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| | issue date = 01/24/1995 | | | issue date = 01/24/1995 |
| | title = LER 94-014-00:on 941225,discovered That TS Surveillance 4.11.2.1.2 Gland Seal Exhaust Weekly Gaseous Effluent Grab Sample Not Completed for 941217-25.Caused by Personnel Error.Surveillance Schedule Sheet modified.W/950124 Ltr | | | title = LER 94-014-00:on 941225,discovered That TS Surveillance 4.11.2.1.2 Gland Seal Exhaust Weekly Gaseous Effluent Grab Sample Not Completed for 941217-25.Caused by Personnel Error.Surveillance Schedule Sheet modified.W/950124 Ltr |
| | author name = BLIND A A, MOREY D O | | | author name = Blind A, Morey D |
| | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | | | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:RIDRITY(ACCELERATED RIDSPROCI'.SSliGi REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9502020100 DOC-DATE: | | {{#Wiki_filter:RIDRITY (ACCELERATED RIDS PROCI'.SSliGi REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| 95/01/24NOTARIZED-NODOCKET.NFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM05000315AUTH.NAMEAUTHORAFFILIATION MOREY,D.O. | | ACCESSION NBR:9502020100 DOC-DATE: 95/01/24 NOTARIZED- NO DOCKET. N FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH. NAME AUTHOR AFFILIATION MOREY,D.O. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele BLIND,A.A. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION |
| IndianaMichiganPowerCo.(formerly Indiana&MichiganEleBLIND,A.A.
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| IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER94-014-00:on 941225,discovered thatTSsurveillance 4.11.2.1.2 glandsealexhaustweeklygaseouseffluentgrabsamplenotcompleted for941217-25.Caused bypersonnel error.Surveillance schedulesheetmodified.W/950124 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR gENCLiSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTESRECIPIENT IDCODE/NAME PD3-1PDINTERNAL:
| | LER 94-014-00:on 941225,discovered that TS surveillance 4.11.2.1.2 gland seal exhaust weekly gaseous effluent grab sample not completed for 941217-25.Caused by personnel error. Surveillance schedule sheet modified.W/950124 ltr. |
| AEOD/SPDjRABF/IZCENTE@02NRR/DE/EELB NRR/DISP/PIPB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DSSA/SPLB RES/DSIR/EIB EXTERNAL: | | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| LSTLOBBYWARDNOACMURPHY,G.A NRCPDRCOPIESLTTRENCL111111111111111111111111RECIPIENT IDCODE/NAME HICKMAN,J AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DOPS/OECB NRR/DRCH/HICB NRR/DRSS/PRPB NRR/DSSA/SRXB RGN3FILE01LITCOBRYCEPJHNOACPOORE,W.NUDOCSFULLTXTCOPIESLTTRENCL111111111111221111221111i'OTETOALL"RlDS"RECIPIENTS:
| | g ENCL i SIZE: |
| PLEASEHELPl'STOREDL'CEiVASTE.'Oi IAC'I"IHEDOCL'iIEi TCONTROLDESk.ROOXIPl-3"(EXT.5%.2083)TOILlilli:KTE i'OI.'lI%ANILPROilDISTRIDl'TIOiLISTSI:ORDOCI.'ill X'I'SYol.')Oi'"I iI.:I:.D'ULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
| | NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 PD 1 1 HICKMAN,J 1 1 INTERNAL: AEOD/SPDjRAB 1 1 AEOD/SPD/RRAB 1 1 F/IZ CENTE@ 02 1 1 NRR/DE/ECGB 1 1 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DISP/PIPB 1 1 NRR/DOPS/OECB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRSS/PRPB 2 2 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DSIR/EIB 1 1 RGN3 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE P J H 2 2 NOAC MURPHY,G.A 1 1 NOAC POORE,W. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 i'OTE TO ALL"Rl DS" RECIPIENTS: |
| LTTR26ENCL26
| | PLEASE HELP l'S TO RE DL'CE iVASTE.'Oi I AC'I"I HE DOCL'iIEiT CONTROL i |
| | DESk. ROOXI Pl-3" (EXT. 5%.2083 ) TO I Llilli:KTEi'OI.'lI %ANIL PROil DISTR I Dl'TIOi LISTS I:OR DOCI.'ill X'I'S Yol.')Oi'"I I.:I:. |
| | D'ULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26 |
