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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 ML20031E3891981-10-0707 October 1981 Deficiency Rept Re Eight Broken Flywheel Bearing Pedestal Holddown Bolt Lockwashers on LPCI Motor Generator Sets. Caused by Improper Heat Treatment of Lockwashers by Vendor 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 ML19323J3271980-06-0606 June 1980 Final Part 21 Rept Re Mixed Heat of Steel Supplied by Us Steel from Which 4-inch Elbows & 2-inch Tees Were Mfg to A234WPB Requirement.Investigations Conducted & Closed at 46 Listed Facilities 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 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 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 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 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 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 ML20085E8411976-05-24024 May 1976 Final Deficiency Rept Re Potential for RHR Pump Operation in Excess of Design Runout.Initially Reported on 760203 1999-04-01
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000260/LER-1999-010, :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 Satisfactorily1999-10-15015 October 1999
- 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
05000260/LER-1999-009, :on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug1999-10-14014 October 1999
- on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug
05000260/LER-1999-008, :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 Instructions1999-10-0808 October 1999
- 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 05000296/LER-1999-005-02, :on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With1999-09-30030 September 1999
- 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
ML20212G2241999-09-27027 September 1999 Safety Evaluation Supporting Amend 221 to License DPR-68 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 ML18039A8481999-08-16016 August 1999 Safety Evaluation Supporting Amends 260 & 219 to Licenses DPR-52 & DPR-68,respectively ML18039A8521999-08-0909 August 1999 SER Granting Licensee Request for Temporary Exemption from Requirements of 10CFR50.65,dtd 990204 ML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts ML18039A8361999-08-0303 August 1999 Safety Evaluation Re Revs to Radiological Consequences Analyses Resulting from Power Uprates for Browns Ferry,Units 2 & 3 ML18039A8321999-08-0202 August 1999 Safety Evaluation Supporting Amends 259 & 218 to Licenses DPR-52 & DPR-68,respectively 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 05000296/LER-1999-004-02, :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 Position1999-07-26026 July 1999
- 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
05000260/LER-1999-007, :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.With1999-07-20020 July 1999
- 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
05000260/LER-1999-006, :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%.With1999-07-19019 July 1999
- 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
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 05000260/LER-1999-005, :on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With1999-07-12012 July 1999
- on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With
ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With 05000260/LER-1999-004-01, :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 Reset1999-06-28028 June 1999
- 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 05000260/LER-1999-002-02, :on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With1999-06-14014 June 1999
- on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With
05000260/LER-1999-001-05, :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.With1999-06-14014 June 1999
- 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
05000260/LER-1999-003-02, :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 Scram1999-06-14014 June 1999
- 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
ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A7861999-05-21021 May 1999 SER Accepting TVA Proposed Alternatives Contained in 3-ISI-3 & 3-ISI-6 Pursuant to 10CFR50.55a(a)(3)(i) 05000296/LER-1999-003-01, :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 Tightened1999-05-0606 May 1999
- 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
ML18039A7731999-05-0303 May 1999 SER Accepting Util Second 10-year Interval Inservice Insp Program Plan Relief from ASME Boiler & Pressure Vessel Code, Section XI requirements-relief Request 3-ISI-2 for Browns Ferry Nuclear Plant,Unit 3 B130202, Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 31999-04-30030 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 ML18039A7641999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternative to Use Wire Penetrameters for Radiography Exams as Provided for in ASME Section Iii,Provides Acceptable Level of Quality & Safety ML18039A7561999-04-23023 April 1999 Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal ML18039A7401999-04-0808 April 1999 Safety Evaluation Approving Licensee Alternative for Second 10-yr Interval ISI for Class 1,2 & 3 Pressure Retaining Bolted Connections at Bfn,Unit 2 ML18039A7671999-04-0808 April 1999 Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr 05000260/LER-1999-001-03, :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 Operable1999-04-0707 April 1999
- 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 ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 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 ML18039A7271999-03-11011 March 1999 Safety Evaluation Supporting Amend 258 to License DPR-52 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 ML18039A6901999-02-23023 February 1999 SER Granting Relief from ASME Boiler & Pressure Vessel Code, Section XI Requirements,Relief Request 2-ISI-6 for Browns Ferry Nuclear Plant,Unit 2 05000296/LER-1999-002, :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.With1999-02-19019 February 1999
- 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
05000259/LER-1999-001-01, :on 990115,inoperable CR Emergency Ventilation Sys During Post Maint Testing Was Noted.Caused by Failure of Procedure Writers & Reviewers.Returned a Crev to Operable State & Revised B Crev Train Procedures.With1999-02-12012 February 1999
- on 990115,inoperable CR Emergency Ventilation Sys During Post Maint Testing Was Noted.Caused by Failure of Procedure Writers & Reviewers.Returned a Crev to Operable State & Revised B Crev Train Procedures.With
1999-09-30
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08/29/94 11:25 95137524545 E&W idOO2 n
b ELLIS & WAI IS
<m zsseooo amory amwesconwovorunc4 FAX (513) 752-4983 August 29, 1994 Nr. Leif J. Norrholm, Chief U.S. NUCLEAR REGULATORY COMMISSION Vendor Inspection Branch Division of Reactor Inspection and Licensee Performance Office of Nuclear Reactor Regulation Washington, D.C.
