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7-I GULF STA TES UTILXTIES COMPANY ttyt f: ht P.D it Ah ?N PO$1 Of hcl &DX 2D f.1 f fANT $ W,'.L LOJ:OAM N711 Ant. A CM'T 6N Lib tiy>4 M b(10f1 April 9, 1989 RBG-32683 File Nos. G9.5, G9.25.1.3 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
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Gentlemen:
River Bend Station - Unit 1 Docket No. 50-458 Please find enclosed Licensee Event Report No.90-007 for i
River Bend Station - Unit 1.
This report is being subnitted pursuant to 10CFR50.73.
Sincerely, 2
Manager-Oversight River Bend Nuclear Group l
TFP/WH0/PDG/es /JCH/ch i
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U.S. Nuclear egulatory Connission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 V
l NRC Resident inspector P.O. Box 1051 St. Francisville, LA 70775 INPO Records Center 1100 Circle 75 Parkway Atlanta, GA 30339-3064 l
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At 1248 on 3/11/90 with the unit at 100 percent power the Division II control building ventilation system isolated and its respective filtration unit automatically initiated.
The initiation was caused by a spurious signal from the control building intake radiation monitor 1RMS*RE13B.
The operators determined that no actual high radiation condition existed and returned the system to its normal configuration.
Radiation monitor 1RMS*RE13B and other radiation monitors have previously shown susceptibility to electrical transients.
Therefore, two modifications were implemented prior to this event in order to reduce spurious radiation monitor trips on a programmatic basis by reducing radiation monitor / detector susceptibility to electrical noise and transients.
The safe operation of the plant and the health and safety of the public were not affected as a result of this event.
The continued operation of the plant will have no impact on safety since the system which actuated placed the plant in a more conservative configuration by filtering the supply air to the main control room.
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RIVER BEND STATIO!1 010 Ol ? M 013 O l017 o l6 ]o lo lc l d l 519 91 0 REPORTED CONDITION At 1248 on 3/11/90 with the unit at 100 percent power a transformer at a local industrial facility failed.
Consequently a severe transient on the electrical distribution system occurred which resulted in the Division II control building ventilation system (*VI*)
isolating and its respective filtration unit (IHVC* PLT 3D)
(*FLT*) automatically initiating.
The initiation was caused by a spurious high alarm signal from the control building intake radiation monitor 1RMS*RE13B (
The operators returned the system to a
normal configuration after verifying that a high radiation condition did not exist.
The spurious high alarm signal from the radiation monitor and subsequent Division II control building ventilation system isolation with auto-initiation of the filtration unit constitutes an engineered safety feature (ESP) actuation.
Therefore, this event is reportable under 10CFR50.73 (a) (2) (iv).
INVESTIGATION The severity of the transient was such that the voltage on switchgear IENS*SWGID dropped to 3193V.
As a result, 1RMS*RE13B went into a high alarm state causing the actuation of the Division II control building filter trains, per design.
In
- addition, all inverters swapped to battery supply during the transient and provided appropriate alarms to control room annunciators.
The ventilation system and radiation monitor were returned to a
normal configuration after the high radiation alarm was determined to be invalid.
Inverter alarms were reset following the event and the response was verified to be in accordanco with the design.
Previously submitted LERs concerning events in which ESF actuations occurred due to spurious actuations of radiation monitors have been reviewed.
In seven cases radiation monitors have shown susceptibility to electrical noise / transients.
Four of these incidents occurred in 1986, one in 1987, one in 1988, and one in 1989.
These events have been reported in LERs86-020, 86-040,86-052, 86-062,87-008, 88-008 and 89-037.
Four of these previous occurrences were caused by 1RMS*RE138.
Electrical transients of this severity have an impact on downstream equipment fed from unregulated power supplies.
This is evidenced by 1RMS*RE13B going into high alarm along with 19 other monitors which momentarily lost sample flow plus two other monitors entering high alarm conditions due to the electrical transient.
The problems with electrical noise / transients resulted in two major modifications following electrical noise studies on the radiation monitors.
MR86-1113 installed RC networks (voltage suppressors) at each radiation monitor noise source such as manual _ switches and light g,.o===
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MR86-1669 has changed preamplifier discriminator settings to make the detector circuitry less sensitive to electrical noise.
These modifications have been very effective as evidenced by spurious radiation monitor actuations due to electrical noise / transients being reduced from_four per year in 1986 to one per year in 1987, 1988, and 1989.
