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PHILADELPHIA ELECTRIC COMPANY LIMERICK GENER ATING ST ATION P. O. 00X A SAN ATOO A. PENNSYLV ANI A is464 (ris) sedizoo en. noco November 21, 1990 Docket No. 50-353 m. s. u.c o u c a. s..
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License No. NPf-85 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Licensee Event Report Limerick Generating Station - Unit 2 This LER reports a failure to meet Technical Specifications (TS) Section 3.7.6.4, "Halon Systems," since the Halon System had been inoperable and the Action required by TS was not taken in the appropriate time period. This resulted in a condition prohibited by 15.
Reference:
Docket No. 50-353 Report Number:
2-90-016 Revision Number:
01 Event Date:
August 11, 1990 Discovery Date:
August 13, 1990 Reportability Date: September 10, 1990 Report Date:
November 21, 1990 facility:
Limerick Generating Station P.O. Box A. Sanatoga, PA 19464 This revised LER is being submitted to provide additional information regarding-the cause and corrective actions. Changes to this revised LER are indicated by revision bar markers in the right hand margin.
The original LER was submitted pursuanttotherequirementsof10CFR50.73(a)(2)(1)(B).
Very ruly yours,
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T. T. Martin, Administrator, Region 1. USNRC T. J. Kenny, USNRC Senior Resident inspector, LGS ool13co m. 90112i
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l On July 5, 1990. Unit 2 Surveillance Test (ST) Procedure ST-7-022-353-2. "Halon System Inventory " was performed for the Auxiliary Equipment Room (AER) Halon fire Suppression System.
This ST identified one weight deficient bottle in tne Halon System Main Bank. The Main Bank was declared inoperable and the
" Main / Reserve" switch (HS-22-283A) was placed in the " Reserve" position switching the Halon System to its redundant Reserve Bank. The deficient bottle was removed on July 24, 1990 to be refilled and HS-22-283A was still in the "as left" position of " Reserve." However, on August 13, 1990, while preparing to replace the refilled Main Bank bottle. station personnel discovered that HS-22-283A was in the " Main" position. HS-22-283A was immediately put in the
" Reserve" position by the fire Protection system engineer and Halon system operability was restored. There were no adverse consequences in that no fires occurred in the Unit 2 AER during this time period. Further investigation into this event identified the cause to be: 1) a lack of adequate job planning and coordination and 2) use of a tagging system that has been determined to be inadequate for this halon system application. Corrective actions include a revision to STs that will initiate a blocking mechanism to provide administrative control of Halon bottles and the development of a halon system Maintenance Request form historv file that will be referenced and duplicated to ensure adequate job planning.
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UCENSEE EVENT REPORT (LER) TEXT C:NTINUATION c.:ovfo ove *o m o e t uhat s l'2ilen e outy hawa sti poc a a t huws t a u' Le n avusta its PA04 0' UN'N Limerick Generating Station 0 l6 ]o l0 l0 l3l Sl3 9l0 0 l1 Ol2 0' O l5 0l1[6 mm -...-...~ ~ac m.s o n Unit Conditions Prior to the Event:
Unit 2 Operating Condition was 1 (Power Operation) at 100% Power Level.
Description of the Event:
On July 5, 1990, Unit 2 Surveillance Test (ST) Procedure ST-7-022-353-2, "Halon System inventory," was performed for the Auxiliary Equipment Room (AER) subfloor and panel Halon fire Suppression system.
The fire Protection system engineer identified at the completion of this test that one bottle in the Unit 2 Halon System Main Bank (i.e. consisting of 7 bottles) was low on weight and pressure.
The Halon System Main Bank was then declared inoperable and the " Main / Reserve" Switch (HS-22-283A) wat placed in the " Reserve" position switching the Halon System to its redundant Reserve Bank and ensuring system operability.
Additionally, an Equipment Status Control Tag was placed on HS-22-283A by the fire Protection system engineer as directed by operations personnel to indicate that the system was in an off-normal system alignment. These actions were to ensurethatTechnicalSpecifications(TS)Section3.7.6.4,"HalonSystems,"was satisfied by maintaining an Qerable Halon system with 95% of full charge weight dnd 90% of full charge pressure. The deficient bottle was removed on July 24, 1990 to be refilled and HS-22-283A was in the " Reserve" position which aligned the redundant Halon system Reserve Bank to automatically initiate in the event of a fire in the Unit 2 AER.
