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POJ 2s o8 of esRC perm 3es-U S. NUCLEAA REGULATORY COsassessoas
- 83 APPRQvt3 Oess ano 3:30-C104 UCENSEE EVENT REPORT (LER)
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On January 1,1985 with the unit at 34% power, at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, it was disco,ered that a safe signal was in place in "B" loop channel 2 of overtemperature delta T (0 PAT) without the cognizance of the Operations or Instrumentation staff.
Safe signals are permitted by Technical Specifications for short periods of time during testing, however, this does imply cognizance of the signal.
With the activity associated with the trip on 12-31-84 and the subsequent investigations to determine the trip cause, Admin. Control of the safe signal was not maintained in the turnover from day shif t to swing shif t.
A procedure was written that will be used when a safe signal is required.
Details of the event will be reviewed by licensed personnel. The NI's were rescaled,the "B" loop AT channel was placed in trip and the safe sign 61 removed.
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Description of the Event On January 1,1985 with the unit at 34% power, at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, it was discovered that a safe signal was in place in "B" loop channel 2 of over-temperature delta T (0 PAT) without the cognizance of the Operations or Instrumentation staff. Safe signals are permitted by Technical Specifications for short periods of time during testing, however, this does imply cognizance of the signal.
This event began on 12-29-84 when the (OTAT) channel 2.bistables for "B" loop were placed in trip due to a failed RTD. On 12-31-84 at 1147 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.364335e-4 months <br />, a safe signal was injected, with the permission of the Shif t supervisor, into the "B" loop AT instrumentation channel to allow performance of Periodic Test 8.1 (Reactor Protection Logic) 'and to rescale the excore nuclear detectors (NI's).
During this test, a reactor trip occurred at 1324 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.03782e-4 months <br /> (See Unit 1 LER-84-026-00). The test was terminateo, but the safe signal remained in for rescaling the NI's.
This informatic s was not passed on to the subsequent _shif ts and was not detected by pre-criticality checklists.
2.
Probable Consequences The OTAT logic is designed to protect the core against departure from nucicate boiling (DNB). Sufficient margin to DNB is maintained with the unit at full power. A very large margin to DNB was maintained from the reactor trip until the safe signal was discovered because reactor power remained below 35%.
The total time the safe signal was in place was 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> 13 minutes, however, the time that plant personnel were unaware of it was 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 30 minutes. Also, the 2 redundant OTAT channels remained operable throughout this event, therefore an unreviewed safety question was not created and the health and safety of the public were unaffected.
3.
Cause
With the activity associated with the trip on 12-31-84 and the subsequent investigations to determine the trip cause, Admin. Control of the safe signal was not maintained in the turnover from day shift to swing shift. This information was available in the Control Room Operator's log.
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4.
Immediate Corrective Action
When the safe signal was discovered, administrative control was reestablished, and since it was still needed for rescaling the NI's, no immediate corrective actions were taken.
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Additional Corrective Actions
The NI's were rescaled, and the "B" loop AT channel was placed in trip and the safe signal removed.
6.
Action Taken to Prevent Recurrence A procedure was written that will be used when a safe signal is required.
Details of the event will be reviewed by licensed personnel.
7.
Generic Implications None.
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f VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Statim P. O. Box 315 Surry, Virginia 23883 Serial No:
85-001 January 28, 1985 Docket No:
50-280 License No: DPR-32 U. S. Nuclear Regulatory Commission Document Control Desk 016 Phillips Building Washington, D.C. 20555 Gentlemen:
Pursuant to Surry Power Station Technical Specifications, the Virginia Electric
' and Power Company 1.ereby submits the following Licensee Event Report for Surry Unit 1.
REPORT NUMBER 85-001-00
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This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control.
