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{{#Wiki_filter:ACCELERATED DIS~BUTION DEMONS+ATION SYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9205280129 DOC.DATE:
{{#Wiki_filter:ACCELERATED DIS~BUTION DEMONS+ATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9205280129 DOC.DATE: 92/05/20 NOTARIZED:
92/05/20NOTARIZED:
NO DOCKET.iz FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION BACKUS,W.H.
NODOCKET.iz FACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G05000244AUTH.NAMEAUTHORAFFILIATION BACKUS,W.H.
Rochester Gas&Electric Corp.MECREDY,R.C.
Rochester Gas&ElectricCorp.MECREDY,R.C.
Rochester Gas&'lectric Corp.RECIP.NAME RECIPIENT AFFILIATION
Rochester Gas&'lectric Corp.RECIP.NAME RECIPIENT AFFILIATION


==SUBJECT:==
==SUBJECT:==
LER92-005-00:on 920420,annual maintenance examperformed onbothS/G"A"&"B."242tubesin"A"&216tubesin"B"S/GrequiredC/Aduetotubedegradation.
LER 92-005-00:on 920420,annual maintenance exam performed on both S/G"A"&"B." 242 tubes in"A"&216 tubes in"B" S/G required C/A due to tube degradation.
Causedbyrecurring IGA/SCC&PWSCC.S/G returntonormal.W/920520 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR l.ENCLQSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.DNOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72).
Caused by recurring IGA/SCC&PWSCC.S/G return to normal.W/920520 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR l.ENCL Q SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244'ARECIPIENT IDCODE/NAME PD1-3LAJOHNSON,A INTERNAL:
05000244'A RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: ACNW AEOD/DS P/TPAB NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB8H3 NRR/DST/SRXB 8E RES/DSIR/EIB EXTERNAL: EG&G BRYCE,J.H NRC PDR NSIC POOREiW~COPIES LTTR ENCL 1 1 1 1 2 2 1.1 1 1 1 1 2 2 1 1 1 1 1.1 3 3 1 1 1.1 RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DOA AEOD/ROA B/DS P NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8D NRR DST/SPLB8D1 R&02 RGN1 FI E 01 L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 D D S, R D NOTE TO ALL"RIDS" RECIPIENTS:
ACNWAEOD/DSP/TPABNRR/DET/EMEB 7ENRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB8H3 NRR/DST/SRXB 8ERES/DSIR/EIB EXTERNAL:
A D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOiv1 P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30 t I
EG&GBRYCE,J.H NRCPDRNSICPOOREiW~COPIESLTTRENCL1111221.111112211111.133111.1RECIPIENT IDCODE/NAME PD1-3PDAEOD/DOAAEOD/ROAB/DSPNRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8DNRRDST/SPLB8D1 R&02RGN1FIE01LSTLOBBYWARDNSICMURPHY,G.A NUDOCSFULLTXTCOPIESLTTRENCL11DDS,RDNOTETOALL"RIDS"RECIPIENTS:
'OCHESTER GAS AND ELECTRIC CORPORATION ROBERTC MECREDY Vice President Cinna Nuclear PsoducRon i;coen aeaee~e9 EAST AVENUE, ROCHESTER N.K 14649-0001 a TECEPHOkE AREA CODE 716 546 2700 May 20, 1992 U.S.Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
ADDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOiv1P1-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
LTTR30ENCL30 tI
'OCHESTER GASANDELECTRICCORPORATION ROBERTCMECREDYVicePresident CinnaNuclearPsoducRon i;coenaeaee~e9EASTAVENUE,ROCHESTER N.K14649-0001 aTECEPHOkE AREACODE7165462700May20,1992U.S.NuclearRegulatory Commission DocumentControlDeskWashington, DC20555