However, on August 13, 1990 at 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br />, while preparing to perform procedure S1-7-022-353-2 to replace the refilled Halon bottle in the Main Bank. HS-22-283A was discovered by the fire Protection system engineer to be in the " Main" position with the Equipment Status Control Tag missing and only six Halon bottles in the Main Bank. The fire Protection system engineer recognized this i
condition as inappropriate and immediately notified shift supervision.
Operations personnel then returned HS-22-283A to the " Reserve" position at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> returning the Halon system to an operable condition. The procedure ST-7-022-353-2 was then completed by reinstalling the refilled Halon bottle in the Main Bank and returning the Halon system " Main / Reserve" Switch, HS-22-283A, into the " Main" position. This returned the Main Bank to an operable condition with the Reserve Bank in ' standby. Both Main and Reserve Halon Banks had a full Halon charge.
On August 13, 1990, an investigation was then initiated to investigate the cause and the actual date/ time when HS-22-283A was changed to the " Main" position.
The specific period of time in question was between the removal of the deficient Main Bank Halon bottle on July 24, 1990 until the discovery that HS-22-283A was mispositioned with the Equipment Status Control Tag missing on August 13, 1990.
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... n.o me w w.wn The investigation revealed that the switch was repositioned on August 11, 1990 as the result of operations personnel performing procedure ST-6-022-453-0,"
Halon System Lineup Verification." The operators who performed this ST observed that all of the seven Halon bottles were in place. Based on the satisfactory completion of ST-6-022-453-0, shift supervision determined that HS-22-283A could be placed in the " Main" position.
The Equipment Status Control Tag was then removed and HS-22-283A was placed in the " Main" position by operations personnel on August II, 1990. However, between August 11, 1990 and August 13, 1990 we suspect that maintenance personnel may have again removed the Main Bank Halon bottle to have it weighed. Therefore, for this time period, with HS-22-283A in the Main position and one Halon bottle removed, the AER Halon system for Unit 2 should have been considered inoperable.
As a result of the Halon system being degraded, the performance of l
ST-7-022-353-2, on July 5, 1990, was evaluated to determine what percentage of Halon weight existed in the Main Bank of the Unit 2 Halon system with one bottle missing (i.e. six bottles in place) which would be used to conclude whether the Main Bank was operable or not.
In conjunction with this evaluation, the load cell and digital display used to weigh the Halon system bottles during the performance of ST-7-022-353-2 were sent to the Philadelphia Electric Conpany Testing and Labs facility to verify instrument calibration. The evaluation of ST-7-022-353-2 was completed on September 10, 1990 and determined that the weight of the Halon Main Bank with six bottles in place was at 94.48% of full charged weight. Also, Testing and Labs confirmed that the load cell and digital display were properly calibrated.
Therefore, with HS-22-283A in the " Main" position and less than 95% of full charged weight, due to the Main Halon bottle being removed to be weighed, the Unit 2 Halon system was inoperable for some time between August 11 and 13, 1990. During this time period the TS Action 3.7.6.4 "with one or more of the required Halon Systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly firewatch patrol " was not taken in the specified time period, This resulted in a condition prohibited by TS and this report is being submitted in accordance with 10CFR50.73(a)(2)(i)(B).
Analysis of the Event
There were no adverse consequences and no radioactive material was released to the environment as a result of this event. During the time the Unit 2 Halon system was aligned to the Main Bank containing six fully charged bottles, no fires occurred in the Unit 2 AER requiring the use of the Halon fire suppression system.
In the event of a fire in the AER, with HS-22-283A in the Main position and the Main Bank missing one Halon bottle, the Main Bank would have automatically initiated and suppressed the firu. There was sufficient Halon in the six Halon bottles in the Main Bank to meet the design levels of fire suppression in the Unit 2 AER panels and subfloor. Main Control Room annunciation of a fire in the
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n.co. m.,an AER would have occurred and alerted operators of a fire in the Unit 2 AER. The fire brigade would then respond as directed by Special Event (SE) Procedure SE-8, " fire," and implement procteure F-A-542, " Auxiliary Equipment Room 542 Elevation 289' fire Area 25."
