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o, Carolina Power & Light Company Brunswick Nuclear Pruject P-. O. Box 10429 Southport, N.C.
28461 0429 April 30, 1990 FILE:
B09 135100 10CFR50.73 SERIAL:
BSEP/90 0359 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D. C. 20555 BRUNSWICK STEAM ELECTRIC PLANT UNIT 2 DOCKET No. 50 324 LICENSE NO. DPR-62 SUPPLEMENT TO LICENSEE EVENT REPORT 2-90-001 Gentlemen:
In accordance with Title 10 of the Code of Federal Regulations, the enclosed Supplemental Licensee Event Report is submitted. The original report fulfilled the requirement for a written report within thirty (30) days of a reportable occurrence and was submitted in accordance with the format set forth in NUREG.
1022, September 1983.
Very truly yours,
/ fcf J
L. Harne,, General Manager l
Brunswick Nuclear Project 1
TMJ/
Enclosure cc:
Mr. S. D. Ebneter Mr. N. B. Le BSEP NRC Resident Office 9005040013 900430 PDR ADOCK 05000324 l
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On February 10, 1990, it was determined that the Unit 2 Core Spray (CS) loops A
and B
were inoperable because of a
missed l
surveillance.
A maintenance surveillance test (MBT),
Residual Heat Removal (RHR)/CS Lo Reactor Pressure - Permissive Trip Unit i
Channel Calibration, 2MST-RHR26M, had been excepted from j
performance on September 25, 1989, due to the RHR system being out of service during a refuel outage.
The MST was added to the supplement sheet of the RHR LCOs, but not on a CS LCO.
On February 6,
1990, both CS loops were declared operable after the work items j
listed on the LCO supplement sheets were completed; the RHR sub-systems continued to be under LCO.
At 1305 on February 7, the spent fuel pool gates were installed, requiring two low pressure core cooling sub-systems to be operable (T/8 3.5.3.1).
The missed MST was discovered at 1300 on February 10, and CS A and B were declared inoperable.
At 1454, the MST was completed and CS operability was declared.
The event was caused by the lack of formal guidelines for determining LCOs applicable to excepted MSTs and a lack of readily available information to the SRO about the surveillances associated with the MST.
Interim measures will be initiated to require personnel requesting SRO concurrence to provide surveillance information associated with the exception.
Procedural guidance will be incorporated by September 1, 1990.
This is an isolated event and had minimal safety significance.
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EVENT Failure to meet Technical Specification (T/8) 3.5.3.1 as a result of a missed surveillance.
j INITIAL CONDITIONS On. February 10, 1990, Unit 2 reactor was shutdown, in refuel mode (i.e., Mode'5), during a scheduled outage., vessel reload was' i
completed and the fuel pool gates were installed.
The Residual I'
Heat Removal / Low Pressure Coolant Injection (RHR/LPCI) loops A and B were inoperable under Limiting condition For Operation (LCO), A-2-89-1705 and A-2-89-1716, for outage related work.
Loops A and B of the Core Spray (CS) System were considered operable.
Preparations were in progress to enter cold shutdown' "
(i.e., Mode 4) from refuel in accordance with General Plant Operating Procedure (GP) 08, Refueling to Cold Shutdown.
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EVENT DESCRIPTION
In accordance with GP-08, step 5.1.12, a Mode Change System Report (Mode 5 to 4) print out was obtained from the Surveillance Tracking and Scheduling System (STSS) to identify the surveillances required to enter Mode 4.
At 1300 on February 10, 1990, while verifying that the identified surveillances were current or listed on an appropriate LCO, per step 5.1.15, a Senior Reactor Operator (SRO) determined that a Maintenance Surveillance Test (MST) required for Core Spray to be operable had been missed.
LCO A-2-89-0197 was initiated on CS loops A and B at 1300.
At 1454, the MST was completed and operability was declared.
EVENT INVESTIGATION /CAUSJ[
2MST-RHR26M, RHR CS Low Reactor Pressure Permissive Trip Unit Channel Calibration, had last been performed on August 28, 1989.
