)(ii).
| | This.represents the lowest adverse containment RCS pressure when instrument error is considered, without the error due to excess radiation exposure.Excess radiation was not an expected condition. |
| Operations providedWestinghouse withdetailsontheuseoftheEOPstepandrequested ananalysisofthesignificance ofthecondition. | | The assessment concludes that no design basis SBLOCA, requiring one or more Sl pumps, would be deprived of flow as a result of a SBLOCA.The conclusion is cited as applicable for all past operation and also as applying to a proposed future revision of the EOP which would call for stopping the SI pumps when the indicated RCS pressure is 1250 psig (1200 psig for adverse containment). |
| OnNovember4,1998,Westinghouse provideditsassessment ofthecondition basedonitsanalysis.
| | Therefore, the'plant was within its analyzed condition of operation, and LER 315/98-039-00 is being retracted. |
| TheWestinghouse assessment examineswhetheradesignbasisSBLOCAfortheCookNuclearPlantwouldleadtoconditions requiredbythevariousrevisions oftheprocedure forSltermination.
| | NRC FORM 366A (6-1998)}} |
| Toassesstheconditions thatcouldbepresented bycontrolroomindications following apostulated SBLOCA,designbasissimulations usingtheMAAP4computercodewereused.Theeffectsofplantspecificuncertainties wereincludedintheassessment.
| |
| ArangeofSBLOCAsizes,downtoverysmallbreaksthatwouldresultinRCSrepressurization, wasconsidered.
| |
| Thepotential foroperation withoutSlflow,withRCSpressures aslowas835poundspersquareinchabsolute, wasconsidered.
| |
| This.represents thelowestadversecontainment RCSpressurewheninstrument errorisconsidered, withouttheerrorduetoexcessradiation exposure. | |
| Excessradiation wasnotanexpectedcondition.
| |
| Theassessment concludes thatnodesignbasisSBLOCA,requiring oneormoreSlpumps,wouldbedeprivedofflowasaresultofaSBLOCA.Theconclusion iscitedasapplicable forallpastoperation andalsoasapplyingtoaproposedfuturerevisionoftheEOPwhichwouldcallforstoppingtheSIpumpswhentheindicated RCSpressureis1250psig(1200psigforadversecontainment).
| |
| Therefore, the'plantwaswithinitsanalyzedcondition ofoperation, andLER315/98-039-00 isbeingretracted. | |
| NRCFORM366A(6-1998)}}
| |
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LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
ML17335A5171999-02-11011 February 1999
LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted
ML17335A5141999-02-10010 February 1999
LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405
ML17335A5011999-02-0101 February 1999
LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr
ML17335A4951999-01-29029 January 1999
LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr
ML17335A4961999-01-27027 January 1999
LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr
ML17335A4921999-01-19019 January 1999
LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components
ML17335A4721999-01-0606 January 1999
LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing
ML17335A4691999-01-0606 January 1999
LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr
ML17335A4661999-01-0505 January 1999
LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing
ML17335A4631999-01-0404 January 1999
LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr
ML17335A4481998-12-30030 December 1998
LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr
ML17335A4581998-12-28028 December 1998
LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process
ML17335A4281998-12-22022 December 1998
LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event
ML17335A4111998-12-17017 December 1998
LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr
ML17335A4141998-12-16016 December 1998
LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122
ML17335A4181998-12-16016 December 1998
LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria
ML17335A3871998-12-11011 December 1998
LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing
ML17335A3821998-12-0808 December 1998
LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr
ML17335A3781998-12-0707 December 1998
LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr
ML17335A3771998-12-0303 December 1998
LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned
ML17335A3741998-12-0202 December 1998
LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3
1999-09-17
[Table view]
Category:RO)
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
ML17335A5171999-02-11011 February 1999
LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted
ML17335A5141999-02-10010 February 1999
LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405
ML17335A5011999-02-0101 February 1999
LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr
ML17335A4951999-01-29029 January 1999
LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr
ML17335A4961999-01-27027 January 1999
LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr
ML17335A4921999-01-19019 January 1999
LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components
ML17335A4721999-01-0606 January 1999
LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing
ML17335A4691999-01-0606 January 1999
LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr
ML17335A4661999-01-0505 January 1999
LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing
ML17335A4631999-01-0404 January 1999
LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr
ML17335A4481998-12-30030 December 1998
LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr
ML17335A4581998-12-28028 December 1998
LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process
ML17335A4281998-12-22022 December 1998
LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event
ML17335A4111998-12-17017 December 1998
LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr
ML17335A4141998-12-16016 December 1998
LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122
ML17335A4181998-12-16016 December 1998
LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria
ML17335A3871998-12-11011 December 1998
LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing
ML17335A3821998-12-0808 December 1998
LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr
ML17335A3781998-12-0707 December 1998
LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr
ML17335A3771998-12-0303 December 1998
LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned
ML17335A3741998-12-0202 December 1998
LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3
1999-09-17
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17335A5631999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr
ML17335A5621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr
ML17335A5481999-09-30030 September 1999
Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3).
