LER-1980-012, /03L-0:on 800428,reactor Water Conductivity Exceeded 10 Umhos/Cm Tech Spec Limit.Caused by Depleted Demineralizers.Unit Shutdown Initiated.Demineralizers Regenerated & Low Conductivity Coolant Added to Reactor |
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,c EVENT DESCRIPTION AND PROBABLE CONSEQUENCES O'o Lo # 21 )
On April 27, 1980, at 5:25 p.m. Unit Two was placed in the STARTUP mode and the l
reactor was made critical at 6:50 p.m.
Prior to startup, the unit had been shutdown [
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for a five month outage. At 3:45 4.m. on April 28, 1980, reactor water analysis I
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- o to i i limi t of TS 3.6.C.3 The chloride-oxygen concentration during this occurrence was l
well below the TS limits. Thus, the consequences of this occurrence were minimal.
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- AUSE DESCRIPTION AND CORRECTIVE ACTIONS h jitoi: Depleted demineralizers. The exact cause of the decrease in reactor water quality l
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system after a five month outage, contributed to by the introduction of new clean-up [
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of the demineralizers. At 5:45 a.m. conductivity was decreased to 9 umhos/cm.
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LER NUMBER: 80-12/03L-0 11.
LICENSEE NAME: Commonwealth Edison Company quad-Cities Nuclear Power Station Ill.
FACILITY NAME: Unit Two IV.
DOCKET NUMBER: 050-265 V.
EVENT DESCRIPTION
On April 27, 1980, at 5:25 p.m.,
Unit Two was placed in the STARTUP mode and the reactor was made critical at 6:50 p.m.
Prior to startup, the unit had been shutdown for a five month outage. At 3:45 a.m., on April 28, 1980, analysis of reactor water Indicated conductivity had increased to 13 umhos/cm, which was in excess of the 10 umhos/cm limit of Technical Specification 3.6.C.3.
At this time the Chemistry Technician notified the Shif t Engineer and an orderly unit shutdown was initiated.
Following this, reactor water clean-up demineralizers and condensate demineralizers were regenerated. At 5:45 a.m. reactor water conductivity decreased to 9 umhos/cm and reactor startup was resumed.
VI.
PROBABLE CONSEQUENCES OF THE OCCURRENCE:
Technical Specification 3.6.C.3 is concerned with limits for conductivity and chloride concentration to prevent stress corrosion cracking of stain-less steel.
Figure 4.6-1 of Technical Specification 3.6.C; Limiting Conditions for Operation Bases, indicates the stainless steel failure boundary for ranges of chloride-oxygen combinations in reactor water.
The chloride-oxygen concentration for Unit Two reactor water during this startup never exceeded the 3.6.C.3 limits and subsequently was well below the Figure 4.6-1 failure boundary. Thus, the safety consequences of this cccurrence are minimal.
Vll.
CAUSE
The cause of this occurrence was due to depleted demineralizers. The exact cause of the decrease in reactor water quality is not known. A possible cause being the effect of startup temperatures on the system af ter a five month outage contributed to by the introduction of new clean-up system piping.
During the outage the clean-up system piping was modified to improve clean-up pump reliability. Main condenser tube leaks were also deemed probable.
Vill. CORRECTIVE ACTION:
An orderly unit shutdown was initiated. The reactor water clean-up de-mineralizers and condensate demineralizers were regenerated and low con-ductivity coolant was added to the reactor. At 5:45 a.m. reactor water conductivity decreased to 9 umhos/cm and reactor startup was resumed. On April 29,1980, reactor water conductivity had decreased to I umho/cm. On May 18,1980, during a weekend outage, a number of main conder.ser tube leaks were detected and were repaired by plugging tubes.