Very truly yours, R. F. Saunders Station Manager Enclosure cc: Mr. James P. O'Reilly Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323 i
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| 05000280/LER-1985-001, :on 850101,safe Signal Placed in Loop B Channel 2 of Overtemp Delta T W/O Cognizance of Operations or Instrumentation Staff.Caused by Lack of Administrative Controls.Event Will Be Reviewed |
- on 850101,safe Signal Placed in Loop B Channel 2 of Overtemp Delta T W/O Cognizance of Operations or Instrumentation Staff.Caused by Lack of Administrative Controls.Event Will Be Reviewed
| | | 05000281/LER-1985-001-02, :on 850106,auxiliary Feed Pump Operated During Monthly Reactor Protection Logic Test,Contrary to Planned Evolution.Caused by Failure to Perform Test in Proper Sequence |
- on 850106,auxiliary Feed Pump Operated During Monthly Reactor Protection Logic Test,Contrary to Planned Evolution.Caused by Failure to Perform Test in Proper Sequence
| | | 05000281/LER-1985-002-03, :on 850215,svc Water Isolated to Charging Pump Intermediate Seal Cooler & Component Cooling Water Isolated.Caused by Valve Misposition Due to Operator Error. Valve Repositioned & Personnel Counseled |
- on 850215,svc Water Isolated to Charging Pump Intermediate Seal Cooler & Component Cooling Water Isolated.Caused by Valve Misposition Due to Operator Error. Valve Repositioned & Personnel Counseled
| | | 05000280/LER-1985-002-01, :on 850113,lo-lo Level in Steam Generator B Caused Reactor Scram.Caused by Failure of Personnel to Adequately Control Steam Generator Level.Feedwater Bypass Flow Indication Design Installed |
- on 850113,lo-lo Level in Steam Generator B Caused Reactor Scram.Caused by Failure of Personnel to Adequately Control Steam Generator Level.Feedwater Bypass Flow Indication Design Installed
| | | 05000281/LER-1985-002, :on 850215,charging Pump Intermediate Seal Coolers Discovered Improperly Aligned.Caused by Personnel Error.Proper Intermediate Seal Cooler Placed in Svc. Personnel Reinstructed Re Following Procedures |
- on 850215,charging Pump Intermediate Seal Coolers Discovered Improperly Aligned.Caused by Personnel Error.Proper Intermediate Seal Cooler Placed in Svc. Personnel Reinstructed Re Following Procedures
| | | 05000281/LER-1985-003, :on 850423,outside Recirculation Spray Pump a Suction Valve Found Degraded & Pump B Valve Found Inoperable.Caused by Inadequate Sector Gear & Sheared Pins in Extension Shafts.Pins Replaced |
- on 850423,outside Recirculation Spray Pump a Suction Valve Found Degraded & Pump B Valve Found Inoperable.Caused by Inadequate Sector Gear & Sheared Pins in Extension Shafts.Pins Replaced
| | | 05000280/LER-1985-003, :on 850126,reactor Tripped Due to Voltage Transient Induced on Vital Bus I When Momentary Overload Condition Caused Circuit Breaker 13 to Trip Open.Cause Unknown.Plant Returned to Stable Condition |
- on 850126,reactor Tripped Due to Voltage Transient Induced on Vital Bus I When Momentary Overload Condition Caused Circuit Breaker 13 to Trip Open.Cause Unknown.Plant Returned to Stable Condition
| | | 05000281/LER-1985-003-03, :on 850428,Type C Testing Revealed Both Outside Recirculation Spray Pump Suction Valves MOV-RS-255A, B(Eiis 20) Inoperable.On 850510,outside Recirculation Spray Pump Discharge Valve Inoperable |
