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| {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM<RIDS)DISTRIBUTION FORINCOMINGMATERIAL50-220REC'RIERBHNRCORG:SCHNEIDER RRNIAGARAMOHAWKPWRDOCDATE:02/24/78DATERCVD:03/07/78DOCTYPE:LETTERNOTARIZED: | | {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM<RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-220 REC'RIER B H NRC ORG: SCHNEIDER R R NIAGARA MOHAWK PWR DOCDATE: 02/24/78 DATE RCVD: 03/07/78 DOCTYPE: LETTER NOTARIZED: |
| NOCOPIESRECEIVED
| | NO COPIES RECEIVED |
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| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LTR0ENCL1LICENSEEEVENTREPT<RO50-220/78-06)
| | LTR 0 ENCL 1 LICENSEE EVENT REPT<RO 50-220/78-06) |
| ON01/27/78CONCERNING PERFORMANCE OFSURVEILLANCE TESTIC-75FOUNDATRIPSETPOINTOF22.5INCHESWATERONONEVACUUMSWITCHINTHEVACUUMRELIEFSYSTEMFROMTHEPRESSURESUPPRESSION CHAMBERTOTHERXBLDG(68-12B>.
| | ON 01/27/78 CONCERNING PERFORMANCE OF SURVEILLANCE TEST IC-75 FOUND A TRIP SETPOINT OF 22.5 INCHES WATER ON ONE VACUUM SWITCH IN THE VACUUM RELIEF SYSTEM FROM THE PRESSURE SUPPRESSION CHAMBER TO THE RX BLDG (68-12B>.PLANT NAME: NINE MILE PT-UNIT 1 REVIEWER INITIAL: X JM DISTRIBUTOR. |
| PLANTNAME:NINEMILEPT-UNIT1REVIEWERINITIAL:XJMDISTRIBUTOR.
| | INITIAL: gQ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS<DISTRIBUTION CODE A002)FOR ACTION: INTERNAL: EXTERNAL:/4 ENCL EG ILE~~~~W/ENCL I 8.E%~%SCHROEDER/I PPOL I T044 W/ENCL NOVAK/CHECK++W/ENCL KNI GHT++W/ENCL HANAUER+4W/ENCL E I SENHUT++W/ENCL SHAO++W/ENCL KREGER/J.COLLINS44W/ENCL K SEYFRIT/IE++W/ENCL LPDR'S OSWEGO'Y++W/ENCL TIC++W/ENCL NS I C+4 W/ENCL ACRS CAT B++W/16 ENCL NRC PDR44W/ENCL MIPC++W/3 ENCL HOUSTON4+W/ENCL GR IMES++W/ENCL BUTLER++W/ENCL TEDESCO++W/ENCL BAER44W/ENCL VOLLMER/BUNCH>~W/ENCL ROSA++W/ENCL DISTRIBUTION: |
| INITIAL:gQDISTRIBUTION OFTHISMATERIALISASFOLLOWSINCIDENTREPORTS<DISTRIBUTION CODEA002)FORACTION:INTERNAL: | | LTR 45 ENCL 45 SI ZE: iP+iP THE END CONTROL NB: 780680044 |
| EXTERNAL: | | ~4.I~Ihh Ih h J t'V;.>'1:,"',"t,', 4~*khh'I t',"V I I I I I kl hh Ik h~l'~I, k k~h,PV"k htt"I 4'h h h 4 4 ,'I~Vk I h,b I,K H((LQRE MMH teI'F(NMP-0124 NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y.13202/TELEPHONE (315)474-1511 Febeuucg 24, 1978 A..Bogce H.G/L4.et, Mn.ecto/I. |
| /4ENCLEGILE~~~~W/ENCL I8.E%~%SCHROEDER/I PPOLIT044W/ENCLNOVAK/CHECK++W/ENCL KNIGHT++W/ENCL HANAUER+4W/ENCL EISENHUT++W/ENCL SHAO++W/ENCL KREGER/J. | | U~ed Staf:e5 NueLea/1.ReguZato/I.y Commission Region I 631 Pa/I.k Avenue King o(Pm56~, PA.19406 RE: Socket No.50-220 Pea/I.(k.G/Iie/I,: 9~f//pe'+~,t@ZAN c W/~Ay~~/In acco/u(ance uIith Nine NLe Point Nuct'.ea/I. |
| COLLINS44W/ENCL KSEYFRIT/IE++W/ENCL LPDR'SOSWEGO'Y++W/ENCL TIC++W/ENCL NSIC+4W/ENCLACRSCATB++W/16ENCLNRCPDR44W/ENCL MIPC++W/3 ENCLHOUSTON4+W/ENCL GRIMES++W/ENCL BUTLER++W/ENCL TEDESCO++W/ENCL BAER44W/ENCL VOLLMER/BUNCH>~W/ENCL ROSA++W/ENCL DISTRIBUTION: | | S~on Unit>1 Technicat'. |
| LTR45ENCL45SIZE:iP+iPTHEENDCONTROLNB:780680044
| | Speci.+cation/, me he/1eby sub~Licensee Event Repo/Lt LER 78-06, IvhichLe in v~o~n o(Section 3.3.6.F o)Ae Technicat'pecigcations. |
| ~4.I~IhhIhhJt'V;.>'1:," | | Th&aepoM uIm completed in She JotuIat designated in NUREG-0161, dated JId'(g 1977.Ve/I.y~g go~, ORIGINAL SIGNEP BY R.R.SCHNEISER R.R.Schneide/I, Vice P/I.u&e<-ELecttu.c P/I,odu~on n4n Attachments (3)xc: Nrce&on.,'0(I(ice o(18E (30 copiu)Si/Iecto/L, 0(pce o(h(IPC (3 copim)78pggo NRC FORM 3GG (7 77)U.S.NUCLEAR REGULATORY COMMISSION |
| ',"t,',4~*khh'It',"VIIIIIklhhIkh~l'~I,kk~h,PV"khtt"I4'hhh44,'I~VkIh,bI,K H((LQREMMHteI'F(NMP-0124NIAGARAMOHAWKPOWERCORPORATION/300 ERIEBOULEVARD WEST,SYRACUSE, N.Y.13202/TELEPHONE (315)474-1511Febeuucg24,1978A..BogceH.G/L4.et,Mn.ecto/I. | | ~o 7 8 CON'T~01 7 8 Qs.0 2 2 4 7 8 Qg soURGE MLQG 5 0 0 0 2 2 0 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 Durin stead state o eration erformance of surveillance test IC-75 LICENSEE EVENT REPOR~~~CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) |
