05000304/LER-1985-028, :Not Used

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:Not Used
Person / Time
ML20195D003
Site:	Zion File:ZionSolutions icon.png
Issue date:	05/23/1986
From:	Pliml G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
LER-85-028, LER-85-28, NUDOCS 8606020042
Download: ML20195D003 (1)
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LER-1985-028, Not Used

Event date:
Report date:
3041985028R00 - NRC Website
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text

Conunonw :lth Edis:n Zion G';:n:riting Station 101 Shiloh Blvd.

Zion, Illinois 60099 Telephone 312/746-2084 May 23, 1986 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555

Dear Sir:

This is to inform you that Licensee Event Report Number 85-028-00 for Zion Unit 2 Docket 50-304 was not used.

Very truly yours,

)[

M G.

J. PEiml y

Station Manager Zion Generating Station GJP/lv cc:

J. G.

Keppler M.

Ifolzmer INPO Record Center CECO. distribution list 8606020042 860523 PDR ADOCK 05000304 fj S

Licensee Event Report

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

		Reporting criterion
05000304/LER-1985-001-01, :on 850115,diesel Generator 2B Tripped.Caused by Nonrepeatable Spurious Relay Actuation Resulting from Loose Connection or Relay Terminal.Failure Corrected During Troubleshooting Manipulation to Control Sys	on 850115,diesel Generator 2B Tripped.Caused by Nonrepeatable Spurious Relay Actuation Resulting from Loose Connection or Relay Terminal.Failure Corrected During Troubleshooting Manipulation to Control Sys
05000295/LER-1985-004, :on 850124,during Sump Valve Stroke Test PT-2B, Valves 1MOV-SI8812 a & B Failed to Reopen After Being Stroked Closed.Caused by Too Short Bypass Circuit Time.Time Reset & Tested	on 850124,during Sump Valve Stroke Test PT-2B, Valves 1MOV-SI8812 a & B Failed to Reopen After Being Stroked Closed.Caused by Too Short Bypass Circuit Time.Time Reset & Tested
05000304/LER-1985-005-01, :on 850806,discovered Svc Bus Undervoltage Start of Auxiliary Feedwater Pump Not Periodically Tested & Relays Which Start Pumps on lo-lo Steam Generator Level Not Tested for Three Steam Generators	on 850806,discovered Svc Bus Undervoltage Start of Auxiliary Feedwater Pump Not Periodically Tested & Relays Which Start Pumps on lo-lo Steam Generator Level Not Tested for Three Steam Generators
05000304/LER-1985-005-09, :on 850806,discovered That Svc Bus Undervoltage Start of steam-driven Auxiliary Feedwater Pump Not Tested Per Tech Spec Table 4.4-1.Procedure PT-5C Prepared & Will Be Placed on Surveillance Schedule by 851115	on 850806,discovered That Svc Bus Undervoltage Start of steam-driven Auxiliary Feedwater Pump Not Tested Per Tech Spec Table 4.4-1.Procedure PT-5C Prepared & Will Be Placed on Surveillance Schedule by 851115	10 CFR 50.73(a)(2)(i)
05000295/LER-1985-007-01, :on 850218,unmonitored Alternate Vent Path Created When Valve IFCV-RV85B Opened.Caused by Failure of current-to-pneumatic Pressure Converter.Procedures Now Require Valve Position Check Before Venting	on 850218,unmonitored Alternate Vent Path Created When Valve IFCV-RV85B Opened.Caused by Failure of current-to-pneumatic Pressure Converter.Procedures Now Require Valve Position Check Before Venting	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)(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)
05000304/LER-1985-008, :on 850317,while at Steady State Power Operation,Reactor Tripped.Caused by Turbine Trip Induced by Actuation of Phase Main Power Transformer back-up Differential Relay	on 850317,while at Steady State Power Operation,Reactor Tripped.Caused by Turbine Trip Induced by Actuation of Phase Main Power Transformer back-up Differential Relay
