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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20140A4761997-05-27027 May 1997 Provides Addl Info to 970429 Part 21 Rept Re Potential safety-related Problem W/Asco HV 266000-007J Scram Solenoid Pilot Valves.Corrective Actions Also Listed ML18038A8971994-09-0707 September 1994 Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures ML20072P6781994-08-29029 August 1994 Part 21 Re Condensers for Four 25 Ton Safety Related Packaged Air Conditioner Units (Acu) for BFN Units 1 & 3. Acus Supplied by Ellis & Watts & Condensers Supplied by Itt. Condensers Returned to Itt to Rerate Shell ML20128N6281993-02-12012 February 1993 Updates 920929 Part 21 Rept Re Failure of Wyle Rept 30081-99 to Provide Sufficient Evidence That Eight Cited Solenoid Valve Assemblies Qualified Per Rev a to Wyle Rept 17514-1.Parts Returned to Util on 930211.Rept Withheld ML20127N2341992-11-25025 November 1992 Interim Part 21 Rept Re Defect in GE RMS-9 Trip Devices W/ Instantaneous Trip Function.Initially Reported on 921027. Util Formally Discontinued Installation of Defective Devices & Investigating Replacement of Units W/Ge ML20116J8651992-11-0909 November 1992 Update to 920929 Part 21 Rept Re Failure of Wyle Rept 30081-99 to Provide Sufficient Evidence That Noted Serial Numbers on Solenoid Manifold Assemblies,Mfg by Automatic Valve Co,Qualified.Util Returned Valves on 921005 ML20116L6001992-10-27027 October 1992 Part 21 Rept Documenting Event 24505 Re GE Ak Circuit breaker,RMS-9 Trip Devices W/Instantaneous Trip Adjustment. Installation of RMS-9 W/Instantaneous Function Discontinued ML20115C6381992-09-30030 September 1992 Part 21 Rept Re Failure to Provide Sufficient Evidence That Eight Solenoid Manifold Valves,W/Codes GRE-001 Through GRE-008,mfg by Automatic Valve,Qualified to Wyle Rept 17514-1,Rev A.Return of Defective Valves Requested ML20118B8291992-09-30030 September 1992 Potential Part 21 Rept Re Lack of Evidence That Eight Solenoid Manifold Assemblies Mfg by Automatic Valve Qualified to NUREG-0588,Category I Requirements.Return of Suspect Assemblies Requested ML20106B8351992-09-24024 September 1992 Part 21 Rept Re Cracked Weld Found in Sample of ASTM A-500 Grade B Steel Tubing Heat T42510 from Coil 924544.Micro Analysis Indicated That Edges of Tubing Did Not Come in Contact from Weld During Mfg Process ML20115B7401992-09-22022 September 1992 Part 21 Rept Re Crack in Weld Seam of One End of Sample Taken of 4 X 4 X 1/2 ASTM-500 Grade B Tubing Supplied by Consolidated Power Supply.Appropriate Personnel Reinstructed on Importance of Weld Quality ML20118B6081992-09-22022 September 1992 Part 21 Rept Re Crack in Weld Seam on Wall Section of ASTM A-500 Grade B Steel Tubing Found by Tva/Bechtel.Caused by Not Enough Contact or No Contact Near Tube Outside Diameter.Mill Operators Should Be Reinstructed ML20079A9791991-04-0505 April 1991 Part 21 Rept Re Failure to Comply W/Purchase Orders When Shipping 12 3000 Socket Weld Unions,Astm B247 Alloy 6061-T6 & Three 150 Pipe Flanges,Astm B62 Cast Brass.Matl Supplied Following Commercial Program ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML20012C2401990-02-16016 February 1990 Part 21 Rept Re Defective Pieces of ASTM A500 Square Tubing Mfg by UNR-Leavitt.Initially Reported by Licensee on 900215. Limited Number of 29 Pieces Determined to Actually Be Defective,Per TVA Visual Insp.Matl Will Be Returned ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML19354D7171989-12-19019 December 1989 Part 21 Rept Re Use of Electrical Components & Cabling in Air Conditioning Units Not Environmentally Qualified. Initially Reported on 890920.Nonqualified Cable Will Be Replaced & Control Panel Relocated ML19325E0861989-10-16016 October 1989 Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway ML19351A2941989-10-0909 October 1989 Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment ML19325C9521989-09-29029 September 1989 Part 21 Rept Re Potential Common Failure of SMB-000 & SMB-00 Cam Type Torque Switches Supplied Prior to 1981 & 1976. Vendor Recommends That Switch W/Fiber Spacer Be Replaced ML20247Q1331989-09-20020 September 1989 Part 21 Rept Re Defect W/Two Air Conditioning Units Provided by Ellis & Watts.Caused by Undocumented Electrical Components & Cabling in Units.Tva Will Use Addl Procurement Receipt Insps of safety-related Matl ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint ML20246K2201989-05-0202 May 1989 Part 21 Rept Re EMD Air Start Motors/Ingersoll Rand 150 Bmp Model D.Initially Reported on 890404.Problem Not Considered 10CFR21 Finding by Div Based on Encl Investigation Rept & Corrective Actions Taken by Power Sys Div.Matter Closed 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 