The frequency of the MST is at least once per 31 days-when the RNR and/or CS systems are required to be operable.
The next scheduled date for the MST was September 23, 1989, with an overdue date of September 30,-1989.
On September 9, 1989, the Unit 2 reactor began a shutdown for a scheduled refuel and maintenance outage.
The unit entered cold shutdown on September 10, 1989.
On September 11 and 12, 1989, RHR Low Pressure Coolant Injection (LPCI) system loops A and B were removed from service and placed under LCOs A-2-89-1705 and 1716, respectively.
In accordance with T/S 3.5.3.2 (i.e., LPCI
- - LCO) both loops of CS were operable at the time.. On September 13, 1989, Unit 2 entered Refuel at 2230.
At 0155 on September 16, 1989, the fuel pool gates were removed.
The CS LCO, 3.5.3.1, 4
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.an we as uim states that:
The core spray system is not required to be OPERRBLE provided that the reactor vessel head is removed and the cavity is flooded, the spent fuel pool gates are removed, and the water level is maintained within the limits of Specifications 3.9.8 and 3.9.9.
Therefore, on september 16, 1989, with the vessel head removed, the vessel flooded and the level maintained within the appropriate limits, neither LPCI nor CS were required to be
- - l operable after the removal of the spent fuel pool gates was accomplished.
On september 21, 1989, the B loop of CS was placed under LCO A-2-89-1788 for outage related work.
On September 25, 1990, 2MST-RHR26M was " excepted" from performance because the RHR system was removed from service.
(HExcepted" is the term applied whenever a test is not performed or is unsatisfactory.)
In order to except the MST, the group responsible for its completion has to fill l
out a surveillance Test Completion / Exception Form and route it to the Regulatory Compliance group responsible for the Surveillance Tracking and Scheduling System (STSS).
The referenced forms are l
l printed out on a weekly basis and delivered to the groups l
responsible for the performance of the scheduled tests.
In this case, an Instrumentation and Control (IEC) technician took the exception form to the Unit 2 control room to inform operations that the test could not be performed and that the MST needed to be added to the appropriate LCOs.
It is Operations responsibility to determine which LCOs are required.
The SRO~
reviewing the exception sheet recalls that september 25, 1989, I
was a busy day and that the IEC technician brought a number of exception forms to the control room to be filled out.
- However, the exception form only lists the procedure number and does not specify which T/s surveillance requirements are satisfied by the i
scheduled test or what the actual title is.
In addition, if the procedure involves more than ene system, its associated procedure number only references the system most involved with the test.
The surveillance in question is numbered 2MST-RNR26M.
Since the majority of procedures only affect the system coded in the procedure number and the IEC technician did not provide him with a listing of the T/8s associated with the MBT, the SRO assumed that only the RHR system was involved and he added the M8T to the RHR LCOs only.
This ensured that the MST would be performed _ _
prior to cancellation of the RHR LCOs but did not tie the MST to C8 operability.
In fact, the MST should also have been added-to h.c Fera agaA (6491 2
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u.c mmnn the existing LCO on B loop CS and a LCo should have been initiated on the A loop.
i On October 19, 1989, the A loop of C8 was placed under LCO, A 89-2016 for outage work.
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on october 23, November 18, December 16, 1989 and on January 14,-
1990, the MST was again excepted from performance because the RHR systems were still under LCos A-2-89-1705 and 1716.
During these exceptions, the IEC personnel verified that the referenced RNR LCOs were still active and then filled out the exception form based on the assumption that the MST had been properly excepted in September of 1989.
This removed operations from the exception loop and prevented the detection of the error.
I On February 6, 1990, at 0533 and 1137, the C8 B and A loop LCOs t
were cancelled, respectively.
The C8 loops were declared operable based on the fact that the work and testing associated with the LCos had been completed.
Since the MST had not been added to the LCO it was not known that it needed to be performed.
