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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000317/LER-1990-0191990-07-20020 July 1990 LER 90-019-00:on 900622,determined That Inadequate Breaker Coordination Resulted in Condition Outside Design Basis. Root Cause of Improperly Sized Breaker Not Determined. W/900720 Ltr 05000318/LER-1987-005, Revised LER 87-005-00,correcting Block 15 to Reflect 870501 as Supplemental Rept Expected Submittal Date1987-08-0606 August 1987 Revised LER 87-005-00,correcting Block 15 to Reflect 870501 as Supplemental Rept Expected Submittal Date 05000317/LER-1984-004, Updated LER 84-004-01:on 840228,charging Pumps 12 & 13 Taken Out of Svc Due to Excessive Packing Leakage.Caused by Plunger Packing Failure.Evaluation of Alternative Charging Pump Packing Matls in Progress1984-04-25025 April 1984 Updated LER 84-004-01:on 840228,charging Pumps 12 & 13 Taken Out of Svc Due to Excessive Packing Leakage.Caused by Plunger Packing Failure.Evaluation of Alternative Charging Pump Packing Matls in Progress 05000318/LER-1983-043, Updated LER 83-043/03X-1:on 830809,following Reactor Trip, Steam Generator Safety Valve Failed to Reseat.Caused by Missing Pin.Valves Inspected to Ensure That Blowdown Ring & Pin Not worn.W/840330 Ltr1984-03-30030 March 1984 Updated LER 83-043/03X-1:on 830809,following Reactor Trip, Steam Generator Safety Valve Failed to Reseat.Caused by Missing Pin.Valves Inspected to Ensure That Blowdown Ring & Pin Not worn.W/840330 Ltr 05000318/LER-1983-046, Updated LER 83-046/03X-1:on 830906,penetration Room Exhaust Fan 21 Would Not Start on Containment Isolation Sys Signal While Performing Surveillance Test STP-0-22.Caused by Intermittently Failing Module.Module removed.W/8403301984-03-30030 March 1984 Updated LER 83-046/03X-1:on 830906,penetration Room Exhaust Fan 21 Would Not Start on Containment Isolation Sys Signal While Performing Surveillance Test STP-0-22.Caused by Intermittently Failing Module.Module removed.W/840330 Ltr 05000317/LER-1983-046, Updated LER 83-046/01X-1:on 830816,swing Diesel Generator 12 Shut Down on Loss of Fuel Oil During Surveillance.Caused by Isolation of Day Tank Level Switches,Preventing Fuel Oil Transfer Pump & Low Level Alarm actuation.W/840331984-03-30030 March 1984 Updated LER 83-046/01X-1:on 830816,swing Diesel Generator 12 Shut Down on Loss of Fuel Oil During Surveillance.Caused by Isolation of Day Tank Level Switches,Preventing Fuel Oil Transfer Pump & Low Level Alarm actuation.W/840330 Ltr 05000317/LER-1981-058, Updated LER 81-058/03X-1:on 810721,emergency Diesel Generator 12 to 4 Kv Bus 21 out-of-svc.Caused by Stuck Auxiliary Contact in Emergency Diesel Generator 12 Output Breaker to 4 Kv Bus 14.Switch replaced.W/840330 Ltr1984-03-30030 March 1984 Updated LER 81-058/03X-1:on 810721,emergency Diesel Generator 12 to 4 Kv Bus 21 out-of-svc.Caused by Stuck Auxiliary Contact in Emergency Diesel Generator 12 Output Breaker to 4 Kv Bus 14.Switch replaced.W/840330 Ltr 05000317/LER-1983-034, Updated LER 83-034/03X-1:on 830525,ECCS Pump Room Cooler 12 Taken Out of Svc.Cause Unknown.Supply Piping & Strainers Disassembled,Inspected & Cleaned.New Mechanical Preventive Maint Procedures implemented.W/840306 Ltr1984-03-0606 March 1984 Updated LER 83-034/03X-1:on 830525,ECCS Pump Room Cooler 12 Taken Out of Svc.Cause Unknown.Supply Piping & Strainers Disassembled,Inspected & Cleaned.New Mechanical Preventive Maint Procedures implemented.W/840306 Ltr 05000318/LER-1981-025, Updated