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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency LD-97-033, Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 9712011997-11-20020 November 1997 Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 971201 LD-97-028, Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys1997-10-13013 October 1997 Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys LD-97-024, Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-0041997-08-14014 August 1997 Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-004 ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs LD-96-009, Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power1996-04-15015 April 1996 Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power ML20077D3431994-11-29029 November 1994 Part 21 Rept Re Suspect Master Connecting Rods & Contains Info Location in Engine for Rods ML20078G3051994-11-0909 November 1994 Rev to Part 21 Rept Re Potential Problem W/Master Power Connecting Rods.Vendor Recommends Listed Utils Perform Visual Insp of Master Rods to Determine Applicability of Rept LD-93-003, Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared1993-01-13013 January 1993 Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML17306B0581992-10-0808 October 1992 Part 21 Rept Advising That Preliminary Evaluation of Rosemount Part 21 Notification Determined That Change in Systematic Static Pressure Span for Pressure Differential Transmitters May Result in Increase in Indicated Power ML17306A3341991-12-13013 December 1991 Followup Part 21 Rept Re Potential for Certain Westinghouse Products,Utilizing Dc Coil Assemblies,To Malfunction.Caused by Epoxy Compound Becoming semi-fluid During Svc.Initially Reported on 910624.Epoxy Check Will Be Incorporated ML20086P1591991-10-31031 October 1991 Part 21 Rept Re Microscopic Cracks in Fuel Nozzle Tip from Mfg Lot D87001.Cracks Perpendicular to Axis of Nozzle & Extend Through Case Hardening & Stop at Core.Interim/Final Report Will Be Forwarded as Further Development Occurs ML17305B6181991-06-24024 June 1991 Part 21 Rept Re Potential for Certain Westinghouse-supplied Products,Utilizing Dc Coil Assemblies,To Malfunction. Initially Reported on 910620.Recommends That All Suspect Devices Be Replaced & Epoxy Compound Probed ML17348A1621990-03-27027 March 1990 Part 21 Rept Re Matls W/Programmatic Defects Supplied by Dubose Steel,Inc.Customers,Purchase Order,Items & Affected Heat Numbers Listed 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 ML17304B1281989-04-20020 April 1989 Part 21 Rept Re Multiple Control Element Assembly Slip or Drop Events at Unit 1 on 881210.Caused by Intermittent T Grounding of Control Element Drive.Initially Reported on 890419.Stack Assemblies Will Be Replaced 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 ML17304B1691989-02-0202 February 1989 Part 21 Rept Re Ruskin Div Supplied Dampers W/Itt Actuators. Div Currently Evaluating Loctite Compound Which May Be Applied,Following Verification of Proper Damper Adjustment, to Threads of Extension Shaft in Place ML17304A9711989-01-18018 January 1989 Part 21 Rept Re Ksv Standby Diesel Generator Rocker Arm Failure.On 890104,exhaust Valve Rocker Arm Installed in KSV-20-T Engine Broke at Plant.Investigation Revealed That Castings Cracked During Mfg.Review Underway 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 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 ML17303A6081987-10-0202 October 1987 Part 21 Rept Re Fasteners Installed in motor-operated Valves.Initially Reported on 870930.Valve yoke-to-yoke Adapter Fasteners Replaced to Meet Allowable Stress Limits ML17303A5231987-07-17017 July 1987 Final Part 21 Rept RER-QSE 87-12 Re Improper Application of Agastat Relay.Initially Reported on 870714.Relay Contacts Burnished.Design Change Implemented to Replace Relays W/ Hermetically Sealed Relay W/Bifurcated Contacts ML17300A7791987-04-13013 April 1987 Revised Deficiency Evaluation Repts DER 84-30 & 86-25 Re U-2 Diesel Generator Valves & Kaman Radiation Monitors, Respectively.Changes to Reported Info or Corrective Actions Noted ML20205P7771987-03-19019 March 1987 Rev 3 to Final Part 21 & Deficiency Rept DER 82-46 Re Itt Barton Pressure