| U~edStaf:e5NueLea/1. | | I 6 N Y N N P 1 QE 0 0-0 0 0 0 0-0 0 Q34 1 1 1 1 QE~QE LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58~03 found a tri set oint of 22.5 inches water on one vacuum swi tch in the~o 4 vacuum relief s stem from the ressure su ression chamber to the Rx~o 5 Buildin (68-12B).T.S.3.3.64F re uires a set oint less than or equal~o G to 0.5 si 13.85 inches water.This condition resulted in minimal~o 7 safet im lications. |
| ReguZato/I.y Commission RegionI631Pa/I.kAvenueKingo(Pm56~,PA.19406RE:SocketNo.50-220Pea/I.(k.G/Iie/I,: | | A redundant switch was available to initiate~o s o eration of the vacuum relief valve.7 8 9 80~Os SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~SA Q>>E Q13~6Q13 I N S T R 0 04~SQPE~Z QPE 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LEAPPAO EVENT YEAR REPORT NO.CODE TYPE NO.Q17 REPQRT~78~~00 6~~~03~L~0 21 22 23 24 26 27 28 29 30 31 32 ACTION 4 FUTURE EFFECT SHUTDOWN ATTACHh'IENT NPADP PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER gJQ~Q gJ gJQ o" Q33~Q34~QEE QEE 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o The cause of the failure was instrument drift in a mercoid model CP4122 vacuum switch.Trip setpoint was reset to 6.8 inches water.Current surveillance testing schedules are adequate to ensure early detection of future instrument drifts.7 8 9 FACILITY STATUS 66POWEA OTHER STATUS Q 1 5 E 2S 9 6 29 NA Q~0Q ACTIVITY CONTENT RELEASED OF AEI.EASE AMOUNT OF ACTIVITY Q Z Q33~ZQ34 nA 7 8 9 10 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7~00 0 Q37 Z Q33 NA 7 8 9 11 12 13 PEASONNEL IN3URIES METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q2~BQ31 Survei 1 1 ance Testing 45 46 LOCATION OF RELEASE Q 45 80 80 80 80 7 8 7 8 n ,7 NAMF-OF PREPARER Dennis MacVittie 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION |
| 9~f//pe'+~,t@ZANcW/~Ay~~/Inacco/u(ance uIithNineNLePointNuct'.ea/I. | | ~ZQ42 NA 9 10 PUBLICITY ISSUED DESCRIPTION l N IWnI NA 80 NRC USE ONLY I t i i 1J.L.LLL..Li I'7 J'''315-343-2110 ext.]558 0 , PHONE: a NRC FORh1'366 I7 77)U.b.NVCLFAR HEUULATOHY CL7<IIP Ilb>ICJEN I IPLEASE PRINT OR TYPE ALL REOUIREO INFORMATIONI 6 1 020 01 0 0 0 0 0 14 15 LICENSE NUAIBER 0 0 Q24 I I I I QE~QE 25 26 LICENSE TYPE'0 57 CAT 58 ICENSEE EVENT REPORT P (ONTROL BLOCK: I~or N I Y N.I'I P 7 8 9 I.ICENSEE CODE CON'T~or Eov'REE~LQE 0 5 0.0 0 2 2 QT.O8022 478 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74~75 REPORT DATE 80 EVEITIT DESCRIPTION ANO PROBABI.E CONSEQUENCES 10~oz Burin stead state o eration erformance of surveillance test IC-75~o 2 found a trip setpoint of 22.5 inches water on one vacuum switch in the~o R vacuum relief s stem from the ressure su ression chamber to the Rx~o s Buildin (68-128.T.S.3.3.6.F requires a setpoint less than or equ'al~o 8 to 0.5 si 13.85 inches ivater.This condition resulted in minimal~o T safet im Iications. |
| S~onUnit>1Technicat'. | | A redundant switch was available to initiate~o 8 o aration of the vacuum relief valve.7 8 9 80 7 8 SYSTES1 CAUSE CAUSE COMP.VALVE CODE CODE"SUBCODE COMPONFNT CODE SUBCOOE SUBCODE~SA Q~EQ~EQ I N S T R 0 Q~SQ~2cl 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LEREPRO EVENT YEAR REPORT NO.CODE>YPE NO.Qir REPQRT~78~~00 6~m~03~L~~0 21 22 23, 24 26 27 28 29 30 31 32 ACTION, FUTURE EFFECT SHUTDOWN ATTACHA1ENT NPROK PRIME COMP COMPONcNT TAKEN ACTION ON PLANT METHOD~OURS 22 SUBS11 TTED FORM SUB, SUPPLIER MANUFACTURER Q18 LIEO>>~2O20~2Q21 0 0 0~~NQ22~TOTE~NQzs N 2 3 5 Q28 33 34 35 36 37 40 41 42 43 44 47 CAUSF DESCRIPTION AND CORRECTIVE ACTIONS'27 o The cause of the failure was instrument drift in a mercoid model CP4122 vacuum switch.Trip setpoint was reset to 6.8 inches water.Current surveillance testing schedules are adequate to ensure early detection of future instrument drifts.4 7 8 9 FACILITY~STATUS<<8 POWER OTHER STATUS S E 28 0 9 6 29 NA 7 8 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION 2 Q42 NA 9 10 PUBLICITY ISSUED~DESCRIPTION |
| Speci.+cation/, | | ~6)E~EE IEA Dennis t 1acVi tti e NAME OF PREPARER CO LJO~O ACTIVITY CONTENT REI.EASED OF RELEASE AMOUNT OF ACTIVITY Q 8~2 Qzz~2QEE NA 7 8 9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION |
| mehe/1ebysub~LicenseeEventRepo/LtLER78-06,IvhichLeinv~o~no(Section3.3.6.Fo)AeTechnicat'pecigcations.