LER 81-025/03X-1:on 810430 & 0514,reactor Protective Sys Channel B Trip Units 1,3,7,8 & 10 Bypassed to Investigate Problem w/T-hot Channel B.Caused by Failure of Two Oscillators in Transmitter Circuitry1984-03-0505 March 1984 Updated LER 81-025/03X-1:on 810430 & 0514,reactor Protective Sys Channel B Trip Units 1,3,7,8 & 10 Bypassed to Investigate Problem w/T-hot Channel B.Caused by Failure of Two Oscillators in Transmitter Circuitry 05000317/LER-1981-032, Updated LER 81-032/03X-1:on 810420,reactor Protective Sys Channel D Hi Power Thermal Margin/Low Pressure & Axial Shape Index Trip Units Bypassed for Maint.Caused by Oscillator Noise in transmitter.W/840305 Ltr1984-03-0505 March 1984 Updated LER 81-032/03X-1:on 810420,reactor Protective Sys Channel D Hi Power Thermal Margin/Low Pressure & Axial Shape Index Trip Units Bypassed for Maint.Caused by Oscillator Noise in transmitter.W/840305 Ltr 05000317/LER-1983-037, Updated LER 83-037/03X-1:on 830718,response Time of Trip Circuit Breakers 3 & 4 Undervoltage Trip Devices Slower than Tech Spec Limits.Caused by Setpoint Drift.Setpoints adjusted.W/840305 Ltr1984-03-0505 March 1984 Updated LER 83-037/03X-1:on 830718,response Time of Trip Circuit Breakers 3 & 4 Undervoltage Trip Devices Slower than Tech Spec Limits.Caused by Setpoint Drift.Setpoints adjusted.W/840305 Ltr 05000318/LER-1983-036, Updated LER 83-036/03X-1:on 830719,response Time for Reactor Trip Circuit Breakers 4 & 7 Undervoltage Devices Indicated Slower than Tech Spec Limits.Caused by Setpoint Drift & Worn Front Frame Assembly mechanisms.W/840305 Ltr1984-03-0505 March 1984 Updated LER 83-036/03X-1:on 830719,response Time for Reactor Trip Circuit Breakers 4 & 7 Undervoltage Devices Indicated Slower than Tech Spec Limits.Caused by Setpoint Drift & Worn Front Frame Assembly mechanisms.W/840305 Ltr 05000317/LER-1983-049, Updated LER 83-049/03X-1:on 830818,auxiliary Feedwater Pump 11 Found Inoperable.Caused by Stage & Shaft piece-balance Being Bound Up.Parts replaced.W/840305 Ltr1984-03-0505 March 1984 Updated LER 83-049/03X-1:on 830818,auxiliary Feedwater Pump 11 Found Inoperable.Caused by Stage & Shaft piece-balance Being Bound Up.Parts replaced.W/840305 Ltr 05000318/LER-1981-030, Updated LER 81-030/03X-1:on 810305,discovered Temp Transmitter 122HB Out of Tolerance in Nonconservative Direction.Caused Two Oscillators Producing Noise on Transmitter Output.Transmitter replaced.W/840305 Ltr1984-03-0505 March 1984 Updated LER 81-030/03X-1:on 810305,discovered Temp Transmitter 122HB Out of Tolerance in Nonconservative Direction.Caused Two Oscillators Producing Noise on Transmitter Output.Transmitter replaced.W/840305 Ltr 05000318/LER-1983-074, Updated LER 83-074/03X-1:on 831223,main Steam Supply Valve to Steam Driven Auxiliary Feedwater (AFW) Pumps Failed, Causing AFW Pump 21 to Start.Caused by Insufficient Torque on Casing Cap Screws.New Diaphragm installed.W/8402091984-02-0909 February 1984 Updated LER 83-074/03X-1:on 831223,main Steam Supply Valve to Steam Driven Auxiliary Feedwater (AFW) Pumps Failed, Causing AFW Pump 21 to Start.Caused by Insufficient Torque on Casing Cap Screws.New Diaphragm installed.W/840209 Ltr 05000317/LER-1983-047, Updated LER 83-047/03X-1:on 830822,control Room Air Conditioner Compressor 12 Failed to Run W/Start Signal. Caused by Compressor Trip Due to High Pressure.High Pressure Switch reset.W/840126 Ltr1984-01-26026 January 1984 Updated LER 83-047/03X-1:on 830822,control Room Air Conditioner Compressor 