:on 980124,Unit 1 HPCI Sys Initiation Occurred. Caused by Less than Adequate Understanding for Potential Loss of Grounding Signal Upon Troubleshooting Control Form. Event Will Be Reviewed by All Work Group Personnel| ML20203E290 |
| Person / Time |
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| Site: |
Limerick  |
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| Issue date: |
02/23/1998 |
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| From: |
Moore T PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
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| To: |
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| Shared Package |
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| ML20203E277 |
List: |
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| References |
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| LER-98-001, LER-98-1, NUDOCS 9802270013 |
| Download: ML20203E290 (4) |
|
text
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e spron matety a singie.gateJ typewritten line5J Lib) on 01/24/98, at 0019 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> a Unit 1 High Pressure Coolant Injection (HPCI) system initiation occurred coincident with the removal of a troubleshooting control form (TCF). The TCP was initiated on 01/21/98, to install a recorder to monitor performar.cc of the IB Residual Heat Removal Pump Minimum Flow Valve control circuit. Following TCP installation, a failed trip unit was identified and was replaced.
With the cause of the spurious valve operation determined, the TCP was no longer required and TCP removal commenced.
While removing a banana jack from one of the control relays, thereby interrupting a series (daisy chained) ground circuit, arching was observed and relay chatter was heard by the technician.
Coincident with this action, the HPC1 system initiated and operated in the minimum flow mode; however, no HPCI injection or power excursions occurred. The HPCI system was secured and lined up for automatic operation. The HPCI initiation resulted from a temporary i
interruption in the ground circuit that caused a current flow through a HPCI initi.4 tion relay.
The cause of this event was less than adequate undert,tanding for the potential loss of grounding signal upon TCP removal.
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liaCh9U:Lundi On January 21, 1998, at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />, the Work Week Manager (WWM) contacted the shift I&C technicians stating that the Residual 11 eat Removal ( Rif R, EIIS:BO) System Manager wanted to monitor minimum flow valve, 11V - 0 51 - 1 F 0 07 B, for troubleshooting purposes.
The valve had exhibited previous occurrences related to spurious closure prior to this event.
Through communications between the I&C shift technicians, the Engineering Duty Manager (EDM) and the WWM, it was determined that a Troubleshooting Control Form (TCF) would be utilized to hook up a recorder to monitor valve trip unit input and output, and valve relay status.
Followirg operations approval the TCP was installed on January 22,
- 998, at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />.
During the installation of the TCF, I&C technicians noticed that the trip unit output was reading 7.5 volts.
This expected value was zero (0) volts. A work order was generated on January 23, 1998 to replace the trip unit.
Following the trip unit replacement, a satisfactory post maintenance test was performed verifying proper operation of the minimum fluw valve, and removal of the TCF test points began.
Ileseription of the Event :
At 0019 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> on January 24, 1998, the High Pressure Coolant Injection (llPCI, EIIS:BJ) system opuriously started and began operating in the minimum flow mode of operation.
The Plant Reactor Operator (PRO) verified Unit 1 11PCI did not inject into the reactor vessel.
The Unit 1 Reactor Operator (RO) verified no power excursions had occurred.
The Floor Supervisor was sent to the auxiliary equipment room to investigate.
The Floor Supervisor confirmed that no trip units actuated.
Unit 1 IIPCI was secured and lined up for automatic operation in accordance with the applicable operating procedure.
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An investigation identified that the llPCI initiation occurred upon removal of a banana jack located on the ground circuit of RHR relay EllA K5B.
Removal of the banana jack was being performed by an I&C technician during the restoration of the TCP for monitoring of the RHR minimum flow valve. While properly removing the banana jack in accordance with the TCP restoration, the I&C technician observed arching and heard relay chatter.
The llPCI initiation was caused when a temporary interruption in the series (daisy chained) ground circuitry occurred between two relays fed from a single trip unit during removal of the banana jack.
The ground interruption caused a current path through a llPCI initiation relay.
