LER-1981-005, /01T-0:on 810220,during Testing,Three of Four Condenser Low Vacuum Scram Switches Found Outside Setting Per Tech Spec 3.1-3.Caused by Instrument Setpoint Drift.All Switches Recalibr |
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6 60 61 DOC A ET NUY8 E R sid b9 EV ENT DATE 74 15 RE80RT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h l o l 21 l While performing QlS 19-1, Quarterly Low Condenser Vacuum Calibration and Functional l
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go;4; l equal to 23 inches Hg vacuum as required by Technical Specifications. The low l
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The low vacuum scram would have occurred at 22.9 inches; therefore, j
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40 4-42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l i j o l l The cause of this occurrence is instrument setpoint drif t.
All switches were 1
i, ;i l l immediately recalibrated and functionally tested satisfactorily.
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LER NUMBER: LER/R0 81-5/0lT-0 ll.
LICENSEE NAME: Commonwealth Edison Company Quad-Cities Nuclear Power Station lil. FACILITY NAME: Unit One IV.
DOCKET NUMBER: 050-254 V.
EVENT DESCRIPTION
On February 20, 1981, the condenser low vacuum scram switches were calibrated and functionally tested in accordance with procedure Qls 19-1.
Three out of the four vacuum swi tches were found to be outside the setting as required in the Limiting Conditions of Operation in Technical Specification Table 3.1-3 The Technical Specification trip level setting for the switches is greater than or equal to 23 inches Hg vacuum.
The as-found settings were as follows:
1-503A, 22.7; l-503B, 22.5; l-503C, 22.9; and 1-503D, 23.0.
Recallbration of the vacuum switches was begun immediately.
VI.
PROBABLE CONSEQUENCES OF THE OCCURRENCE:
The probable consequences of this occurrence were minimal. The condenser low vacuum scram is an anticipatory scram of the reactor to minimize pressure and neutron flux transients. The scram occurs prior to the main turbine stop valve closure on low condenser vacuum, which is used to protect the. turbine. WI S the one-out-of-two-twice logic of the reactor protection system, the i tor would have scrammed at 22.9 inches Hg vacuum. This is only C.
iches Hg greater than the Technical Specifica-tion -limitation, and 2.! 1.ches Hg prior to closure of the main turbine-stop valves. The 2.9 t.ich Hg differential should be sufficient to safely shutdown the reactor before a turbine trip occurs. Safe operation of the reactor was not affected as a result of this occurrence.
Vll. CAUSE:
The cause of this occurrence has been designated as instrument setpoint drift. The procedural setpoint range for these switches are 23.3 to 23.6 inches Hg.
The largest drif t occurred on switch 1-503B, which drif ted 0.9 Inches Hg'to a setpoint of 22 5 inches Hg vacuum.
The vacuum switches are diaphragm type switches, manufactured by Barksdale Company, Model DIT-H1855 Vill. CORRECTIVE ACTION:
The immediate corrective action was to recalibrate the vacuum switches to within_ Technical Specification and procedural limitations. The as-left setpoints of the switches are as follows:
1-503A, 23.4; l-5038, 23.45; 1-503C, 23.35; and 1-503D, 23.45 The switches were successfully functional tested following recalibration. The last setpoint drift problem with these switches occurred in 1973; thus, this corrective action is deemed adequate to prevent recurrence.
