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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
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Category:LER)
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Category:TEXT-SAFETY REPORT
MONTHYEARML17265A7601999-10-0505 October 1999
Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis
ML17265A7621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Re Ginna Npp.With
ML17265A7531999-09-23023 September 1999
Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped
05000244/LER-1999-011, :on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With1999-09-22022 September 1999
- on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With
ML17265A7471999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With
05000244/LER-1999-004, :on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed1999-08-24024 August 1999
- on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed
ML17265A7381999-08-16016 August 1999
SE Approving Licensee Requests for Relief 37,38,39,40 & 41 for Re Ginna Nuclear Power Plant for Third & Fourth 10-year Inservice Insp Interval
ML17265A7341999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Re Ginna Npp.With
ML17265A7291999-07-29029 July 1999
Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent
05000244/LER-1999-007, :on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians1999-07-23023 July 1999
- on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians
ML17265A7131999-07-22022 July 1999
Special Rept:On 990407,radiation Monitor RM-14A Was Declared Inoperable.Caused by Failed Communication Link from TSC to Plant Process Computer Sys.Communication Link Was re-established & RM-14A Was Declaed Operable on 990521
05000244/LER-1998-003, :on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored1999-07-22022 July 1999
- on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored
ML17265A7121999-07-19019 July 1999
Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding
ML17265A7211999-07-19019 July 1999
ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp
ML17265A7031999-07-19019 July 1999
LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With
05000244/LER-1999-010, :on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With1999-07-15015 July 1999
- on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With
ML17265A7661999-06-30030 June 1999
1999 Rept of Facility Changes,Tests & Experiments Conducted Without Prior NRC Approval for Jan 1998 Through June 1999, Per 10CFR50.59.With
ML17265A7011999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Re Ginna Npp.With
05000244/LER-1999-001, :on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With1999-06-21021 June 1999
- on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With
ML17265A6831999-06-17017 June 1999
Safety Evaluation Re Response to Supplement 1 to GL 87-02 for Ginna Nuclear Power Plant on USI A-46
ML17265A6761999-06-16016 June 1999
Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis
05000244/LER-1999-009, :on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With1999-06-0202 June 1999
- on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With
ML17265A6681999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With
05000244/LER-1999-008, :on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With1999-05-27027 May 1999
- on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With
ML17265A6651999-05-27027 May 1999
Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001
05000244/LER-1999-006, :on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With1999-05-21021 May 1999
- on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With
ML17265A6591999-05-17017 May 1999
Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested
05000244/LER-1999-005, :on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With1999-05-13013 May 1999
- on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With
ML17265A6381999-05-0707 May 1999
Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG
ML17265A6391999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Re Ginna Nuclear Power Plant.With
ML17265A7251999-04-23023 April 1999
Rev 1 to Rept of Development of Rg&E Seismic Safe SD Equipment & Relay Review Lists for USI A-46
ML17265A6361999-04-23023 April 1999
Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001
ML17265A6341999-04-23023 April 1999
Safety Evaluation Supporting Amend 74 to License DPR-18
ML17265A6301999-04-18018 April 1999
Rev 1 to Cycle 28 COLR for Re Ginna Npp
ML17265A6251999-04-15015 April 1999
Special Rept:On 990309,halon Systems Were Removed from Svc & Fire Door F502 Was Blocked Open.Caused by Mods Being Made to CR Emergency Air Treatment Sys.Continuous Fire Watch Was Established with Backup Fire Suppression Equipment
ML17265A6551999-04-0909 April 1999
Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open
ML17265A6221999-04-0808 April 1999
Safety Evaluation Approving Rg&E Proposed Alternative to Exam Requirement of ASME Code,Section Xi,For Circumferential Shell Welds of RPV for Third 10-year Insp Interval
ML17265A6181999-04-0606 April 1999
