ML20084E610
From kanterella
| ML20084E610 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/11/1971 |
| From: | Green G ROCHESTER GAS & ELECTRIC CORP. |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8304150161 | |
| Download: ML20084E610 (3) | |
Similar Documents at Ginna | |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20207R7521987-03-0909 March 1987
[Table view]Ro:On 870207,MSIV Failed to Close During Plant Shutdown. Caused by Binding of Valve Disc on Partially Removed Valve Stop.Disc Stop Matl Removed & Valve Tested.Sketch of Valve & Stop Encl ML20207C8141986-12-22022 December 1986 Ro:On 861023 & 1128,RCS High Pressure Transient Occurred. Caused by Lifted Pressurizer PORV Due to Internal Event.More Specific Info Re Events Can Be Found in LERs 86-008 & 86-011 ML20215D6231986-12-11011 December 1986 Followup Ro:On 861128,operator Inadvertently Closed Main Steam Line Isolation Valves 3516 & 3517 Instead of Containment Vessel Depressurization Valves,Causing Pressurizer High Pressure Reactor Trip ML20204F9221986-07-29029 July 1986 Ro:On 860729,manual Reactor Trip Initiated When Large Quantity of Steam Found Rising Over Turbine Bay Area.Caused by Leak from Moisture Separator Reheater Drain Line 2A to High Pressure Feedwater Heater 5B.Drain Lines Repaired ML20138Q8751985-11-0707 November 1985 Followup Summary:On 851106,alarm & Deluge of Fire Sys S-05 Received in Control Room.Caused by Spurious Signal Spike on Second Alarm Module.Investigation on Failure Mode of Fire Sys Continuing.Cable Tunnel Dried Out ML20128L9181985-07-12012 July 1985 Ro:On 850701,containment Vessel Sump Pump Actuation Interval Decreased Significantly from Normal.Caused by Svc Water Leak.Fan Cooler Inspected & Repaired ML20083P8141984-03-20020 March 1984 Ro:On 840307,during Drainage of RCS to Holdup Tanks,Rhr Containment Sump B Suction Valves MOV 851 a & B Opened Before Valve 850 a Closed,Causing Drainage of RCS Into Sump B ML20087P7331984-02-21021 February 1984 Ro:Providing Sequence Summary of Closeout or Class Reduction Condition for Unusual Event on 840219 Re out-of-svc Accumulators.Accumulators Returned to Svc & Declared Operable ML20087P9711984-01-27027 January 1984 Ro:On 831228,turbine Driven Auxiliary Feedwater Pump Steam Stop Valve Found in Tripped Position,Although Control Room Indication Indicated Valve Open.Caused by Contractor Stepping on Valve Trip Mechanism ML20077N5901983-08-31031 August 1983 Ro:On 830303,diesel Fuel Oil for Fire Pump Found Below Viscosity Limit.Caused by Delays in Transporting Sample to Lab for Analysis.Procedures to Expedite Resampling & Analysis Being Reviewed ML20072N5891983-07-0808 July 1983 Ro:On 830609,during Safety Injection Functional Test,When Safety Injection Signal Initiated by Simulating High Containment Pressure,Charging Pump 1C Did Not Trip, Causing Operation of Reactor Overpressure Protection Sys ML20072U5941983-03-31031 March 1983 Ro:On 830331,health Physics Technician Fell 40 Ft to Floor of Reactor Cavity.Individual Removed from Area & Taken to Hosp to Be Treated for Serious Injuries & Decontaminated ML20083P1021983-01-21021 January 1983 RO 83-006/01:on 830120,alarm Received in Control Room Indicating Low Screenhouse Water Level of 20 Ft,Rendering Fire Suppression Water Sys Inoperable.Addl Info Will Be Presented in 14-day Written Rept 05000244/LER-1982-003, RO 82-007/01T:on 820125,unit Experienced Event Described in LER 82-003 Leading to RCS Cooldown Rate Greater than 100 F/H.Further Info Will Be Submitted w/14-day Written Rept1982-02-24024 February 1982 RO 82-007/01T:on 820125,unit Experienced Event Described in LER 82-003 Leading to RCS Cooldown Rate Greater than 100 F/H.Further Info Will Be Submitted w/14-day Written Rept ML20084D9411977-07-15015 July 1977 Supplemental RO-77-010:four Addl Supports (SW-69,73,78 & 83) Found W/Stresses Under DBE Conditions in Excess of Allowable Values.Corrective Actions Underway ML20084D9381977-07-14014 July 1977 RO-77-010:on 