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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected 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 ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed 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 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 L-98-041, Interim Part 21 Rept Re Notification to Dlc Thorugh Stone & Webster Corp.Senior Flexonics Expansion Joints Installed in Unit 2 Service Water Sys,Were Evaluated for Effects of Increased Stiffness Due to Expansion Joint Tie Rods1998-03-0909 March 1998 Interim Part 21 Rept Re Notification to Dlc Thorugh Stone & Webster Corp.Senior Flexonics Expansion Joints Installed in Unit 2 Service Water Sys,Were Evaluated for Effects of Increased Stiffness Due to Expansion Joint Tie Rods NRC-97-0141, Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility1997-12-23023 December 1997 Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility L-97-059, Interim Part 21 Rept Re Evaluation of Senior Flexonics Expansion Joints.Work on Small Piping Resource Intensive. Rept Date for Conclusions Scheduled by 9802151997-11-14014 November 1997 Interim Part 21 Rept Re Evaluation of Senior Flexonics Expansion Joints.Work on Small Piping Resource Intensive. Rept Date for Conclusions Scheduled by 980215 ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected 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 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20141K7741997-04-24024 April 1997 Part 21 Rept Re Auxiliary Feedwater Check Valve Failure. Concluded Thermal Gradient Conditions Created by Flowing Cold Water Through Hot Valve Created Rapid Cooldown of Seat Ring,Allowing Ring to Displace ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20137F3221997-03-26026 March 1997 Part 21 Rept Re Perry Nuclear Power Plant Experiencing False Trip of K600S K-Line Low Voltage Circuit Breaker w/SS-5 Solid State Trip Device.Breaker Removed from Svc & Returned to Abb for Analysis NRC-97-0005, Part 21 Rept Re 961113,EDG 11 Failed Surveillance Test 24.307.01 for LOP Coincident W/Loca.Avr Board Rev B Was Sent Offsite to an Independent Engineering Test Facility. CA Include More Analysis & Testing of AVR Board1997-02-0606 February 1997 Part 21 Rept Re 961113,EDG 11 Failed Surveillance Test 24.307.01 for LOP Coincident W/Loca.Avr Board Rev B Was Sent Offsite to an Independent Engineering Test Facility. CA Include More Analysis & Testing of AVR Board 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 ML20134H3361996-11-0505 November 1996 Part 21 Rept Re Defective Inner Thrust Bearing 1801461-01 Used in PSA 35 Mechanical Shock Arrestor Used as Restraint on Piping Sys for Nuclear Generating Plant.Lot of Defective Parts Located & Isolated to Three Customers 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 ML20115D2001996-07-0909 July 1996 Part 21 Rept Re Mfg Defect of Enterprise DSR-4 & DSRV-4 Edgs,Originally Mfg by Calcon Corp.Amot Control Corp Purchased Calcon Product Line & Maintains Design & Production.Valves Returned to Cooper Energy Svcs on 960131 ML20112D0101996-05-30030 May 1996 Part 21 Rept Re Possible Matl Defect in Certain Stainless Steel Swagelok Tube Fittings.List of Three Addl Shipments to Nuclear Facility of Parts Included in Investigation Encl ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML20092H3811995-09-12012 September 1995 Part 21 Rept Re Addl Defective Lot of 3/8-16x11/2 Hex Capscrews ASTM-A-193 Grade B7 from Which Orders Had Been Processed & Sold to Customers by Licensee ML20092H3761995-09-11011 September 1995 Part 21 Rept Re Mechanical Failures Discovered When Conducting Suppl Testing on Lot 3/8-24 X 2 A-193 B7 Hex Capscrews Identified by Head Markings ML20092A0361995-08-29029 August 1995 Part 21 Rept Re Mechanical Failures Discovered When Conducting Suppl Testing on 3/8-24 x2 A-193 B7 Hex Capscrews Identified by Head Markings ML20086T1761995-07-19019 July 1995 Part 21 Rept Re Potential Problem W/Type 51's & 87T Relays. Potential Problem Identified as Defective Tap Block. Recommends That Users Identified on Attachment 1 Page Verify Testing Per Instruction Listed on Encl Product Advisory Ltr ML20083R9101995-04-26026 April 1995 Final Part 21 Rept Re Kepco,Inc Model RMX24-D-20804 Power Supplies in Which Transistors Q15 &/Or Q16 Failed to Open & R1 Was Open.Replacement of Transmitters w/XSIS-095 Along W/ Replacement of Electrolytic Capacitors Provides Solution ML20077C2801994-11-21021 November 1994 Deficiency Rept Re Defective Yokes P/N 342849 Mfg by Copes- Vulcan,Inc.Affected Utilities Notified & Defective Yokes Will Be replaced.Copes-Vulcan Also re-inspected All Yokes in Inventory & Verified Yokes Acceptability 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 ML20072S4611994-09-0505 September 1994 Part 21 Rept Re Ssps semi-automatic Tester at Plant 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 NRC-94-0072, Part 21 Rept Re Improper Installation of Thermo-Lag Fire Barrier Matl Furnished & Delivered by Thermal Science,Inc. Eight of Ten Thermo-Lag Fire Barriers Installed by Pr Sussman Co Being Replaced1994-08-15015 August 1994 Part 21 Rept Re Improper Installation of Thermo-Lag Fire Barrier Matl Furnished & Delivered by Thermal Science,Inc. Eight of Ten Thermo-Lag Fire Barriers Installed by Pr Sussman Co Being Replaced ML20070H1471994-07-15015 July 1994 Part 21 Rept Re Problems W/Thermolag Fire Barriers.Initially Reported on 