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| IndianaMichiganPowerCompanyCookNuclearPlant~OneCookPlaceBridgman, Ml491066164655901INDIANANICHIGANPOWERJanuary24,1994UnitedStatesNuclearRegulatory Commission DocumentControlDeskRockville, Maryland20852Operating LicensesDPR-58DocketNo.50-315DocumentControlManager:Inaccordance withthecriteriaestablished by10CFR50.73entitlediceseeEveteortSstemthefollowing reportisbeingsubmitted:
| | Indiana Michigan Power Company Cook Nuclear Plant One Cook Place |
| 94-014-00 Sincerely, A.A.BlindPlantManager/sbAttachment cJ.B.Martin,RegionIIIE.E.Fitzpatrick P.A.BarrettR.F.KroegerM.A.Bailey-Ft.WayneNRCResidentInspector J.B.Hickman-NRCJ.R.PadgettG.Charnoff, Esq.D.HahnINPOS.J.Brewer9502020100 950i24PDRADOCK050003i5SPDR NRCFORM366(5921.NUCLEARREGULATORY COMMISSION tAPPROVEDBYOMBNO.315~104EXPIRES5/31/95LICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/characters foreachblock)ESTIMATED BURDENPERRESPONSETOCOMPLYWITHTHISINFORMATION COLLECTION REOUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHEtNFORMATION ANDRECORDSMANAGEMENT BRANCHIMNBBTTI4)~U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC205550001 | | ~ |
| ~ANDTOTHEPAPERWORK REDUCTION PRCUECT(31500104), | | Bridgman, Ml 49106 616 465 5901 INDIANA NICHIGAN POWER January 24, 1994 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-58 Docket No. 50-315 Document Control Manager: |
| OFRCEOFMANAGEMENT ANDBUDGET.WASHlNGTON, OC20503.FACILITYNAME(I)CookNuclearPlant-Unit1DOCKETNUMBER(2)osoooPAOE(3}10F3TITLE(4)WeeklyGaseousGrabSampleNotTakenDuetoPersonnel ErrorEVENTDATE5LERNUMBER6REPORTNUMBER7OTHERFACILITIES INVOLVED8MONTH12DAYYEAR2594SEOUENTIAL NUMBER94-O14REvlsroNNUMBER00MONTHDAY012495FACIUTYNAMECookUnit2FACIUTYNAMEDOCKETNUMBER05000316DOCKETNUMBER05000OPERATING MODE(9)20.402(b) 20.405(c) 50.73(a)(2)(iv)73.71(b)THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFR5:Checkoneormore11POWERLEVEL(10)10020.405(a)
| | In accordance with the criteria established by 10 CFR 50.73 entitled ice see Eve t e ort S stem the following report is being submitted: |
| (1)(i)Fa20.405(a)(l](lt) 20.405(a) | | 94-014-00 Sincerely, A. A. Blind Plant Manager |
| (1)(lii)20.405(a) | | /sb Attachment c J. B. Martin, Region E. E. Fitzpatrick III P. A. Barrett R. F. Kroeger M. A. Bailey - Ft. Wayne NRC Resident Inspector J. B. Hickman NRC J. R. Padgett G. Charnoff, Esq. |
| (1)(iv)20.405(a)(1)(v) 50.36(c)(1)50.36(c)(2)ZS0.73(a)(2)(l) 50.73(a)(2)(ii) 50.73(a)(2)(iii)50.73(a)(2)(v)50.73(a)(2)(vii)50.73(a)(2)(viii)(A)50.73(a)(2) | | D. Hahn INPO S. J. Brewer 9502020100 950i24 PDR ADOCK S 050003i5 PDR |
| (viii)(8)50.73(a)(2)(lt)73.71(c)OTHER(SpeotyInAbstractbelowandInTexLNRCForm366A)LICENSEECONTACTFORTHISLER12NAMED.0.Morey,Chemistry Superintendent TELEPHONE NUMBER(IncludeAreaCode)616/465-5901 X2502COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TONPRDSCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TONPRDSSUPPLEMENTAL REPORTEXPECTED14YES(ttyes.completeEXPECTEDSUBMISSION DATE)NoABSTRACT(Limitto1400spaces.i.e.,approximately 15single-spaced typewritten lines)(16)EXPECTEDMONTHOAYYEARSUBMISSION DATE(15)OnJanuary6,1995itwasdiscovered thatTechnical Specification surveillance 4.11.2.1.2 forUnitsOneandTwoGlandSealExhaustweeklygaseouseffluentgrabsamplewasnotcompleted fortheperiodofDecember17throughDecember25,1994.Asthesamplingrequirement wasnotmet,thiseventisreportable under10CFR50.73(a) | | |
| (2)(i)(B),asacondition prohibited byTechnical Specifications. | | NRC FORM 366 (5 921 LICENSEE EVENT REPORT (LER) |
| Technical Specification 4.11.2.1.2 requiresamonthlysurveillance ontheGlandSealExhaustforparticulate, iodineandtritiuminadditiontotheweeklygaseousgrabsample.Theindividual involvedmistakenly markedthelineitemforthegaseoussampleasnNotApplicable" (N/A)ontheNuclearTest,Schedulesystem,believing theitemwasthemonthlysurveillance forparticulate, iodineandtritiumwhichhadbeencompleted thepreviousweek.Thiseventisattributable topersonnel error.Weaknesses intheNuclearTestSchedulesystemscheduleformanditsusewereidentified duringtheinvestigation. | | . NUCLEAR REGULATORY COMMISSION t APPROVED BY OMB NO. 315~104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS. |
| Theseweaknesshavebeenaddressed.