This procedure instructs the fire brigade to verify automatic initiation of the Halon system and then manually initiate the redundant Halon system bank if needed.
Cause of the Event
The root cause of this event is unknown due to the inability to identify the specific maintenance personnel who may have been involved in moving the Halon bottle. However, causal factors for this event are: 1) the use of an Equipment Status Control Tag that has since been determined to be inadequate in controlling the position of HS-22-283A due to not specifically identifying the need to complete ST-7-022-353-2 prior to placing HS-22-283A in the main position aad 2) the lack of job planning and coordination for the Halon bottle during the time that the Halon bottle was received onsite from the vendor after refilling to the time the bottle was finally-reinstalled.
The investigation into the cause of this event revealed that the Halon bottle, removed on July 24, 1990 and shipped offsite to the vendor for refilling, was received back on site on August 9, 1990. On August 11, 1990, Operators performed ST-6-022-453-2 and verified that all fourteen Halon bottles were in place (i.e., all seven bottles were in the Main Bank and all seven bottles were in the Reserve Bank) prior to remov hg the Equipment Status Control Tag from HS-22-283A.
This tagging mechanism was inadequate for this application in that it indicated the halon bottle was removed, but did not provide any indication of l
outstanding work or testing requirements pending completion prior to returning l
the Main Bank to service. As a result of the information placed on the EquipmentStatusControlTag(i.e.,halonbottleremoved),operationspersonnel l
then reverified that all fourteen Unit 2 halon bottles were in place prior to l
placing HS-22-283A in the " Main" position. The operators who performed the ST were certain that all fourteen Unit ? Halon bottles were in place on August 11, 1990. This is further supported by the operators performing a second verification by physically walking out to the Unit 2 Halon bottles and rechecking as a result of questioning by shift supervision, j
We suspect that the Unit 2 Halon bottle was ' reinstalled by maintenance persor on August 10 or August 11, 1990 as directed by the associated Maintenance Request form (MRF).
This MRf was inadequate in that it indicated that the H' i
bottle needed to be removed, refilled and then installed but did not specify l
that the bottle must be weighed prior to installation. Therefore, we conclude l
that the installation was completed without weighing the bottle between August l
11, 1990 and August 13, 1990, and maintenance personnel again removed the Main Bank bottle to have it weighed after either recognii'ing on their own or being notified by the fire Protection system engineer that the bottle needed to be weighed prior to installation.
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... -.- h.c,- -,m n in conclusion, as a result of inadequate jrb planning and work coordination, the halon bottle was installed prior to involving the fire Protection system enginee who would have ensured the Halon bottle was weighed. Additionally, the tagging mechanism used was inadequate in that it did not identify to operations personnel the necessary actions to perform and groups to contact prior to returning the Halon System Main Bank back to service.
Corrective Actions
ST-7-022-353-1 and ST-7-022-353-2 performed by the Fire Protection group were revised on November 19, 1990 to require the initiation of a supervisory block that controls equipment and will provide administrative controls for halon bottles determined to be deficient and requiring removal from the associated Halon system rack. These procedures will specifically require the deficient halon bottle (s) to be weighed prior to changing position of HS-22-283A and placing a Halon Bank back in service. Additionally, this supervisory block will provide adequate information such as associated MRf numbers and testing requirements enabling operations personnel to be fully, aware of halon system conditions. This supervisory block will ensure that proper STs are performed to demonstrate operability to meet TS Section 3.7.6.4 prior to placing a Halon System Bank back in service.
Additionally, maintenance personnel responsible for the planning section of all MRfs have been provided with instructions located in the MRf history files that l
will be referenced by maintenance planners and written on MRFs for future Halon bottle work. These instructions will ensure that any MRF associated with the removal and installation of Halon bottles will inform maintenance personnel of the need to have the Halon bottle weighed by involving
'"e protection personnel prior to installation of the bottle.
