LER-1981-008, /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. Switch Replaced & Instrument Calibr |
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U.S. NUCLEAR R3BU'MN NRC FCRM 366 (1773 LICENSEE EVENT REPORT CONTROL BLOCr* l l
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LICENSE NUM8ER 25 16 LICENSE TYPE 30 67 CAT 58 7
8 9 LICENSEE CODE 14
'10121 2'R: L'_J@lo 15 to lo Ic 12 is 14 i@i O i u i 0 i 71 s i i i@i 0 i u l i l CCYT 60 68 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 7
8 EVENT DESCRIPTION AND PROSABLE CONSEQUENCES h l 19 # 21 l At 11:40 a.m. the RCIC System received a spurious High Steam Flow automatic l
l This caused I
isolation signal which closed valves M0-1-1301-16 and M0-1-1301-17 DTDl RCIC to be declared inoperable. The consequences are minimized by the fact that
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g3g,gl HPCI was available at all times per Technical Specification 3 5.E.2. and that RCIC l
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g was inoperable for only two hours and ten minutes.
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SEQUENTIAL OCCUR RENCE REPORT LE R. RO EVENT YE AR REPORT NO.
COOE TYPE NO.
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40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l lMg,J l The sourious sianal was caused by a faulty micro switch in DPIS 1-1960-1B which is l
I one of two bellows type pressure cells provided for this isolation function.
l Wl The micro switch was replaced and the instrument calibrated satisfactorily at I
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- 50 p.m. on April 7, 1981.
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DESCRIPTION
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!.ER MUMBER: LER/R0 81-8/03L-0 11.
LICENSEE NAME: Commonwealth Edison Company Quad-Ci ties Nuclear Power Station 2
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FACILITY NAME: Unit One IV.
DOCKET NUMBER: 050-254 V.
EVENT DESCRIPTION
On April 7,1981 at 11:40 a.m., while Unit One was in RUN mode at 806 MWe and 2481 MWt, Reactor Core Isolation Cooling System (RCIC) Automatic-Isolation and RCIC High Steam Flow signals were received by the unit operator. The RCIC Automatic isolation closed valves M0-1-1301-16 and MO-1-1301-17, thereby. isolating the steam supply to the RCIC turbine. The RCIC system was declared inoperable. Technical Specification 3 5.E.I.
requires the RCIC system to be operable whenever reactor pressure is greater than 150 psi. A similar. event occurred in 1979 (LER/R0 79-01/
03L-0) when Unit Oae RCIC Automatic isolation tripped on a high steam flow signal.
In accordance with Technical Specification 3 5.E.2.,
preparations were made to demonstrate the operability of the HIqh Pressure Coolant injection System (HPCI).
VI.
PROBABLE CONSEQUENCES OF THE OCCURRENCE:
The er
'quenc.es of this occurrence are minimized due to the short outage of ti system (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 10 minutes), and because safe plant operation was m.
' with the HPCI system being available. The RCIC High Steam Flow iso,
, designed to isolate the RCIC steam line in case of a RCIC pipe bi..
outside of the ?ramary Containment. This feature functioned os designed.
Vll.
CAUSE
The spurious High Steam Flow signal was due to a micro switch in.one of two differential pressure cells, DPIS-1-1360-1B which failed in the CLOSED position. This is a Bellows type pressure cell, manufactured by Barton
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instruments Company, Model Number 288.
l Vill. CORRECTIVE ACTION:
Immediate action was to initiate demonstration of operability of the H?Cl System. Work Request Q11969 was issued to replace the low side micro switch and recalibrate according to QlS 18-1, RCIC Steam Line High Flow Calibration. The switch was replaced and set at 200" H 0; normal setpoint 2
ls 200" + 4" H20. The RCIC Automatic isolation was cleared and 'the system was declared operable at 1350 on April 7, 1981.
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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 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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 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| | 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. Switch Replaced & Instrument Calibr | /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. 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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