Transmitters Supplied by C-E That Do Not Meet Overpressure Requirements.Rev Updates & Clarifies Info Re Description of Deficiency & Corrective Actions ML20205P9241987-03-19019 March 1987 Part 21 & Rev 2 to Final Deficiency Rept DER 84-08 Re Itt Barton Model 763 Transmitters Supplied by C-E Having Output Errors of -2 to -3% of Calibr Span.Defects May Affect Monitoring & Alarm Capabilities of Shutdown Cooling Sys ML20207S8341987-03-0606 March 1987 Final Part 21 & Deficiency Rept RER-GSE 86-41 Re Control of Design Change Packages (Dcp).Initially Reported on 861205. Review & Correction of DCPs Will Be Completed by 870101. Conditions Not Reportable Per 10CFR50.55 & Part 21 ML20207S6981987-03-0505 March 1987 Final Part 21 & Deficiency Rept RER-QSE 87-05 Re Travel Limit Switches on HVAC Dampers.Initially Reported on 870217. Condition Not Reportable Per 10CFR21 & 50.55 ML20207S9861987-03-0505 March 1987 Part 21 & Deficiency Rept RER-QSE 87-08 Re Lead Wires on Limitorque Operators.Initially Reported on 870217.Condition Found Not Reportable Under 10CFR50.55(e) & 10CFR21 ML17300A6741987-02-27027 February 1987 Part 21 & Final Deficiency Rept DER 86-29 Re Crack in Letdown HX Nozzle Mfg by Richmond Engineering Co & Supplied by C-E.Initially Reported on 861114.Nozzle Crack Initially Weld Repaired Under Nonconformance Rept Ncr NA-1942 ML20207R0951987-02-23023 February 1987 Deficiency Rept DER 86-29 Re Letdown HX Nozzle Crack. Initially Reported on 861114.Due to Extensive Investigation, Time Extension Requested.Final Rept Expected by 870227 ML20212D8301987-02-12012 February 1987 Deficiency Rept DER 86-29 Re Letdown HX Nozzle Crack. Initially Reported on 861114.Due to Extensive Investigation, More Time Required for Final Rept.Rept Anticipated by 870223 ML20211Q2681987-02-0909 February 1987 Final Part 21 & Deficiency Rept RER-QSE 86-47 Re Failure of Unit 3 B Diesel Generator Engine.Initially Reported on 861223.Units 2 & 3 Cylinder Master Rods Replaced.All Diesel 3A & Remaining 3B Rods Ultrasonically Examined ML20211A2101987-01-29029 January 1987 Final Part 21 & Deficiency Rept DER 86-32 Re Discrepancies Between Pipe Support Designs & Stress Calculations.Initially Reported on 861231.Caused by Personnel Design Errors. Condition Not Reportable Per 10CFR50.55(e) & 10CFR21 ML20211A6951987-01-23023 January 1987 Interim Deficiency Rept DER 86-30 Re Unqualified Fuses, Terminal Blocks & Wires.Initially Reported on 861104.Due to Extensive Investigation & Evaluation Required to Address Issue,Final Rept Expected by 870219 ML20213A0711987-01-20020 January 1987 Final Part 21 & Deficiency Rept RER-QSE 87-01 Re Brown Boveri K600/K800 Circuit Breakers W/Possible Cut Wires on Wire Harness.Initially Reported on 860630.Gear Guards Will Be Installed to Protect Circuit Breakers During Next Outage ML20212Q1231987-01-13013 January 1987 Part 21 & Updated Interim Deficiency Rept RER-QSE 86-47 Re Diesel Engine Generator Failure.Initially Reported on 861223.Iron Plated Rod Previously Identified as 6 Should Be Rod 9.Final Rept Will Be Submitted by 870220 ML20212H5451987-01-12012 January 1987 Part 21 Rept Re Break of Master Power Rod at Fractured Surface.Caused by Fatigue Failure Originating in Rod When Iron Plating in Articulated Rod Pin Bore Failed,Resulting in Engine Inoperability.Rod Replaced ML20212R3301987-01-0909 January 1987 Interim Deficiency Rept DER 86-29 Re Letdown HX Nozzle Crack.Initially Reported on 861114.Due to Extensive Investigation & Evaluation Required to Address Complexity of Issue,Next Rept Delayed Until 870216 ML20212Q1711987-01-0909 January 1987 Part 21 & Interim Deficiency Rept RER-QSE 86-47 Re Diesel Generator Engine Failure.Initially Reported on 861223.Caused by Fatigue Failure of Main Connecting Rod 9 Due to Addition of Iron.Final Rept Will Be Submitted by 870220 ML20210A9191987-01-0707 January 1987 Rev 1 to Final Part 21 & Deficiency Rept DER 85-38 Re QA Audit at Ge.Initially Reported on 851108.Re-audit at GE Identified Addl Purchase Orders Requiring Review for Validity of Proper Certification ML20207M2561987-01-0202 January 1987 Interim Deficiency Rept DER 86-31 Re Loose Windings of Diesel Generator.Initially Reported on 861205.Defective Rotor Removed & Visually Inspected by Vendor.Pole