Advises That LER 91-001-00 Will Not Be Used
Person / Time
ML20079C648
Site:	Byron
Issue date:	06/18/1991
From:	Pleniewicz R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-91-0434, BYRON-91-434, LER-91-001-00, LER-91-1, NUDOCS 9106240307
Download: ML20079C648 (1)
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LER-1991-001, Advises That LER 91-001-00 Will Not Be Used

Event date:
Report date:
4551991001R00 - NRC Website
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text

) C:mm:nw alth Edison [C'

7 Byron Nucicar Station g

4450 North German Church Road

.N Dyron, Ilknois 61010 e

June 18, 1991

)

LTR DYRON 91-0434 FILE:

3.03.800 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555

Dear Sir:

For Docket No. 50.-455, Licenseo Event Report n tmber 91-001 f rom hyron Generating Station, will not be used.

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R. Plenlewict Station Manager Byron Nuclear Power Station RP/DK/cp cc A. Bert Davis, HRC Region III Administrator W.

opp, NRC Senior Resident Inspector INPO Record Center CECO Distribution List (3444M/0329M) g 0

910624030'7 910618 PDR ADOCK 05000455 S

FDR

Licensee Event Report

Byron

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		Reporting criterion
05000455/LER-1991-001, Advises That LER 91-001-00 Will Not Be Used	Advises That LER 91-001-00 Will Not Be Used
05000454/LER-1991-001-10, :on 910312 & 13,voltage Transient Occurred When 345-kV Line 0624 Tripped Open,Causing Monitors to Go Into Interlock Mode & Resulting in Engineered Safeguards Actuations.Caused by Faults on Lines	on 910312 & 13,voltage Transient Occurred When 345-kV Line 0624 Tripped Open,Causing Monitors to Go Into Interlock Mode & Resulting in Engineered Safeguards Actuations.Caused by Faults on Lines	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000455/LER-1991-002-06, :on 910311,containment Emergency Hatch Surveillance Not Performed within 72 H After Test on Hatch. on 901111,Type B LLRT Not Performed within 72 H.Caused by Procedure Deficiency.Procedures Revised	on 910311,containment Emergency Hatch Surveillance Not Performed within 72 H After Test on Hatch. on 901111,Type B LLRT Not Performed within 72 H.Caused by Procedure Deficiency.Procedures Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000455/LER-1991-002-04, :on 910311,discovered That Local Leak Rate Test on Containment Emergency Hatch Not Performed within TS Required Time of 72 H.On 901111,Type B Tests Not Performed within 72 H.Caused by Procedural Deficiency	on 910311,discovered That Local Leak Rate Test on Containment Emergency Hatch Not Performed within TS Required Time of 72 H.On 901111,Type B Tests Not Performed within 72 H.Caused by Procedural Deficiency	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1991-002-11, :on 910505,voltage Transient Occurred When Lines Momentarily Opened During Thunderstorm.Caused by Lightning from Storm.Undervoltage Setpoint for Radiation Monitors Previously Lowered	on 910505,voltage Transient Occurred When Lines Momentarily Opened During Thunderstorm.Caused by Lightning from Storm.Undervoltage Setpoint for Radiation Monitors Previously Lowered	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A)
05000455/LER-1991-003-11, :on 911026,experienced RCS Leak in Excess of TS Requirements.Caused by Failed Packing Associated w/2RC029C Valve.Packing on Subj Valve Replaced	on 911026,experienced RCS Leak in Excess of TS Requirements.Caused by Failed Packing Associated w/2RC029C Valve.Packing on Subj Valve Replaced	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000454/LER-1991-003-09, :on 910729,identified Errors in Scaling Which Could Prevent Over Temp Delta Temp (OTDT) from Initiating Reactor Trip.Caused by Deficiency in Design That Indicated How OTDT Setpoint Was to Be Scaled	on 910729,identified Errors in Scaling Which Could Prevent Over Temp Delta Temp (OTDT) from Initiating Reactor Trip.Caused by Deficiency in Design That Indicated How OTDT Setpoint Was to Be Scaled	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000454/LER-1991-004-12, :on 911016,Train B SI,1B DG & Several Other Pieces of Equipment Actuated.Caused by Cognitive Personnel Error.Procedures Will Be Revised & Addl Training Will Be Provided on Operation of Auto SI Block	on 911016,Train B SI,1B DG & Several Other Pieces of Equipment Actuated.Caused by Cognitive Personnel Error.Procedures Will Be Revised & Addl Training Will Be Provided on Operation of Auto SI Block	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000454/LER-1991-004-11, :on 911016,inadvertent Safety Injection (SI) Occurred While Resetting Status Light for Auto SI Blocked Following ESFAS Surveillance.Caused by Personnel Error. Signal Reset & Equipment Restored	on 911016,inadvertent Safety Injection (SI) Occurred While Resetting Status Light for Auto SI Blocked Following ESFAS Surveillance.Caused by Personnel Error. Signal Reset & Equipment Restored	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A)
05000455/LER-1991-004-13, :on 911030,spurious Train B Feedwater Isolation Signal Generated,Causing Tempering Line Flow Control & Downstream Isolation Valves to Close.Caused by Failure of Logic Card.Isolation Reset	on 911030,spurious Train B Feedwater Isolation Signal Generated,Causing Tempering Line Flow Control & Downstream Isolation Valves to Close.Caused by Failure of Logic Card.Isolation Reset	10 CFR 50.73(a)(1), Submit an LER 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A)
05000455/LER-1991-005-09, :on 911107,low-2 Steam Generator Level Received on Steam Generator 2A Which Initiated Reactor Trip. Caused by Difficulty in Controlling Westinghouse D-5 Steam Generator Level.Level Instrument Taps Moved	on 911107,low-2 Steam Generator Level Received on Steam Generator 2A Which Initiated Reactor Trip. Caused by Difficulty in Controlling Westinghouse D-5 Steam Generator Level.Level Instrument Taps Moved	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(4)
05000454/LER-1991-005-08, :on 911027,Mode 4 Entered W/Containment Spray Sys & ECCS Recirculation Sump Isolation Valves Inoperable. Caused by Control Room Personnel Failure.Mode Change Checklists Will Be Revised	on 911027,Mode 4 Entered W/Containment Spray Sys & ECCS Recirculation Sump Isolation Valves Inoperable. Caused by Control Room Personnel Failure.Mode Change Checklists Will Be Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000455/LER-1991-005-01, :on 900817,preoutage Mod Work Initiated W/O Proper Operability Review Due to Programmatic Deficiencies. Daily Const Work Authorization Sheet Formalized	on 900817,preoutage Mod Work Initiated W/O Proper Operability Review Due to Programmatic Deficiencies. Daily Const Work Authorization Sheet Formalized	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000454/LER-1991-006-10, :on 911114,determined That Testing of 4160 Volt ESF Bus Undervoltage Relay Circuits Inadequate.Caused by Inadequate Testing Procedures.Surveillance Procedures Will Be Revised	on 911114,determined That Testing of 4160 Volt ESF Bus Undervoltage Relay Circuits Inadequate.Caused by Inadequate Testing Procedures.Surveillance Procedures Will Be Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)

05000455/LER-1991-001, Advises That LER 91-001-00 Will Not Be Used

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Dear Sir:

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