| | ~I7~00 0 QTT~L Q28 N A 7 8 9 11 12 13 PERSOiNiNEL INJURIES NUMBER O'ESCRIPTIONQ |
| Th&aepoMuImcompleted inSheJotuIatdesignated inNUREG-0161, datedJId'(g1977.Ve/I.y~ggo~,ORIGINALSIGNEPBYR.R.SCHNEISER R.R.Schneide/I, ViceP/I.u&e<- | | ~00 0 Qio NA I,IETHQD OF DISCOVERY~BQSI 45 46 NA DISCOVERY OESCRIPTIQi'4 Q3 Surveillance Testing LOCATION OF RELEASE QB 80 80 80 80 80 80 NRC IJSE ONLY I I I I I I.I.I..I.I I I"", 315-343-2110 ext.1558 PHONE: |
| ELecttu.c P/I,odu~on n4nAttachments (3)xc:Nrce&on., | |
| '0(I(iceo(18E(30copiu)Si/Iecto/L, 0(pceo(h(IPC(3copim)78pggo NRCFORM3GG(777)U.S.NUCLEARREGULATORY COMMISSION | |
| ~o78CON'T~0178Qs.022478QgsoURGEMLQG50002206061DOCKETNUMBER6869EVENTDATE7475REPORTDATE80EVENTDESCRIPTION ANDPROBABLECONSEQUENCES Q10Durinsteadstateoerationerformance ofsurveillance testIC-75LICENSEEEVENTREPOR~~~CONTROLBLOCK:QI(PLEASEPRINTORTYPEALLREQUIREDINFORMATION) | |
| I6NYNNP1QE00-00000-00Q341111QE~QELICENSEECODE1415LICENSENUMBER2526LICENSETYPE3057CAT58~03foundatrisetointof22.5incheswaterononevacuumswitchinthe~o4vacuumreliefsstemfromtheressuresuressionchambertotheRx~o5Buildin(68-12B).
| |
| T.S.3.3.64Freuiresasetointlessthanorequal~oGto0.5si13.85incheswater.Thiscondition resultedinminimal~o7safetimlications. | |
| Aredundant switchwasavailable toinitiate~osoerationofthevacuumreliefvalve.78980~OsSYSTEMCAUSECAUSECOMP.VALVECODECODESUBCODECOMPONENT CODESUBCODESUBCODE~SAQ>>EQ13~6Q13INSTR004~SQPE~ZQPE78910111213181920SEQUENTIAL OCCURRENCE REPORTREVISIONLEAPPAOEVENTYEARREPORTNO.CODETYPENO.Q17REPQRT~78~~006~~~03~L~02122232426272829303132ACTION4FUTUREEFFECTSHUTDOWNATTACHh'IENT NPADPPRIMECOMP.COMPONENT TAKENACTIONONPLANTMETHODHOURS22SUBMITTED FORMSUB.SUPPLIERMANUFACTURER gJQ~QgJgJQo"Q33~Q34~QEEQEE3334353637404142434447CAUSEDESCRIPTION ANDCORRECTIVE ACTIONSQ27oThecauseofthefailurewasinstrument driftinamercoidmodelCP4122vacuumswitch.Tripsetpointwasresetto6.8incheswater.Currentsurveillance testingschedules areadequatetoensureearlydetection offutureinstrument drifts.789FACILITYSTATUS66POWEAOTHERSTATUSQ15E2S9629NAQ~0QACTIVITYCONTENTRELEASEDOFAEI.EASEAMOUNTOFACTIVITYQZQ33~ZQ34nA7891044PERSONNEL EXPOSURES NUMBERTYPEDESCRIPTION Q397~000Q37ZQ33NA789111213PEASONNEL IN3URIESMETHODOFDISCOVERY DISCOVERY DESCRIPTION Q2~BQ31Survei11anceTesting4546LOCATIONOFRELEASEQ45808080807878n,7NAMF-OFPREPARERDennisMacVittie 91112LOSSOFORDAMAGETOFACILITYQ43TYPEDESCRIPTION
| |
| ~ZQ42NA910PUBLICITY ISSUEDDESCRIPTION lNIWnINA80NRCUSEONLYItii1J.L.LLL..Li I'7J'''315-343-2110 ext.]5580,PHONE:a NRCFORh1'366 I777)U.b.NVCLFARHEUULATOHY CL7<IIPIlb>ICJEN IIPLEASEPRINTORTYPEALLREOUIREOINFORMATIONI 6102001000001415LICENSENUAIBER00Q24IIIIQE~QE2526LICENSETYPE'057CAT58ICENSEEEVENTREPORTP(ONTROLBLOCK:I~orNIYN.I'IP789I.ICENSEE CODECON'T~orEov'REE~LQE050.0022QT.O8022478786061DOCKETNUMBER6869EVENTDATE74~75REPORTDATE80EVEITITDESCRIPTION ANOPROBABI.E CONSEQUENCES 10~ozBurinsteadstateoerationerformance ofsurveillance testIC-75~o2foundatripsetpointof22.5incheswaterononevacuumswitchinthe~oRvacuumreliefsstemfromtheressuresuressionchambertotheRx~osBuildin(68-128.T.S.3.3.6.Frequiresasetpointlessthanorequ'al~o8to0.5si13.85inchesivater.Thiscondition resultedinminimal~oTsafetimIications. | |
| Aredundant switchwasavailable toinitiate~o8oarationofthevacuumreliefvalve.7898078SYSTES1CAUSECAUSECOMP.VALVECODECODE"SUBCODECOMPONFNT CODESUBCOOESUBCODE~SAQ~EQ~EQINSTR0Q~SQ~2cl910111213181920SEQUENTIAL OCCURRENCE REPORTREVISIONLEREPROEVENTYEARREPORTNO.CODE>YPENO.QirREPQRT~78~~006~m~03~L~~0212223,2426272829303132ACTION,FUTUREEFFECTSHUTDOWNATTACHA1ENT NPROKPRIMECOMPCOMPONcNT TAKENACTIONONPLANTMETHOD~OURS22SUBS11TTEDFORMSUB,SUPPLIERMANUFACTURER Q18LIEO>>~2O20~2Q21000~~NQ22~TOTE~NQzsN235Q283334353637404142434447CAUSFDESCRIPTION ANDCORRECTIVE ACTIONS'27oThecauseofthefailurewasinstrument driftinamercoidmodelCP4122vacuumswitch.Tripsetpointwasresetto6.8incheswater.Currentsurveillance testingschedules areadequatetoensureearlydetection offutureinstrument drifts.4789FACILITY~STATUS<<8POWEROTHERSTATUSSE2809629NA787891112LOSSOFORDAMAGETOFACILITYQ43TYPEDESCRIPTION 2Q42NA910PUBLICITY ISSUED~DESCRIPTION
| |
| ~6)E~EEIEADennist1acVittieNAMEOFPREPARERCOLJO~OACTIVITYCONTENTREI.EASED OFRELEASEAMOUNTOFACTIVITYQ8~2Qzz~2QEENA789101144PERSONNEL EXPOSURES NUMBERTYPEDESCRIPTION | |
