:on 880408,Tech Spec 3.5-2,Item 3.2.b Exceeded. Caused by Failure of Relays in Undervoltage Protection Scheme.Relays Replaced & Satisfactorily Tested Before Unit Shutdown Commenced| ML17345A180 |
| Person / Time |
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| Site: |
Turkey Point  |
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| Issue date: |
05/09/1988 |
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| From: |
Hart R FLORIDA POWER & LIGHT CO. |
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| To: |
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| Shared Package |
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| ML17345A181 |
List: |
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| References |
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| LER-88-004-03, LER-88-4-3, NUDOCS 8805310057 |
| Download: ML17345A180 (4) |
|
text
NAC Form 344 (943)
LICENSEE EVENT REPORT (LER)
U.S. NVCLKARAKOULATOAYCOMMISSION APPROVED OMS NO, 315OOIOI EXPIRES: 4I31 IBS FACILITYNAME 0) urke Point Unit 4 AE PORT OATE (7)
MONTH DAY YEAR EVENT DATE (5)
MONTH OAY YEAR LER NUMBER (4)
SKOVSNTrAL NVMSKR RKvtaroN NVMSKR YEAR ac nrca Oacr rca ron c ron a
oman ~xcee a
Undervol tage Relay Failed During Periodic Testing OTHER FACILITIES INVOLVED(SI FACILITYNAMES DOCKET NUMBER(S) 0 5
0 0
0 DOCKET NUMBER (2)
PA E
3 0
5 0
0 0
1 OF 0
004 0
0 05088 0
5 0
0 0
OPEAATING MODE (9)
POWER LEY EL 1 p p
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7KF7g7r(My4$
20A02(S) 20A05
(~ I(I)II) 20 AOB(~ l(1 I(4) 20AOB(~ l(1)(BII 20A054)(ll(iv) 20AOS(e I(IHvl 20AOS(cl 50.34(cl (I) 50.34(cl(2l 50.73(al(2HI) 50.73(e I(2 IIIII 50.73(e l(2)(iiil 50.73(e) (2) (iv) 50.734H2Hv) 50.734) I2)(vBI 50.734) (2)(viii)(A) 50.73(eH2)(viiiHS) 50.73(el(2Hxl 0 THE AEOUIREMKNTS OF 10 C FR
('I: ICnec>> one or more of the follorffnol (11)
THIS AEPORT IS SUBMITTED PURSUANT 7 73.7((S) 73.71(c)
OTHER (Specify in Aettrect Oelovr encl In Text, AIIICForm 344A)
NAME LICENSEE CONTACT FOR THIS LER (12)
Randall D. Hart, Licensing Engineer TELEPHONE NUMBER AAEA CODE 305 24 6-6 55 9
COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OKSCRISED IN THIS RKPOAT (13)
CAUSE
SYSTEM X
J E
X J
E COMPONENT RLY RLY MANUFAC.
TURER G
0 8 G
0 8 NWP NI&
COMPONENT MANUFAC.
TUAER N~S 9'O N'ADS Pja@YP. K4 SUPPLKMENTAL REPORT EXPECTED (Iel YKS llfyet, complere EXPECTED SUSMISSIOH DATEI NO ABSTRACT (Limit to teOO tpecet, I.e., approximately fifteen afnOleepece typevrrltten lineal (I~)
EXPECTED SUBMISSION DATE (15)
MONTH DAY YEAR On April 8,
- 1988, the requirements of Technical Specification (TS) Table 3.5-2, item 3.2.b were exceeded.
During the performance of operating procedure (OP) 9404.2, 4160 volt and 480 volt switchgear - undervoltage
- test, the undervoltage protection circuit for the 4A 480 volt load center would not pass the test.
This channel was declared out of service and maintenance was requested to investigate the failure.
TS section 3.5, Table 3.5-2, item 3.2.b requires that for the 480V load centers, power operation may continue with one channel inoperable as long as the inoperable channel is placed in the tripped condition.
Operations was unable to place the channel in the tripped condition.
