:on 901120,Train B of Control Room HVAC Sys Actuated Unexpectedly in Emergency Recirculation Mode.Caused by Inadequate Instruction.Procedure Revised Re Correct Guidance During Loss of Power to Bus K-1-N| ML20024F742 |
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| Site: |
Perry  |
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| Issue date: |
12/14/1990 |
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| From: |
Hegrat H CENTERIOR ENERGY |
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| To: |
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| Shared Package |
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| ML20024F740 |
List: |
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| References |
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| LER-90-033, LER-90-33, NUDOCS 9012170125 |
| Download: ML20024F742 (3) |
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, aa an.a-. - - aa. o o On November 20, 1990 at 0248, the B train of the Control Room Heatingt i
Ventilation and Air Conditioning (CRHVAC) System actuated unexpectedly in the Emergency Recirculation mode of operation when temporary power to a power distribution panel, K-1-N, was removed to allow restoration of the normal power supply.
All equipment responded as designed, and the system was returned to normal operation.
The root cause of this event was an inadequate instruction.
The Unit Supervisor, reviewing the tagout for system restoratien, ref erred to Of f-Normal Instruction j
(ON1-R25-2) " Leap of a Non-essential 120V Bus (Unit 1)" to determine expected plant response to the evolution; however, the instruction was inadequate as it did not provide the correct guidance concerning the effects on the CRHVAC system when K-1-N was doenergized.
To prevent recurrence, ONI-R25-2 has been revised to reflect the correct guidance during loss of power to the K-l-N bus.
Additionally, Operations is developing more detailed system operating instructions to provide better guidance for the operations of low voltage electrical systems.
Finally, as part of the established roqualification training program, this event will be discussed with all plant licensed operators.
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., - wc w m a n On November 20, 1990 at 0248, the B train of the Control Room Heating, Ventilation and Air Conditioning (CRHVAC) [V1] System actuated unexpectedly in the Emergency Recirculation mode of operation when temporary power to a power distribution panel, K-1-N, was removed to allow restoration of the normal power supply. At the time of the event, the plaM was in Operational Condition 5 (Refuel), with the Reactor Pressure Vesse' [RPV) at atmospheric conditions and reactor water temperature at approxi% rely 78 degrees.
On November 20, 1990, the Unit Supervisor authorized clearance of a tagout which would remove temporary power that was supplying power to distribution panel K-1-N.
Prior to this, the Unit Supervisor reviewed Of f Normal Instruction (ON1-R25-2) " Loss of a Non-essential 120V Bus (Unit 1)" to determine the effects of a loss of power to K-1-N on plant systems and determine if any mitigating actions should be taken. At this time, both of the CRHVAC trains were considered inoperable due to duct work modifications; however, the A train was operating in the Emergency Recirculation mode and the B train was in the standby readiness mode. At 0248, plant operators removed temporary power from panel K-1-N to enable restoration of its normal power supply. When power to the distribution panel was removed, the Common Airborne Radiation Monitor Panel (IL] and an associated instrument, Control Room Airborne Gas Radiation Monitor (R1], were deenergized. Upon the loss of power to thir. instrument, the CRHVAC B train received an automatic initiation signal and started in the Emergency Recirculation mode.
The A train continued to operate in the Emergency Recirculation mode throughout the event. At 0258, normal power was restored to K-1-N.
At 1216 the A train was returned to normal operation and the B train was placed in the standby readiness mode.
The root cause of this event was an inadequate instruction. The Unit Supervisor reviewed the tagout with the appropriate Off-Normal Instruction for a lose of power to K-1-N.
The instruction was inadequate in that it did not provide the correct guidance concerning the effects on the CRHVAC system when K-1-N was deenergized. This instruction had previously included information regarding initiation of Emergency Recirculation when power is lost to K-1-N.
However, a previous revision to the instruction in November of 1988 removed the subject information. The tevision was made in response to a design change which removed the automatic initiation of the Emergency Recirculation mode due to a loss of l
power to Ethylene Oxide Monitors (45).
The review of this change only focused on
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the effect of Ethylene Oxide monitors. Therefore, it was not recognized that a loss of power to K-1-N would still cause an automatic initiation of the Emergency Mode of the CRHVAC system due to a loss of power to the Control Room Airborne Cas Radiation Monitor.
