05000255/LER-1992-038-01, Forwards LER 92-038-01,providing Final Results of Testing Program Performed on Sola Electric Constant Voltage Transformers & Results of Evaluation of Failure of Charging Pump auto-start Circuit

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Forwards LER 92-038-01,providing Final Results of Testing Program Performed on Sola Electric Constant Voltage Transformers & Results of Evaluation of Failure of Charging Pump auto-start Circuit
Person / Time
ML18058B263
Site:	Palisades
Issue date:	12/07/1992
From:	Slade G CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18058B264	List: 05000255/LER-1992-038, :on 920825,reactor Tripped,Resulting from Loss of Preferred Ac Bus Y-20,coincident W/Blown Fuse in Second Channel of Rps.Caused by Failure of Inverter ED-07.All Fuses Checked & Plant Drawings/Vendor Manuals Updated 05000255/LER-1992-038-01, Forwards LER 92-038-01,providing Final Results of Testing Program Performed on Sola Electric Constant Voltage Transformers & Results of Evaluation of Failure of Charging Pump auto-start Circuit
References
NUDOCS 9212140166
Download: ML18058B263 (1)
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LER-1992-038, Forwards LER 92-038-01,providing Final Results of Testing Program Performed on Sola Electric Constant Voltage Transformers & Results of Evaluation of Failure of Charging Pump auto-start Circuit

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv), System Actuation
2551992038R01 - NRC Website
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text

-consumers Power l'OWERIN&

/llllCHl&AN"S l'IUl&RESS

Palisades Nuclear Plant:

27780 _Blue Star Memorial Highway, Coven, Ml 49043 December 7, 1992 Nuclear Regulatory Commission-Document Control Desk

Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

GB Slade General Manager

- SUPPLEMENTAL LICENSEE EVENT REPORT 92-038 REACTOR TRIP CAUSED BY A LOSS OF THE PREFERRED AC BUS Y-20 COINCIDENT WITH A BLOWN FUSE IN A SECOND CHANNEL OF THE REACTOR PROTECTIVE SYSTEM Supplemental Licensee Event Report (LER) 92-038-01 is attached. This event was originally reportable in accordance with 10CFR50.73(a)(2)(iv) as an event that resulted in the automatic actuation of the reactor protective sy~tem (RPS).

The supplement provides the final results of the testing performed on

- the SOLA constant voltage transformers and the results of an evaluation of the failure of the charging pump auto-start circuit. The supplemental info~mation is indicated by a vertical line in the margin of the LER.

Gerald B Slade General Manager CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment 9212140166 921207 PDR ADOCK 05000255 5

