LER-1980-011, /03L-0:on 801118,axial Flux Difference Deviated from Target Band.Caused by Improper Interpretation of Tech Specs Resulting in Failure to Lower High Neutron Flux Setpoint.Instruction Clarified |
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OOCK ET NUMBE R ha 69 Eir ENT DATE 74 75 REPORT DATE fl0 EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h 10121 l During a normal startup, the indicated axial flux dif%rence was noted 1 t o 131 l as deviating from its target band.
After unsuccessfully attempting to l 1014 l l return the axial flux difference to the target band within the.:ime I
t o lsl l allotted, the reactor was limited to 50% power.
However, the high I
l o is i I neutron flux setpoint was not reduced to 55% as indicated by Technical l l0l71l Specification 15.3.10.B.2.d.l.
This event is reportable in accordance I g o is i ; with Technical Specification 15.6.9.2.B.l.
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I g l Supervisory personnel have been made aware of the proper interpretationI g,13 l l of Technical Specification 15. 3.10.B.2 as it applies to startup 1
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The applicable instruction is being changed to make this l
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ATTAC.iMENT TO LICENSEE EVENT REPORT NO. 80-Oll/03L-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 2 Docke t No. 50-301 During a normal startup following an outage to repair a safety injection pump, the indicated axial flux difference was noted as deviating from its target band.
After unsuccessfully attempting to return the axial flux to within the target band within the time allotted, the reactor was limited to 50% power as required in Technical Specification 15.3.10.B.2.e.
However, the reduction of the high neutron flux setpoint as indicated in Technical Specification 15.3.10.B.2.d.1 to no greater than 55,% was not performed.
Administrative controls were employed to ensure reactor power was maintained below 50%.
The indicated axial flux was within the target band at 0621 hours0.00719 days <br />0.173 hours <br />0.00103 weeks <br />2.362905e-4 months <br /> on November 19, 1980, and reactor power was increased as allowed by Technical Specifications above 50% at 0435 hours0.00503 days <br />0.121 hours <br />7.19246e-4 weeks <br />1.655175e-4 months <br /> on November 20, 1980.
Upon the expiration of the allotted time to return the axial flux to the target band, the Duty Shif t Supervisor contacted the Duty & Call Superintendent and in the ensuing discussion they decided that the provisions of Technical Specification 15. 3.10.B. 2.d did not apply.
Technical Specification 15.3.10.B.2.d refers to a power level "no greater than 90 percent of rated power" and the paragraph following is dencriptive of a reduction in power from 90%
due to exceeding the delta flux limits at an appreciatle power level.
The Duty Shift Supervisor and Duty & Call Superintendent resolved the resetting of the power range setpoint was not applicable to the condition of a normal startup sequence.
Technical Specification 15.3.10.2.e, "at a power level no greater than 50% of rated power", was the paragraph interpreted as applicable and power was administratively controlled to levels less than 50% until the flux was reestablished in the target band for the period required by che Technical Specifications.
The Superintendent -
Technical Services conducted a technical review of the event upon his return on November 21, 1980, with several of the Manager's Supervisory Staff members and the NRC resident inspectors.
At this meeting it was determined that the Technical Specifications had been improperly interpreted and that the high neutron flux setpoint should have been lowered to less than or equal to 55% of rated power.
All other reactor protection and safety devices were operable and the functional requirement of the high neutron flux setpoint was not comp romised.
A revision is being incorporated into Reactor Engineering Instruction, REI 12.0,
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" Technical Specifications and Delta Flux", to incorporate 1
this interpretation of Technical Specifications.
i This item is reportable in accordance with Technical Specification 15.6.9.2.B.l.