12 Failed to Run W/Start Signal. Caused by Compressor Trip Due to High Pressure.High Pressure Switch reset.W/840126 Ltr 05000318/LER-1983-064, Updated LER 83-064/03X-1:on 831105,after Obtaining Results of Unit 1 HPSI Flow Balance Test,Six Unit 2 HPSI Header Isolation Valves Required Adjustment.Caused by Inadequate Procedures.Maint Procedures revised.W/840124 Ltr1984-01-24024 January 1984 Updated LER 83-064/03X-1:on 831105,after Obtaining Results of Unit 1 HPSI Flow Balance Test,Six Unit 2 HPSI Header Isolation Valves Required Adjustment.Caused by Inadequate Procedures.Maint Procedures revised.W/840124 Ltr 05000318/LER-1983-052, Revised LER 83-052/03X-1:on 830928,auxiliary Feedwater Pump 23 Found Inoperable Due to Tripped Protective Relays. Probably Caused by Workers Shorting Internal Breaker Circuits When Working Scaffolding W/Door open.W/831028 Ltr1983-10-28028 October 1983 Revised LER 83-052/03X-1:on 830928,auxiliary Feedwater Pump 23 Found Inoperable Due to Tripped Protective Relays. Probably Caused by Workers Shorting Internal Breaker Circuits When Working Scaffolding W/Door open.W/831028 Ltr 05000318/LER-1983-007, Followup LER 83-007/01T-0:on 830203,de-energization of Reactor Protection Sys (RPS) Channels Caused PORV & Pressurizer Quench Tank Rupture Disk to Open.Caused by Blown Fuse in RPS Channel a Due to Crossed Leads in Inverter 211983-02-18018 February 1983 Followup LER 83-007/01T-0:on 830203,de-energization of Reactor Protection Sys (RPS) Channels Caused PORV & Pressurizer Quench Tank Rupture Disk to Open.Caused by Blown Fuse in RPS Channel a Due to Crossed Leads in Inverter 21 ML20062N3181982-08-13013 August 1982 LER-021/03L-0:on 820714,22B Safety Injection Tank Pressure Found Decreased to 197 Psig on 820427.Caused by Loop Isolator Failure.Isolator Replaced 05000317/LER-1982-022, Updated LER 82-022/01T-1:on 820503,total Type B & C Penetration Leakage Calculations Compared to Wrong Spec. Caused by Incorrectly Revised Local Leak Rate Surveillance Test Procedure.Procedure Revised1982-07-22022 July 1982 Updated LER 82-022/01T-1:on 820503,total Type B & C Penetration Leakage Calculations Compared to Wrong Spec. Caused by Incorrectly Revised Local Leak Rate Surveillance Test Procedure.Procedure Revised ML20062F7081978-12-14014 December 1978 /01x-0 on 781213:reactor Was Made Critical w/11 Component Cooling Heat Exchanger Out of Svc & 11 Saltwater sub-sys Partially Drained.Caused by Personnel Error ML20062G1191978-12-14014 December 1978 /03L-0 on 781117: 5 Halon sub-sys Discharged When Door to 22 Inverter Was Open.Caused by Thermal Detector Being Overly Sensitive to Rate of Rise of Temp.When Door Opened,Internal Airflow Disturbed,Setting Off Detector ML20062E9211978-12-0707 December 1978 /03L-0 on 781113:during Normal Oper the Containment Particulate Radioactivity Monitor Failed Low at 1110.Caused by Disconnection of Signal Cable to Monitor. Cable Connected & Monitor Returned to Svc ML20062E8961978-12-0707 December 1978 /03L-0 on 781115:during Normal Oper Periodic Water Inventory Balance Indicated That Unidentified Reactor Coolant Leakage Was 1.72 Gpm at 0600.Leak Identified as Cracked Weld ML20062D8011978-11-24024 November 1978 /03L-0 on 781115:RWT Level Discovered to Be at 455 Inches.Caused by Rad-Chem Technician'S Failure to Fully Close Local Sample Valve After Drawing Routine Sample. Technician Has Been Reinstructed in Valve Sampling ML20062D7181978-11-24024 November 1978 /03L-0 on 781103:in Routine Surveillance test,11 Auxiliary