At. 0348 hours0.00403 days <br />0.0967 hours <br />5.753968e-4 weeks <br />1.32414e-4 months <br /> on January 24, 1998, a 4-hour notification was made to the NRC in accordance with the requirements of 10CFR50.72 (b) (2) (ii),
since this event resulted in an unplanned automatic ESF actuation.
This report is submitt ed in accordance with 10CFR50.73 (a) (2) (iv).
Analysin of tht_liYf.DL The consequences of this event were minimal.
The llPCI system operated in the minimum flow mode, taking a suction from the condensate storage tank (CST), and returning flow back to the CST again.
There were no events which occurred during the time the HPCI system had been c perating in minimum flow which would have required injection of the llPCI system.
Additionally, operatier of HPCI in the minimum flow mode would not have prevented automatic lineup of the system if injection was required.
The steam use for llPCI did not impact reactor power and there were no adverse radiological consequences due to the use of reactor steam for operation of HPCI.
A Health Physica review of the event determined that no unexpected exposures incurred due to the HPCI initiation.
Cause of the Event
Less than adequate understanding of the potential for a loss of ground that could result in the energizing of a llPCI initiation relay.
During the removal of the TCF, the daisy chained circuit ground was interrupted, and this resulted in an energized relay back feeding a llPCI initiation relay that resulted in the HPCI initiation.
The removal of the banana jack was a required step in the TCP restoration process; however the I&C technician did not understand the impact the banana jack removal would have on the system during the TCF planning
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The less than adequate understanding of the daisy chained ground circuit by the I&C technician lead to insufficient research of the troubleshooting activity.
Cross-disciplinary interaction was less than adequate.
The I&C technician and the system manager did not directly discuss the troub.1.eshooting activity prior to installation.
Such a discussion may have lead to choosing alternate monitoring locations.
Corrective Actions
This event will be reviewed by all work group personnel that are expected to perform similar troubleshooting to address: t rouble shoot.ing techniques including initial point checks vs. intrusive monitoring, researching all relevant documentation prior to TCP generation, and ensuring adequate pre-job cross-disciplinary interaction.
This review was completed for station I&C technicians as of February le, 1998.
Evaluations for the remaining relevant organizations addressing the above concerns will be completed by February 27, 1998, Contractors will likewise be briefed on this event by April 01, 1998, prior to performing work in the upcoming refuel outage.
Troubleshooting techniques related to daisy chained circuits will become part of the formal Routine Continuing Training (RCT) program to ensure continued emphasis in this area.
The next cycle of RCT training will be implemented by October 01, 1998.
En yipus similar Occurrences No previous occurrences were identified enat related to HPCI system initiations as a result of test equipment removal.
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| 05000352/LER-1998-001, :on 980124,Unit 1 HPCI Sys Initiation Occurred. Caused by Less than Adequate Understanding for Potential Loss of Grounding Signal Upon Troubleshooting Control Form. Event Will Be Reviewed by All Work Group Personnel |
- on 980124,Unit 1 HPCI Sys Initiation Occurred. Caused by Less than Adequate Understanding for Potential Loss of Grounding Signal Upon Troubleshooting Control Form. Event Will Be Reviewed by All Work Group Personnel
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000353/LER-1998-001-03, :on 980602,three Barksdale Model C9622-3-B Pressure Switches Located on Relayed Emergency Trip Sys Found Inoperable from Common Cause.Caused by Inadequate Allowances for Switch Performance.Trip Setpoint Revised |
