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| | Title = Corrected LER 85-008-00:on 850610,review by Operations Dept Discovered That Temporary Jumper/Block Log 2036 Not Reviewed by General Superintendent within 14-day Time Limit,Per Tech Spec 6.8.3.C | | | Title = Corrected LER 85-008-00:on 850610,review by Operations Dept Discovered That Temporary Jumper/Block Log 2036 Not Reviewed by General Superintendent within 14-day Time Limit,Per Tech Spec 6.8.3.C |
| | Plant = | | | Plant = |
| | Reporting criterion = | | | Reporting criterion = 10 CFR 50.73(a)(2)(i) |
| | Power level = | | | Power level = |
| | Mode = | | | Mode = |
| | Docket = 05000220 | | | Docket = 05000220 |
| | LER year = 2085 | | | LER year = 1985 |
| | LER number = 8 | | | LER number = 8 |
| | LER revision = | | | LER revision = 0 |
| | Event date = | | | Event date = |
| | Report date = | | | Report date = |
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| =text= | | =text= |
| {{#Wiki_filter:a e | | {{#Wiki_filter:a e |
| NRC fore 388 U 5 NUCLE AR KEGULATOAV COMM88880N | | NRC fore 388 U 5 NUCLE AR KEGULATOAV COMM88880N |
| * *3 ' APPROvtD OMS NO 2190-4i04
| | * *3 ' |
| "''"" 8''''
| | APPROvtD OMS NO 2190-4i04 |
| | " ' ' " " 8'''' |
| LICENSEE EVENT REPORT (LER) | | LICENSEE EVENT REPORT (LER) |
| DOCKE Y NUMSE R tal PAGEi34
| | PAGEi34 |
| /ACILITY NAME til Nine Mile Point Unit #1 o l5 j o jo lol2l 21 0 1 loFl 012 Tint ..
| | /ACILITY NAME til DOCKE Y NUMSE R tal Nine Mile Point Unit #1 o l5 j o jo lol2l 21 0 1 loFl 012 Tint.. |
| Failure to review Jumper / Block log within 14 days EVENT DATE I5I LE R NUMBE R 18, REPORY DATE IF) OTHE R F ACILITtES sNv0LVED 408 F ACitiv v %44 55 DOcaE.7 NUMetR Sl MONTH DAY YEAR vEAR 8'('Z ',4 6 ;e .$ MONTw 04v vtAR 0 151010101 l l 1] O 1l 6 8 4 8 l5 0l0 l 8 0l 0 0 l7 1l 0 8l5 o isio 1 0 1 0 1 1 I TMis REPomT is sueMarTED PunsuANT To THE REouiREurNTs on to Ce R I <Ca.c. .a. or mer. ee ra. e."...ari et ti oPERAfiNo | | Failure to review Jumper / Block log within 14 days EVENT DATE I5I LE R NUMBE R 18, REPORY DATE IF) |
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| n .ae..imi.i so n4.nzn ,> no n<. nan.i LICENSEE CONTACT POR THIS LER tt:I NAME TELEPHONE NLM8ER ARE A CODE Robert Randall. Supervisor. Technical Services 31115 31419 l -12141415 COMPLETE ONE LINE FOR E ACH COMPONENT F AILURE DESCRIBED IN TMit REPORT fi3t w | | n ni.i g |
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| *# "E CAuSE $v5TEU COMPONENT CAVSE SYSTEM COYPONENT "''Om TQ pT_A D5 8 L E I I I i i l l I i i I ! I f I l I l l l l l I l ! I I I SUPPLEMENTAL REPORT EXPECTED li.i MONTH DAv vEAR 5L 9 V' 5580 %
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| vE5 <tr vos c.morare E2PECTED susMrss10N DMEl NO l l l AS$TR ACT !Lef to 1400 so. css e e esproses, y resea pag e mece type.r,rme wess (ISi ABSTRACT On June 10, 1985, during normal operations, a review performed by Operations Department personnel discovered that temporary Jumper / Block Log #2036 had not been reviewed by the General Superintendent-Nuclear Generation within the 14 day time limit per Technical Specification 6.8.3.C. It has since been reviewed by the General Superintendent-Nuclear Generation per Technical Specifications. | | .a n..nzn, |
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| | no n<. nan.i LICENSEE CONTACT POR THIS LER tt:I NAME TELEPHONE NLM8ER ARE A CODE Robert Randall. Supervisor. Technical Services 31115 31419 l -12141415 COMPLETE ONE LINE FOR E ACH COMPONENT F AILURE DESCRIBED IN TMit REPORT fi3t w |
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| | R EPOR,T A8 LE CAVSE SYSTEM COYPONENT |
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| | |
| | ==CAuSE== |
