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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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20141D8051986-04-0101 April 1986 Part 21 Rept Re Model 402 Series Level Control Used for safety-related Application Shipped W/O Torque Check. Customers Will Be Notified by 860428 & Requested to Perform Torque Check.List of Plants Using Component Encl ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20101R9441985-01-18018 January 1985 Part 21 Rept Re Defective Mounting Bolts Supplied by Unistrut Corp on Level Switches for Scram Discharge Vol Tanks.Initially Reported on 850117.Personnel Trained on Identifying Specified Bolt Matl ML20106D1321984-10-0909 October 1984 Part 21 Rept Re Cracking of LPCI M-G Set Generator Coil Clamps & Rectifier Mounting Rings Mfg by Louis-Allis Co. Initially Reported on 841005.Components Returned to Vendor ML20097K1021984-09-14014 September 1984 Part 21 Rept Re Mfg &/Or Design Defects on motor-alternator Sets.Plan Established W/Tva for Corrective Action.Coil Support Blocks to Be Replaced W/Block of Different Matl ML20079J2141984-01-11011 January 1984 Part 21 Rept Re Problems W/Elma Power Supplies Bought as Spare Parts for Two Mods.Defective Wiring,Cold Solder Joints & Overall Poor Quality Workmanship Found.Parts Installed Only in Reactor Protection Sys ML20086G8441984-01-0404 January 1984 Part 21 Rept Re Gilbert Mfg Co Nylon Bolts Used to Make Connections Between Positive Bus & Leg of Distribution Panel Breakers.Nylon Bolts to Be Replaced W/Brass Bolts ML20076E7291983-05-23023 May 1983 Deficiency Rept Re Inability of Prompt Notification Sys Mobile Sirens to Complete Routes in Required Time.Initially Reported on 830502.Addl Sirens Will Be Procured & Mobile Routes Modified.Full Compliance Expected by 830901 ML20040G8581982-02-0303 February 1982 Part 21 Rept Re Rotation of Inboard babbit-lined Bearing Mount Causing Partial Blockage of Oil Supply.Caused by Lack of Antirotation Pin or Device.Set Screw Installed in Upper Half of Bearing Mount to Prevent Rotation ML20003C0561981-02-20020 February 1981 Interim Deficiency Rept Re Flammability of Suspended Ceiling Tile in Control Rooms at Facilities.Util Evaluating Ceiling Sys Design & Available Alternatives.Next Rept Will Be Transmitted by 810403 ML19321A9691980-06-30030 June 1980 Part 21 Rept Re Defective Terry Turbine Co HPCI Turbine. Caused by Machining Error in Fabrication of Mechanical Overspeed Trip Valve Body Assembly Which Resulted in HPCI Remaining in Tripped Condition.Valve Body Replaced ML19294A7081979-03-0202 March 1979 Suppl Info Re Reportable Occurrence:During Nondestructive Examinations of Main Steam Relief Valves,Linear Indications of Minor Casting Defects Were Found During Mod of Valves by Offsite Facility.Defects Were Ground Out & Weld Repaired ML20085G4891976-11-26026 November 1976 Tenth Interim Deficiency Rept Re Potential Design Deficiency in Valve Yoke to Motor Maint Weld.Initially Reported on 740514.Spargers & Orifice Plate for Torus Line Installed ML20085E7541976-11-22022 November 1976 Third Interim Deficiency Rept Re Clogged Cooling Water Lines to RHR & Core Spray Motor Bearing Coolers.Initially Reported on 760422.Commitment Made to Perform Sys Test Every Three Months.Next Rept After Evaluation of Test Results ML20085E8751976-09-11011 September 1976 Final Deficiency Rept Re Use of Improper Schedule Pipe in Standby Liquid Control Sys.Initially Reported on 760112. Schedule 40 Pipe Will Be Replaced W/Schedule 80 Pipe.Mod Documentation Reviewed ML20085E7581976-08-23023 August 1976 Second Interim Deficiency Rept Re Clogged Cooling Water Lines to RHR & Core Spray Pump Motor Bearing Coolers. Initially Reported on 760422.Corrective Actions to Be Determined After Final Fix Proposals Evaluated ML20085E4691976-08-11011 August 1976 Final Deficiency Rept Re Defective Cam Folowers in GE Type Sbm Switches.Initially Reported on 760416.GE Revised Assembly Process to Reduce Force Applied to Insert Pivot Pins ML20084H6981976-08-0505 August 1976 Ninth Interim Deficiency Rept Re Potential Design Deficiency in Valve Yoke to Motor Mount Weld.Initially Reported on 740514.Util Is Replacing 12-inch Globe Valve in Test Return Line