Event Notification Report for October 15, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/14/2002 - 10/15/2002
EVENT NUMBERS
3928639287392883928939291
Power Reactor
Event Number: 39286
Facility: BYRON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAVID LYON
HQ OPS Officer: MIKE NORRIS
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAVID LYON
HQ OPS Officer: MIKE NORRIS
Notification Date: 10/15/2002
Notification Time: 15:32 [ET]
Event Date: 10/15/2002
Event Time: 12:18 [CDT]
Last Update Date: 10/15/2002
Notification Time: 15:32 [ET]
Event Date: 10/15/2002
Event Time: 12:18 [CDT]
Last Update Date: 10/15/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
KENNETH RIEMER (R3)
TERRY REIS (NRR)
KENNETH RIEMER (R3)
TERRY REIS (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
REACTOR TRIP AS A RESULT OF LOSS OF TURBINE GENERATOR LOAD AT BYRON STATION UNIT 1
"At 12:18 10/15/02 Unit I reactor tripped as the result of exceeding the over-temperature Delta-temperature (OT[Delta]T) reactor trip set point. The OT[Delta]T set point was exceeded as the result of a loss of Turbine load. The loss of Turbine load is currently under investigation.
"As the result of the reactor trip a feedwater isolation was initiated as expected and the auxiliary feedwater system was manually started to restore steam generator level.
"As the result of high pressure in the reactor coolant system following the loss of load, the pressurizer power operated relief valves (PORV's) lifted.
"Following the Unit trip 6.9kV, Bus 157 was de-energized due to unavailability of its back up feed breaker from the system auxiliary transformer. Planned maintenance on the breaker was in progress at the time of the trip. As a result the 1A reactor coolant pump was de-energized. All other reactor coolant pumps remained running.
"All plant systems responded as expected."
All rods fully inserted into the core and the pressurizer PORVs re-seated. There are no restrictions on restarting the 1A reactor coolant pump.
The licensee notified the NRC Resident Inspector.
"At 12:18 10/15/02 Unit I reactor tripped as the result of exceeding the over-temperature Delta-temperature (OT[Delta]T) reactor trip set point. The OT[Delta]T set point was exceeded as the result of a loss of Turbine load. The loss of Turbine load is currently under investigation.
"As the result of the reactor trip a feedwater isolation was initiated as expected and the auxiliary feedwater system was manually started to restore steam generator level.
"As the result of high pressure in the reactor coolant system following the loss of load, the pressurizer power operated relief valves (PORV's) lifted.
"Following the Unit trip 6.9kV, Bus 157 was de-energized due to unavailability of its back up feed breaker from the system auxiliary transformer. Planned maintenance on the breaker was in progress at the time of the trip. As a result the 1A reactor coolant pump was de-energized. All other reactor coolant pumps remained running.
"All plant systems responded as expected."
All rods fully inserted into the core and the pressurizer PORVs re-seated. There are no restrictions on restarting the 1A reactor coolant pump.
The licensee notified the NRC Resident Inspector.
General Information or Other
Event Number: 39287
Rep Org: ALTECH CORPORATION
Licensee: ALTECH CORPORATION
Region: 4
City: POCATELLO State: ID
County: BANNOCK
License #: 11-27657-01
Agreement: N
Docket:
NRC Notified By: BILLY BERRY
HQ OPS Officer: GERRY WAIG
Licensee: ALTECH CORPORATION
Region: 4
City: POCATELLO State: ID
County: BANNOCK
License #: 11-27657-01
Agreement: N
Docket:
NRC Notified By: BILLY BERRY
HQ OPS Officer: GERRY WAIG
Notification Date: 10/15/2002
Notification Time: 15:52 [ET]
Event Date: 10/15/2002
Event Time: 11:30 [MDT]
Last Update Date: 11/04/2002
Notification Time: 15:52 [ET]
Event Date: 10/15/2002
Event Time: 11:30 [MDT]
Last Update Date: 11/04/2002
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):
GREG PICK (R4)
FRED BROWN (NMSS)
GREG PICK (R4)
FRED BROWN (NMSS)
LOST OR STOLEN TROXLER MOISTURE DENSITY GAUGES
The licensee reported that two (2) Troxler moisture density gauges model number #2401 were missing from their storage area. The two gauges were serial number 2813 and 2744. Both gauges contain an 8.2 millicurie Cs-137 and 50 millicurie Am-241:Be source. The gauges are inventoried every six months and were verified in storage in March 2002. The cases (storage boxes) were verified again in August 2002. The licensee has notified local and county police of the missing gauges. Additionally, the licensee has contacted NRC Region 4 to inform them of this event.
* * * * * UPDATE BY LICENSEE TO MIKE RIPLEY 1210 EST 11/4/02 * * *
The licensee reported that both Troxler moisture density gauges were found and returned to the licensee. The gauges were found in the Portneauf River on 10/13/2002 by two hunters in the Blaze Creek Area near Lava Hot Springs, ID. The licensee stated that the Idaho State Police at Boise, ID, are continuing to investigate the lost gauges. Notified R4DO (C. Marschall) and NMSS EO (F. Brown).
