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seRC perm aos APNt0VED Oess No. 3190-410e i
LICENSEE EVENT REPORT (LER)
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ftTLE 446 Computer Rod Position Deviation Alarm SVEIET DATE 19 LOR 90URSER 181 ILSPORT DATE (73 OTHER PACILITIES serv 0Lv80 21 i
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AMTRACT (LiaWe to f 400 misser, d.a..soresim.esty fifisse sapegsor symmertrsse Naamp (146 On 01/16/85 a series of blown fuses in the computer resulted in actuation of about 90 alarms on the Computer Alarm Typewriter at the time that I&C technicians were removing and restoring Foxboro channels for Periodic Test procedures.
The computer technician was swapping trend and log typewriters.
A printout alerting the operator to Control Rod Banks not being updated at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> went unnoticed due to previous alarm activity.
Subsequent printouts for Rods not updated occurred and this printout was detected when the afternoon shift operator attempted to perform the computer program check at 1634 hours0.0189 days <br />0.454 hours <br />0.0027 weeks <br />6.21737e-4 months <br />.
The Rod Banks were updated at 1703 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.479915e-4 months <br />.
Procedure S-26.2 (Computer out of Service) and Technical Specification Table 4.1-1 Item #9 dictates that Control Rod Position Indicators should be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the alarm.
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NaC Form 3BSA U S. NUCLE AR REGUL ATORY COMMIS$40N LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AreaOvEO Ou No 2iuo.
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. w an we a -ms4w nn On 01/16/85 at 0756 hours0.00875 days <br />0.21 hours <br />0.00125 weeks <br />2.87658e-4 months <br /> the " Computer Rod Deviation" alarm was satisfactorily tested.
At 0833 hours0.00964 days <br />0.231 hours <br />0.00138 weeks <br />3.169565e-4 months <br /> I&C Technicians removed Foxboro Channel 4 from scan to complete PT-5.40 (Process Instrumen-tation Reactor Protection Channel Trip Test).
At the same time the Computer Technician was swapping trend and log typewriter devices.
At 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> and 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> the rod position monitor was functional.
At 1102 hours0.0128 days <br />0.306 hours <br />0.00182 weeks <br />4.19311e-4 months <br /> indication of about 90 alarms came in on the Computer Alarm Typewriter as a result of a blown fuse in the computer.
A Foxboro channel was added to scan at about the same time.
At 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> a printout (no alarm) was displayed that Control Rod Banks were not updated.
The operator failed to detect this printout and subsequent printouts on the typewriter device, alluding to the Control Rod Banks not updated, since they were not audibly alarmed.
At 1253 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.767665e-4 months <br /> Foxboro Channel 1 was removed from scan and the same series of about 90 alarms reoccurred.
Another blown fuse was found to be the cause.
Further printouts followed indicating Control Rod Banks were not updated.
The afternoon shift, during the computer program check, identified the problem at 1634 hours0.0189 days <br />0.454 hours <br />0.0027 weeks <br />6.21737e-4 months <br /> and updated the computer at 1703 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.479915e-4 months <br />.
According to procedure S-26.2 and Technical Specifications Table 4.1-1 Item #9 Control Rod Position Indicators should be hand logged within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the initial printout (or the program updated) by 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />.
Although the event falls into the category of personnel error, it is felt that contributing factors include the unforeseen possibility of the failure of fuses concurrent with a Periodic Test well known for the excessive activity of audible alarms.
A possible corrective Action plan should include increasing the frequency of the computer check (since this action identified the problea) to every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> rather than once per shift.
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ROCHESTER GAS AND ELECTRIC CORPORATION e 89 EAST AVENUE, ROCHESTER, N.Y.14645-b001 NQ f40CER W. KOBER VCE PRESIDEN.
TE L E P6*ON E ELec1Rc a STEAM PRODUCTeON age 4 CODE M6 546 2700 February 15, 1985 U.S.
Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
LER 85-001, Inoperable Analog Rod Position (Computer i
Rod Position Deviation Alarm) n.E.
Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(i)(B) which requests a report of, "any operation or conditions prohibited by the plant Technical Specification",
the attached Licensee Event Report LER 85-001 is hereby submitted.
' r-truly yours, Y*
R er W. Kober RWK/eeg xc U.S.
Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406
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| 05000244/LER-1985-001, :on 850116,series of Blown Fuses in Computer Resulted in Actuation of 90 Alarms on Computer Alarm Typewriter at Time I&C Technicians Removing & Restoring Foxboro Channels.Caused by Personnel Error |
- on 850116,series of Blown Fuses in Computer Resulted in Actuation of 90 Alarms on Computer Alarm Typewriter at Time I&C Technicians Removing & Restoring Foxboro Channels.Caused by Personnel Error
| | | 05000244/LER-1985-002, :on 850121,control Room Notified That Low Frequency of 59.9 Hertz Existed.Caused by Ny Power Pools Imbalance Between Load Demand & Electrical Generation Due to Cold Weather.Diesel Generator Operation Begun |
- on 850121,control Room Notified That Low Frequency of 59.9 Hertz Existed.Caused by Ny Power Pools Imbalance Between Load Demand & Electrical Generation Due to Cold Weather.Diesel Generator Operation Begun
| | | 05000244/LER-1985-003, :on 850309,cable Tunnel Smoke Detection Sys Auto Deluge Inadvertently Removed from Svc.Caused by Personnel Error of Misreading Zone to Be Deactivated. Procedure Reviewed |
- on 850309,cable Tunnel Smoke Detection Sys Auto Deluge Inadvertently Removed from Svc.Caused by Personnel Error of Misreading Zone to Be Deactivated. Procedure Reviewed
| | | 05000244/LER-1985-004, :on 850326,safety Injection Actuation Signal Generated Twice.First Event Caused by Deficiency in Maint Procedure M-48.14.Second Event Caused by Momentary Loss of Power |
- on 850326,safety Injection Actuation Signal Generated Twice.First Event Caused by Deficiency in Maint Procedure M-48.14.Second Event Caused by Momentary Loss of Power
| | | 05000244/LER-1985-005, :on 850405,leads of Resistance Temp Detector in Channel 4 Opened,Resulting in Reactor Trip Signal During Hot Shutdown.Only Actuation Was Automatic Opening of Reactor Trip Breakers.Caused by Personnel Error |
- on 850405,leads of Resistance Temp Detector in Channel 4 Opened,Resulting in Reactor Trip Signal During Hot Shutdown.Only Actuation Was Automatic Opening of Reactor Trip Breakers.Caused by Personnel Error
| | | 05000244/LER-1985-006-01, :on 850406,during Startup from Refueling Outage,Reactor Trip & Turbine Trip Occurred.Caused by Steam Generator B Level Below 30% W/Tripped Feedwater Flow Less than Steam Flow Bistable,Per Procedure CP-477 |
- on 850406,during Startup from Refueling Outage,Reactor Trip & Turbine Trip Occurred.Caused by Steam Generator B Level Below 30% W/Tripped Feedwater Flow Less than Steam Flow Bistable,Per Procedure CP-477
| | | 05000244/LER-1985-007, :on 850406,reactor Tripped & Turbine Failed to Automatically Trip.Caused by Steam Generator Level B Reducing Below 17% Narrow Range Level.Caused by Mechanical Binding of 20ET Trip Solenoid |
- on 850406,reactor Tripped & Turbine Failed to Automatically Trip.Caused by Steam Generator Level B Reducing Below 17% Narrow Range Level.Caused by Mechanical Binding of 20ET Trip Solenoid
| | | 05000244/LER-1985-008, :on 850407,reactor Tripped on Low Steam Generator Level.Caused by Operations Personnel Inability to Maintain Steam Generator Levels Above Trip Setpoints While Transferring Level Control |
- on 850407,reactor Tripped on Low Steam Generator Level.Caused by Operations Personnel Inability to Maintain Steam Generator Levels Above Trip Setpoints While Transferring Level Control
| | | 05000244/LER-1985-009, :on 850408,during Secondary Sys Pressure Transient,Condensate Bypass Valve Automatically Opened Causing Turbine to Trip.Caused by Condensate Bypass Valve Switch in Automatic Position |
- on 850408,during Secondary Sys Pressure Transient,Condensate Bypass Valve Automatically Opened Causing Turbine to Trip.Caused by Condensate Bypass Valve Switch in Automatic Position
| | | 05000244/LER-1985-010, :on 850408,during Operational Test of Nuclear Instrumentation Intermediate Range Channel N-35,reactor Trip Breaker B Opened W/No Annunciation of Reactor Trip First Out.Caused by Faulty Coil.Relay Replaced |