Radiation monitor 1RMS*RE13B is apparently much more sensitive to electrical noise than other radiation monitors.
However, further filtering, voltage suppression or discrimination against electrical noise for 1 RMS
- RE13 B is not feasible without adversely affecting detector sensitivity.
CORRECTIVE ACTION
Based on the improved performance of radiation monitors subsequent to the implementation of MR86-1113 and MR86-1669, along with the severity of the subject electrical transient to which the monitor was subiected, no further corrective action is necessary.
SAFETY ASSF;SSMENT The safe operation of the plant and the health and safety of the public were not affected as a result of this -event.
The continued operation of the plant will have no impact on safety since the system which actuated placed the plant in a more conservative configuration
.by tiltering the air entering the main control room.
NOTE:
Energy Industry Identification System Codes are identified in the text as
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| 05000458/LER-1990-001, :on 900103,isolation of RCIC Steam Supply Inboard Isolation Valve Occurred During Surveillance Testing of RCIC Sys.Caused by Technician Lifting Wrong Lead,Causing ESF Actuation.Lead Relanded on Terminal |
- on 900103,isolation of RCIC Steam Supply Inboard Isolation Valve Occurred During Surveillance Testing of RCIC Sys.Caused by Technician Lifting Wrong Lead,Causing ESF Actuation.Lead Relanded on Terminal
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-004, :on 900211,div II Emergency 125-volt Dc Bus Experienced Voltage Spike Causing Topaz Inverter Unit to Trip.Caused by Drift of Inverter High Voltage Trip Setpoint. Inverters Calibr |
- on 900211,div II Emergency 125-volt Dc Bus Experienced Voltage Spike Causing Topaz Inverter Unit to Trip.Caused by Drift of Inverter High Voltage Trip Setpoint. Inverters Calibr
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-006, :on 900309,error in Calculations for Pressure Temp Limit Curves in Tech Specs 3.4.6.1-1 Discovered.Caused by Personnel Error.Tech Spec Pressure Temp Limit Curves to Be Revised,Per Generic Ltr 88-11 |
- on 900309,error in Calculations for Pressure Temp Limit Curves in Tech Specs 3.4.6.1-1 Discovered.Caused by Personnel Error.Tech Spec Pressure Temp Limit Curves to Be Revised,Per Generic Ltr 88-11
| | | 05000458/LER-1990-007, :on 900311,control Bldg Ventilation Sys Isolated & Filtration Unit Initiated.Caused by Severe Electrical Transient.Performance of Radiation Monitors Improved Prior to Implementation of Procedures |
- on 900311,control Bldg Ventilation Sys Isolated & Filtration Unit Initiated.Caused by Severe Electrical Transient.Performance of Radiation Monitors Improved Prior to Implementation of Procedures
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-008, :on 900315,main Turbine Generator Tripped, Resulting in Reactor Scram.Caused by Loss of Field Relay. Relay Reworked & Returned to Svc After Testing & Maint Procedures Revised |
- on 900315,main Turbine Generator Tripped, Resulting in Reactor Scram.Caused by Loss of Field Relay. Relay Reworked & Returned to Svc After Testing & Maint Procedures Revised
| | | 05000458/LER-1990-009, :on 900319,both Inboard & Outboard Isolation Valves Failed Local Leak Rate Test.Caused by Silt & Corrosion Products Present in Both Valves.Disk Hinge Ping Area Cleaned & Valve Seats Inspected |
- on 900319,both Inboard & Outboard Isolation Valves Failed Local Leak Rate Test.Caused by Silt & Corrosion Products Present in Both Valves.Disk Hinge Ping Area Cleaned & Valve Seats Inspected
| | | 05000458/LER-1990-010, :on 900320,rope Barricade for High Radiation Area Removed.Caused by Personnel Error.Training on Radiation Protection Practices Will Be Provided to Plant Operators to Emphasize Importance of Requirements |
- on 900320,rope Barricade for High Radiation Area Removed.Caused by Personnel Error.Training on Radiation Protection Practices Will Be Provided to Plant Operators to Emphasize Importance of Requirements
