Event Notification Report for March 06, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/05/2004 - 03/06/2004
EVENT NUMBERS
4057940570405714057240573
General Information or Other
Event Number: 40579
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: Titan Atlantic
Region: 1
City: RALEIGH State: NC
County:
License #: 092-1064-1
Agreement: Y
Docket:
NRC Notified By: SHARN JEFFRIES
HQ OPS Officer: BILL GOTT
Licensee: Titan Atlantic
Region: 1
City: RALEIGH State: NC
County:
License #: 092-1064-1
Agreement: Y
Docket:
NRC Notified By: SHARN JEFFRIES
HQ OPS Officer: BILL GOTT
Notification Date: 03/09/2004
Notification Time: 14:06 [ET]
Event Date: 03/06/2004
Event Time: 00:00 [EST]
Last Update Date: 03/09/2004
Notification Time: 14:06 [ET]
Event Date: 03/06/2004
Event Time: 00:00 [EST]
Last Update Date: 03/09/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
EUGENE COBEY (R1)
FRED BROWN (NMSS)
EUGENE COBEY (R1)
FRED BROWN (NMSS)
AGREEMENT STATE REPORT OF A STOLEN RADIOGRAPHER'S DARKROOM. NO RADIOACTIVE MATERIAL INVOLVED
An industrial radiographer's 14 ft tandem axle trailer (darkroom) was stolen from the parking lot behind the home office sometime between 3/6/04 and 3/9/04. The trailer is red with white lettering, "Titan Atlantic." Neither the radiography source nor camera was in the trailer at the time of the theft. The following materials were in the trailer: overpack with "Caution Radioactive Materials" and "Radioactive Yellow II" labels, "Caution Radioactive Materials", "Caution Radiation Area", and "Caution High Radiation Area" signs, and yellow and magenta ropes and barricades.
The Raleigh NC police were notified on 3/9/04.
An industrial radiographer's 14 ft tandem axle trailer (darkroom) was stolen from the parking lot behind the home office sometime between 3/6/04 and 3/9/04. The trailer is red with white lettering, "Titan Atlantic." Neither the radiography source nor camera was in the trailer at the time of the theft. The following materials were in the trailer: overpack with "Caution Radioactive Materials" and "Radioactive Yellow II" labels, "Caution Radioactive Materials", "Caution Radiation Area", and "Caution High Radiation Area" signs, and yellow and magenta ropes and barricades.
The Raleigh NC police were notified on 3/9/04.
Power Reactor
Event Number: 40570
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JANET NOVAK
HQ OPS Officer: RICH LAURA
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JANET NOVAK
HQ OPS Officer: RICH LAURA
Notification Date: 03/06/2004
Notification Time: 02:02 [ET]
Event Date: 03/06/2004
Event Time: 00:50 [EST]
Last Update Date: 03/06/2004
Notification Time: 02:02 [ET]
Event Date: 03/06/2004
Event Time: 00:50 [EST]
Last Update Date: 03/06/2004
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):
MOHAMED SHANBAKY (R1)
MOHAMED SHANBAKY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP AT MILLSTONE 2 DUE TO SPURIOUS TRIP OF THE "B" FEED PUMP
The licensee reported that the "B" Steam Generator Feed Pump tripped unexpectedly and would not reset causing lowering steam generator water levels. Operators manually tripped the reactor and all control rods properly inserted. The auxiliary feed water (AFW) system automatically initiated to restore steam generator water levels. The lowest steam generator water level observed during the event was 55% level as opposed to the normal level of 70%. No primary relief valves lifted. Operators established decay heat removal capability using AFW system and the atmospheric steam dump valves. The licensee initiated a post trip review to determine the cause of the feed pump trip.
The NRC Resident inspector has been notified by the licensee.
The licensee reported that the "B" Steam Generator Feed Pump tripped unexpectedly and would not reset causing lowering steam generator water levels. Operators manually tripped the reactor and all control rods properly inserted. The auxiliary feed water (AFW) system automatically initiated to restore steam generator water levels. The lowest steam generator water level observed during the event was 55% level as opposed to the normal level of 70%. No primary relief valves lifted. Operators established decay heat removal capability using AFW system and the atmospheric steam dump valves. The licensee initiated a post trip review to determine the cause of the feed pump trip.