Feed Pump Was Tripped Per Procedure & Oper Was Unable to Reset Throttle Valve Due to Binding.Assembly Was Freed Upon Lubrication of Stem & Nut ML20062D7691978-11-17017 November 1978 /03L-0 on 781031:solenoid Valve 1-SV-4043 for Main Steam Isolation Valve Hydraulic Accumulators Was Leaking Due to Failure of 1 of 4 O Ring Seals.Cause of Ring Failure Unknown.All 4 Seals Replaced & Valve Returned to Svc ML20062D3411978-11-16016 November 1978 /03L-0 on 781020:pump for Radiat Monitors Seized, Perhaps Due to Graphite Particles from Pump Being Deposited in Bearings.A Normal End of Life Failure.Code Pump Model 6 ML20062D0471978-11-13013 November 1978 /01t-0 on 781025:during LPPT in Mode 2,containment Air Lock Was Opened to Repair Failed Oper Mechanism & Was Kept Ajar,Due to Misunderstanding Between Supervisor & Maintenance Personnel.All Personnel Have Been Reinstructed ML20062D0361978-11-10010 November 1978 /03L-0 on 781025:during Oper,Reactor Protec Instru Wide Range Logarithmic Neutron Flux Monitor Channel a Read 2 Decades Lower than Other Channels,Due to Connector,For Channel a Not Being Dried Completely When Recently Cleaned ML20062C8041978-11-0202 November 1978 /01T-0 on 781023:during Routine Test of Steam Generator Isolation Signal logic,21 Main Steam Isolation Valve Failed to Shut Upon Sgisa & Sgisb Signal or Hand Switch in Control Room,Due to Sticking MSIV Solenoid Valves ML20062C6941978-10-24024 October 1978 /01X-0 on 781023:during Inspec of Steam Generator Isolation Signal logic,21 Main Steam Isolation Valves Failed to Shut When Given Sgisa & Sgisb Signal.Cause Undetermined 1990-07-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G6971999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant ML20212A4441999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with ML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. with ML20210N6001999-07-27027 July 1999 ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included ML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs LD-99-039, Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999 Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With LD-99-035, Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999 Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed ML20196C6981999-06-21021 June 1999 Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable ML20195K2811999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ccnpp,Units 1 & 2. with ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models ML20205N2951999-04-13013 April 1999 Special Rept:On 990314,fire Detection Sys Was Removed from Svc to Support Mod to Replace SRW Heat Exchangers in Unit 2 SRW Room During Unit 2 Refueling Outage.Contingency Measure 15.3.5.A.1 Will Continue Until Fire Detection Sys Restored ML20210T5211999-04-0101 April 1999 Rev 0 to Ccnpp COLR for Unit 2,Cycle 13 ML20205P5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M8321999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Calvert Cliffs Nuclear Power Plant.With ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20206Q3221999-01-11011 January 1999 Special Rept:On 981226,wide Range Noble Gas Effluent RM Was Removed from Operable Status.Caused by Failure of mid-range Checksource to Properly Reseat.Completed Maint & post-maint Testing & RM Was Returned to Operable Status on 990104 ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors ML20199F4781999-01-0808 January 1999 Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with