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| | v AS$TR ACT !Lef to 1400 so. css e e esproses, y resea pag e mece type.r,rme wess (ISi ABSTRACT On June 10, 1985, during normal operations, a review performed by Operations Department personnel discovered that temporary Jumper / Block Log #2036 had not been reviewed by the General Superintendent-Nuclear Generation within the 14 day time limit per Technical Specification 6.8.3.C. |
| | It has since been reviewed by the General Superintendent-Nuclear Generation per Technical Specifications. |
| | 8508150694 850726 PDR ADOCK 05000220 S |
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| IfI NRC Form 384 89 SJi | | IfI NRC Form 384 89 SJi |
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| GEPiAES 4/3115 | | 4AC Per8m J844 g & *euCLEAR AEGukaTOAV COMesesssCae LICENSEE EVENT REP 9RT (LERI TEXT CONTINUATION |
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| 008 99 ]0,00go, Of TEXT On June 10, 1985, during normal operation, a review performed by Operations Department personnel discovered that temporary Jumper / Block Log #2036 had not been reviewed by the General Superintendent-Nuclear Generation within the 14 day time limit per Technical Specifications. This constituted a violation of Technical Specification 6.8.3.C, which states that a temporary change in procedure required by Technical Specifications must be documented, reviewed and approved by the Gcneral Superintendent-Nuclear Generation or designee within 14 days of implementation. The purpose of Jumper / Block Log | | i a 6 yat:l;;M ef,p |
| #2036 was to lift several leads for the performance of required maintenance on a faulty amplifier (AMP). This faulty amplifier (AMP) was causing the computer to read the reactor pressure as 34 psig when the actual pressure was 1019 psig. The work request for the maintenance of the amplifier (AMP) was issued on July 21, 1984 The leads were lifted on October 2, 1984 and the work completed on October S, 1984. The lifting of the 1 cads did not cause any safety related system to become inoperable, and the
| | ]0,00go, Of Nine Mile Point Unit #1 |
| #11 Channel Reactor Pressure Computer point was always operable. The Jumper / Block Log has since been reviewed by the General Superintendent- _
| | , g,,,,,, 2,208g 008 9 9 TEXT On June 10, 1985, during normal operation, a review performed by Operations Department personnel discovered that temporary Jumper / Block Log #2036 had not been reviewed by the General Superintendent-Nuclear Generation within the 14 day time limit per Technical Specifications. This constituted a violation of Technical Specification 6.8.3.C, which states that a temporary change in procedure required by Technical Specifications must be documented, reviewed and approved by the Gcneral Superintendent-Nuclear Generation or designee within 14 days of implementation. The purpose of Jumper / Block Log |
| Nuclear Generation per Technical Specifications. | | #2036 was to lift several leads for the performance of required maintenance on a faulty amplifier (AMP). This faulty amplifier (AMP) was causing the computer to read the reactor pressure as 34 psig when the actual pressure was 1019 psig. The work request for the maintenance of the amplifier (AMP) was issued on July 21, 1984 The leads were lifted on October 2, 1984 and the work completed on October S, 1984. The lifting of the 1 cads did not cause any safety related system to become inoperable, and the |
| CORRECTIVE ACTION The immediate corrective action consisted of completing the required review by the General Superintendent-Nuclear Generation. | | #11 Channel Reactor Pressure Computer point was always operable. The Jumper / Block Log has since been reviewed by the General Superintendent-Nuclear Generation per Technical Specifications. |
| | |
| | ==CORRECTIVE ACTION== |
| | The immediate corrective action consisted of completing the required review by the General Superintendent-Nuclear Generation. |