| | COMMENTS REGARDING BURDEN ESTIMATE TO THE tNFORMATION FORWARD AND RECORDS MANAGEMENTBRANCH IMNBB TTI4)~ U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 205550001 ~ AND TO THE PAPERWORK REDUCTION PRCUECT (31500104), OFRCE OF (See reverse for required number of digits/characters for each block) MANAGEMENTAND BUDGET. WASHlNGTON, OC 20503. |
| DuringthemonthofDecember1994,noabnormaloperational activities occurredthatwouldhavecausedanalteration inthenormalnuclidecomposition ofeitherunits'land SealExhausteffluent.
| | FACILITYNAME (I) DOCKET NUMBER (2) PAOE (3} |
| Areviewofthegaseoussamplesobtainedbeforeandafterthiseventindicated nounusualnuclidespresent.Itwasconcluded thatthemissedsurveillance creatednosafetyhazard,norwasthehealthandsafetyofthepublicjeopardized atanytime.NRCFORM366r5921 NRCFORM355A(Ii(SSS)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION tAPPROVED0MBNO.3150010iEXPIRES,'i/30/02ESTIMATED BURDENPKRRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUEST:500HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(F430),U.S.NUCLEARREGULATORY COMMISSION.
| | Cook Nuclear Plant - Unit 1 osooo 10F 3 TITLE (4) |
| WASHINGTON. | | Weekly Gaseous Grab Sample Not Taken Due to Personnel Error EVENT DATE 5 LER NUMBER 6 REPORT NUMBER 7 OTHER FACILITIES INVOLVED 8 SEOUENTIAL REvlsroN FACIUTY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NUMBER MONTH DAY Cook Unit 2 05000 316 FACIUTY NAME 12 25 94 94 O14 00 01 24 95 DOCKET NUMBER 05000 OPERATING THIS REPORT IS SUBMITTED PURSUA NT TO THE REQUIREMENTS OF 10 CFR 5: Check one or more 11 MODE (9) 20.402(b) 20.405(c) 50.73(a) (2) (iv) 73.71(b) |
| DC20555.ANDTOTHEPAPERWORK REDUCTION PROJECT13150010il.
| | POWER 20.405(a) (1) (i) 50.36(c) (1) 50.73(a) (2) (v) 73.71(c) |
| OFFICKOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACILITYNAME((ICookNuclearPlantUnit1DOCKETNUMBER(2)YEARLERNUMBER(5)seaveNNAI.
| | LEVEL (10) 100 Fa 20.405(a)(l](lt) 50.36(c) (2) 50.73(a) (2) (vii) OTHER 20.405(a) (1) (lii) Z S0.73(a)(2)(l) 50.73(a) (2) (viii)(A) (Speoty In Abstract below and In TexL NRC 20.405(a) (1) (iv) 50.73(a)(2)(ii) 50.73(a)(2) (viii)(8) Form 366A) 20.405(a)(1)(v) 50.73(a) (2) (iii) 50.73(a) (2) (lt) |
| NVMEIIRev(sloN~NVMee/IPACK(3)TEXT///morototcoitroeor/od.