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| 05000266/LER-1980-001-01, /01T-0:on 800202,during Routine Calibr of Pressure Transmitters for Motor Driven Auxiliary Feed Pumps, Transmitter Isolation Block Valves Discovered Closed.Caused by Inadvertent Closing of Isolation Valves.Snubbers Added | /01T-0:on 800202,during Routine Calibr of Pressure Transmitters for Motor Driven Auxiliary Feed Pumps, Transmitter Isolation Block Valves Discovered Closed.Caused by Inadvertent Closing of Isolation Valves.Snubbers Added | | | 05000266/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000301/LER-1980-001-01, /01T-0:on 800221,during Full Power Operation, Momentary Loss of Red Instrument Bus Occurred,Resulting in Power Range Channel N41 Failing Low.Caused by Faulty Capacitor in 2DY01 Power Supply.Capacitor Replaced | /01T-0:on 800221,during Full Power Operation, Momentary Loss of Red Instrument Bus Occurred,Resulting in Power Range Channel N41 Failing Low.Caused by Faulty Capacitor in 2DY01 Power Supply.Capacitor Replaced | | | 05000301/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000301/LER-1980-002-01, /01T-0:on 800227,primary-to-secondary Leak Was Identified in Steam Generator a Resulting in Shutdown of Unit.Caused by Leaking Tube at Position R18C37.Six Defective Tubes Found in Steam Generator a | /01T-0:on 800227,primary-to-secondary Leak Was Identified in Steam Generator a Resulting in Shutdown of Unit.Caused by Leaking Tube at Position R18C37.Six Defective Tubes Found in Steam Generator a | | | 05000266/LER-1980-002, Updated LER 80-002/01T-01:on 800311,during 800 Psi Secondary to Primary Hydrostatic Leak Test,Tubes R23C44 & R8C37 & Plug End R23C50 Found Leaking.Eddy Current Insp Performed.Tube Holes & Leaking Explosive Plugs Were Plug Welde | Updated LER 80-002/01T-01:on 800311,during 800 Psi Secondary to Primary Hydrostatic Leak Test,Tubes R23C44 & R8C37 & Plug End R23C50 Found Leaking.Eddy Current Insp Performed.Tube Holes & Leaking Explosive Plugs Were Plug Welded | | | 05000266/LER-1980-002-01, /01T-0:on 800311,during shutdown,800 Psi secondary-to-primary Hydrostatic Leak Test of B Steam Generator Revealed Tube R23C44 Leaking,Tube R8C37 Wet & Plug End R23C50 Wet.Tube Holes Will Be Weld Plugged | /01T-0:on 800311,during shutdown,800 Psi secondary-to-primary Hydrostatic Leak Test of B Steam Generator Revealed Tube R23C44 Leaking,Tube R8C37 Wet & Plug End R23C50 Wet.Tube Holes Will Be Weld Plugged | | | 05000301/LER-1980-002, Updated LER 80-002/01T-1:on 800227,during Normal Operation, Indication of Increasing primary-to-secondary Leak in a Steam Generator Noted.Caused by Leaking Tube in a Steam Generator Position R18C37 | Updated LER 80-002/01T-1:on 800227,during Normal Operation, Indication of Increasing primary-to-secondary Leak in a Steam Generator Noted.Caused by Leaking Tube in a Steam Generator Position R18C37 | | | 05000266/LER-1980-003, Forwards LER 80-003/03T-0 | Forwards LER 80-003/03T-0 | | | 05000301/LER-1980-003, Forwards LER 80-003/01T-0 | Forwards LER 80-003/01T-0 | | | 05000266/LER-1980-003-03, /03T-0:on 800318,during post-mod Testing of Containment Spray Sys,Relay 1CSB Would Not Latch.Caused by Latching Mechanism Misalignment.Latch Adjusted & Proper Operation Verified on 800318.Similar Relay Bench Tested | /03T-0:on 800318,during post-mod Testing of Containment Spray Sys,Relay 1CSB Would Not Latch.Caused by Latching Mechanism Misalignment.Latch Adjusted & Proper Operation Verified on 800318.Similar Relay Bench Tested | | | 05000301/LER-1980-003-01, /01T-0:on 800408,while Testing Pressurizer Logic Channels,Pressurizer Level Channel 427 Was Momentarily Failed Low by Instrumentation & Control Technicians.Caused by Personnel Error.Event Discussed W/Personnel | /01T-0:on 800408,while Testing Pressurizer Logic Channels,Pressurizer Level Channel 427 Was Momentarily Failed Low by Instrumentation & Control Technicians.Caused by Personnel Error.Event Discussed W/Personnel | | | 05000266/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000301/LER-1980-004-03, /03L-0:on 800417,during Seismic Analysis of as-built safety-related Sys Per IE Bulletin 79-14, Discovered Overstressed Condition in Component Cooling Sys Piping.Caused by Lack of Support Upstream of Juncture | /03L-0:on 800417,during Seismic Analysis of as-built safety-related Sys Per IE Bulletin 79-14, Discovered Overstressed Condition in Component Cooling Sys Piping.Caused by Lack of Support Upstream of Juncture | | | 05000301/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000266/LER-1980-004-03, /03L-0:on 