LER-1980-083, /01X-1:on 801118,average Power Range Monitor Channel D Was Inoperable & Channels B or F Bypassed Against Tech Spec.Caused by Crosswiring Low Power Range Monitor Detectors 44-37B & 44-37C.Wiring Corrected |
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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 81- 083/0l x-1 Page 1
of 3 During normal operation, while conducting Local Power Range Monitor 8
(LPRM) response tests, it was discovered that LPRM detectors44-37B and 44-37C were cross-wired. As a result of this cross-wiring, Average Power Range Monitor (APRM) Cnannel "D" was determined inoperable because I
only one "B Level" LPRM input was present which is contrary to the requirements of Technical Specifications Table 3.1-1, Note 10.
APRM "D" i
was bypassed and tagged until the instrument was made operable. This i
action was accomplished by restoring LPRM 12-37B (which had been bypassed at an earlier time) to the operating mode.
)
)
As a result of these findings and discussions in a Plant Operations Review Committee (PORC) meeting held on November 18, 1980, additional j
investigation into the event was initiated. This investigation revealed that on a number of occassions during the time period between 1058 on October 8,1980 and 0228 on October 25, 1980 the minimum requirements of Technical Specification Table 3 1-1 were not met for a total of approxi-mately nine hours. Shown below is a summary of the occassions in which APRM "B" or "F" was bypassed while APRM "D" was inoperable (but not known to the plant staff) due to an inadequate number of "B Level" inputs:
i DATE TIME REMARKS 1.
10/8/80 1058 LPRM 12-37B bypassed due to drif t.
This action made APRM "D" Inoperable because the 44-37B LPRM input was actually an input from LPRM 44-37C.
Periods of time during which the requirements of Technical Specification Table 3.1-1 were not met began at this point.
2.
10/ 8 -
Various APRM "B" or "F" was bypassed on a number of 10/13 occasions for the routine conduct of surveillance.
Each time APRM "B" or "F" was bypassed the minimum requirements of Tecnnical Specification Table 3.1-1 was not met due to the inoperable condi tion of APRM "D".
The total time of these events was approximately 127 minutes.
3 10/13/80 1321 Reactor scram due to Reactor Protection System (RPS) MG problem. No change in APRM status.
l
i POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 81-083/OlX-1 Page 2
of 3
DATE TIME REMARKS 4.
10/13 -
Various APRM "B" or "F" bypassed on a number of occasions 10/16 totaling approximately 359 minutes while the plant was shutdown following reactor scram on October 13, 1980.
5 10/16/80 1904 Commenced plant startup.
6.
10/17 -
Various APRM "B" or "F" bypassed for a total of approximately 10/25 42 minutes for routine APRM surveillance.
7 10/25/80 0228 LPRM 44-378 and 44-37C cross-wiring problem found. APRM "D" bypassed and tagged. This action ended those periods of time when the requirements of Technical Specifications Table 3.1-1 were not met.
8.
10/25/80 1700 LPRM 12-37B was removed f rom bypass and placed in " operate" restoring APRM "D" to a fully operable conditton.
9.
11/18/80 N/A PORC reviewed the event described in item 7, above and initiated the investigation described in this LER resulting in the determination that the plant had been operating for varying periods of time between October 8,1980 and October 25, 1980 in a condition less conservative than the least conservative aspect of LCO permitted by Table 3.1-1.
The total time during which Technical Specification Table 3 1-1 limits were not met was approximately nine (9) hours or approximately 2.3% of the time.
Placing APRM "D" In bypass until it was restored to a fully operable condition by placing LPRM 12-37B in operate brought the plant in full compliance with the requirements of Technical Specification Table 3.1-1.
In addition, ~ LPRM response tests results and other data which might provide an Indication of other LPRM wiring errors has been evaluated to provide assurance that the remaining LPRM detectors are properly wired.
The cross-wiring of the detectors is believed to have occurred within primary containment when LPRM detectors were replaced during the 1980 refueling outage.
Following a plant shutdown on January 17, 1981 a primary containment entry was made and the existance of a wiring error at the connection between plant wiring and LPRM string connectors was conf i rmed.
The wiring error was corrected and a review of administrative controls associated with the installation and testing of LPRM strings was conducted. As a result of this review the following actions will be l
l taken to prevent recurrence:
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9 POWER AUTHORITY OF THE STATE OF NEW YORK i
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 81- 083/0lx-1 Page 3
of 3
1.
Permanent labels will be affixed to the plant wiring that connects to the LPRM string connectors. These labels will allow rapid and positive verification that each detector is connected to the proper signal cable.
2.
Procurement and installation of the labels and revision of the administrative controls associated with installation of LPRM strings is expected to be complete prior to the next LPRM replacement.