The CRHVAC system provides cooling, heating, ventilation, and when required, smoke removal for the control room and equipment areas during normal plant operation, and during periods of emergency (LOCA or high radiation conditions or high chlorine gas level). The Emergency Recirculction mode provides the necessary supplementary particulate and halogen flitration of the air supplied to oc.. m. u,
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1 the control room areas during emergency conditions and other abnormal conditions to reduce the radiation dose for personnel protection. The Emergency Recirculation mode will automatically initiate upon receipt of a high chlorine l
gas, high radiation, Loss Of Offsite Power (LOOP) or Loss Of Coolant Accident (LOCA). signal.
In this event, the B train properly responded as designed to the automatic initiation signal, while the-A train continued to operate in Emergency Recirculation. This even' is not considered to be safety significant. A review of previous events identified two CRHVAC Emergency Recirculation actuations since 1986 that were a result of inadequate surveillance and operating instructions (refer to LERs 86073 and 89008).
In both cases, precautions were added to these instructions; however, none of the procedural changes implemented as corrective actions would have prevented the November 20 event.
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_As a result of previous events, and the recognized need to provide complete guidance for loss of various plant power supplies,.the 1 ent Operations Section has maintained a continuing effort to ensure that Electrical Operating Instructions are complete and accurate.
For example, detailed load lists have been developed for 125 VDC distribution systems and included in the Plant Data Book. The inaccuracy in ON1-R25-2 was the direct renuit of an error in the procedure revision process and in considered to be an isolated event.
To prevent recurrence, ON1-R25-2 has been revised to reflect the correct guidance during loss of power to the K-1-N bus. Additionally, Operations is developing more detailed system operating instructions to provide better guidance for the operation of low voltage electrical system.
Finally, as part of the established requalification training program this event will-be discussed with all plant licensed operators.
Energy Industry Identification Codes are identified in the test as [XX).
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NRC I.em.A 66491
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| 05000440/LER-1990-001, :on 900107,reactor Scram Occurred After Improper Transfer of 480-volt Ac Power Supplies Resulted in Total Loss of Feedwater Flow & Power Interruption.Caused by Personnel Error.Operator Counseled & Instructions Revised |
- on 900107,reactor Scram Occurred After Improper Transfer of 480-volt Ac Power Supplies Resulted in Total Loss of Feedwater Flow & Power Interruption.Caused by Personnel Error.Operator Counseled & Instructions Revised
| | | 05000440/LER-1990-002, :on 900107,RCIC Sys Isolated Due to High Differential Temp Signal Detected Across RCIC Room Cooler Following Reactor Scram Due to Loss of Feedwater Flow. Caused by Design Deficiency.Procedures Re Flow Rate Revised |
- on 900107,RCIC Sys Isolated Due to High Differential Temp Signal Detected Across RCIC Room Cooler Following Reactor Scram Due to Loss of Feedwater Flow. Caused by Design Deficiency.Procedures Re Flow Rate Revised
| | | 05000440/LER-1990-003, :on 900222 & 23,discovered That Stroke Time Measurements Not Performed in Both Directions for motor- Operated Valves in safety-related Sys.Caused by Program Deficiency.Procedural Enhancement Implemented |
- on 900222 & 23,discovered That Stroke Time Measurements Not Performed in Both Directions for motor- Operated Valves in safety-related Sys.Caused by Program Deficiency.Procedural Enhancement Implemented
| | | 05000440/LER-1990-004, :on 900329,determined That 12 Snubbers Not Inspected on 900302 & Two Snubbers Not Inspected on 900327, Per Tech Spec 4.7.4.Caused by Program Inadequacy.Procedures Changed & Snubber Program Evaluated |