PDR A CMS Ne?GY COMPANY

Licensee Event Report

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 |

		Reporting criterion
05000255/LER-1992-001, :on 911209,observed That Seal Oil Pressure on Air Side of Electrical Generator Had Decreased from Previous Reading.Caused by Malfunction of Electrical Generator Seal Oil Sys Due to Plugged Filter.Filter Cleaned	on 911209,observed That Seal Oil Pressure on Air Side of Electrical Generator Had Decreased from Previous Reading.Caused by Malfunction of Electrical Generator Seal Oil Sys Due to Plugged Filter.Filter Cleaned	10 CFR 50.73(a)(2)(iv), System Actuation
05000255/LER-1992-002, :on 911216,discovered That Selected Reactor Protective Sys Instrument Surveillance Requirements Not Being Performed,Per Tech Spech.Caused by Procedural Weakness.Ts Surveillance Procedures Reviewed	on 911216,discovered That Selected Reactor Protective Sys Instrument Surveillance Requirements Not Being Performed,Per Tech Spech.Caused by Procedural Weakness.Ts Surveillance Procedures Reviewed	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000255/LER-1992-003, :on 911215,both Diesel Generators Inadvertently Started Due to Undervoltage Condition.Caused by Failure to Properly Calculate Cable Impedance.Analysis Being Performed of Voltage Transient	on 911215,both Diesel Generators Inadvertently Started Due to Undervoltage Condition.Caused by Failure to Properly Calculate Cable Impedance.Analysis Being Performed of Voltage Transient	10 CFR 50.73(a)(2)(iv), System Actuation
05000255/LER-1992-004, :on 920107,loss of Containment Integrity Due to Failure of Emergency Escape Airlock Equalizing Valve Occurred.Caused by Lubricant on Valve Stem.Maint Procedure for Airlocks Being Revised	on 920107,loss of Containment Integrity Due to Failure of Emergency Escape Airlock Equalizing Valve Occurred.Caused by Lubricant on Valve Stem.Maint Procedure for Airlocks Being Revised	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000255/LER-1992-005, :on 920115,NRC Notified Plant Staff of Apparent Misrouting of Class 1E Pressurizer Level Instrument Loop. Caused by Inadequate Design Control During Equipment Mod. Loop Disconnected	on 920115,NRC Notified Plant Staff of Apparent Misrouting of Class 1E Pressurizer Level Instrument Loop. Caused by Inadequate Design Control During Equipment Mod. Loop Disconnected	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000255/LER-1992-006, :on 920120,temp Element Was Not Environmentally Qualified in Accordance W/Regulatory Guide 1.97.Caused by Personnel Error & Inaccurate Documentation.Mod Prepared to Replace TE-0351B Instrument	on 920120,temp Element Was Not Environmentally Qualified in Accordance W/Regulatory Guide 1.97.Caused by Personnel Error & Inaccurate Documentation.Mod Prepared to Replace TE-0351B Instrument	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000255/LER-1992-007, :on 920205,determined That MSIV Actuator Solenoid Valves Could Be Rendered Inoperable by Main Steam Line Break Outside Containment.Caused by Installation of Unqualified Electrical Circuit.Valve Relocated	on 920205,determined That MSIV Actuator Solenoid Valves Could Be Rendered Inoperable by Main Steam Line Break Outside Containment.Caused by Installation of Unqualified Electrical Circuit.Valve Relocated	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000255/LER-1992-008, :on 920206,both HVAC Trains Inoperable When Air Conditioning Condensing Unit Bypass Line Leaked.Caused by Lack of Clearance Between Hot Gas Bypass Line & Penetration. Condensing Units Will Be Inspected	on 920206,both HVAC Trains Inoperable When Air Conditioning Condensing Unit Bypass Line Leaked.Caused by Lack of Clearance Between Hot Gas Bypass Line & Penetration. Condensing Units Will Be Inspected
05000255/LER-1992-009, :on 920213,control Room Ventilation Sys Inadvertently Switched to Emergency Mode.Caused by Combination of Inadequate Job Planning & Personnel Error. Job Planning Requirements Reviewed	on 920213,control Room Ventilation Sys Inadvertently Switched to Emergency Mode.Caused by Combination of Inadequate Job Planning & Personnel Error. Job Planning Requirements Reviewed	10 CFR 50.73(a)(2)(iv), System Actuation
05000255/LER-1992-010, :on 920213,SIRWT Liquid Sample Exceeded MPC of Radionuclides.Caused by Inadequate Corrective Action for Prior Event & Defective Review of MPC Limit.Evaluation to Be Performed of PCS Operating Procedures	on 920213,SIRWT Liquid Sample Exceeded MPC of Radionuclides.Caused by Inadequate Corrective Action for Prior Event & Defective Review of MPC Limit.Evaluation to Be Performed of PCS Operating Procedures