Piece Fasteners re-torqued.Final Rept Delayed Until 870209 ML20207M6541987-01-0202 January 1987 Interim Deficiency Rept RER-QSE 86-41 Re Withdrawal of Limitorque Operators from Warehouse W/O Required Design Changes.Initially Reported on 861205.Operators Located & Procedures Reviewed.Next Rept Delayed Until 870306 ML20207C5661986-12-12012 December 1986 Rev 2 to Deficiency Rept DER 86-04 Re Certain Seals Not Properly Supported & Rev 19 to DER 86-19 Re Modules Returned to Ga/Sorrento Electronics.Summary Description & Evaluation of Impact Encl ML20215E3691986-12-0505 December 1986 Interim Deficiency Rept DER 86-29 Re Letdown HX Nozzle Crack.Initially Reported on 861114.Due to Extensive Investigation & Evaluation,Final Rept Delayed Until 870115 1999-03-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17300B3811999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr ML17300B3271999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3 ML17313B0751999-08-27027 August 1999 LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr ML17313B0611999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr ML17313B0191999-07-16016 July 1999 LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure ML17300B3151999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pvngs,Units 1,2 & 3.With 990714 Ltr ML17313A9921999-06-21021 June 1999 Special Rept:On 990525,RMS mini-computer Was Removed from Service to Implement Yr 2000 Mod & Was OOS Longer than 72 H Allowed.Caused by Planned Y2K Mods.Preplanned Alternate Sampling Program Was Initiated ML17313A9911999-06-18018 June 1999 Special Rept:On 990510,loose-part Detection Sys Channel 2 Was Declared Inoperable.Caused by Malfunction of Mineral Cable Connector to Accelerometer.Licensee Will Implement Modifications Which Will Enhance loose-part Detection Sys ML17313A9731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pvngs,Units 1,2 & 3.With 990608 Ltr ML17313A9281999-05-0707 May 1999 LER 99-004-00:on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs ML17313A9201999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pvngs,Units 1,2 & 3.With 990512 Ltr ML17313A8951999-04-14014 April 1999 LER 99-003-00:on 990317,required Surveillance Requirement Not Completed Due to Deficient Procedure,Was Determined. Caused by Cognitive Personnel Error.St Procedures Revised to Require Chiller to Be Operating & Oil Temperature Checked ML17313A8921999-04-13013 April 1999 LER 98-003-01:on 980902,discovered That MSSV as-found Lift Pressures Were Outside TS Limits.Caused by Bonding of Valve Disc to Nozzle Seat.Affected Valves Were Adjusted,Retested & Returned to Svc ML17313A8891999-04-0909 April 1999 LER 99-001-00:on 990310,RT on High Pressurizer Pressure Was Noted.Caused by Loss of Heat Removal.Cr Supervisor Was Removed from Shift Duties for Diagnostics Skills Training. with 990409 Ltr ML17300B3071999-03-31031 March 1999 Seismic Portion of Submittal-Only Screening Review of Palo Verde Nuclear Generating Station Units Ipeee. ML17313A8801999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pvngs,Units 1,2 & 3.With 990412 Ltr ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207H7471999-03-10010 March 1999 1999 Emergency Preparedness Exercise 99-E-AEV-03003 ML17313A8361999-03-0101 March 1999 LER 99-001-00:on 990103,TS Violation for Power Dependent Insertion Limit Alarm Being Inoperable.Caused by Personnel Error.Revised Procedure to Clarify How Computer Point Is to Be Returned to Scan Mode.With 990302 Ltr ML17313A8501999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Palo Verde Nuclear Generating Station.With 990311 Ltr ML17313A7791999-02-0505 February 1999 Safety Evaluation Accepting Licensee Rev to Emergency Plan That Would Result in Two Less Radiation Protection Positions Immediatelu Available During Emergencies ML17313A8061999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Pvngs,Units 1,2 & 3.With 990218 Ltr ML17313A7701999-01-15015 January 1999 LER 96-008-00:on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised ML17313A7381998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.With 990113 Ltr ML20206H2101998-12-31031 December 1998 SCE 1998 Annual Rept ML17313A7031998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pvngs,Unit 