- on 980602,three Barksdale Model C9622-3-B Pressure Switches Located on Relayed Emergency Trip Sys Found Inoperable from Common Cause.Caused by Inadequate Allowances for Switch Performance.Trip Setpoint Revised
| | | 05000353/LER-1998-001, Forwards LER 98-001-00 Re Discovery of Three Barksdale Model C9622-3-B Differential Pressure Switches Located on Main Turbine Relayed Emergency Trip Sys | Forwards LER 98-001-00 Re Discovery of Three Barksdale Model C9622-3-B Differential Pressure Switches Located on Main Turbine Relayed Emergency Trip Sys | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000352/LER-1998-002, :on 980206,primary Containment & Rv Isolation Control Sys Actuation Occurred.Caused by Personnel Error. Fuse Was Replaced & All Isolations Were Reset within 55 Minutes |
- on 980206,primary Containment & Rv Isolation Control Sys Actuation Occurred.Caused by Personnel Error. Fuse Was Replaced & All Isolations Were Reset within 55 Minutes
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000353/LER-1998-002-01, :on 980603,automatic Isolation of Reactor Water Cleanup Suction Valve,Occurred.Caused by Electromagnetic Interference.Ferrite Torroids Were Added to Wires Entering & Leaving RRCS Hpoi Cards to Filter Out High Frequency Spike |
- on 980603,automatic Isolation of Reactor Water Cleanup Suction Valve,Occurred.Caused by Electromagnetic Interference.Ferrite Torroids Were Added to Wires Entering & Leaving RRCS Hpoi Cards to Filter Out High Frequency Spikes
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000353/LER-1998-002, Forwards LER 98-002-00,reporting Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Occurring When Electromagnetic Interference Due to Component Testing Inducing Signal in Redundant Reactivity Control Sys C | Forwards LER 98-002-00,reporting Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Occurring When Electromagnetic Interference Due to Component Testing Inducing Signal in Redundant Reactivity Control Sys Cable | | | 05000353/LER-1998-003, Forwards LER 98-003-00 Re 980622 Inoperability of Main Condenser Offgas pre-treatment Radioactivity Monitor Skid Which Resulted from Incorrect Procedure | Forwards LER 98-003-00 Re 980622 Inoperability of Main Condenser Offgas pre-treatment Radioactivity Monitor Skid Which Resulted from Incorrect Procedure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000353/LER-1998-003-02, :on 980622,determined That Main Condenser Offgas pre-treatment Rad Monitor Was Inoperable.Caused by Incorrect Procedure.Sys Procedure Has Been Revised to Remove Incorrect Procedure |
- on 980622,determined That Main Condenser Offgas pre-treatment Rad Monitor Was Inoperable.Caused by Incorrect Procedure.Sys Procedure Has Been Revised to Remove Incorrect Procedure
| 10 CFR 50.73(a)(2)(1) | | 05000352/LER-1998-003, :on 980213,ESF Actuation Due to Incidental Contact W/Rv Instrument Rack Occurred.Caused by Personnel Error.Counseled Individual Involved & Training for Site Personnel |
- on 980213,ESF Actuation Due to Incidental Contact W/Rv Instrument Rack Occurred.Caused by Personnel Error.Counseled Individual Involved & Training for Site Personnel
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000353/LER-1998-004, Forwards LER 98-004-00,reporting Manual Actions Taken in Response to Plant Conditions,To Perform Secondary Containment Isolation,Sgts Initiation & RERS Initiation | Forwards LER 98-004-00,reporting Manual Actions Taken in Response to Plant Conditions,To Perform Secondary Containment Isolation,Sgts Initiation & RERS Initiation | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000353/LER-1998-004-02, :on 980626,secondary Containment Isolation, SGTS & RERS Initiation Manual Action,Occurred.Caused by Failure of Normal Reactor Enclosure HVAC to Maintain Negative Pressure.Repaired B Train SGTS Control Components |
- on 980626,secondary Containment Isolation, SGTS & RERS Initiation Manual Action,Occurred.Caused by Failure of Normal Reactor Enclosure HVAC to Maintain Negative Pressure.Repaired B Train SGTS Control Components