==Subject:==
==Subject:==
LER92-005,SteamGenerator TubeDegradation DuetoIGA/SCC,CausesQ.A.ManualReportable LimitstobeReachedR.E.GinnaNuclearPower.PlantDocketNo.50-244Inaccordance with10CFR50.73,LicenseeEventReportSystem,item(other),andtheGinnaStationQualityAssurance ManualAppendixB,whichrequiresthat,"Ifthenumberoftubesinagenerator fallingintocategories (a)or(b)belowexceedsthecriteria, thenresultsoftheinspection shallbeconsidered areportable eventpursuantto10CFR50.73,"theattachedLicenseeEventReportLER92-005'is herebysubmitted.
LER 92-005, Steam Generator Tube Degradation Due to IGA/SCC, Causes Q.A.Manual Reportable Limits to be Reached R.E.Ginna Nuclear Power.Plant Docket No.50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (other), and the Ginna Station Quality Assurance Manual Appendix B, which requires that,"If the number of tubes in a generator falling into categories (a)or (b)below exceeds the criteria, then results of the inspection shall be considered a reportable event pursuant to 10 CFR 50.73," the attached Licensee Event Report LER 92-005'is hereby submitted.
Thiseventhasinnowayaffectedthepublic'shealthandsafety.Verytrulyyours,RobertC.MeredXC'.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussiaPA19406GinnaUSNRCSeniorResidentInspector 9205280129 920520PDRADOCK050002448PDR~@PE,<7~E W/~gag'l<
This event has in no way affected the public's health and safety.Very truly yours, Robert C.Me red XC'.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia PA 19406 Ginna USNRC Senior Resident Inspector 9205280129 920520 PDR ADOCK 05000244 8 PDR~@PE,<7~E W/~gag'l<
l NACFORM368(64)9)LICENSEEEVENTREPORT(LERIAPPROVEDOMBNO.31504)104 EXPIRES:4(30(92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(F630).V.S.NUCLEARREGULATORY COMMISSION, WASHINGTON.
l NAC FORM 368 (64)9)LICENSEE EVENT REPORT (LERI APPROVED OMB NO.31504)104 EXPIRES: 4(30(92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F630).V.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON.
DC20555,ANDTOTHEPAPERWORK REDUCTION PROJECT(31500104),
DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31500104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON.
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON.
DC 20503.'ACILITY NAME (1I R.E.Ginna Nuclear Power Plant DOCKET NUMBER (2)PA E 3 050002441OF09
DC20503.'ACILITYNAME(1IR.E.GinnaNuclearPowerPlantDOCKETNUMBER(2)PAE3050002441OF09
"""" Steam Generator Tube Degradation Due To 1GA/SCC Causes Q.A.Manual Reportable Limits To Be Reached EVENT DATE IS)LER NUMBER (6I>>REPORT DATE (7)OTHER FACILITIES INVOLVED (8)MONTH DAY YEAR YEAR BEOUENTIAL erg NUMBER NUMBER REYIBON MONTH OAY YEAR FACILITY NAMES DOCKET NUMBER(S)0 5 0 0 0 042 0 9 2 9 2 0 0 5 000 5 2 0 9 2 0 5 0 0 0 OPERATING MODE (9)POWER LEVEL (10)@P)CP@&m(r'.a)P 20A02(B)20.405 (s I (I)ill 20.405 (s Ill I (II I 20.405(el(1llill) 20A05 (s I (1)(lv)20.405(s)(I I(vl 20A05(c)50.38(cl(1) 50.38(cl(2) 50.73(s I l2)(l)50.73(el(2)(li) 50.73(s l(2)Bill LICENSEE CONTACT FOR THIS LER (12)50.73(s)(2)(irl 50.73(sl(2)(vl 50,73(sl(2)(vill 50,73(s I (2 I (ri II I (Al 50,73(s)(2)(rill l(B)50,73(sl(2)(sl THIS REPORT IS SUBMITTFO PURSUANT T 0 THE RLQVIREMENTS OF 10 CFR ()I ICnec>>One or more ol the lollowinPI (11 73.71(BI 73.7((cl X OTHER ISpeclly In Aottrect Below end ln Tenet, HRC Form 366A)NAME Wesley H.Backus.Technical Assistant to-the Operations Manager TELEPHONE NUMBER AREA CODE 31 552 4-4 446 COMPLETE ONE LINE FOA EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TURER EPORTABLE TO NPRDS SYSTEM COMPONENT MANUFAC TURER EPORTABLE TO NPRDS X A B T BGH 31 4 IR4$e($BW@~NIINA!
""""SteamGenerator TubeDegradation DueTo1GA/SCCCausesQ.A.ManualReportable LimitsToBeReachedEVENTDATEIS)LERNUMBER(6I>>REPORTDATE(7)OTHERFACILITIES INVOLVED(8)MONTHDAYYEARYEARBEOUENTIAL ergNUMBERNUMBERREYIBONMONTHOAYYEARFACILITYNAMESDOCKETNUMBER(S) 05000042092920050005209205000OPERATING MODE(9)POWERLEVEL(10)@P)CP@&m(r
r.k45%4: SUPPLEMENTAL REPORT EXPECTED (14)EXPECTED SU 6 M I SS IO N DATE 115)MONTH DAY YEAR YES III yer, complete EXPECTED S(IB4IISSION DATEI NO ABSTRACT ILlmlt to 1400 rpecsL i,e., epproslmerely Irfteen tinple spree typewritten linn)(18)During the 1992 Annual Refueling and Maintenance Outage, subsequent to the Eddy Current Examination performed on both the'"A" and"B" Westinghouse Series 44 Steam Generator (S/G)., 242 tubes in the"A" S/G and 2'16 tubes in the"B"'S/G required corrective action due to tube degradation.
'.a)P20A02(B)20.405(sI(I)ill20.405(sIllI(III20.405(el(1llill) 20A05(sI(1)(lv)20.405(s)
-Two additional tubes in each S/G were stabilized and plugged as preventive action, due to anti-vibration bar (AVB)concerns.The immediate cause of the event was that the"A" and"B" S/G tube degradation was in excess of the Ginna Quality Assurance Manual Reportability Limits.The underlying cause of the tube degradation is a common S/G'roblem of a partially rolled tube sheet crevice with recurring intergranular attack/stress corrosion cracking (IGA/SCC)and Primary Water-Stress Corrosion Cracking (PWSCC)attack.on S/G tubing.Corrective action taken was to either sleeve'r plug the affected tubes with accepted industry repair methods.NRC Form 366 (64)9) t I NRC FORM 38SA (589)t US.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED OMB NO.3150010O EXPIRES: O/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUESTI 50/)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F430), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION.
(II(vl20A05(c)50.38(cl(1) 50.38(cl(2) 50.73(sIl2)(l)50.73(el(2)(li) 50.73(sl(2)BillLICENSEECONTACTFORTHISLER(12)50.73(s)(2)(irl50.73(sl(2)(vl 50,73(sl(2)(vill 50,73(sI(2I(riIII(Al50,73(s)(2)(rilll(B)50,73(sl(2)(sl THISREPORTISSUBMITTFO PURSUANTT0THERLQVIREMENTS OF10CFR()IICnec>>OneormoreolthelollowinPI (1173.71(BI73.7((clXOTHERISpecllyInAottrectBelowendlnTenet,HRCForm366A)NAMEWesleyH.Backus.Technical Assistant to-theOperations ManagerTELEPHONE NUMBERAREACODE315524-4446COMPLETEONELINEFOAEACHCOMPONENT FAILUREDESCRIBED INTHISREPORT(13)CAUSESYSTEMCOMPONENT MANUFAC.TUREREPORTABLE TONPRDSSYSTEMCOMPONENT MANUFACTUREREPORTABLE TONPRDSXABTBGH314IR4$e($BW@~NIINA!
PROJECT (315041(H), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1I DOCKET NUMBER l2)LER NUMBER (5)PAGE (3)YEAR g)SEQUENTIAL NUMBER REVISION NUM854 R.E.Ginna Nuclear Power Plant TEXT///II>>>><<>>cob JoqokaL Uoo d/I/ooo/HRC FeIIR 3SSAB/(17) o s o o o 2 4 4 9 2 0 0 5 0 0 02 o" 0 9 PRE-EVENT PLANT CONDITIONS The plant was in the Cold/Refueling Shutdown condition for the Annual Refueling and Maintenance Outage.Reactor Coolant System (RCS)was depressurized and RCS temperature was approximately 65 F.Steam Generator (S/G)Eddy Current Inspection was'in progress.DESCRIPTION OR EVENT A.DATES AND APPROXIMATE TIMES OR MAZOR OCCURRENCES:
r.k45%4:SUPPLEMENTAL REPORTEXPECTED(14)EXPECTEDSU6MISSIONDATE115)MONTHDAYYEARYESIIIyer,completeEXPECTEDS(IB4IISSION DATEINOABSTRACTILlmltto1400rpecsLi,e.,epproslmerely Irfteentinplespreetypewritten linn)(18)Duringthe1992AnnualRefueling andMaintenance Outage,subsequent totheEddyCurrentExamination performed onboththe'"A"and"B"Westinghouse Series44SteamGenerator (S/G).,242tubesinthe"A"S/Gand2'16tubesinthe"B"'S/Grequiredcorrective actionduetotubedegradation.
0 April 20, 1992, 1200 EDST: Event Date and Time 0 April 20, 1992, 1200 EDST: Discovery Date and Time 0 April 21, 1992, 1330 EDST: Oral Notification made to the NRC Office of Nuclear Reactor Regulation (NRR)..0 April 26, 1992, 1742 EDST: repairs completed.
-Twoadditional tubesineachS/Gwerestabilized andpluggedaspreventive action,duetoanti-vibration bar(AVB)concerns.
Steam Generator 0 May 5, 1992: Follow-up written report sent to NRC Office of NRR.B.EVENT During the 1992 Annual Refueling and Maintenance Outage, an Eddy Current Examination was performed in both the"A" and"B" Westinghouse Series 44 Design Recirculating Steam Generators.
Theimmediate causeoftheeventwasthatthe"A"and"B"S/Gtubedegradation wasinexcessoftheGinnaQualityAssurance ManualReportability Limits.Theunderlying causeofthetubedegradation isacommonS/G'roblem ofapartially rolledtubesheetcrevicewithrecurring intergranular attack/stress corrosion cracking(IGA/SCC) andPrimaryWater-StressCorrosion Cracking(PWSCC)attack.onS/Gtubing.Corrective actiontakenwastoeithersleeve'rplugtheaffectedtubeswithacceptedindustryrepairmethods.NRCForm366(64)9) tI NRCFORM38SA(589)tUS.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDOMBNO.3150010OEXPIRES:O/30/92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUESTI50/)HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(F430),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555,ANDTO1HEPAPERWORK REDUCTION.
The purpose of the Eddy Current Examination was to assess any corrosion or mechanical damage that may have occurred during the cycle since the 1991 examination.
PROJECT(315041(H),
The examination was performed by personnel from Rochester Gas and Electric (RG&E)and Allen Nuclear Associates, Inc.(ANA).All personnel were trained and qualified in the Eddy Current Examination method and have been certified to a minimum of Level I for data acquisition and Level II for data analysis.NRC Form 355A (609)
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACILITYNAME(1IDOCKETNUMBERl2)LERNUMBER(5)PAGE(3)YEARg)SEQUENTIAL NUMBERREVISIONNUM854R.E.GinnaNuclearPowerPlantTEXT///II>>>><<>>cobJoqokaLUood/I/ooo/HRC FeIIR3SSAB/(17) osooo244920050002o"09PRE-EVENT PLANTCONDITIONS TheplantwasintheCold/Refueling Shutdowncondition fortheAnnualRefueling andMaintenance Outage.ReactorCoolantSystem(RCS)wasdepressurized andRCStemperature wasapproximately 65F.SteamGenerator (S/G)EddyCurrentInspection was'inprogress.
I NRC FORM 388A (IS$9)US.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT ILER)TEXT CONTINUATION t APPROVED OMB NO.3)600104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS.INFORMATION COLLECTION REQUEST: 503)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P4)30).U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31504)104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (6)PAGE (3)R.E.Ginna Nuclear Power Plant TEXT (ff more Soeoe le rfo/reer/, Iree/frfooo/HRC
DESCRIPTION OREVENTA.DATESANDAPPROXIMATE TIMESORMAZOROCCURRENCES:
%%drrrr 36543/(12) 0 s 0 0 o 2 4 4 YEAR$g 9 2-SEDUENTIAL NUMBER 005@>REVISION.x: NUM ER-0 0 0 3 cF 09 The initial Eddy Current Examination of the"AE(and"B" Steam Generators was performed" utilizing the Zetec 3-Coil Motorized Rotating Pancake Coil (MRPC)probe and the Zetec MIZ-18 Digital Data Acquisition System.The'frequencies selected were 400, 300, 100, and 25 KHZ.Additional Eddy Current Examinations of the"A"'nd"B" Steam Generators were performed utilizing the.standard 0.740" or 0.720" O.D.Bobbin Coil Probe.The frequencies selected were 400, 200, 100 and 25 KHZ.The Inlet or Hot Leg Examination Program Plan included the examination of 100%of each open unsleeved steam generator tube.from'the tube end to the top of the tube sheet with MRPC.Twenty percent of the tubes were selected and examined for their full length (20%random sample as recommended in the Electric Power Research Institute (EPRI)guidelines) with a bobbin coil.In addition, 204 of.each type of sleeve was examined and the remainder (unsleeved portion)of the tube was examined full length.All Row 1 and Row 2 U-bend regions selected as part of the 204 random sample were examined with the MRPC between the g6 Tube Support Plate Hot Side (TSPH)and the g6 Tube Support Plate Cold Side (TSPC)from the Cold Leg Side.Results of the above inspections indicated that 244 tubes in the"A" Steam Generator (i.e.226-new repairs, plus 16 previously plugged tubes, plus 2 tubes stabilized for Anti-Vibration Bar (AVB)concerns)and 218 tubes in the"B" Steam Generator (i.e.183 new repairs, plus 3 B&W explosive plugs, plus 30 previously plugged tubes, plus 2 tubes stabilized for AVB concerns)required action.Corrective actions were therefore taken for 242 tubes in the"A" S/G, and for 216 tubes in the"B" S/G.Preventive actions (for AVB concerns)were taken for 2 tubes in each S/G.NRC Form 368A (689)  
0April20,1992,1200EDST:EventDateandTime0April20,1992,1200EDST:Discovery DateandTime0April21,1992,1330EDST:OralNotification madetotheNRCOfficeofNuclearReactorRegulation (NRR)..0April26,1992,1742EDST:repairscompleted.
SteamGenerator 0May5,1992:Follow-up writtenreportsenttoNRCOfficeofNRR.B.EVENTDuringthe1992AnnualRefueling andMaintenance Outage,anEddyCurrentExamination wasperformed inboththe"A"and"B"Westinghouse Series44DesignRecirculating SteamGenerators.
ThepurposeoftheEddyCurrentExamination wastoassessanycorrosion ormechanical damagethatmayhaveoccurredduringthecyclesincethe1991examination.
Theexamination wasperformed bypersonnel fromRochester GasandElectric(RG&E)andAllenNuclearAssociates, Inc.(ANA).Allpersonnel weretrainedandqualified intheEddyCurrentExamination methodandhavebeencertified toaminimumofLevelIfordataacquisition andLevelIIfordataanalysis.
NRCForm355A(609)
I NRCFORM388A(IS$9)US.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORTILER)TEXTCONTINUATION tAPPROVEDOMBNO.3)600104EXPIRES:4/30/92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHIS.INFORMATION COLLECTION REQUEST:503)HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(P4)30).U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555,ANDTO1HEPAPERWORK REDUCTION PROJECT(31504)104),
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACILITYNAME(1)DOCKETNUMBER(2)LERNUMBER(6)PAGE(3)R.E.GinnaNuclearPowerPlantTEXT(ffmoreSoeoelerfo/reer/,
Iree/frfooo/HRC
%%drrrr36543/(12) 0s00o244YEAR$g92-SEDUENTIAL NUMBER005@>REVISION.x:NUMER-0003cF09TheinitialEddyCurrentExamination ofthe"AE(and"B"SteamGenerators wasperformed" utilizing theZetec3-CoilMotorized RotatingPancakeCoil(MRPC)probeandtheZetecMIZ-18DigitalDataAcquisition System.The'frequencies selectedwere400,300,100,and25KHZ.Additional EddyCurrentExaminations ofthe"A"'nd"B"SteamGenerators wereperformed utilizing the.standard0.740"or0.720"O.D.BobbinCoilProbe.Thefrequencies selectedwere400,200,100and25KHZ.TheInletorHotLegExamination ProgramPlanincludedtheexamination of100%ofeachopenunsleeved steamgenerator tube.from'thetubeendtothetopofthetubesheetwithMRPC.Twentypercentofthetubeswereselectedandexaminedfortheirfulllength(20%randomsampleasrecommended intheElectricPowerResearchInstitute (EPRI)guidelines) withabobbincoil.Inaddition, 204of.eachtypeofsleevewasexaminedandtheremainder (unsleeved portion)ofthetubewasexaminedfulllength.AllRow1andRow2U-bendregionsselectedaspartofthe204randomsamplewereexaminedwiththeMRPCbetweentheg6TubeSupportPlateHotSide(TSPH)andtheg6TubeSupportPlateColdSide(TSPC)fromtheColdLegSide.Resultsoftheaboveinspections indicated that244tubesinthe"A"SteamGenerator (i.e.226-newrepairs,plus16previously pluggedtubes,plus2tubesstabilized forAnti-Vibration Bar(AVB)concerns) and218tubesinthe"B"SteamGenerator (i.e.183newrepairs,plus3B&Wexplosive plugs,plus30previously pluggedtubes,plus2tubesstabilized forAVBconcerns) requiredaction.Corrective actionsweretherefore takenfor242tubesinthe"A"S/G,andfor216tubesinthe"B"S/G.Preventive actions(forAVBconcerns) weretakenfor2tubesineachS/G.NRCForm368A(689)  


