05000455/LER-1986-001, Errata to LER 86-001-00,incorporating Page 4 Inadvertently Omitted from Original LER Re Crosby Relief Valve JO-25WR

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Errata to LER 86-001-00,incorporating Page 4 Inadvertently Omitted from Original LER Re Crosby Relief Valve JO-25WR
Person / Time
ML20210T961
Site:	Byron
Issue date:	02/06/1987
From:	Querio R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-87-0173, BYRON-87-173, LER-86-001-ERR, LER-86-1-ERR, NUDOCS 8702180352
Download: ML20210T961 (2)
v • d • e

LER-1986-001, Errata to LER 86-001-00,incorporating Page 4 Inadvertently Omitted from Original LER Re Crosby Relief Valve JO-25WR

Event date:
Report date:
4551986001R00 - NRC Website
v • d • e

text

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,.9-LICENSEE EVENT REPORT'<LER) TEXT CONTINUATION

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FACILITY NAME (1)

DOCKET NUMBER (2)

- LER NUMBER f6)

Pace (1)

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Year

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Sequential

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Revision f)//f Number

/

Number I

Byron. Unit 2-0 i S I 0 l 0 1 0 1 4l El 5 al 6-01 0 l 1 01 0 14 0F 01 4 j

t TEXT Energy Industry Identification System (EIIS) codes are identified in the text as [xx]

F. PREVIOUS OCCURRENCES

LER NUMBER TITLE NONE G.

COMPONENT FAILURE DATA

MANUFACTURER NOMENCLATURE MODEL NUMBER MFG PART NUPSER f

Crosby Reitef Valve J0-25WR N57027-00-0008 1

1 l

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8702180352 870206 g

PDR ADOCK 05000455 1

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, [* % - Commonwealth Edison

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) Byron NucitarSt1 tion

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Byron, Illinois 61010 February 6,1987 LTR:

BYRON 87-0173 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Dear Sir:

It has come to our attention that some of the distributees of Licensee Event Report 455-86-001-00 did not receive page four of the report. Please check your copy and insert the attached if page four is missing. Thank you.

Very truly yours, l

~

ff R. E. Querio Station Manager Byron Nuclear Power Station REQ /JL/bf Attachment ec:

J. G. Keppler NRC Region III Administrator J. Ilinds, NRC Resident Inspector INPO Record Center CECO Distribution List

43/02 U

Y

,t

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
05000454/LER-1986-001-06, :on 860116,reactor Trip Occurred Due to Ambiguities in Temporary Procedure.Caused by Insufficient Detail in Procedure to Distinguish Between Two Nearly Identical Auto Shunt Trip Test Panels	on 860116,reactor Trip Occurred Due to Ambiguities in Temporary Procedure.Caused by Insufficient Detail in Procedure to Distinguish Between Two Nearly Identical Auto Shunt Trip Test Panels	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)(x) 10 CFR 50.73(a)(2)
05000455/LER-1986-001, Errata to LER 86-001-00,incorporating Page 4 Inadvertently Omitted from Original LER Re Crosby Relief Valve JO-25WR	Errata to LER 86-001-00,incorporating Page 4 Inadvertently Omitted from Original LER Re Crosby Relief Valve JO-25WR
05000455/LER-1986-001-11, :on 861120,component Cooling Pumps 2A & 2B Tripped Due to Pressure Spike Caused by Shutdown of Pump 2A. Event Caused by Personnel Error in Setting Relief Valve. Valve Repaired & Reinstalled	on 861120,component Cooling Pumps 2A & 2B Tripped Due to Pressure Spike Caused by Shutdown of Pump 2A. Event Caused by Personnel Error in Setting Relief Valve. Valve Repaired & Reinstalled	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-002, :on 860126 & 0204,w/plant in Mode 1,process Radiation Monitor OPR31J (Main Control Room Outside Air Intake a) Went Into Interlock Mode Due to Spike on Monitor Iodine Channel.Caused by Bad Component	on 860126 & 0204,w/plant in Mode 1,process Radiation Monitor OPR31J (Main Control Room Outside Air Intake a) Went Into Interlock Mode Due to Spike on Monitor Iodine Channel.Caused by Bad Component	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000455/LER-1986-002-10, :on 861122,digital Rod Position Indication & Bank Demand Step Counters Differed by More than 12 Steps, Requiring Opening of Reactor Trip Breakers.Caused by Defective Detector Encoder Card.Card Replaced	on 861122,digital Rod Position Indication & Bank Demand Step Counters Differed by More than 12 Steps, Requiring Opening of Reactor Trip Breakers.Caused by Defective Detector Encoder Card.Card Replaced	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-002-04, :on 860126 & 0204,control Room Ventilation Actuation Occurred Due to Process Radiation Monitor OPR31J Iodine Channel Spike.Iodine Channel High Voltage Power Supply & Circuit Boards Replaced	on 860126 & 0204,control Room Ventilation Actuation Occurred Due to Process Radiation Monitor OPR31J Iodine Channel Spike.Iodine Channel High Voltage Power Supply & Circuit Boards 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) 10 CFR 50.73(a)(2)(1)
05000455/LER-1986-003-10, :on 861216,Safety Injection Train 2B Rendered Inoperable by Closed & out-of-svc Safety Injection Pump 2B During Hot Standby (Mode 3).Caused by Cognitive Personnel Error.Mode Change Checklists Revised	on 861216,Safety Injection Train 2B Rendered Inoperable by Closed & out-of-svc Safety Injection Pump 2B During Hot Standby (Mode 3).Caused by Cognitive Personnel Error.Mode Change Checklists Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-003-01, :on 860129,reactor Trip & Auxiliary Feedwater Actuation Occurred.Caused by Grounded Conditions on Positive & Negative Poles of 125 Volt Dc Bus.Reservoir Mods & Updates to Filling Procedures Planned	on 860129,reactor Trip & Auxiliary Feedwater Actuation Occurred.Caused by Grounded Conditions on Positive & Negative Poles of 125 Volt Dc Bus.Reservoir Mods & Updates to Filling Procedures Planned	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) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-004-01, :on 860131 & 0205,outside Diameter Auxiliary Bldg Charcoal Booster Fan Automatically Started W/O Proper Signal.Caused by Failure of Westinghouse AR-3 Relay in Fan Breaker Closing Circuitry.Leads Moved	on 860131 & 0205,outside Diameter Auxiliary Bldg Charcoal Booster Fan Automatically Started W/O Proper Signal.Caused by Failure of Westinghouse AR-3 Relay in Fan Breaker Closing Circuitry.Leads Moved	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) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2)(viii)(8)
05000454/LER-1986-004-03, :on 860131 & 0205,auxiliary Charcoal Booster Fan Automatically Started W/O Receipt of Valid Start Signal. Caused by Failure of Westinghouse AR-3 Relay in Fan Breaker Closing Circuitry	on 860131 & 0205,auxiliary Charcoal Booster Fan Automatically Started W/O Receipt of Valid Start Signal. Caused by Failure of Westinghouse AR-3 Relay in Fan Breaker Closing Circuitry	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000000/LER-1986-005-03, Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points	Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points
05000454/LER-1986-005-02, :on 860129,loss of Sample Flow Alarm Occurred & on 860130,radioactive Liquid Release Started.Loss of Sample Flow Alarm Due to Sample Pump Seal Failure.Sample Pump Rebuilt	on 860129,loss of Sample Flow Alarm Occurred & on 860130,radioactive Liquid Release Started.Loss of Sample Flow Alarm Due to Sample Pump Seal Failure.Sample Pump Rebuilt	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)