Therefore, the requirements of TS Table 3.5-2, item 3.2.b could not be met and Unit 4 was required to be placed into TS 3.0.1 which requires the unit to be in hot standby in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
Maintenance replaced relays 327TX/4A1 and 327TX/4A2, OP 9404.2 was recommenced and the replaced relays were satisfactorily tested.
This took the unit out of TS 3.0.1.
The cause of the event was failure of relays 327TX/4Al and 327TX/4A2 in the undervoltage protection scheme for the 4A 480 volt load center.
FPL s Engineering Department has been requested to evaluate this failure to determine root cause and appropriate
corrective actions
8805310057 88O50'0 PDR ADOCK 0500o25i S
PDR NRC Farm 344 (943 I
NRC Form 3ddA 18431 LICENSEE E ENT REPORT (LER) TEXT CONTINUA N
US NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO. 3150M(04 EXPIRES: 8/31/88 FACILITYNAME (1l OOCKET NUMBER (3(
VE'AR LER NUMBER (dl SEGUENTIAL NUMBER REVISION NUMBER PAGE (3)
'urkey Point Unit 4 TEXT ///moro EI>>ea/E roqrrinrd, rr>> oddrr/ar>>/NRC Form 38843/(17) 0 s
0 0
s 2
5 1
8 8 0
0 4
00 02 oF 03 EVENT:
On April 8, 1988, the requirements of Technical Specification (TS) Table 3.5-2, item 3.2.b were exceeded At 1410 during the performance of operating procedure (OP) 9404.2, 4160 volt and 480 volt switchgear undervoltage
- test, the undervoltage protection circuit for the 4A 480 volt load center would not pass the test.
The red indicating light did not come'n as required by the procedure.
This channel was declared out of service and the Electrical Maintenance Department was requested to investigate the occurrence.
They discovered that relays 327TX/4A1 and 327TX/4A2 had failed.
The circuit in which these relays are used utilizes a two-of-two logic to enable a non-safety in)ection degraded voltage trip received by both 327/**>
relays (General Electric inverse-time type relay model IAV55C).
Since this relay failed in an open-circuited condition (coil burned out), the trip position for that portion of the circuit could not be applied.
While the IAV55C degraded voltage relay has provisions to place it in the trip mode via shorting bars to create a one-of-one trip logic scheme, no similar provision exits for the 327TX/4A1 and 327TX/4A2 auxiliary relays downstream in the circuit.
TS section 3.5, Table 3.5-2 (Engineered Safety Features Actuation), item 3.2.b requires that for the 480V load centers, power operation may continue with one channel inoperable as long as the inoperable channel is placed in the tripped condition.
Since the design of the circuit does not allow the affected relays to be placed in the tripped condition, continued operation of Unit 4 was prohibited by TS Table 3.5-2, item 3.2.b.
This placed Unit 4 into'S 3.0.1, which required the unit to be in hot standby within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
Electrical Maintenance replaced relays 327TX/4Al and 327TX/4A2, OP 9404.2 was recommenced and the replaced relays were tested satisfactorily at 1650.
This took the unit out of TS 3.0.1.
CAUSE
OF EVENT:
1 The cause of the event was a failure of relays 327TX/4Al and 327TX/4A2 in the undervoltage protection scheme for the 4A 480 volt load center and the inability to place the failed relay into the tripped condition to meet TS action statement requirements.
These relays failed due to an open circuited coil.
The cause of the relay failure is still under investigation by power plant engineering.
The preliminary investigations have not identified any clear failure mechanism for the failed relays.
NRC FORM SddA (8831
drRc Form 344A (NI3(
F*CIL(TYNAMEtll LICENSEE NT REPORT (LER) TEXT CONTlNU N
OOCYTE T NUMEER IEI LER NUMEER (El NUCLEAR REOULATORY COMMISSION APPROVEO OM4 NO. 3150W104 EXPIRESI 4/3I/44 PACE (3I YEAR SEQUENTIAL NUMEER rrEvrs IoN NI/M ER P int Unit 4 TEXT /I/moro IPoco rfrNRrrod, rrw fddd/ooo/ HRC Fonrr 36644/ llT(
0 5
0 0
0 OF ANALYSIS OP EVENT:
Upon identification of the failure, the affected relays were replaced and returned to service before a unit shutdown was commenced.