05000304/LER-1985-010-06, :on 850422,required Weekly Functional Test of Boric Acid Transfer Pumps Missed.Caused by Personnel Oversight.Tracking of Required Weekly Surveillance & Daily Reviews Will Prevent Recurrence	on 850422,required Weekly Functional Test of Boric Acid Transfer Pumps Missed.Caused by Personnel Oversight.Tracking of Required Weekly Surveillance & Daily Reviews Will Prevent Recurrence
05000304/LER-1985-011-06, :on 850503,during Shift Surveillance of Monitor Panels,Discovered That Previous Shift Surveillance Not Performed.Caused by Personnel Error.Responsible Rad-Chem Technician Trained	on 850503,during Shift Surveillance of Monitor Panels,Discovered That Previous Shift Surveillance Not Performed.Caused by Personnel Error.Responsible Rad-Chem Technician Trained	10 CFR 50.73(a)(2)(i)
05000304/LER-1985-012-07, :on 850702,purge Valves Closed on High Radiation Signal from Containment Purge Exhaust Noble Gas Monitor.Caused by Procedural Deficiency Resulting in High Alarm Setpoint Set Too Low.Procedure Revised	on 850702,purge Valves Closed on High Radiation Signal from Containment Purge Exhaust Noble Gas Monitor.Caused by Procedural Deficiency Resulting in High Alarm Setpoint Set Too Low.Procedure Revised	10 CFR 50.73(a)(2)(iv), System Actuation
05000295/LER-1985-012, :on 850329,during QA Audit Exit,Fire Hose Hydrostatic Pressure Tests Performed Improperly.Caused by Procedural Error.Procedure PT-203 Revised & Retesting of All Fire Hoses in Progress	on 850329,during QA Audit Exit,Fire Hose Hydrostatic Pressure Tests Performed Improperly.Caused by Procedural Error.Procedure PT-203 Revised & Retesting of All Fire Hoses in Progress
05000304/LER-1985-013-07, :on 850707,steam Generator Blowdown Radiation Monitor 2RE0019 High Alarmed,Causing Isolation of Blowdown. Notice Issued to Operating Dept Reiterating Proper Procedures	on 850707,steam Generator Blowdown Radiation Monitor 2RE0019 High Alarmed,Causing Isolation of Blowdown. Notice Issued to Operating Dept Reiterating Proper Procedures	10 CFR 50.73(a)(2)(iv), System Actuation
05000295/LER-1985-013, :on 850402,reactor Cavity Inadvertently Diluted During ECCS Full Flow Test.Caused by Failure to Fully Close Two Primary Water Sys Valves After Hydro Performed on Vol Control Sys Suction Line	on 850402,reactor Cavity Inadvertently Diluted During ECCS Full Flow Test.Caused by Failure to Fully Close Two Primary Water Sys Valves After Hydro Performed on Vol Control Sys Suction Line
05000304/LER-1985-013-01, :on 850707,following Restoration of Steam Generator Blowdown,Radiation Monitor High Alarmed Causing Isolation Valve BD-17 to Close (ESF Actuation).Caused by primary-secondary Tube Leak	on 850707,following Restoration of Steam Generator Blowdown,Radiation Monitor High Alarmed Causing Isolation Valve BD-17 to Close (ESF Actuation).Caused by primary-secondary Tube Leak	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)
05000295/LER-1985-014-05, :on 850208,offgas Air Ejector Noble Gas Radiation Monitor Discovered Failed Low.Caused by Faulty Transistor in Test/Calibr Printed Circuit Board & Defective Rate Board.Boards Replaced	on 850208,offgas Air Ejector Noble Gas Radiation Monitor Discovered Failed Low.Caused by Faulty Transistor in Test/Calibr Printed Circuit Board & Defective Rate Board.Boards Replaced	10 CFR 50.73(a)(2)(i)
05000304/LER-1985-014-08, :on 850718,w/RHR Pump 2B Out of Svc,Diesel Generator 2B Tripped on Overspeed.Caused by Increased Speed Setting by Dialing 50% Droop.Temporary Procedure Change Initiated to Allow for Lower Speed Setting	on 850718,w/RHR Pump 2B Out of Svc,Diesel Generator 2B Tripped on Overspeed.Caused by Increased Speed Setting by Dialing 50% Droop.Temporary Procedure Change Initiated to Allow for Lower Speed Setting