Previous Similar Occurrences:
l None Tracking Codes:
I (A) Personnel Error 1
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| 05000353/LER-1990-001, :on 900108,Tech Spec Violation & Reactor Encl Ventilation Isolation Occurred.Caused by Personnel Error. Chief Operator Counseled on Importance of Communicating All Pertinent Info |
- on 900108,Tech Spec Violation & Reactor Encl Ventilation Isolation Occurred.Caused by Personnel Error. Chief Operator Counseled on Importance of Communicating All Pertinent Info
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(1) | | 05000352/LER-1990-001-01, :on 900122,discovered That Monthly Instrument Channel Functional Test for RCIC Steam Supply Pressure Low Missed.Caused by Deficiency in Computer Program Used to Schedule Tests.Computer Program Revised |
- on 900122,discovered That Monthly Instrument Channel Functional Test for RCIC Steam Supply Pressure Low Missed.Caused by Deficiency in Computer Program Used to Schedule Tests.Computer Program Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | | 05000352/LER-1990-002-01, :on 900125,identified That Main Control Room Ventilation Sys Outside Design Basis.Caused by Misapplication of Design Basis Assumptions.No Immediate Actions Taken as Existing Procedures Adequate |
- on 900125,identified That Main Control Room Ventilation Sys Outside Design Basis.Caused by Misapplication of Design Basis Assumptions.No Immediate Actions Taken as Existing Procedures Adequate
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000353/LER-1990-002, :on 900105,containment H2/O2 Analyzer Declared Inoperable During Containment Inerting.Caused by Reversed Tubing Connections in Installation of Analyzer Due to Mislabeling.Analyzer Restored |
- on 900105,containment H2/O2 Analyzer Declared Inoperable During Containment Inerting.Caused by Reversed Tubing Connections in Installation of Analyzer Due to Mislabeling.Analyzer Restored
| 10 CFR 50.73(a)(2)(1) | | 05000352/LER-1990-003, :on 900208,HPCI Sys Inboard Isolation Valve Isolated During Isolation Logic Surveillance Test.Caused by Mfg Error.Program for Replacement/Rework of Trip Units Being Implemented.Estimated Completion Date Dec 1993 |
- on 900208,HPCI Sys Inboard Isolation Valve Isolated During Isolation Logic Surveillance Test.Caused by Mfg Error.Program for Replacement/Rework of Trip Units Being Implemented.Estimated Completion Date Dec 1993
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-003-01, :on 900208,HPCI Sys Inboard Isolation Valve Inadvertently Isolated & Closed When One Channel of Isolation Logic Tripped.Caused by Degradation of Darlington Output Transistor.Isolation Reset |
- on 900208,HPCI Sys Inboard Isolation Valve Inadvertently Isolated & Closed When One Channel of Isolation Logic Tripped.Caused by Degradation of Darlington Output Transistor.Isolation Reset
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000353/LER-1990-003, :on 900112,primary Containment & Reactor Vessel Isolation Control Sys Isolation Signals Initiated, Closing Inboard & Outboard Isolation Valves for Rwcu.Caused by Lifting Relief Valve.Opening Time Reset |
- on 900112,primary Containment & Reactor Vessel Isolation Control Sys Isolation Signals Initiated, Closing Inboard & Outboard Isolation Valves for Rwcu.Caused by Lifting Relief Valve.Opening Time Reset
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-004, :on 900209,station Personnel Discovered That on 890708,22-s Reactor Power Transient Occurred in Which Reactor Thermal Power Changed by More than 15% of Rated Thermal Power in 1 H.Procedure Revised |
- on 900209,station Personnel Discovered That on 890708,22-s Reactor Power Transient Occurred in Which Reactor Thermal Power Changed by More than 15% of Rated Thermal Power in 1 H.Procedure Revised
| 10 CFR 50.73(a)(2)(1) | | 05000352/LER-1990-005, :on 900211,no Fire Watch Insps for Rooms 103, 114 & 117 on Elevation 177 Ft in Reactor Encl Performed by Personnel.Caused by Personnel Error.Person Involved Disciplined.Training Program Improved |