ML20206R9911998-12-0808 December 1998 Rept of Changes,Tests & Experiments (10CFR50.59(b)(2)). with ML20198B2631998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative ML20196E2211998-10-31031 October 1998 Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves ML20195E5281998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With ML20154Q7191998-10-21021 October 1998 Special Rept:On 980923,unit 1 Wrngm Was Removed from Operable Status.Caused by Failure of Process Flow Transducer.Completed Maint to Remove Process Flow Transducer Input to Wrngm Microprocessor & Completed Formal Evaluation ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20154M5841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Calvert Cliffs Nuclear Plant,Units 1 & 2.With ML20153C2571998-09-18018 September 1998 Special Rept:On 980830,wide Range Noble Gas Monitor (Wrngm) Channel Was Removed from Operable Status.Caused by Need to Support Performance of Required 18-month Channel Calibr.Will Return Wrngm to Operable Status by 980925 ML20153C1091998-09-18018 September 1998 Part 21 Rept Re Defective Capacity Control Valves.Trentec Personnel Have Been in Contact with Bg&E Personnel Re Condition & Have Requested Potentially Defective Valves ML20151U5441998-09-0404 September 1998 Bg&E ISI Summary Rept for Calvert Cliffs ML20151T5281998-09-0101 September 1998 Special Rept:On 980819,declared Rv Water Level Monitor Channel a Inoperable.Caused by Failure of Three Heated Junction Thermocouples (Sensors) in Lower Five Sensors. Channel a & B Rv Water Level Probes Will Be Replaced ML20151Y1191998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Calvert Cliffs Nuclear Power Plant Units 1 & 2.With ML20237D4981998-08-19019 August 1998 Safety Evaluation Accepting Licensee Request for Extension of Second ten-year Inservice Insp Interval 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 ML20237B9371998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Calvert Cliffs Nuclear Power Plant ML20237D5941998-07-22022 July 1998 Rev 2 to Ccnpp COLR for Unit 2,Cycle 12 ML20236L7521998-07-0606 July 1998 Safety Evaluation Granting Bg&E 980527 Request for Relief from Requirement of Section IWA-5250 of ASME Code for Calvert Cliffs Unit 2.Alternatives Provide Reasonable Assurance of Operational Readiness ML20236F7791998-06-30030 June 1998 Safety Evaluation Authorizing Request for Temporary Relief from Requirement of Subsection IWA-5250 of ASME Code,Section XI for Plant,Unit 1 ML20236R0881998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20236X3101998-06-19019 June 1998 Rev 1 to Calvert Cliffs Nuclear Power Plant COLR for Unit 2,Cycle 12 ML20249A9571998-06-15015 June 1998 Special Rept:On 980430,fire Detection Sys Was Removed from Svc to Support Mod to Purge Air Sys 27-foot Elevation & 5-foot Elevation East Piping Penetration Rooms.Installed Temporary Alteration & Returned Fire Detection Sys to Svc ML20249A7711998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ccnpp,Units 1 & 2 1999-09-30
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- BALTIMORE i OAS AND i i ELECTRIC l CHARLES CENTER e P.O. BOX 1475 e BALTIMORE, MARYLAND 21203 1475 l R E. DENTON d
.AANAQt h 1 l ': CA(VIRT CLfFf $ SnC.E Ab r= twin ><&ui mAnwsu,'
July 20, 1990 f i
U.S. Nuclear Regulatory Commission Docket No. 50 317 t .- Document Control Desk License No. DPR 53 >
Washington, D.C. 20555
Dear Sirs:
The attached LER 90 019, Revision 0, is being sent to you as required under 10 CFR 50.73 guidelines.