| ~I7~000QTT~LQ28NA789111213PERSOiNiNEL INJURIESNUMBERO'ESCRIPTIONQ | |
| ~000QioNAI,IETHQDOFDISCOVERY | |
| ~BQSI4546NADISCOVERY OESCRIPTIQi'4 Q3Surveillance TestingLOCATIONOFRELEASEQB808080808080NRCIJSEONLYIIIIII.I.I..I.III"",315-343-2110 ext.1558PHONE: | |
|
| |
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| To:PIB-39~)~)rooN.3fa-gQ2lg~or<TL/TorY<iŽ(lil~~.riG l'w:;b~:r | | To: PIB-39~)~)rooN.3fa-gQ 2 lg~or<TL/To r Y<iŽ(lil~~.riG l'w:;b~:r', lel ephonc lou::il~ci TO: Director of Pco>>lat<<ry Operation OSl;lK l.-.:ir,n I 63l Pari: l:;en c l:in@nf Pros'ia, Ph.19406 Frooi: Hiirgara lTol:a';cl; Po.jcr Corporation bine hilt.Point, Duel cdr Station U>>lt fiT P 0.Bor.i<32 Lp'colllin9, hcl'I York 13093 SUPiilECT: |
| ',lelephonclou::il~ci TO:DirectorofPco>>lat<<ry Operation OSl;lKl.-.:ir,nI63lPari:l:;encl:in@nfPros'ia,Ph.19406Frooi:HiirgaralTol:a';cl; Po.jcrCorporation binehilt.Point,DuelcdrStationU>>ltfiTP0.Bor.i<32Lp'colllin9, hcl'IYork13093SUPiilECT: | |
| PP.Ol',1'T Rl.PO.,TN)].!! | | PP.Ol',1'T Rl.PO.,TN)].!! |
| OCD).J)El'CE DOC):l'.T l'0."0-220LICLl!SEl!0.DPR-G3ASSJ(islED LERHO.'8-09CYGNETDATE:78022EREPORTDf<TE:78022IEVErlTDFSCRIPTTnrl: | | OCD).J)El'CE DOC):l'.T l'0."0-220 LICLl!SE l!0.DPR-G3 ASSJ(islED LER HO.'8-09 CYGNET DATE: 78022E REPORT Df<TE: 78022I EVErlT DFSCRIPTTnrl: |
| SEEATTACHED.
| | SEE ATTACHED.CO:(POlKliTS Il'OL"ED: TIP machine shear va'1ve squfb devices , CAUSE l(t!D RKr':ENf(L ACTIDIL circuit per GE revisi'on Institution of modiffcation in squib FE(CILITV STATUS=c)Routine Startop d)Routln~Sll:: dc"n e)stea<ry s:.iie opLl-~f)Load Cl'.-.age S;TllEt:Wnt. |
| CO:(POlKliTS Il'OL"ED:TIPmachineshearva'1vesqufbdevices,CAUSEl(t!DRKr':ENf(L ACTIDILcircuitperGErevisi'on Institution ofmodiffcation insquibFE(CILITV STATUS=c)RoutineStartopd)Routln~Sll::dc"ne)stea<rys:.iieopLl-~f)LoadCl'.-.age S;TllEt:Wnt. | | bi(1840 Slwit<foi~o refuel lng Other l(ot lippj'IcBI>IL IL i'riticn follow-up rcport will be sent v;itbin i<io v.'ccl:s.vr..roon ro 35 7 6.H:i ll.roo~rV: P.~~a" owL a 2.i llM H. |
| bi(1840Slwit<foi~o refuellngOtherl(otlippj'IcBI>IL ILi'riticnfollow-up rcportwillbesentv;itbini<iov.'ccl:s. | |
| vr..roonro3576.H:ill.roo~rV:P.~~a"owLa2.illMH. | |
|
| |
|
| ATTACHMENT TOLER78-09EventDescription: | | ATTACHMENT TO LER 78-09 Event |
| Duringroutinestationoperation withtheTIPdetectors.
| | |
| withdrawn, repTacement explosive chargesintheTIPsystemshearvalveswerereplcaedwithnewcharges.Following replacement, itwasfoundthattheohmnetercontlnuity testforacceptable eTectriccontactwasunsatisfactory. | | == Description:== |
| ThenormalTIPtubetsoTaticm systemwas.operabTeatthistime.IItwasfoundthartthe.actualetectricaV connections tothe.explosive chargeswerenetas-described
| | |
| -4nthemaStenance-procedure. | | During routine station operation with the TIP detectors. |
| -Theshear.valveswouldnothaveoperatedto5solatetheTIPguide.tubawitlrtheTIpinsertedDectrical connections villbecheckedandtestedtoassure.thattheexplosive.va7.ves wAloperateasdescribed intheoperaticprocedures."..Station records;including. | | withdrawn, repTacement explosive charges in the TIP system shear valves were replcaed with new charges.Following replacement, it was found that the ohmneter contlnuity test for acceptable eTectric contact was unsatisfactory. |
| theau6ntenance.-.procedures,-wfTT
| | The normal TIP tube tsoTaticm system was.operabTe at this time.I It was found thart the.actual etectricaV connections to the.explosive charges were net as-described |
| =becorrected toreflectthecorrect.wirinyconnections Anend-ta-end demonstration-at'he. | | -4n the maStenance-procedure. |
| explosive shearva7ves=will beperformed'ith theexplosive chargeremoved.from..the, system..'orrective actionwfllbecompTeted beforetheTIPsystemisagainusedrTheexplosive operatedTIPsheartsolation valvesareaback-upsystemtobeusedforisa'Eatioe oftheTIPtubesintheeventitisnotpossible. | | -The shear.valves would not have operated to 5solate the TIP guide.tuba witlr the TIp inserted Dectrical connections vill be checked and tested to assure.that the explosive.va7.ves wAl operate as described in the operatic procedures."..Station records;including. |
| tewfthdrwrthe.detectnrsethenormaTautomat%a.