NRCFORM366A(669)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LERITEXTCONTINUATION eAPPAOVED0MBNO.3)500)OEEXPIRE5I4/30/92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUEST.'00 HRS.FORWARDCOMMENTSAEGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(F430),U.S.NUCLEARAEGULATOAY COMMISSION, WASHINGTON, OC20555,ANDTOTHEPAPERWORK REDUCTION PROJECT(3)500104),
NRC FORM 366A (669)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LERI TEXT CONTINUATION e APPAOVED 0MB NO.3)500)OE E XPIR E 5 I 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST.'00 HRS.FORWARD COMMENTS AEGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F430), U.S.NUCLEAR AEGULATOAY COMMISSION, WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3)500104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER FSI SEOVENTIAL NVM ER@r REVISION NVM ER PAGE (3)R.E.Ginna Nuclear Power Plant TEXT///mom EPEEE/E/PEVked, IIEP J/(/BRE/NRC
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACILITYNAME(1)DOCKETNUMBER(2)YEARLERNUMBERFSISEOVENTIAL NVMER@rREVISIONNVMERPAGE(3)R.E.GinnaNuclearPowerPlantTEXT///momEPEEE/E/PEVked, IIEPJ/(/BRE/NRC
%%dnR 35663)((7)0 6 0 0 0 2 4 4 9 2 0 0 5 00 04 QF 0 9 On April 20, 1992 at approximately 1200 EDST, with the RCS depressurized and temperature at approximately 65 F, final review of the 1992 S/G Inspection Eddy Current results was completed.
%%dnR35663)((7)06000244920050004QF09OnApril20,1992atapproximately 1200EDST,withtheRCSdepressurized andtemperature atapproximately 65F,finalreviewofthe1992S/GInspection EddyCurrentresultswascompleted.
Results of this review indicated that more than 10 percent of the total tubes inspected are degraded (i.e.imperfections greater than 20 percent of the nominal wall thickness) and more than one percent of the total tubes inspected are degraded (i.e.imperfections greater than the repair limit)..Because of the above, the results of the inspection are considered a reportable event pursuant to 10 CFR 50.73 per Appendix B-of the Ginna Station Quality Assurance Manual.On April 21, 1992 at approximately 1330 EDST, oral notification was made to the NRC Office of NRR pursuant to Appendix B of the Ginna,Station Quality Assurance Manual.On May 5, 1992 a follow-up written report of the Steam Generators Inspection and Repairs was sent to the NRC pursuant to'Appendix B of the Ginna Station Quality Assurance Manual.C.r INOPERABLE STRUCTURES COMPONENTS, OR SYSTEMS THAT CONTRIBUTED TO THE EVENT: D.None.OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED None.E.METHOD OP DISCOVERY:
Resultsofthisreviewindicated thatmorethan10percentofthetotaltubesinspected aredegraded(i.e.imperfections greaterthan20percentofthenominalwallthickness) andmorethanonepercentofthetotaltubesinspected aredegraded(i.e.imperfections greaterthantherepairlimit)..Becauseoftheabove,theresultsoftheinspection areconsidered areportable eventpursuantto10CFR50.73perAppendixB-oftheGinnaStationQualityAssurance Manual.OnApril21,1992atapproximately 1330EDST,oralnotification wasmadetotheNRCOfficeofNRRpursuanttoAppendixBoftheGinna,Station QualityAssurance Manual.OnMay5,1992afollow-up writtenreportoftheSteamGenerators Inspection andRepairswassenttotheNRCpursuantto'Appendix BoftheGinnaStationQualityAssurance Manual.C.rINOPERABLE STRUCTURES COMPONENTS, ORSYSTEMSTHATCONTRIBUTED TOTHEEVENT:D.None.OTHERSYSTEMSORSECONDARY FUNCTIONS AFFECTEDNone.E.METHODOPDISCOVERY:
The event was apparent after the final review of the"A" and"B" Steam Generators Eddy Current Examination results.NRC PARR 366A (669)  
Theeventwasapparentafterthefinalreviewofthe"A"and"B"SteamGenerators EddyCurrentExamination results.NRCPARR366A(669)  