| NMPC is in the process of implementing a new procedure to ensure that these reviews will be completed in a timely manner. This will be complete by September 1, 1985. | | NMPC is in the process of implementing a new procedure to ensure that these reviews will be completed in a timely manner. This will be complete by September 1, 1985. |
| a ASSESSMENT OF SAFETY CONSEQUENCES There was no potential safety consequences arising out of this event because the device that was the subject to the lifting of leads (amplifier) did not cause any portionof a safety related system or component to become inoperabic. The parameter that this amplifier (AMP) services (Reactor Pressure) has numerous redundant indications which were available in analog readout form and the #11 Channel Reactor Pressure Computer point was operabic and availabic to the operator throughout the event. | | a |
| | |
| | ==ASSESSMENT OF SAFETY CONSEQUENCES== |
| | There was no potential safety consequences arising out of this event because the device that was the subject to the lifting of leads (amplifier) did not cause any portionof a safety related system or component to become inoperabic. The parameter that this amplifier (AMP) services (Reactor Pressure) has numerous redundant indications which were available in analog readout form and the #11 Channel Reactor Pressure Computer point was operabic and availabic to the operator throughout the event. |
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| NIAGARA MOHAWK POWER CORPORATION NI AGAR A MOHAWK 300 ERIE DOULEV ARD. WEST SYRACUSE. N. Y.13 202 Juig 26, 1985 United States Nuclear Regulatorij Comnission Document Controi Desk k'ashington, DC 20555 Re: Docket No. 50-220 LER 85-08 Gentiemen: | | NIAGARA MOHAWK POWER CORPORATION NI AGAR A MOHAWK 300 ERIE DOULEV ARD. WEST SYRACUSE. N. Y.13 202 Juig 26, 1985 United States Nuclear Regulatorij Comnission Document Controi Desk k'ashington, DC 20555 Re: Docket No. 50-220 LER 85-08 Gentiemen: |
| In accordance teith 10 CFR 50.73, we licrebi j submit tite folioxing Licensee Event Repott: | | In accordance teith 10 CFR 50.73, we licrebi submit tite folioxing j |
| : LER 85-08 k'hich is being subntotted in accordance leith 10 CFR 50.73 (a) (2) (i), "Anry deviation from l tite plant's Technicai Specifications authorized pursuant to S 50. 54 (x) o f this part. "
| | Licensee Event Repott: |
| | LER 85-08 k'hich is being subntotted in accordance leith 10 CFR 50.73 (a) (2) (i), "Anry deviation from l |
| | tite plant's Technicai Specifications authorized pursuant to S 50. 54 (x) o f this part. " |
| This report was compicted in the format designated in NUREG-1022, dated September 1983. | | This report was compicted in the format designated in NUREG-1022, dated September 1983. |
| Verij truitj yours, | | Verij truitj yours, ye |
| ~ ,
| | ~ |
| ye Thon.as E. Lunpges Vice President Nacicar Generation TEL/tg cc: Dr. Thomas E. bfurlet)
| | Thon.as E. Lunpges Vice President Nacicar Generation TEL/tg cc: Dr. Thomas E. bfurlet) |
| Regionai Adninistrator Attaclunent J | | Regionai Adninistrator Attaclunent J |
| }} | | }} |
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| {{LER-Nav}} | | {{LER-Nav}} |
LER-1985-008, Corrected LER 85-008-00:on 850610,review by Operations Dept Discovered That Temporary Jumper/Block Log 2036 Not Reviewed by General Superintendent within 14-day Time Limit,Per Tech Spec 6.8.3.C |
| Event date: |
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| Reporting criterion: |
10 CFR 50.73(a)(2)(i) |
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| 2201985008R00 - NRC Website |
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NRC fore 388 U 5 NUCLE AR KEGULATOAV COMM88880N
APPROvtD OMS NO 2190-4i04
" ' ' " " 8'
LICENSEE EVENT REPORT (LER)
PAGEi34
/ACILITY NAME til DOCKE Y NUMSE R tal Nine Mile Point Unit #1 o l5 j o jo lol2l 21 0 1 loFl 012 Tint..