- on 900329,determined That 12 Snubbers Not Inspected on 900302 & Two Snubbers Not Inspected on 900327, Per Tech Spec 4.7.4.Caused by Program Inadequacy.Procedures Changed & Snubber Program Evaluated
| | | 05000440/LER-1990-005, :on 900405,HPCS Declared Inoperable Due to Fuel Oil Sediment Exceeding Tech Spec Limits.Caused by Fuel Oil & Storage Tank Degradation,Due to Contaminant in Biocide Additive.Contaminated Biocide Additive Removed |
- on 900405,HPCS Declared Inoperable Due to Fuel Oil Sediment Exceeding Tech Spec Limits.Caused by Fuel Oil & Storage Tank Degradation,Due to Contaminant in Biocide Additive.Contaminated Biocide Additive Removed
| | | 05000440/LER-1990-006, :on 900411,control Room Emergency Recirculation Sys Found to Be Inoperable & Tech Specs 3.0.3 Entered on Three Occasions.Caused by Operator Error & Component Failure,Respectively.Personnel Retrained |
- on 900411,control Room Emergency Recirculation Sys Found to Be Inoperable & Tech Specs 3.0.3 Entered on Three Occasions.Caused by Operator Error & Component Failure,Respectively.Personnel Retrained
| | | 05000440/LER-1990-007, :on 900418,ruptured Seal on Outer Door of Upper Containment Airlock Occurred Causing Loss of Containment Integrity.Caused by Inadequate Communications & Equipment Failure.Seal on Outer Door Replaced |
- on 900418,ruptured Seal on Outer Door of Upper Containment Airlock Occurred Causing Loss of Containment Integrity.Caused by Inadequate Communications & Equipment Failure.Seal on Outer Door Replaced
| | | 05000440/LER-1990-008, :on 900420,unexpected Isolation of RWCU Sys Occurred.Caused by Component Failure.Faulty Transmitter Transmitter Identified & Replaced |
- on 900420,unexpected Isolation of RWCU Sys Occurred.Caused by Component Failure.Faulty Transmitter Transmitter Identified & Replaced
| | | 05000440/LER-1990-009, :on 900517,RHR Sys B HX Bypass Valve Failed to Reposition on Demand,Rendering RHR Sys Train Operable for Containment Spray Cooling Mode of Operation.Caused by Failure of Valve Stem Nut.Stem Nut Replaced |
- on 900517,RHR Sys B HX Bypass Valve Failed to Reposition on Demand,Rendering RHR Sys Train Operable for Containment Spray Cooling Mode of Operation.Caused by Failure of Valve Stem Nut.Stem Nut Replaced
| | | 05000440/LER-1990-010, :on 900521,Tech Spec Action Requirements Not Implemented for Inoperable Control Rod Scram Accumulators. Caused by Inadequate Procedures & Malfunctioning Transformer.Analyzer Reset & Leakage Monitored |
- on 900521,Tech Spec Action Requirements Not Implemented for Inoperable Control Rod Scram Accumulators. Caused by Inadequate Procedures & Malfunctioning Transformer.Analyzer Reset & Leakage Monitored
| | | 05000440/LER-1990-011, :on 900521,discovered That Divisional LPCI & LPCS Sys Inoperable in Excess of Tech Spec Action Limits Between 871119-23 & 891218-22.Caused by Procedural Deficiency.Sys Operating Instruction Revised |
- on 900521,discovered That Divisional LPCI & LPCS Sys Inoperable in Excess of Tech Spec Action Limits Between 871119-23 & 891218-22.Caused by Procedural Deficiency.Sys Operating Instruction Revised
| | | 05000440/LER-1990-013, :on 900619,discovered That Main Steam Line Radiation Monitor C Inoperable for Greater than Time Allowed by Tech Specs 3.3.1.a & 3.3.1.b.Caused by Personnel Error. Personnel Counseled |
- on 900619,discovered That Main Steam Line Radiation Monitor C Inoperable for Greater than Time Allowed by Tech Specs 3.3.1.a & 3.3.1.b.Caused by Personnel Error. Personnel Counseled
| | | 05000440/LER-1990-014, :on 900621,trains of Control Room HVAC Sys Actuated Unexpectedly in Emergency Recirculation Mode of Operation.Caused by Multiple Personnel Errors.Personnel Reinstructed Re Using Appropriate Drawings for Application |
- on 900621,trains of Control Room HVAC Sys Actuated Unexpectedly in Emergency Recirculation Mode of Operation.Caused by Multiple Personnel Errors.Personnel Reinstructed Re Using Appropriate Drawings for Application