1,2 & 3. with 981209 Ltr ML17313A6701998-11-0404 November 1998 Rev 2 to PVNGS Unit 2 Colr. ML17313A6741998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pvngs,Units 1,2 & 3.With 981109 Ltr ML17313A6611998-10-24024 October 1998 LER 98-008-00:on 980729,EQ of Electrical Connectors Were Not Adequately Demonstrated.Caused Because Test Was Conducted with Only Single Lv Connector & Without Fully Ranged Inputs. Revised EQ Requirements ML17313A6561998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for PVNGS Units 1,2 & 3.With 981007 Ltr ML17313A5961998-09-14014 September 1998 LER 98-002-00:on 980814,B Train H Recombiner Was Noted Inoperable Due to cross-wired Power Receptacle.Cause of Event Is Under investigation.Cross-wired Power Supply Receptacle for B Train H Recombiner Was re-wired ML17313A5761998-09-0808 September 1998 LER 98-003-01:on 980113,discovered That One Channel of RWT Level Sys Had Failed High.Caused by Water Intrusion Into Electrical Termination Pull Box.Weep Holes Were Drilled Into Bottoms of Pull Boxes Nearest Level Transmitters ML17313A5591998-08-28028 August 1998 LER 98-001-00:on 980730,entered TS 3.0.3 Due to Safety Injection Flow Instruments Being Removed from Svc.Caused by Personnel Error.Transmitters Were Unisolated & Returned to svc.W/980828 Ltr ML20151S0941998-08-21021 August 1998 Rev 6 to COLR for PVNGS Unit 3 ML20151S0861998-08-21021 August 1998 Rev 4 to COLR for PVNGS Unit 1 ML20151S0901998-08-21021 August 1998 Rev 1 to COLR for PVNGS Unit 2 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML17313A5401998-08-13013 August 1998 Special Rept:On 980715,declared PASS Inoperable.Caused by Failure of Offgas Flush/Purge Control Handswitch HS0101. Handswitch Replaced & Post Maintenance Retesting Was Initiated ML17313A5301998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pvgns,Units 1,2 & 3.W/980812 Ltr ML17313A5201998-07-30030 July 1998 LER 98-004-00:on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve reviewed.W/980730 Ltr ML17313A5791998-07-0707 July 1998 to PVNGS SG Tube ISI Results for Seventh Refueling Outage Mar & Apr 1998. ML17313A5001998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.W/980710 Ltr ML17313A4671998-06-19019 June 1998 LER 98-007-00:on 980520,CR Personnel Observed Flow & Pressure Perturbations on Chemical & Vol Control Sys Letdown Sys.Caused by Cyclic Fatigue Due to Dynamic Pressure Transients.Unit Letdown Piping Replaced ML17313A4521998-06-19019 June 1998 Rev 5 to COLR for Pvngs,Unit 3. ML17313A4501998-06-19019 June 1998 Rev 4 to COLR for Pvngs,Unit 3. ML17313A4131998-06-0505 June 1998 LER 98-006-00:on 980507,determined That Plant Was Outside Design Basis Due to SI Discharge Check Valve Reverse Flow. Check Valve Was Disassembled,Examined & Reassembled, Whereupon Valve Met Acceptance Criteria ML17313A4211998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pvngs,Units 1,2 & 3.W/980609 Ltr ML17313A3951998-05-26026 May 1998 LER 98-005-00:on 980428,noted That Required Response Time Testing Had Not Been Performed.Caused by Personnel Error. Coached I&C Personnel Responsible for Reviewing Work Authorization Documentation ML17313A3691998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for PVNGS.W/980412 Ltr ML17313A3251998-04-0101 April 1998 LER 98-004-00:on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three Mssv'S & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7 1999-09-30
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Text
, _ _ . . .
F.ECOVED
. UGC Arizona Public Service Company P.O BOX 21666 . PHOENIX, ARIZONA 85036
-5 N 1: 39 June 24, 1983 i ANPP-24170-BSK/RQp.3;();g y [f- l k
U. S. Nuclear Regulatory Commission /
-Region V
.Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. D. M. Sternberg, Chief l Reactor Projects Branch 1
Subject:
Final Report - DER 83-33 A 50.55(e) Potentially Reportable Deficiency Relating to GE AKR-50 Breakers With EC-1 Trips May Have A Generic Defect Which Could Cause A Malfunction.
File: 83-019-026; D.4.33.2 Re ference: Telephone Conversation between T. Young and R. Tucker on May 25, 1983
Dear Sir:
Attached is our final written report of the Reportable Deficiency under 10CFR50.55(e), referenced above.
Very truly y urs,
(
m a E. E. Van Brunt, Jr.