Failure to review Jumper / Block log within 14 days EVENT DATE I5I LE R NUMBE R 18, REPORY DATE IF)
OTHE R F ACILITtES sNv0LVED 408 MONTH DAY YEAR vEAR 8'('Z ',4 6
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NIAGARA MOHAWK POWER CORPORATION NI AGAR A MOHAWK 300 ERIE DOULEV ARD. WEST SYRACUSE. N. Y.13 202 Juig 26, 1985 United States Nuclear Regulatorij Comnission Document Controi Desk k'ashington, DC 20555 Re: Docket No. 50-220 LER 85-08 Gentiemen:
In accordance teith 10 CFR 50.73, we licrebi submit tite folioxing j
Licensee Event Repott:
LER 85-08 k'hich is being subntotted in accordance leith 10 CFR 50.73 (a) (2) (i), "Anry deviation from l
tite plant's Technicai Specifications authorized pursuant to S 50. 54 (x) o f this part. "
This report was compicted in the format designated in NUREG-1022, dated September 1983.
Verij truitj yours, ye
~
Thon.as E. Lunpges Vice President Nacicar Generation TEL/tg cc: Dr. Thomas E. bfurlet)
Regionai Adninistrator Attaclunent J
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| 05000220/LER-1985-001, :on 850123,24 & 0207,automatic Initiations of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by off-normal Spiking of Ventilation Duct Radiation Monitor 11.Sensor Converter Replaced |
- on 850123,24 & 0207,automatic Initiations of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by off-normal Spiking of Ventilation Duct Radiation Monitor 11.Sensor Converter Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000220/LER-1985-002, :on 850214,auxiliary Control Room Fire Suppression Sys Inoperable.Caused by Inoperable Fire Dampers.Fire Dampers Repaired & Tested.Personnel Instructed in Tech Spec Requirements |
- on 850214,auxiliary Control Room Fire Suppression Sys Inoperable.Caused by Inoperable Fire Dampers.Fire Dampers Repaired & Tested.Personnel Instructed in Tech Spec Requirements
| | | 05000220/LER-1985-003, On 850304,reactor Scram Initiated.Caused by Technicians Trying to Rectify Error Condition in Transmitter During Monthly Surveillance.Procedure Revised to Caution Technicians on Effects of Errors | On 850304,reactor Scram Initiated.Caused by Technicians Trying to Rectify Error Condition in Transmitter During Monthly Surveillance.Procedure Revised to Caution Technicians on Effects of Errors | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000220/LER-1985-004, :on 850304,during Shutdown,Turbine Trip Signal Led to HPCI Initiation.Caused by High Reactor Water Level.Level Control Adjusted.Water Level Returned to Normal |
- on 850304,during Shutdown,Turbine Trip Signal Led to HPCI Initiation.Caused by High Reactor Water Level.Level Control Adjusted.Water Level Returned to Normal
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000220/LER-1985-005, :on 850416,reactor Scram Occurred Due to APRM High Flux Level.Caused by Partial Closing of Turbine Control Valves Due to Disturbance in Turbine Control Sys.Work Requests Issued to Troubleshoot Sys |
- on 850416,reactor Scram Occurred Due to APRM High Flux Level.Caused by Partial Closing of Turbine Control Valves Due to Disturbance in Turbine Control Sys.Work Requests Issued to Troubleshoot Sys
| | | 05000220/LER-1985-006, :on 850419,automatic Initiation of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by off-normal Spiking of Reactor Bldg Ventilation Duct Monitor 11.Sys Checked & Source Calibr.Sys Returned to Svc |
- on 850419,automatic Initiation of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by off-normal Spiking of Reactor Bldg Ventilation Duct Monitor 11.Sys Checked & Source Calibr.Sys Returned to Svc
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000220/LER-1985-007, :on 850424,automatic Initiation of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by Technician Shorting Wire in Cable Connector to Sensor for Emergency Condensor Ventilation Monitor 121 |
- on 850424,automatic Initiation of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by Technician Shorting Wire in Cable Connector to Sensor for Emergency Condensor Ventilation Monitor 121