05000304/LER-1985-015-06, :on 850809,during Aircraft Fire Detection Sys Test (PT-210),diesel Generator 2A & 2B Room Ventilation Fan Outlet Butterfly Dampers Failed to Close.Caused by Stuck Pilot Valves.Valves Replaced	on 850809,during Aircraft Fire Detection Sys Test (PT-210),diesel Generator 2A & 2B Room Ventilation Fan Outlet Butterfly Dampers Failed to Close.Caused by Stuck Pilot Valves.Valves Replaced
05000295/LER-1985-015-04, :on 850417,excess Letdown HX Relief Valve Lifted & Remained Open.Caused by Mispositioned Nozzle Rings. Valve Reset	on 850417,excess Letdown HX Relief Valve Lifted & Remained Open.Caused by Mispositioned Nozzle Rings. Valve Reset	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000304/LER-1985-016-06, :on 850815,during Review of Util Integral Simulation Test Program,Discovered That Several Check Valves Not Tested Per ASME Code or Inservice Test Program.Caused by Administrative Oversight	on 850815,during Review of Util Integral Simulation Test Program,Discovered That Several Check Valves Not Tested Per ASME Code or Inservice Test Program.Caused by Administrative Oversight	10 CFR 50.73(a)(2)(i)
05000295/LER-1985-016-05, :on 850731,operator Accidentally Tripped Over & Broke Off Control Air Line to Fire Protection Containment Isolation Valve 1FCV-FP08.Broken Air Line Repaired & Valve Returned to Position	on 850731,operator Accidentally Tripped Over & Broke Off Control Air Line to Fire Protection Containment Isolation Valve 1FCV-FP08.Broken Air Line Repaired & Valve Returned to Position	10 CFR 50.73(a)(2)(iv), System Actuation
05000295/LER-1985-017-04, :on 850514,during Insp of safety-related Snubbers,Two of Eight Pulled Due to Low Fuel Levels & Declared Inoperable.Caused by Poor Seal Conditions Allowing Leakage of Hydraulic Fluid	on 850514,during Insp of safety-related Snubbers,Two of Eight Pulled Due to Low Fuel Levels & Declared Inoperable.Caused by Poor Seal Conditions Allowing Leakage of Hydraulic Fluid	10 CFR 50.73(a)(2)(1)
05000304/LER-1985-017-07, :on 850909,purge Valves Tripped Shut.Caused by Workers Inadvertently Actuating High Radiation Protection Circuitry.Mod Initiated to Remove Necessity of Installing Jumpers to Start Fans	on 850909,purge Valves Tripped Shut.Caused by Workers Inadvertently Actuating High Radiation Protection Circuitry.Mod Initiated to Remove Necessity of Installing Jumpers to Start Fans	10 CFR 50.73(a)(2)(iv), System Actuation
05000295/LER-1985-018-04, :on 850516,during Type C Leak Testing of Containment Isolation Valves,Two Valves Found W/Excessive Leakage.Cause Not Stated.Valves Repaired & Retested	on 850516,during Type C Leak Testing of Containment Isolation Valves,Two Valves Found W/Excessive Leakage.Cause Not Stated.Valves Repaired & Retested	10 CFR 50.73(a)(2)(i)
05000304/LER-1985-018-06, :on 850930,discovered That Four Limitorque Valve Operators Had Jumper Wires Different from Wires Tested by Vendor in Environ Qualification Program.Cause Not Stated.Part 21 Related	on 850930,discovered That Four Limitorque Valve Operators Had Jumper Wires Different from Wires Tested by Vendor in Environ Qualification Program.Cause Not Stated.Part 21 Related
05000295/LER-1985-019-01, :on 850607,reactor Tripped & MSIVs Closed.Trip Caused by Removal of Source Range Fuses During Troubleshooting & Closure Caused by Failure of Summator. Module Replaced	on 850607,reactor Tripped & MSIVs Closed.Trip Caused by Removal of Source Range Fuses During Troubleshooting & Closure Caused by Failure of Summator. Module Replaced