FPL s Engineering Department has been requested to evaluate this failure to determine root cause, appropriate
corrective actions
and the safety significance of this event.
Should this evaluation significantly change the information provided in this LER, a LER update will be sent accordingly.
CORRECTIVE ACTIONS
1)
Relays 327TX/4Al and 327TX/4A2 were replaced and satisfactorily tested before a unit shutdown was commenced.
2)
FPL s Engineering Department has been requested to evaluate this concern to assist in identifying the root cause and appropriate corrective'actions.
This effort will proceed in accordance with the Integrated Schedule (IS).
This schedule for completion is currently being reviewed to determine if enhancements can be made.
ADDITIONALDETAILS:
The affected relay is manufactured by General Electric and is model number CR120BD04341
~
Similar Occurrences:
LER 251-87-013 reported a similar failure of a 480 volt load center undervoltage relay on the 4C 480 volt load center NRC FORM 344A (943(
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| | | Reporting criterion |
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| 05000250/LER-1988-001, :on 880113,unit Experienced Turbine Runback Due to Dropped Control Rod Assembly & Manual Subcritical Reactor Trip Occurred When Addl Control Rods Dropped Into Core. Caused by Personnel Error.Personnel Counseled |
- on 880113,unit Experienced Turbine Runback Due to Dropped Control Rod Assembly & Manual Subcritical Reactor Trip Occurred When Addl Control Rods Dropped Into Core. Caused by Personnel Error.Personnel Counseled
| | | 05000251/LER-1988-001-01, :on 880129,operability Requirements of Tech Spec 3.5.1 for Steam Generator lo-lo Level Reactor Could Not Be Met.Caused by Procedural Error.Setpoints of Affected Channels Rechecked,Calibr & Procedure Revised |
- on 880129,operability Requirements of Tech Spec 3.5.1 for Steam Generator lo-lo Level Reactor Could Not Be Met.Caused by Procedural Error.Setpoints of Affected Channels Rechecked,Calibr & Procedure Revised
| 10 CFR 50.73(a)(2) | | 05000251/LER-1988-002-01, :on 880202,containment & Control Room Ventilation Isolation Occurred.Caused by Personnel Error While Performing Mod to Remove Remote Alarm Function.Planner & Technician Involved Counselled |
- on 880202,containment & Control Room Ventilation Isolation Occurred.Caused by Personnel Error While Performing Mod to Remove Remote Alarm Function.Planner & Technician Involved Counselled
| 10 CFR 50.73(e)(2) | | 05000250/LER-1988-002, :on 880115,RCS Pressure Decreased to 625 Psig & Accumulators Started to Inject.Caused by Defective Controller for Valve PCV-3-455B.Controller Replaced |
- on 880115,RCS Pressure Decreased to 625 Psig & Accumulators Started to Inject.Caused by Defective Controller for Valve PCV-3-455B.Controller Replaced
| 10 CFR 50.73(e)(2)(v) | | 05000250/LER-1988-003, :on 880308,containment Ventilation & Control Room Ventilation Isolation Occurred.Caused by Minor Electrical Transient Upon Failure of One Light Filament. Failed Dual Filament Bulb Replaced |
- on 880308,containment Ventilation & Control Room Ventilation Isolation Occurred.Caused by Minor Electrical Transient Upon Failure of One Light Filament. Failed Dual Filament Bulb Replaced
| 10 CFR 50.73(e)(2) | | 05000251/LER-1988-003-01, :on 880207,shutdown of Unit from 100% Power Commenced Due to Exceeding Requirements of Tech Spec for Having Battery Charger 4S Out of Svc.Caused by Failure of Snubber Capacitor.Capacitor Replaced |