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| 05000265/LER-1981-001-03, /03L-0:on 810116,during High Drywell Pressure Calibr & Functional Test,Pressure Switch PS-1-1001-88D Trip Point Found Above Tech Spec Limit.Caused by Setpoint Drift.Switch Recalibr & Tested | /03L-0:on 810116,during High Drywell Pressure Calibr & Functional Test,Pressure Switch PS-1-1001-88D Trip Point Found Above Tech Spec Limit.Caused by Setpoint Drift.Switch Recalibr & Tested | | | 05000254/LER-1981-001-03, /03L-0:on 810105,while Placing Standby Gas Treatment Sys B in Normal Shutdown Lineup,Discharge Valve MO-1/2-7507B Failed to Close When Operated from Control Room.Caused by Worn Breaker Auxiliary Contacts | /03L-0:on 810105,while Placing Standby Gas Treatment Sys B in Normal Shutdown Lineup,Discharge Valve MO-1/2-7507B Failed to Close When Operated from Control Room.Caused by Worn Breaker Auxiliary Contacts | | | 05000254/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000265/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000265/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000254/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000254/LER-1981-002-03, /03L-0:on 810107,Unit 1 Emergency Diesel Generator Tripped & Failed to Restart.Caused by Loose Fuse in 125 Vdc Engine Starting & Fuel Control Circuit & Misalignment of Output Breaker Auxiliary Contacts.Fuse Holder Tightened | /03L-0:on 810107,Unit 1 Emergency Diesel Generator Tripped & Failed to Restart.Caused by Loose Fuse in 125 Vdc Engine Starting & Fuel Control Circuit & Misalignment of Output Breaker Auxiliary Contacts.Fuse Holder Tightened | | | 05000265/LER-1981-002-03, /03L-0:on 810116,pressure Controller for Electromatic Relief Valve 2-203-3B Tripped in Excess of Tech Specs Limit.Caused by Instrument Drift,Possibly Contributed to by Faulty Microswitch.Switch Replaced | /03L-0:on 810116,pressure Controller for Electromatic Relief Valve 2-203-3B Tripped in Excess of 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Failed to Operate While Performing Surveillance Testing.Caused by Failure of High Side Switch in DPIS-2-1360-1B.Switch Adjusted,Recalibr & Satisfactorily Tested | /03L-0:on 810224,switch in DPIS-2-1360-1B Failed to Operate While Performing Surveillance Testing.Caused by Failure of High Side Switch in DPIS-2-1360-1B.Switch Adjusted,Recalibr & Satisfactorily Tested | | | 05000265/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000254/LER-1981-005-01, /01T-0:on 810220,during Testing,Three of Four Condenser Low Vacuum Scram Switches Found Outside Setting Per Tech Spec 3.1-3.Caused by Instrument Setpoint Drift.All Switches Recalibr | /01T-0:on 810220,during Testing,Three of Four Condenser Low Vacuum Scram Switches Found Outside Setting Per Tech Spec 3.1-3.Caused by Instrument Setpoint Drift.All Switches Recalibr | | | 05000254/LER-1981-005, Forwards LER 81-005/01T-0 | Forwards LER 81-005/01T-0 | | | 05000265/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000265/LER-1981-006-03, /03L-0:on 810312,differential Pressure Between Drywell & Suppression Chamber Was Lost.Caused by Isolation of Differential Pressure Sys Due to Short in Electrical Circuit Resulting in Blown Fuse.Fuse Replaced | /03L-0:on 810312,differential Pressure Between Drywell & Suppression Chamber Was Lost.Caused by Isolation of Differential Pressure Sys Due to Short in Electrical Circuit Resulting in Blown Fuse.Fuse Replaced | | | 05000254/LER-1981-006-03, /03L-0:on 810302,flexible Air Line to Target Rock Main Steam Safety/Relief Valve Found Broken During Routine Insp of Drywell.Caused by Improper Installation of Flexible Air Line.Air Line Replaced W/Longer One | /03L-0:on 810302,flexible Air Line to Target Rock Main Steam Safety/Relief Valve Found Broken During Routine Insp of Drywell.Caused by Improper Installation of Flexible Air Line.Air Line Replaced W/Longer One | | | 05000254/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000265/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000265/LER-1981-007-03, /03L-0:on 810322,MSIV AO-2-203-2A Failed to Initiate half-scram in Reactor Protection Sys Channel B. Caused by Sticking Limit Switch Due to Steam Leak on RCIC Testable Check Valve | /03L-0:on 810322,MSIV AO-2-203-2A Failed to Initiate half-scram in Reactor Protection Sys Channel B. Caused by Sticking Limit Switch Due to Steam Leak on RCIC Testable Check Valve | | | 05000254/LER-1981-007-03, /03L-0:on 810313,no Position Indication Found on Recirculation Pump 1A Discharge Valve MO-1-202-5A.Caused by Tripped Valve Motor Breaker Due to Several Shorted Conductors in Cable 12507 Leading to Valve Inside Drywell | /03L-0:on 810313,no Position Indication Found on Recirculation Pump 1A Discharge Valve MO-1-202-5A.Caused by Tripped Valve Motor Breaker Due to Several Shorted Conductors in Cable 12507 Leading to Valve Inside Drywell | | | 05000254/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000265/LER-1981-008-03, /03L-0:on 810326,two Instrument Cable Risers Found to Have Open Penetrations.Caused by Failure to Seal After Plant Mods.Fire Watch Established & Penetrations Sealed | /03L-0:on 810326,two Instrument Cable Risers Found to Have Open Penetrations.Caused by Failure to Seal After Plant Mods.Fire Watch Established & Penetrations Sealed | | | 05000265/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000254/LER-1981-008-03, /03L-0:on 810407,reactor Core Insulation Cooling Sys Received Spurious High Steam Flow Automatic Isolation Signal.Caused by Faulty Micro Switch in DPIS 1-1360-1B. 