Forwards LER 80-143/03L-0
Person / Time
ML19340B849
Site:	Hatch
Issue date:	11/04/1980
From:	Manry M GEORGIA POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19340B850	List: 05000366/LER-1980-143, Forwards LER 80-143/03L-0 05000366/LER-1980-143-03, /03L-0:on 801015,while Performing HNP-1-5279,main Steam Line Pressure switch,2B21-N015B Tripped at 315 Psig. Caused by Setpoint Drift.Switch Calibr Per HNP-2-5279 & Functionally Tested Per HNP-2-3105
References
PM-80-1085, NUDOCS 8011120445
Download: ML19340B849 (1)
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LER-1980-143, Forwards LER 80-143/03L-0

Event date:
Report date:
3661980143R00 - NRC Website
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text

Gentgra Poser Cornpany Post Othce Box "42 Daoy Goarga 315 t 3 Tc!cchonc9t?367 7781 912 537 9444 M,

'5IIjCN

-..... m w,j r Georgia Power Edwini. Hatch Nuclear Plant

!!v. < 4:!% 1n o e s tit. 9 Jo - r :

353 G / 12 Rd 9 10 flovember 4 PM-80-1085, 1980

...1 bERVICES L

'-4 Cli PLANT E. I. HATCH Licensee Event Report Docket No. 50-366 United States Nuclear Regulatory Commission Office of Inspection and Enforcement Region II Suite 31000 101 Marietta Street Atlanta, Georgia 30303 ATTENTION:

Mr. Jares P. O'Reilly Pursuant to Section 6.9.1.9.b of Hatch Unit II Technical Specifications, please find attached Reportable Occurrence Report No. 50-366/1980-143 Plant Manager l'J4/RTN/mla xc:

J. H. Miller, Jr.

R. J. Kelly W. A. Widner J. T. Beckham, Jr.

C. L. Coggin R. D. Baker Control Room File son 12045 g

Licensee Event Report

Hatch

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		Reporting criterion
05000321/LER-1980-001-01, /01T-0:on 800103,while Performing Maint on RHR LPCI Injection Valve,Clevis Pin Found Missing from Strut on Drywell Penetration Restraint.Caused by Improper Installation.New Clevis Pin Installed	/01T-0:on 800103,while Performing Maint on RHR LPCI Injection Valve,Clevis Pin Found Missing from Strut on Drywell Penetration Restraint.Caused by Improper Installation.New Clevis Pin Installed
05000366/LER-1980-001, Forwards LER 80-001/03L-0	Forwards LER 80-001/03L-0
05000366/LER-1980-001-03, /03L-0:on 800102,while Performing Narrow Range Torus Water Level Functional Test & Calibr,Level Transmitter 2T48-N021B Found Out of Tolerance.Caused by Range Drift. Transmitter Recalibr & Returned to Svc	/03L-0:on 800102,while Performing Narrow Range Torus Water Level Functional Test & Calibr,Level Transmitter 2T48-N021B Found Out of Tolerance.Caused by Range Drift. Transmitter Recalibr & Returned to Svc
05000321/LER-1980-001, Forwards LER 80-001/01T-0	Forwards LER 80-001/01T-0
05000321/LER-1980-002-03, /03L-0:on 800112,while Performing HNP-1-3655,fan lT46-C001B Would Not Meet Flow Requirements Per Tech Specs. Ten Days Later,While Venting Drywell Per HNP-1-1500,flow Did Not Meet Tech Specs.Equipment Recalibr	/03L-0:on 800112,while Performing HNP-1-3655,fan lT46-C001B Would Not Meet Flow Requirements Per Tech Specs. Ten Days Later,While Venting Drywell Per HNP-1-1500,flow Did Not Meet Tech Specs.Equipment Recalibr
05000321/LER-1980-002, Forwards LER 80-002/03L-0	Forwards LER 80-002/03L-0
05000366/LER-1980-002, Forwards LER 80-002/01T-0	Forwards LER 80-002/01T-0
05000366/LER-1980-002-01, /01T-0:on 800128,during Cold Shutdown,Ae Notified Util That Single Mode Failure Existed for Torus Gravity Fill Isolation Valve 2G51-F013.Caused by Design Deficiency. Standing Order Issued	/01T-0:on 800128,during Cold Shutdown,Ae Notified Util That Single Mode Failure Existed for Torus Gravity Fill Isolation Valve 2G51-F013.Caused by Design Deficiency. Standing Order Issued
05000366/LER-1980-003, Forwards LER 80-003/03L-0	Forwards LER 80-003/03L-0
05000366/LER-1980-003-03, /03L-0:on 800117,while Applying Equalizing Charge to 125/250-volt Dc Station Svc Batteries,Hpci Automatic Flow Control Power Inverter Tripped.Caused by Instrument Drift. Instrument Recalibr Satisfactorily	/03L-0:on 800117,while Applying Equalizing Charge to 125/250-volt Dc Station Svc Batteries,Hpci Automatic Flow Control Power Inverter Tripped.Caused by Instrument Drift. Instrument Recalibr Satisfactorily
05000321/LER-1980-003-03, While Performing RHR Valve Operability Procedure,Outboard Shutdown Cooling Isolation Valve F008 Opened in 25.8-S.Caused by Normal Wear & Human Reaction Time.Valve Operator Adjusted	While Performing RHR Valve Operability Procedure,Outboard Shutdown Cooling Isolation Valve F008 Opened in 25.8-S.Caused by Normal Wear & Human Reaction Time.Valve Operator Adjusted
05000321/LER-1980-003, Forwards Revised LER 80-003/03X-1	Forwards Revised LER 80-003/03X-1
05000321/LER-1980-004, Forwards LER 80-004/03L-0	Forwards LER 80-004/03L-0
05000321/LER-1980-004-03, /03L-0:on 800106,during Startup Mode,Main Steam Line Inboard Isolation Drain Valve Failed in mid-position. Caused by Failure of Valve Motor Winding.Motor Replaced & Valve Returned to Operable Status	/03L-0:on 800106,during Startup Mode,Main Steam Line Inboard Isolation Drain Valve Failed in mid-position. Caused by Failure of Valve Motor Winding.Motor Replaced & Valve Returned to Operable Status
05000366/LER-1980-004-03, /03L-0:on 800118,during Steady State Power Operation Hydrogen Recombiner Inlet Valve 2T49-F003A Did Not Open.Caused by a Failed Torque Switch.Sys Returned to Operation After Switch Was Replaced	/03L-0:on 800118,during Steady State Power Operation Hydrogen Recombiner Inlet Valve 2T49-F003A Did Not Open.Caused by a Failed Torque Switch.Sys Returned to Operation After Switch Was Replaced
05000366/LER-1980-004, Forwards LER 80-004/03L-0	Forwards LER 80-004/03L-0
05000321/LER-1980-005, Forwards LER 80-005/03L-0	Forwards LER 80-005/03L-0