940715.Replaced Thermolag Fire Barriers ML20073S9541994-06-27027 June 1994 Part 21 Rept Re Incorrect Matl Supply Discovered on Unshipped Order.Pump Div Will Notify Enertech W/ Recommendation That Items Supplied W/Incorrect Matl Be Removed & Destroyed ML20070A1441994-06-22022 June 1994 Part 21 Rept Re Conditions Which Affect Hydraulic Valve Operators Supplied by Bw/Ip to Enertech Co & Listed Utils. Vendor Will Notify Enertech W/Recommendations That All Items Supplied W/Incorrect Matl Be Removed & Destroyed ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20059E9081993-12-29029 December 1993 Part 21 Rept Re Decreases in Valve Actuator Motor Starting Torques Resulting from Increasing 3-Phase Actuator Motor Temp.Concludes Valves Capable of Performing Intended safety- Related Function ML20058K6431993-12-10010 December 1993 Part 21 Rept Re Potential for Unacceptable Recirculation Spray Sys Operation for Supporting Long Term Core Cooling Capability.Caused by Disc of motor-operated Valve on Suction of Pump Not Engaged to Motor Operator ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20058H0791993-12-0303 December 1993 Part 21 Rept Re BVPS Unit 2 Suction Valves for Rs Pumps Supplied by Henry Pratt Co,W/Regard to Inadequate Discharge Pressure.Temporary Mod Made to Four Affected Suction Valves Which Will Properly Position & Retain Spline Adapter ML20058G5981993-11-17017 November 1993 Part 21 Rept Re Westronics Recorders,Model 2100C.Signal Input Transition Printed Circuit Board Assembly Redesigned to Improve Recorder Immunity to Electromagnetic Interference.List of Affected Recorders & Locations Encl ML20059A7181993-10-19019 October 1993 Part 21 Rept Re Defective Rocker Arms Supplied to TU & Clei. Rocker Arms Machined & Inspected to Incorrect Print & Discovered at Tu.Defective Rocker Arms Recalled from Nuclear Customers.No Corrective Action Required at Respective Utils ML20057G1511993-10-0707 October 1993 Part 21 Rept Re Westronics Model 2100C Series Recorders. Informs That Over Several Tests,Observed That Recorder Would Reset During Peak Acceleration & Door Being Forced Off Recorder.Small Retaining Clips Added to Bottom of Door ML20046B1321993-07-23023 July 1993 Interim Part 21 Rept Re Decreases in MOV Motor Starting Torques Resulting from Increasing Motor Temp.Valves Mfg by Limitorque Corp.Mfg in Process of Revising Recommended Torque Degradation Calculation at Degraded Voltage ML20056D7071993-07-15015 July 1993 Part 21 Rept Re Reportable defect-75 PSIG Relief Check Valve 1 Npt,Emd 9521844,Kepner 416C-1-75 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 ML20128H4561993-01-25025 January 1993 Followup Part 21 Rept Re Disintegration of Balston 21554-1 Automatic Drain Float & Air Piping Filter Assemblies Mfg Prior to Nov 1989.Caused by Contaminants in Air Start Sys. Customers Should Order Air Filters Mfg After Nov 1989 ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites 1999-04-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N4381999-10-25025 October 1999 Safety Evaluation Supporting Amend 17 to License DPR-9 ML20217P3551999-10-22022 October 1999 LER 99-S01-00:on 990922,loaded 9mm Handgun Was Discovered on Truck Cargo Area of Vehicle Inside Protected Area.Caused by Inadequate Vehicle Search.Guidance in Procedures & Security Training to Address Multiple Vehicle Searches Was Provided ML18039A9041999-10-15015 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 ML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program 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 ML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico NRC-99-0095, Monthly Operating Rept for Sept 1999 for Fermi 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fermi 2.With PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With L-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with 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 ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999 LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with 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. ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With NRC-99-0067, Monthly Operating Rept for Aug 1999 for Fermi 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fermi 2.With NUREG-1482, SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant1999-08-0909 August 1999 SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant 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 ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept NRC-99-0065, Monthly Operating Rept for July 1999 for Fermi 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fermi 2.With PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210R0931999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval 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 L-99-107, Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With NRC-99-0064, Monthly Operating Rept for June 1999 for Fermi 2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fermi 2.With NRC-99-0088, Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with1999-06-30030 June 1999 Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage 1999-09-30
[Table view] |
Text
~ ~
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y, ,
' r ft ASEA BROWN BOVERI L iFebruary:22."1990 Mr. Carl Berlinger, Branch Chief s
office of Generic Communications
.U.S.: Nuclear Regulatory Commission Washington,-D.C.- 20555
Subject:
- 10CFR Part'21 Report s !