20555-0001 RE:
10 CFR 21 Notification
Dear Mr. Norrholm,
In compliance with the code of federal regulation requirements, attached is a 10 CFR 21 report.
Although E&W is working with Bechtel, TVA, and ITT Standard to correct the deficiency, we feel a 10 CFR 21 report is warranted. It is our understanding that TVA is independently submitting a 10 CFR 21 report.
Should you have any questions or require further information, please contact me at (513) 752-9000.
Sincerely, Richard D. Porco Director of Engineering.
cc: Roger R. Schertler, Q.A. Manager Roy W. Howard, Vice-President RDP/jml l
l i
0Jr %
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c 4400 Glen Willow Lake Lane Batavia, Ohio 45103 l
E F R862R 3sB8B b PDR
08/29/94 11:23 35137524540 EkW 16003 FORM 0.C. 34 10CFR21 DEFICIENCY REPORT Number: 101_ __
To:
Quality Assurance Manager Date:
a nn /oa From: R.D. Porco (Preparer's Name)
Copy:R Mcu ard (Preparer's immediate supervisor)
Nature of Defect:
(Attach additional data and drawings as required)
Thn mnaensers fhr the four (4) 25 ten safstv rnhted parkegna air t:ondit:bner units supplied under TV A cnntract No. 23042-M-0106 Q.
prYs*s8EeTYA"pWur#lht Ahsb"ifE8cElcE""D"eMdd"r$$EfM em ITT /TV A /Bechte3/E&W taihd to.ident2fy defic.iency. (see attachment 1).
1 Job Number:
renato
)
Tun n ork m1 - wm i
Other persons with knowledge of the defect:
Date you learned of defect:
7/18/94 Enaineerino Review - Reviewed by:
[.N k[) kem Date:
{IMF V Could the defect create a substantial safety hazard? -
Is further customer / vendor information required?
ync Name of customer / vendor: c u rtern o r-Tvn f a nchml) (v ana nc e wT)
Project affected: mvA w r~ n = Perrv n n" b r Un4+= 1
.c Ouality Assurance Review - Reviewed by:
~I h k l k Date:
B, 4L Do quality record confirm / disprove existence of defect?
yo=
Is the defect correctable on site?
mn kn anem inna Y*8 Is Engineering disposition in compliance with E&W policy?
Is corrective action required to prevent recurrence?
un Enaineerino Manager Review - Reviewed by:
b ___/ 3 b Date:
r'M /fy Defect could create a substantial safety hazard and it could exist in delivered components - Notification of Engineering Manager required.
2K5exk mot xorA ttcxk wrx itono utdx ntx :extst x x xonofuth M *Ckt0R XRQUltedx b
)Om r,/ed/f.f By:
Date reported to Engineering Manager:
08/29/94 11:26 35137524545 E&W 16004
]
10 CPR 21 REPORT MO. 101 ATTACHXEMT 1 1.
Name and address of individual informing commiscion:
Richard D. Porco, Director of Engineering Ellis & Watts 4400 Glen Willow Lake Lane Batavia, Ohio 45103 11.
Idantification of the facility, the activity, or the basic component supplied for such facility or such activity within the U.