- on 850428,Type C Testing Revealed Both Outside Recirculation Spray Pump Suction Valves MOV-RS-255A, B(Eiis 20) Inoperable.On 850510,outside Recirculation Spray Pump Discharge Valve Inoperable
| | | 05000281/LER-1985-004-01, :on 850501,discrepancies Noted W/Rosemount Model 1153 Transmitters & Conax Environ Seal Assemblies. Caused by Overtorqued Hollow Screws in Transmitters & Improper Installation of Connectors |
- on 850501,discrepancies Noted W/Rosemount Model 1153 Transmitters & Conax Environ Seal Assemblies. Caused by Overtorqued Hollow Screws in Transmitters & Improper Installation of Connectors
| | | 05000281/LER-1985-004-03, :on 850501,degraded Terminal Screws Used to Terminate Field Wiring Inside Rosemount Transmitters & Conax Seal Assemblies Did Not Provide Positive Environ Seal. Caused by Overtorquing Hollow Screws |
- on 850501,degraded Terminal Screws Used to Terminate Field Wiring Inside Rosemount Transmitters & Conax Seal Assemblies Did Not Provide Positive Environ Seal. Caused by Overtorquing Hollow Screws
| | | 05000280/LER-1985-004, :on 850127,reactor Tripped Due to Closing of Four Turbine Stop Valves.Caused by Insufficient Consideration of Steam Leakage Effect on Plant Parameters. Plant Parameters Returned to Stable Conditions |
- on 850127,reactor Tripped Due to Closing of Four Turbine Stop Valves.Caused by Insufficient Consideration of Steam Leakage Effect on Plant Parameters. Plant Parameters Returned to Stable Conditions
| | | 05000281/LER-1985-005-03, :on 850514 & 15,automatic Initiation of Hazard Zones 8 & 4,respectively,locked Out W/No Fire Watch Present. Caused by Lack of Procedure & Training.Procedure for CO2 Sys Lockouts Will Be Implemented |
- on 850514 & 15,automatic Initiation of Hazard Zones 8 & 4,respectively,locked Out W/No Fire Watch Present. Caused by Lack of Procedure & Training.Procedure for CO2 Sys Lockouts Will Be Implemented
| | | 05000280/LER-1985-005-01, :on 850403,operator Discovered Lockout of Automatic Initiation of CO2 for Fire Zone 7 W/O Required Fire Watch.Caused by Misunderstanding Between Personnel Re Fire Zone Tagging |
- on 850403,operator Discovered Lockout of Automatic Initiation of CO2 for Fire Zone 7 W/O Required Fire Watch.Caused by Misunderstanding Between Personnel Re Fire Zone Tagging
| | | 05000280/LER-1985-006, :on 850128,reactor Trip Occurred Due to Differential Pressure anti-motoring Turbine Trip.Caused by Isolation of Exhaust Pressure Sensing Line Root Valve in anti-motoring Instrumentation.Plant Returned to Svc |
- on 850128,reactor Trip Occurred Due to Differential Pressure anti-motoring Turbine Trip.Caused by Isolation of Exhaust Pressure Sensing Line Root Valve in anti-motoring Instrumentation.Plant Returned to Svc
| | | 05000281/LER-1985-007-02, :on 850612,spurious Safety Injection Occurred During Periodic Functional Test.Caused by Procedure Deficiency.Function Test Will Be Modified to Provide Separate Steps & Signoffs |
- on 850612,spurious Safety Injection Occurred During Periodic Functional Test.Caused by Procedure Deficiency.Function Test Will Be Modified to Provide Separate Steps & Signoffs
| | | 05000280/LER-1985-007, :on 850429,turbine/reactor Trip Occurred as Result of Main Feed Pump a Trip.Caused When Valve Open Signal Not Sent to Feed Pump Trip Logic.Valve Position Actuator Arm Modified |
- on 850429,turbine/reactor Trip Occurred as Result of Main Feed Pump a Trip.Caused When Valve Open Signal Not Sent to Feed Pump Trip Logic.Valve Position Actuator Arm Modified