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Switch Replaced & Instrument Calibr | | | 05000254/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000254/LER-1981-009-03, /03L-0:on 810407,while 1A RHR Svc Water Pump Being Run for Packing Adjustment,Pump Failed to Meet Flow Requirements of 3,500 Gpm at 198 Psig.Caused by 3 Pieces of Wood in Pump Suction.Packing Sleeve & Bearings Replaced | /03L-0:on 810407,while 1A RHR Svc Water Pump Being Run for Packing Adjustment,Pump Failed to Meet Flow Requirements of 3,500 Gpm at 198 Psig.Caused by 3 Pieces of Wood in Pump Suction.Packing Sleeve & Bearings Replaced | | | 05000265/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000254/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000265/LER-1981-009-03, /03L-0:on 810504,while Performing RHR Containment Cooling Valve Operability Test,Breaker for Valve MO-2-1001-37B Tripped During Attempt to Close Valve.Caused by Internal Corrosion Buildup | /03L-0:on 810504,while Performing RHR Containment Cooling Valve Operability Test,Breaker for Valve MO-2-1001-37B Tripped During Attempt to Close Valve.Caused by Internal Corrosion Buildup | | | 05000254/LER-1981-010-03, /03L-0:on 810414,valve AO-1-1301-35 Observed Closed Causing Reactor Core Isolation Cooling to Be Inoperable.Caused by Shorted Solenoid Coil on Valve Operator.Solenoid Replaced.Valve Tested Satisfactorily | /03L-0:on 810414,valve AO-1-1301-35 Observed Closed Causing Reactor Core Isolation Cooling to Be Inoperable.Caused by Shorted Solenoid Coil on Valve Operator.Solenoid Replaced.Valve Tested Satisfactorily | | | 05000254/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000265/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000265/LER-1981-010-03, /03L-0:on 810515,diesel Generator Declared Inoperable When Trouble Alarm Received & Room Found Full of Smoke.Caused by Control Power Ground Fault.Ground & Damaged Components Repaired | /03L-0:on 810515,diesel Generator Declared Inoperable When Trouble Alarm Received & Room Found Full of Smoke.Caused by Control Power Ground Fault.Ground & Damaged Components Repaired | | | 05000265/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000254/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000265/LER-1981-011-03, /03L-0:on 810608,during Routine Maint,Diesel Generator 1/2 Was Removed from Svc Prior to Demonstrating Diesel Generator 2 Operability,In Violation of Tech Spec. Caused by Personnel Error.Personnel Reinstructed | /03L-0:on 810608,during Routine Maint,Diesel Generator 1/2 Was Removed from Svc Prior to Demonstrating Diesel Generator 2 Operability,In Violation of Tech Spec. Caused by Personnel Error.Personnel Reinstructed | | | 05000254/LER-1981-011-03, /03L-0:on 810618,diesel Fire Pump B Out of Svc for More than 7 Days.Caused by Wood Debris Found in Suction Piping.New Strainers Ordered for Both Pumps | /03L-0:on 810618,diesel Fire Pump B Out of Svc for More than 7 Days.Caused by Wood Debris Found in Suction Piping.New Strainers Ordered for Both Pumps | | | 05000265/LER-1981-012-03, /03L-0:on 810518,during Surveillance Testing,Valve MO-2-1001-7B Failed to Reopen.Caused by Failure of Auxiliary Contacts in Circuit Breakers to Disengage.Valve Manually Opened & Contacts Replaced | /03L-0:on 810518,during Surveillance Testing,Valve MO-2-1001-7B Failed to Reopen.Caused by Failure of Auxiliary Contacts in Circuit Breakers to Disengage.Valve Manually Opened & Contacts Replaced | | | 05000254/LER-1981-012-03, /03L-0:on 810624,pressure Switch 1-5600-PS-3 Tripped Below Tech Spec Level During Loss of Electrohydraulic Fluid Pressure Calibr & Functional Test. Caused by Instrument Drift.Switch Recalibr & Tested | /03L-0:on 810624,pressure Switch 1-5600-PS-3 Tripped Below Tech Spec Level During Loss of Electrohydraulic Fluid Pressure Calibr & Functional Test. Caused by Instrument Drift.Switch Recalibr & Tested | | | 05000254/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000265/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000254/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000265/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | |
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