05000296/LER-1985-007-01, Canceled

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Canceled
Person / Time
ML20100M514
Site:	Browns Ferry
Issue date:	03/29/1985
From:	Jones G TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
LER-85-007-01, LER-85-7-1, NUDOCS 8504170610
Download: ML20100M514 (1)
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LER-1985-007, Canceled

Event date:
Report date:
2961985007R01 - NRC Website
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text

TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P.'O. Box 2000 Decatur, Alabama 35602 March 29, 1985 U. S. Nuclear Regulatory Comission Document Control Desk Washington, D. C.

20555

Dear Sir:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 3 -

DOCKET NO. 50-296 - FACILITY OPERATING LICENSE DPR-68 A Licensee Event Report will not be prepared under ntanber 50-296/85007.

Please b6 advised of this vacancy in our accounting sequence.

Very truly yours, TENNESSEE VALLEY AUTHORITY l

r b-la psgn G. T.

nes Plant nager Browns Ferry Nuclear Plant

(

Enclosures cc (Enclosures):

Regional Administrator INPO Records Center U. S. Nuclear Regulatory Commission Suite 1500 Office of Inspection and Enforcement 1100 Circle 75 Parkway Region II Atlanta, Georgia 30339 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 l

NRC Resident Inspector, BFN l

85041 0610 850329 PDR ADocK 05000296

^

S'