APS Vice President, Nuclear Projects Management ANPP Project Director EEVB/RQT:ru Enclosure cc: See Page 2 7120529 B30624
-P ADOCK 0$000530
, S PDR _
l Ill f ,T 7
a .
U. S. Nuclear Regula' tory Commission Page Two cc: Richard DeYoung , Director -
Of fice .of Inspection and Enforcement -
U. S. Nuclear Regulatory Commission Washington, D. C. 20555 ,
T. G. Woods, Jr.
G. C.'Andognini J. A. Roedel D. B. Fasnacht A. C. Rogers B. S.'Kaplan W. E. Ide J. Vorees J. R. Bynum P. P. Klute/D. D. Green A. C.-Gehr.
W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher.
.R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiore11i S. R. Frost J. Self Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339 h
r- ,
FINAL REPORT - DER 83-33 POTENTIAL REPORTABLE DEFICIENCY ARIZONA.PUBLIC SERVICE COMPANY (APS)
'PVNGS UNIT 3
+
- 1. ' Potentia 1' Problem As documented by APS -letter ANPM-16183-JTB/SLK dated 4-29-83 (Attachment '1), General Electric (GE) notified APS' of a generic defect in CE model AKR-50 circuit breakers with an EC-1 trip device which could prevent proper operation of the tripping device. GE had
'previously notified th'e Nuclear Regulatory Commission of this defect per GE to.NRC letter dated 6-15-82 (Attachment 2). Attachment 2 also identifies two additional defects in their model AKR-30 and AKR-50 circuit breakers. - APS was notified of these two additional defects per GE Service Advice 175-CPD 9.11, as indicated in APS letter. ANPM-16317-JTB/SLK dated 5-18-83 (Attachment 3). This Deficiency Evaluation Report was subsequently initiated to evaluate these three defects, which are described in the following:
1.. Failure of AKR-30 and AKR-50 low voltage power circuit breakers to close'upon command due to failure of an incompletely hardened steel part in the breaker -operator.
- 2. Failure of AKR-30 and AKR-50 low voltage power circuit breakers to close upon command due to failure of the molded case of a switch in .the breaker closing circuitry. The failure is caused by improper curing- of the molded case which encloses. the switch mechanism.
- 3. Spurious tripping of AKR-50 low voltage power circuit breakers due to failure of ground break relay components. .The failure is caused by -a manufacturing defect in the silicon controlled rectifier used in the' ground break relay..
-The subject 1 breakers are used in the following equipment for each unit at PVNGS:
J Breaker Reference Be'chtel Breaker Equipment Number Drawing (s)
AKR-5 0 . : Class'IE Battery Breaker- PKA-M4102 13-E-PKA-002 AKR-50 ' Class IE Battery Breaker PKB-M4202 13-E-PKA-005
~AKR-50 ; Class'_IE Battery Breaker :PKC-M4302~ ~ 13-E-PKA-004 1AKR _ Class IE Battery Breaker PKD-M4402 13-E-PKA-007
~AKR Reactor Trip Switchgear. :TCB-1 and. 13-E-SBB-001 and AKR Circuit Breakers TCB-2 N001-13.03-16 6-1 l _.-
t s }
L.J . m i-
l'.
Final Report DER 83-33 Page 2
'II.- Approach To'And Status Of Proposed Resolution
- 1. Defects 1 and 2 The first and second defects described in " Condition Description" (an incompletely hardened steel part in the breaker operator and an imporperly cured molded switch mechanism case, respectively) each result in a failure of the circuit breaker (AKR-30 and AKR-50) to close upon command For the Class IE battery circuit breakers (model AKR-50), FSAR Technical Specification 16.3/4.8.2.3 (DC Distribution-Operating) requires all four Class IE battery banks to be energized and operable (i.e. , capable of perfonning its design function) for plant operation. Should the Class IE battery breakers fail to close in preparation for startup, the technical specification would not be met, precluding the plant from starting up. During plant operation, these breakers are normally closed and are not operated.
For the reactor trip switchgear circuit breakers (model AKR-30),
these circuit breakers must be closed before control rods can be
. withdrawn and the plant operated. These breakers are only opened after the control rods have been inserted and the reactor is being shut down.
Since these two defects, if left uncorrected, would not adversely affect the safety of operations of the plant during '
thel lifetime of the plant, they are evaluated as not reportable under the requirements of 10CFR50.55(e).