| | LICENSEE CONTACT FOR THIS LER 12 NAME TELEPHONE NUMBER (Include Area Code) |
| Vtooddroooo/HRC Form355A'I/I)))050003159401400020F03Conditions PriortoOccurrence UnitOneinMode1at100percentpower;UnitTwoinModeOneat68percentpower.DescritionofEventOnJanuary6,1995itwasdiscovered thatTechnical Specification surveillance 4.11.2.1.2 forUnitsOneandTwoGlandSealExhaustweeklygaseouseffluentgrabsamplewasnotcompleted fortheperiodofDecember17throughDecember25,1994.Technical Specification Table4.11-2(C) requiresthegrabsampletobetakenonaweeklybasis.Surveillance requirements aretrackedusingtheNuclearTrackingSystem(NTS)surveillance trackingsystem.Aseachlineitemrepresenting asurveillance requirement iscompleted, theresponsible individual "signsoffH(initials) theform.Inadditiontotheweeklygaseousgrabsample,Technical Specification4.11.2.1.2, Table4.11-2(C) requiresamonthlysurveillance ontheGlandSealExhaustforparticulate, iodineandtritium.Theinvolvedindividual wasawarethatthismonthlysurveillance hadbeencompleted thepreviousweek.OnDecember23,1994,whentheweeklygaseousgrabsamplewasdue,theindividual mistakenly markedthelineitemforthegaseoussampleasRNotApplicable" (N/A)ontheNTSform,believing thatthelineitemrepresented themonthlysurveillance forparticulate, iodineandtritium.CauseofEventThi..v.ntisattributable topersonnel error.Theknowledge thatthemonthlysurveillance hadbeencompleted thepreviousweekresultedintheresponsible individual exhibiting alackofattention todetail.Theindividual failedtoreadtheNTSformcarefully, andsubsequently markedtheformincorrectly.
| | D. 0. Morey, Chemistry Superintendent 616/465-5901 X2502 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 CAUSE SYSTEM REPORTABLE REPORTABLE COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED MONTH OAY YEAR YES SUBMISSION (tt yes. complete EXPECTED SUBMISSION DATE) No DATE (15) |
| Animportant contributing factortothiserrorwastheambiguity oftheNTSscheduleformforChemistry.
| | ABSTRACT (Limit to 1400 spaces. i.e., approximately 15 single-spaced typewritten lines) (16) |
| Theformatfailedtoclearlydefinesurveillance frequencies andtheTechnical Specification require(Rent whichthesamplingfulfilled.
| | On January 6, 1995 it was discovered that Technical Specification surveillance 4.11.2.1.2 for Units One and Two Gland Seal Exhaust weekly gaseous effluent grab sample was not completed for the period of December 17 through December 25, 1994. |
| Inaddition, theformcontained tasksunrelated toTechnical Specification surveillance requirements.
| | As the sampling requirement was not met, this event is reportable under 10CFR50.73(a) (2) (i) (B), as a condition prohibited by Technical Specifications. |
| Alsocontributing tothiseventwasthelackoftimelyreviewofthecompleted surveillances fortheperiodinquestion.
| | Technical Specification 4.11.2.1.2 requires a monthly surveillance on the Gland Seal Exhaust for particulate, iodine and tritium in addition to the weekly gaseous grab sample. The individual involved mistakenly marked the line item for the gaseous sample as nNot Applicable" (N/A) on the Nuclear Test, Schedule system, believing the item was the monthly surveillance for particulate, iodine and tritium which had been completed the previous week. |
| Supervisory personnel werenotavailable toreviewthecompleted paperwork priortotheexpiration ofthegraceperiodforthesurveillance. | | This event is attributable to personnel error. Weaknesses in the Nuclear Test Schedule system schedule form and its use were identified during the investigation. These weakness have been addressed. |
| NRCForot358A(585)
| | During the month of December 1994, no abnormal operational activities occurred that would have caused an alteration in the normal nuclide composition of either units'land Seal Exhaust effluent. A review of the gaseous samples obtained before and after this event indicated no unusual nuclides present. |
| NRCFORM35SA(549)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION IAPPROVED0MBNO.3)50410S EKPIRESls/30/92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUEST:508)HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCHIP430).U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555,ANDTOTHEPAPERWORK REDUCTION PROJECT131504104).