At this time the fuel pool gates were still removed and the C8 loops were not required by T/8 to be operable.
On February 7, 1990, at 1257, the fuel pool gates were installed and C8 A and B loops were now required to be operable because the LPCI loop A and B LCOs were still in affect.
On February 10, 1990, at 1300, during preparations to enter cold shutdown in accordance with GP-08, it was determined that CB A and B loops were inoperable because 2 MBT-RNR26M had not been performed.
The A and B loops of C8 were placed under LCO A 90-0197 at 1300.
The test was performed and the T/8 surveillance requirements were met.
LCO A-2-90-0197 was cancelled at 1454.
Three days, one hour and fifty seven minutes elapsed from the time CS was required to be operable till the time it was accurately declared operable.
This event was caused by the lack of formal guidelines for determining which LCOs need to be initiated when a test is excepted.
Factors contributing to this event include the lack of readily available information to the SRO about the surveillances associated with the MST and-the mindset that the system abbreviated in the procedure number is the only system which has surveillance requirements associated with the procedure.
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CORRECTIVE ACTIONS
As an interim measure, instructions will be issued that require 3
personnel obtaining concurrence from the 8F/8R0 on an exception to provide the 8F/8R0 with a copy of the purpose section of the test.or a 8T88 Surveillance Test Cross Reference to T/S (i. e.,.
RCI-02.5) printout.
Either of these items will provide the 'n'~
8F/8R0 with the information needed to determine what 1,cos are applicable to the test being excepted.
Procedural guidance will be incorporated.by September 1, 1990 and the interim instructions will be deleted.
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EVENT ASSESSMENT This event had minimal safety significance as the Core Spray i
system would have injected, if required, as evidenced by the completion of the test with T/8 surveillance requirements' met.
l In addition, the condensate system was available as>a backup injection source.
This is considered an isolated event.
i EIJB Component Identifiera SYSTEM IDENTIFIER RHR/LPCI B0 CS BM 1
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| | | Reporting criterion |
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| 05000325/LER-1990-001, :on 900102,RCIC Removed from Svc & HPCI Rendered Inoperable,Placing Unit in Tech Spec 3.0.3.Caused by Personnel Error.Individual Counseled & Standing Instruction 90-003 Issued |
- on 900102,RCIC Removed from Svc & HPCI Rendered Inoperable,Placing Unit in Tech Spec 3.0.3.Caused by Personnel Error.Individual Counseled & Standing Instruction 90-003 Issued
| | | 05000324/LER-1990-001-03, :on 900210,determined That Core Spray Loops a & B Inoperable Due to Missed Surveillance.Cause Not Stated. Investigation Continuing |
- on 900210,determined That Core Spray Loops a & B Inoperable Due to Missed Surveillance.Cause Not Stated. Investigation Continuing
| | | 05000324/LER-1990-001, :on 900210,determined That Core Spray Loops a & B Inoperable Due to Missed Surveillance.Caused by Lack of Formal Guidelines.Instructions Issued to Personnel |
- on 900210,determined That Core Spray Loops a & B Inoperable Due to Missed Surveillance.Caused by Lack of Formal Guidelines.Instructions Issued to Personnel
| | | 05000325/LER-1990-002-01, :on 900127,common Control Bldg HVAC Sys Isolated & Transferred to Recirculation Mode as Result of Spurious Actuation of Chlorine Detector.Sensor Connection Checked |