~

gg J,1 An Equal Opaortunity Employer

Licensee Event Report

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		Reporting criterion
05000259/LER-1985-001-02, :on 850121,unidentified Drywell Leakage Rate in Excess of Tech Spec,Noted.Shutdown Initiated.Caused by Leak in Temporary Hose & Weld Crack Inside Drywell.Repairs Made & Pertinent Procedures Revised	on 850121,unidentified Drywell Leakage Rate in Excess of Tech Spec,Noted.Shutdown Initiated.Caused by Leak in Temporary Hose & Weld Crack Inside Drywell.Repairs Made & Pertinent Procedures Revised
05000296/LER-1985-001, :on 850104,during Normal Operation,Employee Accidentally Caused RCIC Sys to Be Inoperable for Approx 2 Minutes.All Other Required Core Standby Cooling Sys Fully Operable	on 850104,during Normal Operation,Employee Accidentally Caused RCIC Sys to Be Inoperable for Approx 2 Minutes.All Other Required Core Standby Cooling Sys Fully Operable
05000259/LER-1985-001-01, :on 850121,drywell Leakage Rate in Excess of Tech Specs Noted.Caused by Leak in Temporary Hose Used to Test Check Valve & Small Weld Crack Inside Drywell.Crack Repaired.Procedures Revised	on 850121,drywell Leakage Rate in Excess of Tech Specs Noted.Caused by Leak in Temporary Hose Used to Test Check Valve & Small Weld Crack Inside Drywell.Crack Repaired.Procedures Revised	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000260/LER-1985-001-03, :on 850221,removal of Thermocouple Revealed 1-inch Long Wall Crack at Weld Located at Junction of Recirculation Sys Header & Riser.Cause Unknown.Crack Will Be Repaired by Weld Overlay	on 850221,removal of Thermocouple Revealed 1-inch Long Wall Crack at Weld Located at Junction of Recirculation Sys Header & Riser.Cause Unknown.Crack Will Be Repaired by Weld Overlay
05000259/LER-1985-002-03, :on 850124,all Eight Diesel Generators & Core Spray Pumps 3A & 3C Started During Performance of Core Spray Logic Functional Surveillance Instruction.Caused by Personnel Error.Personnel Cautioned	on 850124,all Eight Diesel Generators & Core Spray Pumps 3A & 3C Started During Performance of Core Spray Logic Functional Surveillance Instruction.Caused by Personnel Error.Personnel Cautioned	10 CFR 50.73(a)(2)(iv), System Actuation
05000296/LER-1985-002-01, :on 850107,power Cable Accidentally Shorted to Ground,Tripping Breaker That Supplies Several Instrument Panels.Caused by Bad Card.Personnel Briefed on Cause of Event	on 850107,power Cable Accidentally Shorted to Ground,Tripping Breaker That Supplies Several Instrument Panels.Caused by Bad Card.Personnel Briefed on Cause of Event
05000260/LER-1985-002-04, :on 850307,during Refueling Outage Initial Test Results Received for Main Steam Relief Valves.Tech Spec Criteria Not Met by Eight Valves.Caused by Pilot Disc Sticking.Valve Setpoints Will Be Reset	on 850307,during Refueling Outage Initial Test Results Received for Main Steam Relief Valves.Tech Spec Criteria Not Met by Eight Valves.Caused by Pilot Disc Sticking.Valve Setpoints Will Be Reset	10 CFR 50.73(a)(2)(1)
05000296/LER-1985-003-02, :on 850111,during Scheduled Test,Hpci & RCIC Sys Failed to Reach Rated Flow within Allotted Time.Hpci Sys Declared Inoperable.Caused by Incorrect Setting of Limit Switch	on 850111,during Scheduled Test,Hpci & RCIC Sys Failed to Reach Rated Flow within Allotted Time.Hpci Sys Declared Inoperable.Caused by Incorrect Setting of Limit Switch	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000260/LER-1985-003-04, :on 850227,automatic Scram Occurred When Fuses Removed from Reactor Protection Sys Circuitry During Mod. Caused by Deficient Work Plan.Plan Revised	on 850227,automatic Scram Occurred When Fuses Removed from Reactor Protection Sys Circuitry During Mod. Caused by Deficient Work Plan.Plan Revised	10 CFR 50.73(a)(2)(iv), System Actuation
05000259/LER-1985-003-03, :on 850205,diesel Generators C & D Inadvertently Started.Caused by Voltage Spike Trip Causing Cooling Tower Transformer Overpressurization Relays to Operate.Caution Signs Posted	on 850205,diesel Generators C & D Inadvertently Started.Caused by Voltage Spike Trip Causing Cooling Tower Transformer Overpressurization Relays to Operate.Caution Signs Posted	10 CFR 50.73(a)(2)(iv), System Actuation