| | concluded that the missed surveillance created no safety hazard, nor was the It was health and safety of the public jeopardized at any time. |
| OFFICEOFMANAGEMENT ANOBUDGET,WASHINGTON.DC 20503.FACILITYNAME(1)CookNuclearPlantUnit1DOCKETNUMBER(2)LERNUMBER(5)YEAR(Trs>SEOUSNTIAL
| | NRC FORM 366 r5 921 |
| @>AEYISIONIIUMSSIIS.OIIUMSIIPAGE(3)TGCT/IImoressrsselsss)O/red, useeddr)ioosl llRCForm3SSA's/(I))o5ooo3159401400030F03AnalsisofEventThiseventisbeingreportedinaccordance with10CFR50.73(a)(2)(i)(B) asoperation prohibited bytheplant'sTechnical Specifications. | | |
| Technical Specification 4.11.2.1Table4.11-2(C) requirestheGlandSealExhaustgaseouseffluenttobesampledandanalyzedonaweeklybasis.DuringthemonthofDecember1994,noabnormaloperational activities occurredthatwouldhavecausedanalteration inthenormalnuclidecomposition ofeitherunits'land SealExhausteffluent. | | (I i NRC FORM355A (SSS) |
| Areviewofthegaseoussamplesobtainedbeforeandafterthiseventindicated nounusualnuclidespresent.Inaddition, theresultofthesampleanalysesforparticulate, iodineandtritiumwerereviewedfortheperiodspriortoandafterthemissedgaseoussample,andnounusualnuclideswerepresent.Itwasconcluded thatthemissedsurveillance creatednosafetyhazard,norwasthehealthandsafetyofthepublicjeopardized atanytime.Corrective ActionTheNTSsurveillance schedulesheethasbeenmodifiedusinghumanfactorprinciples.
| | LICENSEE EVENT REPORT (LER) |
| Previously, theformhadcontained entriesbothforTechnical Specification requiredsurveillances andadministrative tasks.Tolessenthepotential forconfusion, theadministrative taskshavebeenremovedandtheNTSscheduleformnowcontainsonlyTechnical Specification requiredsurveillances. | | TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION t APPROVED EXP I 0MB NO. 3150010i R ES,'i/30/02 ESTIMATED BURDEN PKR RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 500 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F430), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT 13150010il. OFF ICK OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503. |
| Theformathasalsobeenrevisedtoorganizetheinformation fortherequiredsurveillances inaconsistent andobviousmanner.TheChemistry Department hasestablished apolicyconcerning theuseof"N/A"whichmakesitclearthatitsuseisnolongeracceptable ontheNTSsurveillance scheduleform.Theprocedure governing theuseofNTShasbeenrevisedtoreflectthisclarification.
| | FACILITY NAME ((I DOCKET NUMBER (2) LER NUMBER (5) PACK (3) |
| Staffbriefings ontheprocedure changeshavebeencompleted.
| | Cook Nuclear Plant Unit 1 YEAR seaveNNAI. |
| Personnel resources havebeenreallocated tobeavailable onatimelybasistoreviewfinishedsurveillances forcompleteness andaccuracy. | | NVM EII ~ Rev(sloN NVMee/I 0 5 0 0 0 315 94 014 0 0 0 2 0F 0 3 TEXT ///moro totcoit roeor/od. Vto oddroooo/HRC Form 355A'I/ I))) |
| PreviousSimilarEvents315/94-012 316/93-010 316/93-002 315/92-013 316/91-003 FailedComonentIdentification NoneNRCForm3SSA(549)}}
| | Conditions Prior to Occurrence Unit One in Mode 1 at 100 percent power; Unit Two in Mode One at 68 percent power. |
| | Descri tion of Event On January 6, 1995 it was discovered that Technical Specification surveillance 4.11.2.1.2 for Units One and Two Gland Seal Exhaust weekly gaseous effluent grab sample was not completed for the period of December 17 through December 25, 1994. |
| | Technical Specification Table 4.11-2(C) requires the grab sample to be taken on a weekly basis. |
| | Surveillance requirements are tracked using the Nuclear Tracking System (NTS) surveillance tracking system. As each line item representing a surveillance requirement is completed, the responsible individual "signs offH (initials) the form. |
| | In addition to the weekly gaseous grab sample, Technical Specif ication 4.11.2.1.2, Table 4.11-2(C) requires a monthly surveillance on the Gland Seal Exhaust for particulate, iodine and tritium. The involved individual was aware that this monthly surveillance had been completed the previous week. On December 23, 1994, when the weekly gaseous grab sample was due, the individual mistakenly marked the line item for the gaseous sample as RNot Applicable" (N/A) on the NTS form, believing that the line item represented the monthly surveillance for particulate, iodine and tritium. |
| | Cause of Event Thi ..v.nt is attributable to personnel error. The knowledge that the monthly surveillance had been completed the previous week resulted in the responsible individual exhibiting a lack of attention to detail. The individual failed to read the NTS form carefully, and subsequently marked the form incorrectly. |
| | An important contributing factor to this error was the ambiguity of the NTS schedule form for Chemistry. The format failed to clearly define surveillance frequencies and the Technical Specification require(Rent which the sampling fulfilled. In addition, the form contained tasks unrelated to Technical Specification surveillance requirements. |
| | Also contributing to this event was the lack of timely review of the completed surveillances for the period in question. Supervisory personnel were not available to review the completed paperwork prior to the expiration of the grace period for the surveillance. |