- on 900127,common Control Bldg HVAC Sys Isolated & Transferred to Recirculation Mode as Result of Spurious Actuation of Chlorine Detector.Sensor Connection Checked
| | | 05000324/LER-1990-002-02, :on 900224,Group I Isolation Occurred When Undervoltage Relay Replaced.Caused by Lack of Recognition of Significance of Having Turbine Reset While Performing Electro Hydraulic Control Evolutions |
- on 900224,Group I Isolation Occurred When Undervoltage Relay Replaced.Caused by Lack of Recognition of Significance of Having Turbine Reset While Performing Electro Hydraulic Control Evolutions
| | | 05000324/LER-1990-003, :on 900312,full Group 1 Isolation Signal Received,Resulting in Automatic Closure of Msivs.Caused by Personnel Failing to Follow Procedures.Personnel Counseled & Procedure Separated Into Two Tests |
- on 900312,full Group 1 Isolation Signal Received,Resulting in Automatic Closure of Msivs.Caused by Personnel Failing to Follow Procedures.Personnel Counseled & Procedure Separated Into Two Tests
| | | 05000325/LER-1990-003-02, :on 900302,HPCI Sys Declared Inoperable to Stop Leak on Steam Supply Drain Line.Caused by Severe Steam Erosion at 90 Degree Elbow.Involved Section of Piping Replaced on Units 1 & 2 |
- on 900302,HPCI Sys Declared Inoperable to Stop Leak on Steam Supply Drain Line.Caused by Severe Steam Erosion at 90 Degree Elbow.Involved Section of Piping Replaced on Units 1 & 2
| | | 05000324/LER-1990-003-03, :on 900312,closure of Main Steam Line Isolation Valves Occurred.Caused by Failure to Reset Half Scram Signal on Channel a Prior to Continuing Test on Channel B of Associated Instrumentation |
- on 900312,closure of Main Steam Line Isolation Valves Occurred.Caused by Failure to Reset Half Scram Signal on Channel a Prior to Continuing Test on Channel B of Associated Instrumentation
| | | 05000324/LER-1990-004-02, :on 900313,manual Reactor Scram Initiated Due to Failure of Safety/Relief Valve to Close During Startup Testing.Caused by Failure of Solenoid Valve.Valve Replaced |
- on 900313,manual Reactor Scram Initiated Due to Failure of Safety/Relief Valve to Close During Startup Testing.Caused by Failure of Solenoid Valve.Valve Replaced
| | | 05000325/LER-1990-004-03, :on 900322,injector Piping Failed on Chlorinator 5 Due to Improper Bonding of Piping.Caused by Sudden Separation of Chlorine Assembly at Junction of Reducing Bushing & Flange Adapter |
- on 900322,injector Piping Failed on Chlorinator 5 Due to Improper Bonding of Piping.Caused by Sudden Separation of Chlorine Assembly at Junction of Reducing Bushing & Flange Adapter
| | | 05000324/LER-1990-005-03, :on 900514,unplanned Closure of HPCI Isolation Valve Occurred During Maint Surveillance Test.Caused by Technician Placing RCIC Instead of HPCI Test Switch to Test Position.Personnel Counseled & Trained |
- on 900514,unplanned Closure of HPCI Isolation Valve Occurred During Maint Surveillance Test.Caused by Technician Placing RCIC Instead of HPCI Test Switch to Test Position.Personnel Counseled & Trained
| | | 05000325/LER-1990-005-02, :on 900330,Clearance F-2-90-F0096 Placed on Makeup Water Treatment Bldg Sprinkler Sys W/O Meeting Requirements of Tech Spec 3.7.7.2.Oversight Caused by Personnel Error.Fire Watch Established |
- on 900330,Clearance F-2-90-F0096 Placed on Makeup Water Treatment Bldg Sprinkler Sys W/O Meeting Requirements of Tech Spec 3.7.7.2.Oversight Caused by Personnel Error.Fire Watch Established