- on 880207,shutdown of Unit from 100% Power Commenced Due to Exceeding Requirements of Tech Spec for Having Battery Charger 4S Out of Svc.Caused by Failure of Snubber Capacitor.Capacitor Replaced
| 10 CFR 50.73(c)(2) | | 05000250/LER-1988-004, :on 880318,auxiliary Feedwater Pumps Actuated Due to Drop in Steam Generator Level.Caused by Reactor Control Operator Failure to Monitor Steam Generator Level. Operator Counseled Re Awareness of Actions |
- on 880318,auxiliary Feedwater Pumps Actuated Due to Drop in Steam Generator Level.Caused by Reactor Control Operator Failure to Monitor Steam Generator Level. Operator Counseled Re Awareness of Actions
| 10 CFR 50.73(e)(2) | | 05000251/LER-1988-004-02, :on 880408,Tech Spec Table 3.5-2 Requirements Exceeded.Caused by Failure of Relays 327TX/4A2 & 327TX/4A2 in Undervoltage Protection Scheme for 4A 480 Volt Load Ctr. Relays Replaced & Tested |
- on 880408,Tech Spec Table 3.5-2 Requirements Exceeded.Caused by Failure of Relays 327TX/4A2 & 327TX/4A2 in Undervoltage Protection Scheme for 4A 480 Volt Load Ctr. Relays Replaced & Tested
| | | 05000251/LER-1988-004-03, :on 880408,Tech Spec 3.5-2,Item 3.2.b Exceeded. Caused by Failure of Relays in Undervoltage Protection Scheme.Relays Replaced & Satisfactorily Tested Before Unit Shutdown Commenced |
- on 880408,Tech Spec 3.5-2,Item 3.2.b Exceeded. Caused by Failure of Relays in Undervoltage Protection Scheme.Relays Replaced & Satisfactorily Tested Before Unit Shutdown Commenced
| 10 CFR 50.73(e)(2)(iv) | | 05000251/LER-1988-004, Forwards Corrected LER 88-004,correcting Event Date in Block 5 of Rept Form as Submitted W/Util | Forwards Corrected LER 88-004,correcting Event Date in Block 5 of Rept Form as Submitted W/Util | | | 05000251/LER-1988-005-01, :on 880425,calibr of Nuclear Instrumentation Sys Power Range Detectors Performed Late.Caused by Personnel Error.Digital Data Processing Sys Repaired & Group Responsible for Performance Discussed Event |
- on 880425,calibr of Nuclear Instrumentation Sys Power Range Detectors Performed Late.Caused by Personnel Error.Digital Data Processing Sys Repaired & Group Responsible for Performance Discussed Event
| | | 05000250/LER-1988-005, :on 880415,loss of Flowpath from Boric Acid Storage Tanks to RCS Occurred.Caused by Loose Screw in Motor/Pump Coupling.Boric Acid Transfer Pump 4A Realigned to Provide Boric Acid Flow Path to Unit 3 |
- on 880415,loss of Flowpath from Boric Acid Storage Tanks to RCS Occurred.Caused by Loose Screw in Motor/Pump Coupling.Boric Acid Transfer Pump 4A Realigned to Provide Boric Acid Flow Path to Unit 3
| | | 05000251/LER-1988-006-01, :on 880716,containment Ventilation & Control Room Ventilation Sys Isolation Occurred.Caused by Very Conservative Setpoint for R-11 Actuation.Unit Removed from Operation & Temporary Repair Effected |
- on 880716,containment Ventilation & Control Room Ventilation Sys Isolation Occurred.Caused by Very Conservative Setpoint for R-11 Actuation.Unit Removed from Operation & Temporary Repair Effected
| 10 CFR 50.73(e)(2) | | 05000250/LER-1988-006, :on 880408,surveillance of Hydrogen & Oxygen Concentration of Inservice Gas Decay Tank Missed.Caused by Personnel Error.Surveillance Incorporated Into Chemistry Primary Daily Worksheet & Personnel Counseled |
- on 880408,surveillance of Hydrogen & Oxygen Concentration of Inservice Gas Decay Tank Missed.Caused by Personnel Error.Surveillance Incorporated Into Chemistry Primary Daily Worksheet & Personnel Counseled