'ABB 27/59 Relay. ;
Catalog Series 211L a
~Gentlement-1An.ABB'27/59' Relay (Catalog No. 211Lil75) was returned by CEI Perry Nuclear Station ~for evaluation. Examination has revealed that six (6) solder .
connections,1where the leads from three (3) wire wound 3 watt resistors !
connect to the printed wiring runs on the bottom of the circuit board.:have !
. deteriorated due.to thermal stress. The resistors are-designated R38, R39 and: l l : R41' on the circuit' board.-
'The printed wiring patternt'uses pads of only 1/8 inch diameter at these-locations.: The heat is dissipated in the wire wound resistors and:isi >
L , conducted tiirough the leads of. the resistors to these pads. It is-also '[
n radiated from the body of the-resistor to the board below.. This thermal stress has: caused the bond.of-the printed: wiring pattern to the glass epoxy
~
j
& . circuit' board to: show discoloration -and the pads have 1if ted f rom the surf ace
~
- of the board. This#jeopardizesithe integrity of the connections. No actual.
l
. failure has occurred, however should the connection fail,:the; relay would not*
~ operate properly. The likely failure mode for Catalog Number 211L1175, would o be.tofgo into an "Undervoltage" condition. -
P -ABB proposed to CEI.to furnish an interim circuit board with provisions for- '
'< ' adequate heat; dissipation. These boards'could be changed out'one at a time L since-the plant is in operation. It was also proposed that these relays be- '
. changed out at the'next outage with different model relays. CEI has advised
~
[ ' ABB: that, they are' evaluating their procedures for alternatives to circuit, y board or relay replacement. ,
j The' newer model relays have substantially larger pads- and higher wattage
- rating' resistors to lower the operating temperature, and avoid the conditions ' f s listed-previously.
'These 211L relays are used in other nuclear stations and are listed in Appendix "A". It is believed that the relays installed at.the TVA Browns >
Ferry!and-Sequoyah plants were replaced with the ABB 27N relay to obtain a f
- higher set point accuracy, and therefore 'will not have this condition.
}:
> I 9003020075 90022 e ,
PDR E '
A ADOCK 05000 59 PDC. h ABB Power Distribution Inc.
AB8 Powet oistreuhon inc. Telephone. Telefax.
201 Hekman Drive 407 323 8220 407 322 8934 Po. Box 1978 o i < Sanford, FL 327721978 - i, i
4 - ,< .- . e.. .. ~ . . .
3g
4 .
~ ~
- w. ..
.? ,_
'. .j
._Mr. Carl Berlinger #
U.S. Nuclear Regulatory Commission February 22,.1990 Page 2 The: relays in the switchgear at PSI Marble Hill (cancelled) may have been resold to other plants or users. ABB has no knowledge of their current location. '
Detroit Edison (Fermi) cnd Duquesne Light (beaver Valley) should contact ABB ,
= for recommended corrective action depending upon the application of these relays -
The quantity of relays listed in Appendix "A" includes the total number of ,
relays at.each location. Not all are used in Safety Related app 12 cations. I Also, the relays may be identified as "1TE" 27/59 rather than ABB 27/59.
J Copies of this report are being sent to the nuclear, stations listed in Appendix "A". >
) ' 6**' M q
' A. F. Kaiser, Presiden't ABB. power Distribution Inc.
EWR/jm
-Attachment J cc: K. Naidu-9.s \ i Q'q/. ,
V
- p; F ~' ' "" '
1
)fi ys . .z. - ,
,?%)
..L '
C' ,
APPENDIX "A" il .
Company Station -SUj( Relay S.O. Switchgear S.0, CEI . .
Perry 48 ---- 33-51959 (211L1175)
Detroit Edison Fe rmi '12 34-31322 ----
(211LO275)-
i
.Duquesne Light ~ Beaver 2 34-34310 ----
- (211LO275) Valley 2 34-34717 ----
Y PSI Marble Hill 12 34-39971 33-52213
'(211Lil75) 12 34-39902 33-52213 f
TVA .
Browns Ferry 13 34-38625 ----
L(211LO175)
? TVA 'Sequoyah .12 34-42905 -----
(211L0175) l i
-i F
9
.[: .
i
,6 ?
i ,
J , ,