| | the au6ntenance.-.procedures,-wfTT |
| i.soTation systemmayfunction}} | | =be corrected to reflect the correct.wiriny connections An end-ta-end demonstration-at'he. |
| | explosive shear va7ves=will be performed'ith the explosive charge removed.from..the, system..'orrective action wfll be compTeted before the TIP system is again used r The explosive operated TIP shear tsolation valves are a back-up system to be used for isa'Eatioe of the TIP tubes in the event it is not possible.te wfthdrwr the.detectnr se the normaT automat%a. |
| | i.soTation system may function}} |
|
|---|
Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024
Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
IR 05000220/20243022024-10-0303 October 2024
Initial Operator Licensing Examination Report 05000220/2024302
NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024
Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000220/20240052024-08-29029 August 2024
Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005)
IR 05000220/20240102024-08-22022 August 2024
Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024
Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000220/20240022024-08-0505 August 2024
Integrated Inspection Report 05000220/2024002 and 05000410/2024002
ML24215A3002024-08-0202 August 2024
Operator Licensing Examination Approval
ML24213A1412024-07-31031 July 2024
Requalification Program Inspection
NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024
Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024
Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations
ML24198A0852024-07-16016 July 2024
Senior Reactor and Reactor Operator Initial License Examinations
RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024
Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024
License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
IR 05000220/20244012024-05-30030 May 2024
Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only)
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024
Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request
NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024
2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2
ML24158A2052024-05-15015 May 2024
Annual Radioactive Environmental Operating Report
IR 05000220/20240012024-05-10010 May 2024
Integrated Inspection Report 05000220/2024001 and 05000410/2024001
RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024
Updated Notice of Intent to Pursue Subsequent License Renewal Applications
RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024
Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
NMP2L2880, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024
Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum
NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024
Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024
2023 Annual Environmental Operating Report
NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024
Core Operating Limits Report
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
ML24092A3352024-04-0101 April 2024
NRC Office of Investigations Case No. 1-2023-002
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24074A2812024-03-14014 March 2024
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
IR 05000220/20230062024-02-28028 February 2024
Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006)
NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024
Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
IR 05000220/20230042024-02-0101 February 2024
Integrated Inspection Report 05000220/2023004 and 05000410/2023004
05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024
Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater
NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024
CFR 50.46 Annual Report
ML24004A2122024-01-0808 January 2024
Senior Reactor and Reactor Operator Initial License Examinations
ML23354A0012024-01-0404 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23278A1292023-12-14014 December 2023
Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines
NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023
Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station
IR 05000410/20243012023-12-14014 December 2023
Initial Operator Licensing Examination Report 05000410/2024301
ML23305A1402023-12-13013 December 2023
Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580
2024-09-04
[Table view]
Category:Licensee Event Report (LER)
MONTHYEARNMP2L2880, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024
Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum
05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024
Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater
ML18018B1152018-01-18018 January 2018
Scram Summary 91-01 Relating to a Turbine Trip and Automatic Reactor Scram When the Main Transformer Phase B Developed an Internal Fault on August 13, 1991
ML18018B1122018-01-18018 January 2018
Scram Summary 91-01 Relating to an Event on August 13, 1991 Concerning a Turbine Trip and Automatic Reactor Scram When the Main Transformer Phase B Developed an Internal Fault
05000410/LER-2017-0022017-11-28028 November 2017
Secondary Containment Inoperable Due to Wind Conditions, LER 17-002-00 for Nine Mile Point Nuclear Station, Unit 2 Regarding Secondary Containment Inoperable Due to Wind Conditions
05000220/LER-2017-0032017-11-0202 November 2017
Automatic Reactor Scram due to Reactor Vessel Low Water Level, LER 17-003-00 for Nine Mile Point, Unit 1, Regarding Automatic Reactor Scram due to Reactor Vessel Low Water Level
05000410/LER-2017-0012017-10-0404 October 2017
1 OF 5, LER 17-001-00 for Nine Mile Point Nuclear Station, Unit 2, Regarding Automatic Reactor Scram due to High Reactor Pressure
05000220/LER-2017-0022017-05-18018 May 2017
Manual Reactor Scram Due to Pressure Oscillations, LER 17-002-00 for Nine Mile Point Nuclear Station, Unit 1 Regarding Manual Reactor Scram Due to Pressure Oscillations
NMP1L3129, LER 17-01-00 for Nine Mile Point Unit 1 Manual Reactor Scram Due to High Turbine Vibration2017-02-0808 February 2017
LER 17-01-00 for Nine Mile Point Unit 1 Manual Reactor Scram Due to High Turbine Vibration
05000220/LER-2017-0012017-02-0808 February 2017
Manual Reactor Scram Due to Hiah Turbine Vibration, LER 17-01-00 for Nine Mile Point Unit 1 RE: Manual Reactor Scram Due to High Turbine Vibration
05000220/LER-2016-0022016-09-26026 September 2016
Isolation of both Emergency Condensers due to loss of UPS 162B, LER 16-002-00 for Nine Mile Point, Unit 1, Regarding Isolation of Both Emergency Condensers due to Loss of UPS 1628
05000220/LER-2016-0012016-07-12012 July 2016
Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors, LER 16-001-00 for Nine Mile Point Nuclear Station Unit 1 Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors
05000410/LER-2016-0012016-06-0606 June 2016
Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors, LER 16-001-00 for Nine Mile Point, Unit 2, Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors
05000410/LER-2015-0032016-03-31031 March 2016
Primary Containment Isolation Function for some valves not maintained during Surveillance Testing, LER 15-003-01 for Nine Mile Point, Unit 2, Regarding Primary Containment Isolation Function For Some Valves Not Maintained During Surveillance Testing
ML1005504842010-02-15015 February 2010
Special Report: Inoperable Suppression Chamber Water Level Instrumentation
ML0903605172009-01-21021 January 2009
Special Report: Inoperable Channel of Suppression Chamber Water Level Instrumentation
ML0534802052005-12-0202 December 2005
Special Report for Nine Mile Point Unit 1 Re Channel #12 of the Containment Hydrogen Monitoring System Inoperable
ML0515400362005-05-24024 May 2005
Special Report, Channel #11 of the Containment Hydrogen Monitoring Inoperable for Scheduled Preventive Maintenance
ML0509602522004-12-17017 December 2004
Final Precursor Analysis - NMP-2 Grid Loop
ML0509602422004-12-17017 December 2004
Final Precursor Analysis - NMP-1 Grid Loop
ML0434304492004-11-22022 November 2004
Special Report for Nine Mile Point, Unit 1 Regarding Channel #12 of the Containment Hydrogen Monitoring System Removed from Service for Planned Maintenance
ML0425300732004-08-27027 August 2004
Special Report for Nine Mile Point Unit 1 Re Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance
ML0418105152004-06-18018 June 2004
Revised Special Report for Nine Mile Point, Unit 1 Re Channel #12 of the Containment Hydrogen Monitoring System Inoperable
ML0413204992004-05-0404 May 2004
Special Report for Nine Mile Point Unit 1 Regarding Inoperability of Channel #12 of the Containment Hydrogen Monitoring System
ML0410603992004-04-0707 April 2004
Special Report, Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Corrective Maintenance
ML0336404932003-12-19019 December 2003
Special Report Regarding Channel #11 Containment Hydrogen Monitoring System Being Inoperable for Scheduled Preventive Maintenance
ML0221303572002-07-23023 July 2002
Special Report for Nine Mile Point Unit 2 Re Noble Gas Activity Monitoring Instrumentation Inoperable for Greater than 72 Hours
ML18018B1112000-03-0707 March 2000
LER 99-019-01 Supplement 1, for Nine Mile Point, Unit 2, Regarding Two Standby Liquid Control Valves Not Tested as Required by Technical Specification 4.0.5 and LER 99-010-01, Supplement 1, Unit 2 Reactor Trip Due to a Feedwater Master ..