NRCFORM366A(889)(LS.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION tAPPROVEDOMBNO.3(500)04EXPIRES:4(30/92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUESTI50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(P430),U.S.NUCLEARREGULATORY COMMISSION.
NRC FORM 366A (889)(LS.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION t APPROVED OMB NO.3(500)04 EXPIRES: 4(30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUESTI 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P430), U.S.NUCLEAR REGULATORY COMMISSION.
WASHINGTON.
WASHINGTON.
DC20555,ANDTOTHEPAPERWORK REDUCTION PROJECT(3150010E),
DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150010E), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (6)PAGE (3)YEAR oyer SEQUENTIAL NUMSER REVISION NUMBER R.EP Ginna Nuclear Power Plant TEXT (I/more epece Je eePJPPIL Iree aB(ro'encl HRC Fcnn 36848)()7)0 6 0 0 0 2 4 4 9 2-0 0 5 0 005 QF0 9 P.OPERATOR ACTION: Control Room operators completed the notifications and evaluations required by the A-25.1 (Ginna Station Event Report), submitted for the event by the S/G supervision.
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACILITYNAME(1)DOCKETNUMBER(2)LERNUMBER(6)PAGE(3)YEARoyerSEQUENTIAL NUMSERREVISIONNUMBERR.EPGinnaNuclearPowerPlantTEXT(I/moreepeceJeeePJPPILIreeaB(ro'encl HRCFcnn36848)()7)0600024492-0050005QF09P.OPERATORACTION:ControlRoomoperators completed thenotifications andevaluations requiredbytheA-25.1(GinnaStationEventReport),submitted fortheeventbytheS/Gsupervision.
G.SAFETY SYSTEM RESPONSES.
G.SAFETYSYSTEMRESPONSES.
None.III CAUSE OP EVENT A.IMMEDIATE CAUSE: The immediate cause of the event was that the"ALI and"BLI Steam Generator tube degradation was in excess of the Ginna Station Quality Assurance Manual Reportable Limits.B.ROOT CAUSE: The results of the examination indicate that Intergranular Attack (IGA)and Intergranular Stress Corrosion Cracking (IGSCC)continue to be active within the tubesheet crevice region on the inlet side of each steam generator.
None.IIICAUSEOPEVENTA.IMMEDIATE CAUSE:Theimmediate causeoftheeventwasthatthe"ALIand"BLISteamGenerator tubedegradation wasinexcessoftheGinnaStationQualityAssurance ManualReportable Limits.B.ROOTCAUSE:Theresultsoftheexamination indicatethatIntergranular Attack(IGA)andIntergranular StressCorrosion Cracking(IGSCC)continuetobeactivewithinthetubesheet creviceregionontheinletsideofeachsteamgenerator.
As in the past, IGA/SCC is much more prevalent in the"B" Steam Generator with 118 new crevice indications reported.In the"A" Steam Generator, 34 new crevice indications were reported.The majority of the inlet tubesheet crevice corrosion indications are IGA/SCC of the Mill Annealed Inconel 600 tube material.This form of corrosion's believed to be the result of an alkaline environment forming in the tubesheet crevices.This environment has developed over the years as deposits and active species such as sodium and phosphate, have reacted, changing a neutral or inhibited crevice into the aggressive environment that presently exists.NRC Form 366A (6J)9)  
Asinthepast,IGA/SCCismuchmoreprevalent inthe"B"SteamGenerator with118newcreviceindications reported.
Inthe"A"SteamGenerator, 34newcreviceindications werereported.
Themajorityoftheinlettubesheet crevicecorrosion indications areIGA/SCCoftheMillAnnealedInconel600tubematerial.
Thisformofcorrosion's believedtobetheresultofanalkalineenvironment forminginthetubesheet crevices.
Thisenvironment hasdeveloped overtheyearsasdepositsandactivespeciessuchassodiumandphosphate, havereacted,changinganeutralorinhibited creviceintotheaggressive environment thatpresently exists.NRCForm366A(6J)9)  