800409,w/plant at Normal Steady State, Emergency Diesel Generator Failed to Start During Routine Surveillance Test.Second Attempt Unsuccessful.Caused by Broken Vane in Starting Air Motor.Air Motor Replaced | /03L-0:on 800409,w/plant at Normal Steady State, Emergency Diesel Generator Failed to Start During Routine Surveillance Test.Second Attempt Unsuccessful.Caused by Broken Vane in Starting Air Motor.Air Motor Replaced | | | 05000266/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000266/LER-1980-005-03, /03L-0:on 800417,during Normal Operation,Review of Security Logs Revealed That Designated Fire Brigade Was Below Min Supervision Requirements on Three Occasions.Caused by Operations Personnel Designation Error | /03L-0:on 800417,during Normal Operation,Review of Security Logs Revealed That Designated Fire Brigade Was Below Min Supervision Requirements on Three Occasions.Caused by Operations Personnel Designation Error | | | 05000301/LER-1980-005-03, /03L-0:on 800609,during Training Walkdown of Safeguards Electrical Supply Cabinets,Noted That Tie Breaker Between AO5 & AO6 Safeguards Buses Was Shut.Probably Caused by Improper Electrical Lineup After Loss of Ac Test | /03L-0:on 800609,during Training Walkdown of Safeguards Electrical Supply Cabinets,Noted That Tie Breaker Between AO5 & AO6 Safeguards Buses Was Shut.Probably Caused by Improper Electrical Lineup After Loss of Ac Test | | | 05000301/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000266/LER-1980-006-03, /03L-0:on 800417,during Analysis of as-built safety-related Piping Sys Per IE Bulletin 79-14,overstressed Condition Discovered in Cooling Sys Piping.Caused by Lack of Support Between Valves Upstream of Juncture | /03L-0:on 800417,during Analysis of as-built safety-related Piping Sys Per IE Bulletin 79-14,overstressed Condition Discovered in Cooling Sys Piping.Caused by Lack of Support Between Valves Upstream of Juncture | | | 05000301/LER-1980-006-01, /01T-0:on 800617,during Safeguards Logic Test W/ One Emergency Diesel Generator Out of Svc,Auto Containment Spray Pump Actuation Threatened During Loss of Ac & high- High Containment Pressure.Caused by Personnel Error | /01T-0:on 800617,during Safeguards Logic Test W/ One Emergency Diesel Generator Out of Svc,Auto Containment Spray Pump Actuation Threatened During Loss of Ac & high- High Containment Pressure.Caused by Personnel Error | | | 05000301/LER-1980-006, Forwards LER 80-006/01T-0 | Forwards LER 80-006/01T-0 | | | 05000266/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000301/LER-1980-007-01, /01T-0:on 800619,at Full Power,Test IT-04 Was Performed W/Emergency Diesel Generator 3D Out of Svc. Emergency Safeguards Train Equipment Would Have Been Inoperable on Loss of Ac Power.Caused by Personnel Error | /01T-0:on 800619,at Full Power,Test IT-04 Was Performed W/Emergency Diesel Generator 3D Out of Svc. Emergency Safeguards Train Equipment Would Have Been Inoperable on Loss of Ac Power.Caused by Personnel Error | | | 05000266/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000266/LER-1980-007-01, /01T-0:on 800611,blue Instrument Bus 1Y02 Was de-energized,resulting in de-energization of 3 Containment Pressure Channels.Caused by Personnel Error.Power Restored & Instrumentation Returned to Normal | /01T-0:on 800611,blue Instrument Bus 1Y02 Was de-energized,resulting in de-energization of 3 Containment Pressure Channels.Caused by Personnel Error.Power Restored & Instrumentation Returned to Normal | | | 05000301/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000266/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000266/LER-1980-008-03, /03L-0:on 800606,during Normal Operation,Testing Revealed That Relay 1-247/AO2X in Train B Would Not Drop Out to Initiate Undervoltage Trip Function.Cause Not Determined. Relay Replaced & Tested Satisfactorily | /03L-0:on 800606,during Normal Operation,Testing Revealed That Relay 1-247/AO2X in Train B Would Not Drop Out to Initiate Undervoltage Trip Function.Cause Not Determined. Relay Replaced & Tested Satisfactorily | | | 05000301/LER-1980-008, Forwards LER 80-008/01T-0 | Forwards LER 80-008/01T-0 | | | 05000301/LER-1980-008-01, /01T-0:on 800912,following Trip from Full Power, Main Steam Stop Valve B Failed to Close Upon Receiving Close Signal.Caused by Deposit Buildup on Valve Shaft &/Or Hardening of Gland Packing | /01T-0:on 800912,following Trip from Full Power, Main Steam Stop Valve B Failed to Close Upon Receiving Close Signal.Caused by Deposit Buildup on Valve Shaft &/Or Hardening of Gland Packing | | | 