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1998-004, :on 980320,missing Fire Dampers in Safe Shutdown Barriers Were Noted.Caused by Inadequate Design Review of Initial Fire barrier.Fire-watches Previously Established for Thermo-lag Issues Were Verified |
- on 980320,missing Fire Dampers in Safe Shutdown Barriers Were Noted.Caused by Inadequate Design Review of Initial Fire barrier.Fire-watches Previously Established for Thermo-lag Issues Were Verified
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000353/LER-1998-005-01, :on 980629,discovered That Procedure ST-6-107-887-2 Which Has Weekly Frequency Had Exceeded TS Surveillance Period W/Applicable TS Action Not Being Met. Caused by Personnel Error.Developed Routine OOS Rept |
- on 980629,discovered That Procedure ST-6-107-887-2 Which Has Weekly Frequency Had Exceeded TS Surveillance Period W/Applicable TS Action Not Being Met. Caused by Personnel Error.Developed Routine OOS Rept
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000353/LER-1998-005, Forwards LER 98-005-00,reporting Condition Prohibited by TS in That Surveillance Test Exceeded TS Surveillance Requirement Time Period & Applicable TS Action Had Not Been Met | Forwards LER 98-005-00,reporting Condition Prohibited by TS in That Surveillance Test Exceeded TS Surveillance Requirement Time Period & Applicable TS Action Had Not Been Met | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000352/LER-1998-005, :on 980322,load Ctr Feedwater Breaker 124B-62 tripped,de-energizing Components Supported by Load Ctr 124B. Caused by Combination of pre-existing Steam Leak in 1A RWCU Pump Room Circuit Breaker Replaced |
- on 980322,load Ctr Feedwater Breaker 124B-62 tripped,de-energizing Components Supported by Load Ctr 124B. Caused by Combination of pre-existing Steam Leak in 1A RWCU Pump Room Circuit Breaker Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1998-006, :on 980405,post Maint Surveillance Test Was Not Performed for A2 RPS Channel Relay Replacement.Caused by Incomplete Document Review.Relay Work Was Reviewed to Evaluate & Resolve Impact of Relay Work on Any Required Sys |
- on 980405,post Maint Surveillance Test Was Not Performed for A2 RPS Channel Relay Replacement.Caused by Incomplete Document Review.Relay Work Was Reviewed to Evaluate & Resolve Impact of Relay Work on Any Required Sys
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) | | 05000353/LER-1998-006-01, :on 980726,noted Failure to Perform 4KV Emergency D24 Bus Undervoltage Channel Calibr Surveillance Test Prior to TS Due Date.Caused by Personnel Error. Counseled Personnel & Conducted Training Re Event |
- on 980726,noted Failure to Perform 4KV Emergency D24 Bus Undervoltage Channel Calibr Surveillance Test Prior to TS Due Date.Caused by Personnel Error. Counseled Personnel & Conducted Training Re Event
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) | | 05000353/LER-1998-006, Forwards LER 98-006-00 Re Failure to Perform 4KV Emergency D24 Bus Undervoltage Channel Calibr Surveillance Test Prior to TS Due Date.Cause of 980726 Event Is Attributed to Personnel Error | Forwards LER 98-006-00 Re Failure to Perform 4KV Emergency D24 Bus Undervoltage Channel Calibr Surveillance Test Prior to TS Due Date.Cause of 980726 Event Is Attributed to Personnel Error | | | 05000352/LER-1998-007, :on 980422,discovered Three Itt Barton Model 580A Differential Pressure Switches Inoperable.Caused by Misapplication.Replaced Subject Itt Barton Differential Pressure Switches in safety-related Applications |
- on 980422,discovered Three Itt Barton Model 580A Differential Pressure Switches Inoperable.Caused by Misapplication.Replaced Subject Itt Barton Differential Pressure Switches in safety-related Applications
| | | 05000353/LER-1998-007-01, :on 971210,personnel Determined That Surveillance Requirements Were Not Met for RHR Heat Exchanger Discharge Line High Radiation Indication. Caused by Personnel Error.Test for Common Monitor Revised |