- on 900211,no Fire Watch Insps for Rooms 103, 114 & 117 on Elevation 177 Ft in Reactor Encl Performed by Personnel.Caused by Personnel Error.Person Involved Disciplined.Training Program Improved
| 10 CFR 50.73(a)(2)(1) | | 05000353/LER-1990-006-01, :on 900312,automatic Actuation of HPCI Sys & Primary Containment & Reactor Vessel Isolation Control Sys Occurred.Caused by Spurious Low Reactor Water Level Signal. Event Discussed at I&C Group Meeting |
- on 900312,automatic Actuation of HPCI Sys & Primary Containment & Reactor Vessel Isolation Control Sys Occurred.Caused by Spurious Low Reactor Water Level Signal. Event Discussed at I&C Group Meeting
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-006, :on 900223,determined That Capability to Activate Emergency Public Notification Sys Sirens from Counties Lost from 900112-0205.Caused by Disconnection of Phone Lines.Lines Reconnected for All Counties |
- on 900223,determined That Capability to Activate Emergency Public Notification Sys Sirens from Counties Lost from 900112-0205.Caused by Disconnection of Phone Lines.Lines Reconnected for All Counties
| | | 05000352/LER-1990-007, :on 900222,high Radiation Reactor Protection Sys Actuation & Isolation Setpoints Set Outside Required Limits.Caused by Personnel Error by Nonlicensed Employee. Setpoints Adjusted & Personnel Counseled |
- on 900222,high Radiation Reactor Protection Sys Actuation & Isolation Setpoints Set Outside Required Limits.Caused by Personnel Error by Nonlicensed Employee. Setpoints Adjusted & Personnel Counseled
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | | 05000353/LER-1990-007-01, :on 900330,actuations of Primary Containment & Reactor Vessel Isolation Control Sys ESF Occurred.Caused by Gross Failure of Inverter Inductor.Inverter Bypassed,Shunt Trip Breaker Closed & Isolations Reset |
- on 900330,actuations of Primary Containment & Reactor Vessel Isolation Control Sys ESF Occurred.Caused by Gross Failure of Inverter Inductor.Inverter Bypassed,Shunt Trip Breaker Closed & Isolations Reset
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000353/LER-1990-008-01, :on 900417,HPCI Sys Isolation & Inoperability Occurred Due to Failure of Differential Pressure Transmitter.Cause of Transmittal Failure Under Investigation.Transmitter Returned to Mfg |
- on 900417,HPCI Sys Isolation & Inoperability Occurred Due to Failure of Differential Pressure Transmitter.Cause of Transmittal Failure Under Investigation.Transmitter Returned to Mfg
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-009, :on 900405,control Room Chlorine Isolation of Habitability Control Room Isolation Sys & ESF Initiated. Caused by Failure of B Toxic Gas Detector & False Signal from Untested Analyzer.Detector Replaced |
- on 900405,control Room Chlorine Isolation of Habitability Control Room Isolation Sys & ESF Initiated. Caused by Failure of B Toxic Gas Detector & False Signal from Untested Analyzer.Detector Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-010, :on 900415,ESF Actuation Occurred Closing Three Containment Isolation Valves for Analyzers.Cause Unknown. Isolation Reset,Analyzers Returned to Svc & Voltmeter Not Being Used Pending Determination of Cause |
- on 900415,ESF Actuation Occurred Closing Three Containment Isolation Valves for Analyzers.Cause Unknown. Isolation Reset,Analyzers Returned to Svc & Voltmeter Not Being Used Pending Determination of Cause
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000353/LER-1990-011, :on 900713,reactor Encl Secondary Containment Isolation or Low Differential Pressure Occurred.Caused by Severed Instrument Air Line.Instrument Air Line Repaired on 900713 |
- on 900713,reactor Encl Secondary Containment Isolation or Low Differential Pressure Occurred.Caused by Severed Instrument Air Line.Instrument Air Line Repaired on 900713
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-011, :on 900420,discovered That Emergency Svc Water Pump B Discharge Check Valve Not Preventing Reverse Flow. Caused by Personnel Error in That Actuating Arm Incorrectly Assembled.Actuating Arm Repositioned |