| | NRC Forot 358A (585) |
| | |
| | NRC FORM 35SA (549) |
| | LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION I |
| | INFORMATION APPROVED 0MB NO.3)50410S EKPIRESl s/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS COLLECTION REQUEST: 508) HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP430). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT 131504104). OFFICE OF MANAGEMENTANO BUDGET, WASHINGTON.DC 20503. |
| | FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (5) PAGE (3) |
| | YEAR (Trs> SEOUSNTIAL @> AEYISION Cook Nuclear Plant Unit 1 IIUMSSII S.O IIUM SII o 5 o o o 315 9 4 014 0 0 0 30F 0 3 TGCT /IImore ssrsse ls ss)O/red, use eddr)ioosl llRC Form 3SSA's/ (I)) |
| | Anal sis of Event This event is being reported in accordance with 10CFR50.73(a)(2)(i)(B) as operation prohibited by the plant's Technical Specifications. Technical Specification 4.11.2.1 Table 4.11-2(C) requires the Gland Seal Exhaust gaseous effluent to be sampled and analyzed on a weekly basis. |
| | During the month of December 1994, no abnormal operational activities occurred that would have caused an alteration in the normal nuclide composition of either units'land Seal Exhaust effluent. A review of the gaseous samples obtained before and after this event indicated no unusual nuclides present. In addition, the result of the sample analyses for particulate, iodine and tritium were reviewed for the periods prior to and after the missed gaseous sample, and no unusual nuclides were present. |
| | It was concluded that the missed surveillance created no safety hazard, nor was the health and safety of the public jeopardized at any time. |
| | Corrective Action The NTS surveillance schedule sheet has been modified using human factor principles. Previously, the form had contained entries both for Technical Specification required surveillances and administrative tasks. To lessen the potential for confusion, the administrative tasks have been removed and the NTS schedule form now contains only Technical Specification required surveillances. |
| | The format has also been revised to organize the information for the required surveillances in a consistent and obvious manner. |
| | The Chemistry Department has established a policy concerning the use of "N/A" which makes it clear that its use is no longer acceptable on the NTS surveillance schedule form. The procedure governing the use of NTS has been revised to reflect this clarification. Staff briefings on the procedure changes have been completed. |
| | Personnel resources have been reallocated to be available on a timely basis to review finished surveillances for completeness and accuracy. |
| | Previous Similar Events 315/94-012 316/93-010 316/93-002 315/92-013 316/91-003 Failed Com onent Identification None NRC Form 3SSA (549)}} |
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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: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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Text
RIDRITY (ACCELERATED RIDS PROCI'.SSliGi REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9502020100 DOC-DATE: 95/01/24 NOTARIZED- NO DOCKET. N FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH. NAME AUTHOR AFFILIATION MOREY,D.O. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele BLIND,A.A. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 94-014-00:on 941225,discovered that TS surveillance 4.11.2.1.2 gland seal exhaust weekly gaseous effluent grab sample not completed for 941217-25.Caused by personnel error. Surveillance schedule sheet modified.W/950124 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
g ENCL i SIZE:
NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 PD 1 1 HICKMAN,J 1 1 INTERNAL: AEOD/SPDjRAB 1 1 AEOD/SPD/RRAB 1 1 F/IZ CENTE@ 02 1 1 NRR/DE/ECGB 1 1 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DISP/PIPB 1 1 NRR/DOPS/OECB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRSS/PRPB 2 2 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 RES/DSIR/EIB 1 1 RGN3 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE P J H 2 2 NOAC MURPHY,G.A 1 1 NOAC POORE,W. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 i'OTE TO ALL"Rl DS" RECIPIENTS:
PLEASE HELP l'S TO RE DL'CE iVASTE.'Oi I AC'I"I HE DOCL'iIEiT CONTROL i
DESk. ROOXI Pl-3" (EXT. 5%.2083 ) TO I Llilli:KTEi'OI.'lI %ANIL PROil DISTR I Dl'TIOi LISTS I:OR DOCI.'ill X'I'S Yol.')Oi'"I I.:I:.
D'ULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26
Indiana Michigan Power Company Cook Nuclear Plant One Cook Place
~
Bridgman, Ml 49106 616 465 5901 INDIANA NICHIGAN POWER January 24, 1994 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-58 Docket No. 50-315 Document Control Manager:
In accordance with the criteria established by 10 CFR 50.73 entitled ice see Eve t e ort S stem the following report is being submitted:
94-014-00 Sincerely, A. A. Blind Plant Manager
/sb Attachment c J. B. Martin, Region E. E. Fitzpatrick III P. A. Barrett R. F. Kroeger M. A. Bailey - Ft. Wayne NRC Resident Inspector J. B. Hickman NRC J. R. Padgett G. Charnoff, Esq.