Safety Evaluation Concluding Proposed Rev 26 to Rg&E QAP for Station Operation Incorporating Reductions in Stated Commitments Will Continue to Comply with QA Criteria of App B to 10CFR50 & Therefore,Acceptable
ML17265A6241999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Ginna Station.With
ML17265A6291999-03-31031 March 1999
Rev 0 to Cycle 28 COLR for Re Ginna Npp
05000244/LER-1999-003, :on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With1999-03-31031 March 1999
- on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With
05000244/LER-1999-002, :on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With1999-03-29029 March 1999
- on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With
ML17265A5941999-03-0808 March 1999
Safety Evaluation Accepting Request for Relief 34 from ASME Code Section XI Requirements for Plant Third 10-yr ISI Interval
ML17265A5621999-03-0303 March 1999
Safety Evaluation Supporting Amend 73 to License DPR-18
ML17265A5661999-03-0101 March 1999
Rev 26 to QA Program for Station Operation
ML17265A5581999-03-0101 March 1999
Rev 1 to Gnpp Internal Flooding Probabilistic Safety Assessment Final Rept
ML17265A5961999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With
ML17265A5541999-02-25025 February 1999
Safety Evaluation Approving Request to Apply leak-before- Break Status to Portions of Plant Residual Heat Removal Sys Piping
ML17265A5341999-02-0404 February 1999
Safety Evaluation Granting Request Relief 36 from ASME Code Section XI Requirements for Plant Third 10-yr ISI Interval
ML17265A5371999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With
1999-09-30
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REGUL~RYINFORMATIONDISTRISUTISYSTEM(RIDE)ACCESSIONNBR:8906280101DOC.DATE:89/06/20NOTARIZED:NOFACIL:50-244'RooertEmmetGinnaNuclearPlant,Unit1,Rocheste"GAUTH.NAMAUTHORAFFILZATZONSPECTOR,S.M.RochesterGas&ElectricCorp.RECIP.NAMERECIPIENTAFFILIATIONDocumentConr,rolBranch(DocumentControlDesk)SUBJECT-:RO:on890619,B&Csaetvinjectionpumprecirculationvalvesdiscoveredlockedfullopenatapprox99%power.DISTRlBUTZONCODE:E22DCOPIESRECEIVED:LTRtENCLtSIZE:TITLE:50.73/50.9LicenseeEventReport(LER)-,IncidentRpt,etc.NOTES:LicenseExpdate'naccordance~rith10CFR2,2.109(9/19/72).DOCKET05000244fi05000244I5RECIPIENTZDCODE/NAME.PD1-3LAJOHNSON,AINTERNAL:ACRSMZCHELSONACRSWYLIEAEOD/DSP/TPABDEDRONRR/DEST/ADE8HNRR/DEST/CEB8HNRR/DEST/ICSB7NRR/DEST/MTB9HNRR/DEST/RSB8ENRR/DLPQ/HFB10NRR/DOEA/EABllNUDOCS-ABSRACRES/DSIR/EZBRGNl"ILE01EXTERNAL:EG&GWZLLIAMSFSLSTLOBBYHARDNRCPDRNSICMURPHY,G.ACOPIESLTTRENCL1-1.1111111111111111111111114411111RECIPIENTZDCODE/NAMEPD1-3PDACRSMOELLERAEOD/DOAAEOD/ROAB/DSPZRM/DCTS/DABNRR/DEST/ADS7ENRR/DEST/ESB8DNRR/DEST/MEB9HNRR/DEST/PSB8DNRR/DEST/SGB8DNRR/DLPQ/PEB10NRREPRPB'0BEGF~~r02RES/DSR/PRABFORDBLDGHOY,ALPDRNSZCMSYSGCOPIESLTTRENCL12121011111211RIDhNOZEK)ALL'KIDS"RZCIPIENIS:PLEASEHELPUS'IOREDUCERESTE.'DNI'ACr'IHEDOCUMERI'ONIROLDESK,RXNPl-37(EXT.20079)ToEIJKQRTEVXKNAMEPRESDIPHGBVPIGNLISTSFORDOCQQZZSKXJDOHFTNEEDtTOTALNUMBEROFCOPIESREQUZR=D:LTTR43NCL42
'l<tFII(~ROCHESTERGASANDELECTRICCORPORATION~89EASTAVENUE,ROCHESTER,N.Y.14649-0001TE'+Obfiiciconc"~<5"G.2700June20,1989U.S.Nuclear'egulatoryCommissionDocumentControlDeskWashington,DC20555
Subject:
Follow-upSummaryofClose-outofJune19,1989UnusualEventR.E.GinnaNuclearPowerPlantDocketNo.50-244InaccordancewithNUREG0654,FEMA-Rep-l,Rev.1reportingrequirementswhichrequiresawrittensummaryof"close-out.orclassreductionconditions",theattachedclose-.outsummaryfortheJune19,1989UnusualEventisherebysubmitted.CThiseventhasinno'ayaffectedthepublic'shealthandsafety.Verytrulyyours,xc:U.S.NuclearRegulatoryCommissionRegionI475AllendaleRoadKingofPrussia,PA19406GinnaUSNRCResidentInspectorR.C.MecredyD.W.BurkeStanlyM.SpectorPlantManagerGinnaStationaeoszsoioi~goooao4CyPgr20PDRADOCV0eguS
AttachmenttoClose-outofJune191989UnusualEventOnJune19,1989atapproximately1440EDSTwiththereactoratapproximately99%power,itwasdiscoveredthatthe"B"and"C"safetyinjectionpumprecirculationvalves-werelockedfullopenratherthanthrottledto50gpmasrequired.The"B"and"C"safetyinjectionpumpswereimmediatelydeclaredinoperableandapowerreductionwascommencedtocomplywiththeplantTechnicalSpecification.Atapproximately1515EDST,theoperationsshiftsupervisordeclaredanUnusualEventinaccordancewithSC-100,"GinnaStationEventEvaluationandClassification>>,EAL:LossofEngineeredSafetyFeatures;ExceedingaLimitingConditionfor.operationsonasafetysystemrequiringaplantshutdown.TechSpecSection3.3EmergencyCoreCoolingSystem.AlloffsitenotificationsweremadeperSC-601,"UnusualEventNotifications".Atapproximately1615EDST;subsequenttothesatisfactorytestingandthrottlingofthe"B"and"C"safetyinjectionpumpsrecirculationvalvesto50gpm,the"B"and"C"safetyinjectionpumpsweredeclaredoperableandtheloadreductionstopped..Withthe"B"and"C"safetyinjectionpumpsdeclaredoperableandtheloadreductionstopped,theoperationsshiftsupervisor,withapprovalandconcurrencefromthePlantManagerGinnaStation,theSuperintendentGinnaProduction,theassistantoperationssupervisor,PORCandthedutyengineer,declaredtheUnusualEventterminated't1626EDST,June19,1989inaccordancewithSC-110,"GinnaStationEventEvaluationforReducingtheClassification".AlloffsitenotificationsweremadeoftheUnusualEventtermina-tionandtheplantwassubsequentlyreturnedtoapproximatelyfullpower.