ML17335A5451999-09-28028 September 1999
Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios.
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1481999-09-17017 September 1999
Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2.
ML17326A1211999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr
ML17326A1201999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17335A5461999-08-0202 August 1999
Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates.
ML17326A0871999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr
ML17326A0861999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0511999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr
ML17326A0501999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17326A0061999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr
ML17326A0071999-05-31031 May 1999
Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17335A5301999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr
ML17335A5291999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5491999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr
ML17325B5441999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B5671999-03-0202 March 1999
Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218.
ML17325B4631999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr
ML17325B4621999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
1999-09-30
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~CA.TE GORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RZDS)ACCESSION NBR:9812140132 DOC.DATE: 98/12/08 NOTARIZED:
NO FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M AUTH.NAME AUTHOR AFFILIATION WEBER,L.Indiana Michigan Power Co.SAMPSON,'J.R.
Indiana Michigan Power Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000315
SUBJECT:
LER 98-039-01 re EOP step conflicts with small break LOCA analysis.LER 98-039-00 has been canceled.With 981208 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I ENCL J SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD3-3 PD INTERNAL: AEOD D RAB FILE CE NRR DE EELB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RGN3 FILE 01 COPIES LTTR ENCL 1 1 2'1 1 1 1.1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME STANG,J AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HOHB NRR/DRPM/PECB RES/DET/EIB COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR 1 1 1 1 1 1 LITCO BRYCE,J H NOAC QUEENER,DS NUDOCS FULL TXT 1 1'1 1 1 D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROZ DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22
Indiana Michigan Power Company Cow Nuaew~~~Ran~M).e cioa 616 M N)l Z INDIANA NICHIGAN IaOWKR December 8, 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating License DPR-58 Docket No.50-315 Document Control Manager: In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event LER 315/98-039-01,"Retraction
-Emergency Operation Procedure Step Conflicts with Small Break LOCA Analysis".
No commitments were identified in this document.Sincerely, J.R.Sampson Site Vice President Imbd Attachment J.'L.Caldwell (Acting), Region III R.P.Powers P.A.Barrett J.B.Kingseed R.-Whale D.Hahn Records Center, INPONRC Resident Inspector 9812140132 981208 PDR ADQCK 05000315 S PDR NRC,Form 366 U.S.NUCLEAR REGULATORY COMMISSION (6-1998)LICENSEE EVENT REPORT (LER)(See.reverse for required number of digits/characters for each block)APPROVED BY OM8 NO.31604104 EXPIRES 06/30/2001 KSTSIATKD BURDEN PKR RESPONSE TO COMPLY WITH TIBS MANDATORY INFORMATlON COLLKCTCN RKOLJKST'.
$0.0 HRS.REPORTED LESSONS LEARNED ARE NCORPORATKO erTO THK LJCKNSLNO PROCESS ANO FKO BACK TO INOLJSTRY.