05000304/LER-1985-019-06, :on 850911,high Particulate Alarm Occurred During Venting of Containment to Atmosphere.Cause Suspected to Be Defect in Alarm Circuitry on Radiation Monitor 2RT-PR09C.Personnel Counseled	on 850911,high Particulate Alarm Occurred During Venting of Containment to Atmosphere.Cause Suspected to Be Defect in Alarm Circuitry on Radiation Monitor 2RT-PR09C.Personnel Counseled	10 CFR 50.73(a)(2)(iv), System Actuation
05000295/LER-1985-019-04, :on 850607,reactor Trip Resulted in High Steam Flow Safeguards Actuation,Closing All Msivs.Caused by Failure of Summator,Which Spiked Low.Module Replaced	on 850607,reactor Trip Resulted in High Steam Flow Safeguards Actuation,Closing All Msivs.Caused by Failure of Summator,Which Spiked Low.Module Replaced	10 CFR 50.73(a)(2)
05000304/LER-1985-019-02, :on 850911,while Venting Unit 1 Containment to Atmosphere,High Particulate Alarm Occurred.Discharge Mistakenly Sampled from Unit 2.Caused by Personnel Error. Personnel Involved Counseled	on 850911,while Venting Unit 1 Containment to Atmosphere,High Particulate Alarm Occurred.Discharge Mistakenly Sampled from Unit 2.Caused by Personnel Error. Personnel Involved Counseled	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)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000295/LER-1985-019, :on 850607,during Investigation of Noise Problem,Fuses Pulled & Replaced Causing Reactor Trip & Unexpected Closure of Msiv.Caused by Personnel Error. Summator 1PM505B Replaced	on 850607,during Investigation of Noise Problem,Fuses Pulled & Replaced Causing Reactor Trip & Unexpected Closure of Msiv.Caused by Personnel Error. Summator 1PM505B 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 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000304/LER-1985-020-06, :on 850527,safeguards Train a Isolation Valves Inadvertently Closed & Could Not Be Reopened During Periodic Test PT-10.Caused by Missed Procedure Step.Memo Re Resetting of Circuit Components Issued	on 850527,safeguards Train a Isolation Valves Inadvertently Closed & Could Not Be Reopened During Periodic Test PT-10.Caused by Missed Procedure Step.Memo Re Resetting of Circuit Components Issued	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)
05000295/LER-1985-021-04, :on 850603,when Instrument Bus Switched from Alternate to Normal Power,Momentary Power Loss Caused Reactor Trip.Caused by Switching Procedure Not Being Referenced.Warning Sign Placed at Switch	on 850603,when Instrument Bus Switched from Alternate to Normal Power,Momentary Power Loss Caused Reactor Trip.Caused by Switching Procedure Not Being Referenced.Warning Sign Placed at Switch	10 CFR 50.73(a)(2)(iv), System Actuation
05000295/LER-1985-021, :on 850603,momentary Loss of Power Due to Instrument Bus 112 Switching from Alternate to Normal Power Supply Opened Reactor Trip Breakers.Caused by Personnel Error.Warning Sign Placed by Transfer Switch	on 850603,momentary Loss of Power Due to Instrument Bus 112 Switching from Alternate to Normal Power Supply Opened Reactor Trip Breakers.Caused by Personnel Error.Warning Sign Placed by Transfer Switch	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)(viii)(B) 10 CFR 50.73(a)(2)(1)
05000304/LER-1985-021-05, :on 851010,inadvertent Containment Purge Trip Due to Spurious U-2 Containment Separate Particulate Iodine & Noble Gas Monitor 2RIA-PR40 High Radiation Alarm Occurred. Caused by Defective Accessory Receptacle	on 851010,inadvertent Containment Purge Trip Due to Spurious U-2 Containment Separate Particulate Iodine & Noble Gas Monitor 2RIA-PR40 High Radiation Alarm Occurred. Caused by Defective Accessory Receptacle	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)