| 10 CFR 50.73(a)(2)(1) | | 05000458/LER-1990-011, :on 900326,faulted Condition on Transformer 1NJS-X1A Resulted in Trip of Circuit Breaker ACB-016 on Switchgear 1NJS-SWGR1A.Caused by Random Failure of Transformer.Tranformer Replaced |
- on 900326,faulted Condition on Transformer 1NJS-X1A Resulted in Trip of Circuit Breaker ACB-016 on Switchgear 1NJS-SWGR1A.Caused by Random Failure of Transformer.Tranformer Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-012, :on 900401,ESF Actuations Occurred Due to Electrical Protection Assembly Breakers Trip.Caused by Voltage Regulator Failure.Replacement Voltage Regulator Card Installed in MG 1C71-S001B |
- on 900401,ESF Actuations Occurred Due to Electrical Protection Assembly Breakers Trip.Caused by Voltage Regulator Failure.Replacement Voltage Regulator Card Installed in MG 1C71-S001B
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-013, :on 900405,discovered That Control Bldg Chiller Motor Current Limiter C Set Incorrectly at 56% Instead of 100%.Caused by Incorrect Setting & Maint Activities.Loop Calibr Data Sheet Revised |
- on 900405,discovered That Control Bldg Chiller Motor Current Limiter C Set Incorrectly at 56% Instead of 100%.Caused by Incorrect Setting & Maint Activities.Loop Calibr Data Sheet Revised
| | | 05000458/LER-1990-014, :on 900407,reactor Scram Occurred While Testing Main Turbine Combined Intermediate Valves.Caused by Low Pressure Signal from Emergency Trip Sys of Electrohydraulic Control Sys.Two Solenoid Valves Replaced |
- on 900407,reactor Scram Occurred While Testing Main Turbine Combined Intermediate Valves.Caused by Low Pressure Signal from Emergency Trip Sys of Electrohydraulic Control Sys.Two Solenoid Valves Replaced
| | | 05000458/LER-1990-015, :on 900409,loss of Div II Reactor Protection Sys Bus Occurred Due to Trip of Electrical Protection Assembly.Another Trip Also Occurred on 900415.Caused by Faulty Integrated Circuit Logics |
- on 900409,loss of Div II Reactor Protection Sys Bus Occurred Due to Trip of Electrical Protection Assembly.Another Trip Also Occurred on 900415.Caused by Faulty Integrated Circuit Logics
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-016, :on 900414,insulator Fault on Local Grid Resulted in Trip of 500 Kv Breaker.Caused by Spurious Alarm Signal from Control Room Local Intake Radiation Monitor 1RMS*RE13B.Sys Returned to Normal Operation |
- on 900414,insulator Fault on Local Grid Resulted in Trip of 500 Kv Breaker.Caused by Spurious Alarm Signal from Control Room Local Intake Radiation Monitor 1RMS*RE13B.Sys Returned to Normal Operation
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-017, :on 900419,inadequate Fire Barrier in Shake Space Occurred Contrary to Tech Spec.Caused by Oversight. Roving Fire Watch Scheduled.Maint Will Rework Voids & Install Seismic Gap Seal |
- on 900419,inadequate Fire Barrier in Shake Space Occurred Contrary to Tech Spec.Caused by Oversight. Roving Fire Watch Scheduled.Maint Will Rework Voids & Install Seismic Gap Seal
| | | 05000458/LER-1990-019, :on 900425,RWCU Sys Isolation & ESF Actuation Occurred After Completion of Channel Check of Riley Temp Trip Unit.Caused by Unit Exceeding Differential Temp Setpoint of 46 F.Unit Replaced |
- on 900425,RWCU Sys Isolation & ESF Actuation Occurred After Completion of Channel Check of Riley Temp Trip Unit.Caused by Unit Exceeding Differential Temp Setpoint of 46 F.Unit Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-020, :on 900504,radwaste Operator Entered High Radiation Area W/O Dose Rate Meter,Alarming Dosimeter or Radiation Protection Technician Coverage.Caused by Personnel Error.Training Provided to Operators |
- on 900504,radwaste Operator Entered High Radiation Area W/O Dose Rate Meter,Alarming Dosimeter or Radiation Protection Technician Coverage.Caused by Personnel Error.Training Provided to Operators
| 10 CFR 50.73(a)(2)(1) | | 05000458/LER-1990-021, :on 900509,RWCU Sys Differential Flow High Trip Instrumentation Inoperable for Period Greater than Allowed by Tech Spec.Caused by Misinterpretation of Tech Spec 3/4.3.2,Table 3.3.2.-1.4.Personnel Retrained |
- on 900509,RWCU Sys Differential Flow High Trip Instrumentation Inoperable for Period Greater than Allowed by Tech Spec.Caused by Misinterpretation of Tech Spec 3/4.3.2,Table 3.3.2.-1.4.Personnel Retrained