- on 971210,personnel Determined That Surveillance Requirements Were Not Met for RHR Heat Exchanger Discharge Line High Radiation Indication. Caused by Personnel Error.Test for Common Monitor Revised
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000353/LER-1998-007, Forwards LER 98-007-00,reporting Condition Prohibited by TS, in That Remote Shutdown Panel Instrument Calibr Was Not within Required Frequency & Required Actions Were Not Taken. Event Occurred Due to Administrative Error | Forwards LER 98-007-00,reporting Condition Prohibited by TS, in That Remote Shutdown Panel Instrument Calibr Was Not within Required Frequency & Required Actions Were Not Taken. Event Occurred Due to Administrative Error | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000353/LER-1998-008-02, :on 981209,plant Personnel Identified That Unit 2 RCIC Turbine Steam Supply Line warm-up Bypass Valve Had Been in Partially Open Condition.Caused by Intermittment Control Circuit Anomaly.Control Circuit Replaced |
- on 981209,plant Personnel Identified That Unit 2 RCIC Turbine Steam Supply Line warm-up Bypass Valve Had Been in Partially Open Condition.Caused by Intermittment Control Circuit Anomaly.Control Circuit Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000353/LER-1998-008, Forwards LER 98-008-00,reporting Condition Prohibited by Tech Specs & Condition That Alone Could Have Prevented Fulfillment of Safety Function of Sys Designed to Mitigate Release of Radioactive Matl | Forwards LER 98-008-00,reporting Condition Prohibited by Tech Specs & Condition That Alone Could Have Prevented Fulfillment of Safety Function of Sys Designed to Mitigate Release of Radioactive Matl | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000352/LER-1998-008-01, Forwards LER 98-008-01 Re Pressure Setpoint Drift of Thirteen Main Steam Sys SRVs Primarily Caused by Corrosion Induced Bonding within SRVs | Forwards LER 98-008-01 Re Pressure Setpoint Drift of Thirteen Main Steam Sys SRVs Primarily Caused by Corrosion Induced Bonding within SRVs | | | 05000352/LER-1998-008, :on 980429,discovered Pressure Setpoint Drift of Five Main Steam Sys Srvs.Caused by Corrosion Induced Bonding.Replaced Fourteen SRV Pilot Valves W/Calibr Spares During 1R07 & Util Is Evaluating three-stage SRV Design |
- on 980429,discovered Pressure Setpoint Drift of Five Main Steam Sys Srvs.Caused by Corrosion Induced Bonding.Replaced Fourteen SRV Pilot Valves W/Calibr Spares During 1R07 & Util Is Evaluating three-stage SRV Design
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000352/LER-1998-009, :on 841026,noted That Primary Containment Overcurrent Protection Circuits May Not Have Provided Redundant Protection.Caused by Original Licensing Basis Interpretation.Corrected Affected Subject Circuits |
- on 841026,noted That Primary Containment Overcurrent Protection Circuits May Not Have Provided Redundant Protection.Caused by Original Licensing Basis Interpretation.Corrected Affected Subject Circuits
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) | | 05000352/LER-1998-010, :on 980526,identified Two Surveillance Tests Associated W/Rc Recirculation Sys Flow Units A/C & B/D Calibr,Respectively.Caused Attributed to Personnel Error. Units Satisfactorily Tested |
- on 980526,identified Two Surveillance Tests Associated W/Rc Recirculation Sys Flow Units A/C & B/D Calibr,Respectively.Caused Attributed to Personnel Error. Units Satisfactorily Tested
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) | | 05000352/LER-1998-011, :on 970901,1B RHR Pump Was Inoperable Due to Intermittent Min Flow Valve Closures.Caused by Failed Rosemount 510DU Trip Unit.Failed Trip Unit Was Replaced |
- on 970901,1B RHR Pump Was Inoperable Due to Intermittent Min Flow Valve Closures.Caused by Failed Rosemount 510DU Trip Unit.Failed Trip Unit Was Replaced
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000352/LER-1998-012, :on 980530,HPCIS Declared Inoperable.Caused by Locking Tab Piece from Older Style & Piece Broke Off of Currently Installed Locking Tab.Conducted Internal Insp of HPCI Turbine on Each Unit |