NRCFORM386A(BJIS)i(LS.NUCLEARAEGULATORY COMMISSION LICENSEEEVENTREPORTILER)TEXTCONTINUATION tAPPROVEDOMBNO.31500104EXPIRES'/30/$
NRC FORM 386A (BJIS)i (LS.NUCLEAR AEGULATORY COMMISSION LICENSEE EVENT REPORT ILER)TEXT CONTINUATION t APPROVED OMB NO.31500104 EXPIRES'/30/$
2ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFOAMATION COLLECTION REQUEST:500HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(PJ)30),US.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555,ANDTO1'HEPAPERWORK REDUCTION PROJECT(3)500104),
2 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFOAMATION COLLECTION REQUEST: 500 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (PJ)30), US.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1'HE PAPERWORK REDUCTION PROJECT (3)500104), OFF ICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (8)YEAR PR SEQUENTIAL Sa~r..6%NUM ER%o REVISION NVMSER PAGE (3)R.E.Ginna Nuclear Power Plant TEXT////Sore 8/reoe/e/Fr/rer/, Iree///0'ooe/HRC ForIII 38//AS/(IT) 24 492 00 5 000 OF Along with IGA/SCC in'the crevices, there appears to have been a slight increase in"Primary Water Stress Corrosion Cracking (PWSCC)at the roll transition during the last operating cycle.This mechanism was first addressed in 1989 and this year there were 63 roll transition PWSCC indications in"B" Steam Generator and 189 roll transition (PWSCC)indications in"A" Steam Generator.
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACILITYNAME(1)DOCKETNUMBER(2)LERNUMBER(8)YEARPRSEQUENTIAL Sa~r..6%NUMER%oREVISIONNVMSERPAGE(3)R.E.GinnaNuclearPowerPlantTEXT////Sore8/reoe/e/Fr/rer/,
These numbers include tubes that may have PWSCC in combination with IGA and SCC in the crevice.XV ANALYSIS OP EVERT This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report item (other)and the Ginna Station Quality Assurance Manual Appendix B which requires that,."If the number of tubes in a generator falling into categories (a)or (b)exceeds the criteria, then results of the inspection shall be considered a reportable event pursuant to 10 CFR 50.73." The tube degradation in the"AL)and"B" Steam Generators exceeded the criterion of (a)which states,"more than 10 percent of the total tubes inspected are degraded (imperfections ,greater than 20 percent of the nominal wall thickness)", and the criterion of (b)which states,"more than 1 percent of the total tubes inspected are degraded (imperfections greater than the repair limit).This repair limit is defined as,"Steam Generator tubes that have imperfections greater than 40 percent through wall, as indicated by Eddy Current, shall be repaired by plugging or sleeving." NRC Form 386A (86$)  
Iree///0'ooe/HRC ForIII38//AS/(IT) 24492005000OFAlongwithIGA/SCCin'thecrevices, thereappearstohavebeenaslightincreasein"PrimaryWaterStressCorrosion Cracking(PWSCC)attherolltransition duringthelastoperating cycle.Thismechanism wasfirstaddressed in1989andthisyeartherewere63rolltransition PWSCCindications in"B"SteamGenerator and189rolltransition (PWSCC)indications in"A"SteamGenerator.
.J NRC FOAM 366A (669)US.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION e APPROVED OMB NO.31500)04 EXPIRES: 6/30/92 ESTIMATED BURDEN PE4 RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50A)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE 4ECORDS AND 4EPOATS MANAGEMENT BRANCH (F430).U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK 4EDUCTION PROJECT (31500104).
ThesenumbersincludetubesthatmayhavePWSCCincombination withIGAandSCCinthecrevice.XVANALYSISOPEVERTThiseventisreportable inaccordance with10CFR50.73,LicenseeEventReportitem(other)andtheGinnaStationQualityAssurance ManualAppendixBwhichrequiresthat,."Ifthenumberoftubesinagenerator fallingintocategories (a)or(b)exceedsthecriteria, thenresultsoftheinspection shallbeconsidered areportable eventpursuantto10CFR50.73."Thetubedegradation inthe"AL)and"B"SteamGenerators exceededthecriterion of(a)whichstates,"morethan10percentofthetotaltubesinspected aredegraded(imperfections
OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER (6)SEOUENTIAL gP NUMBER REVISION NUMBER PAGE (3)R.E..Ginna Nuclear Power Plant TEXT/I/more<<>>ce/e nrFI/rer/Bee a///Noor>>l NRC Forrrl J(ISAB/((2) 0 5 0 0 0 24-4 9 2 0 0 5 00 07 OF 0 9 An assessment was performed considering the safety.consequences and implications of this event with the following results and conclusions:
,greaterthan20percentofthenominalwallthickness)",
There were no safety consequences or implications resulting from the Steam Generator tube degradation in excess of the Quality Assurance Manual Reportable Limits because:.o The.degraded tubes were identified and repaired prior to any significant leakage or Steam Generator tube rupture occurring.
andthecriterion of(b)whichstates,"morethan1percentofthetotaltubesinspected aredegraded(imperfections greaterthantherepairlimit).Thisrepairlimitisdefinedas,"SteamGenerator tubesthathaveimperfections greaterthan40percentthroughwall,asindicated byEddyCurrent,shallberepairedbypluggingorsleeving."
0 Even assuming a complete severance of a Steam Generator tube at full power, as stated in the R.E.Ginna Nuclear Power Plant Updated Final Safety Analysis Report (Ginna/UFSAR) section 15.6.3, (Steam Generator Tube Rupture), the sequence of recovery actions ensures early termination.of primary to secondary leakage with or without offsite power available thus limiting offsite radiation doses to within the guidelines of 10 CFR 100.~Based on the above, it can be concluded that the public's health and safety was assured at all times.V.CORRECTIVE ACTION A.ACTION TAKEN TO RETURN AFFECTED SYSTEMS.TO PRE-EVENT NORMAL STATUS: o'f the 244 tubes in the"A" Steam Generator, 36 tubes were repaired using a Combustion Engineering 27" welded sleeve in the Hot Leg, plus 194 tubes were repaired using a Babcock and Wilcox explosively welded tubesheet sleeve in the Hot Leg and all of the above tubes will remain in service.The remaining 14 tubes=were removed from service by plugging both the Hot and Cold Leg tube ends.A total of 185 tubes in the"A" Steam Generator are currently plugged and 555 tubes are sleeved.NRC Form 366A (689)
NRCForm386A(86$)  
I NRC FORM 3SSA (W)US.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT ILER)TEXT CONTINUATION l APPROVEOOMB NO.3I50010O i EXPIRES: O/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (PJ)30), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31504104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACII.ITY NAME (1I DOCKET NUMBER (2)YEAR LER NUMBER (Sl SEOVENTIAL NVM ER REVISION NUMBER PAGE (3)R.E.Ginna Nuclear Power Plant TEXT/I/more e/>>ce/or/q/rer/
.J NRCFOAM366A(669)US.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION eAPPROVEDOMBNO.31500)04EXPIRES:6/30/92ESTIMATED BURDENPE4RESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUEST:50A)HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHE4ECORDSAND4EPOATSMANAGEMENT BRANCH(F430).U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555,ANDTO1HEPAPERWORK 4EDUCTION PROJECT(31500104).
Iree<<IChE/<<>>/NRC%%de 3SBAB/(IT)0 S 0 0 0 2 4 4 9 2 0 0 5 000 OF 0 Of the 218 tubes in the"B" Steam Generator, 186 tubes were repaired using a Combustion Engineering 27" welded sleeve in the Hot Leg, plus 9 tubes were repaired using a Combustion Engineering 30" welded sleeve in the Hot Leg and all of the above tubes will remain in service.The remaining 23 tubes were removed from=service by plugging both the Hot and Cold Leg tube ends.A total of 313 tubes.in the"BL(Steam Generator are currently plugged and 1134 tubes are sleeved.All the above repairs on the"A" and"BL(Steam Generators were completed on April 26, 1992 at approximately 1742 EDST.B.ACTION TAKEN OR PLANNED TO PRVTENT RECURRENCE:-The occurrence/presence of IGA, SCC,.and PWSCC is a common PWR Steam Generator problem.Utilities with susceptible tubing and partially rolled crevices must deal with this recurring attack on Steam Generator tubing.R.E.Ginna Nuclear Power Plant will continue careful monitoring of both primary RCS and'econdary side water chemistry parameters.
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, OC20503.FACILITYNAME(1)DOCKETNUMBER(2)YEARLERNUMBER(6)SEOUENTIAL gPNUMBERREVISIONNUMBERPAGE(3)R.E..GinnaNuclearPowerPlantTEXT/I/more<<>>ce/enrFI/rer/
These water chemistry parameters will continue to be evaluated against accepted industry guidelines in order to minimize harmful primary and/or secondary side environments.
Beea///Noor>>l NRCForrrlJ(ISAB/((2) 0500024-4920050007OF09Anassessment wasperformed considering thesafety.consequences andimplications ofthiseventwiththefollowing resultsandconclusions:
Degraded Steam Generator tubes shall be sleeved or plugged in accordance with the Inservice Inspection Program and Accepted Industry Repair methods.ADDITIONAL INFORMATION A.FAILED COMPONENTS:
Therewerenosafetyconsequences orimplications resulting fromtheSteamGenerator tubedegradation inexcessoftheQualityAssurance ManualReportable Limitsbecause:.
The degraded components are: Inconel Grade 600 tubes having an outside diameter of 0.875 inches and a.nominal wall thickness of 0.050 inches.These tubes were manufactured by Huntington Alloy Company.'NR C Form 3SSA (589)  
oThe.degradedtubeswereidentified andrepairedpriortoanysignificant leakageorSteamGenerator tuberuptureoccurring.
0Evenassumingacompleteseverance ofaSteamGenerator tubeatfullpower,asstatedintheR.E.GinnaNuclearPowerPlantUpdatedFinalSafetyAnalysisReport(Ginna/UFSAR) section15.6.3,(SteamGenerator TubeRupture),
thesequenceofrecoveryactionsensuresearlytermination
.ofprimarytosecondary leakagewithorwithoutoffsitepoweravailable thuslimitingoffsiteradiation dosestowithintheguidelines of10CFR100.~Basedontheabove,itcanbeconcluded thatthepublic'shealthandsafetywasassuredatalltimes.V.CORRECTIVE ACTIONA.ACTIONTAKENTORETURNAFFECTEDSYSTEMS.TOPRE-EVENT NORMALSTATUS:o'fthe244tubesinthe"A"SteamGenerator, 36tubeswererepairedusingaCombustion Engineering 27"weldedsleeveintheHotLeg,plus194tubeswererepairedusingaBabcockandWilcoxexplosively weldedtubesheet sleeveintheHotLegandalloftheabovetubeswillremaininservice.Theremaining 14tubes=wereremovedfromservicebypluggingboththeHotandColdLegtubeends.Atotalof185tubesinthe"A"SteamGenerator arecurrently pluggedand555tubesaresleeved.NRCForm366A(689)
I NRCFORM3SSA(W)US.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORTILER)TEXTCONTINUATION lAPPROVEOOMB NO.3I50010O iEXPIRES:O/30/92ESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REOUEST:50.0HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(PJ)30),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555,ANDTOTHEPAPERWORK REDUCTION PROJECT(31504104),
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, DC20503.FACII.ITY NAME(1IDOCKETNUMBER(2)YEARLERNUMBER(SlSEOVENTIAL NVMERREVISIONNUMBERPAGE(3)R.E.GinnaNuclearPowerPlantTEXT/I/moree/>>ce/or/q/rer/
Iree<<IChE/<<>>/
NRC%%de3SBAB/(IT)0S00024492005000OF0Ofthe218tubesinthe"B"SteamGenerator, 186tubeswererepairedusingaCombustion Engineering 27"weldedsleeveintheHotLeg,plus9tubeswererepairedusingaCombustion Engineering 30"weldedsleeveintheHotLegandalloftheabovetubeswillremaininservice.Theremaining 23tubeswereremovedfrom=servicebypluggingboththeHotandColdLegtubeends.Atotalof313tubes.inthe"BL(SteamGenerator arecurrently pluggedand1134tubesaresleeved.Alltheaboverepairsonthe"A"and"BL(SteamGenerators werecompleted onApril26,1992atapproximately 1742EDST.B.ACTIONTAKENORPLANNEDTOPRVTENTRECURRENCE:
-Theoccurrence/presence ofIGA,SCC,.andPWSCCisacommonPWRSteamGenerator problem.Utilities withsusceptible tubingandpartially rolledcrevicesmustdealwiththisrecurring attackonSteamGenerator tubing.R.E.GinnaNuclearPowerPlantwillcontinuecarefulmonitoring ofbothprimaryRCSand'econdary sidewaterchemistry parameters.
Thesewaterchemistry parameters willcontinuetobeevaluated againstacceptedindustryguidelines inordertominimizeharmfulprimaryand/orsecondary sideenvironments.
DegradedSteamGenerator tubesshallbesleevedorpluggedinaccordance withtheInservice Inspection ProgramandAcceptedIndustryRepairmethods.ADDITIONAL INFORMATION A.FAILEDCOMPONENTS:
Thedegradedcomponents are:InconelGrade600tubeshavinganoutsidediameterof0.875inchesanda.nominalwallthickness of0.050inches.Thesetubesweremanufactured byHuntington AlloyCompany.'NRCForm3SSA(589)  