05000255/LER-1992-011, :on 920212,discovered Inadequate Electrical Isolation of Class 1E Pressurizer Pressure Indicator Cable. Caused by Inadequate Design Control When Equipment Installed in 1980.Mod Controls Re Changes Revised	on 920212,discovered Inadequate Electrical Isolation of Class 1E Pressurizer Pressure Indicator Cable. Caused by Inadequate Design Control When Equipment Installed in 1980.Mod Controls Re Changes Revised
05000255/LER-1992-012, :on 920214,determined That Main Steam Line Radiation Elements Not Environmentally Qualified.Caused by Personnel Error.Main Steam Line Radiation Elements Will Be Modified or Justification Will Be Provided	on 920214,determined That Main Steam Line Radiation Elements Not Environmentally Qualified.Caused by Personnel Error.Main Steam Line Radiation Elements Will Be Modified or Justification Will Be Provided	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000255/LER-1992-013, :on 920217,lack of Enviornmental Qualification for Stack Gas Flow Transmitter FT01818 Noted.Caused by Lack of Appropriate Controls.Temporary Mod Performed on Radioactive Gaseous Effluent Monitor Sys	on 920217,lack of Enviornmental Qualification for Stack Gas Flow Transmitter FT01818 Noted.Caused by Lack of Appropriate Controls.Temporary Mod Performed on Radioactive Gaseous Effluent Monitor Sys	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000255/LER-1992-014, :on 920217,unauthorized Individual Granted Unescorted Access to Plant Protected Area.Caused by Personnel Error.Personnel Reminded of Need for Attention to Detail & Log Revised	on 920217,unauthorized Individual Granted Unescorted Access to Plant Protected Area.Caused by Personnel Error.Personnel Reminded of Need for Attention to Detail & Log Revised
05000255/LER-1992-015, :on 900923,heavy Load Moved in Load Path Which Deviated from Established Safe Load Paths & Was Not Approved by Reactor Engineer.Caused by Inappropriate Procedure Rev. Reactor Engineer Will Approve Subj Deviations	on 900923,heavy Load Moved in Load Path Which Deviated from Established Safe Load Paths & Was Not Approved by Reactor Engineer.Caused by Inappropriate Procedure Rev. Reactor Engineer Will Approve Subj Deviations	10 CFR 50.73(a)(2)(i)
05000255/LER-1992-016, :on 920225,determined That Solenoid Valves & Position Switches for Control Valves Controlling Svc Water Flow from CCW HXs Not Environmentally Qualified.Caused by Inadequate Analysis.Schemes Modified	on 920225,determined That Solenoid Valves & Position Switches for Control Valves Controlling Svc Water Flow from CCW HXs Not Environmentally Qualified.Caused by Inadequate Analysis.Schemes Modified	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000255/LER-1992-017, :on 920229,unusual Event Declared When Upper Guide Structure Raised for Removal from Reactor Vessel & Fuel Assembly Observed Hanging from Structure.Caused by Bent Fuel Alignment Pins.Pins Straightened	on 920229,unusual Event Declared When Upper Guide Structure Raised for Removal from Reactor Vessel & Fuel Assembly Observed Hanging from Structure.Caused by Bent Fuel Alignment Pins.Pins Straightened
05000255/LER-1992-018-01, :on 920309,discovered That Electrical Connections Not Environmentally Qualified Existed in Electrical Circuits for Position Switches Due to Inadequate Review.Wire Nut Connections Replaced	on 920309,discovered That Electrical Connections Not Environmentally Qualified Existed in Electrical Circuits for Position Switches Due to Inadequate Review.Wire Nut Connections Replaced	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000255/LER-1992-018, :on 920305,determined That Containment Electrical Penetration Connectors Were Not Qualified W/ 10CFR50.49.Caused by Lack of Adequate Technical Guidance. Subj Connectors Replaced	on 920305,determined That Containment Electrical Penetration Connectors Were Not Qualified W/ 10CFR50.49.Caused by Lack of Adequate Technical Guidance. Subj Connectors Replaced	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000255/LER-1992-020, :on 920303,discovered That Four SI Valves Which Should Have Been Closed Arranged W/Two Closed by One Safety Injection Signal Channel.Caused by Personnel Error. HPCI Sys Modified to Use Existing Piping	on 920303,discovered That Four SI Valves Which Should Have Been Closed Arranged W/Two Closed by One Safety Injection Signal Channel.Caused by Personnel Error. HPCI Sys Modified to Use Existing Piping