05000454/LER-1986-006-02, :on 860212,control Room Ventilation Sys Train B Shifted to ESF Actuation on Signal from Control Room Air Intake Monitor ORE-PR033.Caused by Procedural Error During Monitor Filter Change.Checklist Implemented	on 860212,control Room Ventilation Sys Train B Shifted to ESF Actuation on Signal from Control Room Air Intake Monitor ORE-PR033.Caused by Procedural Error During Monitor Filter Change.Checklist Implemented	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-007, :on 860212,process Radiation Monitor 0PR34J Went Into Interlock Mode Due to Noise Spike on Monitor Gas Channel.Caused by Bad Edge Component or Connector on Motherboard.Motherboard Replaced	on 860212,process Radiation Monitor 0PR34J Went Into Interlock Mode Due to Noise Spike on Monitor Gas Channel.Caused by Bad Edge Component or Connector on Motherboard.Motherboard Replaced	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)
05000454/LER-1986-007-02, :on 860212,process Radiation Monitor OPR34J Went Into Interlock Mode Due to Noise Spike on Monitor Gas Channel.Cause of Noise Spike Unknown.Troubleshooting Being Performed to Determine Cause	on 860212,process Radiation Monitor OPR34J Went Into Interlock Mode Due to Noise Spike on Monitor Gas Channel.Cause of Noise Spike Unknown.Troubleshooting Being Performed to Determine Cause	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2)(viii)(8)
05000454/LER-1986-008, :on 860217,turbine Generator & Reactor Trips Occurred Due to Phase Differential Current Sensed by Main Transformer.Caused by Ice Buildup on Transmission Line Tower During Ice Storm.Transformer Replaced	on 860217,turbine Generator & Reactor Trips Occurred Due to Phase Differential Current Sensed by Main Transformer.Caused by Ice Buildup on Transmission Line Tower During Ice Storm.Transformer Replaced	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)(x) 10 CFR 50.73(a)(2)
05000454/LER-1986-009, :on 860222,during Cold Shutdown,Containment Vent Isolation Occurred Due to Undervoltage Condition at Radiation Monitors 1RT-AR011 & 1RT-AR012.Caused by Voltage Transient on 345 Kv Distribution Sys	on 860222,during Cold Shutdown,Containment Vent Isolation Occurred Due to Undervoltage Condition at Radiation Monitors 1RT-AR011 & 1RT-AR012.Caused by Voltage Transient on 345 Kv Distribution Sys	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)(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-1986-010-03, :on 860318,w/plant in Mode 1,main Control Room Outside Air Intake B Process Radiation Monitor OPR34J Went Into Interlock Mode Due to Loss of Sample Flow.Caused by Sample Pump Shutdown Due to Bumping Switch	on 860318,w/plant in Mode 1,main Control Room Outside Air Intake B Process Radiation Monitor OPR34J Went Into Interlock Mode Due to Loss of Sample Flow.Caused by Sample Pump Shutdown Due to Bumping Switch
05000454/LER-1986-011-02, :on 860324,main Control Room Outside Air Intake Process Radiation Monitor B Went Into Interlock Mode Due to High Vacuum Alarm.Caused by Clogged Sample Particulate Filter.Filters on Radiation Monitors Changed	on 860324,main Control Room Outside Air Intake Process Radiation Monitor B Went Into Interlock Mode Due to High Vacuum Alarm.Caused by Clogged Sample Particulate Filter.Filters on Radiation Monitors Changed	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)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)
05000454/LER-1986-012-01, :on 860327,RPI Surveillance Not Performed within 4 H.Caused by Personnel Error.Bank Demand Vs Digital RPI Surveillance Reinstated	on 860327,RPI Surveillance Not Performed within 4 H.Caused by Personnel Error.Bank Demand Vs Digital RPI Surveillance Reinstated	10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(B) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-012-02, :on 860327,4 H Surveillance of Digital Rod Position Indication Vs Bank Demand Position Indication Mistakenly Stopped.Caused by Personnel Error.More Specific Instructions on Daily Orders Instituted	on 860327,4 H Surveillance of Digital Rod Position Indication Vs Bank Demand Position Indication Mistakenly Stopped.Caused by Personnel Error.More Specific Instructions on Daily Orders Instituted	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)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-013-03, :on 860423,containment Air Lock Leakage Rate Surveillance Performed Late Due to Misapplication of Tech Spec 4.0.2.Caused by Personnel Error.Computer Program Revised to Require Testing Every 6 Months	on 860423,containment Air Lock Leakage Rate Surveillance Performed Late Due to Misapplication of Tech Spec 4.0.2.Caused by Personnel Error.Computer Program Revised to Require Testing Every 6 Months	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-014-03, :on 860512,main Control Room Outside Air Intake Process Radiation Monitor a Went Into Interlock Mode.Caused by Clogged Particulate Sample Filter.Filter Interval Changed	on 860512,main Control Room Outside Air Intake Process Radiation Monitor a Went Into Interlock Mode.Caused by Clogged Particulate Sample Filter.Filter Interval Changed	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)(x) 10 CFR 50.73(a)(2)