05000260/LER-1985-004-02, :on 850611,pH Value Below Tech Spec Limits. Cause Unknown.Formal Procedures for Handling of Chemistry Deviations in Special Operating Instructions for Future Safe End Replacement Work Established	on 850611,pH Value Below Tech Spec Limits. Cause Unknown.Formal Procedures for Handling of Chemistry Deviations in Special Operating Instructions for Future Safe End Replacement Work Established	10 CFR 50.73(a)(2)(1)
05000260/LER-1985-004-04, :on 850610,low Ph Value Identified in Reactor Water Chemistry Sample.Caused by Inleakage Into Reactor Water Cleanup Sys.Impurity Removed by Sys Operation	on 850610,low Ph Value Identified in Reactor Water Chemistry Sample.Caused by Inleakage Into Reactor Water Cleanup Sys.Impurity Removed by Sys Operation	10 CFR 50.73(a)(2)(1)
05000259/LER-1985-004-03, :on 850223,generator End of LPCI Motor Generator 1EA Found Overheated.Caused by Diode Failure Due to Vibration of Rectifier Ring.Phenolic Coil Clamps Replaced & Rectifier Rings Tightened	on 850223,generator End of LPCI Motor Generator 1EA Found Overheated.Caused by Diode Failure Due to Vibration of Rectifier Ring.Phenolic Coil Clamps Replaced & Rectifier Rings Tightened	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000296/LER-1985-004-01, :on 850122,surveillance Instruction Not Performed within Required Frequency Band.Caused by Operator Error.Operator Cautioned to More Carefully Apply Frequency Requirements in Future	on 850122,surveillance Instruction Not Performed within Required Frequency Band.Caused by Operator Error.Operator Cautioned to More Carefully Apply Frequency Requirements in Future	10 CFR 50.73(a)(2)(1)
05000296/LER-1985-004, :on 850122,Surveillance Instruction 4.3.A.2 Performed 1 Day Later than Allowed by Tech Specs.Caused by Personnel Error in Interpreting Frequency Requirements. Procedures Re Performance Dates Revised	on 850122,Surveillance Instruction 4.3.A.2 Performed 1 Day Later than Allowed by Tech Specs.Caused by Personnel Error in Interpreting Frequency Requirements. Procedures Re Performance Dates Revised	10 CFR 50.73(a)(2)(1)
05000260/LER-1985-005-04, :on 850611,reactor Water Cleanup Sys Isolated Due to Blown Fuse.Caused by Electrician Shorting Out Wires on Relay During Removal.Personnel Cautioned.Fuse Replaced. Sys Reset	on 850611,reactor Water Cleanup Sys Isolated Due to Blown Fuse.Caused by Electrician Shorting Out Wires on Relay During Removal.Personnel Cautioned.Fuse Replaced. Sys Reset
05000296/LER-1985-005-01, :on 850210,cracked Weld on 3/4-inch Test Connection Line Discovered During Insp Following Shutdown to Investigate for Drywell Unidentified Leakage.Caused by Increased Vibration Due to Missing Pipe Clamp	on 850210,cracked Weld on 3/4-inch Test Connection Line Discovered During Insp Following Shutdown to Investigate for Drywell Unidentified Leakage.Caused by Increased Vibration Due to Missing Pipe Clamp
05000259/LER-1985-005-03, :on 850227,during HPCI Sys Surveillance Testing,Time to Reach Rated Flow 2 Longer than Surveillance Instruction Spec of 25 S.Caused by Inadvertent Closing of Ball Valve on Turbine Hydraulic Sys	on 850227,during HPCI Sys Surveillance Testing,Time to Reach Rated Flow 2 Longer than Surveillance Instruction Spec of 25 S.Caused by Inadvertent Closing of Ball Valve on Turbine Hydraulic Sys	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000296/LER-1985-006, :on 850213,mismatch Between Gemac Water Level Indicators Developed While at Low Pressure.Cause Attributed to Leak in Channel a Ref Leg Line X-28a.Operators Trained to Diagnose Water Level Problems	on 850213,mismatch Between Gemac Water Level Indicators Developed While at Low Pressure.Cause Attributed to Leak in Channel a Ref Leg Line X-28a.Operators Trained to Diagnose Water Level Problems	10 CFR 50.73(a)(2)(iv), System Actuation
05000260/LER-1985-006-04, :on 850620,secondary Containment Isolation Initiated Due to Spike in Refuel Zone Exhaust Channel B Radiation Detector.Cause of Spike Unknown.Detector Successfully surveillance-tested	on 850620,secondary Containment Isolation Initiated Due to Spike in Refuel Zone Exhaust Channel B Radiation Detector.Cause of Spike Unknown.Detector Successfully surveillance-tested	10 CFR 50.73(a)(2)(iv), System Actuation