The licensee reported that two (2) Troxler moisture density gauges model number #2401 were missing from their storage area. The two gauges were serial number 2813 and 2744. Both gauges contain an 8.2 millicurie Cs-137 and 50 millicurie Am-241:Be source. The gauges are inventoried every six months and were verified in storage in March 2002. The cases (storage boxes) were verified again in August 2002. The licensee has notified local and county police of the missing gauges. Additionally, the licensee has contacted NRC Region 4 to inform them of this event.
* * * * * UPDATE BY LICENSEE TO MIKE RIPLEY 1210 EST 11/4/02 * * *
The licensee reported that both Troxler moisture density gauges were found and returned to the licensee. The gauges were found in the Portneauf River on 10/13/2002 by two hunters in the Blaze Creek Area near Lava Hot Springs, ID. The licensee stated that the Idaho State Police at Boise, ID, are continuing to investigate the lost gauges. Notified R4DO (C. Marschall) and NMSS EO (F. Brown).
Power Reactor
Event Number: 39288
Facility: OCONEE
Region: 2 State: SC
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: RANDY TODD
HQ OPS Officer: STEVE SANDIN
Region: 2 State: SC
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: RANDY TODD
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/15/2002
Notification Time: 17:54 [ET]
Event Date: 10/15/2002
Event Time: 15:00 [EDT]
Last Update Date: 10/15/2002
Notification Time: 17:54 [ET]
Event Date: 10/15/2002
Event Time: 15:00 [EDT]
Last Update Date: 10/15/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
KEN BARR (R2)
FRANK GILLESPIE (NRR)
KEN BARR (R2)
FRANK GILLESPIE (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
NRC BULLETIN 2001-01 VISUAL INSPECTION DISCLOSED CRDM NOZZLE PENETRATION THROUGH WALL LEAKAGE
"Event Description: During qualified bare metal visual inspection of the Unit 2 reactor vessel head and CRDM nozzle penetrations per Duke response to NRC Bulletin 2001-01, evidence of through wall leakage was witnessed on seven CRDM penetrations. The locations are nozzle 8, 9,19, 24, 31, 42, and 67. None of these seven nozzles have been previously repaired. Additional nozzle to head penetrations were masked by boron deposits suspected of being from a separate source. NDE will be performed per the Duke response to NRC Bulletin 2001-01 to characterize the status of the masked penetrations.
"Initial Safety Significance: Any RCS leakage from these penetrations would have been below the threshold of measurability by the reactor coolant system leakage measurement process.
"Corrective Actions: The leaking nozzles will be repaired prior to restart from the present refueling outage."
The licensee informed the NRC resident inspector.
"Event Description: During qualified bare metal visual inspection of the Unit 2 reactor vessel head and CRDM nozzle penetrations per Duke response to NRC Bulletin 2001-01, evidence of through wall leakage was witnessed on seven CRDM penetrations. The locations are nozzle 8, 9,19, 24, 31, 42, and 67. None of these seven nozzles have been previously repaired. Additional nozzle to head penetrations were masked by boron deposits suspected of being from a separate source. NDE will be performed per the Duke response to NRC Bulletin 2001-01 to characterize the status of the masked penetrations.
"Initial Safety Significance: Any RCS leakage from these penetrations would have been below the threshold of measurability by the reactor coolant system leakage measurement process.
"Corrective Actions: The leaking nozzles will be repaired prior to restart from the present refueling outage."
The licensee informed the NRC resident inspector.
General Information or Other
Event Number: 39289
Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: CONSTRUCTION INSPECTION AND TESTING
Region: 4
City: TEMPE State: AZ
County:
License #: 7-98
Agreement: Y
Docket:
NRC Notified By: AZ RAD REGULATORY AGENCY
HQ OPS Officer: GERRY WAIG
Licensee: CONSTRUCTION INSPECTION AND TESTING
Region: 4
City: TEMPE State: AZ
County:
License #: 7-98
Agreement: Y
Docket:
NRC Notified By: AZ RAD REGULATORY AGENCY
HQ OPS Officer: GERRY WAIG
Notification Date: 10/15/2002
Notification Time: 19:18 [ET]
Event Date: 10/15/2002
Event Time: 15:25 [MST]
Last Update Date: 11/08/2002
Notification Time: 19:18 [ET]
Event Date: 10/15/2002
Event Time: 15:25 [MST]
Last Update Date: 11/08/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
GREG PICK (R4)
M. WAYNE HODGES (NMSS)
GREG PICK (R4)
M. WAYNE HODGES (NMSS)
AGREEMENT STATE - LOST OR STOLEN TROXLER MOISTURE DENSITY GAUGE
"Description of event: The licensee reported the loss of a Troxler moisture/density gauge sometime between 1030 and 1115 on 15 October after the technician left a job site in the vicinity of Cactus and 151st Ave. The gauge had been in the back of a pickup with the tailgate down. The gauge did not have a handle lock. A search of his route for several hours failed to turn up the gauge. The gauge is a Troxler Model 3400 series, serial number 29519. It contains approximately 10 millicuries of cesium 137 and approximately 50 millicuries of americium-beryllium. The company is offering a $250 reward for information leading to the return of the gauge and truck.
