LER-1980-036, /01X-1:on 800417,during Normal Operation,Average Power Range Monitor F Found Operating W/One Level C Low Power Range Monitor Input.Caused by Failure to Declare Monitor F Inoperable After Low Power Monitor 800409 Calibr |
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N:C Phse u.s. NuCtEAR REcutATORv COuaissiON (7 77)
LICENSEE EVENT REPORT CONTROL BLOCK:
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8 60 61 DOCKET NUMB sH 68 69 EV ENT OATE I4 75 REPORT C ATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES O'o Io Ial l During normal operation personnel noted APMI F was operating with only one (1) l
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[ Level C LPM 1 input which is contrary to TS Table 3.1-1 Note 10.
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,g,3, l bypassing of other APMl's in the same safety system.
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10 11 12 13 18 19 20 SEQU E NTI A L OCCURRENCE REPORT REVISION gga EVENTVEAR R EPORT NO.
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36 37 40 41 42 43 44 47 CAUSE CESCRIPTION AND CORRECTIVE ACTIONS h lilo l [ LPB1 was bypassed' making APMI F inoperable.
Additional administrative controls I
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See attachment for details.
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POWER AUTHORITY OF THE STATE OF NEW YORK e
JAMES A. FITZPATRICK NUCLEAR POWER PI).NT i
DOCKET No.50-333 ATTACHMENT TO LER 80- 036/01X-1 Page 1
of 1
During normal operations, personnel noted that Average Power Range Monitor (APRM) Channel F was operating with only one (1) "C" level Local Power Range Monitor (LPRM) input. Technical Specifications Table 3.1-1, j
Note 10, requires that a minimum of two (2) LPRM inputs from each level must be present for the APRM to be considered operable.
The other APRM channels in the same safety system (Channels "B" and "D") were fully operable with at least eleven (11) LPRM inputs and at least two (2) LPRM l
Inputs for each level.
l A review of plant operating records reveals that APRM "F" should have been declared inoperable on April 9,1980 at the completion of a LPRM calibration. At that time APRM ChTnnels "B" and "D" were operable.
Between April 9, 1980 and April 17, 1980 when the problem was discovered, any time period in which either APRM "B" or "D" was inoperable or bypassed, i
l only one (1) APRM would have been available, which is contrary to the i
requirements of Technical Specifications Table 3.1-1.
A review of the operating records indicates that either APRM Channel "B" or "D" was j-bypassed on seven (7) occasions for a total of approximately seventy-one (71) minutes during the April 9 to April 17, 1980 time period.
In i
addition, operation with only one (1) APRM in the B. safety system operable (that is, with APRM F inoperable and APRM B or D bypassed or inoperable) i is an' example of operation in a degraded mode that is less conservative than the least conservative aspect of the LCO established by Table 3.1-1 2
and is a reportable occurrence as defined by Paragraph 6.9. A.4.1.b.
As soon as the problem was discovered, APRM "F" was bypassed and the switch tagged to inform the operator that the switch must remain in the "APRM F Bypass" position unless other action to satisfy Technical j
Specifications is taken. This action, due to the design of the bypass j
switch, physically prevented the bypassing of APRM "B" or "D" thus assuring that the requirements of Table 3.1-1 were met.
Since the root cause of the problem was the failure of personnel to recogni;e or communicate
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the status of APRM,i'F", the bypassing of APRM "B" or "D" was not recogni:ed as causing operation in conflict with the Technical Sp.cifications.
Accordingly, to preclude recurrence,. administrative controls which i
specifically require a determination of the status of an APRM Channel whenever a LPRM is bypassed, have.been developed and were implemented prior to startup following the 1980 refueliag outage.
No additional action is required.
The event-did not represent a significant hazard to
.the public health and safety.
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Revision 1Lis submitted to. correct or revise Items 10, 17,-19,-27 and the attachment.
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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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