The NRC Resident inspector has been notified by the licensee.
Power Reactor
Event Number: 40571
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GRANT FERNSIER
HQ OPS Officer: RICH LAURA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GRANT FERNSIER
HQ OPS Officer: RICH LAURA
Notification Date: 03/06/2004
Notification Time: 08:20 [ET]
Event Date: 03/06/2004
Event Time: 05:28 [EST]
Last Update Date: 03/06/2004
Notification Time: 08:20 [ET]
Event Date: 03/06/2004
Event Time: 05:28 [EST]
Last Update Date: 03/06/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MOHAMED SHANBAKY (R1)
MOHAMED SHANBAKY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION AT SUSQUEHANNA INVOLVING A TRAFFIC ACCIDENT
"On 3/06/04 at 0528 Plant Security was notified of an accident at the entrance to the site involving an employee leaving work and a south bound vehicle on PA Route 11. There were no reported injuries. Local law enforcement was contacted and investigated the incident. Because of the involvement of a LLEA and potential media or general public interest in the event, the Pennsylvania Emergency Management Agency (PEMA) was notified of the incident at 0812 hours. Based on the notification to a government agency and possible public interest, this event was determined to be reportable under 10CFR50.72(b)(2)(xi)."
The NRC Resident Inspector was notified.
"On 3/06/04 at 0528 Plant Security was notified of an accident at the entrance to the site involving an employee leaving work and a south bound vehicle on PA Route 11. There were no reported injuries. Local law enforcement was contacted and investigated the incident. Because of the involvement of a LLEA and potential media or general public interest in the event, the Pennsylvania Emergency Management Agency (PEMA) was notified of the incident at 0812 hours. Based on the notification to a government agency and possible public interest, this event was determined to be reportable under 10CFR50.72(b)(2)(xi)."
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 40572
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: RICK HUBBARD
HQ OPS Officer: CHAUNCEY GOULD
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: RICK HUBBARD
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/07/2004
Notification Time: 00:14 [ET]
Event Date: 03/06/2004
Event Time: 21:47 [CST]
Last Update Date: 03/07/2004
Notification Time: 00:14 [ET]
Event Date: 03/06/2004
Event Time: 21:47 [CST]
Last Update Date: 03/07/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
GREG PICK (R4)
GREG PICK (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 98 | Power Operation |
PLANT HAD A LOSS OF POWER TO THE STARTUP TRANSFORMER AND THE "B" TRAIN 4.16KV ESFAS BUS.
On 03/06/2004 at 2147 CDT Wolf Creek Generating Station experienced a loss of the west bus in the switchyard causing a loss of power to the Startup Transformer and the "B" Train 4.16 KV ESFAS bus, NB02. The "B" Emergency Diesel Generator started and loaded, as expected, upon the loss of power from the Startup Transformer. All systems and equipment operated as expected for a loss of power to NB02. Reactor power was lowered by the control room staff following the expected start of the steam driven aux. feedwater pump to maintain reactor thermal power below license limits. The cause of the loss of power appears to be the failure of one of the 13.8 KV output bushings on the Startup Transformer. System Operations has dispatched a line crew to the Wolf Creek switchyard to investigate and initiate repair activities. System Operations has reported that all three (3) lines to Wolf Creek are energized and have proper voltage. The plant also entered a 72 hour LCO action statement due to the loss of the power source.
The licensee notified the NRC Resident Inspector.
*** Update on 03/07/04 at 1820 EST by Steve Gifford taken by MacKinnon ****
Licensee will have a contractor perform Doble Testing of Startup Transformer windings and also determine if the bushing has been damaged. Testing results should be known by midnight CST. Repair time will depend on test results. R4DO (Greg Peck) notified.
NRC Resident Inspector was notified of the update by the licensee.