| 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(2)(ii) | | 05000250/LER-1988-007, :on 880427,3A Intake Cooling Water (Icw) Pump out-of-svc Due to Discharge Pressure Gauge Piping Failure. Caused by Corrosion of Coupling Attaching Pressure Gauge Piping to Icw Discharge Pipe.Piping Repaired |
- on 880427,3A Intake Cooling Water (Icw) Pump out-of-svc Due to Discharge Pressure Gauge Piping Failure. Caused by Corrosion of Coupling Attaching Pressure Gauge Piping to Icw Discharge Pipe.Piping Repaired
| 10 CFR 50.73(e)(2)(vii) 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(2)(ii) | | 05000251/LER-1988-007-01, :on 880812,while Performing Corrective Maint, Subcritical Reactor Trip Occurred.Caused by Failure of Source Range Neutron Detector N-32.Post-trip Review Performed & Detector Replaced |
- on 880812,while Performing Corrective Maint, Subcritical Reactor Trip Occurred.Caused by Failure of Source Range Neutron Detector N-32.Post-trip Review Performed & Detector Replaced
| | | 05000251/LER-1988-008-01, :on 880815,Phase a of Containment Isolation Train a Actuated.Caused by Wire Bundle Bouncing Contacts of Relay 4-SIA2.Actuation Signal Reset |
- on 880815,Phase a of Containment Isolation Train a Actuated.Caused by Wire Bundle Bouncing Contacts of Relay 4-SIA2.Actuation Signal Reset
| 10 CFR 50.73(s)(2)(i) 10 CFR 50.73(s)(2)(v) 10 CFR 50.73(s)(2) | | 05000250/LER-1988-008, :on 880613,flowpath Which Could Result in Insufficient NPSH to Certain Pumps During LOCA Recirculation Identified.Procedures Revised to Maintain Valve 887 Locked in Fully Open Position |
- on 880613,flowpath Which Could Result in Insufficient NPSH to Certain Pumps During LOCA Recirculation Identified.Procedures Revised to Maintain Valve 887 Locked in Fully Open Position
| 10 CFR 50.73(e)(2) | | 05000250/LER-1988-009, :on 880527,determined That Tech Spec Surveillances for Station Battery Pilot Cell Rotation Not Properly Implemented in 1987.Caused by Personnel Error & Procedure Inadequacy.Training Bulletin Issued |
- on 880527,determined That Tech Spec Surveillances for Station Battery Pilot Cell Rotation Not Properly Implemented in 1987.Caused by Personnel Error & Procedure Inadequacy.Training Bulletin Issued
| | | 05000251/LER-1988-009, :on 880816,steam Generator Feedwater Pump Tripped During Coating of Condensate Polisher Vessel 4B W/ Resin for Secondary Sys Startup.Caused by Failure of Differential Pressure Switch.Switch Replaced |
- on 880816,steam Generator Feedwater Pump Tripped During Coating of Condensate Polisher Vessel 4B W/ Resin for Secondary Sys Startup.Caused by Failure of Differential Pressure Switch.Switch Replaced
| | | 05000251/LER-1988-010-01, :on 880819,reactor Trip Occurred Due to lo-lo Steam Generator B Level.Caused by Cognitive Personnel Error. Reactor Control Operator Counseled Re Procedural Compliance & Attention to Details |
- on 880819,reactor Trip Occurred Due to lo-lo Steam Generator B Level.Caused by Cognitive Personnel Error. Reactor Control Operator Counseled Re Procedural Compliance & Attention to Details
| 10 CFR 50.73(e)(2) | | 05000250/LER-1988-010, :on 880528,containment Ventilation & Control Room Ventilation Isolation Occurred While Containment Radiation Monitor Setpoint Being Checked.Drawer for Monitor R-11 Initiated Signals.Drawer Replaced |
- on 880528,containment Ventilation & Control Room Ventilation Isolation Occurred While Containment Radiation Monitor Setpoint Being Checked.Drawer for Monitor R-11 Initiated Signals.Drawer Replaced