S. which failed to comply or contains a defect.
Four (4) Safety Related Air Conditioning Units for Browns Ferry Nuclear Units 1 & 3.
f iii. Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.
TVA/Bechtel - Procurement specification Ellis At Watts - supplier of the S. R. ACU'S ITT - supplied the water cooled condensers to E&W 1
iv.
Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect.
The condensers for the four (4) 25 Ton Air Conditioning units were supplied to a refrigerant side design pressure of 150 psi.
The max operating pressure could be as high as 278 psi.
The design pressure indicated on the Bechtelf TVA specification indicate 150 psi.
The data sheet supplied by ITT indicate 150 psi.
The condensar water flow rate for the Post-Accident Condition indicate 150 gpm but should be 75 gpm. Numerous design reviews held by EEW and jointly with E&W/TVA/Bechtel failed to identify the deficiencies.
(See spec.
data sheets attached)
E&W has discussed the deficiencies with TVA and Bechtel, since Browns Ferry Nuclear Units 1 & 3 are defueled, no immediate safety hazard exists.
The date on which the information of such defect or failure to v.
comply was obtained.
Ellis & Watts was informed by TVA on or about July 18, 1994.
08/29/94 11:36 35137526545 E&W cuuo vi.
In the case of a basic component which contains a defect or fails to comply, the number and location of all such components in use at, supplied for, or being supplied for one or more facilities or activities.
ITT water cooled condensers installed in four(4)
S.
R.
ACU's supplied to TVA for Browns Ferry Unita 1 & 3.
vii. The corrective action which has been, is being, or will be taken: the name of the individual or organization responsible for the action: and the length of time that has been or will be taken to complete the action.
The condensers have been returned to ITT to rarate'the shell and provida new tube sheets to meet the required design pressure.
E&W is reviewing all documents, pressure relieving devices and pressure switches to ensure'the entire refrigerant loop is designed to meet required pressures and operation.
TVA/Bechtel is responsible to correct the procurement specification.
i The individual coordinating the ' activity at E&W is Richard D. Porco, Director of Engineering.
Expected completion of rework / replacement of non conforming component is approx, two (2) months.
viii.Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees.
This deficiency is limited to TVA's Brown Ferry Unit 1 &
l 3.
E&W is working with TVA/Bechtel to bring ' the component and specifications in compliance.
i l
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08/29/04 11:27
@5137524545 E&W EQUIPMENT NOa EFN 3 CND4Je./W2.n w
'3ERVICE: W Beasd Asam AIC us, Das 3 TUBE SIDE 9tELL SIDE pggyORS4ANCE: O SHELtj Weser Raingerent Gas (R.Q PLUID GPM ( ACT.)
150 GPM (M AX3 FLUID QUANT. ENTERING
(CPI
- F N/A at (CP) st ep VAPOR
m e
m GRAVITY N/A (ACTUAL) 7.0 94AX1 NUMSER OF PA$sES FT/SEC N/A VEE
_-u i 15 FT WATER PSI 6
PRESSURE DROP (MAX) e PSI PRESSURE DROP (ACTUAL)
D.0132 N/A RK'LINC FACTOR 95
e
- F TEMPERATUkE OUT CORRECTED MTD *
- F TUTAL HEAT REIECTED (Ben /Hv):
POULDIG FACTOR OVERALL CLEAN
- 50. FT. EPPECTIVE TRANSPER AREA. GROSS
185 DESIGN PRESSURE
( PSIC, 150 j 27s PslG.
~225 TEST PRESSURE 300
- F 300 DESIGN TPMPERATURE l*
NONE CORROslON.^1LnWANCE PfTCH BWG*
LENCTH O.D.
(O.D)*
(I.D.)
CONNECTIONS: SHELL : INLET
- i fSIZE & RATING). CH ANNEL: INLET
- l CODES AND STANDARDS APP' 'M ASME BP&V SECTION VUl, Dfylsl0N 1 i
BUNDLE ONLY:
OPERATING:
FLOODED:
MATERIAL j
PART MATERIAL FART PLOAT.TURE SHEET TURES PIXED TURE SHEET WELDFD C.S.