ML18018B0771997-12-29029 December 1997
Letter Replying to Notice of Violation as Contained in NRC Inspection Report 50-220/97-07 and 50-410/97-07
ML18018B1171991-09-0404 September 1991
NRC UPS Meeting
ML18018B2511978-09-29029 September 1978
LER 78-034-00 for Nine Mile Point, Unit 2, Regarding an Environmental Contractor Obtaining 22 Hourly Fish Impingement Samples, and One Two-Hour Sample, Which Is Contrary to the Technical Specification Requiring 24 Hourly Samples
ML18018B2521978-08-24024 August 1978
LER 78-030-00, 78-031-00, and 78-032-00 for Nine Mile Point Unit 1 Regarding, Respectively, Unavailability of Feedwater Pump 29-03 While Its Pump Seals Were Replaced, Unavailability of Liquid Poison Pump NP02A While a Frozen Valve ..
ML18018B2531978-07-28028 July 1978
LER 78-029-00 for Nine Mile Point, Unit 2, Regarding Discovery of High Drywell Pressure Switches RE04A, RE04B, and RE04C with Setpoints Less Conservative than the Technical Specifications
ML18018B2541978-07-25025 July 1978
LER 78-028-00 for Nine Mile Point Unit 1 Regarding Discovery of the Allowable Test Interval of TS 4.1.4c for the Core Spray Power-Operated Valves Had Been Exceeded
ML18018B2551978-07-13013 July 1978
LERs 78-025-00, 78-026-00, and 78-027-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery of RE04D with a Setpoint of 3.70 PSIG, Discovery of Numerous Small Leaks in Small Sample and Instrument Pipes, and Discovery of RE22D wit
ML18018B2561978-06-21021 June 1978
LER 78-024-00 for Nine Mile Point Unit 1 Regarding Discovery That Test N1-St-Q2,4,5,7,8,9, and 10 Had Not Been Performed During a Review of Quarterly Surveillance Test Results
ML18018B2571978-06-12012 June 1978
LERs 78-020-00, 78-021-00, 78-022-00, and 78-023-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery of RE18A with a Setpoint of 135 Inches Wc, Discovery of RE04A and RE04B with a Setpoint of 3.65 PSIG, Discovery of Turbine ...
ML18018B2591978-06-0101 June 1978
LER 78-019-00 for Nine Mile Point Unit 1 Regarding Discovery That Hydraulic Snubber 31-HS-1 Had Failed and Was Empty of Hydraulic Fluid and Disconnected from Its Anchor at the Feedwater Pipe
ML18018B2581978-05-26026 May 1978
LER 78-009-01 for Nine Mile Point Unit 1 Regarding Replacement of Explosive Charges in the TIP Shear Valves with New Charges and the Resulting Unsatisfactory Ohmmeter Continuity Test for Acceptable Electric Contact
ML18018B2601978-04-24024 April 1978
LER 78-018-00 for Nine Mile Point Unit 1 Regarding Discovery of Main Steam High Flow Switch with a Setpoint of 106.2 PSI, Which Is Above the Technical Specification
ML18018B2611978-04-0707 April 1978
LERs 78-014,00, 78-016-00, and 78-016-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery That the Fuel Transfer Pump on 102 D/G Would Not Fill the Day Tank, Discovery of RE18C with a Setpoint of 129 Inches Wc, and RE04B ..
ML18018B2621978-03-28028 March 1978
LER 78-014-00 and LER 78-015-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery That the Fuel Transfer Pump in 102 D/G Would Not Fill the Day Tank and Discovery That #12 Control Room Air Treatment Fan Would Not Run
ML18018B2631978-03-16016 March 1978
LER 78-011-00, LER 78-012-00 and LER 78-013-00 for Nine Mile Point, Unit 1 Re Technical Specification Violations of Section 3.6.2
ML18018B2641978-03-0101 March 1978
LER 78-007-00, LER 78-008-00, LER 78-009-00 and LER 78-010-00 for Nine Mile Point, Unit 1 Re Technical Specification Violations of Listed Sections
ML18018B2651978-02-24024 February 1978
LER 78-006-00 for Nine Mile Point, Unit 1 Re During Steady State Operation, Performance of Surveillance Test IC-75 Found a Trip Setpoint of 22.5 Inches Water on One Vacuum Switch in the Vacuum Relief System from the Pressure Suppression Cha
ML18018B2661978-02-0707 February 1978
LER 78-004-00 and LER 78-005-00 for Nine Mile Point, Unit 1 Re During Unit Shutdown, Reserve Power Breaker on Power Board II Failed to Close in After Loss of Normal Power and During Plant Outage While Marking Up Outside MSIV 01-03 Discovere
ML18094A0301978-01-31031 January 1978
LER 1978-003-03 for Nine Mile Point Unit 1 Re Surveillance Test Found Main Steam High Flow Switch with Setpoint of 107.5 PSI
ML18018B1221978-01-31031 January 1978
LER 78-002-00 for Nine Mile Point 1 Regarding Drywell High Pressure Switch RE04A Setpoint Drift and LER 78-003-00
ML18094A0291978-01-13013 January 1978
LER 1978-001-00 for Nine Mile Point Station Unit 1 Re Delta Temperature of Discharge Water Exceeded Specification 2.1.5 of Environmental Tech Specs
ML18018B2701978-01-13013 January 1978
Submittal of Licensee Event Report LER 78-01 Concerning Delta Temperature of the Discharge Water Exceeded Environmental Tech. Spec
2024-05-01
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM<RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-220 REC'RIER B H NRC ORG: SCHNEIDER R R NIAGARA MOHAWK PWR DOCDATE: 02/24/78 DATE RCVD: 03/07/78 DOCTYPE: LETTER NOTARIZED:
NO COPIES RECEIVED
SUBJECT:
LTR 0 ENCL 1 LICENSEE EVENT REPT<RO 50-220/78-06)
ON 01/27/78 CONCERNING PERFORMANCE OF SURVEILLANCE TEST IC-75 FOUND A TRIP SETPOINT OF 22.5 INCHES WATER ON ONE VACUUM SWITCH IN THE VACUUM RELIEF SYSTEM FROM THE PRESSURE SUPPRESSION CHAMBER TO THE RX BLDG (68-12B>.PLANT NAME: NINE MILE PT-UNIT 1 REVIEWER INITIAL: X JM DISTRIBUTOR.