05000259/LER-1985-006-02, :on 850304,during Performance of HPCI Sys Motor Operated Valve Operability Surveillance Instruction 4.5.E.1.c,HPCI Inverter Fuse Cleared.Caused by Blown Inverter Fuse.Fuse Replaced	on 850304,during Performance of HPCI Sys Motor Operated Valve Operability Surveillance Instruction 4.5.E.1.c,HPCI Inverter Fuse Cleared.Caused by Blown Inverter Fuse.Fuse Replaced	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000260/LER-1985-007-03, :on 850627,alternate Feeder Breaker Failed to Close,Resulting in Secondary Containment Isolation & Loss of Reactor Protection Sys Motor Generator.Caused by Breaker Failure Due to Loosened Bolts.Bolts Tightened	on 850627,alternate Feeder Breaker Failed to Close,Resulting in Secondary Containment Isolation & Loss of Reactor Protection Sys Motor Generator.Caused by Breaker Failure Due to Loosened Bolts.Bolts Tightened	10 CFR 50.73(a)(2)(iv), System Actuation
05000259/LER-1985-007-02, :on 850318,handswitch Used for Purging Plant Stack Radiation Monitor Left in on Position,Allowing 2 H Unmonitored Release.Caused by Personnel Error.Switch Turned Off.Individual Reprimanded	on 850318,handswitch Used for Purging Plant Stack Radiation Monitor Left in on Position,Allowing 2 H Unmonitored Release.Caused by Personnel Error.Switch Turned Off.Individual Reprimanded	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
05000296/LER-1985-007-01, Canceled	Canceled
05000260/LER-1985-008-04, :on 850711,primary Containment Isolation Sys Group 3 Isolation Occurred When Incorrect Output Breaker of Reactor Protection Sys Motor Generator Set Opened.Caused by Personnel Error	on 850711,primary Containment Isolation Sys Group 3 Isolation Occurred When Incorrect Output Breaker of Reactor Protection Sys Motor Generator Set Opened.Caused by Personnel Error	10 CFR 50.73(a)(2)(iv), System Actuation
05000259/LER-1985-008, :on 850318,HPCI & RCIC Turbine Exhaust Valve Flanged Bonnets Not Local Leak Tested in Accordance w/10CFR50,App J Requirements.All Valves Will Be Repaired & Pass Leak Test	on 850318,HPCI & RCIC Turbine Exhaust Valve Flanged Bonnets Not Local Leak Tested in Accordance w/10CFR50,App J Requirements.All Valves Will Be Repaired & Pass Leak Test	10 CFR 50.73(a)(2)(1)
05000259/LER-1985-008-02, :on 850315,discovered Listed Valves Not Local Leak Tested.Caused by Failure to Identify Valves Per 10CFR50.Two Valves Failed Subsequent Test & Unit Manually Scrammed.Two Other Valves to Be Modified	on 850315,discovered Listed Valves Not Local Leak Tested.Caused by Failure to Identify Valves Per 10CFR50.Two Valves Failed Subsequent Test & Unit Manually Scrammed.Two Other Valves to Be Modified	10 CFR 50.73(a)(2)(i)
05000296/LER-1985-008-01, :on 850309,reactor Manually Scrammed Due to Problems W/Rod Worth Minimizer Program During Controlled Shutdown.Cause Not Stated	on 850309,reactor Manually Scrammed Due to Problems W/Rod Worth Minimizer Program During Controlled Shutdown.Cause Not Stated	10 CFR 50.73(a)(2)(iv), System Actuation
05000296/LER-1985-009-04, :on 850320,during Investigation of Motor Noise, RHR Pump Motor 3D Failed.Caused by Failure of Lower Radial Guide Bearing Resulting in Failure of Stator Winding.On 850218,unrelated RHR Pump Motor Also Failed	on 850320,during Investigation of Motor Noise, RHR Pump Motor 3D Failed.Caused by Failure of Lower Radial Guide Bearing Resulting in Failure of Stator Winding.On 850218,unrelated RHR Pump Motor Also Failed
05000296/LER-1985-009, :on 850320,RHR Pump Motor 3D Began to Smoke During Investigation of Unusual Motor Noise.Caused by Failure of Lower Radial Guide Bearing Resulting in Stator Winding Failure	on 850320,RHR Pump Motor 3D Began to Smoke During Investigation of Unusual Motor Noise.Caused by Failure of Lower Radial Guide Bearing Resulting in Stator Winding Failure
05000260/LER-1985-009-03, :on 850712,during Unit 2 Refuel Outage, Inadvertent Containment Isolation Occurred When 480-V Shutdown Board Transferred to Deenergized Bus.Caused by Personnel Error.Employee Retrained on 850718	on 850712,during Unit 2 Refuel Outage, Inadvertent Containment Isolation Occurred When 480-V Shutdown Board Transferred to Deenergized Bus.Caused by Personnel Error.Employee Retrained on 850718	10 CFR 50.73(a)(2)(iv), System Actuation