| | | 05000220/LER-1985-008-01, :on 850610,discovered That Temporary Jumper Block Log 2036 Not Reviewed by General Superintendent within 14-day Time Limit.Cause Unstated.Review Completed.New Procedure to Ensure Timely Reviews Implemented |
- on 850610,discovered That Temporary Jumper Block Log 2036 Not Reviewed by General Superintendent within 14-day Time Limit.Cause Unstated.Review Completed.New Procedure to Ensure Timely Reviews Implemented
| 10 CFR 50.73(a)(2)(i) | | 05000220/LER-1985-008, Corrected LER 85-008-00:on 850610,review by Operations Dept Discovered That Temporary Jumper/Block Log 2036 Not Reviewed by General Superintendent within 14-day Time Limit,Per Tech Spec 6.8.3.C | Corrected LER 85-008-00:on 850610,review by Operations Dept Discovered That Temporary Jumper/Block Log 2036 Not Reviewed by General Superintendent within 14-day Time Limit,Per Tech Spec 6.8.3.C | 10 CFR 50.73(a)(2)(i) | | 05000220/LER-1985-009, :on 850522 & 31,discovered Instrument Channel Tests Not Performed on Three of Four Emergency Condenser Sys Noble Gas Activity & Suppression Chamber Water Level Monitors.Cause Unknown.Tests Performed |
- on 850522 & 31,discovered Instrument Channel Tests Not Performed on Three of Four Emergency Condenser Sys Noble Gas Activity & Suppression Chamber Water Level Monitors.Cause Unknown.Tests Performed
| 10 CFR 50.73(a)(2)(1) | | 05000220/LER-1985-010, :on 850815,accidental Initiation of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by Electrical Spike Experienced by Channel 12 Reactor Bldg Ventilation Duct Monitor.Ventilation Sys Reset |
- on 850815,accidental Initiation of Reactor Bldg Emergency Ventilation Sys Occurred.Caused by Electrical Spike Experienced by Channel 12 Reactor Bldg Ventilation Duct Monitor.Ventilation Sys Reset
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000220/LER-1985-011, :on 850610,review Revealed That Radiological Habitability of Technical Support Ctr (TSC) Not Consistent w/NUREG-0737,Suppl 1.Cause Unstated.Tsc Being Relocated to Better Location Re Radiation Shielding |
- on 850610,review Revealed That Radiological Habitability of Technical Support Ctr (TSC) Not Consistent w/NUREG-0737,Suppl 1.Cause Unstated.Tsc Being Relocated to Better Location Re Radiation Shielding
| | | 05000220/LER-1985-012, :on 850916,reactor Cleanup Sys Isolated Due to High Area Temp.Caused by Steam Leaking from Gland Packing on 1-inch Vent Valve from Cleanup Nonregenerative Hx.Leak Repaired |
- on 850916,reactor Cleanup Sys Isolated Due to High Area Temp.Caused by Steam Leaking from Gland Packing on 1-inch Vent Valve from Cleanup Nonregenerative Hx.Leak Repaired
| | | 05000220/LER-1985-013, :on 850621 & 25,automatic Actuation of Control Room Emergency Ventilation Sys Occurred.Caused by Spurious Upscale Deflection of Control Room Vent Monitor Due to Line Noise.Involved Monitors Recalibr |
- on 850621 & 25,automatic Actuation of Control Room Emergency Ventilation Sys Occurred.Caused by Spurious Upscale Deflection of Control Room Vent Monitor Due to Line Noise.Involved Monitors Recalibr
| | | 05000220/LER-1985-014, :on 850819,during Surveillance Insp,Maint Electrician Inadvertently Grounded Main Generator Excitation Sys Amplidyne Motor Generator Set,Causing Main Generator & Turbine Trips & Reactor Scram |
- on 850819,during Surveillance Insp,Maint Electrician Inadvertently Grounded Main Generator Excitation Sys Amplidyne Motor Generator Set,Causing Main Generator & Turbine Trips & Reactor Scram
| | | 05000220/LER-1985-015, :on 850911,personnel Informed of Three Instances of Cable Routing Discrepancies.Operators Informed. Mods Designed & Will Be Installed in Timely Manner |
- on 850911,personnel Informed of Three Instances of Cable Routing Discrepancies.Operators Informed. Mods Designed & Will Be Installed in Timely Manner
| | | 05000220/LER-1985-016, :on 850927,three Normally Open Dampers Failed to Isolate on Halon Suppression Signal.Caused by Interruption to Initiation Circuit Due to Wiring Change on 850918.Wiring Corrected |