14 review of the possible effect on core performance calculations indicates that since the cross wiring was associated with a LPRM string near the core periphery (not in a high power region) other higher power fuel bundles were at all times more limiting with respect to Minimum Critical Power Ratio, Limiting Heat Generation Rate and Maximum Fraction of Limiting Power Density parameters. As a result, the FitzPatrick plant does not consider a significant hazard to have existed.
NOTE:
Vertical lines in right-hand margin indicate those portions of the attachment changed by Revision 1.
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| 05000333/LER-1980-001-03, /03L-0:on 800101,during Surveillance Testing, Average Power Range Monitor E Downscale Trip Found at 2.0/125 Compared to Tech Spec Limit of Equal to or Greater than 2.5/125.Caused by Instrument Drift.Instrument Calibr | /03L-0:on 800101,during Surveillance Testing, Average Power Range Monitor E Downscale Trip Found at 2.0/125 Compared to Tech Spec Limit of Equal to or Greater than 2.5/125.Caused by Instrument Drift.Instrument Calibr | | | 05000333/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000333/LER-1980-002, Forwards LER 80-002/04L-0 | Forwards LER 80-002/04L-0 | | | 05000333/LER-1980-002-04, /04L-0:on 800102,failure of Makeup Water Sys Neutralizer Tank Discharge Valve Allowed Release of Approx 50,000 Gallons Regeneration Waste Water W/Ph Outside Tech Spec Limit.Caused by Solenoid Valve Sticking.Valve Cleaned | /04L-0:on 800102,failure of Makeup Water Sys Neutralizer Tank Discharge Valve Allowed Release of Approx 50,000 Gallons Regeneration Waste Water W/Ph Outside Tech Spec Limit.Caused by Solenoid Valve Sticking.Valve Cleaned | | | 05000333/LER-1980-003-03, /03L-0:on 800106,during Surveillance Testing of torus-to-drywell Vacuum Breakers,Torus Water Level Decreased Approx 1 Inch Below Tech Spec Limit.Caused by Testing of Breakers,Allowing Torus Water to Fill Downcomer Pipes | /03L-0:on 800106,during Surveillance Testing of torus-to-drywell Vacuum Breakers,Torus Water Level Decreased Approx 1 Inch Below Tech Spec Limit.Caused by Testing of Breakers,Allowing Torus Water to Fill Downcomer Pipes | | | 05000333/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000333/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000333/LER-1980-004-03, /03L-0:on 800107,during Surveillance Testing,One of Four Core Spray Injection Permissive Switches Found to Be Set Approx 10 Psi Below Tech Spec Limit.Caused by Instrument Drift.Switch Recalibr | /03L-0:on 800107,during Surveillance Testing,One of Four Core Spray Injection Permissive Switches Found to Be Set Approx 10 Psi Below Tech Spec Limit.Caused by Instrument Drift.Switch Recalibr | | | 05000333/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000333/LER-1980-005-03, /03L-0:on 800107,during Review of Reactor Water Chemistry Data,Noted That Some Required Samples Were Not Obtained.Technicians Did Not Take Samples Due to Low Level Conductivity & Chloride Ion Concentrations | /03L-0:on 800107,during Review of Reactor Water Chemistry Data,Noted That Some Required Samples Were Not Obtained.Technicians Did Not Take Samples Due to Low Level Conductivity & Chloride Ion Concentrations | | | 05000333/LER-1980-006-03, Core Spray Injection Valve 14-MOV-12A Improperly Operated During 791221 Surveillance Test.Caused by Misoperation of Valve Circuit Breaker Overload Trip Device | Core Spray Injection Valve 14-MOV-12A Improperly Operated During 791221 Surveillance Test.Caused by Misoperation of Valve Circuit Breaker Overload Trip Device | | | 05000333/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000333/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000333/LER-1980-007-03, /03L-0:on 800109,during Normal Operation,B Loop of RHR Declared Inoperable While Hanger H10-28 Was Inoperable for IE Bulletin 79-02 Testing.Caused by Failure of Concrete Anchors Under Pull Test.Repairs Made | /03L-0:on 800109,during Normal Operation,B Loop of RHR Declared Inoperable While Hanger H10-28 Was Inoperable for IE Bulletin 79-02 Testing.Caused by Failure of Concrete Anchors Under Pull Test.Repairs Made | | | 05000333/LER-1980-008-03, /03L-0:on 800109,while Performing Surveillance, Core Spray Valve 14-MOV-12B Failed to Open as Required. Caused by Torque Switch Not Being Bypassed for Sufficient Time Period.Adjusted Torque & Limit Switches | /03L-0:on 800109,while Performing Surveillance, Core Spray Valve 14-MOV-12B Failed to Open as