NRCFORM388A(669)US.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APPROVEDOMBNO.3)504104EXPIRES:E/30/IQESTIMATED BURDENPERRESPONSETOCOMPLYWTHTHISINFORMATION COLLECTION REQUEST:505)HRS.FORWARDCOMMENTSREGARDING BURDENESTIMATETOTHERECORDSANDREPORTSMANAGEMENT BRANCH(F830),U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20555,ANDTO1)IEPAPERWORK REDUCTION PROJECT(3150010E).
NRC FORM 388A (669)US.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED OMB NO.3)504104 E XP I R ES: E/30/IQ ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 505)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F830), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1)IE PAPERWORK REDUCTION PROJECT (3150010E).
OFFICEOFMANAGEMENT ANDBUDGET,WASHINGTON, OC20503.FACILITYNAME(1)DOCKETNUMBER(2)YEARLERNUMBER(6)S~SEQVENTIAL NVM@ERj>gjREVISION:i.'/NVMSERPAGE(3)R.E.GinnaNuclearPowerPlantTEXT///IIRvoEPoooJIISA(RR/,vJo//I/ooo/NRC Form36643/(17)060002449005-0009"09B.PREVIOUSLERsOMSIMILAREVENTS:AsimilarLEReventhistorical searchwasconducted withthe.following results:Thecreviceindications aresimilartothosereportedinA0-74-02, AO-75-07, R0-75-013, andLERs76-008,77-008,78-003,79-006,79022/80003/81009/82003/82022/83013/89=-001,90-004,and91-005.CSPECIALCOMMEHTS:
OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER (6)S~SEQVENTIAL NVM@ER j>gj REVISION:i.'/NVMSER PAGE (3)R.E.Ginna Nuclear Power Plant TEXT///IIRvo EPooo JI ISA(RR/, vJo//I/ooo/NRC Form 36643/(17)0 6 0 0 0 2 4 4 9 0 0 5-0 0 0 9"0 9 B.PREVIOUS LERs OM SIMILAR EVENTS: A similar LER event historical search was conducted with the.following results: The crevice indications are similar to those reported in A0-74-02, AO-75-07, R0-75-013, and LERs 76-008, 77-008, 78-003, 79-006, 79 022/80 003/81 009/82 003/82 022/83 013/89=-001, 90-004, and 91-005.C SPECIAL COMMEHTS: For a more indepth report, refer to the"1992 Steam Generator Eddy Current Inspection" Summary Examination Report sent to the NRC May 5, 1992.NRC Form 368A (BJ)9)
Foramoreindepthreport,refertothe"1992SteamGenerator EddyCurrentInspection" SummaryExamination ReportsenttotheNRCMay5,1992.NRCForm368A(BJ)9)
S~~}}
S~~}}

Revision as of 13:15, 7 July 2018

LER 92-005-00:on 920420,determined That 242 Tubes in a SG & 216 Tubes in B SG Required Corrective Action Due to Tube Degradation.Affected Tubes Either Sleeved or Plugged.W/ 920520 Ltr
ML17262A863
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/20/1992
From: BACKUS W H, MECREDY R C
ROCHESTER GAS & ELECTRIC CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-92-005, LER-92-5, NUDOCS 9205280129
Download: ML17262A863 (22)


Text

ACCELERATED DIS~BUTION DEMONS+ATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9205280129 DOC.DATE: 92/05/20 NOTARIZED:

NO DOCKET.iz FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION BACKUS,W.H.

Rochester Gas&Electric Corp.MECREDY,R.C.

Rochester Gas&'lectric Corp.RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 92-005-00:on 920420,annual maintenance exam performed on both S/G"A"&"B." 242 tubes in"A"&216 tubes in"B" S/G required C/A due to tube degradation.

Caused by recurring IGA/SCC&PWSCC.S/G return to normal.W/920520 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR l.ENCL Q SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244'A RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: ACNW AEOD/DS P/TPAB NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB8H3 NRR/DST/SRXB 8E RES/DSIR/EIB EXTERNAL: EG&G BRYCE,J.H NRC PDR NSIC POOREiW~COPIES LTTR ENCL 1 1 1 1 2 2 1.1 1 1 1 1 2 2 1 1 1 1 1.1 3 3 1 1 1.1 RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DOA AEOD/ROA B/DS P NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8D NRR DST/SPLB8D1 R&02 RGN1 FI E 01 L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 D D S, R D NOTE TO ALL"RIDS" RECIPIENTS:

A D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOiv1 P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30 t I

'OCHESTER GAS AND ELECTRIC CORPORATION ROBERTC MECREDY Vice President Cinna Nuclear PsoducRon i;coen aeaee~e9 EAST AVENUE, ROCHESTER N.K 14649-0001 a TECEPHOkE AREA CODE 716 546 2700 May 20, 1992 U.S.Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

LER 92-005, Steam Generator Tube Degradation Due to IGA/SCC, Causes Q.A.Manual Reportable Limits to be Reached R.E.Ginna Nuclear Power.Plant Docket No.50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (other), and the Ginna Station Quality Assurance Manual Appendix B, which requires that,"If the number of tubes in a generator falling into categories (a)or (b)below exceeds the criteria, then results of the inspection shall be considered a reportable event pursuant to 10 CFR 50.73," the attached Licensee Event Report LER 92-005'is hereby submitted.

This event has in no way affected the public's health and safety.Very truly yours, Robert C.Me red XC'.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia PA 19406 Ginna USNRC Senior Resident Inspector 9205280129 920520 PDR ADOCK 05000244 8 PDR~@PE,<7~E W/~gag'l<

l NAC FORM 368 (64)9)LICENSEE EVENT REPORT (LERI APPROVED OMB NO.31504)104 EXPIRES: 4(30(92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F630).V.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON.

DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31500104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON.

DC 20503.'ACILITY NAME (1I R.E.Ginna Nuclear Power Plant DOCKET NUMBER (2)PA E 3 050002441OF09

"""" Steam Generator Tube Degradation Due To 1GA/SCC Causes Q.A.Manual Reportable Limits To Be Reached EVENT DATE IS)LER NUMBER (6I>>REPORT DATE (7)OTHER FACILITIES INVOLVED (8)MONTH DAY YEAR YEAR BEOUENTIAL erg NUMBER NUMBER REYIBON MONTH OAY YEAR FACILITY NAMES DOCKET NUMBER(S)0 5 0 0 0 042 0 9 2 9 2 0 0 5 000 5 2 0 9 2 0 5 0 0 0 OPERATING MODE (9)POWER LEVEL (10)@P)CP@&m(r'.a)P 20A02(B)20.405 (s I (I)ill 20.405 (s Ill I (II I 20.405(el(1llill) 20A05 (s I (1)(lv)20.405(s)(I I(vl 20A05(c)50.38(cl(1) 50.38(cl(2) 50.73(s I l2)(l)50.73(el(2)(li) 50.73(s l(2)Bill LICENSEE CONTACT FOR THIS LER (12)50.73(s)(2)(irl 50.73(sl(2)(vl 50,73(sl(2)(vill 50,73(s I (2 I (ri II I (Al 50,73(s)(2)(rill l(B)50,73(sl(2)(sl THIS REPORT IS SUBMITTFO PURSUANT T 0 THE RLQVIREMENTS OF 10 CFR ()I ICnec>>One or more ol the lollowinPI (11 73.71(BI 73.7((cl X OTHER ISpeclly In Aottrect Below end ln Tenet, HRC Form 366A)NAME Wesley H.Backus.Technical Assistant to-the Operations Manager TELEPHONE NUMBER AREA CODE 31 552 4-4 446 COMPLETE ONE LINE FOA EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TURER EPORTABLE TO NPRDS SYSTEM COMPONENT MANUFAC TURER EPORTABLE TO NPRDS X A B T BGH 31 4 IR4$e($BW@~NIINA!

r.k45%4: SUPPLEMENTAL REPORT EXPECTED (14)EXPECTED SU 6 M I SS IO N DATE 115)MONTH DAY YEAR YES III yer, complete EXPECTED S(IB4IISSION DATEI NO ABSTRACT ILlmlt to 1400 rpecsL i,e., epproslmerely Irfteen tinple spree typewritten linn)(18)During the 1992 Annual Refueling and Maintenance Outage, subsequent to the Eddy Current Examination performed on both the'"A" and"B" Westinghouse Series 44 Steam Generator (S/G)., 242 tubes in the"A" S/G and 2'16 tubes in the"B"'S/G required corrective action due to tube degradation.