| | | 05000325/LER-1990-006, :on 900426,hydraulic Perturbation Occurred Causing Reactor Bldg Ventilation Sys to Isolate.Caused by Air in Transmitters During Flushing of Instrument.Procedure Revs Initiated to Change Valving Process |
- on 900426,hydraulic Perturbation Occurred Causing Reactor Bldg Ventilation Sys to Isolate.Caused by Air in Transmitters During Flushing of Instrument.Procedure Revs Initiated to Change Valving Process
| | | 05000325/LER-1990-006-02, :on 900426,hydraulic Perturbation Occurred on Variable Leg of Instrumentation Used to Sense Reactor Water Level,Causing Isolation of RWCU Sys & Initiation of Standby Gas Treatment Sys.Diaphragm Assembly Recalibr |
- on 900426,hydraulic Perturbation Occurred on Variable Leg of Instrumentation Used to Sense Reactor Water Level,Causing Isolation of RWCU Sys & Initiation of Standby Gas Treatment Sys.Diaphragm Assembly Recalibr
| | | 05000324/LER-1990-006-01, :on 900604,hydraulic Perturbation of Reactor Vessel Resulted in Isolation of RWCU Sys.Caused by Increased Differential Pressure.Operations Personnel Restored Affected Sys to Svc |
- on 900604,hydraulic Perturbation of Reactor Vessel Resulted in Isolation of RWCU Sys.Caused by Increased Differential Pressure.Operations Personnel Restored Affected Sys to Svc
| | | 05000325/LER-1990-007-01, :on 900511,identified That Damper Would Fail to Close on Loss of Power to Solenoid Valve & on 900526,damper Found Approx 30 Degrees Open.Caused by Failure of Design to Include Fail Safe Damper.Damper Modified |
- on 900511,identified That Damper Would Fail to Close on Loss of Power to Solenoid Valve & on 900526,damper Found Approx 30 Degrees Open.Caused by Failure of Design to Include Fail Safe Damper.Damper Modified
| | | 05000325/LER-1990-007, :on 900511,identified That Emergency Air Filtration Sys Inlet Damper 2L-D-CB Would Fail to Close on Loss of Power to Damper Solenoid Valve.Caused by Inadequate Damper Design.Damper Secured & Mod Implemented |
- on 900511,identified That Emergency Air Filtration Sys Inlet Damper 2L-D-CB Would Fail to Close on Loss of Power to Damper Solenoid Valve.Caused by Inadequate Damper Design.Damper Secured & Mod Implemented
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000324/LER-1990-007-03, :on 900724,unit HPCI Sys Received Three Isolations of Outboard Valve.Caused by Loose Wire Landing on Terminal of Temp Module.Loose Wire Tightened.Request Made to Have Engineering Evaluate Adequacy of Design |
- on 900724,unit HPCI Sys Received Three Isolations of Outboard Valve.Caused by Loose Wire Landing on Terminal of Temp Module.Loose Wire Tightened.Request Made to Have Engineering Evaluate Adequacy of Design
| | | 05000325/LER-1990-008-02, :on 900514,HPCI Sys Rendered Inoperable When Control Power Lost to Min Flow Bypass Valve to Suppression Pool.Probably Caused by Design Problem W/Ge Model CR2940 Sockets.Light Bulb & Fuse Replaced |
- on 900514,HPCI Sys Rendered Inoperable When Control Power Lost to Min Flow Bypass Valve to Suppression Pool.Probably Caused by Design Problem W/Ge Model CR2940 Sockets.Light Bulb & Fuse Replaced
| | | 05000324/LER-1990-008-03, :on 900816,reactor Automatically Shutdown on Turbine Stop Valve Fast Closure Reactor Protection Sys Trip Signal.Caused by Failure of Primary Power Fuse C32-F5.Fuse Replaced |
- on 900816,reactor Automatically Shutdown on Turbine Stop Valve Fast Closure Reactor Protection Sys Trip Signal.Caused by Failure of Primary Power Fuse C32-F5.Fuse Replaced
| | | 05000325/LER-1990-009-01, :on 900507,determined That Tech Spec 4.6.1.1 Requirements Not Met After Performing Monthly Periodic Test 2.2.4a.Caused by Inadequate Procedure.Recommended Procedure Revs to Prevent Recurrence Being Evaluated |