W/Larger Globe Valve & Orifice Plate Combination ML20085E7651976-08-0505 August 1976 Final Deficiency Rept Re Incorrect Installation of Reactor Pressure Vessel (RPV) Seismic Stabilizer Plates.Initially Reported on 760513.Formal QA Program Developed & Implemented Since Pvs Stabilizer Assembly Installed ML20085E7031976-07-23023 July 1976 Final Deficiency Rept Re Restraints for Standby Gas Treatment Sys Ducts.Initially Reported on 760615.Duct Inspected to Insure as-designed Seismic Restraint Installation.Drawing Verification Controls Reevaluated ML20085E6981976-07-23023 July 1976 Final Deficiency Rept Re Violation of Electrical Divisional Separations Criteria in RHR Sys.Initially Reported on 760615.Memo Issued Requesting Reevaluation of Existing Controls on Drawing Verification & Mods.Wires Disconnected ML20085E7771976-06-14014 June 1976 Interim Deficiency Rept Re Reactor Pressure Vessel Stabilizer Plate Incorrect Installation.Initially Reported on 760513.New Shim Plates Fabricated & Installed.Final Rept Will Follow Installation Completion & Receipt of GE Info ML20085E7401976-05-24024 May 1976 Interim Deficiency Rept Re Clogged Cooling Water Lines to RHR & Core Spray Pump Motor Bearing Coolers.Initially Reported on 760422.Check Valves Removed & Cleaned & Lines Backflushed.Final Plans Incomplete ML20085E8411976-05-24024 May 1976 Final Deficiency Rept Re Potential for RHR Pump Operation in Excess of Design Runout.Initially Reported on 760203 ML20084T9571976-05-19019 May 1976 Interim Deficiency Rept Re Defective Cam Followers in GE Type Sbm Switches.Initially Reported on 760416.Numerous Crazed Switches Found Throughout Plants.Investigation Continuing.All Crazed Switches Will Be Replaced 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 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 ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With 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 ML18039A7761999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3. ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With 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 ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205S0661999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with No Status Change from Previous Update,990331, Atlas Corp 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 ML18039A6931999-02-0303 February 1999 Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 Colr. ML18039A6941999-02-0303 February 1999 Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr. 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 ML20199K8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With ML20199F2721998-12-31031 December 1998 ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation 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
[Table view] |
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- TENNESSEE VALLEY - AUTHORITY CH ATTANOOGA.-TENNESSEE 374o1 500A Chestnut Street Tower II January.4, 1984~
Mr. James P. O'Reilly,~ Director U. S. Nuclear Regulatory Commission
-- Office of Inspection and Enforcement
, - - Region IIi 101 %rietta Street, -Suite 3100
' Atlanta, Georgia -- 30303:
Dear Mr. O'Reilly:
TENNESSEE VALLEY UTHORITY - BROWNS FERRY NUCLEAR PLANT UNITS 1 AND 2 -
DOCKET NOS. 50- 9 AND -260 - FACILITY OPERATING LICENSES DPR-33 AND 10 CFR 21 REPOR g During performance of Surveillance Instruction 4.9.A.2.c (Battery Discharge
. Test) on diesel generator (D/G) D, it was found that nylon bolts are used to make connections between the positive bus and the positive leg of all distribution panel breakers. This was discovered when troubleshooting revealed that the loss of the normal battery charger was due to a nylon-bolt breaking.
The nylon bolts are used in panels with the wilowing nameplate data:
Gilbert Manufacturing Company Model'No. GM-16801 Los Gatos, California Multiple failures of these bolted connections could result in more than one diasel ^ generator being . inoperable.
This problem is reportable under 10 CFR 21- and was reported to me on December 30, 1983 Verbal notification.was made to D. Verrelli, of your-staff, on December 30, 1983 The enclosed part 21 report contains additional information about this matter.