ML20244D8161989-04-13013 April 1989 Part 21 Rept Re Failure of Rosemount Transmitters.All Failed Transmitters Replaced,Inservice Test Procedure Prepared & Monthly Test of All 12 Transmitters in RCS Throughout Cycle 2 Operation Will Be Performed.Review Continuing ML20247P7991989-04-0404 April 1989 Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML20247G2481989-02-0606 February 1989 Part 21 Rept Re Hydro Test of Inboard Isolation Valve.Disc in Valve in RHR Sys Not Tested for Pressure Retention Capability During ASME Test.Item Not Reportable Per Part 21 ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20207P0451988-10-0505 October 1988 Part 21 Rept 146 Re Defect in Left Intercooler Inlet Adapter on Standby Diesel Engine Generator.Recommends Utils Inspect Left Intake Manifold Drain as Part of Operating Plan.Addl Info Expected by 881015 ML20207P0151988-10-0404 October 1988 Part 21 Rept Re Fuel Nozzle Tips in Standby Diesel Generator KSV-20-T W/Cracks Permitting Diesel Fuel to Be Sprayed Into Cylinders.Heavy Vapors Observed Emitting from Breathers on Some Cylinder Heads ML20154R9751988-09-28028 September 1988 Rev 0 to Part 21 Rept 10CFR21-0037-1 Re diesel-generator Standby Power Supply for Nuclear Power Stations EMD Model 999 Sys.Power Sys Div Will Notify All Stations Which Were Supplied W/Emd 999 Units ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve ML20153G0111988-05-0606 May 1988 Part 21 Rept Re Potential Defect in Bussman Buss KTK-R Fuse Blocks W/Part Numbers 2078,2079 & 2080.Purchasing Records Reviewed to Identify If Any Parts Were Actually Used or Shipped to Customers.Results Listed ML18093A8281988-05-0606 May 1988 Part 21 & Deficiency Rept Re Asea Brown Boveri,Power Distribution,Inc Low Voltage K-Line Circuit Breakers. Efforts Underway to Define Quantity & Type of Component Parts That May Need to Be Replaced ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed ML20153B2811988-02-22022 February 1988 Part 21 Rept Re Defect in Operation of Gas Monitors Using Fixed Filters.Initially Reported on 880212.Caused by Error in Software for Monitors.Vendor Testing Mod to Software & in Interim Recommends Changing Filters Every 48 H ML20196D6281988-02-10010 February 1988 Part 21 Rept Re Potential Defect in Certain Model RTF-480/120-30 Ac Line Regulating Transformers Involving Nuisance Tripping of 100 Ampere Ac Input Circuit Breaker When Initializing Unit.Breaker Should Be Replaced ML20149J4921988-02-0505 February 1988 Part 21 Rept Re Potential Problem W/Type 999 Unit Emergency Power Generator.Field Breaker Tripped at Facility During Test on EMD20-645E4 - Type 999 Unit.Appears That 100 Amp Is Too Low Rating & Should Be 125 Amp ML20149J0261987-12-21021 December 1987 Part 21 Rept Re Installation of Relay Part B8002DN in Foxboro 62H Controllers in Facilities.Subj Relay Must Be Replaced by Relay Part N0196ZN.Relay B8002DN Not Used in Any Other Plants ML20235U0271987-10-0707 October 1987 Part 21 Rept Re Westinghouse Plant Steam Generator Tubes Susceptible to High Cycle Fatigue Failure Similar to 870715 Event at North Anna Unit 1.Caused by Mean Stress in Tube & Superimposed Alternating Stress 1999-04-01
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18039A9041999-10-15015 October 1999 LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML20212E6341999-09-23023 September 1999 Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML20212B8561999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With ML18039A8821999-08-31031 August 1999 Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept. ML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts. ML20210N1221999-08-0202 August 1999 Safety Evaluation Accepting Licensee Request for Relief from ASME B&PV Code,Section XI Requirements.Request 3-ISI-7, Pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210R0931999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML20209J0771999-07-16016 July 1999 Safety Evaluation Concluding That Licensee Provided Adequate Information to Resolve ampacity-related Points of Concern Raised in GL 92-08 for BFN & That No Outstanding Issues Re GL 92-08 Ampacity Issues for Browns Ferry NPP Exist ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML20196F8811999-06-23023 June 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With ML18039A7761999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3. ML18039A7561999-04-23023 April 1999 Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal. ML18039A7671999-04-0808 April 1999 Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr. ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205F9341999-04-0101 April 1999 Safety Evaluation Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST Testing,Valve Program for Plant,Units 1,2 & 3 ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With ML20205S0661999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with No Status Change from Previous Update,990331, Atlas Corp ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML18039A7361999-03-11011 March 1999 Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr. ML20204C7891999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A6951999-02-19019 February 1999 LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr ML18039A6871999-02-12012 February 1999 LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr ML18039A6941999-02-0303 February 1999 Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr. ML18039A6931999-02-0303 February 1999 Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 Colr. ML20199F2721998-12-31031 December 1998 ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation ML20199K8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With ML18039A6671998-12-31031 December 1998 LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr ML18039A6661998-12-31031 December 1998 Ro:On 981215,HRPCRM 2-RM-90-273C Was Declared Inoperable. Caused by Downscale Indication.Containment RM Will Be Utilized as Planned Alternate Method of Monitoring Until Hrpcrm 2-RM-90-273C Can Be Returned to Operable Status ML18039A6471998-12-15015 December 1998 LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor ML18039A6371998-12-0707 December 1998 LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr ML20199F2791998-12-0303 December 1998 Bfnp Unit 3 Cycle 8 ASME Section XI NIS-2 Data Rept ML20198D9621998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bfn,Units 1,2 & 3. with ML18039A6071998-11-12012 November 1998 LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr 1999-09-30
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$ Q () TENNESSEE VALLEY A HORITY IE FILE COPY M -
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JUM l' r!.3 Mr. hornan C. !!oseley, Director Office of Inspection end Enforcenent U.S. Uucicar Regulatory Conaission Region II - Suite 818 230 Peachtree Street, IM.
Atlanta, Georgia 30303
Dear IIr. lioscley:
BROWilS FERRY NUCIIAR PLA11T UNIT 3 - PIPORTABLE DEFICIENCY -
RPV STABILIZER PLATES DISTALLED DICORREC11Y Initial report of the subject reportabic deficiency was c:ade to G. R.12ingler, IHtC-IE, Region II, on May 13, 1976. In compliance with paragraph 50.55(e) of 10 CFR Part 50, we are enclosing an interiza report of the deficiency. A final report will be prepared once all of the new shins have been installed and pertinent backup information is received from General Electric.
' Very truly yours, J. E. Gilleland Assistant Manager of Power Enclosure CC (Enclosure):
Dr. E. Volgenau, Director' Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 P
8308160579 760005 PDR ADOCK 05000296 S PDR l
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4 An Equal Opportunity Employer
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ENCLOSUllE
. . BROWNS FERRY NUCLEAR PLANT UNIT 3 RPV STABILIZER PIA'IES INSTALLED INCORRECTLY
,, , DDR 232 - INTERIM REPORT The General Electric Company recently released s fleid disposition instruction (FDI) requesting that an inspecticn be perfomed on the
- reactor pressure vessel (RPV) seismic stabilizers at Browns Ferry lI Nuclear Plant. The purpose of the inspection was to detemine if the
., stabilizers were installed with sufficient clearances to permit rela-tive deflections between the reactor vessel and shield wall without binding and inducing cyclic stresses in the stabilizers.
i-In performing this inspection it was discoveied that part of the
!, stabilizer assembly had been incorrectly installed. Bearing plates
! at each end of the stabilizer assembly had been installed 90 degrees l' from the intended orientation. These plates make contact during a seismic event with bumper brackets mounted on top of the biological shield wall. 'Ihe incorrect orientation reduces the amount of contact
' area between the bearing plate and bumper bracket. This could lead
, ., to damage of the stabilizer assembly during a seismic event. .
After being notified of the deficiency, GE recommended one of two fixes:
! , (2j replace the shim plate on the bumper iscucket wiva a (1} new de different dimensions. Since the stabilizers are fully assembled and 7
are located in an area with limited access, rotation of the bearing plates would have been very difficult. Instead, new shim plates have been.
fabricated and are being installed.
A final report will be prepared once all of the new shims have been
-installed and pertinent backup information is received from GE.
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