- on 900507,determined That Tech Spec 4.6.1.1 Requirements Not Met After Performing Monthly Periodic Test 2.2.4a.Caused by Inadequate Procedure.Recommended Procedure Revs to Prevent Recurrence Being Evaluated
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(s)(2) | | 05000324/LER-1990-009-03, :on 900819,ESF Actuation/Rps Trip Occurred While Performing Surveillance Test on Condenser Low Vacuum Instrumentation & Isolation Logic.Caused by Personnel Error. Maint Surveillance Tests Reperformed |
- on 900819,ESF Actuation/Rps Trip Occurred While Performing Surveillance Test on Condenser Low Vacuum Instrumentation & Isolation Logic.Caused by Personnel Error. Maint Surveillance Tests Reperformed
| | | 05000324/LER-1990-010-02, :on 900822,reactor Protection Sys Bus a Deenergized During Cold Shutdown.Caused by Personnel Error. Operators Disciplined & Clearance Procedure Will Be Revised to Clarify Double/Independent Verification |
- on 900822,reactor Protection Sys Bus a Deenergized During Cold Shutdown.Caused by Personnel Error. Operators Disciplined & Clearance Procedure Will Be Revised to Clarify Double/Independent Verification
| | | 05000324/LER-1990-011, :on 900830,RWCU Sys Manually Isolated Following Receipt of RWCU Leak Hi & hi-hi Annunciators |
- on 900830,RWCU Sys Manually Isolated Following Receipt of RWCU Leak Hi & hi-hi Annunciators
| | | 05000324/LER-1990-011-02, :on 900830,RWCU Sys G31 Received Leak Hi & RWCU Leak Hi Hi Annunciators Although Actual Leak Had Not Occurred.Caused by Air in Instrument 2-G31-FT-N012 Sensing Lines.Investigation to Be Conducted |
- on 900830,RWCU Sys G31 Received Leak Hi & RWCU Leak Hi Hi Annunciators Although Actual Leak Had Not Occurred.Caused by Air in Instrument 2-G31-FT-N012 Sensing Lines.Investigation to Be Conducted
| | | 05000324/LER-1990-012, :on 900830,reactor Scram Occurred |
- on 900830,reactor Scram Occurred
| | | 05000324/LER-1990-012-02, :on 900830,Unit 2 Reactor Scram Occurred During Reactor Startup.Investigation Continuing.Level Recovered W/O Need for Safety Sys Injection & Unit Designed for Level Transient from Full Power |
- on 900830,Unit 2 Reactor Scram Occurred During Reactor Startup.Investigation Continuing.Level Recovered W/O Need for Safety Sys Injection & Unit Designed for Level Transient from Full Power
| | | 05000325/LER-1990-012-01, :on 900705,determined That 18-month Surveillance on Battery 1A-1 Exceeded Surveillance Time Interval.Probably Caused by Tech Spec Change & Rescheduling of Outage.Personnel Counseled |
- on 900705,determined That 18-month Surveillance on Battery 1A-1 Exceeded Surveillance Time Interval.Probably Caused by Tech Spec Change & Rescheduling of Outage.Personnel Counseled
| | | 05000325/LER-1990-013-01, :on 900725,containment Atmospheric Control & Containment Atmospheric Dilution Subsystem Design Does Not Meet FSAR Commitments & Design Requirements.Seven Day Tracking Condition for Operator Established |
- on 900725,containment Atmospheric Control & Containment Atmospheric Dilution Subsystem Design Does Not Meet FSAR Commitments & Design Requirements.Seven Day Tracking Condition for Operator Established
| | | 05000324/LER-1990-013-02, :on 900906,HPCI Declared Inoperable Due to Erratic Performance During Periodic Testing.Caused by Deficient Needle Valve Position.Maint Will Revise Procedures to Enhance Controls for Egr Needle Valve Adjustments |