INITIAL: gQ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS<DISTRIBUTION CODE A002)FOR ACTION: INTERNAL: EXTERNAL:/4 ENCL EG ILE~~~~W/ENCL I 8.E%~%SCHROEDER/I PPOL I T044 W/ENCL NOVAK/CHECK++W/ENCL KNI GHT++W/ENCL HANAUER+4W/ENCL E I SENHUT++W/ENCL SHAO++W/ENCL KREGER/J.COLLINS44W/ENCL K SEYFRIT/IE++W/ENCL LPDR'S OSWEGO'Y++W/ENCL TIC++W/ENCL NS I C+4 W/ENCL ACRS CAT B++W/16 ENCL NRC PDR44W/ENCL MIPC++W/3 ENCL HOUSTON4+W/ENCL GR IMES++W/ENCL BUTLER++W/ENCL TEDESCO++W/ENCL BAER44W/ENCL VOLLMER/BUNCH>~W/ENCL ROSA++W/ENCL DISTRIBUTION:
LTR 45 ENCL 45 SI ZE: iP+iP THE END CONTROL NB: 780680044
~4.I~Ihh Ih h J t'V;.>'1:,"',"t,', 4~*khh'I t',"V I I I I I kl hh Ik h~l'~I, k k~h,PV"k htt"I 4'h h h 4 4 ,'I~Vk I h,b I,K H((LQRE MMH teI'F(NMP-0124 NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y.13202/TELEPHONE (315)474-1511 Febeuucg 24, 1978 A..Bogce H.G/L4.et, Mn.ecto/I.
U~ed Staf:e5 NueLea/1.ReguZato/I.y Commission Region I 631 Pa/I.k Avenue King o(Pm56~, PA.19406 RE: Socket No.50-220 Pea/I.(k.G/Iie/I,: 9~f//pe'+~,t@ZAN c W/~Ay~~/In acco/u(ance uIith Nine NLe Point Nuct'.ea/I.
S~on Unit>1 Technicat'.
Speci.+cation/, me he/1eby sub~Licensee Event Repo/Lt LER 78-06, IvhichLe in v~o~n o(Section 3.3.6.F o)Ae Technicat'pecigcations.
Th&aepoM uIm completed in She JotuIat designated in NUREG-0161, dated JId'(g 1977.Ve/I.y~g go~, ORIGINAL SIGNEP BY R.R.SCHNEISER R.R.Schneide/I, Vice P/I.u&e<-ELecttu.c P/I,odu~on n4n Attachments (3)xc: Nrce&on.,'0(I(ice o(18E (30 copiu)Si/Iecto/L, 0(pce o(h(IPC (3 copim)78pggo NRC FORM 3GG (7 77)U.S.NUCLEAR REGULATORY COMMISSION
~o 7 8 CON'T~01 7 8 Qs.0 2 2 4 7 8 Qg soURGE MLQG 5 0 0 0 2 2 0 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 Durin stead state o eration erformance of surveillance test IC-75 LICENSEE EVENT REPOR~~~CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I 6 N Y N N P 1 QE 0 0-0 0 0 0 0-0 0 Q34 1 1 1 1 QE~QE LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58~03 found a tri set oint of 22.5 inches water on one vacuum swi tch in the~o 4 vacuum relief s stem from the ressure su ression chamber to the Rx~o 5 Buildin (68-12B).T.S.3.3.64F re uires a set oint less than or equal~o G to 0.5 si 13.85 inches water.This condition resulted in minimal~o 7 safet im lications.
A redundant switch was available to initiate~o s o eration of the vacuum relief valve.7 8 9 80~Os SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~SA Q>>E Q13~6Q13 I N S T R 0 04~SQPE~Z QPE 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LEAPPAO EVENT YEAR REPORT NO.CODE TYPE NO.Q17 REPQRT~78~~00 6~~~03~L~0 21 22 23 24 26 27 28 29 30 31 32 ACTION 4 FUTURE EFFECT SHUTDOWN ATTACHh'IENT NPADP PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER gJQ~Q gJ gJQ o" Q33~Q34~QEE QEE 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o The cause of the failure was instrument drift in a mercoid model CP4122 vacuum switch.Trip setpoint was reset to 6.8 inches water.Current surveillance testing schedules are adequate to ensure early detection of future instrument drifts.7 8 9 FACILITY STATUS 66POWEA OTHER STATUS Q 1 5 E 2S 9 6 29 NA Q~0Q ACTIVITY CONTENT RELEASED OF AEI.EASE AMOUNT OF ACTIVITY Q Z Q33~ZQ34 nA 7 8 9 10 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7~00 0 Q37 Z Q33 NA 7 8 9 11 12 13 PEASONNEL IN3URIES METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q2~BQ31 Survei 1 1 ance Testing 45 46 LOCATION OF RELEASE Q 45 80 80 80 80 7 8 7 8 n ,7 NAMF-OF PREPARER Dennis MacVittie 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION
~ZQ42 NA 9 10 PUBLICITY ISSUED DESCRIPTION l N IWnI NA 80 NRC USE ONLY I t i i 1J.L.LLL..Li I'7 J315-343-2110 ext.]558 0 , PHONE: a NRC FORh1'366 I7 77)U.b.NVCLFAR HEUULATOHY CL7<IIP Ilb>ICJEN I IPLEASE PRINT OR TYPE ALL REOUIREO INFORMATIONI 6 1 020 01 0 0 0 0 0 14 15 LICENSE NUAIBER 0 0 Q24 I I I I QE~QE 25 26 LICENSE TYPE'0 57 CAT 58 ICENSEE EVENT REPORT P (ONTROL BLOCK: I~or N I Y N.I'I P 7 8 9 I.ICENSEE CODE CON'T~or Eov'REE~LQE 0 5 0.0 0 2 2 QT.O8022 478 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74~75 REPORT DATE 80 EVEITIT DESCRIPTION ANO PROBABI.E CONSEQUENCES 10~oz Burin stead state o eration erformance of surveillance test IC-75~o 2 found a trip setpoint of 22.5 inches water on one vacuum switch in the~o R vacuum relief s stem from the ressure su ression chamber to the Rx~o s Buildin (68-128.T.S.3.3.6.F requires a setpoint less than or equ'al~o 8 to 0.5 si 13.85 inches ivater.This condition resulted in minimal~o T safet im Iications.