On 03/06/2004 at 2147 CDT Wolf Creek Generating Station experienced a loss of the west bus in the switchyard causing a loss of power to the Startup Transformer and the "B" Train 4.16 KV ESFAS bus, NB02. The "B" Emergency Diesel Generator started and loaded, as expected, upon the loss of power from the Startup Transformer. All systems and equipment operated as expected for a loss of power to NB02. Reactor power was lowered by the control room staff following the expected start of the steam driven aux. feedwater pump to maintain reactor thermal power below license limits. The cause of the loss of power appears to be the failure of one of the 13.8 KV output bushings on the Startup Transformer. System Operations has dispatched a line crew to the Wolf Creek switchyard to investigate and initiate repair activities. System Operations has reported that all three (3) lines to Wolf Creek are energized and have proper voltage. The plant also entered a 72 hour LCO action statement due to the loss of the power source.
The licensee notified the NRC Resident Inspector.
*** Update on 03/07/04 at 1820 EST by Steve Gifford taken by MacKinnon ****
Licensee will have a contractor perform Doble Testing of Startup Transformer windings and also determine if the bushing has been damaged. Testing results should be known by midnight CST. Repair time will depend on test results. R4DO (Greg Peck) notified.
NRC Resident Inspector was notified of the update by the licensee.
Power Reactor
Event Number: 40573
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/07/2004
Notification Time: 04:06 [ET]
Event Date: 03/06/2004
Event Time: 22:10 [EST]
Last Update Date: 03/08/2004
Notification Time: 04:06 [ET]
Event Date: 03/06/2004
Event Time: 22:10 [EST]
Last Update Date: 03/08/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MOHAMED SHANBAKY (R1)
MOHAMED SHANBAKY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
SPDS WILL BE DE-ENERGIZED FOR MORE THAN 8 HOURS DUE TO REFUELING OUTAGE ACTIVITIES
"At 22:10 on March 6, 2004 the Unit 1 Safety Parameter Display System (SPDS) was deenergized during planned refuel outage activities. It has been determined that it will not be restored within the required eight hours. Currently, restoration is scheduled for March 7, 2004 at 17:00. All required instrumentation is available in the control room.
Since the Unit 1 SPDS computer system will be unavailable for greater than 8 hours, this is considered a Loss of Emergency Assessment Capability and therefore reportable under 10CFR50,72(b)(3)(xiii). Unit 1 is currently in Mode 5 for the planned 13th Refuel and Inspection Outage."
The licensee notified the NRC Resident Inspector
**** Update at 2219 EST on 03/07/04 by Gordon Robinson taken by MacKinnon ****
SPDS is still out of service and it will be restored to service by 0600 EST on 03/08/04. R1DO (M. Shanbaky) notified.
NRC Resident has be notified of the update by the licensee.
* * * UPDATE ON 03/09/04 @ 1122 BY GRANT FERNSLER TO C. GOULD* * *
As of 1117 the SPDS was energized and restored to service.
The NRC Resident Inspector was notified.
Reg 1 RDO(Cobey) was notified.
"At 22:10 on March 6, 2004 the Unit 1 Safety Parameter Display System (SPDS) was deenergized during planned refuel outage activities. It has been determined that it will not be restored within the required eight hours. Currently, restoration is scheduled for March 7, 2004 at 17:00. All required instrumentation is available in the control room.
Since the Unit 1 SPDS computer system will be unavailable for greater than 8 hours, this is considered a Loss of Emergency Assessment Capability and therefore reportable under 10CFR50,72(b)(3)(xiii). Unit 1 is currently in Mode 5 for the planned 13th Refuel and Inspection Outage."
The licensee notified the NRC Resident Inspector
**** Update at 2219 EST on 03/07/04 by Gordon Robinson taken by MacKinnon ****
SPDS is still out of service and it will be restored to service by 0600 EST on 03/08/04. R1DO (M. Shanbaky) notified.
NRC Resident has be notified of the update by the licensee.
* * * UPDATE ON 03/09/04 @ 1122 BY GRANT FERNSLER TO C. GOULD* * *
As of 1117 the SPDS was energized and restored to service.
The NRC Resident Inspector was notified.
Reg 1 RDO(Cobey) was notified.