| | | 05000281/LER-1985-008-01, :on 850619,auxiliary Ventilation Damper I-VS-MOD-58A Drifted Closed.Cause Undetermined.Unit 2 Containment Purge Stopped & Damper Manually Opened.Parts Needed to Repair Actuator Ordered |
- on 850619,auxiliary Ventilation Damper I-VS-MOD-58A Drifted Closed.Cause Undetermined.Unit 2 Containment Purge Stopped & Damper Manually Opened.Parts Needed to Repair Actuator Ordered
| | | 05000281/LER-1985-008, :on 850619,auxiliary Ventilation Damper 1-VS-MOD-58A Drifted Closed.Caused by Short in Damper Actuator Relief Valve Coil.Actuator Sent to Mfg for Overhaul |
- on 850619,auxiliary Ventilation Damper 1-VS-MOD-58A Drifted Closed.Caused by Short in Damper Actuator Relief Valve Coil.Actuator Sent to Mfg for Overhaul
| | | 05000280/LER-1985-008, :on 850318,tag Inadvertently Placed on Fire Zone 5,locking Out Automatic Initiation of CO2 W/O Fire Watch as Required by Tech Specs.Caused by Operator Error.Sys Returned to Automatic.Red Tags Used in Future |
- on 850318,tag Inadvertently Placed on Fire Zone 5,locking Out Automatic Initiation of CO2 W/O Fire Watch as Required by Tech Specs.Caused by Operator Error.Sys Returned to Automatic.Red Tags Used in Future
| | | 05000280/LER-1985-009, :on 850512,PORV PCV-1455C Cycled Twice Due to Overpressure Condition.Caused by Failure of Normal Letdown Pressure Control Valve PCV-1145 Due to Positioner Misadjustment.Part Adjusted |
- on 850512,PORV PCV-1455C Cycled Twice Due to Overpressure Condition.Caused by Failure of Normal Letdown Pressure Control Valve PCV-1145 Due to Positioner Misadjustment.Part Adjusted
| | | 05000281/LER-1985-009-03, :on 851107,six Individual Rod Position Indicators in Controlling Bank D & One Indicator in Bank C Declared Inoperable Due to Incorrect Positions.Caused by Instrumentation Drift.Indicators Calibr |
- on 851107,six Individual Rod Position Indicators in Controlling Bank D & One Indicator in Bank C Declared Inoperable Due to Incorrect Positions.Caused by Instrumentation Drift.Indicators Calibr
| | | 05000281/LER-1985-009, :on 851107,individual Rod Position Indicators for Six Rods in Controlling Bank D & One Rod in Controlling Bank C Indicated More than 12 Steps from Bank Demand Position.Caused by Instrument Drift |
- on 851107,individual Rod Position Indicators for Six Rods in Controlling Bank D & One Rod in Controlling Bank C Indicated More than 12 Steps from Bank Demand Position.Caused by Instrument Drift
| | | 05000281/LER-1985-010-02, :on 850813,unit Experienced Turbine Runback to Approx 48% Power Resulting in Partial Loss of Emergency Bus. Caused by Tripped Series Breaker to Vital Bus 2-1 Sola Transformer.Breakers Reset |
- on 850813,unit Experienced Turbine Runback to Approx 48% Power Resulting in Partial Loss of Emergency Bus. Caused by Tripped Series Breaker to Vital Bus 2-1 Sola Transformer.Breakers Reset
| | | 05000281/LER-1985-010-01, :on 850813,turbine Runback to Approx 48% Power Occurred,Initiating Loss of Vital Bus 2-I.Caused by Tripped Transformer Breaker.Breakers Replaced |
- on 850813,turbine Runback to Approx 48% Power Occurred,Initiating Loss of Vital Bus 2-I.Caused by Tripped Transformer Breaker.Breakers Replaced
| | | 05000280/LER-1985-010, :on 850515,intermediate Range High Flux Trip Bistables NI-35 & NI-36 Tripped at 30% & 31% Power, Respectively.Apparently Caused by Lack of Experience in Developing Intermediate Setpoints |