| | | 05000440/LER-1990-016, :on 900710,condensate Storage Tank Level Low Actuation Instrumentation Failure Resulted in HPCS Shift. Caused by Component Failure.Rosemount Master Trip Unit Replaced |
- on 900710,condensate Storage Tank Level Low Actuation Instrumentation Failure Resulted in HPCS Shift. Caused by Component Failure.Rosemount Master Trip Unit Replaced
| | | 05000440/LER-1990-017, :on 900814,thermal Power Exceeded Authorized Limits Due to Feedwater Heater Level Control Failure.Caused by Component Failure W/Contributing Procedural Deficiency. Off Normal Instruction Enhanced |
- on 900814,thermal Power Exceeded Authorized Limits Due to Feedwater Heater Level Control Failure.Caused by Component Failure W/Contributing Procedural Deficiency. Off Normal Instruction Enhanced
| | | 05000440/LER-1990-018, :on 900817,determined That Containment Average Temp/Relative Humidity Not Verified within Tech Spec Figure 3.6.5.2-1 Limits.Caused by Programmatic Weakness in Use of Process Computer Sys Info to Determine Tech Spec Compliance |
- on 900817,determined That Containment Average Temp/Relative Humidity Not Verified within Tech Spec Figure 3.6.5.2-1 Limits.Caused by Programmatic Weakness in Use of Process Computer Sys Info to Determine Tech Spec Compliance
| | | 05000440/LER-1990-019, On 900817 & 0901,liquid Radiological Effluent Releases Performed W/Radioactive Effluent Monitoring Instrumentation Inoperable W/O Completing Independent,Per Tech Spec 3.3.7.9.On 900820,channel Improperly Calibr | On 900817 & 0901,liquid Radiological Effluent Releases Performed W/Radioactive Effluent Monitoring Instrumentation Inoperable W/O Completing Independent,Per Tech Spec 3.3.7.9.On 900820,channel Improperly Calibr | | | 05000440/LER-1990-020, :on 900831,maint Activities on Control Room Emergency Recirculation Sys Resulted in Tech Spec Violation & Compromise of Safety Sys.Caused by Program Deficiency. Maint Acitivities & Insp Being Revised |
- on 900831,maint Activities on Control Room Emergency Recirculation Sys Resulted in Tech Spec Violation & Compromise of Safety Sys.Caused by Program Deficiency. Maint Acitivities & Insp Being Revised
| | | 05000440/LER-1990-021, :on 900907,MSIV Failed to Close Following Successful Slow Closures |
- on 900907,MSIV Failed to Close Following Successful Slow Closures
| | | 05000440/LER-1990-023, :on 900907,reactor Protection Sys Bus Deenergization & Shutdown Cooling Isolation Occurred During Surveillance Testing Due to Personnel Error.Personnel Instructed on Ramifications of Inattention During Tests |
- on 900907,reactor Protection Sys Bus Deenergization & Shutdown Cooling Isolation Occurred During Surveillance Testing Due to Personnel Error.Personnel Instructed on Ramifications of Inattention During Tests
| | | 05000440/LER-1990-024, :on 900909,determined That Failure to Properly Control Surveillance Testing Resulted in Suppression Pool Instrumentation Being Out of Svc.Caused by Procedural Deficiency.Licensed Operators Trained to Lessons Learned |
- on 900909,determined That Failure to Properly Control Surveillance Testing Resulted in Suppression Pool Instrumentation Being Out of Svc.Caused by Procedural Deficiency.Licensed Operators Trained to Lessons Learned
| | | 05000440/LER-1990-025-01, Responds to NRC Ltr Re Violations Noted in Insp Rept 50-440/90-20 on 900920-1116.Corective Actions:Valve Repair & Rebuilding,Per LER 90-025-01,dtd 901123 & Restoration of Six MSIV That Required Disassembly to Original Condit | Responds to NRC Ltr Re Violations Noted in Insp Rept 50-440/90-20 on 900920-1116.Corective Actions:Valve Repair & Rebuilding,Per LER 90-025-01,dtd 901123 & Restoration of Six MSIV That Required Disassembly to Original Condition | | | 05000440/LER-1990-027, :on 900925,personnel Error Resulted in Air Roll of Div 1 Diesel Generator |
- on 900925,personnel Error Resulted in Air Roll of Div 1 Diesel Generator
| | | 05000440/LER-1990-028, :on 901009,failure to Perform Surveillance Resulted in Inoperable Containment Isolation Valves |