- on 850927,three Normally Open Dampers Failed to Isolate on Halon Suppression Signal.Caused by Interruption to Initiation Circuit Due to Wiring Change on 850918.Wiring Corrected
| 10 CFR 50.73(a)(2) | | 05000220/LER-1985-017, :on 850823,reactor Scram Initiated Due to Reactor Low Water Level.Caused by Detached Range Spring & Lock Screw in Valve Positioner Closing Valve on Feedwater Pump 11.Lock Screw & Addl Hardware Replaced |
- on 850823,reactor Scram Initiated Due to Reactor Low Water Level.Caused by Detached Range Spring & Lock Screw in Valve Positioner Closing Valve on Feedwater Pump 11.Lock Screw & Addl Hardware Replaced
| | | 05000220/LER-1985-018, :on 851010,low Air Pressure Start Test of Tech Spec Section 4.6.7.b.4 Failed.Caused by Need to Energize or Manually Bypass Solenoids on Governor Sys.Mods to Governor Sys & Sys Manual Start Performed |
- on 851010,low Air Pressure Start Test of Tech Spec Section 4.6.7.b.4 Failed.Caused by Need to Energize or Manually Bypass Solenoids on Governor Sys.Mods to Governor Sys & Sys Manual Start Performed
| | | 05000220/LER-1985-019, :on 851015,discovered Emergency Isolation Dc Motor Operated Valves 39-07 & 39-08 Might Not Close within 38 During Accident.Possibly Caused by Incorrectly Sized Electric Supply Cables.Cables Replaced |
- on 851015,discovered Emergency Isolation Dc Motor Operated Valves 39-07 & 39-08 Might Not Close within 38 During Accident.Possibly Caused by Incorrectly Sized Electric Supply Cables.Cables Replaced
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000220/LER-1985-020, :on 851030,momentary Loss of Output Power from Uninterruptible Power Supply Motor Generator Set 162 Experienced.Caused by Generator Undervoltage Relay Sensing Spurious Undervoltage |
- on 851030,momentary Loss of Output Power from Uninterruptible Power Supply Motor Generator Set 162 Experienced.Caused by Generator Undervoltage Relay Sensing Spurious Undervoltage
| | | 05000220/LER-1985-021, :on 851101,during Normal Operation,Feedwater Flow Control Valve 12 Malfunctioned Causing 95-inch Reactor Water Level Condition.Caused by Problem W/Instrument Air Sys |
- on 851101,during Normal Operation,Feedwater Flow Control Valve 12 Malfunctioned Causing 95-inch Reactor Water Level Condition.Caused by Problem W/Instrument Air Sys
| | | 05000220/LER-1985-022, :on 851107,turbine Bypass Valve 12-H Inadvertently Closed,Causing Decrease in Reactor Water Level & Subsequent Scram & Initiation of HPCI Mode of Feedwater. Valve to Be Inspected |
- on 851107,turbine Bypass Valve 12-H Inadvertently Closed,Causing Decrease in Reactor Water Level & Subsequent Scram & Initiation of HPCI Mode of Feedwater. Valve to Be Inspected
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000220/LER-1985-023, :on 851108,during Preparations for Main Turbine Startup,High Temp in Main Turbine Exhaust Hood Caused Turbine Trip & Actuation of HPCI Mode of Feedwater Flow |
- on 851108,during Preparations for Main Turbine Startup,High Temp in Main Turbine Exhaust Hood Caused Turbine Trip & Actuation of HPCI Mode of Feedwater Flow
| 10 CFR 50.73(a)(2) | | 05000220/LER-1985-024, :on 851212,turbine Trip & Subsequent HPCI Mode of Feedwater Initiation Occurred.Caused by Difference Between Level Indications Due to Different Indicator Mfg. Water Level Lowered & HPCI Reset |
- on 851212,turbine Trip & Subsequent HPCI Mode of Feedwater Initiation Occurred.Caused by Difference Between Level Indications Due to Different Indicator Mfg. Water Level Lowered & HPCI Reset
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000220/LER-1985-025, :on 851215,reactor Power Reduction Initiated Due to Inability to Monitor Specified Core Thermal Parameters.Caused by Plant Process Computer Failure. Reactor Power Restored |
- on 851215,reactor Power Reduction Initiated Due to Inability to Monitor Specified Core Thermal Parameters.Caused by Plant Process Computer Failure. Reactor Power Restored
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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