Required. Caused by Torque Switch Not Being Bypassed for Sufficient Time Period.Adjusted Torque & Limit Switches | | | 05000333/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000333/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000333/LER-1980-009-03, /03L-0:on 800110,during Normal Operation,Diesel Fire Pump Made Inoperable to Correct Minor Boil Over of Engine Following Shutdown.Boil Over Caused by Defective Coolant Sys Cap.Cap Replaced | /03L-0:on 800110,during Normal Operation,Diesel Fire Pump Made Inoperable to Correct Minor Boil Over of Engine Following Shutdown.Boil Over Caused by Defective Coolant Sys Cap.Cap Replaced | | | 05000333/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000333/LER-1980-010-03, /03L-0:on 800110,recirculation Loop Temp Instruments Found Out of Calibr.Caused by Use of Wrong Type of Test Signal in Previous Calibr.Problem Corrected by Recalibr | /03L-0:on 800110,recirculation Loop Temp Instruments Found Out of Calibr.Caused by Use of Wrong Type of Test Signal in Previous Calibr.Problem Corrected by Recalibr | | | 05000333/LER-1980-011-03, /03L-0:on 800110,during Surveillance Testing, Hydraulic Snubber Found Inoperable.Caused by Snubber Accumulator Cocked & O-ring Leakage.Overhaul & post-repair Testing Restored Snubber to Operable Status as Spare | /03L-0:on 800110,during Surveillance Testing, Hydraulic Snubber Found Inoperable.Caused by Snubber Accumulator Cocked & O-ring Leakage.Overhaul & post-repair Testing Restored Snubber to Operable Status as Spare | | | 05000333/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000333/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000333/LER-1980-012-03, /03L-0:on 800111,during Surveillance Testing, Emergency Diesel Generator a Tripped on Low Lube Oil Pressure.Caused by Partial Failure of Engine Immersion Heater Resulting in Cold Lube Oil.Heater Replaced | /03L-0:on 800111,during Surveillance Testing, Emergency Diesel Generator a Tripped on Low Lube Oil Pressure.Caused by Partial Failure of Engine Immersion Heater Resulting in Cold Lube Oil.Heater Replaced | | | 05000333/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000333/LER-1980-013-03, /03L-0:800114,during Surveillance Testing,Reactor lo-lo-lo Level Switch a Operated Improperly.Caused by Improper Closing of Level Switch Contact at Switch Set Point.Switch Replaced | /03L-0:800114,during Surveillance Testing,Reactor lo-lo-lo Level Switch a Operated Improperly.Caused by Improper Closing of Level Switch Contact at Switch Set Point.Switch Replaced | | | 05000333/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000333/LER-1980-014-03, /03L-0:on 800116,during Normal Operation,Torus Water Level Limits Exceeded Tech Specs for 20 Minutes. Caused by Testing of HPCI Sys,Adding Water to Torus Via Min Flow Valve.Torus Pumped Down to Tech Spec Limit | /03L-0:on 800116,during Normal Operation,Torus Water Level Limits Exceeded Tech Specs for 20 Minutes. Caused by Testing of HPCI Sys,Adding Water to Torus Via Min Flow Valve.Torus Pumped Down to Tech Spec Limit | | | 05000333/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000333/LER-1980-015-03, /03L-0:on 800123,during Normal Operation,Lpci Independent Power Supply a Inverter Tripped for No Apparent Reason.Caused by Failed Capacitors in Inverter Control Circuit.Capacitors Replaced | /03L-0:on 800123,during Normal Operation,Lpci Independent Power Supply a Inverter Tripped for No Apparent Reason.Caused by Failed Capacitors in Inverter Control Circuit.Capacitors Replaced | | | 05000333/LER-1980-016-03, /03L-0:on 800125,during Normal Operation, Containment Isolation Valve 20-MOV-82 Was Inoperable.Caused by Ground Fault.Replaced Burned Up Motor Limit Switch Assembly,Torque Switch Assembly & Modified Termination Box | /03L-0:on 800125,during Normal Operation, Containment Isolation Valve 20-MOV-82 Was Inoperable.Caused by Ground Fault.Replaced Burned Up Motor Limit Switch Assembly,Torque Switch Assembly & Modified Termination Box | | | 05000333/LER-1980-016, Forwards LER 80-016/03L-0 | Forwards LER 80-016/03L-0 | | | 05000333/LER-1980-017, Forwards LER 80-017/03L-0 | Forwards LER 80-017/03L-0 | | | 05000333/LER-1980-017-03, /03L-0:on 800130,drywell-to-torus Differential Pressure Did Not Meet 1.7 Psi Requirements of Tech Specs for Approx 1-h.Caused by Rapid Temp Decrease in Drywell Cooling Sys.Nitrogen Added,Restoring Pressure to Normal | /03L-0:on 800130,drywell-to-torus Differential Pressure Did Not Meet 1.7 Psi Requirements of Tech Specs for