Should you have any questions regarding this report, we would be pleased to discuss them with you.
Very truly yours, ,
/r R. E. Denton i Manager i
KWG/bjd r Attachment 1
c c '. - Mr. T. T. Martin l Director, Office of Management Information l- and Program Control dessrs: C. C. Creel C. H. Cruse R. E. Denton R. P. Heibel J. R. Lemons L. B. Russell ,
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] no gg2 3;3 9;o nestiact <t a.= = s.= ... . . ,, . . ,, , o ei On June 22, 1990 during a review of a design discrepancy, it was octermined that certain breakers supplying power to non safety related loads from 1E safety related buses were not properly coordinated with the motor control center supply breaker. Under certain circumstances this condition could have resulted in an adverse affect on the safety related loads of the motor control center (MCC). If a ground fault had existed on the non safety related load circuits, the MCC supply breaker may have opened causing a loss of power to the safety and non safety related loads supplied by the MCC. In addition, one breaker was identified which was of improper current interruption capability for its application, which could have also caused the MCC feeder breaker to open. This condition was limited to thermal magnetic breakers without ground fault protection which were added to safety related MCOs.
The root cause of the lack of breaker ground fault coordination was a design error due to use of a MCC breaker design which was not addressed in tht existing MCC coordination calculation. The root cause of the use of em improperly sized breaker has not been determined.
Since the improperly coordinated breakers were installed, design unit checklists have been revised to specifically document consideration of circuit coordination. Circuits powered from safety related MCCs have been reviewed to identify similar coordination concerns. Corrective actions will also include replacement and/or roodification ci the MCC breakers to provido proper coordination, and breaker size verification through walkdowns, once - se. = =
UCENSEE EVENT REPORT (LER) TEXT CONTINUATION menm uw oocatnumeen tan mumun uw Calvert Cliffs, Unit 1 05000317 90 019 00 0 2 0F 0 4 '
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I. DESCRIPTION OF CONDITION on June 22, 1990 during a review of a design discrepancy, it was determined that certain non safety related loads supplied from the Class 1E 480 Volt power system motor control cen'.ers (MCC) could, under certain conditions, cause the associated MCC supply breakers to open, de energizing the entire ,
MCC. In addition, one breaker was inappropriately sized and did not have the required maximum fault current interruption capability. This is a condition outside the design bases of the Calvert Cliffs Nuclear Power Plant (CCNPP). ;
At the time of discovery, Unit I was in Mode 5, Cold fhutdown at etmospheric '
pressure and approximately 140 F, and Unit 2 was defueled.
The CCNPP 480 Volt power system includes four safety related 1E motor control centers, two for each unit. Two of the safety related 1E MCCs, one on each unit, were determined to supply power to three non safety related loads (2 on one MCC in unit 1, 1 on one MCC in unit 2), which could adversely affect the ,
ability of these two MCCs to supply power to safety related loads.
Specifically, the three thermal magnetic MCC circuit breakers which supply the '
non safety related loads were not fully coordinated with the MCC feeder breaker. These breakers did not include ground fault protection, and for a limited range of ground fault currents the MCC feeder breaker may have opened in response to a ground fault on the non safety related portion of the three loads. The MCC breakers should have been coordinated in a way which isolated a postulated fault frem the MCC, allowing the safety related portions of the 1
system to continue to perform their required functions.
The non safety related loads supplied by the safety related buses listed above were installed as plant modifications between 1975 and the mid 80s. The breakers used for the non safety related loads were molded case, thermal magnetic without the ground fault features required to assure proper coordination. The breakers were apparently erroneously chosen based on misapplication of a breaker coordination calculation package for the associated MCCs.
Furthermore, one of the three breakers was rated for a maximum fault current ,
L of 14000 amperes when the design of the MCC specified use of a breaker capable of interrupting a current of 25000 amperes. Had a postulated fault existed on the non safety related circuit which exceeded this rating, the MCC supply breaker may have opened, isolating the entire MCC and its loads from their power supply.