770713,design Error Found in Redundant Svc Water Discharge Line Support.Overstress Condition Could Exist W/Line Not Yet Charged or in Svc.Line in Hold Condition ML20084B8551977-02-10010 February 1977 Supplemental RO 76-24:on 761008,leaks Found in 8-inch Schedule 10 Boric Acid Piping.Cause of Cracks Probably Due to Stress Corrosion Attack ML20084C1511976-12-21021 December 1976 Supplemental RO-76-21:on 760819,two Control Rods Dropped. Westinghouse Recommendations for Cause Later Determined Not to Be Actual Cause.New Recommendations to Be Carried Out During Next Refueling Outage ML20084C3151976-06-21021 June 1976 Supplemental RO 76-10:on 760228,excessive Leakage Observed from Valve Inside Purge Supply Control Valve.Results of Vendor Insp of Assembly Submitted ML20084C2901976-05-25025 May 1976 Supplemental RO-76-12:on 760331,during Testing,Excessive Leakage Found in Containment Personnel Airlock Handwheel Shaft Seal.Corrective Action Include Placing Seal on Packing Gland Nuts to Prevent Rotation W/Shaft ML20084A0971976-05-12012 May 1976 Supplemental RO 76-07 Re Train a Containment Isolation & Ventilation Isolation Failure to Latch.Fourteen Relays Checked for Clearance Between Electromagnet Pole Face & Raised Section of Armature ML20083R8881976-03-0909 March 1976 RO 76-11:on 760308,control Room Charcoal Filter Damper Discovered Improperly Positioned.Trouble Card Issued & Work Initiated to Correct Problem ML20084A0121976-02-23023 February 1976 RO 76-08:on 760227,39 Steam Generator Tubes Explosively Plugged in Steam Generator a & 2 in Steam Generator B.Tubes Exhibited Tube Wall Deterioration in Excess of 40% ML20084A1351976-02-0808 February 1976 RO 76-05:on 760208,excessive Leakage Observed Through Several Containment Penetrations.Cause Not Stated.Repairs to Valves Underway ML20084A9721974-11-0707 November 1974 Ro:On 741008,Westinghouse Informed Util That Safety Injection Sys Delivery Curve Employed for Steam Line Break Accident Analysis Inconsistent W/Analyses Used for Recent Loca.Util to Maintain Shutdown Margin of at Least 2.45% ML20084E2251974-06-0707 June 1974 Ro:On 740509,during Surveillence Procedure PT 16,little Flow Reduction Occurred Following Opening of Motor Driven Auxiliary Feedwater Pump a & B Discharge Valve.Cause Unapparent.Frequency of Surveillance Test Increased ML20084H0961974-02-25025 February 1974 RO: Overexposure of Individual to Radiation Occurred During First Quarter of 1974.Correction to Reporting Similar Occurrence Encl ML20084H0991974-02-20020 February 1974 RO: Individuals Overexposed to Radiation During First Quarter 1974.Investigation Underway ML20084E3341973-06-21021 June 1973 Ro:On 730523,thirty Minutes After Boric Acid Transfer Pumps Started Recirculation,Control Rods Noted as Stepping Out. Caused by Malfunction of Blend Sys Valve FCV-110B.Repair Instituted & Completed on 730524 ML20084E4361973-06-0808 June 1973 Ro:On 730529,during Performance of Monthly Surveillance Undervoltage & Underfrequency Protection,Device Armature of Knife Switches for Solenoid Coil Discovered Not Dropping to Assume Deenergized Condition.Caused by Scale Accumulation ML20084E3651973-06-0707 June 1973 Ro:On 730606,high Bistable Setting Approx 2.1% Higher than Specified Value Set Forth in Plant Procedure.Caused by Personnel Error in Transposing Desired Calculated Current Level from Work Sheet.Setting to Correspond W/Steam Flow ML20084E3541973-05-31031 May 1973 Ro:On 730502,Bank D Control Rod Sys Observed Stepping Out of Core.Caused by Loose Solder Joint in QM-401.Automatic Rod Control Immediately Switched to Manual W/No Indication of Any Change in Reactor Power.Averaging Unit Repaired ML20084E4561973-05-30030 May 1973 Ro:On 730529,upon Opening Knife for Solenoid Coil of Primary Undervoltage Device 273/IIA,device Armature Discovered Not Dropping Down to Assume Deenergized Condition.Caused by Scale Accumulation on Device.Investigation Continuing ML20084E6161972-12-28028 December 1972 RO:720831 & 