Approx 1-h.Caused by Rapid Temp Decrease in Drywell Cooling Sys.Nitrogen Added,Restoring Pressure to Normal | | | 05000333/LER-1980-018-03, /03L-0:on 800201,during Normal Operation,Core Spray Sys Pipe Break Detector Was Outside of Tech Spec Limits for Nine Days.Caused by Change in Tech Specs.Detector Recalibr to New Tech Spec Value | /03L-0:on 800201,during Normal Operation,Core Spray Sys Pipe Break Detector Was Outside of Tech Spec Limits for Nine Days.Caused by Change in Tech Specs.Detector Recalibr to New Tech Spec Value | | | 05000333/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | | 05000333/LER-1980-019-03, /03L-0:on 800205,during Normal Operation,Rod Sequence Control Sys Failed to Come Into Svc at Expected Power Level.Caused by Calibr Procedure Error.Procedure Corrected,Instrument Recalibr & Returned to Svc | /03L-0:on 800205,during Normal Operation,Rod Sequence Control Sys Failed to Come Into Svc at Expected Power Level.Caused by Calibr Procedure Error.Procedure Corrected,Instrument Recalibr & Returned to Svc | | | 05000333/LER-1980-019, Forwards LER 80-019/03L-0 | Forwards LER 80-019/03L-0 | | | 05000333/LER-1980-020, Advises That Date on Transmittal Ltr for LER 80-020/04L-0 Should Be 800305,instead of 800205 | Advises That Date on Transmittal Ltr for LER 80-020/04L-0 Should Be 800305,instead of 800205 | | | 05000333/LER-1980-020-04, /04L-0:on 800205,during Routine Shutdown & Cooldown Operations,Plant Stack Gas Monitoring Sys Was Inoperable Due to Freeze Up of Sample Line.Caused by Cold Weather & Purge of Humid Containment Atmosphere | /04L-0:on 800205,during Routine Shutdown & Cooldown Operations,Plant Stack Gas Monitoring Sys Was Inoperable Due to Freeze Up of Sample Line.Caused by Cold Weather & Purge of Humid Containment Atmosphere | | | 05000333/LER-1980-021, Forwards LER 80-021/03L-0 | Forwards LER 80-021/03L-0 | | | 05000333/LER-1980-021-03, /03L-0:on 800207,during Normal Shutdown Operations Intermediate Range Monitor B Was Made Inoperable to Repair Signal Cable Connector.Reactor Protections Sys B Placed in Tripped Condition.Caused by Normal Wear | /03L-0:on 800207,during Normal Shutdown Operations Intermediate Range Monitor B Was Made Inoperable to Repair Signal Cable Connector.Reactor Protections Sys B Placed in Tripped Condition.Caused by Normal Wear | | | 05000333/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000333/LER-1980-022-03, /03L-0:on 800208,during Normal Startup Operations, Drywell Atmosphere Monitor a Was Made Inoperable While B Was Out of Svc Resulting in Operation in Degraded Mode.Caused by Need to Investigate Noise from Sample Pump | /03L-0:on 800208,during Normal Startup Operations, Drywell Atmosphere Monitor a Was Made Inoperable While B Was Out of Svc Resulting in Operation in Degraded Mode.Caused by Need to Investigate Noise from Sample Pump | | | 05000333/LER-1980-023-03, /03L-0:on 800211,during Normal Startup Operations, Water Chemistry Samples Indicated Chloride Ion Concentration in Excess of Tech Specs.Probably Caused by Sample Contamination.Second Water Cleanup Filter Placed in Svc | /03L-0:on 800211,during Normal Startup Operations, Water Chemistry Samples Indicated Chloride Ion Concentration in Excess of Tech Specs.Probably Caused by Sample Contamination.Second Water Cleanup Filter Placed in Svc | | | 05000333/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000333/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000333/LER-1980-024-03, /03L-0:on 800213,during Normal Operation,Hpci Steam Isolation Valve Closed Due to Spurious Operation Signal.Caused by Loose Wire within Thermocouple Switch Associated W/High Area Temp Isolation Logic.Wire Fastened | /03L-0:on 800213,during Normal Operation,Hpci Steam Isolation Valve Closed Due to Spurious Operation Signal.Caused by Loose Wire within Thermocouple Switch Associated W/High Area Temp Isolation Logic.Wire Fastened | | | 05000333/LER-1980-025, Forwards LER 80-025/03L-0 | Forwards LER 80-025/03L-0 | | | 05000333/LER-1980-025-03, /03L-0:on 800228,during Normal Operation While Conducting Surveillance Tests,Average Power Reactor Monitor B Remained Inoperable When Function Switch Was Returned to Operation Position.Caused by Normal Hysteresis Effect | /03L-0:on 800228,during Normal Operation While Conducting Surveillance Tests,Average Power Reactor Monitor B Remained Inoperable When Function Switch Was Returned to Operation Position.Caused by Normal Hysteresis Effect | |
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