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4 4 g N LICENSEl! EVENT REPORT (LER) TEXT CONTINUATION FAciUTY hatet DOCKtt leutet4R L8R NutettR PAat Colvert Cliffs, Unit 1 05000317 90 019 00 0 3 0F 0 4 Trxton wan w o .mi *im)
II. CAUSE OF EVENT 1 The root cause of the lack of breaker ground fault coordination was a design ,
error due to use of a MCC breaker design which was not addressed in the j existing MCC coordination calculation. The root cause of the use of an 1 improperly sized breaker hao not been determined.
III.- ANALYSIS OF EVENT ;
This condition was reportable in accordance with the requirements of 10 CFR 50.73(a)(2)(ii)(B) in that the plant was operated in a condition outside its design bases.
Cround Fault Concern If a ground fault had occurrod on one of the three affected non safety related circuits, and the fault current was of a defined magnitude, the safety related portions of the' motor control center might have been adversely effected by the ;
opening of the supply breaker, isolating the entire MCC and its loads from the power supply. ,
Current Interruption Capability Concern Had a postulated fault existed on the non safety related circuit with the ,
undersized fault interruption capability, the breaker may not have opened. If this had occurred, the MCC supply breaker would have opened, isolating the entire MCC and its loads from their power supply. !
This condition did not significantly threaten the health and safety of the public, nor did it significantly increase the risk, or potential severity, of a postulated design bases accicent.
The reportable condition was limited to thermal magnetic breakers without ground fault protection which ware added to safety related MCCs. For the condition to have resulted in an actual event, a number of specific conditions would have to exist at the same time. For the ground fault concern to have resulted in an actual event, the fault would have to result in a current within a specific magnitude rante, (i.e. neither extremely high or very low resistance paths to ground.) Fcr the undersized fault interruption capability to have resulted in an actual ev+nt, the fault experienced by the circuit would have to be of low resistanae and high current carrying capability.
Finally, had a deficiency ruaulted in an actual failure, only a single MCC would have been affected, the refundant train of safety related equipment would not have been affected.
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION eacutt maan oocartmuseen tan muussa Paoc j C:1 vert Cliffs Unit 1 05000317 90 019 00 0 4 0F 0 4 i i
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IV. CORRECTIVE ACTIONS The effected breakers have been opened and tagged to administrative 1y assure their associated circuits are isolated from the safety related MCCs which normally power them. This assures that any postulated fault will not affect i s
safety related loads currently powered from the MCC. q Since the period during which these breakers were installed, the design unit checklists have been modified to specifically require consideration of circuit f coordination.
Circuits powered from safety related motor control centers have been reviewed to identify similar coordination concerns. Two breakers which supply power to the safety related Post Accident Sampling System were identified which could also result in a ground fault propagating to the associated load control '
center feeder breaker. All five (3 non. safety related, 2 safety related) occurrences will be resolved by equipment replacement or modification.
To enhance configuration management, a task has been organized to review breaker coordination in all MCC circuits and prepare separate coordination curves for each circuit. The review will assure proper coordination exists t and is properly documented.
The cause of the improporiv sized breaker has not yet been determined. Initial actions will verify that .11 other MCC breakers are properly sized. The need for additional corrective actions will be determined following completion of an investigation into the circumstances which led to the breakers installation. The results of this investigation and any additional corrective actions will be described in a supplement to this LER.
V. ~ ADDITIONAL INFORMATION L No similar events have been identified.
Equipment Affected Description EIIS System Code EIIS Component Code Breakers ED BKR l
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05000317/LER-1990-019 | LER 90-019-00:on 900622,determined That Inadequate Breaker Coordination Resulted in Condition Outside Design Basis. Root Cause of Improperly Sized Breaker Not Determined. W/900720 Ltr | |
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