05000321/LER-1980-005-03, /03L-0:on 800109,w/reactor Mode Switch in Run Mode,Discovered That Surveillance Procedure HNP-1-3007, Turbine Control Valve Fast Closure,Was Not Performed in Grace Period.Caused by Personnel Error	/03L-0:on 800109,w/reactor Mode Switch in Run Mode,Discovered That Surveillance Procedure HNP-1-3007, Turbine Control Valve Fast Closure,Was Not Performed in Grace Period.Caused by Personnel Error
05000366/LER-1980-005, Forwards LER 80-005/03L-0	Forwards LER 80-005/03L-0
05000366/LER-1980-005-03, /03L-0:on 800119,during Power Operation,Tech Specs 4.8.1.1.1.a & 4.8.1.1.2a4 for Electrical Power Sources Were Not Performed within 1-h.Caused by Personnel Misinterpretation of Tech Spec Requirements	/03L-0:on 800119,during Power Operation,Tech Specs 4.8.1.1.1.a & 4.8.1.1.2a4 for Electrical Power Sources Were Not Performed within 1-h.Caused by Personnel Misinterpretation of Tech Spec Requirements
05000321/LER-1980-006-03, /03L-0:on 800113,one Standby Gas Treatment Sys Rendered Inoperable W/Both Units in Power Operation.Unit Not Proven Operable within Required 4-h.Caused by Inability to Prove Filter Train Operable within 4-h	/03L-0:on 800113,one Standby Gas Treatment Sys Rendered Inoperable W/Both Units in Power Operation.Unit Not Proven Operable within Required 4-h.Caused by Inability to Prove Filter Train Operable within 4-h
05000321/LER-1980-006, Forwards LER 80-006/03L-0	Forwards LER 80-006/03L-0
05000321/LER-1980-007-03, /03L-0:on 800114,while Testing Standby Svc Water Pump,Pump Would Not Meet Criteria.Caused by Disengagement of Pump First Stage Impeller Lock Collet.Lock Collet Replaced & Pump Reinstalled	/03L-0:on 800114,while Testing Standby Svc Water Pump,Pump Would Not Meet Criteria.Caused by Disengagement of Pump First Stage Impeller Lock Collet.Lock Collet Replaced & Pump Reinstalled
05000321/LER-1980-007, Forwards LER 80-007/03L-0	Forwards LER 80-007/03L-0
05000366/LER-1980-007-01, /01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift	/01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift
05000366/LER-1980-007, Forwards LER 80-007/01T-0	Forwards LER 80-007/01T-0
05000366/LER-1980-008-03, While Increasing Reactor Power by Rod Withdrawal,Operator Noticed Rod Select Matrix Backlighted & Rod Sequence Control Sys Not Initiating Rod Blocks Properly.Caused by Design Change	While Increasing Reactor Power by Rod Withdrawal,Operator Noticed Rod Select Matrix Backlighted & Rod Sequence Control Sys Not Initiating Rod Blocks Properly.Caused by Design Change
05000366/LER-1980-008, Forwards LER 80-008/03L-1	Forwards LER 80-008/03L-1
05000321/LER-1980-008-03, /03L-0:on 800115,during Steady State Power Operation,Secondary Containment Integrity Violated When Personnel Opened 164-ft Elevation Reactor Bldg & Turbine Bldg Airlock Doors Simultaneously.Procedure Revised	/03L-0:on 800115,during Steady State Power Operation,Secondary Containment Integrity Violated When Personnel Opened 164-ft Elevation Reactor Bldg & Turbine Bldg Airlock Doors Simultaneously.Procedure Revised
05000321/LER-1980-008, Forwards LER 80-008/03L-0	Forwards LER 80-008/03L-0
05000366/LER-1980-009-03, /03L-0:on 800130,while Performing Procedure HNP-2-33-3,HPCI Min Flow Valve 2E41-F012 Failed to Close. Caused by Sticking Switch Contacts on Flow Switch 2E41-N006. Switch Contacts Cleaned & Procedure HNP-2-3303 Performed	/03L-0:on 800130,while Performing Procedure HNP-2-33-3,HPCI Min Flow Valve 2E41-F012 Failed to Close. Caused by Sticking Switch Contacts on Flow Switch 2E41-N006. Switch Contacts Cleaned & Procedure HNP-2-3303 Performed
05000321/LER-1980-009-03, /03L-0:on 800118,during Normal Operation,Drywell/ Torus Temp Recorder 1T47-R611 Found Stamping Erratically, Making Drywall & Torus Air Temps & Water Temp Difficult to Ascertain.Caused by Failure of Microswitch.Switch Replace	/03L-0:on 800118,during Normal Operation,Drywell/ Torus Temp Recorder 1T47-R611 Found Stamping Erratically, Making Drywall & Torus Air Temps & Water Temp Difficult to Ascertain.Caused by Failure of Microswitch.Switch Replaced
05000366/LER-1980-009, Forwards LER 80-009/03L-0	Forwards LER 80-009/03L-0
