Forwards LER 80-018/03L-0
Person / Time
ML19305D851
Site:	Calvert Cliffs
Issue date:	04/10/1980
From:	Russell L BALTIMORE GAS & ELECTRIC CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19305D852	List: 05000318/LER-1980-018, Forwards LER 80-018/03L-0 05000318/LER-1980-018-03, /03L-0:on 800311,during Routine Insp Tour,Watch Stander Noticed Leak Weld on 23 Charging Pump Suction Relief Valve Causing Degradation of Sys Designed to Contain Radioactive Fluid.Caused by vibration-induced Metal Fatigue
References
NUDOCS 8004150624
Download: ML19305D851 (1)
v • d • e

LER-1980-018, Forwards LER 80-018/03L-0

Event date:
Report date:
3181980018R00 - NRC Website
v • d • e

text

_____

T BALTIMORE G AS AND ELECTRIC COMPANY P.O. B O X 147 5 B ALTIMOR E, M A RYLAN D 21203 ELECTRIC PRODUCTION DEPARTMENT CALVERT CLIFFS NUCLEAR POWER PLANT LUSBY. M ARYLAND 20657 April 10,1980 Mr. Boyce H. Grier, Director Docket No.

50-318 Office of Inspection & Enforcement License No. DPR-69 U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406

Dear Mr. Grier:

Per Technical Specification 6.9.1.9.b, please find attached the thirty-day report for LER 80-18/3L.

Should you have any questions regarding this report, we would be pleased to discuss them with you.

Very truly yours, ph-L. B. Russell Chief Engineer LBR/DEH/g1a Attachment cc:

Director, Office of Management Infomation and Program Control Messrs. A. E. Lundvall, Jr.