- on 900420,discovered That Emergency Svc Water Pump B Discharge Check Valve Not Preventing Reverse Flow. Caused by Personnel Error in That Actuating Arm Incorrectly Assembled.Actuating Arm Repositioned
| 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)(1) | | 05000353/LER-1990-011-02, :on 900713,positive Differential Pressure Condition Between Reactor Encl Secondary Containment & Outside Atmosphere Occurred,Resulting in Blowout Panel Actuation.Caused by Severed Air Supply Line |
- on 900713,positive Differential Pressure Condition Between Reactor Encl Secondary Containment & Outside Atmosphere Occurred,Resulting in Blowout Panel Actuation.Caused by Severed Air Supply Line
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000353/LER-1990-012-02, :on 900715,reactor Scram Occurred Due to Main Turbine Trip on Low Main Condenser Vacuum Due to Failed Pipe.Caused by Insufficient Pipe Support Resulting in Vibration Induced Metal Fatigue.Pipe Replaced |
- on 900715,reactor Scram Occurred Due to Main Turbine Trip on Low Main Condenser Vacuum Due to Failed Pipe.Caused by Insufficient Pipe Support Resulting in Vibration Induced Metal Fatigue.Pipe Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-012, :on 900426,inoperability of RHR Sys Modes Occurred Due to Physical Separation Deficiencies.Caused by Drawing Deficiency Resulting in Installation Error During Original Const.Nonclass 1E Cable Sleeved |
- on 900426,inoperability of RHR Sys Modes Occurred Due to Physical Separation Deficiencies.Caused by Drawing Deficiency Resulting in Installation Error During Original Const.Nonclass 1E Cable Sleeved
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(1) | | 05000353/LER-1990-013-02, :on 900831,RCIC Sys Isolation Occurred.Caused by Personnel Error Resulting in Procedural Noncompliance. Procedural Compliance & Higher Attention to Detail Reinforced to Personnel |
- on 900831,RCIC Sys Isolation Occurred.Caused by Personnel Error Resulting in Procedural Noncompliance. Procedural Compliance & Higher Attention to Detail Reinforced to Personnel
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-013, :on 900611,review of Dc Electrical Distribution Sys Identified That Divs 1 & 2 Had Inadequate Isolation Capability Between Class 1E & non-Class 1E Components & Also Had under-rated Dc Fuses |
- on 900611,review of Dc Electrical Distribution Sys Identified That Divs 1 & 2 Had Inadequate Isolation Capability Between Class 1E & non-Class 1E Components & Also Had under-rated Dc Fuses
| 10 CFR 50.73(a)(2)(1) | | 05000352/LER-1990-013-01, :on 900611,dc Distribution Sys Identified to Have Inadequate Isolation Capability Between Class IE & non-Class IE Components.Cause of Event Under Investigation. Hourly Fire Watches Established Until 900626 |
- on 900611,dc Distribution Sys Identified to Have Inadequate Isolation Capability Between Class IE & non-Class IE Components.Cause of Event Under Investigation. Hourly Fire Watches Established Until 900626
| 10 CFR 50.73(a)(2)(1) | | 05000353/LER-1990-014-02, :on 900906,ESF Actuation of Primary Containment & Reactor Vessel Isolation Control Sys Occurred.Caused by Lack of Attention to Detail Resulting in Procedural Noncompliance.Personnel Counseled |
- on 900906,ESF Actuation of Primary Containment & Reactor Vessel Isolation Control Sys Occurred.Caused by Lack of Attention to Detail Resulting in Procedural Noncompliance.Personnel Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-014-01, :on 900705,group III Primary Containment & Reactor Vessel Isolation Control Sys Isolation Signal Occurred,Initiating RWCU Sys Isolation.Causes Included High Outside Air Temp.Normal Ventilation Restored |
- on 900705,group III Primary Containment & Reactor Vessel Isolation Control Sys Isolation Signal Occurred,Initiating RWCU Sys Isolation.Causes Included High Outside Air Temp.Normal Ventilation Restored
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-015-01, :on 900813,RWCU Sys Isolation Occurred. Isolation Resulted from High Regenerative HX Room Temp. Caused by Leaking Sys Vent Valves.Leaking Valves Replaced |
- on 900813,RWCU Sys Isolation Occurred. Isolation Resulted from High Regenerative HX Room Temp. Caused by Leaking Sys Vent Valves.Leaking Valves Replaced