05000255/LER-1992-021, :on 920314,determined That Containment Integrity Had Been Breached Due to Simultaneous Opening of Sys Boundaries.Caused by Personnel Error.Reiterated to Staff That Work Should Begin on Proper Work Orders	on 920314,determined That Containment Integrity Had Been Breached Due to Simultaneous Opening of Sys Boundaries.Caused by Personnel Error.Reiterated to Staff That Work Should Begin on Proper Work Orders	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000255/LER-1992-023, :on 920327,discovered That Previously Unidentified Junction Boxes in Electrical Circuits Contained Environmentally Unqualified Connections.Caused by Design Failure.Terminal Blocks to Be Replaced	on 920327,discovered That Previously Unidentified Junction Boxes in Electrical Circuits Contained Environmentally Unqualified Connections.Caused by Design Failure.Terminal Blocks to Be Replaced	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000255/LER-1992-024, :on 920327,inadvertent Opening of Station Power Breaker Resulting in ESF Actuation & Interruption of Shutdown Cooling.Caused by Supervisor Allowing Work to Proceed on C Bus.Event Discussed W/Maint	on 920327,inadvertent Opening of Station Power Breaker Resulting in ESF Actuation & Interruption of Shutdown Cooling.Caused by Supervisor Allowing Work to Proceed on C Bus.Event Discussed W/Maint
05000255/LER-1992-025, :on 920331,determined That Longitudinal Welds on 36-inch Main Steam Line Piping Not Included in Inservice Insp Program.Caused by Personnel Error.All Welds Inspected Using Volumetric/Surface Methods	on 920331,determined That Longitudinal Welds on 36-inch Main Steam Line Piping Not Included in Inservice Insp Program.Caused by Personnel Error.All Welds Inspected Using Volumetric/Surface Methods	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000255/LER-1992-026, :on 920331,discovered That During LOCA, Concurrent W/Loss of Offsite Power,Overcurrent Trip of EDG 1-1 Could Occur.Caused by Oversight in Original Plant Design.Time Delay Relay Installed	on 920331,discovered That During LOCA, Concurrent W/Loss of Offsite Power,Overcurrent Trip of EDG 1-1 Could Occur.Caused by Oversight in Original Plant Design.Time Delay Relay Installed	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000255/LER-1992-027, :on 920401,wire Cage Door on 625-ft Elevation in Containment Found Closed But Wire Cut So That Person Could Have Reached Through to Unlock Door.Possibly Caused by Vandalism.Door Secured by Steel Plate	on 920401,wire Cage Door on 625-ft Elevation in Containment Found Closed But Wire Cut So That Person Could Have Reached Through to Unlock Door.Possibly Caused by Vandalism.Door Secured by Steel Plate	10 CFR 50.73(a)(2)(i)
05000255/LER-1992-028, :on 920331,potential Inability to Maintain Diesel Generator Room Temp Qualification Due to non-1E Qualified Cooling Fan Noted.Procedures Revised & Design Will Be Corrected	on 920331,potential Inability to Maintain Diesel Generator Room Temp Qualification Due to non-1E Qualified Cooling Fan Noted.Procedures Revised & Design Will Be Corrected	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000255/LER-1992-028-02, Informs of Completion of Mod Re Emergency Diesel Generator Room Cooling Per LER 92-028-02	Informs of Completion of Mod Re Emergency Diesel Generator Room Cooling Per LER 92-028-02
05000255/LER-1992-029, :on 920404,inadvertent Actuation of Left Channel Sequencer Occurred.Caused by Failure to Follow Test Procedure.Importance of Incident Was Discussed W/All Shifts on Rotation	on 920404,inadvertent Actuation of Left Channel Sequencer Occurred.Caused by Failure to Follow Test Procedure.Importance of Incident Was Discussed W/All Shifts on Rotation	10 CFR 50.73(a)(2)(iv), System Actuation
05000255/LER-1992-030, :on 920403,inadvertent Start of Both Diesel Generators Occurred.Caused by Electrical Discontinuity in Contacts.Fuse Panels for Both 2400 Volt Engineered Safeguard Buses Were Inspected	on 920403,inadvertent Start of Both Diesel Generators Occurred.Caused by Electrical Discontinuity in Contacts.Fuse Panels for Both 2400 Volt Engineered Safeguard Buses Were Inspected	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)
05000255/LER-1992-031, :on 920402,left Channel DBA Sequencer Inadvertently Activated by Technician Preparing to Test Left Normal Shutdown Sequencer Due to Inadequate Test Procedures. Procedures RT-13A & B & RT-8C & D Revised	on 920402,left Channel DBA Sequencer Inadvertently Activated by Technician Preparing to Test Left Normal Shutdown Sequencer Due to Inadequate Test Procedures. Procedures RT-13A & B & RT-8C & D Revised