J. B. Bullock i

W I 8004150624

Licensee Event Report

Calvert Cliffs

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
05000317/LER-1980-001, Forwards LER 80-001/03L-0	Forwards LER 80-001/03L-0
05000317/LER-1980-001-03, /03L-0:on 800104,high Pressure Safety Injection Loop 12A Stop Would Not Move to Throttled Position.Caused by Loose Termination on One Electrical Lead Terminating at Valve Torque Switch.Terminal Screw Tightened	/03L-0:on 800104,high Pressure Safety Injection Loop 12A Stop Would Not Move to Throttled Position.Caused by Loose Termination on One Electrical Lead Terminating at Valve Torque Switch.Terminal Screw Tightened
05000318/LER-1980-001, Forwards LER 80-001/03L-0	Forwards LER 80-001/03L-0
05000318/LER-1980-001-03, /03L-0:on 800225,although Low Pressure Safety Injection Pump 21 Was Placed Out of Svc for Maint, Containment Spray Pump 21 Was Disassembled.Caused by Verbal Communication Error	/03L-0:on 800225,although Low Pressure Safety Injection Pump 21 Was Placed Out of Svc for Maint, Containment Spray Pump 21 Was Disassembled.Caused by Verbal Communication Error
05000318/LER-1980-002-03, /03L-0:on 800107,refueling Water Tank Narrow Range Level Indicator Was in Alarm W/Low Level,But Instrument Did Not Indicate Alarm Conditions.Caused by Faulty Indicator Alarm light-emitting Diode.Diode Replaced	/03L-0:on 800107,refueling Water Tank Narrow Range Level Indicator Was in Alarm W/Low Level,But Instrument Did Not Indicate Alarm Conditions.Caused by Faulty Indicator Alarm light-emitting Diode.Diode Replaced
05000318/LER-1980-002, Forwards LER 80-002/03L-0	Forwards LER 80-002/03L-0
05000317/LER-1980-002-04, /04T-0:on 800322,instantaneous Hourly Average for Condenser Temp Rise Observed in Excess of Tech Spec Limit. Caused by Operator Inattention to Temp Rise Across Condenser & Environ Conditions	/04T-0:on 800322,instantaneous Hourly Average for Condenser Temp Rise Observed in Excess of Tech Spec Limit. Caused by Operator Inattention to Temp Rise Across Condenser & Environ Conditions
05000317/LER-1980-002, Forwards LER 80-002/04T-0	Forwards LER 80-002/04T-0
05000317/LER-1980-003-03, /03L-0:on 800108,during Routine Containment Air Lock Surveillance,Emergency Escape Lock Leakage Found Greater than Allowed.Caused by Excessive Leaking of Packing Glands for Doors Handwheels.Packing Tightened	/03L-0:on 800108,during Routine Containment Air Lock Surveillance,Emergency Escape Lock Leakage Found Greater than Allowed.Caused by Excessive Leaking of Packing Glands for Doors Handwheels.Packing Tightened
05000317/LER-1980-003, Forwards LER 80-003/03L-0	Forwards LER 80-003/03L-0
05000318/LER-1980-003-03, /03L-0:on 800110,repairs to Number 21 Diesel Generator Jacket Coolant Sys Required Diesel Be Out of Svc. Caused by Leaking Gasket on Jacket Cooling Water Discharge Header.Leak Located & Repaired	/03L-0:on 800110,repairs to Number 21 Diesel Generator Jacket Coolant Sys Required Diesel Be Out of Svc. Caused by Leaking Gasket on Jacket Cooling Water Discharge Header.Leak Located & Repaired
05000318/LER-1980-003, Forwards LER 80-003/03L-0	Forwards LER 80-003/03L-0
05000317/LER-1980-004, Forwards LER 80-004/03L-0	Forwards LER 80-004/03L-0
05000317/LER-1980-004-03, /03L-0:on 800110,low Flow Alarm Received for Containment Particulate & Gaseous Radiation Monitor Sys. Caused by Gasket Leakage at Particulate Detector Sample Psig.Gaskets Replaced & Flow Restored to Normal	/03L-0:on 800110,low Flow Alarm Received for Containment Particulate & Gaseous Radiation Monitor Sys. Caused by Gasket Leakage at Particulate Detector Sample Psig.Gaskets Replaced & Flow Restored to Normal
05000318/LER-1980-004-03, /03L-0:on 800121,during Steady State Operation, Received Indication of Several Spurious Loss of Load Trips on Channel B.Cause of Event Unknown.Troubleshooting Revealed Electrical Noise on Input Leads	/03L-0:on 800121,during Steady State Operation, Received Indication of Several Spurious Loss of Load Trips on Channel B.Cause of Event Unknown.Troubleshooting Revealed Electrical Noise on Input Leads
05000318/LER-1980-004, Forwards LER 80-004/03L-0	Forwards LER 80-004/03L-0
05000318/LER-1980-005, Forwards LER 80-005/03L-0	Forwards LER 80-005/03L-0