'3 HELL TUBE SUPPORT 5 SHELL COVER CROSS BAFFLE CHANNEL LONG BAFPLE CHANNEL COVER GASKET 3 PLOAT HEAD COVER POREIGN PRINT No.:
MANUFACTURER MODEL LOCATION DWG. NO.:
VENDOR P & I DIAGRAM NO.:
PURCHASE ORDER NO.
SPEC. NO. 21042-M.001 JOR NO. 21042 APPENDIX B REV,2 CONDENSER DATA SHEET SHEET 2 OF 4 BROWNS FERRY NUCLEAR PLANT
- DATA IU BF SUrrutD NY 5Eu,4,5 _
MR 21042. Ah/06 Bf_.
PACE.kI OF fCO ATTACHMENT 1
08/29/04 11:37 C5137584565 E&W fd]007 EQUIPMENT ho.: tiu's c.a 4 eu.
E- *;r.1 Board Itooin NC uns. Unh 3 SERV 3CE:
FOST-ACCIDENT NORMAL Dr COTL DATA:
ONE ONE Hanbar of'Coan Per Usk 300 m 252m Na CM Per Coa <*-n) au/Hr 300.000 230.000 Nd C&iry Per cod (Total). Stu/Hr 100 5 90 5 SEM. %
10.500 10.500 Air Flow Pur Unit. CFM 15 d 104 Easanas AnrTessperature.*P DB e
laeving Air T;=-i =% *P DR'WB e
W===== Air Pressurs Drop, in. w.g.
R22 R22 R d,*
e Ds CoE Fees Area. As e
Design Pressesw.sei ASME SECTION Vm A5ME SECTION VIII Codes and e ad*4 A,,M C___OMPRE$$QR UNTT DATA:
m Sat. Sucuom T - =.twe 'F e
Sat. Diasharge Tv:urs. *F e
(#----- M [w-wi $5fp%$. N e
e C-- --. % Rana e
e liig!:11do CtAaW Erwuft Law SBs MamWurn T.are 460 V/3 PH/60 H2 460 V/3 PH/60 HZ L'7.u g,3, op, gn.
Sve6co Line OD. in l
D' harge Line CD. in.
l ARI 520 ARI $20 CW and S A rd Applied DX COILS:
(
MATERIALS:
Tube OD in.
AFTM B75 SEAMLESS COPPER / 0.035 IN.
TubenfEd==
SEE SECTION 7.4.4 P A-rType
'nPE 304 STAINLESS STEEL
_" 93/Gnarc COPPERfD.010 IN.
F;natWA -s CAST IRON
'* - w /Heusing REMARKS:
EFN 3-EVP4DI 7205 ATE 06A. BFN 3-EVP 031-7205Br7206B
- 1. DX COII 5:
BFN MMP431-7205f?206
- 2. COMP.:
i l
SPEC NO. 21042-M401 JOB NO. 21042 APPENDIX B DX COOLING CO1L AND COMPRESSOR DATA SHEET
~'5HEET 3 OF 4
- REV, 2
j BROWN 3 FERRY NUr # AR FLANT
)
MR 21042 6/06 E ATTACHMENT /
PACE 6 E OF Io'3
- DAT A FKOVi pt.D BY bhJ Lt.K
08/39/94 11:28
'R5137534545 E&W Q)D08 4
AbtRMt. /ARAl0RIML OPfRRf/Aki CONblTIONS APPfmD11 C
SMEET /
OF 2 naax e storCorr s N1-M/>l/E PaoC mrootsT e PROC ACTIVITY #
QUAlff1TT
- (Foldf) agr e UNID # ABM- /- AC#-d21-728f/ Egg COWsr ACTIVITY a
! Tan a BM t-nes-ell-ner/ pang
_ MAMs a sCutDULE o G) REFERENCE DATA:
AF4 A) FUNCTION:
- 37. Instrument Data Sheet
- 38. Assy Data Dws mfM
- 3) CENERAL DATA:
10
- 39. System Design Criteria A/A/* fd-B MA
- 1. Assy E.3.P In. WC
/E-CAAa'fF #tarF44
- 2. Min operatins CFM Id /rlo so. 1g33 Class
- 3. Air Flow: Orient /Affgat str#f' MAL al. ASME Code / Class 71/A /## /IAff 7 Min I.E.P. to be allowed for (Lit.