05000255/LER-1992-031-01, Forwards LER-92-031-01 Re Inadvertent ESF Actuation Caused by Inadequate Test Procedures.Original Corrective Action to Revise Test Connection Drawings No Longer Required Because Plant Procedures Revised in Such Detail to Eli	Forwards LER-92-031-01 Re Inadvertent ESF Actuation Caused by Inadequate Test Procedures.Original Corrective Action to Revise Test Connection Drawings No Longer Required Because Plant Procedures Revised in Such Detail to Eliminate Need	10 CFR 50.73(a)(2)(iv), System Actuation
05000255/LER-1992-032, :on 920406,unplanned Actuation of Right Channel of Safety Injection Sys Relays Occurred.Caused by Inadequate Procedure.Instructions & Steps Added to TSs Surveillance Procedures	on 920406,unplanned Actuation of Right Channel of Safety Injection Sys Relays Occurred.Caused by Inadequate Procedure.Instructions & Steps Added to TSs Surveillance Procedures	10 CFR 50.73(a)(2)(iv), System Actuation
05000255/LER-1992-033, :on 920414,inoperable Control Room Penetration Occurred.Caused by Misapplication of Procedures & Inaccurate Procedures.Plant Administrative Procedure on Control of Equipment Status Will Be Updated	on 920414,inoperable Control Room Penetration Occurred.Caused by Misapplication of Procedures & Inaccurate Procedures.Plant Administrative Procedure on Control of Equipment Status Will Be Updated
05000255/LER-1992-034, :on 920701,reactor Automatically Tripped on Loss of Load Signal,Resulting in Turbine Generator Trip & Loss of Signal.Caused by Momentary Loss of Power to Turbine Sys computers.Post-trip Review Completed	on 920701,reactor Automatically Tripped on Loss of Load Signal,Resulting in Turbine Generator Trip & Loss of Signal.Caused by Momentary Loss of Power to Turbine Sys computers.Post-trip Review Completed	10 CFR 50.73(a)(2)(iv), System Actuation
05000255/LER-1992-035, :on 920724,reactor Tripped Due to Loss of Turbine Digital Electrohydraulic Control Sys.Caused by Momentary Loss of Power to Electrohydraulic Sys Computers. Power Supply Switching Circuits Replaced	on 920724,reactor Tripped Due to Loss of Turbine Digital Electrohydraulic Control Sys.Caused by Momentary Loss of Power to Electrohydraulic Sys Computers. Power Supply Switching Circuits Replaced	10 CFR 50.73(a)(2)(iv), System Actuation
05000255/LER-1992-036, :on 920802,during Monthly TS Procedure for 1-1 Edg,Noted That Exhaust Temp Indicated Low Reading.Caused by Lack of Adequate Controls in DG Cylinder Latch.Edg Test Procedures Will Be Revised	on 920802,during Monthly TS Procedure for 1-1 Edg,Noted That Exhaust Temp Indicated Low Reading.Caused by Lack of Adequate Controls in DG Cylinder Latch.Edg Test Procedures Will Be Revised	10 CFR 50.73(a)(2)(i)
05000255/LER-1992-037, :on 920814,reactor Tripped Due to Low SG Level Resulting from Broken Air Line on Main Feedwater Regulating Valve.Air Lines to Main Feedwater Regulating Valves CV-0701 & CV-0703 Replaced & Satisfactorily Tested	on 920814,reactor Tripped Due to Low SG Level Resulting from Broken Air Line on Main Feedwater Regulating Valve.Air Lines to Main Feedwater Regulating Valves CV-0701 & CV-0703 Replaced & Satisfactorily Tested	10 CFR 50.73(a)(2)(iv), System Actuation
05000255/LER-1992-038-01, Forwards LER 92-038-01,providing Final Results of Testing Program Performed on Sola Electric Constant Voltage Transformers & Results of Evaluation of Failure of Charging Pump auto-start Circuit	Forwards LER 92-038-01,providing Final Results of Testing Program Performed on Sola Electric Constant Voltage Transformers & Results of Evaluation of Failure of Charging Pump auto-start Circuit	10 CFR 50.73(a)(2)(iv), System Actuation
05000255/LER-1992-038, :on 920825,reactor Tripped,Resulting from Loss of Preferred Ac Bus Y-20,coincident W/Blown Fuse in Second Channel of Rps.Caused by Failure of Inverter ED-07.All Fuses Checked & Plant Drawings/Vendor Manuals Updated	on 920825,reactor Tripped,Resulting from Loss of Preferred Ac Bus Y-20,coincident W/Blown Fuse in Second Channel of Rps.Caused by Failure of Inverter ED-07.All Fuses Checked & Plant Drawings/Vendor Manuals Updated
05000255/LER-1992-039, :on 921030,reactor Automatically Tripped Due to Loss of Load Resulting from Unstable Voltage to Turbine Control Sys Computers.Caused by Failure to Maintain Power Voltage to Ups.New Transformers Installed	on 921030,reactor Automatically Tripped Due to Loss of Load Resulting from Unstable Voltage to Turbine Control Sys Computers.Caused by Failure to Maintain Power Voltage to Ups.New Transformers Installed	10 CFR 50.73(a)(2)(iv), System Actuation

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