Event Notification Report for January 05, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/04/2000 - 01/05/2000
EVENT NUMBERS
36562365633656436565
Power Reactor
Event Number: 36562
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: M KIER
HQ OPS Officer: JOHN MacKINNON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: M KIER
HQ OPS Officer: JOHN MacKINNON
Notification Date: 01/05/2000
Notification Time: 12:34 [ET]
Event Date: 01/05/2000
Event Time: 11:30 [CST]
Last Update Date: 01/05/2000
Notification Time: 12:34 [ET]
Event Date: 01/05/2000
Event Time: 11:30 [CST]
Last Update Date: 01/05/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
Person (Organization):
JOHN MADERA (R3)
JOHN MADERA (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
SAFETY PARAMETER DISPLAY SYSTEM (SPDS) INOPERABLE (NOT Y2K RELATED)
Clinton Power Station's SPDS was determined to be inoperable at 0400 CST on 01/05/00 due to the loss of computer points utilized in the SPDS for determining Emergency Operating Procedure entry conditions.
At 1130 CST on 01/05/00, the licensee determined that the extent of repairs to restore the SPDS function would take longer than 8 hours. Thus, based on the potential unavailability of the SPDS function for longer than 8 hours, this condition is being reported pursuant to 10CFR50.72(b)(1)(v).
This problem has no apparent link to transition to Y2K issues.
The NRC Resident Inspector was notified of this event by the licensee.
* * * UPDATE AT 1743 ON 01/05/00 FROM HALVERSON TAKEN BY MACKINNON * * *
SPDS returned to service at 1605 CST on 01/05/00. R3DO (Madera) notified.
The NRC Resident Inspector was notified of this update by the licensee.
Clinton Power Station's SPDS was determined to be inoperable at 0400 CST on 01/05/00 due to the loss of computer points utilized in the SPDS for determining Emergency Operating Procedure entry conditions.
At 1130 CST on 01/05/00, the licensee determined that the extent of repairs to restore the SPDS function would take longer than 8 hours. Thus, based on the potential unavailability of the SPDS function for longer than 8 hours, this condition is being reported pursuant to 10CFR50.72(b)(1)(v).
This problem has no apparent link to transition to Y2K issues.
The NRC Resident Inspector was notified of this event by the licensee.
* * * UPDATE AT 1743 ON 01/05/00 FROM HALVERSON TAKEN BY MACKINNON * * *
SPDS returned to service at 1605 CST on 01/05/00. R3DO (Madera) notified.
The NRC Resident Inspector was notified of this update by the licensee.
Other Nuclear Material
Event Number: 36563
Rep Org: ADVANCED INPUT DEVICES
Licensee: ADVANCED INPUT DEVICES
Region: 4
City: COEUR d' ALENE State: ID
County:
License #:
Agreement: N
Docket:
NRC Notified By: JODY PLUMMER
HQ OPS Officer: JOHN MacKINNON
Licensee: ADVANCED INPUT DEVICES
Region: 4
City: COEUR d' ALENE State: ID
County:
License #:
Agreement: N
Docket:
NRC Notified By: JODY PLUMMER
HQ OPS Officer: JOHN MacKINNON
Notification Date: 01/05/2000
Notification Time: 13:47 [ET]
Event Date: 01/05/2000
Event Time: 00:00 [MST]
Last Update Date: 01/05/2000
Notification Time: 13:47 [ET]
Event Date: 01/05/2000
Event Time: 00:00 [MST]
Last Update Date: 01/05/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
CHARLES CAIN (R4)
JOHN HICKEY (NMSS)
CHARLES CAIN (R4)
JOHN HICKEY (NMSS)
MISSING 10 MILLICURIE POLONIUM-210 STATIC IONIZER ELIMINATOR CARTRIDGE
On 03/14/99, Advanced Input Devices Company moved to a new location. A box containing one polonium-210 static ionizer eliminator cartridge was shipped to the new office and the box apparently got lost during the move. The caller discovered that the ionizer eliminator was missing since last week and that the box ended up in a land fill. The model P-2021 series static ionizer eliminator cartridge, made by NDR, Grand Island, NY, contained 10 millicuries of polonium-210. The static ionizer eliminator is used to remove static from the air at their printing company. The caller has already relayed the above information to NRC Region 4 Jeffrey Cruz.
On 03/14/99, Advanced Input Devices Company moved to a new location. A box containing one polonium-210 static ionizer eliminator cartridge was shipped to the new office and the box apparently got lost during the move. The caller discovered that the ionizer eliminator was missing since last week and that the box ended up in a land fill. The model P-2021 series static ionizer eliminator cartridge, made by NDR, Grand Island, NY, contained 10 millicuries of polonium-210. The static ionizer eliminator is used to remove static from the air at their printing company. The caller has already relayed the above information to NRC Region 4 Jeffrey Cruz.
Power Reactor
Event Number: 36564
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: HARRINGTON
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: HARRINGTON
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 01/05/2000
Notification Time: 13:48 [ET]
Event Date: 01/05/2000
Event Time: 11:50 [CST]
Last Update Date: 01/05/2000
Notification Time: 13:48 [ET]
Event Date: 01/05/2000
Event Time: 11:50 [CST]
Last Update Date: 01/05/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(v) - EMERGENCY SIREN INOP
10 CFR Section:
50.72(b)(1)(v) - EMERGENCY SIREN INOP
Person (Organization):
JOHN MADERA (R3)
JOHN MADERA (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 97 | Power Operation | 97 | Power Operation |
EMERGENCY SIRENS INOPERABLE.