05000454/LER-1986-015-03, :on 860507,discovered Test Voltage for Verifying Neutron Flux Multiplication for Boron Dilution Protection Sys Incorrect.Caused by Inadequate Procedures. Interim Procedure SPP-86-71 Written	on 860507,discovered Test Voltage for Verifying Neutron Flux Multiplication for Boron Dilution Protection Sys Incorrect.Caused by Inadequate Procedures. Interim Procedure SPP-86-71 Written	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)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 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(s)(2)(i)
05000454/LER-1986-016-03, :on 860527,following Installation of Backup Electrical Power Supply,Continuous Fire Watch Inadvertently Released from Post.Caused by Personnel Error.Engineer Instructed on Fire Watch Procedures	on 860527,following Installation of Backup Electrical Power Supply,Continuous Fire Watch Inadvertently Released from Post.Caused by Personnel Error.Engineer Instructed on Fire Watch Procedures	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) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-017-03, :on 860602,both Trains of Main Control Room Ventilation Sys Inoperable.Caused by Setpoint Drift on Train a Makeup Fan & Bent Spring Release on Train B Supply Fan Breaker.Setpoint Recalibr & Spring Repaired	on 860602,both Trains of Main Control Room Ventilation Sys Inoperable.Caused by Setpoint Drift on Train a Makeup Fan & Bent Spring Release on Train B Supply Fan Breaker.Setpoint Recalibr & Spring Repaired	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)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-018-03, :on 860602,main Control Room Outside Air Intake Process Radiation Monitor a Went Into Interlock Mode. Caused by Misaligned Check Source Mechanism.Mechanism Realigned	on 860602,main Control Room Outside Air Intake Process Radiation Monitor a Went Into Interlock Mode. Caused by Misaligned Check Source Mechanism.Mechanism Realigned	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)(B) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-019-03, :on 860630,discovered That power-range Nuclear Instrumentation Channel Not Fully Tripped within 6 H of Declaring Channel Inoperable.Caused by Personnel Error. Procedures Revised	on 860630,discovered That power-range Nuclear Instrumentation Channel Not Fully Tripped within 6 H of Declaring Channel Inoperable.Caused by Personnel Error. Procedures 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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-020-02, :on 860702,RCS Leakage Exceeded Tech Specs. Caused by Failed Packing Diaphragms on Isolation Valve. Entire Valve Cut Out & Replaced	on 860702,RCS Leakage Exceeded Tech Specs. Caused by Failed Packing Diaphragms on Isolation Valve. Entire Valve Cut Out & 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-021-03, :on 860614,performance of RCS Water Inventory Balance Exceeded Tech Spec Action Statement by 1 H & 27 Minutes.Caused by Personnel Misinterpretation of Requirement.Personnel Counseled	on 860614,performance of RCS Water Inventory Balance Exceeded Tech Spec Action Statement by 1 H & 27 Minutes.Caused by Personnel Misinterpretation of Requirement.Personnel Counseled
05000454/LER-1986-022-03, :on 860703,during Required Shutdown to Mode 5 Due to Excessive RCS Unidentified Leak,Source Range Nuclear Instrumentation Channels Improperly Declared Operable.Caused by Personnel Error	on 860703,during Required Shutdown to Mode 5 Due to Excessive RCS Unidentified Leak,Source Range Nuclear Instrumentation Channels Improperly Declared Operable.Caused by Personnel Error	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)(B), Prohibited by Technical Specifications 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)(B) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-023-03, :on 860718,discovered Installation of Defective Pressurizer Safety Valve as Result of Excessive Seat Leakage on 860717.Caused by Series of Personnel Errors.Secure Storage Cages Constructed	on 860718,discovered Installation of Defective Pressurizer Safety Valve as Result of Excessive Seat Leakage on 860717.Caused by Series of Personnel Errors.Secure Storage Cages Constructed	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)(B), Prohibited by Technical Specifications 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)(1)
05000454/LER-1986-024-02, :on 860725,w/plant in Power Operation Mode 1, Main Control Room Outside Air Intake a Process Radiation Monitor Went Into Interlock Mode.Caused by Noise Spike on Monitor Particulate Channel	on 860725,w/plant in Power Operation Mode 1, Main Control Room Outside Air Intake a Process Radiation Monitor Went Into Interlock Mode.Caused by Noise Spike on Monitor Particulate Channel	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 50.72(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-1986-025-02, :on 860826,Tech Spec 3.12.1 Re Radiological Environ Monitoring Not Met.Caused by Personnel Error.Suppl to 1985 Annual Radiological Environ Operating Rept Will Be Submitted	on 860826,Tech Spec 3.12.1 Re Radiological Environ Monitoring Not Met.Caused by Personnel Error.Suppl to 1985 Annual Radiological Environ Operating Rept Will Be Submitted	