- on 900906,HPCI Declared Inoperable Due to Erratic Performance During Periodic Testing.Caused by Deficient Needle Valve Position.Maint Will Revise Procedures to Enhance Controls for Egr Needle Valve Adjustments
| | | 05000325/LER-1990-013, :on 900725,determined That Cad/Containment Atmosphere Dilution Subsystem Design Did Not Meet FSAR Re Redundancy of Power Supply for Vaporizer Trains.Caused by Changing Regulatory Commitments.Sys Reviewed |
- on 900725,determined That Cad/Containment Atmosphere Dilution Subsystem Design Did Not Meet FSAR Re Redundancy of Power Supply for Vaporizer Trains.Caused by Changing Regulatory Commitments.Sys Reviewed
| 10 CFR 50.73(a)(2) | | 05000325/LER-1990-014-02, :on 900907,reactor Protection Sys Bus a Tripped When Electrical Protection Assembly a Opened on Underfrequency.Caused by Circuit Board Failure.Circuit Board Sent to GE for Analysis |
- on 900907,reactor Protection Sys Bus a Tripped When Electrical Protection Assembly a Opened on Underfrequency.Caused by Circuit Board Failure.Circuit Board Sent to GE for Analysis
| | | 05000324/LER-1990-014-01, :on 900908,discovered ESF Actuation - RWCU Isolation When Fuse Blew in Power Supply to Differential Flow Istrument |
- on 900908,discovered ESF Actuation - RWCU Isolation When Fuse Blew in Power Supply to Differential Flow Istrument
| 10 CFR 50.73(a)(2) | | 05000325/LER-1990-014, :on 900907,ESF/RPS Actuation Occurred When Electrical Protection Assembly 2 Opened on Under Frequency & RPS Bus a Tripped Due to Failed Circuit Board |
- on 900907,ESF/RPS Actuation Occurred When Electrical Protection Assembly 2 Opened on Under Frequency & RPS Bus a Tripped Due to Failed Circuit Board
| | | 05000324/LER-1990-015-02, :on 900927,generator Voltage Oscillations Experienced Which Resulted in Loss of Main Generator Due to Loss of Excitation.Caused by Unstable Voltage Regulator. Regulator & Circuitry Reset |
- on 900927,generator Voltage Oscillations Experienced Which Resulted in Loss of Main Generator Due to Loss of Excitation.Caused by Unstable Voltage Regulator. Regulator & Circuitry Reset
| | | 05000325/LER-1990-015-01, :on 900926,incorrect LPRM Assignment Occurred Due to Reversed Cables |
- on 900926,incorrect LPRM Assignment Occurred Due to Reversed Cables
| | | 05000325/LER-1990-016-01, :on 900917,operation Prohibited by Tech Specs During Scram Discharge Vol Maint & Surveillance Activities |
- on 900917,operation Prohibited by Tech Specs During Scram Discharge Vol Maint & Surveillance Activities
| | | 05000324/LER-1990-016-02, :on 901012,reactor Scram Occurred on Turbine Stop Valve Fast Closure Caused by Reactor High Level When Fuse Failed in Feedwater Control Sys Circuitry |
- on 901012,reactor Scram Occurred on Turbine Stop Valve Fast Closure Caused by Reactor High Level When Fuse Failed in Feedwater Control Sys Circuitry
| 10 CFR 50.73(a)(2) | | 05000324/LER-1990-017-02, :on 901023,ESF Actuation Occurred Due to Blown Fuse in Main Steam Line B & Reactor Bldg Ventilation Radiation Monitoring Power Supply B |
- on 901023,ESF Actuation Occurred Due to Blown Fuse in Main Steam Line B & Reactor Bldg Ventilation Radiation Monitoring Power Supply B
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) | | 05000324/LER-1990-017, :on 901023,half Trip Signal,Half PCIS Group 1 Isolation Signal & Group 6 Isolation Occurred.Caused by Failure of Kepco Power Supply in Numac Lvps to Radiation Monitor B.Numac Lvps Replaced |
- on 901023,half Trip Signal,Half PCIS Group 1 Isolation Signal & Group 6 Isolation Occurred.Caused by Failure of Kepco Power Supply in Numac Lvps to Radiation Monitor B.Numac Lvps Replaced