| | | 05000458/LER-1990-022, :on 900518,HPCS Sys Declared Inoperable & 14-day Shutdown Limiting Condition for Operation Entered Due to Inoperative Suppression Pool Level Transmitter.Caused by Personnel Error.Reactor Operators Trained |
- on 900518,HPCS Sys Declared Inoperable & 14-day Shutdown Limiting Condition for Operation Entered Due to Inoperative Suppression Pool Level Transmitter.Caused by Personnel Error.Reactor Operators Trained
| | | 05000458/LER-1990-023, :on 900523,standby Gas Treatment & Annulus Mixing Sys Declared Inoperable.Caused by Failure of Radiation Monitor Sample Pump.Operation Section Procedure, OSP-012 Revised |
- on 900523,standby Gas Treatment & Annulus Mixing Sys Declared Inoperable.Caused by Failure of Radiation Monitor Sample Pump.Operation Section Procedure, OSP-012 Revised
| 10 CFR 50.73(a)(2)(1) | | 05000458/LER-1990-024, :on 900719,discovered Missed Fire Watch Patrol. Caused by Miscommunication & Inadequate Verification of Fire Watch Log.New Log Book Designed to Be Passed Down to Each Succeeding Shift,Will Be Used |
- on 900719,discovered Missed Fire Watch Patrol. Caused by Miscommunication & Inadequate Verification of Fire Watch Log.New Log Book Designed to Be Passed Down to Each Succeeding Shift,Will Be Used
| 10 CFR 50.73(a)(2)(1) | | 05000458/LER-1990-025, :on 900809,surveillance Requirements Not Performed on Valve Due to Omission from Tech Spec Table 3.6.4-1.Caused by Personnel Oversight.Monthly Operating Log Revised |
- on 900809,surveillance Requirements Not Performed on Valve Due to Omission from Tech Spec Table 3.6.4-1.Caused by Personnel Oversight.Monthly Operating Log Revised
| | | 05000458/LER-1990-026, :on 900810,RWCU Isolated.Caused by Short Circuit During Jumper Manipulation.Prompt Maint Work Order Initiated to Replace Blown Fuses |
- on 900810,RWCU Isolated.Caused by Short Circuit During Jumper Manipulation.Prompt Maint Work Order Initiated to Replace Blown Fuses
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-027, :on 900916,fire Watch Missed Due to Personnel Illness |
- on 900916,fire Watch Missed Due to Personnel Illness
| | | 05000458/LER-1990-028, :on 900930,RPS Actuation Occurred on High Level Scram Disharge Vol |
- on 900930,RPS Actuation Occurred on High Level Scram Disharge Vol
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-029, :on 901006,safety Relief Valve Air Supply Sys Removed from Svc Resulting in Violation of Tech Specs.W/ |
- on 901006,safety Relief Valve Air Supply Sys Removed from Svc Resulting in Violation of Tech Specs.W/
| 10 CFR 50.73(a)(2)(1) | | 05000458/LER-1990-030, :on 901010,high Radiation Area Violated Due to Personnel Error |
- on 901010,high Radiation Area Violated Due to Personnel Error
| 10 CFR 50.73(a)(2)(1) | | 05000458/LER-1990-031, :on 901003,areas Omitted from Hourly Fire Watch Patrols Due to Personnel Error |
- on 901003,areas Omitted from Hourly Fire Watch Patrols Due to Personnel Error
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000458/LER-1990-032, :on 901021,snubber Removed from Piping in Violation of Tech Spec 3.7.4 |
- on 901021,snubber Removed from Piping in Violation of Tech Spec 3.7.4
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000458/LER-1990-035, :on 901027,loss of Shutdown Cooling Occurred Due to Engineer Failing to Recognize Effect of Cable Removal |
- on 901027,loss of Shutdown Cooling Occurred Due to Engineer Failing to Recognize Effect of Cable Removal
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-036, :on 901104,Div I balance-of-plant Isolation Occurred During Mods to Wiring in Control Room Panel.W/ |
- on 901104,Div I balance-of-plant Isolation Occurred During Mods to Wiring in Control Room Panel.W/
| | | 05000458/LER-1990-037, :on 901105,two Contract Employees Entered High Radiation Area in Violation of Tech Specs |
- on 901105,two Contract Employees Entered High Radiation Area in Violation of Tech Specs
| | | 05000458/LER-1990-038, :on 901108,loosening of Common Neutral Connection in RPS a Resulted in Div I balance-of-plant Isolation & Loss of Shutdown Cooling.Caused by Design Engineer Error.Mod Request Revised |