05000318/LER-1980-005-03, /03L-0:on 800122,five Channel B Trip Units Were Bypassed Due to Spurious High Power Levels.Caused by Noise from Excore Nuclear Instrument Upper Subchannel Detector. Troubleshooting Planned for Next Cold Shutdown	/03L-0:on 800122,five Channel B Trip Units Were Bypassed Due to Spurious High Power Levels.Caused by Noise from Excore Nuclear Instrument Upper Subchannel Detector. Troubleshooting Planned for Next Cold Shutdown
05000317/LER-1980-005, Forwards LER 80-005/03L-0	Forwards LER 80-005/03L-0
05000317/LER-1980-005-03, /03L-0:on 800325,during Normal Operation,Control Room Air Conditioning Unit 12 Tripped.Caused by Failure of Diaphragm on Unipressure Valve.Valve Replaced & Unit Returned to Svc	/03L-0:on 800325,during Normal Operation,Control Room Air Conditioning Unit 12 Tripped.Caused by Failure of Diaphragm on Unipressure Valve.Valve Replaced & Unit Returned to Svc
05000317/LER-1980-006, Forwards LER 80-006/03L-0	Forwards LER 80-006/03L-0
05000317/LER-1980-006-03, /03L-0:on 800103,while Performing Routine Surveillance Test,Control Element Assembly 60 Was Dropped Into Core.Cause Unknown.All Parameters Found Normal & No Problems Encountered.No Further Action Anticipated	/03L-0:on 800103,while Performing Routine Surveillance Test,Control Element Assembly 60 Was Dropped Into Core.Cause Unknown.All Parameters Found Normal & No Problems Encountered.No Further Action Anticipated
05000318/LER-1980-006, Forwards LER 80-006/03L-0	Forwards LER 80-006/03L-0
05000318/LER-1980-006-03, /03L-0:on 800126,during Steady State Operation, Reactor Protective Sys Channel a High Power,Low Flow,Axial Flux Offset & Thermal Margin/Low Pressure Trip Units Bypassed for Corrective Maint.Meter Input Jacks Cleaned	/03L-0:on 800126,during Steady State Operation, Reactor Protective Sys Channel a High Power,Low Flow,Axial Flux Offset & Thermal Margin/Low Pressure Trip Units Bypassed for Corrective Maint.Meter Input Jacks Cleaned
05000317/LER-1980-007-01, /01X-0:on 800129,while Conducting Core Flush, Emergency Relief Valve RC-404 Opened.Apparently Caused by High Pressure Signal from Overpressure in Protection Circuit.Valve Shut W/Manual Override	/01X-0:on 800129,while Conducting Core Flush, Emergency Relief Valve RC-404 Opened.Apparently Caused by High Pressure Signal from Overpressure in Protection Circuit.Valve Shut W/Manual Override
05000318/LER-1980-007, Forwards LER 80-007/03L-0	Forwards LER 80-007/03L-0
05000318/LER-1980-007-03, /03L-0:on 800130,while Performing Routine Surveillance Testing,Discovered Control Element Assembly 54 Would Not Drive Down Electrically.Cause Not Known.Rod Became Operable During Investigation of Rod Circuitry	/03L-0:on 800130,while Performing Routine Surveillance Testing,Discovered Control Element Assembly 54 Would Not Drive Down Electrically.Cause Not Known.Rod Became Operable During Investigation of Rod Circuitry
05000317/LER-1980-007, Forwards LER 80-007/01T-0	Forwards LER 80-007/01T-0
05000317/LER-1980-008, Forwards LER 80-008/03L-0	Forwards LER 80-008/03L-0
05000317/LER-1980-008-03, /03L-0:on 800126,while Cooling Down for Scheduled Outage,Survey Technician Discovered Steam Blowing from 11A Reactor Coolant Pump.Sensing Line lPDT-123A Had through-wall Leak.Caused by Friction of Sensing Line W/Another Pipe	/03L-0:on 800126,while Cooling Down for Scheduled Outage,Survey Technician Discovered Steam Blowing from 11A Reactor Coolant Pump.Sensing Line lPDT-123A Had through-wall Leak.Caused by Friction of Sensing Line W/Another Pipe
05000318/LER-1980-008-03, /03L-0:on 800125,containment Spray Header 22 Was Isolated.Caused by Need to Repair Shutdown Heat Exchanger Inlet Cross Connect Valve.New Packing Installed	/03L-0:on 800125,containment Spray Header 22 Was Isolated.Caused by Need to Repair Shutdown Heat Exchanger Inlet Cross Connect Valve.New Packing Installed
05000318/LER-1980-008, Forwards LER 80-008/03L-0	Forwards LER 80-008/03L-0
05000318/LER-1980-009-03, /03L-0:on 800131,while Conducting Routine Test, Control Element Assembly (CEA) 32 Dropped Into Core.Cause Unknown.Technician Will Be Assigned During Next STP 0-29 to Monitor Operating Parameters of All CEAs on real-time Basi	/03L-0:on 800131,while Conducting Routine Test, Control Element Assembly (CEA) 32 Dropped Into Core.Cause Unknown.Technician Will Be Assigned During Next STP 0-29 to Monitor Operating Parameters of All CEAs on real-time Basis