| 10 CFR 50.73(s)(2) | | 05000250/LER-1988-011, :on 880529,discovered That Diesel Oil Storage Tank Isolation Valve 70-003 Locked Closed.Caused by Personnel Error.Technician Disciplined & Info Bulletin Re Work Controls & Procedural Compliance Issued |
- on 880529,discovered That Diesel Oil Storage Tank Isolation Valve 70-003 Locked Closed.Caused by Personnel Error.Technician Disciplined & Info Bulletin Re Work Controls & Procedural Compliance Issued
| 10 CFR 50.73(e)(2) | | 05000251/LER-1988-011-01, :on 880816,damage Occurred to Property in Excess of $2,000 Due to Spent Fuel Pool Leakage.Caused by Pump Failure Causing Vent Valve to Vibrate Open.Floor Drain Sys Cleaned.Pump & Oiler Repaired & Inspected |
- on 880816,damage Occurred to Property in Excess of $2,000 Due to Spent Fuel Pool Leakage.Caused by Pump Failure Causing Vent Valve to Vibrate Open.Floor Drain Sys Cleaned.Pump & Oiler Repaired & Inspected
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(e)(2) | | 05000250/LER-1988-012, :on 880614,QA Audit Caused Investigation Into Delay in Issuing Fire Protection Impairment Form for Four Penetration Seals in Switchgear Room.Caused by Inadequate Controls.Seal Surveillance Being Generated |
- on 880614,QA Audit Caused Investigation Into Delay in Issuing Fire Protection Impairment Form for Four Penetration Seals in Switchgear Room.Caused by Inadequate Controls.Seal Surveillance Being Generated
| | | 05000251/LER-1988-012-01, :on 880905,control Rod K-12 Dropped from 228 Steps to 0 Step,Causing Turbine Runback to 60% Power.Cause of Drop Under Investigation.Insp of Control Rod K-12 Will Be Performed During Current Refueling Outage |
- on 880905,control Rod K-12 Dropped from 228 Steps to 0 Step,Causing Turbine Runback to 60% Power.Cause of Drop Under Investigation.Insp of Control Rod K-12 Will Be Performed During Current Refueling Outage
| 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(1)(0) | | 05000250/LER-1988-013, :on 880707,discovered That Monthly Channel Functional Test Surveillance Procedure Did Not Check Sys Alarm.Caused by Personnel Error.Surveillance Procedure Corrected & Personnel Counseled |
- on 880707,discovered That Monthly Channel Functional Test Surveillance Procedure Did Not Check Sys Alarm.Caused by Personnel Error.Surveillance Procedure Corrected & Personnel Counseled
| | | 05000250/LER-1988-014, :on 880714,RCS Leakage Surveillance Not Performed within Required Interval Due to Personnel Error. Note Placed in Night Book Stressing Need to Meet 18-30 H Tech Specs Requirements |
- on 880714,RCS Leakage Surveillance Not Performed within Required Interval Due to Personnel Error. Note Placed in Night Book Stressing Need to Meet 18-30 H Tech Specs Requirements
| 10 CFR 50.73(e)(2) | | 05000250/LER-1988-015, :on 880729,valves in Flow Path Between Hydrogen Monitors & Containment Bldg Not Verified in Proper Position. Caused by Inadequate Administrative Controls.Procedures Revised to Verify Valve Position |
- on 880729,valves in Flow Path Between Hydrogen Monitors & Containment Bldg Not Verified in Proper Position. Caused by Inadequate Administrative Controls.Procedures Revised to Verify Valve Position
| | | 05000250/LER-1988-016, :on 880811,containment Spray Pump out-of-svc for Maint Exceeding Tech Specs Limits.Caused by Lack of Knowledge Re Need for break-in Period for New Bearings. Training Procedures to Be Revised |
- on 880811,containment Spray Pump out-of-svc for Maint Exceeding Tech Specs Limits.Caused by Lack of Knowledge Re Need for break-in Period for New Bearings. Training Procedures to Be Revised