- on 850408,during Operational Test of Nuclear Instrumentation Intermediate Range Channel N-35,reactor Trip Breaker B Opened W/No Annunciation of Reactor Trip First Out.Caused by Faulty Coil.Relay Replaced
| | | 05000244/LER-1985-011, :on 850411,reactor Trip Occurred During Attempts to Trip Main Turbine Manually.Caused by Low Condenser Vacuum & Reactor Power Being Above P-7.Inquiry Re Reactor Trip Train Design Undertaken |
- on 850411,reactor Trip Occurred During Attempts to Trip Main Turbine Manually.Caused by Low Condenser Vacuum & Reactor Power Being Above P-7.Inquiry Re Reactor Trip Train Design Undertaken
| | | 05000244/LER-1985-012, :on 850506,two Containment Charcoal Filters & Fan Coolers Discovered Inoperable Under Large Break LOCA Conditions.Caused by Flood Following Refueling Water Storage Tank Emptying Into Containment |
- on 850506,two Containment Charcoal Filters & Fan Coolers Discovered Inoperable Under Large Break LOCA Conditions.Caused by Flood Following Refueling Water Storage Tank Emptying Into Containment
| | | 05000244/LER-1985-013, :on 850531,one Emergency Diesel Generator Started Per Adverse Weather Emergency Plan Due to Notification of Tornado Warning.Generator Removed from Svc When Tornado Warning Rescinded |
- on 850531,one Emergency Diesel Generator Started Per Adverse Weather Emergency Plan Due to Notification of Tornado Warning.Generator Removed from Svc When Tornado Warning Rescinded
| | | 05000244/LER-1985-014, :on 850606,automatic Reactor & Turbine Trips Occurred When Overpower Delta Temp Reactor Trip Actuated. Reactor Stabilized at Hot Shutdown Conditions.Caused by Grounding of Wire During Repairs |
- on 850606,automatic Reactor & Turbine Trips Occurred When Overpower Delta Temp Reactor Trip Actuated. Reactor Stabilized at Hot Shutdown Conditions.Caused by Grounding of Wire During Repairs
| | | 05000244/LER-1985-015, :on 850620,for 45 S,Two Flow Paths from Boric Acid Storage Tank to RCS Unavailable.Caused by Nonlicensed Primary Auxiliary Operator Error.Low Level Logic in Boric Acid Tank Reset |
- on 850620,for 45 S,Two Flow Paths from Boric Acid Storage Tank to RCS Unavailable.Caused by Nonlicensed Primary Auxiliary Operator Error.Low Level Logic in Boric Acid Tank Reset
| | | 05000244/LER-1985-016, :on 850915,control Rod Deviation Alarm Occurred.Caused by Intermittent Fluctuation in RPI & Change in Reactor Coolant Temp.On 850916,control Rod Indication Sys Made Inoperable to Replace Power Supplies |
- on 850915,control Rod Deviation Alarm Occurred.Caused by Intermittent Fluctuation in RPI & Change in Reactor Coolant Temp.On 850916,control Rod Indication Sys Made Inoperable to Replace Power Supplies
| | | 05000244/LER-1985-017, :on 850916,rod Control Sys on Bank D Switch Allowed Only Two Rods in Each of Banks B & D to Move, Causing Control Rod Insertion & Bank Overlap Violations. Caused by Faulty Firing Card.Card Replaced |
- on 850916,rod Control Sys on Bank D Switch Allowed Only Two Rods in Each of Banks B & D to Move, Causing Control Rod Insertion & Bank Overlap Violations. Caused by Faulty Firing Card.Card Replaced
| | | 05000244/LER-1985-018, :on 850928,turbine & Reactor Tripped Manually Due to Electrohydraulic Sys Failure.Caused by Water Entering Electrohydraulic Fluid Through Tube Leak in Fluid Cooler. Tube Leak Repaired.Fluid Replaced |
- on 850928,turbine & Reactor Tripped Manually Due to Electrohydraulic Sys Failure.Caused by Water Entering Electrohydraulic Fluid Through Tube Leak in Fluid Cooler. Tube Leak Repaired.Fluid Replaced
| | | 05000244/LER-1985-019, :on 851125,condenser Circulating Water Pump 1B Tripped,Resulting in Reactor Trip.Caused by Power Factor Relay Trip Setpoint Drift.Trip Setpoint Readjusted & Relay Tested Satisfactorily |
- on 851125,condenser Circulating Water Pump 1B Tripped,Resulting in Reactor Trip.Caused by Power Factor Relay Trip Setpoint Drift.Trip Setpoint Readjusted & Relay Tested Satisfactorily
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