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| 05000265/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000254/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000254/LER-1980-001-03, /03L-0:on 800111,while Performing Suppression Chamber to Drywell Pressure Separation Test,Differential Pressure Transmitter 1-8741-51 Was Not Indicating Properly. Caused by Personnel Error Due to Drawing Error | /03L-0:on 800111,while Performing Suppression Chamber to Drywell Pressure Separation Test,Differential Pressure Transmitter 1-8741-51 Was Not Indicating Properly. Caused by Personnel Error Due to Drawing Error | | | 05000254/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000254/LER-1980-002-03, /03L-0:on 800111,while Performing in-place Charcoal Absorber Leak Rate Test on Standby Gas Treatment sys,1.93% Leakage Found.Caused by Damaged Gasket on 4x4 Inch Access Plate.Gasket Replaced | /03L-0:on 800111,while Performing in-place Charcoal Absorber Leak Rate Test on Standby Gas Treatment sys,1.93% Leakage Found.Caused by Damaged Gasket on 4x4 Inch Access Plate.Gasket Replaced | | | 05000265/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000265/LER-1980-002-03, /03L-0:on 800108,while Leak Testing RHR Svc Water Vault Penetrations,Observed Leakage from Electrical Penetration P-12.Caused by Loose hold-down bolts.Hold-down Bolts Tightened & Penetration Retested Satisfactorily | /03L-0:on 800108,while Leak Testing RHR Svc Water Vault Penetrations,Observed Leakage from Electrical Penetration P-12.Caused by Loose hold-down bolts.Hold-down Bolts Tightened & Penetration Retested Satisfactorily | | | 05000265/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000265/LER-1980-003-03, /03L-0:on 800213,while Performing Procedure Qis 35-2,reactor Bldg Ventilation Sys Would Not Reset After Test Isolation.Caused by Burnt CR 120 Relay.Relay 1705-105 Replaced & Functional Test Sucessfully Completed | /03L-0:on 800213,while Performing Procedure Qis 35-2,reactor Bldg Ventilation Sys Would Not Reset After Test Isolation.Caused by Burnt CR 120 Relay.Relay 1705-105 Replaced & Functional Test Sucessfully Completed | | | 05000254/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000254/LER-1980-003-03, /03L-0:on 800206,while Performing Procedure Qos 1000-3,RHR to Suppression Chamber Dump Valve,Mo 1-1001- 36A,circuit Breaker Tripped Out.Caused by Burned Out 480/120-volt Transformer in Circuit Breaker Cabinet | /03L-0:on 800206,while Performing Procedure Qos 1000-3,RHR to Suppression Chamber Dump Valve,Mo 1-1001- 36A,circuit Breaker Tripped Out.Caused by Burned Out 480/120-volt Transformer in Circuit Breaker Cabinet | | | 05000254/LER-1980-004-03, /03L-0:on 800215,while Performing Reactor low-low Water Level Calibr Test,Procedure QIS-11,level Switch LIS-1-263-72A Failed.Caused by Slight Misalignment of Mercury Wetted Magnetic Switch W/Actuating Magnet | /03L-0:on 800215,while Performing Reactor low-low Water Level Calibr Test,Procedure QIS-11,level Switch LIS-1-263-72A Failed.Caused by Slight Misalignment of Mercury Wetted Magnetic Switch W/Actuating Magnet | | | 05000254/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000265/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000265/LER-1980-004-03, /03L-0:on 800219,while Performing Procedure Qms 700-1,automatic Blowdown Timer 287-105A Took 122-s to Time Out,Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Timer Adjusted & Verified to Be 100-s | /03L-0:on 800219,while Performing Procedure Qms 700-1,automatic Blowdown Timer 287-105A Took 122-s to Time Out,Exceeding Tech Spec Limit.Caused by Instrument Setpoint Drift.Timer Adjusted & Verified to Be 100-s | | | 05000265/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000265/LER-1980-005-03, /03L-0:on 800303,while Performing LPCI & Containment Cooling Modes of Rhrs Logic test,5-s Delay Timer 10A-M2A for 1002B RHR Pump Failed to Actuate Relay K21A.Relay Failed to Energize.Caused by Microswitch Drift | /03L-0:on 800303,while Performing LPCI & Containment Cooling Modes of Rhrs Logic test,5-s Delay Timer 10A-M2A for 1002B RHR Pump Failed to Actuate Relay K21A.Relay Failed to Energize.Caused by Microswitch Drift | | | 05000254/LER-1980-005-03, /03L-0:on 800224,while Performing Misv Closure Timing,Valve AD 1-203-1B Failed to Close When