- on 980530,HPCIS Declared Inoperable.Caused by Locking Tab Piece from Older Style & Piece Broke Off of Currently Installed Locking Tab.Conducted Internal Insp of HPCI Turbine on Each Unit
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000352/LER-1998-013, :on 841026,failed to Meet Max Travel Distance Limitation & Guidance for Class a Extinguisher Replacement W/Hose Stations.Caused by Failure to Provide Deviation Documentation.Place Extinguishers in Fire Brigade Locker |
- on 841026,failed to Meet Max Travel Distance Limitation & Guidance for Class a Extinguisher Replacement W/Hose Stations.Caused by Failure to Provide Deviation Documentation.Place Extinguishers in Fire Brigade Locker
| | | 05000352/LER-1998-014, :on 980128,several Rwcs Isolations Were on High Differential Flow Signals.Caused by Sys Perturbations. Shift Update Notice Was Issued to All Operations Personnel |
- on 980128,several Rwcs Isolations Were on High Differential Flow Signals.Caused by Sys Perturbations. Shift Update Notice Was Issued to All Operations Personnel
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000352/LER-1998-015-01, Forwards LER 98-015-01,re Condition Prohibited by TS Due to Calibration Error.Rev Makes Editorial Corrections to Description of Event | Forwards LER 98-015-01,re Condition Prohibited by TS Due to Calibration Error.Rev Makes Editorial Corrections to Description of Event | | | 05000352/LER-1998-015, :on 950216,discovered That Error in Calibr of CS Internal Line Break Detection Instrumentation Resulted in Setpoints Being Outside Required TS Limit.Recalibr Affected Instrumentation to Account for Change in Baseline Dp |
- on 950216,discovered That Error in Calibr of CS Internal Line Break Detection Instrumentation Resulted in Setpoints Being Outside Required TS Limit.Recalibr Affected Instrumentation to Account for Change in Baseline Dp
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000352/LER-1998-016, :on 980728,manual Main CR Ventilation Isolation & CR Emergency Fresh Air Sys Was Initiated Due to Small Freon Leak.Caused by Lack of Preventive Maint.Freon Leak Was Repaired & Chiller Was Tested Satisfactorily |
- on 980728,manual Main CR Ventilation Isolation & CR Emergency Fresh Air Sys Was Initiated Due to Small Freon Leak.Caused by Lack of Preventive Maint.Freon Leak Was Repaired & Chiller Was Tested Satisfactorily
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000352/LER-1998-017, :on 841026,failure of Fire Protection Hatchway Flow Control Valves to Actuate Was Noted.Caused by Lack of Understanding of Hardware.Modified Hatchway Flow Control Valves & Revised Associated Surveillance Tests |
- on 841026,failure of Fire Protection Hatchway Flow Control Valves to Actuate Was Noted.Caused by Lack of Understanding of Hardware.Modified Hatchway Flow Control Valves & Revised Associated Surveillance Tests
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000352/LER-1998-018, :on 980911,potential Loss of EDG Control in Event of Fire,Was Determined.Caused by fire-induced Damage to Unprotected Voltage & Speed Control Cables.Ncr 98-02422 Was Generated to Disposition Identified Deficiencies |
- on 980911,potential Loss of EDG Control in Event of Fire,Was Determined.Caused by fire-induced Damage to Unprotected Voltage & Speed Control Cables.Ncr 98-02422 Was Generated to Disposition Identified Deficiencies
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000352/LER-1998-019, :on 981202,noted Unescorted Access to Contract Employee Who Had Tampered with Drug Test Specimen.Caused by Incorrect Computer Data Entry for pre-access Drug Screening. Will Develop Formal Training Program for Data Entry Clerk |
- on 981202,noted Unescorted Access to Contract Employee Who Had Tampered with Drug Test Specimen.Caused by Incorrect Computer Data Entry for pre-access Drug Screening. Will Develop Formal Training Program for Data Entry Clerk
| 10 CFR 50.73(a)(2)(viii)(A) |
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