0901 Unplanned Release of Radioactive Passes Occurred During Removal of Spent Resins from Spent Resin Tanks.Cause Not Stated.Written Procedure for Handling Resin Revised & Precaution Included Re Vent Header Pressure ML20084E9641972-06-30030 June 1972 Ro:On 720623,w/reactor at 5% Thermal Power,Control Board Received Alarms of Rod Bottom Rod Stop & Rod Control Urgent Failure Rod Stop.Caused by Water from Swagelok Fitting on Tubing Dropping on Rod Control Cabinets.Fitting Repaired ML20084E9731972-05-31031 May 1972 Ro:On 720503,upon Entering Steam Generator & Starting Grit Blasting Equipment,Workman Discovered Face Mask Not Functioning & Exited Area.Caused by Failure to Tighten Threaded Connection of Air Hose to Mask.Exams Performed ML20084E4681972-04-28028 April 1972 Ro:On 720420,while Plant Being Cooled Down in Preparation for Refueling,Release Rate of Airborne I-131 from Plant Vent Exceeded Tech Spec Limits.Cause Unknown.Charcoal Filters from Plant Vent Iodine Monitor Being Replaced ML20084E6591972-03-30030 March 1972 Ro:On 720320,while Reactor in Hot Shutdown,Msivs Tested for Closure & MSIV-1B Valve Found Closed Only Half Way.Cause Unknown.Valve Mfg Contacted for Recommendations to Prevent Recurrence ML20084F0801972-02-0707 February 1972 Ro:On 720131,while Conducting Monthly Surveillance Test, Underfrequency Relay on 4160-kV Bus 11B Failed to Transmit Signal to Logic Racks.Caused by Faulty Capacitor.Spare Relay Installed & Tested Satisfactorily ML20084F1211971-12-14014 December 1971 Ro:On 711205,safety Injection Pump Motor C Tripped Automatically When Nearly Up to Speed.Caused by Motor Tripping Out on Starting Current Due to Leakage in Time Delay Dashpot.Replacement Overcurrent Device Installed ML20084E5671971-07-0909 July 1971 Ro:On 710630,MSIV Failed to Close on Signal.Solenoid Operators on MSIV 1A Removed & Inspected and All Parts ML20084E6101971-06-11011 June 1971 Ro:Between 710601-05,calculations Indicated Gaseous Effluent Release Limits Exceeded.Caused by Gasket Leak on Vol Control Tank Pressure Control Regulator Valve PCV141.Continuous Recording Iodine Monitor Installed on Stack Vent ML20084E6371971-04-29029 April 1971 Ro:On 710422,during Diesel Generator Load & Safeguard Sequence Test,Valves 826 A,B,C & D Failed to Open.Caused by Momentary Loss of Voltage on 480-volt Safeguard Busses.Power Supply Transfer Recommended ML20084E8361970-12-21021 December 1970 Ro:During 700930-1015 Shutdown,Broken Stud Found on One Support for Primary Sys Component.W/O Stated Encl ML20084E8561970-10-14014 October 1970 Ro:On 701004,core Deluge Valve 852B Malfunctioned.Caused by Seizure of Stem Nut to Valve Stem.New Stem Nut Installed ML20084E5501970-07-15015 July 1970 Ro:On 700706,boron Dilution Performed W/Reactor Critical & No Reactor Coolant Pump on RHR Pump in Operation.Orders Issued That Maint Work Performed Only W/Authorized Procedures Available ML20084E7211970-05-22022 May 1970 Ro:On 700514,during Reactor Cooldown Procedure,Msiv 1B Failed to Close.Caused by Malfunction of Valve Mechanism. Packing Gland Loosened ML20084E7821970-03-13013 March 1970 Ro:On 700306,during Surveillance Test,Excessive Air Leakage Around Lower Handwheel Shafts That Penetrate to Outside Handwheels Noted.Ring of Packing to Lower Handwheel Shaft Added ML20084E7771970-02-27027 February 1970 Ro:On 700130,motor Operated Svc Water Valves 4013,4300 & 4028 on Emergency Suction Line to Auxiliary Feedwater Pumps Reported to Operate Improperly.Caused by Operating Personnel Misunderstanding ML20084E4161970-01-19019 January 1970 RO:700108,during Draining Required to Permit Replacement of Coolant Temp detectors,in-core Thermocouple Reading Indicated Temp Exceeded Tech Spec Limit.Caused by Failure to Monitor Temp by Alternate Means 1987-03-09 Category:TEXT-SAFETY REPORT MONTHYEARML17265A7601999-10-0505 October 1999