- on 901009,failure to Perform Surveillance Resulted in Inoperable Containment Isolation Valves
| | | 05000440/LER-1990-030, :on 901011,failure to Perform Required Surveillance Prior to Resuming Fuel Movement Discovered |
- on 901011,failure to Perform Required Surveillance Prior to Resuming Fuel Movement Discovered
| | | 05000440/LER-1990-031, :on 901022,control Rod Withdrawn W/O First Demonstrating by Channel Check That Scram Discharge Vol Level Instrumentation Operable |
- on 901022,control Rod Withdrawn W/O First Demonstrating by Channel Check That Scram Discharge Vol Level Instrumentation Operable
| | | 05000440/LER-1990-032, :on 901116,disconnecting Wires to Test Relay Contact Resulted in RHR a Shutdown Cooling Sys Isolation. Caused by Procedure Deficiency & Inadequate Instructions. Personnel Trained Re Review of Work Orders |
- on 901116,disconnecting Wires to Test Relay Contact Resulted in RHR a Shutdown Cooling Sys Isolation. Caused by Procedure Deficiency & Inadequate Instructions. Personnel Trained Re Review of Work Orders
| | | 05000440/LER-1990-033, :on 901120,Train B of Control Room HVAC Sys Actuated Unexpectedly in Emergency Recirculation Mode.Caused by Inadequate Instruction.Procedure Revised Re Correct Guidance During Loss of Power to Bus K-1-N |
- on 901120,Train B of Control Room HVAC Sys Actuated Unexpectedly in Emergency Recirculation Mode.Caused by Inadequate Instruction.Procedure Revised Re Correct Guidance During Loss of Power to Bus K-1-N
| | | 05000440/LER-1990-034, :on 901125,discovered That Reactor Pressure Vessel Water Level Instrumentation Equalizing Valve Mispositioned.Caused by Personnel Error.Equalizing Valve Closed & Walkdown Performed |
- on 901125,discovered That Reactor Pressure Vessel Water Level Instrumentation Equalizing Valve Mispositioned.Caused by Personnel Error.Equalizing Valve Closed & Walkdown Performed
| | | 05000440/LER-1990-036, :on 901207,control Rod Scram Accumulator Level Switch Inoperable Throughout Second Fuel Cycle in Violation of Tech Spec 3.1.3.3.Caused by Unidentified Sys Interaction. Sys Operating Instruction Revised |
- on 901207,control Rod Scram Accumulator Level Switch Inoperable Throughout Second Fuel Cycle in Violation of Tech Spec 3.1.3.3.Caused by Unidentified Sys Interaction. Sys Operating Instruction Revised
| | | 05000440/LER-1990-038, :on 901211,control Room Noble Gas Radiation Monitor Inoperable for More than 7 Days W/O Taking Compensatory Actions.Caused by Personnel Error.Valve Lineup Instruction Changed & Monitor Will Be Included in Training |
- on 901211,control Room Noble Gas Radiation Monitor Inoperable for More than 7 Days W/O Taking Compensatory Actions.Caused by Personnel Error.Valve Lineup Instruction Changed & Monitor Will Be Included in Training
| | | 05000440/LER-1990-039, :on 901211,discovered That Both Loops of Containment Spray Mode of RHR Sys Inoperable.Caused by Inadequate Instructions.Instructions Revised to Include Isolation Valve for Position Verification |
- on 901211,discovered That Both Loops of Containment Spray Mode of RHR Sys Inoperable.Caused by Inadequate Instructions.Instructions Revised to Include Isolation Valve for Position Verification
| | | 05000440/LER-1990-040, :on 901218,RWCU Isolation Occurred While Correcting Cause of RWCU Sys Outboard Isolation Valves Not Opening.Caused by Personnel Error.Panel & Tools Inspected for Shorting & Fuses Replaced |
- on 901218,RWCU Isolation Occurred While Correcting Cause of RWCU Sys Outboard Isolation Valves Not Opening.Caused by Personnel Error.Panel & Tools Inspected for Shorting & Fuses Replaced
| | | 05000440/LER-1990-041, :Between 901212 & 28,inoperable Reactor Pressure Vessel Level Instrumentation Channels Resulted in HPCS Sys Being Inoperable & in Tech Spec Violation.Caused by Personnel Error.Memo Issued |
- Between 901212 & 28,inoperable Reactor Pressure Vessel Level Instrumentation Channels Resulted in HPCS Sys Being Inoperable & in Tech Spec Violation.Caused by Personnel Error.Memo Issued
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