Defect 3
.The third defect described in " Condition Description" (a -
manufacturing defect in the. silicon controlled rectifier used in the ground. break relay) could result in spurious tripping of the circuit breaker. This defect, which exists in the model AKR-50 breakers,' could result in a loss of a Class' IE battery, which
. provides a backup' source of power for the Class IE 125V DC power system.-
This condition is evaluated as reportable under the requirements L of 10CFR50.55(e) since, if lef t. uncorrected, the operation of
~
the . safety-related 125V DC. system could. be impaired and the 2 deficiency represents a significant deviation from performance p - specifications.
i y--- a-i g 9 y e '9 %
r-Final Report DER 33 Page 3 III.' Projected Completion of Corrective Action And Submittal of the Final Report sedhtel Construction will use the nonconformance report system te have the three identified breaker defects corrected prior to fuel load in each unit. The process of sequentially repairing the breakers at GE and at the jobsite is outlined in Attachment 3.
The PVNGS Project also considers " Defect 3" to be reportable under
- the requirements of 10CFR Part 21., As indicated by Attachment 2, GE
- has notified the NRC of this defect and this report therefore satisfies 'all project reporting requirements.
- A copy of this_ report will be transmitted to the Bechtel Construction Manager to assure that the corrective action plan is properly coordinated.
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'AIHtl!2@Ein IFUYWED 62WD373 DIE @@281RESSW COMPANY CORRESPONDENCE April 29, 1983
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DATE:
TO: D. B. Fasnacht ste. # 6330 FROM: A. C. Rogers sea. # 3003 E xt. # 6041
SUBJECT:
Failure of GE Model AKR50 125 Breaker DC File: EM-021 REF: (A) Telephone conversation between D. B. Fasnacht and J. T. Barrow dated April 26, 1983 (B) Telephone conversation between R. Shaw and J. T. Barrow dated April 22, 1983.
As discussed in Reference (A), GE has notified Nuclear Engineering, via Reference (B), that the model AKR-50 breaker with the EC-1 trip (manufactured
( between 1976 and 1983) has be;n determined to have a generic defect. They have notified the NRC and made an industry-wide factory recall. This defect may prevent proper operation of the tripping deveice. We have 14 breakers of this type on site (4 per unit and 2 spares). These breakers are for the battery feeders in the following DC Control Centers:
E-PKA-M41 E-PKB-M42 E-PKC-M43 E-PKD-M44 In order to expedite the resolution of this problem with the least impact on the Project Schedule, we propose that the Unit 3 breakers be removed, packaged, and returned to GE as soon as possible. When repalred and returned, these ,
breakers could replace those in Unit 1. These would be shipped to GE and when returned, would be installed in Unit 2. Then the balance of the breakers could be shipped to GE.
Bechtel Construction has indicated that they can not take action on this matter ,
without a written requrest. We request that the necessary action be taken to -
expedite the shipment of these breakers back to GE since daily delays in shipping could recult in additional weeks to the lead time required to make corrections.
We need to get at the " front of the line" of the many users of these breakers.
A response to our request is required as soon as possible.
ACR/SLK/sp c -
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( ATTACHMENT 2toDER(33(2pcges)
GENER AL h ELECTRIC "
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E O4J I P M E N T
. GENERAL ELECTRIC COMPANY, 41 WooDFoRD AVENUE, PLAINVILLE, CONN. 06052 _ DIVISIO N Phone (203) 747 7 June 15, 1982 Mr. Richard C. DeYoung Director of Office of Inspections U.S. Nuclear Regulatory Comission ,
Office of Inspection and Enforcement Washington, D.C. 20555 *
Dear Mr. DeYoung:
The Distribution Equipment Division of the General Electric Company has determined that reportable defects exist on certain of its Low-Voltage Power Circuit Breakers and on Ground Break Relay Components.
The following is the text of our notification for your use as necessary:
The General Electric Company has recently encountered a limited number of instances where electrically operated AKR-30 and AKR-50 Low-Voltage Power Circuit Breakers failed to close upon comand. The cause of failure has been traced to a steel part used in these breakers which was incompletely hardened. As far as we have been able to determine, the percentage of breakers exhibiting this reduced life is small.
The General Electric Company has also recently encountered a l limited number of occurrences of a switch used in conjunction with the electrical closing circuitry in AKR-30 and AKR-50 Low-Yoltage !
Power Circuit Breakers failing to operate as intended. This malfunction occurs as a result of improper curing of t'e molded case which encloses the switch mechanism. The mis-operattori of this .
l switch results in the possibility that the breaker may not close upon '
electrical comand.