- on 850515,intermediate Range High Flux Trip Bistables NI-35 & NI-36 Tripped at 30% & 31% Power, Respectively.Apparently Caused by Lack of Experience in Developing Intermediate Setpoints
| | | 05000281/LER-1985-011-02, :on 851023,emergency Diesel Generator (EDG) Automatically Started.Caused by Inadequate Design Change Test Procedure.Control of EDG 2 Transferred to Main Control Room Panel & Diesel Shut Down |
- on 851023,emergency Diesel Generator (EDG) Automatically Started.Caused by Inadequate Design Change Test Procedure.Control of EDG 2 Transferred to Main Control Room Panel & Diesel Shut Down
| | | 05000280/LER-1985-011, :on 850626,while Racking Charging Pump B Breaker 15J5 Out for Pump Maint,Normal Feeder Breaker 15H6 for Operating Charging Pump C Tripped Due to Electrical Interlock.Caused by Inadequate Precautions |
- on 850626,while Racking Charging Pump B Breaker 15J5 Out for Pump Maint,Normal Feeder Breaker 15H6 for Operating Charging Pump C Tripped Due to Electrical Interlock.Caused by Inadequate Precautions
| | | 05000281/LER-1985-012-01, :on 851026,results of RCS Sample Indicated Drop in Boric Acid Concentration from 2,217 Ppm to 1,952 Ppm. Caused by Out of Calibr Flow Transmitter That Inputs to Boric Acid Integrator.Flow Transmitter Calibr |
- on 851026,results of RCS Sample Indicated Drop in Boric Acid Concentration from 2,217 Ppm to 1,952 Ppm. Caused by Out of Calibr Flow Transmitter That Inputs to Boric Acid Integrator.Flow Transmitter Calibr
| | | 05000280/LER-1985-012, :on 850609,during Testing of Discharge Valves, Chemical Addition Tank Water Level Decreased.Caused by Failed Closed Contact,Resulting in Valve Reopening.Flow Path Isolated & Failed Contacts Replaced |
- on 850609,during Testing of Discharge Valves, Chemical Addition Tank Water Level Decreased.Caused by Failed Closed Contact,Resulting in Valve Reopening.Flow Path Isolated & Failed Contacts Replaced
| | | 05000280/LER-1985-013, :on 850721,containment Temp Exceeded 120 F for Approx 3 H.Caused by Loss of Component Cooling Chiller Unit. Component Restarted & Chiller Condenser Svc Water Tubes Cleaned |
- on 850721,containment Temp Exceeded 120 F for Approx 3 H.Caused by Loss of Component Cooling Chiller Unit. Component Restarted & Chiller Condenser Svc Water Tubes Cleaned
| | | 05000280/LER-1985-013-01, :on 850721,containment Temp Exceeded 120 F for Approx 3 H.Caused by Loss of Component Cooling Chiller I-CD-REF-IA Due to Tube Fouling on Water Side Causing High Chiller Condenser Pressure |
- on 850721,containment Temp Exceeded 120 F for Approx 3 H.Caused by Loss of Component Cooling Chiller I-CD-REF-IA Due to Tube Fouling on Water Side Causing High Chiller Condenser Pressure
| | | 05000281/LER-1985-013-02, :on 851107,turbine Trip/Reactor Trip Occurred as Result of High Steam Generator Level.Caused by Operator Inexperience W/Manual Feed Control During Low Power Startup Conditions.Status Tree Reviews Performed |
- on 851107,turbine Trip/Reactor Trip Occurred as Result of High Steam Generator Level.Caused by Operator Inexperience W/Manual Feed Control During Low Power Startup Conditions.Status Tree Reviews Performed
| | | 05000281/LER-1985-014-01, :on 851226,control Rod Urgent Failure Alarm Occurred as Rods Stepping in Automatic.Caused by Problem in Logic Cabinet Pulser Card A101.Card Replaced & Sys Tested Satisfactorily |