- on 901108,loosening of Common Neutral Connection in RPS a Resulted in Div I balance-of-plant Isolation & Loss of Shutdown Cooling.Caused by Design Engineer Error.Mod Request Revised
| | | 05000458/LER-1990-039, :on 901109,power Lost of 480-volt Load Ctr, Causing Loss of RPS B Motor Generator Set & Isolations of RWCU & Div II Containment Isolation Valves.Caused by Inadequate Communication.Training Given |
- on 901109,power Lost of 480-volt Load Ctr, Causing Loss of RPS B Motor Generator Set & Isolations of RWCU & Div II Containment Isolation Valves.Caused by Inadequate Communication.Training Given
| | | 05000458/LER-1990-040, :on 901110,technician Inadvertently Shorted Relay Terminals,Energizing Relay & Causing Emergency Diesel Generator to Start Unexpectedly.Caused by Personnel Error. Generator Manually Secured |
- on 901110,technician Inadvertently Shorted Relay Terminals,Energizing Relay & Causing Emergency Diesel Generator to Start Unexpectedly.Caused by Personnel Error. Generator Manually Secured
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-041, :on 901113,operability Containment Isolation Valve Indeterminate Due to Improperly Installed Torque Switch.Torque Switch Removed & Installed in Proper Position |
- on 901113,operability Containment Isolation Valve Indeterminate Due to Improperly Installed Torque Switch.Torque Switch Removed & Installed in Proper Position
| | | 05000458/LER-1990-043, :on 901119,unanticipated Safety Feature Actuation of Rha Sys a Sys & Control Bldg Emergency Filter Train Occurred.Caused by Error in Preparation of Retest Procedure.Personnel Will Receive Training |
- on 901119,unanticipated Safety Feature Actuation of Rha Sys a Sys & Control Bldg Emergency Filter Train Occurred.Caused by Error in Preparation of Retest Procedure.Personnel Will Receive Training
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-044, :on 901119,div II Valves & Dampers Isolated When Breaker Opened Instead of Power Supply Breaker Causing Deenergization of Power Line Conditioner.Caused by Personnel Failure to Follow Procedure |
- on 901119,div II Valves & Dampers Isolated When Breaker Opened Instead of Power Supply Breaker Causing Deenergization of Power Line Conditioner.Caused by Personnel Failure to Follow Procedure
| | | 05000458/LER-1990-045, :on 901121,unplanned ESF Actuation Occurred During Surveillance Testing of Drywell Bypass Leakage Rate. Caused by Inadequate Procedural Steps in Surveillance Test Procedure.Hpcs Suction Path Automatic Transfer Performed |
- on 901121,unplanned ESF Actuation Occurred During Surveillance Testing of Drywell Bypass Leakage Rate. Caused by Inadequate Procedural Steps in Surveillance Test Procedure.Hpcs Suction Path Automatic Transfer Performed
| | | 05000458/LER-1990-046, :on 901205,unplanned ESF Actuation Occurred When Spurious Trip Signal Received from RCIC Equipment Room Differential Temp Instrumentation.Caused by Isolation Valve Stroked Closed.New Switch Installed |
- on 901205,unplanned ESF Actuation Occurred When Spurious Trip Signal Received from RCIC Equipment Room Differential Temp Instrumentation.Caused by Isolation Valve Stroked Closed.New Switch Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-047, :on 901212,reactor Scrammed Due to Turbine Control Valve Fast Closure Signal During Valve Testing. Caused by Low electro-hydraulic Trip Sys Pressure Transient. Orifices Installed on Tcvs,Tsvs & CIVs |
- on 901212,reactor Scrammed Due to Turbine Control Valve Fast Closure Signal During Valve Testing. Caused by Low electro-hydraulic Trip Sys Pressure Transient. Orifices Installed on Tcvs,Tsvs & CIVs
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000458/LER-1990-048, :on 901224,EQ Operability Status of Two H Ingniters Apparently Exceeded Lifetimes.Caused by Temps Higher than Originally Used to Calculate Lifetimes.Six H Igniters & Associated Cables Replaced |
- on 901224,EQ Operability Status of Two H Ingniters Apparently Exceeded Lifetimes.Caused by Temps Higher than Originally Used to Calculate Lifetimes.Six H Igniters & Associated Cables Replaced
| 10 CFR 50.73(a)(2)(1) |
|