[Table view]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 991008 Ltr 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 ML17265A7541999-09-22022 September 1999 LER 99-011-00: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 990922 Ltr ML17265A7471999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 990909 Ltr ML17265A7431999-08-24024 August 1999 LER 99-004-01: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 ML17265A7341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Re Ginna Npp.With 990806 Ltr 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 ML17265A7181999-07-23023 July 1999 LER 99-007-01: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 ML17265A7081999-07-22022 July 1999 LER 98-003-02: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 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 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 990719 Ltr ML17265A7211999-07-19019 July 1999 ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp. ML17265A7021999-07-15015 July 1999 LER 99-010-00: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 990715 Ltr 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 991020 Ltr ML17265A7011999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Re Ginna Npp.With 990712 Ltr ML17265A6851999-06-21021 June 1999 LER 99-001-01: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 990621 Ltr 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 ML17265A6661999-06-0202 June 1999 LER 99-009-00: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 990602 Ltr ML17265A6681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 990608 Ltr 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 ML17309A6541999-05-27027 May 1999 LER 99-008-00: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 990527 Ltr ML17265A6631999-05-24024 May 1999 LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved ML17265A6601999-05-21021 May 1999 LER 99-006-00: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 990521 Ltr 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 ML17265A6441999-05-13013 May 1999 LER 99-005-00: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 990513 Ltr ML17265A6431999-05-12012 May 1999 LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed 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 990510 Ltr 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 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 ML17265A6291999-03-31031 March 1999 Rev 0 to Cycle 28 COLR for Re Ginna Npp. ML17265A6241999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ginna Station.With 990409 Ltr ML17265A6141999-03-31031 March 1999 LER 99-003-00: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 990331 Ltr ML17265A6131999-03-29029 March 1999 LER 99-002-00: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 990329 Ltr ML17265A6061999-03-24024 March 1999 LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp ML17265A5661999-03-0101 March 1999 Rev 26 to QA Program for Station Operation. ML17265A5961999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With 990310 Ltr ML17265A5371999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr ML17265A5951998-12-31031 December 1998 Rg&E 1998 Annual Rept. ML17265A5001998-12-21021 December 1998 Rev 26 to QA Program for Station Operation. ML17265A4951998-12-21021 December 1998 LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr ML17265A4931998-12-17017 December 1998 LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery ML17265A4761998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Re Ginna Nuclear Power Plant.With 981210 Ltr ML17265A4691998-11-25025 November 1998 LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR ML17265A4531998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Re Ginna Nuclear Power Plant.With 981110 Ltr ML17265A4271998-10-0505 October 1998 LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr ML17265A4291998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Re Ginna Nuclear Power Plant.With 981009 Ltr 1999-09-30 |
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