Control Switch Was Operated.Caused by Blockage of Exhaust Restrictor on on Pilot Valve.Exhaust Restrictor Cleaned | /03L-0:on 800224,while Performing Misv Closure Timing,Valve AD 1-203-1B Failed to Close When Control Switch Was Operated.Caused by Blockage of Exhaust Restrictor on on Pilot Valve.Exhaust Restrictor Cleaned | | | 05000254/LER-1980-006-03, /03L-0:on 800222,while Doing Routine Panel Checks, Reactor Core Isolation Cooling Supply Valves Mo 1-1301-16 & 17 Were Found in Closed Position.Caused by Procedural Inadequacy & Personnel Performance.Procedures Revised | /03L-0:on 800222,while Doing Routine Panel Checks, Reactor Core Isolation Cooling Supply Valves Mo 1-1301-16 & 17 Were Found in Closed Position.Caused by Procedural Inadequacy & Personnel Performance.Procedures Revised | | | 05000254/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000265/LER-1980-006-01, /01T-0:on 800308,while Performing Reactor Vessel Pressure Test,Several Crack Indications Were Discovered in Pipe to Elbow Welds.Cause Not Determined.Affected Pipe Sections Will Be Replaced W/Carbon Steel Piping | /01T-0:on 800308,while Performing Reactor Vessel Pressure Test,Several Crack Indications Were Discovered in Pipe to Elbow Welds.Cause Not Determined.Affected Pipe Sections Will Be Replaced W/Carbon Steel Piping | | | 05000265/LER-1980-006, Forwards LER 80-006/01T-0 | Forwards LER 80-006/01T-0 | | | 05000254/LER-1980-007-03, /03L-0:on 800308,while Performing Control Room Insp & Panel Check,B Main Steam Line Radiation Monitor Found Reading Low.Caused by Logarithmic Radiation Monitor Chassis Electronically Drifting Out of Calibr.Chassis Recalibr | /03L-0:on 800308,while Performing Control Room Insp & Panel Check,B Main Steam Line Radiation Monitor Found Reading Low.Caused by Logarithmic Radiation Monitor Chassis Electronically Drifting Out of Calibr.Chassis Recalibr | | | 05000254/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000265/LER-1980-007-03, /03L-0:on 800316,while Ultrasonically Inspecting Jet Pump Fixture Beam Assemblies One Through 20,width-wise Crack Indication Discovered Along Upper Surface of Pump 16 Near Bolt.Caused by Intergranular Stress Corrosion | /03L-0:on 800316,while Ultrasonically Inspecting Jet Pump Fixture Beam Assemblies One Through 20,width-wise Crack Indication Discovered Along Upper Surface of Pump 16 Near Bolt.Caused by Intergranular Stress Corrosion | | | 05000265/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000254/LER-1980-008-03, /03L-0:on 800308,after Performing Preventive maint,1/2 Diesel Generator Would Not Start from Control Room.Caused by Poor Electrical Contact Between Fuse & Clip. Fuse Clip Adjusted | /03L-0:on 800308,after Performing Preventive maint,1/2 Diesel Generator Would Not Start from Control Room.Caused by Poor Electrical Contact Between Fuse & Clip. Fuse Clip Adjusted | | | 05000265/LER-1980-008-03, /03L-0:on 800305,while Performing LPCI & Containment Cooling Modes,Two 5-S Delay Timers for Starting 1002D RHR Pump Failed to Actuate Timer Contacts.Caused by Microswitch Arm Being Out of Alignment | /03L-0:on 800305,while Performing LPCI & Containment Cooling Modes,Two 5-S Delay Timers for Starting 1002D RHR Pump Failed to Actuate Timer Contacts.Caused by Microswitch Arm Being Out of Alignment | | | 05000265/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000254/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000265/LER-1980-009-03, /03L-0:on 800322,while Performing Pci Simulated Automatic Closure Initiation Test,Procedure Qos 1600-13, Transient in-core Probe 2,failed to Respond to Group 2 Isolation Signal.Caused by Dirty Contacts on Relay K21 | /03L-0:on 800322,while Performing Pci Simulated Automatic Closure Initiation Test,Procedure Qos 1600-13, Transient in-core Probe 2,failed to Respond to Group 2 Isolation Signal.Caused by Dirty Contacts on Relay K21 | | | 05000265/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000254/LER-1980-009-03, /03L-0:on 800410,while Performing Motor Operated Valve Operability Test,Thermal Overload Relay for B-loop Suppression Chamber Cooling Valve Tripped.Caused by High Motor Starting Currents.Torque Switch Adjusted | /03L-0:on 800410,while Performing Motor Operated Valve Operability Test,Thermal Overload Relay for B-loop Suppression Chamber Cooling