-Two additional tubes in each S/G were stabilized and plugged as preventive action, due to anti-vibration bar (AVB)concerns.The immediate cause of the event was that the"A" and"B" S/G tube degradation was in excess of the Ginna Quality Assurance Manual Reportability Limits.The underlying cause of the tube degradation is a common S/G'roblem of a partially rolled tube sheet crevice with recurring intergranular attack/stress corrosion cracking (IGA/SCC)and Primary Water-Stress Corrosion Cracking (PWSCC)attack.on S/G tubing.Corrective action taken was to either sleeve'r plug the affected tubes with accepted industry repair methods.NRC Form 366 (64)9) t I NRC FORM 38SA (589)t US.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED OMB NO.3150010O EXPIRES: O/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUESTI 50/)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F430), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION.

PROJECT (315041(H), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1I DOCKET NUMBER l2)LER NUMBER (5)PAGE (3)YEAR g)SEQUENTIAL NUMBER REVISION NUM854 R.E.Ginna Nuclear Power Plant TEXT///II>>>><<>>cob JoqokaL Uoo d/I/ooo/HRC FeIIR 3SSAB/(17) o s o o o 2 4 4 9 2 0 0 5 0 0 02 o" 0 9 PRE-EVENT PLANT CONDITIONS The plant was in the Cold/Refueling Shutdown condition for the Annual Refueling and Maintenance Outage.Reactor Coolant System (RCS)was depressurized and RCS temperature was approximately 65 F.Steam Generator (S/G)Eddy Current Inspection was'in progress.DESCRIPTION OR EVENT A.DATES AND APPROXIMATE TIMES OR MAZOR OCCURRENCES:

0 April 20, 1992, 1200 EDST: Event Date and Time 0 April 20, 1992, 1200 EDST: Discovery Date and Time 0 April 21, 1992, 1330 EDST: Oral Notification made to the NRC Office of Nuclear Reactor Regulation (NRR)..0 April 26, 1992, 1742 EDST: repairs completed.

Steam Generator 0 May 5, 1992: Follow-up written report sent to NRC Office of NRR.B.EVENT During the 1992 Annual Refueling and Maintenance Outage, an Eddy Current Examination was performed in both the"A" and"B" Westinghouse Series 44 Design Recirculating Steam Generators.

The purpose of the Eddy Current Examination was to assess any corrosion or mechanical damage that may have occurred during the cycle since the 1991 examination.

The examination was performed by personnel from Rochester Gas and Electric (RG&E)and Allen Nuclear Associates, Inc.(ANA).All personnel were trained and qualified in the Eddy Current Examination method and have been certified to a minimum of Level I for data acquisition and Level II for data analysis.NRC Form 355A (609)

I NRC FORM 388A (IS$9)US.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT ILER)TEXT CONTINUATION t APPROVED OMB NO.3)600104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS.INFORMATION COLLECTION REQUEST: 503)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P4)30).U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31504)104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (6)PAGE (3)R.E.Ginna Nuclear Power Plant TEXT (ff more Soeoe le rfo/reer/, Iree/frfooo/HRC

%%drrrr 36543/(12) 0 s 0 0 o 2 4 4 YEAR$g 9 2-SEDUENTIAL NUMBER 005@>REVISION.x: NUM ER-0 0 0 3 cF 09 The initial Eddy Current Examination of the"AE(and"B" Steam Generators was performed" utilizing the Zetec 3-Coil Motorized Rotating Pancake Coil (MRPC)probe and the Zetec MIZ-18 Digital Data Acquisition System.The'frequencies selected were 400, 300, 100, and 25 KHZ.Additional Eddy Current Examinations of the"A"'nd"B" Steam Generators were performed utilizing the.standard 0.740" or 0.720" O.D.Bobbin Coil Probe.The frequencies selected were 400, 200, 100 and 25 KHZ.The Inlet or Hot Leg Examination Program Plan included the examination of 100%of each open unsleeved steam generator tube.from'the tube end to the top of the tube sheet with MRPC.Twenty percent of the tubes were selected and examined for their full length (20%random sample as recommended in the Electric Power Research Institute (EPRI)guidelines) with a bobbin coil.In addition, 204 of.each type of sleeve was examined and the remainder (unsleeved portion)of the tube was examined full length.All Row 1 and Row 2 U-bend regions selected as part of the 204 random sample were examined with the MRPC between the g6 Tube Support Plate Hot Side (TSPH)and the g6 Tube Support Plate Cold Side (TSPC)from the Cold Leg Side.Results of the above inspections indicated that 244 tubes in the"A" Steam Generator (i.e.226-new repairs, plus 16 previously plugged tubes, plus 2 tubes stabilized for Anti-Vibration Bar (AVB)concerns)and 218 tubes in the"B" Steam Generator (i.e.183 new repairs, plus 3 B&W explosive plugs, plus 30 previously plugged tubes, plus 2 tubes stabilized for AVB concerns)required action.Corrective actions were therefore taken for 242 tubes in the"A" S/G, and for 216 tubes in the"B" S/G.Preventive actions (for AVB concerns)were taken for 2 tubes in each S/G.NRC Form 368A (689)

NRC FORM 366A (669)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LERI TEXT CONTINUATION e APPAOVED 0MB NO.3)500)OE E XPIR E 5 I 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST.'00 HRS.FORWARD COMMENTS AEGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F430), U.S.NUCLEAR AEGULATOAY COMMISSION, WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3)500104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER FSI SEOVENTIAL NVM ER@r REVISION NVM ER PAGE (3)R.E.Ginna Nuclear Power Plant TEXT///mom EPEEE/E/PEVked, IIEP J/(/BRE/NRC

%%dnR 35663)((7)0 6 0 0 0 2 4 4 9 2 0 0 5 00 04 QF 0 9 On April 20, 1992 at approximately 1200 EDST, with the RCS depressurized and temperature at approximately 65 F, final review of the 1992 S/G Inspection Eddy Current results was completed.

Results of this review indicated that more than 10 percent of the total tubes inspected are degraded (i.e.imperfections greater than 20 percent of the nominal wall thickness) and more than one percent of the total tubes inspected are degraded (i.e.imperfections greater than the repair limit)..Because of the above, the results of the inspection are considered a reportable event pursuant to 10 CFR 50.73 per Appendix B-of the Ginna Station Quality Assurance Manual.On April 21, 1992 at approximately 1330 EDST, oral notification was made to the NRC Office of NRR pursuant to Appendix B of the Ginna,Station Quality Assurance Manual.On May 5, 1992 a follow-up written report of the Steam Generators Inspection and Repairs was sent to the NRC pursuant to'Appendix B of the Ginna Station Quality Assurance Manual.C.r INOPERABLE STRUCTURES COMPONENTS, OR SYSTEMS THAT CONTRIBUTED TO THE EVENT: D.None.OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED None.E.METHOD OP DISCOVERY:

The event was apparent after the final review of the"A" and"B" Steam Generators Eddy Current Examination results.NRC PARR 366A (669)

NRC FORM 366A (889)(LS.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION t APPROVED OMB NO.3(500)04 EXPIRES: 4(30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUESTI 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P430), U.S.NUCLEAR REGULATORY COMMISSION.

WASHINGTON.

DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150010E), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (6)PAGE (3)YEAR oyer SEQUENTIAL NUMSER REVISION NUMBER R.EP Ginna Nuclear Power Plant TEXT (I/more epece Je eePJPPIL Iree aB(ro'encl HRC Fcnn 36848)()7)0 6 0 0 0 2 4 4 9 2-0 0 5 0 005 QF0 9 P.OPERATOR ACTION: Control Room operators completed the notifications and evaluations required by the A-25.1 (Ginna Station Event Report), submitted for the event by the S/G supervision.