| 10 CFR 50.73(e)(2) | | 05000250/LER-1988-017, :on 880815,control Room Ventilation Sys Out of Svc in Excess of Tech Spec Time Limit Due to Intermittent Circuit Failure.Caused by Procedural Deficiency.Bridge Circuit Replaced & Plant Mod in Effect |
- on 880815,control Room Ventilation Sys Out of Svc in Excess of Tech Spec Time Limit Due to Intermittent Circuit Failure.Caused by Procedural Deficiency.Bridge Circuit Replaced & Plant Mod in Effect
| 10 CFR 50.73(e)(1) | | 05000250/LER-1988-018-06, :on 880822,determined That Refueling Water Storage Tank Supply to ECCS Isolated from Both Trains of ECCS Sys.Caused by Procedure Inadequacy.Procedure Revised to Exclude Monthly Cycling of Tank Outlet Valves |
- on 880822,determined That Refueling Water Storage Tank Supply to ECCS Isolated from Both Trains of ECCS Sys.Caused by Procedure Inadequacy.Procedure Revised to Exclude Monthly Cycling of Tank Outlet Valves
| 10 CFR 50.73(e)(2) | | 05000250/LER-1988-018, :on 880822,refueling Water Storage Tank Supply to ECCS Isolated from Both Trains of Eccs,Including RHR, Containment Spray & Hpsi.Caused by Procedure Inadequacy. Procedures Revised to Exclude Monthly Cycling |
- on 880822,refueling Water Storage Tank Supply to ECCS Isolated from Both Trains of Eccs,Including RHR, Containment Spray & Hpsi.Caused by Procedure Inadequacy. Procedures Revised to Exclude Monthly Cycling
| | | 05000250/LER-1988-019, :on 880822,boric Acid Transfer Pump 3A Declared out-of-svc.Caused by Lack of Visible Water Level & Zero Nitrogen Pressure in Seal Pot & Failure of Pump Seal.Seal Replaced & Pump Returned to Svc |
- on 880822,boric Acid Transfer Pump 3A Declared out-of-svc.Caused by Lack of Visible Water Level & Zero Nitrogen Pressure in Seal Pot & Failure of Pump Seal.Seal Replaced & Pump Returned to Svc
| | | 05000250/LER-1988-020, :on 880831,control Room Ventilation Sys Shifted to Recirculation Mode While Conducting Routine Test of Channel B Air Intake Radiation Monitor.Caused by Spurious Actuation Signal.Recirculation Mode Verified |
- on 880831,control Room Ventilation Sys Shifted to Recirculation Mode While Conducting Routine Test of Channel B Air Intake Radiation Monitor.Caused by Spurious Actuation Signal.Recirculation Mode Verified
| 10 CFR 50.73(s)(2) | | 05000250/LER-1988-021, :on 880913,pressurizer PORV Stroke Time Exceeded Tech Spec Design Basis Value of 3.0 for Heat Input Case.Caused by Undersized Air & Nitrogen Backup Supply Line to Actuators.Procedures Revised |
- on 880913,pressurizer PORV Stroke Time Exceeded Tech Spec Design Basis Value of 3.0 for Heat Input Case.Caused by Undersized Air & Nitrogen Backup Supply Line to Actuators.Procedures Revised
| | | 05000250/LER-1988-022, :on 880920,emergency Diesel Generator a Declared out-of-svc Due to High Fuel Oil Pressure.Diesel Generator B out-of-svc Since 880917.Caused by Excessive Particles in Filter.Filter Replaced |
- on 880920,emergency Diesel Generator a Declared out-of-svc Due to High Fuel Oil Pressure.Diesel Generator B out-of-svc Since 880917.Caused by Excessive Particles in Filter.Filter Replaced
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(x)(2) | | 05000250/LER-1988-023, :on 880926,chemistry Technician Reported That There Was No Flow Indication to Plant Process Radiation Monitor R-19.Caused by Solids from Steam Generator Blowdown. Sample Flows to R-19 Will Be Monitored |