| | | 05000325/LER-1990-017-01, :on 900927,high Pressure Reactor Scram Occurred While Performing Periodic Test PT-40.2.10 Due to Erroneous Procedure Guidance & Defective Turbine Stop Valve Switches |
- on 900927,high Pressure Reactor Scram Occurred While Performing Periodic Test PT-40.2.10 Due to Erroneous Procedure Guidance & Defective Turbine Stop Valve Switches
| | | 05000325/LER-1990-018-01, :on 900927,Group 6 Isolation & Standby Gas Treatment Sys Autostart Signal Received as Result of Momentary Loss of Power to Main Stack Radiation Monitor. Caused by Reactor Scram |
- on 900927,Group 6 Isolation & Standby Gas Treatment Sys Autostart Signal Received as Result of Momentary Loss of Power to Main Stack Radiation Monitor. Caused by Reactor Scram
| | | 05000324/LER-1990-018-02, :on 901123,HPCI Steam Leak Detection Channel B Logic Blew & HPCI Sys Manually Isolated.Probably Caused by Blown Fuse & Loose Wire.Relay & Fuse Replaced |
- on 901123,HPCI Steam Leak Detection Channel B Logic Blew & HPCI Sys Manually Isolated.Probably Caused by Blown Fuse & Loose Wire.Relay & Fuse Replaced
| 10 CFR 50.73(a)(2) | | 05000325/LER-1990-019, :on 901002,technician Mistakenly Placed Channel B Detector to Radiation Source,Resulting in Group 6 Valve Isolations.Caused by Personnel Error.Disciplinary Action Taken |
- on 901002,technician Mistakenly Placed Channel B Detector to Radiation Source,Resulting in Group 6 Valve Isolations.Caused by Personnel Error.Disciplinary Action Taken
| | | 05000324/LER-1990-019-02, :on 901226,isolation Signal Caused Reactor Water Cleanup Inlet Inboard Isolation Valve to Automatically Close.Caused by de-energized HPCI Isolation Relay.Riley Scam Temp Switch Units Will Be Replaced |
- on 901226,isolation Signal Caused Reactor Water Cleanup Inlet Inboard Isolation Valve to Automatically Close.Caused by de-energized HPCI Isolation Relay.Riley Scam Temp Switch Units Will Be Replaced
| 10 CFR 50.73(a)(2) | | 05000325/LER-1990-020-01, :on 901117,primary & Secondary Containment Isolation Signals Received & Standby Gas Treatment Sys auto- Started.Caused by Scan Overload on Microprocessor.Updated Microprocessor Will Be Obtained |
- on 901117,primary & Secondary Containment Isolation Signals Received & Standby Gas Treatment Sys auto- Started.Caused by Scan Overload on Microprocessor.Updated Microprocessor Will Be Obtained
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000324/LER-1990-020-02, :on 901226,while Returning HPCI Sys to Svc, Determined That Min Flow Valve Control Power Fuse Blown, Resulting in Inoperability of Valve.Caused by Short in Indicating Light Bulb.Bulb & Fuse Replaced |
- on 901226,while Returning HPCI Sys to Svc, Determined That Min Flow Valve Control Power Fuse Blown, Resulting in Inoperability of Valve.Caused by Short in Indicating Light Bulb.Bulb & Fuse Replaced
| 10 CFR 50.73(a)(2) | | 05000325/LER-1990-021, :on 901007,diesel Generator 4 Declared Inoperable |
- on 901007,diesel Generator 4 Declared Inoperable
| | | 05000325/LER-1990-022, :on 901022,primary Containment Isolation Sys Actuation of EFCV Occurred While Performing Maint Surveillance Test |
- on 901022,primary Containment Isolation Sys Actuation of EFCV Occurred While Performing Maint Surveillance Test
| 10 CFR 50.73(a)(2) | | 05000325/LER-1990-023, :on 901022,various Isolation Valves in Group 6 Isolation Logic Found Closed Due to Failure of 1-CAC-3A Relay |
- on 901022,various Isolation Valves in Group 6 Isolation Logic Found Closed Due to Failure of 1-CAC-3A Relay
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
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