- on 851226,control Rod Urgent Failure Alarm Occurred as Rods Stepping in Automatic.Caused by Problem in Logic Cabinet Pulser Card A101.Card Replaced & Sys Tested Satisfactorily
| | | 05000280/LER-1985-017-01, :on 850911,following Reactor trip,I-131 Level Exceeded Tech Spec Limit.Caused by Fuel Element Defects in Reactor Core.Dose Equivalent Monitored Until Less than 1.0 Uci/Cc |
- on 850911,following Reactor trip,I-131 Level Exceeded Tech Spec Limit.Caused by Fuel Element Defects in Reactor Core.Dose Equivalent Monitored Until Less than 1.0 Uci/Cc
| | | 05000280/LER-1985-018, :on 850911,turbine Trip/Reactor Trip Occurred Due to Low Condenser Vacuum Signal.Caused by Operation Error.Covers Placed on Inlet Valve Switches & Operator Reinstructed |
- on 850911,turbine Trip/Reactor Trip Occurred Due to Low Condenser Vacuum Signal.Caused by Operation Error.Covers Placed on Inlet Valve Switches & Operator Reinstructed
| | | 05000281/LER-1985-018-01, :on 850911,turbine Trip/Reactor Trip Occurred Due to Low Condenser Vacuum Signal.Caused by Operator Inadvertently Closing Four Condenser Inlet Valves While Throttling Four Condenser Outlet Valves |
- on 850911,turbine Trip/Reactor Trip Occurred Due to Low Condenser Vacuum Signal.Caused by Operator Inadvertently Closing Four Condenser Inlet Valves While Throttling Four Condenser Outlet Valves
| | | 05000280/LER-1985-019, :on 850927,individual Rod Position Indicator for Two Rods Inoperable.Spurious Incorrect Rod Position Indication Is Generic Westinghouse PWR Concern.Portion of Sys Outside Containment Tested & No Problems Found |
- on 850927,individual Rod Position Indicator for Two Rods Inoperable.Spurious Incorrect Rod Position Indication Is Generic Westinghouse PWR Concern.Portion of Sys Outside Containment Tested & No Problems Found
| | | 05000280/LER-1985-020, :on 850927,following Controlled Shutdown Due to Hurricane Gloria,Iodine Spike Discovered.Caused by Known Fuel Element Defects in Reactor Core.Level of Dose Equivalent I-131 Monitored Per Tech Spec Table 4.1-2B |
- on 850927,following Controlled Shutdown Due to Hurricane Gloria,Iodine Spike Discovered.Caused by Known Fuel Element Defects in Reactor Core.Level of Dose Equivalent I-131 Monitored Per Tech Spec Table 4.1-2B
| | | 05000280/LER-1985-021, :on 851114,unexpected Start of Auxiliary Feed Pump 2-FW-P-3A Occurred.Caused by Open Coil in Bfd Relay AFP-2XA.Relay Replaced & Tested Satisfactorily |
- on 851114,unexpected Start of Auxiliary Feed Pump 2-FW-P-3A Occurred.Caused by Open Coil in Bfd Relay AFP-2XA.Relay Replaced & Tested Satisfactorily
| | | 05000280/LER-1985-022-01, :on 851121,spurious auto-start of Auxiliary Vent Emergency Fans Occurred.Cause Not Determined.Steam Generator Pressure Returned to Normal & Letdown Trip Valve TV-1204 Opened |
- on 851121,spurious auto-start of Auxiliary Vent Emergency Fans Occurred.Cause Not Determined.Steam Generator Pressure Returned to Normal & Letdown Trip Valve TV-1204 Opened
| | | 05000280/LER-1985-022, :on 851121, Auxiliary Vent Sys Safety Mode Initiated Alarm Received.Caused by Momentary Decrease of Instrument Air Pressure from Ice Formation.Bypass Valve Adjusted |
- on 851121, Auxiliary Vent Sys Safety Mode Initiated Alarm Received.Caused by Momentary Decrease of Instrument Air Pressure from Ice Formation.Bypass Valve Adjusted
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