- on 880926,chemistry Technician Reported That There Was No Flow Indication to Plant Process Radiation Monitor R-19.Caused by Solids from Steam Generator Blowdown. Sample Flows to R-19 Will Be Monitored
| | | 05000250/LER-1988-024, :on 881001,RHR Pump Declared Out Svc Due to Leakage from Pump Seal.Cause Not Identified.Seal Cooler Flushed Prior to Reassembly to Remove Foreign Matl & Installation Technique Revised |
- on 881001,RHR Pump Declared Out Svc Due to Leakage from Pump Seal.Cause Not Identified.Seal Cooler Flushed Prior to Reassembly to Remove Foreign Matl & Installation Technique Revised
| | | 05000250/LER-1988-025, :on 881013,determined That Potential Interaction Existed Between Emergency Diesel Generator Pump Control Sys Which Could Have Prevented Fulfillment of Safety Function.Caused by Inadequate Design |
- on 881013,determined That Potential Interaction Existed Between Emergency Diesel Generator Pump Control Sys Which Could Have Prevented Fulfillment of Safety Function.Caused by Inadequate Design
| 10 CFR 50.73(e)(2) | | 05000250/LER-1988-026, :on 881107,unit Violated FSAR Design Requirements Re Hurricane Flood Protection |
- on 881107,unit Violated FSAR Design Requirements Re Hurricane Flood Protection
| | | 05000250/LER-1988-027, :on 881006,mechanic Found to Be Contaminated When Exiting Containment Bldg.Specific Cause Unidentified. Addl Temporary Controls Implemented & Area Mopped |
- on 881006,mechanic Found to Be Contaminated When Exiting Containment Bldg.Specific Cause Unidentified. Addl Temporary Controls Implemented & Area Mopped
| 10 CFR 50.73(e)(2) | | 05000250/LER-1988-028, :on 881117,control Room Ventilation Sys Shifted to Recirculation Mode While Conducting Test of Channel B Air Intake Radiation Monitor RAI 6642.Caused by Maladjustment of Monitor During Calibr.Instruction Revised |
- on 881117,control Room Ventilation Sys Shifted to Recirculation Mode While Conducting Test of Channel B Air Intake Radiation Monitor RAI 6642.Caused by Maladjustment of Monitor During Calibr.Instruction Revised
| 10 CFR 50.73(e)(2) | | 05000250/LER-1988-029, :on 881121,specialist Accidently short- Circuited Power Terminal Lead Which Resulted in Closure of RHR Suction Isolation Valve MOV-3-750.Caused by Personnel Error.Personnel Briefed |
- on 881121,specialist Accidently short- Circuited Power Terminal Lead Which Resulted in Closure of RHR Suction Isolation Valve MOV-3-750.Caused by Personnel Error.Personnel Briefed
| 10 CFR 50.73(e)(2) 10 CFR 50.73(e)(1) | | 05000250/LER-1988-030, :on 881202,determined That Safety Injection Accumulator Level Tech Spec Limits Possibly Exceeded During Operation.Caused by Errors in Design Which Installed Transmitters.Transmitters Being Replaced |
- on 881202,determined That Safety Injection Accumulator Level Tech Spec Limits Possibly Exceeded During Operation.Caused by Errors in Design Which Installed Transmitters.Transmitters Being Replaced
| | | 05000250/LER-1988-031, Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed | Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed | | | 05000250/LER-1988-032, :on 881202,personnel Error Resulted in Loss of Power to Vital Instrument Bus & Isolation of Stated Ventilation Sys.Operator Counseled.Spare Inverter Relabeled as Spare & Procedures Revised |
- on 881202,personnel Error Resulted in Loss of Power to Vital Instrument Bus & Isolation of Stated Ventilation Sys.Operator Counseled.Spare Inverter Relabeled as Spare & Procedures Revised
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