05000304/LER-1985-022-01, :on 851015,fuel Handling Accident Radiation Monitor Exceeded High Alarm Setpoint of 300 Mrem/H Due to High Exposure Rate from Upper Internals,Resulting in Closure of Containment Purge Valves.Procedure Revised.W/Undated Ltr	on 851015,fuel Handling Accident Radiation Monitor Exceeded High Alarm Setpoint of 300 Mrem/H Due to High Exposure Rate from Upper Internals,Resulting in Closure of Containment Purge Valves.Procedure Revised.W/Undated Ltr	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 50.72(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)
05000304/LER-1985-022-06, :on 851015,fuel Handling Accident Radiation Monitor Exceeded High Alarm Setpoint Due to High Exposure Rate from Upper Internals Causing Inadvertent Containment Purge Trip.Caused by Procedural Deficiencies	on 851015,fuel Handling Accident Radiation Monitor Exceeded High Alarm Setpoint Due to High Exposure Rate from Upper Internals Causing Inadvertent Containment Purge Trip.Caused by Procedural Deficiencies	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)(1) 10 CFR 50.73(a)(2)(viii)(8)
05000295/LER-1985-022-04, :on 850611,refueling Water Storage Tank Isolation to Safety Injection Pump Failed to Close During Testing.Caused by Single Phase Surge Due to Pinched Leads in Valve Operator Motor Compartment	on 850611,refueling Water Storage Tank Isolation to Safety Injection Pump Failed to Close During Testing.Caused by Single Phase Surge Due to Pinched Leads in Valve Operator Motor Compartment	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
05000295/LER-1985-023, :on 850603,steam Generator Steam Flow Channel II Read High & Temporary Procedure Change Made to Troubleshoot Loop.Temporary Change Paperwork Misplaced. Caused by Inadequate Tracking sys.W/861209	on 850603,steam Generator Steam Flow Channel II Read High & Temporary Procedure Change Made to Troubleshoot Loop.Temporary Change Paperwork Misplaced. Caused by Inadequate Tracking sys.W/861209	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 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A)
05000304/LER-1985-023-06, :on 851016,during Performance of Technical Staff Special Procedure Involving Dropping ESF Electrical Buses,Containment Isolation Valves Closed.Caused by Procedure Deficiency	on 851016,during Performance of Technical Staff Special Procedure Involving Dropping ESF Electrical Buses,Containment Isolation Valves Closed.Caused by Procedure Deficiency	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)(B) 10 CFR 50.73(a)(2)(1)
05000295/LER-1985-023-04, :on 850617,14-day Review Requirement Exceeded by 1 Wk for Change to Surveillance Procedure IMWR-523 Re Loop F-523 Steam Generator Loop C Steam Flow Channel.Caused by Inadequate Review Procedures	on 850617,14-day Review Requirement Exceeded by 1 Wk for Change to Surveillance Procedure IMWR-523 Re Loop F-523 Steam Generator Loop C Steam Flow Channel.Caused by Inadequate Review Procedures	10 CFR 50.73(a)(2)(i)
05000295/LER-1985-024-04, :on 850629,level in Steam Generator D Reached 25% Giving Automatic Reactor Trip in Anticipation of Loss of Heat Sink.Caused by Operator Error,Aggravated by Equipment Failure.Individual Counseled	on 850629,level in Steam Generator D Reached 25% Giving Automatic Reactor Trip in Anticipation of Loss of Heat Sink.Caused by Operator Error,Aggravated by Equipment Failure.Individual Counseled	10 CFR 50.73(a)(2)(iv), System Actuation
05000304/LER-1985-024-05, :on 851016,during Performance of Special Procedure Involving ESF Component Alignment Prior to Dropping Bus 248,component Cooling Pump Ob Restarted After Manual Trip.Caused by Low Pressure Spike	on 851016,during Performance of Special Procedure Involving ESF Component Alignment Prior to Dropping Bus 248,component Cooling Pump Ob Restarted After Manual Trip.Caused by Low Pressure Spike	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)