Valve Tripped.Caused by High Motor Starting Currents.Torque Switch Adjusted | | | 05000254/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000254/LER-1980-010-03, /03L-0:on 800423,while Performing Loss of Electrohydraulic Control Fluid Pressure Scram Surveillance, Pressure Switch 1-5600-PS-3 Tripped Below Tech Spec Limit. Caused by Instrument Setpoint Drift.Switch Adjusted | /03L-0:on 800423,while Performing Loss of Electrohydraulic Control Fluid Pressure Scram Surveillance, Pressure Switch 1-5600-PS-3 Tripped Below Tech Spec Limit. Caused by Instrument Setpoint Drift.Switch Adjusted | | | 05000254/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000265/LER-1980-010-03, /03L-0:on 800517,while Performing Quartlerly MSIV Closure Timing Surveillance Procedure Qos 250-4,MSIV AO 2-203-1C Closed in 2.5-s & MSIV AO 2-203-2D Closed in 9.1-s. Caused by Equipment Failure.Speed Control Valves Adjusted | /03L-0:on 800517,while Performing Quartlerly MSIV Closure Timing Surveillance Procedure Qos 250-4,MSIV AO 2-203-1C Closed in 2.5-s & MSIV AO 2-203-2D Closed in 9.1-s. Caused by Equipment Failure.Speed Control Valves Adjusted | | | 05000265/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000265/LER-1980-011-03, /03L-0:on 800420,while Performing Manual Operation of Relief Valves,Valve 2-203-3C Failed to Open.Caused by Component Failure Due to Excessive Solenoid Plunger to Pilot Valve Stem Clearance | /03L-0:on 800420,while Performing Manual Operation of Relief Valves,Valve 2-203-3C Failed to Open.Caused by Component Failure Due to Excessive Solenoid Plunger to Pilot Valve Stem Clearance | | | 05000265/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000254/LER-1980-011-03, /03L-0:on 800429,main Feed Breaker to MCC 19-1 Tripped.Caused by Excessive Current Trip Time Which Allowed phase-to-phase Short Internal to Be Carried Back to MCC 19-1.Motor & Circuit Breaker Replaced | /03L-0:on 800429,main Feed Breaker to MCC 19-1 Tripped.Caused by Excessive Current Trip Time Which Allowed phase-to-phase Short Internal to Be Carried Back to MCC 19-1.Motor & Circuit Breaker Replaced | | | 05000254/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000254/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000265/LER-1980-012-03, /03L-0:on 800428,reactor Water Conductivity Exceeded 10 Umhos/Cm Tech Spec Limit.Caused by Depleted Demineralizers.Unit Shutdown Initiated.Demineralizers Regenerated & Low Conductivity Coolant Added to Reactor | /03L-0:on 800428,reactor Water Conductivity Exceeded 10 Umhos/Cm Tech Spec Limit.Caused by Depleted Demineralizers.Unit Shutdown Initiated.Demineralizers Regenerated & Low Conductivity Coolant Added to Reactor | | | 05000254/LER-1980-012-03, /03L-0:on 800429,reactor Recirculation Motor Generator Set 1A Tripped Due to Low Oil Pressure from Lube Oil Pump 1A1 Trip.Possibly Caused by Contractor Personnel Dropping Matl on Generator Set Control Cabinet | /03L-0:on 800429,reactor Recirculation Motor Generator Set 1A Tripped Due to Low Oil Pressure from Lube Oil Pump 1A1 Trip.Possibly Caused by Contractor Personnel Dropping Matl on Generator Set Control Cabinet | | | 05000265/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000254/LER-1980-013-03, /03L-0:on 800415,while Performing High,Low & low-low Reactor Water Level Functional Test,Procedure Qis 10-1,reactor Water Level Switch LIS-1-263-57A Was Found to Trip Below Tech Spec Limit.Caused by Instrument Drift | /03L-0:on 800415,while Performing High,Low & low-low Reactor Water Level Functional Test,Procedure Qis 10-1,reactor Water Level Switch LIS-1-263-57A Was Found to Trip Below Tech Spec Limit.Caused by Instrument Drift | | | 05000265/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000254/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000265/LER-1980-013-03, /03L-0:on 800428,while Performing LPCI Motor Operated Valve Operability Test & RHR to Suppression Chamber Test,Cooling Valve Mo 2-1001-36A Failed to Close.Caused by Binding of Plunger Arm on Auxiliary Interlock Contacts | /03L-0:on 800428,while Performing LPCI Motor Operated Valve Operability Test & RHR to Suppression Chamber Test,Cooling Valve Mo 2-1001-36A Failed to Close.Caused by Binding of Plunger Arm on Auxiliary Interlock Contacts | |
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