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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
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 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 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 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 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 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 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 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 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 ML17265A4151998-09-10010 September 1998 Part 21 Rept Re 980325 Discovery of Missing Tripper Bar Tabs During Troubleshooting of DB-75 Breaker Failure.Caused by Failure to Notify Technician of Revised Procedure to Reinstall Tabs.Inspected All DB-75 Breakers ML17265A4031998-08-12012 August 1998 Part 21 Rept Re W DB-75 Circuit Breakers W/Missing Tripper Bar Tabs.Caused by Intermittent Failure to Close in DB-75 B EDG Supply Circuit Breaker to Bus #16.Licensee Nuclear Engineering Personnel Are Performing Vendor Document Review ML20236J1051998-06-29029 June 1998 Part 21 30 Day Written Rept Re Refurbished DB-25 Circuit Breaker Returned W/Missing Pin in Operating Mechanism.Spare DB-25 Circuit Breaker Was Inspected,Tested & Installed to Restore B Service Water Pump to Service ML17265A3181998-06-0808 June 1998 Part 21 Rept Re Receipt of Refurbished DB-25 Circuit Breaker W/Missing Part from W Replacement Components Svcs on 980608. Spare DB-25 Circuit Breaker Was Inspected,Tested & Installed to Restore B Swp to Svc ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML17309A6241998-01-15015 January 1998 Deficiency Rept Re Failure of Shunt Trip Coil Plunger to Return to Deenergized Position Resulting in Breaker Tripper Bar Being Maintained in Trip Free Position,Preventing DB-75 Air Circuit Breaker from Closing.Failed Assembly Replaced ML17264B1401997-12-22022 December 1997 Part 21 Rept Re Binding Plunger of Assembly Shunt Trip Coil on 971114.Failed Shunt Trip Coil Was Replaced W/Spare from Stock ML17309A6211997-09-29029 September 1997 Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML17264A7301996-11-0606 November 1996 Part 21 Rept Re Defective 350 HP,1800 RPM,460 VAC,3 Phase, 5006P Frame,1.15 Sf,Vertical Hollow Shaft Motor Used as Service Water Pump motor.Safety-Relayed Cgiee Revised to Enhance Steps for Exam of Windings & Workmanship ML17264A7331996-10-10010 October 1996 Part 21 Rept Re Defect in 350 HP,1800 RPM,460 VAC,3 Phase, 500GP frame,1.15 Sf Vertical Hollow Shaft Motor for Use as Svc Water Pump Motor.Motor Removed,Disassembled,Inspected, Refurbished,Reinstalled & Satisfactorily Tested ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20115F2471996-07-0303 July 1996 Part 21 Rept Re Piping (Small Portion of Unmelted Matl Drawn Lengthwise Into Bar During Drawing Process) Defect That Existed in Bar as Received from Mill.Addl Insp Procedure for Raw Matl Instituted ML17264A1701995-09-28028 September 1995 Part 21 Rept Re Fuel Oil Booster Pump post-maint Testing Revealed Fuel Oil Sys Pressure Readings of 32 PSIG in Required Action Low Range.Plant Personnel Installed Rebuilt Fuel Oil Booster Pump on B EDG ML20095K0361995-08-28028 August 1995 Part 21 Rept Re Failure of Diesel Min Operating Fuel Oil Pressure Pump Mfg by Tuthill Corp.Safety Hazard May Be Created If Emergency DG B Not Able to Maintain Design Load Rating.Pump End Play Clearance Adjusted ML17264A1091995-07-14014 July 1995 Part 21 Rept Re 14 Inch air-operated Butterfly Valve,Used as SW Outlet Valve AOV-4561 Supplied by Fisher Controls Co.On 950418,found That Valve Actuated Opposite from Required Configuration.Actuator Lever Reinstalled ML17309A5801995-06-16016 June 1995 Initial Part 21 Rept Re air-operated Butterfly Valve Mfg by Fisher Controls Co.Actuator Lever Altered ML17263A3311993-07-20020 July 1993 Part 21 Rept Re CCW HXs Mfg by Atlas Industrial Mfg Co.As Result of Eddy Current Exam Performed During 1993 Refueling Outage,Tubes W/Measurable Defects at Tube Plate Locations That Exceeded 70% of Tube Wall Thickness Removed from Svc ML17263A3231993-06-22022 June 1993 Initial Part 21 Rept Re High Component Cooling Water Flow Results in flow-induced Vibration of HX Tubes Mfg by Atlas Industrial Mfg Co & Subsequent Tube Degradation.Tubes W/ Through Wall Indications Greater than 70% Plugged ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML17262A9821992-08-28028 August 1992 Interim Part 21 Rept Re Weld Overlap Area on body-to-bonnet Weld on 1/2-inch ASME Class II Valve Purchased from Henry Vogt Machine Co.Weld Will Be liquid-penetrant Tested Per ASME Class 2 Requirements.Completion Scheduled by 911215 ML17262A8341992-05-0404 May 1992 Interim Part 21 Rept Re 920313 Discovery of Potential Inaccuracies Associated W/Using Open Calibr Approach to Measure Closing Stem Thrust of Movs.Program for re- Evaluation of Previous Test Results in Progress ML17262A7811992-03-23023 March 1992 Part 21 Rept Re Victoreen,Inc Failure to Perform Calibr on Field Calibr Source Series 877 Detector Used in Radiation Monitoring Sys.Quality of Receipt Insp Will Be Improved Through Use of Health Physics Representative ML17262A7751992-03-23023 March 1992 Interim Part 21 Rept Re Deficiencies W/Movs V826B,V738B & V871A & Two Two Inch Velan Manual 1500 ASME Class II Valves. Further Investigation Being Conducted by Noncompliance Repts Processing Group ML17262A7691992-02-24024 February 1992 Part 21 Re Victoreen Field Calibr Source Being Accepted W/O Meeting Purchase Order Requirements.Initially Reported on 920220.Field Source Will Be Calibr & Returned in Apr 1992 ML17250B2491991-09-0404 September 1991 Forwards 10CFR21 Evaluation & Notification Re Design Defect of Solid State Switch Printed Circuit Cards for 480 Volt Safeguards Undervoltage Monitoring/Protection Sys ML17262A2621990-11-30030 November 1990 Part 21 Rept Re Chilled Water Sys.Initially Reported on 901030.Evaluation of Perry Plant Will Be Sent by 901230 ML17261B0781990-06-15015 June 1990 Part 21 Rept Re Potential Common Mode Failure of OT-2 Type Reset Switches Supplied by Westinghouse.Plungers for Listed OT-2 Type Reset Switches Verified to Be in Proper Position. Separate Independent Switches for Each Train Will Be Added ML17250B1831990-05-31031 May 1990 Part 21 Rept Re Potential Matl Defect of SMA Type Torque Switches Supplied by Limitorque During Late 1960s.Loose Torque Switch Mounting Socket Head Bolts &/Or Wire Termination Bolts Found on 19 of 26 Valve Actuators ML17251A4981989-05-12012 May 1989 Part 21 Rept Re Degradation to Pumping Ring from RHR Pumps Supplied by Pacific Pump,Inc & Mechanical Seal Supplied by Crane Packing Co.Conditon Technically Not 10CFR21 Reportable Due to 1978 Date of Occurrence ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML17261A8711989-02-28028 February 1989 Part 21 Rept Re Crimping Indentor Component Not Machined to Proper Dimensions Causing Tool to Be Out of Calibr Specs. Qualified Tool Furnished by Vendor as Replacement for Defective Item.Crimping Tools Satisfactorily Tested ML17261A5301987-06-18018 June 1987 Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys ML20134Q1741985-08-29029 August 1985 Part 21 Rept Re Potential Maint Issues Associated w/Anker-Holth Snubbers.Owners of Anker-Holth Snubbers Will Be Informed of Problems & Sent Revs to Technical Instruction Manuals to Include Procedures for Seal & Fluid Maint ML20134H0091985-08-23023 August 1985 Part 21 Rept Re Micro Instrument Corp Design Error When Upgrading Auxiliary Bldg Main Hoist Backup Hydraulic Brake Sys.Design Mod Incorporated Hydraulic Valve Which Prevented Hydraulic Pressure Release & Backup Brake Engagement ML20106C2681984-12-0303 December 1984 Part 21 Rept Re Design Error When Upgrading Catalytic,Inc post-accident Filter Duct Butterfly Valve Solenoids.Design Spec Called for Wrong Failure Position for Solenoids. Solenoids Replaced ML20010C6881981-08-0606 August 1981 Interim Deficiency Rept Re Potentially Reportable Diesel Generator Starting Air Sys Design,Initially Reported 810803. Generator Supplier Will Be Contacted to Determine Whether Deficiency Exists.Problem Suspected to Be Generic in Nature 1999-09-23
[Table view] 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 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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UTION DEMONSTIWTION SYSTEM REGULATORY INFORMATION DXSTRXBUTXON SYSTEM (RIDS)
ACCESSION NBR:9006110336 DOC.DATE: 90/05/31 NOTARIZED: NO DOCKET g FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION SMITH,R.E. Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPXENT AFFXLIATXON MURLEY,T.E. Office of Nuclear Reactor Regulation, Director (Post 870411
SUBJECT:
Part 21 rept re potential matl defect of SMA type torque switches supplied by Limitorque during late 1960s.