05000259/LER-1985-009-01, :on 850322,analysis of Primary Containment Isolation Sys Circuitry Revealed That Combination of Switches Could Lead to Failure of Listed Sys to Function. Caused by Design Oversight	on 850322,analysis of Primary Containment Isolation Sys Circuitry Revealed That Combination of Switches Could Lead to Failure of Listed Sys to Function. Caused by Design Oversight	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000260/LER-1985-010-04, :on 850626,inadvertent Secondary Containment Isolation Occurred Due to Failure of Fuse in Panel 9-42. Cause Not Determined.Blown Fuse Replaced.Isolation Signal Reset.Failure Considered Random	on 850626,inadvertent Secondary Containment Isolation Occurred Due to Failure of Fuse in Panel 9-42. Cause Not Determined.Blown Fuse Replaced.Isolation Signal Reset.Failure Considered Random	10 CFR 50.73(a)(2)(iv), System Actuation
05000296/LER-1985-010-02, :on 850421,inadvertent Initiation of Safety Sys Associated W/Primary Containment Isolation Signal Occurred Due to Short Caused During Fuse Removal.Caused by Personnel Error.Sys Returned to Standby Readiness	on 850421,inadvertent Initiation of Safety Sys Associated W/Primary Containment Isolation Signal Occurred Due to Short Caused During Fuse Removal.Caused by Personnel Error.Sys Returned to Standby Readiness	10 CFR 50.73(a)(2)(iv), System Actuation
05000259/LER-1985-010-01, :on 850403,following Upscale Alarm of CAM-1-90-250,chemical Analyst Failed to Continue CAM Hourly Sampling Per Surveillance Instruction 4.8.B.1.a.Caused by Personnel Error.Personnel Given Addl Training	on 850403,following Upscale Alarm of CAM-1-90-250,chemical Analyst Failed to Continue CAM Hourly Sampling Per Surveillance Instruction 4.8.B.1.a.Caused by Personnel Error.Personnel Given Addl Training	10 CFR 50.73(a)(2)(1)
05000260/LER-1985-011-02, :on 850716,reactor Water Cleanup Sys Isolation Occurred When Two Isolation Circuit Fuses Failed During Refueling Outage.Cause Undetermined.Fuses Replaced	on 850716,reactor Water Cleanup Sys Isolation Occurred When Two Isolation Circuit Fuses Failed During Refueling Outage.Cause Undetermined.Fuses Replaced	10 CFR 50.73(a)(2)(iv), System Actuation
05000259/LER-1985-011-01, :on 850411,control Circuit Fuse Blew,Causing Partial Initiation of Primary Containment Isolation Sys. Caused by Failure of Relay 16AK72 Coil.Coil Replaced.New Fuse Installed.Recurrence Control Not Required	on 850411,control Circuit Fuse Blew,Causing Partial Initiation of Primary Containment Isolation Sys. Caused by Failure of Relay 16AK72 Coil.Coil Replaced.New Fuse Installed.Recurrence Control Not Required	10 CFR 50.73(a)(2)(iv), System Actuation
05000259/LER-1985-012, :on 850405,deficiency in Standby Gas Treatment Cable Routing Discovered.Caused by Drawing Design Error. Junction Box Remounted to Meet Seismic Criteria & Design Personnel Counseled	on 850405,deficiency in Standby Gas Treatment Cable Routing Discovered.Caused by Drawing Design Error. Junction Box Remounted to Meet Seismic Criteria & Design Personnel Counseled	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000260/LER-1985-012-03, :on 850812,during Routine Surveillance Instruction,Esf Actuations Occurred.Caused by Slight Maladjustment of Refuel Zone Exhaust Radiation Monitor RI-90-144 Bug Source Due to Normal Wear	on 850812,during Routine Surveillance Instruction,Esf Actuations Occurred.Caused by Slight Maladjustment of Refuel Zone Exhaust Radiation Monitor RI-90-144 Bug Source Due to Normal Wear	10 CFR 50.73(a)(2)(iv), System Actuation
05000296/LER-1985-012-02, :on 850425,0507 & 09,momentary Loss of Secondary Containment Occurred.Caused by Personnel Airlock Door Problems.Problems Considered Random Failures W/No Recurrence Control Required	on 850425,0507 & 09,momentary Loss of Secondary Containment Occurred.Caused by Personnel Airlock Door Problems.Problems Considered Random Failures W/No Recurrence Control Required	10 CFR 50.73(a)(2)(1)