DURING THE MONTHLY TEST OF THE EMERGENCY SIREN NOTIFICATION SYSTEM, THE LICENSEE EXPERIENCED A 59% LOSS OF CAPACITY. THE PROBLEM APPEARS TO BE ASSOCIATED WITH THE INITIATION EQUIPMENT NOT THE REMOTE RECEIVER OR EQUIPMENT. A CALL FOR EQUIPMENT REPAIR HAS BEEN PLACED AND REPAIRS SHOULD BE COMPLETED BY THE END OF THE WORKDAY. A FULL FUNCTION TEST OF A SECONDARY REMOTE LOCATION WAS SATISFACTORY.
THE NRC RESIDENT INSPECTOR WAS NOTIFIED.
DURING THE MONTHLY TEST OF THE EMERGENCY SIREN NOTIFICATION SYSTEM, THE LICENSEE EXPERIENCED A 59% LOSS OF CAPACITY. THE PROBLEM APPEARS TO BE ASSOCIATED WITH THE INITIATION EQUIPMENT NOT THE REMOTE RECEIVER OR EQUIPMENT. A CALL FOR EQUIPMENT REPAIR HAS BEEN PLACED AND REPAIRS SHOULD BE COMPLETED BY THE END OF THE WORKDAY. A FULL FUNCTION TEST OF A SECONDARY REMOTE LOCATION WAS SATISFACTORY.
THE NRC RESIDENT INSPECTOR WAS NOTIFIED.
Power Reactor
Event Number: 36565
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: M HAUNER
HQ OPS Officer: JOHN MacKINNON
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: M HAUNER
HQ OPS Officer: JOHN MacKINNON
Notification Date: 01/05/2000
Notification Time: 15:30 [ET]
Event Date: 01/05/2000
Event Time: 12:09 [CST]
Last Update Date: 01/05/2000
Notification Time: 15:30 [ET]
Event Date: 01/05/2000
Event Time: 12:09 [CST]
Last Update Date: 01/05/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
Person (Organization):
JOHN MADERA (R3)
JOHN MADERA (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
REACTOR SCRAM ON LOW REACTOR VESSEL WATER LEVEL DURING RESTORATION OF REACTOR VESSEL WIDE RANGE LEVEL INSTRUMENTATION
"During the performance of Surveillance Test Procedure 3.3.3.2-01, Remote Shutdown System Instrument Calibration, an instrument technician was restoring the wide range (flood-up) reactor vessel level instrument which resulted in a level transient for the 'A' and 'B' reactor vessel narrow range level instruments which share a common reference leg. The level transient resulted in a Reactor SCRAM on reactor vessel low level and a Turbine trip on reactor vessel high level. All rods fully inserted into the core. Upon receipt of the low level (170 inches), Group 2 (RHR sump & Drywell drains, etc.), Group 3 (Reactor Building Isolation), and Group 4 (Primary Containment Isolation Signal for Shutdown Cooling) isolations were completed. However, a Reactor Water Cleanup partial isolation was initiated as well. The Reactor Operator as directed by the Shift Supervisor took the isolation to completion. The cause of this partial isolation is still under investigation at this time."
"Subsequent to the reactor SCRAM, a Reactor Feed Pump and High Pressure Coolant Injection (HPCI) turbine high level trip occurred (HPCI was not running at this time) and the "A" Reactor Recirculation Pump failed to run back to minimum speed. It was further recognized that a Fuel Pool Cooling pump had tripped but the cause of that trip is still under investigation. Reactor Vessel Level as indicated on the GEMAC Level Indicators was downscale. The plant is at a normal level band with pressure and temperature stable."
The high level turbine trip was caused by the Reactor Feed Regulating Valve not going fully closed.
No Safety Relief Valves opened and the offsite electrical grid is stable.
All Emergency Core Cooling Systems and the Emergency Diesel Generators are fully operable if needed.
The NRC Resident Inspector was notified of this event by the licensee.
"During the performance of Surveillance Test Procedure 3.3.3.2-01, Remote Shutdown System Instrument Calibration, an instrument technician was restoring the wide range (flood-up) reactor vessel level instrument which resulted in a level transient for the 'A' and 'B' reactor vessel narrow range level instruments which share a common reference leg. The level transient resulted in a Reactor SCRAM on reactor vessel low level and a Turbine trip on reactor vessel high level. All rods fully inserted into the core. Upon receipt of the low level (170 inches), Group 2 (RHR sump & Drywell drains, etc.), Group 3 (Reactor Building Isolation), and Group 4 (Primary Containment Isolation Signal for Shutdown Cooling) isolations were completed. However, a Reactor Water Cleanup partial isolation was initiated as well. The Reactor Operator as directed by the Shift Supervisor took the isolation to completion. The cause of this partial isolation is still under investigation at this time."
"Subsequent to the reactor SCRAM, a Reactor Feed Pump and High Pressure Coolant Injection (HPCI) turbine high level trip occurred (HPCI was not running at this time) and the "A" Reactor Recirculation Pump failed to run back to minimum speed. It was further recognized that a Fuel Pool Cooling pump had tripped but the cause of that trip is still under investigation. Reactor Vessel Level as indicated on the GEMAC Level Indicators was downscale. The plant is at a normal level band with pressure and temperature stable."
The high level turbine trip was caused by the Reactor Feed Regulating Valve not going fully closed.
No Safety Relief Valves opened and the offsite electrical grid is stable.
All Emergency Core Cooling Systems and the Emergency Diesel Generators are fully operable if needed.
The NRC Resident Inspector was notified of this event by the licensee.