| | | 05000353/LER-1990-015-02, :on 900910,reactor Scram Occurred Due to Spurious Trip Signal from Steam Leak Detection Sys Temp Switch.Caused by Equipment Failure.Temp Switch TTS-25-216D Was Replaced |
- on 900910,reactor Scram Occurred Due to Spurious Trip Signal from Steam Leak Detection Sys Temp Switch.Caused by Equipment Failure.Temp Switch TTS-25-216D Was Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000353/LER-1990-016-01, :on 900811,Tech Spec 3.7.6.4 Not Met Since Halon Sys Inoperable |
- on 900811,Tech Spec 3.7.6.4 Not Met Since Halon Sys Inoperable
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | | 05000352/LER-1990-016-01, :on 900815,Tech Spec Limiting Condition for Operation Action Not Implemented within Required Time Period Due to Firewatch Employee Failure to Perform Surveillance Procedure.Caused by Personnel Falsifying Tests |
- on 900815,Tech Spec Limiting Condition for Operation Action Not Implemented within Required Time Period Due to Firewatch Employee Failure to Perform Surveillance Procedure.Caused by Personnel Falsifying Tests
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000353/LER-1990-016-02, :on 900811,failure to Meet Tech Spec 3.7.6.4 Since Halon Sys Inoperable & Tech Spec Action Not Taken in Appropriate Time Period |
- on 900811,failure to Meet Tech Spec 3.7.6.4 Since Halon Sys Inoperable & Tech Spec Action Not Taken in Appropriate Time Period
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)(8) | | 05000353/LER-1990-017-02, :on 900916,inadvertent Actuation of Primary Containment & Reactor Vessel Isolation Control Sys Occurred |
- on 900916,inadvertent Actuation of Primary Containment & Reactor Vessel Isolation Control Sys Occurred
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-017-01, :on 900828,ESF Actuation of Primary Containment & Reactor Vessel Isolation Control Sys Occurred.Caused by Technician Inadvertently Shorting Power Supply During Installation of Test Jack.Blown Fuse Replaced |
- on 900828,ESF Actuation of Primary Containment & Reactor Vessel Isolation Control Sys Occurred.Caused by Technician Inadvertently Shorting Power Supply During Installation of Test Jack.Blown Fuse Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000353/LER-1990-018-02, :on 901030,north Stack Wide Range Monitor Exceeded 7-day Limit for Inoperability of Tech Spec 3.3.7.5 |
- on 901030,north Stack Wide Range Monitor Exceeded 7-day Limit for Inoperability of Tech Spec 3.3.7.5
| | | 05000352/LER-1990-018-01, :on 900830,common Plant Water & Steam Barriers in Degraded Condition & Unit Placed in Unanalyzed Condition. Detailed Cause Analysis Will Be Provided.Task Force Established |
- on 900830,common Plant Water & Steam Barriers in Degraded Condition & Unit Placed in Unanalyzed Condition. Detailed Cause Analysis Will Be Provided.Task Force Established
| 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | | 05000353/LER-1990-019-02, :on 901101,half-scram & Isolations Resulted from Loss of Power to Rps/Uninterruptible Supply Panel Due to Inverter Damage |
- on 901101,half-scram & Isolations Resulted from Loss of Power to Rps/Uninterruptible Supply Panel Due to Inverter Damage
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000353/LER-1990-019-01, :on 901101,various Actuations of Primary Containment & Reactor Vessel Isolation Control Sys,Esf & Channel B RPS half-scram Occurred.Caused by Damaged Connector in Inverter Circuitry |
- on 901101,various Actuations of Primary Containment & Reactor Vessel Isolation Control Sys,Esf & Channel B RPS half-scram Occurred.Caused by Damaged Connector in Inverter Circuitry
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-019-01, :on 900915,special Rept for Diesel Generator Surviellance Test Failure |
- on 900915,special Rept for Diesel Generator Surviellance Test Failure
| | | 05000352/LER-1990-019-02, :on 900915,diesel Generator Surveillance Test Failure Reported.Diagnostic Testing Inconclusive on Cause & No Subsequent Failure Noted.No Addl Corrective Actions Planned |