05000259/LER-1985-012-01, :on 850408,discovered Standby Gas Treatment Sys Divisional Cables Routed Through Fire Stop/Pressure Seals Using Spare Cables Designated for nonsafety-related Use. Junction Box Also Determined Seismically Unqualified	on 850408,discovered Standby Gas Treatment Sys Divisional Cables Routed Through Fire Stop/Pressure Seals Using Spare Cables Designated for nonsafety-related Use. Junction Box Also Determined Seismically Unqualified	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000260/LER-1985-013-03, :on 851002,during Performance of Plant Surveillance Instruction,Inadvertent Secondary Containment Isolation Occurred When Alternate Feeder Breaker to Shutdown Board Tripped.Caused by Binding Trip Button	on 851002,during Performance of Plant Surveillance Instruction,Inadvertent Secondary Containment Isolation Occurred When Alternate Feeder Breaker to Shutdown Board Tripped.Caused by Binding Trip Button	10 CFR 50.73(a)(2)(iv), System Actuation
05000296/LER-1985-013-02, :on 850430,four Primary Containment Isolation Valves Failed Closure Time Surveillance Test.Caused by Revised Timing Procedure.Valves Will Be Repaired as Necessary & Timing Adjusted	on 850430,four Primary Containment Isolation Valves Failed Closure Time Surveillance Test.Caused by Revised Timing Procedure.Valves Will Be Repaired as Necessary & Timing Adjusted	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000259/LER-1985-013-01, :on 850418,util Ofc of Engineering Determined That Existing Configuration of Startup Test Instrumentation Panels Cannot Be Determined to Be Seismically Qualified. Caused by Improper Mounting of Panels	on 850418,util Ofc of Engineering Determined That Existing Configuration of Startup Test Instrumentation Panels Cannot Be Determined to Be Seismically Qualified. Caused by Improper Mounting of Panels	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000296/LER-1985-014-01, :on 850429,radiation Indicator RI-90-142 Taken to Zero to Check Recorder Resulting in Inadvertent Initiation of Group 6 Containment Isolation Logic.Caused by Lack of Precautionary Note in Instruction	on 850429,radiation Indicator RI-90-142 Taken to Zero to Check Recorder Resulting in Inadvertent Initiation of Group 6 Containment Isolation Logic.Caused by Lack of Precautionary Note in Instruction	10 CFR 50.73(a)(2)(iv), System Actuation
05000259/LER-1985-014, :on 850405,19,22,0501 & 24,while in Refueling/ Maint Outage,Diesel Generator & Shutdown Board Battery Racks Found Unqualified.Caused by Installation Errors.Racks Modified & Design Drawings Revised	on 850405,19,22,0501 & 24,while in Refueling/ Maint Outage,Diesel Generator & Shutdown Board Battery Racks Found Unqualified.Caused by Installation Errors.Racks Modified & Design Drawings Revised	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000260/LER-1985-014-03, :on 851024,overcurrent Trip of Reactor Protection Sys Motor Generator Set & Inadvertent Partial Containment Isolation Occurred.Caused by Procedural Deficiency.Plant Maint Instruction Revised	on 851024,overcurrent Trip of Reactor Protection Sys Motor Generator Set & Inadvertent Partial Containment Isolation Occurred.Caused by Procedural Deficiency.Plant Maint Instruction Revised	10 CFR 50.73(a)(2)(iv), System Actuation
05000259/LER-1985-014-01, :on 850419,diesel Generator Racks & Shutdown Board Battery Rack 3EB Discovered to Be Seismically Unqualified.Caused by Installation Deficiency.Racks Modified to Meet Design Requirements	on 850419,diesel Generator Racks & Shutdown Board Battery Rack 3EB Discovered to Be Seismically Unqualified.Caused by Installation Deficiency.Racks Modified to Meet Design Requirements	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000296/LER-1985-014-02, :on 850429,Group 6 Containment Isolation Logic Inadvertently Initiated.Caused When RI-90-142 Taken to Zero Position to Check Recorder Reading.Containment Isolation Signal Reset	on 850429,Group 6 Containment Isolation Logic Inadvertently Initiated.Caused When RI-90-142 Taken to Zero Position to Check Recorder Reading.Containment Isolation Signal Reset	10 CFR 50.73(a)(2)(iv), System Actuation
05000296/LER-1985-014, Corrected Ltr Forwarding LER 85-014-00 Re Containment Isolation Initiation	Corrected Ltr Forwarding LER 85-014-00 Re Containment Isolation Initiation	10 CFR 50.73(a)(2)(iv), System Actuation
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