05000321/LER-1980-010-03, /03L-0:on 800118,during Normal Operation While Performing Standby Liquid Control Pump Operability Test & Relief Valve Test,Pump a Discharge Relief Valve 1C41-F029A Operated at 1,225 Psig.Caused by Setpoint Drift.Valve Reset	/03L-0:on 800118,during Normal Operation While Performing Standby Liquid Control Pump Operability Test & Relief Valve Test,Pump a Discharge Relief Valve 1C41-F029A Operated at 1,225 Psig.Caused by Setpoint Drift.Valve Reset
05000321/LER-1980-010, Forwards LER 80-010/03L-0	Forwards LER 80-010/03L-0
05000366/LER-1980-010, Forwards LER 80-010/03L-0	Forwards LER 80-010/03L-0
05000366/LER-1980-010-03, /03L-0:on 800131,during Reactor Startup,At 58% Power,Max Total Peaking Factor Was Calculated at 3.0 Compared to Design Value of 2.38.Caused by Lower than Normal Xenon Distribution During Startup	/03L-0:on 800131,during Reactor Startup,At 58% Power,Max Total Peaking Factor Was Calculated at 3.0 Compared to Design Value of 2.38.Caused by Lower than Normal Xenon Distribution During Startup
05000321/LER-1980-011-03, /03L-0:on 800120,while at Steady State Power, torus-to-drywell Differential Pressure recorder,LT48-R631B Had Low Reading.Cause Not Stated	/03L-0:on 800120,while at Steady State Power, torus-to-drywell Differential Pressure recorder,LT48-R631B Had Low Reading.Cause Not Stated
05000366/LER-1980-011-03, /03L-0:on 800202,while Performing Reactor Core Isolation Cooling Shutdown Flow Test,Power Inverter for Remote Flow Control Loop Found to Be Tripped.Caused by Defective Input Filter Capacitors	/03L-0:on 800202,while Performing Reactor Core Isolation Cooling Shutdown Flow Test,Power Inverter for Remote Flow Control Loop Found to Be Tripped.Caused by Defective Input Filter Capacitors
05000321/LER-1980-011, Forwards LER 80-011/03L-0	Forwards LER 80-011/03L-0
05000366/LER-1980-012-03, /03L-0:on 800214,while at Full Power,Rhr & Plant Svc Water Min Flow Line Found to Be Inadequately Supported. Caused by Design Deficiency.Design Change Request & Maint Request Implemented to Add Supports	/03L-0:on 800214,while at Full Power,Rhr & Plant Svc Water Min Flow Line Found to Be Inadequately Supported. Caused by Design Deficiency.Design Change Request & Maint Request Implemented to Add Supports
05000321/LER-1980-012, Forwards LER 80-012/03L-0	Forwards LER 80-012/03L-0
05000366/LER-1980-012, Forwards LER 80-012/03L-0	Forwards LER 80-012/03L-0
05000321/LER-1980-012-03, /03L-0:on 800122,while Reactor Core Isolation Cooling Sys Was Tagged Out for Maint,Hpci Was Found Inoperable,Requiring Orderly Shutdown.Caused by Leak in Line to HPCI Booster Pump Discharged Pressure Gauge	/03L-0:on 800122,while Reactor Core Isolation Cooling Sys Was Tagged Out for Maint,Hpci Was Found Inoperable,Requiring Orderly Shutdown.Caused by Leak in Line to HPCI Booster Pump Discharged Pressure Gauge
05000321/LER-1980-013, Forwards Updated LER 80-013/03X-1	Forwards Updated LER 80-013/03X-1
05000321/LER-1980-013-03, Reactor Recirculation Pump a Tripped Causing Power Reduction.Caused by Electrical Short Circuit Due to Steam Leak in Drywell.Terminal Board Replaced & Tested	Reactor Recirculation Pump a Tripped Causing Power Reduction.Caused by Electrical Short Circuit Due to Steam Leak in Drywell.Terminal Board Replaced & Tested
05000366/LER-1980-013-03, /03L-0:on 800203,while Maint Was Performed on 2082-K002 Static Inverter,Emergency Control Transfer Switch Was Placed in Emergency Position.Reactor Core Isolation Cooling Was Rendered Inoperable.Caused by Personnel Error	/03L-0:on 800203,while Maint Was Performed on 2082-K002 Static Inverter,Emergency Control Transfer Switch Was Placed in Emergency Position.Reactor Core Isolation Cooling Was Rendered Inoperable.Caused by Personnel Error
05000366/LER-1980-013, Forwards LER 80-013/03L-0	Forwards LER 80-013/03L-0
05000366/LER-1980-014, Forwards LER 80-014/03L-0	Forwards LER 80-014/03L-0
05000366/LER-1980-014-03, /03L-0:on 800204,while Performing HNP-2-3054, Average Power Range Monitor C Failed.Caused by Instrument Drift.Instrument Adjusted Per Procedure & Returned to Svc	/03L-0:on 800204,while Performing HNP-2-3054, Average Power Range Monitor C Failed.Caused by Instrument Drift.Instrument Adjusted Per Procedure & Returned to Svc
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05000366/LER-1980-143, Forwards LER 80-143/03L-0

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