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)(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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-026-01, :on 860921,actuation of Control Room Ventilation Occurred.Caused by Lightning Strike on Offsite 138 Kv Transmission Line.Mods Installed in 1985 to Reduce Undervoltage Trip Setpoint	on 860921,actuation of Control Room Ventilation Occurred.Caused by Lightning Strike on Offsite 138 Kv Transmission Line.Mods Installed in 1985 to Reduce Undervoltage Trip Setpoint	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-027-03, :on 860930,reactor Tripped Following Feedwater Isolation & Turbine Trip Due to Damaged Test Cable.Caused by Personnel Error.Damaged Cable Repaired & Temporary Cable Will Be Installed	on 860930,reactor Tripped Following Feedwater Isolation & Turbine Trip Due to Damaged Test Cable.Caused by Personnel Error.Damaged Cable Repaired & Temporary Cable Will Be Installed	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-028-02, :on 861002,reactor Manually Tripped.Caused by Defective Firing Card & Intermittent Failure of Alarm Card. Rod Drive Sys Troubleshot,Responsible Circuit Cards Replaced & Alarm Cleared	on 861002,reactor Manually Tripped.Caused by Defective Firing Card & Intermittent Failure of Alarm Card. Rod Drive Sys Troubleshot,Responsible Circuit Cards Replaced & Alarm Cleared	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-029-03, :on 861022,480-volt Breaker,Providing Overcurrent Protection for Electrical Penetration Feed to Containment Crane 1HC22G,discovered Not Tested Prior to Entry Into Mode 4.Caused by Personnel Error	on 861022,480-volt Breaker,Providing Overcurrent Protection for Electrical Penetration Feed to Containment Crane 1HC22G,discovered Not Tested Prior to Entry Into Mode 4.Caused by Personnel Error	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-030-03, :on 861023,sampling Period for Inoperable Radiation Monitor Delayed for 12 H.Caused by Personnel Error,Memo Issued Reemphasizing Notification Procedures.W/	on 861023,sampling Period for Inoperable Radiation Monitor Delayed for 12 H.Caused by Personnel Error,Memo Issued Reemphasizing Notification Procedures.W/	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)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-031-03, :on 861121,maint Re Breaking of Nonexempt ASME Code Class 3 Pressure Boundary Strainer Completed & Returned to Svc W/O Required post-maint Visual Exam.Caused by Personnel Error.Visual Exams Performed	on 861121,maint Re Breaking of Nonexempt ASME Code Class 3 Pressure Boundary Strainer Completed & Returned to Svc W/O Required post-maint Visual Exam.Caused by Personnel Error.Visual Exams Performed	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 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) 10 CFR 50.73(a)(1)(1)
05000454/LER-1986-032-02, :on 861208,ESF Response Time Surveillance Discrepancy Noted in Procedure Resulting in Violation of Tech Specs.Caused by Procedure Incorrectly Timing High Steam Pressure Rate Logic Circuitry	on 861208,ESF Response Time Surveillance Discrepancy Noted in Procedure Resulting in Violation of Tech Specs.Caused by Procedure Incorrectly Timing High Steam Pressure Rate Logic Circuitry	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-033-03, :on 861209,post-maint Visual Leak Test Not Performed,Violating Tech Spec.Caused by Defective Procedure. Project Const Now Working Under Station Nuclear Work Request Program	on 861209,post-maint Visual Leak Test Not Performed,Violating Tech Spec.Caused by Defective Procedure. Project Const Now Working Under Station Nuclear Work Request Program	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)
05000454/LER-1986-034-03, :on 861212,radiation Detector to Train B Found Defective.Detector Replaced.On 861215,discovered Leads Restored to Wrong Terminals.Caused by Personnel Error. Personnel Counseled	on 861212,radiation Detector to Train B Found Defective.Detector Replaced.On 861215,discovered Leads Restored to Wrong Terminals.Caused by Personnel Error. Personnel Counseled	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-035, :on 861217,investigation of Possible Part 21 Rept on Cooper Bessemer Ksv Series Emergency Diesel Generators Revealed Nonseismic Switches Had Been Wired Into Engine Overspeed safety-related Trip Circuit	on 861217,investigation of Possible Part 21 Rept on Cooper Bessemer Ksv Series Emergency Diesel Generators Revealed Nonseismic Switches Had Been Wired Into Engine Overspeed safety-related Trip Circuit	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 50.72(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) 10 CFR 50.73(a)(2)(1)
05000454/LER-1986-035-02, :on 861217,notice Received of Possible Part 21 Rept Re Cooper Bessemer Diesel Generators.Investigation Revealed That non-seismic Switches Wired Into Engine Overspeed.Caused by Design Error	on 861217,notice Received of Possible Part 21 Rept Re Cooper Bessemer Diesel Generators.Investigation Revealed That non-seismic Switches Wired Into Engine Overspeed.Caused by Design Error	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)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)

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