Very truly yours, TENNESSEE VALLEY AUTHORITY e
H'. G. Parris Manager of Power E
Enclosures hhdCIAL COPV
[bl$
I e 1
An Equal Opportunity Employer
_ . _ - . .. . . _ s
' L p: P c.J Tenn:sses Vall*.y Authority '
Form DF 119 a T* Browns Ferry Nuclear Planti Page 1 of 1 1 -i<
.I-BF 15.2 Enclosure 1 BF 15.23 "A' .' APR 271983 c-3, EVALUATION LOGIC FOR PART 21 '
^ "
PROBLEM: Miley bolts U. sed la -Ugit lnad ^2 D/& /25V D?ne,%to'o A PA d e ls p IDENTIFIED BY: Ideat;4e.1 dor;,o oerAr,.nwe of SI 4.9. A.Z.c BAtterg_hbrge
? )
i A. Does the problem Test b w inv51ve:It CMrtitopher, r 1. Failure of goods and services to comply with applicable NRC requirements
- [~ uirements are included in the procurement (regardless. of document) 'Yes whether/ / these.No / req //(If yes, go to C) 7_~
F 2. - A procured basic component failure resulting in a condition or circumstance that could contribute to exceeding a safety limit as defined by plant technical specifications. Yes / // No / / (If yes, go to B)
- r- 3. Departure of a delivered component or service from the technical
.d requirements of a procurement document. on acceptance r by NUC PR (e.g. , at receipt inspection). Yes / Delivery / No / v occurs up/
(If yes, g go to B) o h~n'sireFai1TTue'sTioiti aIio~vd.~~Tf"aIfW~s,~~STdF~11ElfE ~ Tf nny-~~- ~6iesM3" " " " "-
y 999 thu g_gs_hgc_a_t_e_d_ _b L t,1 e_ 3 g ppXc_a_bl_e_ ,",GQ_ T_Q " s ta,t_e_n} e gh _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l B. Is component necessary to ensure:
- 1. The integrity of the reactor coolant pressure boundary Yes / /, No / //
~
- 2. The capability to shut down the reactor and maintain it Yes / // No / /
in a safe shutdown condition
~3 . The capability to prevent or mitigate the consequences Yes / // No / /
'of accidents Is security system deficiency involved? Yes / / No / //
, [Ca][@[o!{'((_~@M&~[I]6[}[][]65,~}[e[s['[s((}[~Gy[M[Q~[_-(([_~(((((((((([__~[_~((_]."(( ~
C. ' Could the defect have caused a substantial safety hazard? Yes / // No / /
l (By definition, item A2 constitutes a substantial safety hazard.),
~
[C@@((((6[s[i[tij[ij, ggt,ggportable - If y_es_, this item is~[r~iE(ajl[e[i(([1j(([ art [EII-[
.()
D. Is this item reportable by. NUC PR under Part 217 Yes /// No / /
Submitted: W kReviewer &fLku '
/ /2/7/83 Date Reviewed: [ '
/ /2///h IJate '
g'ality Assurance Supervisor Approved: '
, f, / /2-/5-105 PORC Chairman Date
[
- cc
- Compliance Supervisor I'
Retention: Period - Lifetime; Responsibility - Document Control Supervisor
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^
& I .k . _ , m _~ m1 _ _ m . _ - -- J ..
. . t J~[
- M Tennessee Valley Authorn Page 1 D Browns Ferry Nuclear Plant Form BF 1<15 BF 15.23 7/2G/82 Attachment 1 Part 21
- m. Report #
PART 21 REPORT u
Plant Brews Ferru Nuclear Pina2,_
References Noap PLJ Component or System Identification /25VPc Coa +rel Feuer_#a'4frikoti 4 F nel Diesel G raorator D L3asteM W 25
(- Eupplier of Component _G;lkers many/ALLlalso Co*ynny, k.0LCAtet,SA1LlersiA
\
Nature of Defect or Noncompliance and Cause .S e e u h y-t-f J p
r~
[ Extent of Safety Hazard Mu lt,'gfg [ Adores of sese L.. It ed c oaa ett,'ons could result la mee %na one 'Lesel
. eeHerntor helag $8agetAble.
Date Which Defect or Noncompliance Was Discovered NayfmJff_22f il Number of Identical Compenents in Use _7_4/elp5]X - I9 holta_Edd/h'PI5)
Location of Components (Ju.'t / A n d 2 D ies e l G en e ra t91_ _/15 V D_C_
p Dls trib o Llo ,> PA n e l.s__
L Corrective Action and Recurrence Control Taken or To Be Taken
.See ACAm f . -
r
- Expected Completion Date U~ aunty _81,I983 Ilas defect or noncompliance been reported previously? Yes / / No / //
If yes, by what means?
_ _ ._ -l Date lA U Submittec by
'_ J n $.F -
0? IS'
/ I OltC Ileview l> ate 1
f _& Y-t buperin . adent Approval late Iletention : Period - Lifetime, P.esponsibility Document Control Supervisor
,{
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e-Enclosure 2 Nature of Defect or Noncompliance and Cause - A 1/4" x 1-1/2" nylon bolt broke in the Gilbert Manufacturing Company model GM-16801 125VDC distribution panel ~ causing the normal battery charger to be disconnected from the diesel _ generator (D/G) D battery. Nine nylon bolts are used to make . connections between the positive leg of all distribution panel breakers and the positive bus. Upon replacing the bolts, three others were also found with distorted threads in D/G D panel. Several distorted bolts were also found in D/G B panel.
Corrective Action and Recurrence Control Taken or to be Taken - Nylon bolts will be replaced by brass bolts (reference EN DES safety evaluation, MEDS accession number NEB 831130 218). The nylon bolts were changed out in units 1 and 2 D/G B distribution panel on December 1, 1983, and on D/G D distribution canel on November 30, 1983 Bolts in D/Gs A and C distribution panels will be changed out at the earliest opportunity. All bolted connections in the unit 3 D/G 125VDC distribution panels are made using metal bolts.
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