05000301/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000301/LER-1980-009-03, /03L-0:on 801101,during Normal Operation, Performance of ICP 2.14 Found P8 Permissive Bistable from Channel N44 to Be Set at 50.5%.Caused by Instrument Drift. Bistable Adjusted & Tested Satisfactorily | /03L-0:on 801101,during Normal Operation, Performance of ICP 2.14 Found P8 Permissive Bistable from Channel N44 to Be Set at 50.5%.Caused by Instrument Drift. Bistable Adjusted & Tested Satisfactorily | | | 05000266/LER-1980-009, Forwards LER 80-009/01T-0 | Forwards LER 80-009/01T-0 | | | 05000266/LER-1980-009-01, /01T-0:on 800728 While in Cold Shutdown & During Hydrostatic Leak Test of Steam Generators,Two Dripping Explosive Plugs & Two Wet End Plugs Noted.Cause Not Stated. Dripping Plugs Weld Repaired | /01T-0:on 800728 While in Cold Shutdown & During Hydrostatic Leak Test of Steam Generators,Two Dripping Explosive Plugs & Two Wet End Plugs Noted.Cause Not Stated. Dripping Plugs Weld Repaired | | | 05000266/LER-1980-010-03, /03L-0:on 800827,during Normal Operation,After Redundant Containment Spray Pump Recirculation Phase Suction Valve Maint,Operability Test Was Not Performed.Caused by Personnel Failure to Fully Comprehend Maint Procedures | /03L-0:on 800827,during Normal Operation,After Redundant Containment Spray Pump Recirculation Phase Suction Valve Maint,Operability Test Was Not Performed.Caused by Personnel Failure to Fully Comprehend Maint Procedures | | | 05000266/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000301/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000301/LER-1980-010-03, /03L-0:on 801117,safety Injection Pump 2P15A Motor & Pump Shaft to Coupling Keys Found to Be Sheared.Cause Undetermined.Pump & Motor Checked for Damage,Keys Replaced & Pump Operability Verified | /03L-0:on 801117,safety Injection Pump 2P15A Motor & Pump Shaft to Coupling Keys Found to Be Sheared.Cause Undetermined.Pump & Motor Checked for Damage,Keys Replaced & Pump Operability Verified | | | 05000301/LER-1980-011-03, /03L-0:on 801118,axial Flux Difference Deviated from Target Band.Caused by Improper Interpretation of Tech Specs Resulting in Failure to Lower High Neutron Flux Setpoint.Instruction Clarified | /03L-0:on 801118,axial Flux Difference Deviated from Target Band.Caused by Improper Interpretation of Tech Specs Resulting in Failure to Lower High Neutron Flux Setpoint.Instruction Clarified | | | 05000301/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000266/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000266/LER-1980-011-03, /03L-0:on 800926,found That,Aug 1977-Sept 1980, Containment Spray Sys Spray Additive Valves Were Tested Per ASME Program Requirements Instead of Per Tech Specs.Caused by Administrative Error Re NRC | /03L-0:on 800926,found That,Aug 1977-Sept 1980, Containment Spray Sys Spray Additive Valves Were Tested Per ASME Program Requirements Instead of Per Tech Specs.Caused by Administrative Error Re NRC | | | 05000266/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000266/LER-1980-012-03, /03L-0:on 801005,logs Showed Decrease in Holdup Tank Pressure During 801002-05.Evaluation Showed Leak on Compression Fitting on Inlet to Valve IPCV-1022C.Caused by Improper Reinstallation of Valve After Cleaning | /03L-0:on 801005,logs Showed Decrease in Holdup Tank Pressure During 801002-05.Evaluation Showed Leak on Compression Fitting on Inlet to Valve IPCV-1022C.Caused by Improper Reinstallation of Valve After Cleaning | | | 05000301/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000301/LER-1980-012-03, /03L-0:on 801202,slippage Found in Shaft Driven Seal Water Pump Impeller Resulting in Overheating of Throttle Bushing.Caused by Reduced Seal Water Flow Due to Loosening of Pumping Ring.Shaft Sleeve & Bushing Replaced | /03L-0:on 801202,slippage Found in Shaft Driven Seal Water Pump Impeller Resulting in Overheating of Throttle Bushing.Caused by Reduced Seal Water Flow Due to Loosening of Pumping Ring.Shaft Sleeve & Bushing Replaced | | | 05000266/LER-1980-013, Forwards LER 80-013/01T-0 | Forwards LER 80-013/01T-0 | | | 05000266/LER-1980-013-01, /01T-0:on 801113,suction to 1P4B Boric Acid Transfer Pump Isolated,Rendering Pump Inoperable.Probably Caused by Personnel Error in Returning Valve Lineup to Normal Following Recirculation & Sampling | /01T-0:on 801113,suction to 1P4B Boric Acid Transfer Pump Isolated,Rendering Pump Inoperable.Probably Caused by Personnel Error in Returning Valve Lineup to Normal Following Recirculation & Sampling | |
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