FCRWARO COMMENTS RKCAROLNO BLIOKN KSTSIATK TO THK~ORMATION ANO RECORDS IMNACKMKNT BRANCH IT4 FS)).U.S.NUCLEAR RKGLAATORY COMMISSION.
WASH)NOTCH.
DC 2055%001, ANO TO THK P~RKOLJCTNtr PROJECT L5)5001LH).
OFFlCK OF IlAW CKMKNT ANO BLJOCKT, WAS)eNOTOJL OC FACIUTY NAME II)TITLE<<)Cook Nuclear Plant Unit 1 DOCKET NUMBER (2)05000-315 PAGE P)1 of 2 Retraction
-Emergency Operating Procedure Step Conflicts with Small Break LOCA Analysis EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (8)MONTH DAY 08 24 YEAR YEAR SEQUENTIAL NUMBER REVISION NUMBER 1998 1998-039-01 MONTH 12 DAY 08 1998 A ILI NAM Cook Unit 2 A ILI NUMB 05000-316 D NUM OPERATING MODE (9)50.73(a)(2)(viii) 5o.73(a)(2)(i) 20.2203(a)(2)(v) 20.2201 (b)THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR g: (Check one or more)(11)POWER LEVEL (10)00 O'P~P~F%"k~
'ti45'N E 623 J ('~8 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)
LICENSEE CONTACT FOR THIS LER (12)50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(x) 73.71 OTHER SPeoify h Abelracl be)orr or nNRCForllr 368A Mr.Larry Weber, Operations Manager TELEPHONE NUMBER (B)etude Area Code)616/465-5901 X2443 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX SUPPLEMENTAL REPORT EXPECTED (14)YES (If Yes, complete EXPECTED SUBMISSION DATE X NO EXPECTED SUBMISSION DATE 15 MONTH DAY Abstract (Limit to 1400 spaces, l.e., approximately 15 single-spaced typewritten lines)(16)On August 24, 1998, with both units in Cold Shutdown, a review of the current revision of Emergency Operating Procedure (EOP),"Transfer to Cold Leg Recirculation," identified a step that did not appear to satisfy an assumption in the Westinghouse Small Break Loss of Coolant Accident (SBLOCA)analysis at the point in time when high head safety injection (Sl)pump flow would be delivered to the reactor coolant system (RCS).The EOP step required the Sl pumps to be turned off if RCS pressure exceeded 1250 psig (1000 psig for adverse containment condition) after isolation of the pump minimum flow line returning SI pump flow to the refueling water storage tank (RWST).The Sl pumps would be turned off to prevent pump damage due to inadequate pump minimum flow.This would leave only the centrifugal charging pumps injecting to the RCS during a SBLOCA with high RCS pressure.The Westinghouse analysis assumes SI pump injection to the RCS whenever RCS pressure is less than 1350 psig.When RCS pressure instrument uncertainty was applied, the EOP step to terminate Sl was considered capable of placing the plant in a condition outside of the safety analysis during a SBLOCA that allowed RCS pressure to remain high but less than 1350 psig.An ENS notification was made on August 24, 1998, at 1705 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.487525e-4 months <br /> EDT in accordance with 10CFR50.72(b)(2)(i).
An interim LER was submitted on September 22, 1998, in accordance with 10CFR50.73(a)(2)(ii).
Operations provided Westinghouse with details of the use of the EOP step and requested an analysis of the significance of the condition.
On November 4, 1998, Westinghouse provided an assessment based on its analysis.Our review of the assessment confirmed that by use of the EOPs the plant would not have been placed in a condition where the Sl pump termination criterion would have been reached.Therefore, the plant was within its analyzed basis, and LER 315/98-039-00 is being retracted.