42, seismic Cates *f7 CNC1_
/JA /F#FL 1 4
- 43. Quality Orsup d
AM E #g)$242 load 2n. u.
s sa. Location Bids /El 14 if-#@f.22 t
- 45. Blas Coluum Line: riaftf '- r 5.
~
asir: - sas-ssi: s-a C) COOLING:
- 6. Ent Air *F db/vb 15 A
a..
l.1
- 2 A H) UNIT ENVIRotRIErtAL CONDIT10NE:
7 '. Lvg A1r *F db
/Ad/f.o
- 8. /drf -Capstity. Stuh 2J1120 TTFTAC) a7. Temp *F db Mes/ Kin FA/40
- 9. ADn. Ent. Air *F dbtwb
- /A
- 48. R.N. T. Max /Ein
- 10. Abn. Lyg. Air *F db/wt AFA A9. Amb Fressure NauthAn
- FAr/4#A' F
- 11. Abn. Tot. Cap.. Stuh AFA
- 50. Radiation Dese Total Rads C IJ/df ADSM A/#
ff -
$1. Air Quality
- 12. Cond Max Wtr Temp 'T 56 A VENDon EUPPLIED DATA:
52.
- 13. Cand Min wtr Temp *f
/
IIo 14 Cond Wtr Max Flow gal / n e
- 15. Utr Pressure Drop. Tt M
/f
- 53. Unit Max EVA Input
- 16. Cond Wtr Fouling Factor d.triz
- 54. Compressor Rated HP
- 11. Met Capersho Br\\th.* EfLas fxtsgrigtf)
- 55. Van Ested KP 56.
D) HOUSINC DCTAILs:
- 18. Water Conn Location FMA K) MES DOCUMENT CorTROL DATA:
- 19. Discharse Location 7BP
- 57. Can Regat-TTA Spes i NE& #T-20.1 -
- 20. Max Discharge Dia. W x L SS. Tech Spec--TVA Spot #
TDP
- 59. Motor spec-TVA spec #
_fE-H.2.d/
- 21. Intake Location
- 60. Applic Seismic Criteria AF#-fD-f*745
- 22. Max Intake Dim. W x L
- 61. Ayylis QA Attachment *l /2/dve-8 deO
- 23. oA Lensth or Depth 13'- /."
7'- d' 2a. DA Height S#-/d*
AJ0fdS
- 25. CA Width I. Con!bt'NHR NRf6R DC.fA61/ Arg.stt/RE s
~
1TAcc$so1Es YICjf itS PftG AND BELIGN 'M/sR = iso *F.
t)
- 21. T11tertiype
- 28. Air Discharge Messle g gg 7
- 29. Air Discharge Cowl EM N MM. EM 'ISW6EIt//[
- 30. Min. Dust spot Eff. %
A N O 111 M /thell8 fftAfly&
31.
Illl/I#0 h id II. 8/O 7g gg ggggs50'/P' tau.
T) ELECTRICAL DATA:
- 32. power supply V/PM/M1 FSO/_F/l.d
- 33. Thermostat Installed on Unit f/f 34 memote Tnermostat/ volts HVAC DATA SHEET a,c,
- 35. Dhse sWruotor starters AIR CONDITIONING UNITS p,,oaas _^*nMMt P"Y '""
36.
Pt AAPT
- flLctTRf(AL AMRA lirm Air CAAlblTMansM 11Nrrt il I
I I
I I
T R.s. mt.Y..w.anv' l
I amouvu.tu vu. oAva:
Yi
urn emioscmudmine irre
-4,df l 'uior**
"Y e
MR 21042.dB4 44 ATTACHMENT
/
PACE (r7 OFlo).,
08/89/94 11:38 C3137524545 E&W
@ 009 PMT-ACCfDENT OPERAflNG CSVB11/0NS APPEND!Z _ l' SMEET,f,,,,OF 1 FiRK # __
PAN 2"M&ds PROC REQUEST #
WUANTITY,,,.--
REQ / CONT #
PROC ACTIVITY #
UNID # __
REF #
COWST ACTIVITY #
IrgM s SCHEDULE 8
- MAM3 8 C) REFERENCE DATA:
M/A A) FUNCTION:_
- 37. Instrument Date Sheet N/A
- 38. A88F Data Dwg A'N-D)- 7df04 _
- 8) CENERAL DATA:
$.O_
- 39. Systaa DesiEn criterie12* McEfy RGin1RL
- 1. Assy E.S.P In. WG 10,000
- 40. 1EEE C1ses
'TVM F/AC t'I AT( /'_
- 2. Min operating CTN
- 3. Air riow: Orient /Arrgut VERT /Cft, al. AsME Cods / Class _
Cl/III 1
- 42. Seismic Category 08 LEVE/ f Min 1.5.P. to be allowed for flit.