05000304/LER-1985-025-05, :on 851023,three Steam Generator D narrow-range Level Transmitters Found Out of Tolerance,Due to Instrument Drift Refueling Calibr.Transmitters Replaced Under Mod M22-1(2)-85-21	on 851023,three Steam Generator D narrow-range Level Transmitters Found Out of Tolerance,Due to Instrument Drift Refueling Calibr.Transmitters Replaced Under Mod M22-1(2)-85-21	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)
05000295/LER-1985-025-04, :on 850627,after Taking Unit off-line for Repairs to Feedwater Regulating Valve,Control Rod Failure Received.Operator Manually Tripped Reactor.Caused by Phase Error in Group B.Alarm Reset	on 850627,after Taking Unit off-line for Repairs to Feedwater Regulating Valve,Control Rod Failure Received.Operator Manually Tripped Reactor.Caused by Phase Error in Group B.Alarm Reset	10 CFR 50.73(a)(2)(iv), System Actuation
05000295/LER-1985-026-04, :on 850710,10 Valves W/O Penetration Pressurization Supply Not Tested During Cold Shutdown.Caused by Inadequate Procedural Review of Mod M22-1-81-19.Change to Tech Spec 15.6.10.e Submitted	on 850710,10 Valves W/O Penetration Pressurization Supply Not Tested During Cold Shutdown.Caused by Inadequate Procedural Review of Mod M22-1-81-19.Change to Tech Spec 15.6.10.e Submitted	10 CFR 50.73(a)(2)(i)
05000304/LER-1985-027-05, :on 851118,closure of Containment Purge Isolation Valve Occurred Due to High Alarm on Containment Air Monitor 2RIA-PR40.Caused by Procedure Deficiency. Procedure Revised	on 851118,closure of Containment Purge Isolation Valve Occurred Due to High Alarm on Containment Air Monitor 2RIA-PR40.Caused by Procedure Deficiency. Procedure 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) 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)
05000295/LER-1985-027-04, :on 850726,Procedure CRN-85-357 Re Backfill Feedwater Instrument Sensing Lines Incorrectly Approved. Caused by Employee Error.Procedure Subsequently Approved W/Proper Signatures	on 850726,Procedure CRN-85-357 Re Backfill Feedwater Instrument Sensing Lines Incorrectly Approved. Caused by Employee Error.Procedure Subsequently Approved W/Proper Signatures	10 CFR 50.73(a)(2)(i)
05000304/LER-1985-028, :Not Used	Not Used
05000295/LER-1985-028-04, :on 850806,failure to Periodically Test Svc Bus Undervoltage Start of Steam Driven Auxiliary Feedwater Pump Discovered.Test Procedure PT-5C Written & Performed to Test Automatic Pump Start	on 850806,failure to Periodically Test Svc Bus Undervoltage Start of Steam Driven Auxiliary Feedwater Pump Discovered.Test Procedure PT-5C Written & Performed to Test Automatic Pump Start	10 CFR 50.73(a)(2)(i)
05000295/LER-1985-028, :on 850806,during Review of Tech Spec Surveillance Requirements,Discovered That Svc Bus Undervoltage Start of Steam Driven Auxiliary Feedwater Pump Not Periodically Tested	on 850806,during Review of Tech Spec Surveillance Requirements,Discovered That Svc Bus Undervoltage Start of Steam Driven Auxiliary Feedwater Pump Not Periodically Tested
05000304/LER-1985-028-01, LER Number 85-028 Used to Rept Loss of RHR Cooling Flow.Ltr Should Be Disregarded	LER Number 85-028 Used to Rept Loss of RHR Cooling Flow.Ltr Should Be Disregarded
05000304/LER-1985-028-05, :on 851214,DHR Lost Due to RHR Pump Cavitation. Caused by Inadequate Procedures & Problems W/Level Indication.Procedures Reviewed & Changed.Rcs Level Sys Will Be Modified to Provide Reliable Indication	on 851214,DHR Lost Due to RHR Pump Cavitation. Caused by Inadequate Procedures & Problems W/Level Indication.Procedures Reviewed & Changed.Rcs Level Sys Will Be Modified to Provide Reliable Indication	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)
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