05000318/LER-1980-009, Forwards LER 80-009/03L-0	Forwards LER 80-009/03L-0
05000317/LER-1980-009, Forwards LER 80-009/03L-0	Forwards LER 80-009/03L-0
05000317/LER-1980-009-03, /03L-0:on 800201,during Surveillance Testing, Discovered Hose for One of Two Containment Elevator Hose Stations Missing.Caused by Work Group Using Fire Sys for Cleaning Purposes on Elevation of Containment	/03L-0:on 800201,during Surveillance Testing, Discovered Hose for One of Two Containment Elevator Hose Stations Missing.Caused by Work Group Using Fire Sys for Cleaning Purposes on Elevation of Containment
05000318/LER-1980-010, Forwards LER 80-010/03L-0	Forwards LER 80-010/03L-0
05000318/LER-1980-010-03, /03L-0:on 800224,during Surveillance Testing, Control Element Assemblies 31 & 34 Dropped Into Core.Caused by Fault in Timer Module.Module Replaced	/03L-0:on 800224,during Surveillance Testing, Control Element Assemblies 31 & 34 Dropped Into Core.Caused by Fault in Timer Module.Module Replaced
05000318/LER-1980-011, Forwards Updated LER 80-011/01X-1	Forwards Updated LER 80-011/01X-1
05000318/LER-1980-011-01, Diesel Generator 21 Failed to Achieve 10-s Rated Speed,Rendering Low Pressure Safety Injection Pump 22 Inoperable.Caused by Slow Response of Diesel Generator Governor.Governor Replaced	Diesel Generator 21 Failed to Achieve 10-s Rated Speed,Rendering Low Pressure Safety Injection Pump 22 Inoperable.Caused by Slow Response of Diesel Generator Governor.Governor Replaced
05000317/LER-1980-011-03, W/Rcs at 130 Degrees & 250 Psia,Shutdown Cooling Suction Header Relief Lifted & Failed to Reset.Caused by Personnel Error.Valve Reset	W/Rcs at 130 Degrees & 250 Psia,Shutdown Cooling Suction Header Relief Lifted & Failed to Reset.Caused by Personnel Error.Valve Reset
05000317/LER-1980-011, Forwards Updated LER 80-011/03X-1	Forwards Updated LER 80-011/03X-1
05000317/LER-1980-012, Forwards LER 80-012/03L-0	Forwards LER 80-012/03L-0
05000317/LER-1980-012-03, /03L-0:on 800211,while Performing Routine Surveillance Test,Control Element Assembly (CEA) 35 Dropped Into Core.Cause Unknown.Technician Will Be Assigned to Monitor Operating Parameter of All CEAs During Next STP	/03L-0:on 800211,while Performing Routine Surveillance Test,Control Element Assembly (CEA) 35 Dropped Into Core.Cause Unknown.Technician Will Be Assigned to Monitor Operating Parameter of All CEAs During Next STP
05000318/LER-1980-012-03, /03L-0:on 800219,during Routine Surveillance,Small Leak Discovered on Charging Pump Common Suction Header Relief Valve.Caused by Vibration Induced Metal Fatigue in heat-affected Zone of Welded Penetration in Header	/03L-0:on 800219,during Routine Surveillance,Small Leak Discovered on Charging Pump Common Suction Header Relief Valve.Caused by Vibration Induced Metal Fatigue in heat-affected Zone of Welded Penetration in Header
05000318/LER-1980-012, Forwards LER 80-012/03L-0	Forwards LER 80-012/03L-0
05000318/LER-1980-013-03, /03L-0:on 800303,channel Zf Pressure Input Signal for Steam Generator Isolation 22 Was Bypassed.Caused by Signal Isolater 2-E/E-1023C Being Out of Calibr Due to Nonlinear Response	/03L-0:on 800303,channel Zf Pressure Input Signal for Steam Generator Isolation 22 Was Bypassed.Caused by Signal Isolater 2-E/E-1023C Being Out of Calibr Due to Nonlinear Response
05000318/LER-1980-013, Forwards LER 80-013/03L-0	Forwards LER 80-013/03L-0
05000317/LER-1980-013-03, During Surveillance Test, Channel D Containment High Pressure Setpoint Less Conservative than Tech Specs.Caused by Failed Signal Isolator 1-E/E-5313D.Instrument Returned for Repair	During Surveillance Test, Channel D Containment High Pressure Setpoint Less Conservative than Tech Specs.Caused by Failed Signal Isolator 1-E/E-5313D.Instrument Returned for Repair
05000317/LER-1980-013, Forwards Updated LER 80-013/03X-1	Forwards Updated LER 80-013/03X-1
... further results

05000318/LER-1980-018, Forwards LER 80-018/03L-0

text

Dear Mr. Grier:

Navigation menu

Search