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N, .' . ~ SENERALOrtCaic C Mr. R. C. DeYoung June 15, 1982 The General Electric Company has also recently encountered a limited number of incidents where Ground Break Relay Components I caused the associated circuit breaker to trip without a ground fault l having occurred. Tnis erroneous comand results from a latent '
manufacturing defect in the Silicon Controlled Rectifier used in the Ground Break Relay.
While the number of identified failures is small in each instance identified above, and no failures have been reported in Nuclear Class IE equipment, the General Electric Company has decided to correct these potential problems in all affected Class lE applications. In all cases, the correction will consist of replacing the suspect parts or components. General Electric Company is in the process of determining the period of time over which the potentially affected devices were manufactured and will soon be contacting the affected nuclear sites to arrange for the corrections at a mutual convenient time. ,.
If you require any further information, please contact me.
Very Trul Ygrs, dA'P David . Dixon, Manager Quality Assurance clt _
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May 16, 1983 EC ' - --
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EATE: ' .. ANPM-16317 - JTB/S1 Jy A %_.1 ..,-
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unenAKR-30 and AKR-50 Electrically Operated Circuit Breakers [r,, _, .f 8
j File: Di-020 .
REF: (A) AKR-30 and 50 Breaker Recall and Service Advice 175-CPD 9.11 (Attached) ~
(B) Letter from Norman David to John T. Barrow, dated May /5, 1983 (Attached)
(C) ANPM-16183 - JTB/SLK, dated April 29, 1963 General Electric (GE) has identified possible defects in their electrically operated AKR-30 and AKR-50 circuit breakers. AKR-30 and AKR-50 contain a defective switch and an improperly heat treated part which could result in failure of the circuit breaker to close upon command, n e AKR-50 has a defect in the ECI trip device which could prevent proper tripping action.
The AKR-50 must be returned to the factory to correct the ECI trip defect, so '
GE will correct all the problems at that time. Bechtel Construction, at the request of Nuclear Construction, has developed a program to return the circuit breakers. The first shipment is on its way to GE.
De balance of time defects not associated with the ECI trip will be corrected on site with tha assistance of a GE field representative. GE will coordin e this ef fort with the responsible parties. -
d ng--- _ Q ., 63/'>
No action or response is required by this letter, other than to provia affected groups in Operations and Startup with this information. If you g. g g have any questions, contact Steve Kasler et extension 828-6056. a a
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ACR/SLK/sp aus Attachment ,,
a ec: E. E. cyan Brunt, Jr. (w/a) J. T. Barrow (t " /.; ."i"
" S. G. Gudeman
- C. C.~ Miller D. B. Fasnacht "
G. C. Andognini b
J. R. Bynum J. M. Allen "
J. E. Kirby " W. F. Fernow Eus
" D. P. Sanchez S. M. Moyers "_ ".'
un 88* nr __
W. H. Wilson " W. J. Stubblefield aw ___
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wf1TEAft SUtv>CE DE#44TMENT 70538L PLANT stMvKr.3 L. .s- ...,3
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$$ e1 **' TELE ED:2hY AKR 30150 BREAXER RECALL At:0 SERVICE ADVISE 175-CPD 9.11 70: ff
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Distribution Equipc:ent Divison -
41 Woodford Avenue ?'-
I Plainville. CT 06062
Dear Steve:
9 The following is 'a listing of the AKR30 and AKR50 circuit. breakers at the Palo 'le'rde Nuclear site as of this date.
Item (Init Tag i Type $ rial Number Equip. Class
- 1 1 ,E-PKA-H41 AK50 NO205740004 1E
.. 1 E-PKB-M42 AK50 NO205740001 1E <.
. 3 1 E.PKC-M43 AK50 N0205740003 1E
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- 4 E-PKD-M44 1 AK50 N0205740002 1E
. $ .1 E-ten-E01B AKR-MB-50 AK08915 Non IE
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6 1 J-5BA-C03 AK30 N2589500019 lE
. 7 1 J-SB8-C03 AK30 N2689500011 1E N
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\..? ,' 2 E-PKA N41 AK50 N2360810002 lE ..
E-PXB-H42 AK50 N2390480001 1E .
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- 10 2 E-PKC-M3 AK50 n2360810003 1E 1 s: -
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- 11 2 E-PKD-M44 AK50 N2360810001 1E
- 12 2 E-MBil E01B AKR-NR-50F AK13771 Non IE I
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Mr. St' eve St. John
. Item Unit Tag i Type Scrial Humber Equip. Class
1,A -
- 15 3 E-PXA-M41 AK50 N6850640001 lE r 4,%. . , ..- .