Location Bids /El vlN3-#EACT4X #10
- 43. Quality Group a.
load in. Us.
44 5.
- 45. Bidt Column Line UAf/7' /- F/-#2r A K 11M/r 3 - R20- REI :
P-R_
C) C00LINC:
}0il as.
- 6. Ent ALr *r 66 f5'_
H) Ulf1T Dnr1RONME3rrAL CONDITIONS:
/hS'/-
7 Lvs Air 'r ob
- 47. Tessp *r db Max / Min
- 8. Ngt Capretty. Bauh M(TDT)f/)
- 48. R.H. T. Max / Min
/f stru / -
/da/- _
N/A-
- 9. Abn. Ent. Air *r db/wb
- 49. Amb Fressure Max / Min
- /A -
'Ae7tr /
- 10. Abn. Lvg. Air *r ab/wtr -
A//A_
- 50. Radiation Dose Total Rads '# dom hl#
- 11. Abn. Tot. Cap., Btuh 9
- 51. Air Quality
- 12. Cond Max Wtr To:np 'r 52.
.a
- 13. Cond Hin Wtr Temp *r
( /4'O d ) YENDOR SUFFLIED DATA:
Cond Wtr Max Flow, gal / pin g) 1415. Utr Pressure Drop, rt (MAf) VS__
$3. Unit Max EVA Input
- 16. Cend Utr Foulinig Factor 0-ML
- 54. Compressor Rated MP
- 17. Jef Ca**c4. 8h/A :
lod.dM dEAA7#ff)
- 55. Tan Rated HP __
56, D) HOU31DC DETAILS:
- 18. Water Conn Location *
(Al[,,
K) MEB DOCUMENT CCETROL DATA:
Mf8-88 "20. /
"fo#
- 57. Cen Reqat-.TVA Spec #
- 19. Discharge Location SS. Tech spec.TVA Spec #
SS-6 9 2.ot
- 20. Max Discharts Dia. W x L
- 59. Noter 3pec-TVA spec #
BFN-fo - C-7/45_
ToA
- 60. Applit, seismic Crit.aris
- 21. Intake Location _
- 22. Max Intake Dim. W x L
- 61. Applic QA Attachment Ff ' T2/dV2-6-00/L
- 23. CA Length or Depth 13'-g" 7_',,E
- 24. 0A Height 5',,$1 ygygg.
- 25. 0A Width
- 26. InAr. WIb7M D P s!fla SEC T/64/
7-0*
1.100 bat AADIATibd DOSE 3 C"lXd' Pet {t. Glits E) UNIT ACCESSORIES:
YFK/
- 21. TL1ter/ Type y af fjgv 4 g 7g,
- 28. Air Discharse Notale
- 29. Air Discharge Cowl
- 2. [0WTA0L MN61.S l0CATE0 REMOTE
- 30. Hin. DusL 5 pol Efi.'T, FRom Ait ilNI[$. M A N M y m Tf M M /A fu W 31 4/80/NE.O M/0N # N. U I# US OWOMM-3 er a V/PH/H1
- 33. Themstat Installed on Unit',,,_,n HVAC DATA SHEET
- paig,
~
- 34. Res6ote Thermostat / volts
- 35. Dist SWIMotor Starters AIR CON 0lT10NING UNITS PRO.4CT_ RthuA " /EA#V N//24M A
36.
Aofff) l ~ptas/r-E/CCr/KBf
'o* ' Covo ' 1'**'*"' ""E-yl l
l 1
l l
l l
- 0. _
J 'rkwg33tg NatttY AUTMORITT s380RYLtE TN.
O AT E :
b f bPt'
$ph
.oo jr
' tate DTTR CVERfDSCMt%fR Trt PPD
_ __ b*
MR 21042. Alo/oG G ATTACHMENT /
PACE Cp6 op to3 b