DISTRIBUTION CODE: IE19D COPIES RECEIVED LTR ENCL SIZE: D TITLE: Part 21 Rept (50 DKT) 8 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244
/
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 0 PD1-3 PD 1 1 D JOHNSON,A 1 1 INTERNAL: AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 D
IRM TECH ADV 1 1 NRR CRUTCHFIELD 1 1 NRR VARGA,S 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OGCB11 1 1 DRIS/RVIB9D 1 1 NRR/DST 8E2 1 1 RE 01 1 1 RES/DSIR/EIB 1 1 RGB. 1 1 RGN2 1 1 RGN3 1 1 RGN4 1 1 RGN5 1 1 EXTERNAL: INPO RECORD CTR 1 1 1 1 NRC PDR 1 1 LPDR'S IC S ILVER E g 1 1 D
A D
D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 22
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'III Zi ZWiZZ ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TCLEPNDNC AREA CDDK Tle 546-2700 May 31, 1990 U.S. Nuclear Regulatory Commission Document Control Desk Attention: Dr. Thomas E. Murley Office of Nuclear Reactor Regulation Washington, D.C. 20555
Subject:
Notification of 10CFR, Part 21 R.E. Ginna Nuclear Power Station Docket No. 50-244 Licensee No. DPR-18
Dear Dr. Murley:
Rochester Gas and Electric is submitting the attached 10CFR, Part 21 Evaluation and Notification. The notification concerns a potential material defect of SMA type torque switches supplied by Limitorque during the late 1960's.
One hundred seven (107) of one hundred eight (108) motor operated valves (MOV) installed at R.E. Ginna Nuclear Power Plant, actuator wiring configurations were inspected in conjunction with an on-going Electrical Control Configuration Drawing Upgrade Project.
Twenty-six had SMA-type torque switches installed. The SMA-type torque switch is a black fibrous, laminated, phenolic material.
Ten of the twenty-six switches demonstrated loose one-quarter inch socket head mounting screws and nine of the twenty-six demonstrated loose wire termination bolts.
None of the valves with the loose torque switch bolting demon-strated operability problems during operations or testing. The cause of the loose bolting appears to be consolidation or com-pression of the fibrous material and/or vibration.
Specific information regarding failure identification and correc-tive action taken are detailed on the enclosed Attachment 1.
Should further information be required, please contact Mr. Thomas Marlow, Superintendent of Ginna Support Services at 315/524-4446.
9006li03 6 900531 05000244 PDR ADOCK PDC
'l A,
Page 2 Dr. Thomas E. Murley May 31, 1990 Very truly yours, Robert E.,Smith Senior'ice President Production 6 Engineering xco Mr. Thomas T. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Ginna Station Senior Resident Inspector
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~ Li Attachment. I Name: Robert E. Smith Title: Senior Vice President,'roduction & Engineering Facility: R.E. Ginna Nuclear Power Plant Docket No.: 50-244 Basic Component: Safety Related Motor Operated Valve (MOV)
Actuators Supplier: Limitorque Corporation 11 Nature of Defect: Loose torque switch mounting socket head bolts and/or wire termination bolts associated with SMA-type torque switches found on 19 of 26 valve actuators inspected for wiring configuration. Twenty-six of 107 MOV actuators installed at R.E. Ginna Nuclear Power Plant contained SMA-type torque switches. Torque switch material is a black, fibrous, laminated phenolic material.
Date Obtained: This information was developed during the 1989 and 1990 refueling outage inspections for Electrical Controlled Configuration Drawing Upgrade Project.
Basic Components Affected:
Fourteen safety related MOV actuators (five were non-safety related).
Corrective Action: Immediate corrective action was to tighten the loose bolting. The torque switches are being replaced as scheduled, during a Preven-tive Maintenance Actuator Refurbishment Program. MOV actuators are now on a three year preventive maintenance inspection program for EQ operators, five year preventive maintenance inspection program for safety-related but not EQ and ten year preventive maintenance inspection program for non-safety related actuators.
Responsible Individual for Action:
Thomas A. Marlow, Superintendent Ginna Support Services
Attachment I (continued)
Time to Complete Action:
All loose bolting has been tightened or replaced during refurbishment.
Advice Related to Defect:
Loose bolting had not progressed to a degree that demonstrated an impact on operability at time of defect identification. Torque switch material is a,type supplied with 1967 vintage actuators.