D. Hahn INPO S. J. Brewer 9502020100 950i24 PDR ADOCK S 050003i5 PDR
NRC FORM 366 (5 921 LICENSEE EVENT REPORT (LER)
. NUCLEAR REGULATORY COMMISSION t APPROVED BY OMB NO. 315~104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS.
COMMENTS REGARDING BURDEN ESTIMATE TO THE tNFORMATION FORWARD AND RECORDS MANAGEMENTBRANCH IMNBB TTI4)~ U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 205550001 ~ AND TO THE PAPERWORK REDUCTION PRCUECT (31500104), OFRCE OF (See reverse for required number of digits/characters for each block) MANAGEMENTAND BUDGET. WASHlNGTON, OC 20503.
FACILITYNAME (I) DOCKET NUMBER (2) PAOE (3}
Cook Nuclear Plant - Unit 1 osooo 10F 3 TITLE (4)
Weekly Gaseous Grab Sample Not Taken Due to Personnel Error EVENT DATE 5 LER NUMBER 6 REPORT NUMBER 7 OTHER FACILITIES INVOLVED 8 SEOUENTIAL REvlsroN FACIUTY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NUMBER MONTH DAY Cook Unit 2 05000 316 FACIUTY NAME 12 25 94 94 O14 00 01 24 95 DOCKET NUMBER 05000 OPERATING THIS REPORT IS SUBMITTED PURSUA NT TO THE REQUIREMENTS OF 10 CFR 5: Check one or more 11 MODE (9) 20.402(b) 20.405(c) 50.73(a) (2) (iv) 73.71(b)
POWER 20.405(a) (1) (i) 50.36(c) (1) 50.73(a) (2) (v) 73.71(c)
LEVEL (10) 100 Fa 20.405(a)(l](lt) 50.36(c) (2) 50.73(a) (2) (vii) OTHER 20.405(a) (1) (lii) Z S0.73(a)(2)(l) 50.73(a) (2) (viii)(A) (Speoty In Abstract below and In TexL NRC 20.405(a) (1) (iv) 50.73(a)(2)(ii) 50.73(a)(2) (viii)(8) Form 366A) 20.405(a)(1)(v) 50.73(a) (2) (iii) 50.73(a) (2) (lt)
LICENSEE CONTACT FOR THIS LER 12 NAME TELEPHONE NUMBER (Include Area Code)
D. 0. Morey, Chemistry Superintendent 616/465-5901 X2502 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 CAUSE SYSTEM REPORTABLE REPORTABLE COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED MONTH OAY YEAR YES SUBMISSION (tt yes. complete EXPECTED SUBMISSION DATE) No DATE (15)
ABSTRACT (Limit to 1400 spaces. i.e., approximately 15 single-spaced typewritten lines) (16)
On January 6, 1995 it was discovered that Technical Specification surveillance 4.11.2.1.2 for Units One and Two Gland Seal Exhaust weekly gaseous effluent grab sample was not completed for the period of December 17 through December 25, 1994.
As the sampling requirement was not met, this event is reportable under 10CFR50.73(a) (2) (i) (B), as a condition prohibited by Technical Specifications.
Technical Specification 4.11.2.1.2 requires a monthly surveillance on the Gland Seal Exhaust for particulate, iodine and tritium in addition to the weekly gaseous grab sample. The individual involved mistakenly marked the line item for the gaseous sample as nNot Applicable" (N/A) on the Nuclear Test, Schedule system, believing the item was the monthly surveillance for particulate, iodine and tritium which had been completed the previous week.
This event is attributable to personnel error. Weaknesses in the Nuclear Test Schedule system schedule form and its use were identified during the investigation. These weakness have been addressed.
During the month of December 1994, no abnormal operational activities occurred that would have caused an alteration in the normal nuclide composition of either units'land Seal Exhaust effluent. A review of the gaseous samples obtained before and after this event indicated no unusual nuclides present.
concluded that the missed surveillance created no safety hazard, nor was the It was health and safety of the public jeopardized at any time.
NRC FORM 366 r5 921
(I i NRC FORM355A (SSS)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION t APPROVED EXP I 0MB NO. 3150010i R ES,'i/30/02 ESTIMATED BURDEN PKR RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 500 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F430), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT 13150010il. OFF ICK OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME ((I DOCKET NUMBER (2) LER NUMBER (5) PACK (3)
Cook Nuclear Plant Unit 1 YEAR seaveNNAI.