"The U.S. NRC, FBI, Mexico, and the states of Colorado, Nevada, Utah, New Mexico and California are being informed of this incident."
*****UPDATE ON 11/8/02 AT 14:44 FROM GODWIN TO LAURA*****
"At approximately 10:20 AM a non-licensee reported that a gauge has been turned in to 3777 E McDowell, Phoenix, AZ. Upon investigation the Agency determined that the gauge was the one lost Oct. 15, 2002. The Agency leak test indicated it is not leaking. The Licensee and Agency continue to investigate this event. The states of CO, NV, UT, NM and CA, as well as the U.S. NRC, U.S. FBI and Mexico are being notified of this recovery."
Notified NMSS (Cool)
"Description of event: The licensee reported the loss of a Troxler moisture/density gauge sometime between 1030 and 1115 on 15 October after the technician left a job site in the vicinity of Cactus and 151st Ave. The gauge had been in the back of a pickup with the tailgate down. The gauge did not have a handle lock. A search of his route for several hours failed to turn up the gauge. The gauge is a Troxler Model 3400 series, serial number 29519. It contains approximately 10 millicuries of cesium 137 and approximately 50 millicuries of americium-beryllium. The company is offering a $250 reward for information leading to the return of the gauge and truck.
"The U.S. NRC, FBI, Mexico, and the states of Colorado, Nevada, Utah, New Mexico and California are being informed of this incident."
*****UPDATE ON 11/8/02 AT 14:44 FROM GODWIN TO LAURA*****
"At approximately 10:20 AM a non-licensee reported that a gauge has been turned in to 3777 E McDowell, Phoenix, AZ. Upon investigation the Agency determined that the gauge was the one lost Oct. 15, 2002. The Agency leak test indicated it is not leaking. The Licensee and Agency continue to investigate this event. The states of CO, NV, UT, NM and CA, as well as the U.S. NRC, U.S. FBI and Mexico are being notified of this recovery."
Notified NMSS (Cool)
Power Reactor
Event Number: 39291
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JIM HUNTER
HQ OPS Officer: MIKE RIPLEY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JIM HUNTER
HQ OPS Officer: MIKE RIPLEY
Notification Date: 10/16/2002
Notification Time: 01:45 [ET]
Event Date: 10/15/2002
Event Time: 23:56 [CDT]
Last Update Date: 10/16/2002
Notification Time: 01:45 [ET]
Event Date: 10/15/2002
Event Time: 23:56 [CDT]
Last Update Date: 10/16/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
KEN BARR (R2)
KEN BARR (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO DROPPED ROD
"The Unit 1 Operator-At-The-Controls moved control rod bank D rods in 1/2 step for routine flux control at 2353 on 10/15/02. He immediately noticed rod F-6 indicated 198 steps. The remainder of the rods in bank D indicated 221 steps. A negative rate trip was received on Excore Nuclear Instrument N43 and reactor power decreased approximately 1/2% RTP [rated thermal power]. A manual reactor trip was initiated at 2356 in accordance with Abnormal Operating Procedure FNP-1-AOP-19.0. All plant systems responded per design to the reactor trip. The plant is currently stable in Mode 3. The cause for the rod drop is being investigated. Both motor driven auxiliary feedwater pumps and the turbine driven auxiliary feedwater pumps auto started in response to the main steam generator feed pumps trip."
All rods fully inserted into the core. The Main Condenser is being maintained as the primary heat sink.
The licensee notified the NRC Resident Inspector.
"The Unit 1 Operator-At-The-Controls moved control rod bank D rods in 1/2 step for routine flux control at 2353 on 10/15/02. He immediately noticed rod F-6 indicated 198 steps. The remainder of the rods in bank D indicated 221 steps. A negative rate trip was received on Excore Nuclear Instrument N43 and reactor power decreased approximately 1/2% RTP [rated thermal power]. A manual reactor trip was initiated at 2356 in accordance with Abnormal Operating Procedure FNP-1-AOP-19.0. All plant systems responded per design to the reactor trip. The plant is currently stable in Mode 3. The cause for the rod drop is being investigated. Both motor driven auxiliary feedwater pumps and the turbine driven auxiliary feedwater pumps auto started in response to the main steam generator feed pumps trip."
All rods fully inserted into the core. The Main Condenser is being maintained as the primary heat sink.
The licensee notified the NRC Resident Inspector.