NRC FORM 366 (6-1998)
NRC FORM 366A U.S.NUCLEAR REGULATORY COMMISSION (6-1998)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME (1)Cook Nuclear Plant Unit 1 DOCKET NUMBER(2)05000-315 YEAR 1998 LER NUMBER (6)SEQUENTIAL NUMBER 039 REVISION NUMBER 01 PAGE (3)2of2 TEXT (lf moro speceis required, use eddiiional copies or NRC Form (366A)(17)On August 24, 1998, with both units in Cold Shutdown, a review of the current revision, Revision 5, of Emergency Operating Procedure (EOP)01/02-OHP 4023.ES-1.3,"Transfer to Cold Leg Recirculation," identified a step that did not appear to satisfy an assumption in the Westinghouse Small Break Loss of Coolant Accident (SBLOCA)analysis at the time when high head safety injection (Sl)pump flow would be delivered to the reactor coolant system (RCS).The EOP step required the Sl pumps to be turned off if RCS pressure exceeded 1250 pounds per square inch gage (psig), 1000 psig for adverse containment conditions, after isolation of the pump minimum flow line returning Sl pump flow to the refueling water storage tank (RWST).The Sl pumps would be turned off to prevent pump damage due to inadequate pump minimum flow.The normal minimum flow path to the RWST cannot be used during a LOCA because it is undesirable to pump radioactively contaminated water from the containment sump to the RWST.Therefore, prior to switching SI pump suction from the RWST to the containment sump, as directed by the EOP, the Sl pump minimum flow lines to the RWST would be isolated.The Sl pumps would then have to rely on RCS injection flow to satisfy the requirement for adequate pump minimum flow of approximately 70 gallons per minute.This flow rate is determined by actual RCS pressure and the physical characteristics of the pumps.Indicated RCS pressure was chosen as the procedural criterion for operators to determine if the Sl pumps needed to be stopped.Earlier revisions of the procedure had directed the pumps to be stopped at various indicated RCS pressures between 1000 psig and 1630 psig.Some revisions of the procedure also used indicated low Sl flow to direct stopping the pumps.Due to instrument uncertainty the indicated values could have represented higher or lower actual values.During a SBLOCA, pressure in containment could be high enough to have an adverse effect on RCS pressure instruments.
In such an adverse containment condition, instrument uncertainty could be greater.Turning off the high head Sl pumps would leave only the centrifugal charging pumps injecting to the RCS during a SBLOCA with persistent high RCS pressure.The Westinghouse SBLOCA analysis assumes high head Sl pump injection to the RCS whenever RCS pressure is less than approximately 1350 psig during a SBLOCA.When instrument uncertainty was applied, the EOP step to terminate high head Sl was considered capable of placing the plant in a condition outside of the safety analysis during a SBLOCA that allowed RCS pressure to remain high, but less than 1350 psig.An ENS notification was made on August 24, 1998, at 1705 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.487525e-4 months <br /> EDT in accordance with 10CFR50.72(b)(2)(i).
An interim LER was submitted on September 22, 1998, in accordance with 10CFR50.73 (a)(2)(ii).
Operations provided Westinghouse with details on the use of the EOP step and requested an analysis of the significance of the condition.
On November 4, 1998, Westinghouse provided its assessment of the condition based on its analysis.The Westinghouse assessment examines whether a design basis SBLOCA for the Cook Nuclear Plant would lead to conditions required by the various revisions of the procedure for Sl termination.
To assess the conditions that could be presented by control room indications following a postulated SBLOCA, design basis simulations using the MAAP4 computer code were used.The effects of plant specific uncertainties were included in the assessment.
A range of SBLOCA sizes, down to very small breaks that would result in RCS repressurization, was considered.
The potential for operation without Sl flow, with RCS pressures as low as 835 pounds per square inch absolute, was considered.
This.represents the lowest adverse containment RCS pressure when instrument error is considered, without the error due to excess radiation exposure.Excess radiation was not an expected condition.
The assessment concludes that no design basis SBLOCA, requiring one or more Sl pumps, would be deprived of flow as a result of a SBLOCA.The conclusion is cited as applicable for all past operation and also as applying to a proposed future revision of the EOP which would call for stopping the SI pumps when the indicated RCS pressure is 1250 psig (1200 psig for adverse containment).
Therefore, the'plant was within its analyzed condition of operation, and LER 315/98-039-00 is being retracted.
NRC FORM 366A (6-1998)