NVM EII ~ Rev(sloN NVMee/I 0 5 0 0 0 315 94 014 0 0 0 2 0F 0 3 TEXT ///moro totcoit roeor/od. Vto oddroooo/HRC Form 355A'I/ I)))
Conditions Prior to Occurrence Unit One in Mode 1 at 100 percent power; Unit Two in Mode One at 68 percent power.
Descri tion of Event On January 6, 1995 it was discovered that Technical Specification surveillance 4.11.2.1.2 for Units One and Two Gland Seal Exhaust weekly gaseous effluent grab sample was not completed for the period of December 17 through December 25, 1994.
Technical Specification Table 4.11-2(C) requires the grab sample to be taken on a weekly basis.
Surveillance requirements are tracked using the Nuclear Tracking System (NTS) surveillance tracking system. As each line item representing a surveillance requirement is completed, the responsible individual "signs offH (initials) the form.
In addition to the weekly gaseous grab sample, Technical Specif ication 4.11.2.1.2, Table 4.11-2(C) requires a monthly surveillance on the Gland Seal Exhaust for particulate, iodine and tritium. The involved individual was aware that this monthly surveillance had been completed the previous week. On December 23, 1994, when the weekly gaseous grab sample was due, the individual mistakenly marked the line item for the gaseous sample as RNot Applicable" (N/A) on the NTS form, believing that the line item represented the monthly surveillance for particulate, iodine and tritium.
Cause of Event Thi ..v.nt is attributable to personnel error. The knowledge that the monthly surveillance had been completed the previous week resulted in the responsible individual exhibiting a lack of attention to detail. The individual failed to read the NTS form carefully, and subsequently marked the form incorrectly.
An important contributing factor to this error was the ambiguity of the NTS schedule form for Chemistry. The format failed to clearly define surveillance frequencies and the Technical Specification require(Rent which the sampling fulfilled. In addition, the form contained tasks unrelated to Technical Specification surveillance requirements.
Also contributing to this event was the lack of timely review of the completed surveillances for the period in question. Supervisory personnel were not available to review the completed paperwork prior to the expiration of the grace period for the surveillance.
NRC Forot 358A (585)
NRC FORM 35SA (549)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION I
INFORMATION APPROVED 0MB NO.3)50410S EKPIRESl s/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS COLLECTION REQUEST: 508) HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP430). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT 131504104). OFFICE OF MANAGEMENTANO BUDGET, WASHINGTON.DC 20503.
FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (5) PAGE (3)
YEAR (Trs> SEOUSNTIAL @> AEYISION Cook Nuclear Plant Unit 1 IIUMSSII S.O IIUM SII o 5 o o o 315 9 4 014 0 0 0 30F 0 3 TGCT /IImore ssrsse ls ss)O/red, use eddr)ioosl llRC Form 3SSA's/ (I))
Anal sis of Event This event is being reported in accordance with 10CFR50.73(a)(2)(i)(B) as operation prohibited by the plant's Technical Specifications. Technical Specification 4.11.2.1 Table 4.11-2(C) requires the Gland Seal Exhaust gaseous effluent to be sampled and analyzed on a weekly basis.
During the month of December 1994, no abnormal operational activities occurred that would have caused an alteration in the normal nuclide composition of either units'land Seal Exhaust effluent. A review of the gaseous samples obtained before and after this event indicated no unusual nuclides present. In addition, the result of the sample analyses for particulate, iodine and tritium were reviewed for the periods prior to and after the missed gaseous sample, and no unusual nuclides were present.
It was concluded that the missed surveillance created no safety hazard, nor was the health and safety of the public jeopardized at any time.
Corrective Action The NTS surveillance schedule sheet has been modified using human factor principles. Previously, the form had contained entries both for Technical Specification required surveillances and administrative tasks. To lessen the potential for confusion, the administrative tasks have been removed and the NTS schedule form now contains only Technical Specification required surveillances.
The format has also been revised to organize the information for the required surveillances in a consistent and obvious manner.
The Chemistry Department has established a policy concerning the use of "N/A" which makes it clear that its use is no longer acceptable on the NTS surveillance schedule form. The procedure governing the use of NTS has been revised to reflect this clarification. Staff briefings on the procedure changes have been completed.
Personnel resources have been reallocated to be available on a timely basis to review finished surveillances for completeness and accuracy.
Previous Similar Events 315/94-012 316/93-010 316/93-002 315/92-013 316/91-003 Failed Com onent Identification None NRC Form 3SSA (549)