G.SAFETY SYSTEM RESPONSES.

None.III CAUSE OP EVENT A.IMMEDIATE CAUSE: The immediate cause of the event was that the"ALI and"BLI Steam Generator tube degradation was in excess of the Ginna Station Quality Assurance Manual Reportable Limits.B.ROOT CAUSE: The results of the examination indicate that Intergranular Attack (IGA)and Intergranular Stress Corrosion Cracking (IGSCC)continue to be active within the tubesheet crevice region on the inlet side of each steam generator.

As in the past, IGA/SCC is much more prevalent in the"B" Steam Generator with 118 new crevice indications reported.In the"A" Steam Generator, 34 new crevice indications were reported.The majority of the inlet tubesheet crevice corrosion indications are IGA/SCC of the Mill Annealed Inconel 600 tube material.This form of corrosion's believed to be the result of an alkaline environment forming in the tubesheet crevices.This environment has developed over the years as deposits and active species such as sodium and phosphate, have reacted, changing a neutral or inhibited crevice into the aggressive environment that presently exists.NRC Form 366A (6J)9)

NRC FORM 386A (BJIS)i (LS.NUCLEAR AEGULATORY COMMISSION LICENSEE EVENT REPORT ILER)TEXT CONTINUATION t APPROVED OMB NO.31500104 EXPIRES'/30/$

2 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFOAMATION COLLECTION REQUEST: 500 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (PJ)30), US.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1'HE PAPERWORK REDUCTION PROJECT (3)500104), OFF ICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (8)YEAR PR SEQUENTIAL Sa~r..6%NUM ER%o REVISION NVMSER PAGE (3)R.E.Ginna Nuclear Power Plant TEXT////Sore 8/reoe/e/Fr/rer/, Iree///0'ooe/HRC ForIII 38//AS/(IT) 24 492 00 5 000 OF Along with IGA/SCC in'the crevices, there appears to have been a slight increase in"Primary Water Stress Corrosion Cracking (PWSCC)at the roll transition during the last operating cycle.This mechanism was first addressed in 1989 and this year there were 63 roll transition PWSCC indications in"B" Steam Generator and 189 roll transition (PWSCC)indications in"A" Steam Generator.

These numbers include tubes that may have PWSCC in combination with IGA and SCC in the crevice.XV ANALYSIS OP EVERT This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report item (other)and the Ginna Station Quality Assurance Manual Appendix B which requires that,."If the number of tubes in a generator falling into categories (a)or (b)exceeds the criteria, then results of the inspection shall be considered a reportable event pursuant to 10 CFR 50.73." The tube degradation in the"AL)and"B" Steam Generators exceeded the criterion of (a)which states,"more than 10 percent of the total tubes inspected are degraded (imperfections ,greater than 20 percent of the nominal wall thickness)", and the criterion of (b)which states,"more than 1 percent of the total tubes inspected are degraded (imperfections greater than the repair limit).This repair limit is defined as,"Steam Generator tubes that have imperfections greater than 40 percent through wall, as indicated by Eddy Current, shall be repaired by plugging or sleeving." NRC Form 386A (86$)

.J NRC FOAM 366A (669)US.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION e APPROVED OMB NO.31500)04 EXPIRES: 6/30/92 ESTIMATED BURDEN PE4 RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50A)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE 4ECORDS AND 4EPOATS MANAGEMENT BRANCH (F430).U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK 4EDUCTION PROJECT (31500104).

OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER (6)SEOUENTIAL gP NUMBER REVISION NUMBER PAGE (3)R.E..Ginna Nuclear Power Plant TEXT/I/more<<>>ce/e nrFI/rer/Bee a///Noor>>l NRC Forrrl J(ISAB/((2) 0 5 0 0 0 24-4 9 2 0 0 5 00 07 OF 0 9 An assessment was performed considering the safety.consequences and implications of this event with the following results and conclusions:

There were no safety consequences or implications resulting from the Steam Generator tube degradation in excess of the Quality Assurance Manual Reportable Limits because:.o The.degraded tubes were identified and repaired prior to any significant leakage or Steam Generator tube rupture occurring.

0 Even assuming a complete severance of a Steam Generator tube at full power, as stated in the R.E.Ginna Nuclear Power Plant Updated Final Safety Analysis Report (Ginna/UFSAR) section 15.6.3, (Steam Generator Tube Rupture), the sequence of recovery actions ensures early termination.of primary to secondary leakage with or without offsite power available thus limiting offsite radiation doses to within the guidelines of 10 CFR 100.~Based on the above, it can be concluded that the public's health and safety was assured at all times.V.CORRECTIVE ACTION A.ACTION TAKEN TO RETURN AFFECTED SYSTEMS.TO PRE-EVENT NORMAL STATUS: o'f the 244 tubes in the"A" Steam Generator, 36 tubes were repaired using a Combustion Engineering 27" welded sleeve in the Hot Leg, plus 194 tubes were repaired using a Babcock and Wilcox explosively welded tubesheet sleeve in the Hot Leg and all of the above tubes will remain in service.The remaining 14 tubes=were removed from service by plugging both the Hot and Cold Leg tube ends.A total of 185 tubes in the"A" Steam Generator are currently plugged and 555 tubes are sleeved.NRC Form 366A (689)

I NRC FORM 3SSA (W)US.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT ILER)TEXT CONTINUATION l APPROVEOOMB NO.3I50010O i EXPIRES: O/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (PJ)30), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31504104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACII.ITY NAME (1I DOCKET NUMBER (2)YEAR LER NUMBER (Sl SEOVENTIAL NVM ER REVISION NUMBER PAGE (3)R.E.Ginna Nuclear Power Plant TEXT/I/more e/>>ce/or/q/rer/

Iree<<IChE/<<>>/NRC%%de 3SBAB/(IT)0 S 0 0 0 2 4 4 9 2 0 0 5 000 OF 0 Of the 218 tubes in the"B" Steam Generator, 186 tubes were repaired using a Combustion Engineering 27" welded sleeve in the Hot Leg, plus 9 tubes were repaired using a Combustion Engineering 30" welded sleeve in the Hot Leg and all of the above tubes will remain in service.The remaining 23 tubes were removed from=service by plugging both the Hot and Cold Leg tube ends.A total of 313 tubes.in the"BL(Steam Generator are currently plugged and 1134 tubes are sleeved.All the above repairs on the"A" and"BL(Steam Generators were completed on April 26, 1992 at approximately 1742 EDST.B.ACTION TAKEN OR PLANNED TO PRVTENT RECURRENCE:-The occurrence/presence of IGA, SCC,.and PWSCC is a common PWR Steam Generator problem.Utilities with susceptible tubing and partially rolled crevices must deal with this recurring attack on Steam Generator tubing.R.E.Ginna Nuclear Power Plant will continue careful monitoring of both primary RCS and'econdary side water chemistry parameters.

These water chemistry parameters will continue to be evaluated against accepted industry guidelines in order to minimize harmful primary and/or secondary side environments.

Degraded Steam Generator tubes shall be sleeved or plugged in accordance with the Inservice Inspection Program and Accepted Industry Repair methods.ADDITIONAL INFORMATION A.FAILED COMPONENTS:

The degraded components are: Inconel Grade 600 tubes having an outside diameter of 0.875 inches and a.nominal wall thickness of 0.050 inches.These tubes were manufactured by Huntington Alloy Company.'NR C Form 3SSA (589)

NRC FORM 388A (669)US.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED OMB NO.3)504104 E XP I R ES: E/30/IQ ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 505)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F830), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1)IE PAPERWORK REDUCTION PROJECT (3150010E).

OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER (6)S~SEQVENTIAL NVM@ER j>gj REVISION:i.'/NVMSER PAGE (3)R.E.Ginna Nuclear Power Plant TEXT///IIRvo EPooo JI ISA(RR/, vJo//I/ooo/NRC Form 36643/(17)0 6 0 0 0 2 4 4 9 0 0 5-0 0 0 9"0 9 B.PREVIOUS LERs OM SIMILAR EVENTS: A similar LER event historical search was conducted with the.following results: The crevice indications are similar to those reported in A0-74-02, AO-75-07, R0-75-013, and LERs76-008, 77-008,78-003, 79-006, 79 022/80 003/81 009/82 003/82 022/83 013/89=-001,90-004, and 91-005.C SPECIAL COMMEHTS: For a more indepth report, refer to the"1992 Steam Generator Eddy Current Inspection" Summary Examination Report sent to the NRC May 5, 1992.NRC Form 368A (BJ)9)

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