A redundant switch was available to initiate~o 8 o aration of the vacuum relief valve.7 8 9 80 7 8 SYSTES1 CAUSE CAUSE COMP.VALVE CODE CODE"SUBCODE COMPONFNT CODE SUBCOOE SUBCODE~SA Q~EQ~EQ I N S T R 0 Q~SQ~2cl 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LEREPRO EVENT YEAR REPORT NO.CODE>YPE NO.Qir REPQRT~78~~00 6~m~03~L~~0 21 22 23, 24 26 27 28 29 30 31 32 ACTION, FUTURE EFFECT SHUTDOWN ATTACHA1ENT NPROK PRIME COMP COMPONcNT TAKEN ACTION ON PLANT METHOD~OURS 22 SUBS11 TTED FORM SUB, SUPPLIER MANUFACTURER Q18 LIEO>>~2O20~2Q21 0 0 0~~NQ22~TOTE~NQzs N 2 3 5 Q28 33 34 35 36 37 40 41 42 43 44 47 CAUSF DESCRIPTION AND CORRECTIVE ACTIONS'27 o The cause of the failure was instrument drift in a mercoid model CP4122 vacuum switch.Trip setpoint was reset to 6.8 inches water.Current surveillance testing schedules are adequate to ensure early detection of future instrument drifts.4 7 8 9 FACILITY~STATUS<<8 POWER OTHER STATUS S E 28 0 9 6 29 NA 7 8 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION 2 Q42 NA 9 10 PUBLICITY ISSUED~DESCRIPTION
~6)E~EE IEA Dennis t 1acVi tti e NAME OF PREPARER CO LJO~O ACTIVITY CONTENT REI.EASED OF RELEASE AMOUNT OF ACTIVITY Q 8~2 Qzz~2QEE NA 7 8 9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
~I7~00 0 QTT~L Q28 N A 7 8 9 11 12 13 PERSOiNiNEL INJURIES NUMBER O'ESCRIPTIONQ
~00 0 Qio NA I,IETHQD OF DISCOVERY~BQSI 45 46 NA DISCOVERY OESCRIPTIQi'4 Q3 Surveillance Testing LOCATION OF RELEASE QB 80 80 80 80 80 80 NRC IJSE ONLY I I I I I I.I.I..I.I I I"", 315-343-2110 ext.1558 PHONE:
To: PIB-39~)~)rooN.3fa-gQ 2 lg~or<TL/To r Y<iŽ(lil~~.riG l'w:;b~:r', lel ephonc lou::il~ci TO: Director of Pco>>lat<<ry Operation OSl;lK l.-.:ir,n I 63l Pari: l:;en c l:in@nf Pros'ia, Ph.19406 Frooi: Hiirgara lTol:a';cl; Po.jcr Corporation bine hilt.Point, Duel cdr Station U>>lt fiT P 0.Bor.i<32 Lp'colllin9, hcl'I York 13093 SUPiilECT:
PP.Ol',1'T Rl.PO.,TN)].!!
OCD).J)El'CE DOC):l'.T l'0."0-220 LICLl!SE l!0.DPR-G3 ASSJ(islED LER HO.'8-09 CYGNET DATE: 78022E REPORT Df<TE: 78022I EVErlT DFSCRIPTTnrl:
SEE ATTACHED.CO:(POlKliTS Il'OL"ED: TIP machine shear va'1ve squfb devices , CAUSE l(t!D RKr':ENf(L ACTIDIL circuit per GE revisi'on Institution of modiffcation in squib FE(CILITV STATUS=c)Routine Startop d)Routln~Sll:: dc"n e)stea<ry s:.iie opLl-~f)Load Cl'.-.age S;TllEt:Wnt.
bi(1840 Slwit<foi~o refuel lng Other l(ot lippj'IcBI>IL IL i'riticn follow-up rcport will be sent v;itbin i<io v.'ccl:s.vr..roon ro 35 7 6.H:i ll.roo~rV: P.~~a" owL a 2.i llM H.
ATTACHMENT TO LER 78-09 Event
Description:
During routine station operation with the TIP detectors.
withdrawn, repTacement explosive charges in the TIP system shear valves were replcaed with new charges.Following replacement, it was found that the ohmneter contlnuity test for acceptable eTectric contact was unsatisfactory.
The normal TIP tube tsoTaticm system was.operabTe at this time.I It was found thart the.actual etectricaV connections to the.explosive charges were net as-described
-4n the maStenance-procedure.
-The shear.valves would not have operated to 5solate the TIP guide.tuba witlr the TIp inserted Dectrical connections vill be checked and tested to assure.that the explosive.va7.ves wAl operate as described in the operatic procedures."..Station records;including.
the au6ntenance.-.procedures,-wfTT
=be corrected to reflect the correct.wiriny connections An end-ta-end demonstration-at'he.
explosive shear va7ves=will be performed'ith the explosive charge removed.from..the, system..'orrective action wfll be compTeted before the TIP system is again used r The explosive operated TIP shear tsolation valves are a back-up system to be used for isa'Eatioe of the TIP tubes in the event it is not possible.te wfthdrwr the.detectnr se the normaT automat%a.
i.soTation system may function