- on 900915,diesel Generator Surveillance Test Failure Reported.Diagnostic Testing Inconclusive on Cause & No Subsequent Failure Noted.No Addl Corrective Actions Planned
| | | 05000352/LER-1990-020-01, :on 900918,personnel Manually Initiated Main Control Room Ventilation Sys Chlorine Isolation Due to High Toxic Chemical Concentration Signal |
- on 900918,personnel Manually Initiated Main Control Room Ventilation Sys Chlorine Isolation Due to High Toxic Chemical Concentration Signal
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000353/LER-1990-020-02, :on 901119,primary Containment post-LOCA Radiation Monitoring Sys Declared Inoperable Due to Deficient Circuit Board in Three of Four Channels.Caused by Inadequate Design Review.Replacement Installed |
- on 901119,primary Containment post-LOCA Radiation Monitoring Sys Declared Inoperable Due to Deficient Circuit Board in Three of Four Channels.Caused by Inadequate Design Review.Replacement Installed
| 10 CFR 50.73(a)(2)(1) | | 05000353/LER-1990-021-02, :on 901206,emergency Diesel Generator D21 Output Breaker Tripped on Reverse Power & Declared Inoperable.Caused by Closure of Cross Current Control Relay Contacts.Relay Replaced |
- on 901206,emergency Diesel Generator D21 Output Breaker Tripped on Reverse Power & Declared Inoperable.Caused by Closure of Cross Current Control Relay Contacts.Relay Replaced
| | | 05000352/LER-1990-021-01, :on 900911,seismic Monitoring Sys Declared Inoperable in Preparation for Performance of Surveillance Test Procedure |
- on 900911,seismic Monitoring Sys Declared Inoperable in Preparation for Performance of Surveillance Test Procedure
| | | 05000352/LER-1990-022-01, :on 901003,emergency Diesel Generator Sys Start Failed |
- on 901003,emergency Diesel Generator Sys Start Failed
| | | 05000352/LER-1990-023-01, :on 901015,emergency DGs Discovered to Be Inoperable on Various Occasions,Resulting in Condition Prohibited by Tss.Caused by Inadequate Testing of Redundant Rectifier Banks for Emergency DGs |
- on 901015,emergency DGs Discovered to Be Inoperable on Various Occasions,Resulting in Condition Prohibited by Tss.Caused by Inadequate Testing of Redundant Rectifier Banks for Emergency DGs
| 10 CFR 50.73(a)(2)(1) | | 05000352/LER-1990-024-01, :on 901025,RCIC Sys Inoperable Due to Physical Separation Deficiency Between Class 1E & Non-Class 1E Cables Due to Personnel Error |
- on 901025,RCIC Sys Inoperable Due to Physical Separation Deficiency Between Class 1E & Non-Class 1E Cables Due to Personnel Error
| 10 CFR 50.73(a)(2)(1) | | 05000352/LER-1990-025-01, :on 901110,spurious LOCA Signal Resulted in ESF Actuations |
- on 901110,spurious LOCA Signal Resulted in ESF Actuations
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-026-01, :on 901118,full Reactor Scram Signal Generated on High Reactor Pressure Vessel Pressure of 1,033 Psig. Caused by Personnel Error.Operator Counseled & Event Will Be Included in Operator Training |
- on 901118,full Reactor Scram Signal Generated on High Reactor Pressure Vessel Pressure of 1,033 Psig. Caused by Personnel Error.Operator Counseled & Event Will Be Included in Operator Training
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-027-01, :on 901120,reactor Scram Signal Occurred When Intermediate Range Monitor F Spiked Upscale Causing RPS Channel B Half Scram.Caused by Equipment Problem Coincident W/Performance of RPS Surveillance Procedure |
- on 901120,reactor Scram Signal Occurred When Intermediate Range Monitor F Spiked Upscale Causing RPS Channel B Half Scram.Caused by Equipment Problem Coincident W/Performance of RPS Surveillance Procedure
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1990-028-01, :on 901126,instrumentation & Controls Personnel Discovered That Facility Tech Specs Required Surveillance Requirements Not Met for Two Intermediate Range Monitors.W/ |
- on 901126,instrumentation & Controls Personnel Discovered That Facility Tech Specs Required Surveillance Requirements Not Met for Two Intermediate Range Monitors.W/
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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