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- 16 3 E PKS-H42 AK50 N6350640002 lE
- 17 3 E-.PKC-H43 AK50 N6850640003 1E
- 18 3 E-PXD-H44 AK50 M6850640004 IE j ,
- 19 , 3'. E-NB1-E018 AKR-h8-50F AX27927 Non IE
- *** 20 3 J-SBA-C03 AX30 N26895000i7 IE
- 22 Spare (Bechtel) AK50 N0205740001 1E
- 23 Spare (Bcchtel) AK50 N2360810004 IE
- 24 Spare (Gechtel) AK50 N8690840001 lE ,
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- 25 Spare (Bechtel) AK50 N8682800001 lE *$.-
- 4 -
- 26 Spare (APS) AXR-2BE-50 N066f220001 1E
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Note: The serial numbers listed may not still be located in the referenced equipment (tag #) due to removal and replacement
- for normal maintenance. However, the list does reflect an
. accurate count to the best of r/ ability.
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- Asterick indicates breakers to be returned to factory. , ,
- Indicates field shorting breakers in Genr.erex equipnont.
- Indicates breakers in Combustion Engineering Co. - reactor trip ,
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[ Hr. Steve St. John
. May 5. 1983 Page Three .
Per nur telephone conversation nf this d.dr. you will tw* issnines .i ri* turn authurtratica for 8 f.K',0 breakers listed abuve on items 15. 16. 1/, 18, 22
- 23. 24 and 25 and will be sending the aut.horization to Bob Shsw. EUSD, Phoenix. . 1 i
' . When these are checked out and returned, they will be swapped with unit
. one and unit two breakers (items 1, 2, 3, 4, 8. 9,10 and 11). These then
- (,- -
, will be returned along with item 26 for modification. When you issue your
second return authorization. ,it should be for these 9 breakers. Item 26 __
was received at the site on 4/13/33 as a spare ordered by A.P.S.
l It is our understanding that these returned breakers will have all service i
advices implemented or verified at the factory.
s This#then will. leave items 5. 6, 7,12.13,14.19, 20 and 21 at Palo Verde Nuclear Station, which will have to have Service Advice 175-CPD 9.11 imple-
- mented in the field.
I will require 9 sets of parts to implernent this service advice plus instruc- l
' tior.s. This quantity is only for Palo Verde and does not reflect parts re- 1 quired for non-nuclear users. I will generate this list at a later cate.
If you have any questions, or things are not as I have stated please cor.-
tact us.
I Sincerely, pf % 9 A u
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Norman P. David .
,.., Field Engineering Specialist
,NPD/ca i- . . zc: 3cb Shaw . -
Paul Rinne R. L. Anderson /
C. R. Rouse e=
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c c GENER AL h ELECTRIC j
. --us - E, NorRu si cE c-roNs GENERAL ELECTR:C CCWANY e 990 COEPCRATE CENTER,10040 NCEN 95N AVENUE
- PHOENIK,MZCNA 85021 * (609) 8611991 Hay 3, 1983
~
Arizona Nuclear Power Project ,
~
2 APS P.O. Box 21666 Phoenix, Arizona 85036 -
. Attn.: John T. Barrow, Jr...P.E.
Subject:
AKR-30 and AKR 5C Electrically Operated Circuit Breakers Our records indicate that you have lov . voltage switchgear containing Ceneral Electric electrica M operated lov voltage power circuit -
breskers in Nuclear Power. Plant applications. It has come to our attention that ele:.trically operated AKR-30 and AKR-50 circei: breakers ,
manufactured before May, 1980, may contain a defective switch and an improperly heat treated part which. under certain conditions,.could result in failure of the circuit breaker to close upon co:;=and.
Altheugh we are unaware of any,such failures of electrically operated AKR-30 and AKR-50 circuit breakers in Nuclear Power Plant applications,
. ve intend to modify all affected breakers by replacing the affected i
parts at no cost to you.
We vill contact you in the very near future to schedule the appropriate corrective action and whatever support you require vill be provided by ~
us at no cost to you
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-Very truly yours, s.
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,- Norman P. David s Field Engineering Specialist 7,. '-. x 4s- -
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NOTE: AKR 50 Breakers which are being returned to the factory under another service.' advice because of a defect in the EC1 trip device, vfil have
- this service advice implemented at that time and vill be checked to l insure that all past service advices have bean implemented.
l , .: q ,
cc: Bob Shaw, T.USD ' '
Steve St. John,' CPPD' - '
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