Event Notification Report for March 27, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/26/2004 - 03/27/2004
Other Nuclear Material
Event Number: 40614
Rep Org: CONNECTICUT DEPT. OF RAD. PROT.
Licensee: CONNECTICUT DEPT. OF RAD. PROT.
Region: 1
City: EAST LYME State: CT
County:
License #:
Agreement: N
Docket:
NRC Notified By: MIKE FIRSICK
HQ OPS Officer: RICH LAURA
Licensee: CONNECTICUT DEPT. OF RAD. PROT.
Region: 1
City: EAST LYME State: CT
County:
License #:
Agreement: N
Docket:
NRC Notified By: MIKE FIRSICK
HQ OPS Officer: RICH LAURA
Notification Date: 03/27/2004
Notification Time: 21:22 [ET]
Event Date: 03/27/2004
Event Time: 20:00 [EST]
Last Update Date: 05/07/2004
Notification Time: 21:22 [ET]
Event Date: 03/27/2004
Event Time: 20:00 [EST]
Last Update Date: 05/07/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RONALD BELLAMY (R1)
PATRICIA HOLAHAN (NMSS)
AARAN DANIS (NSIR)
RONALD BELLAMY (R1)
PATRICIA HOLAHAN (NMSS)
AARAN DANIS (NSIR)
STATE OF CONNECTICUT REPORTED THE DISCOVERY OF A STRONTIUM-90 SOURCE
The item was found adjacent to a house in a wooded area in East Lyme, CT. It was a cylinder measuring 6 inches in length and 2 inches in diameter. The bottom of the cylinder had the following serial number: M2477. It was a general licensed strontium-90 source. The source was contained inside a metal box with a radioactive material symbol on the outside. The State response personnel conducted a radiological survey. The source read 250 millirem per hour on contact for gamma. The source read 3.2 rem per hour on contact for beta. At 12 inches, the source measured 5 millirem per hour. At one meter the source measured less than 1 millirem per hour. The State took the source to a secure locked location for followup on Monday to try to determine the owner.
* * * UPDATE 0900 ON 3/29/04 MOSS (NMSS) TO GOTT * * *
The item was identified as a component to a helicopter In-flight Blade Inspection System. Notified Mark Evetts at the Homeland Security Operations Center.
* * * UPDATE 1120 ON 05/07/04 USNA Capt. Dave Farrand TO John MacKinnon * * *
U.S. NRC, Region I (Mr. Jim Schmidt) informed the U. S. Navy (NAVSEADET RASO) on March 31, 2004 that an IBIS device (serial number 2397) containing 500 microCi of Sr-90 was found on private property in East Lyme, Connecticut, on March 28, 2004. The NRC also informed the Navy that the IBIS device was confiscated by the State of Connecticut, and placed in safe and secure storage.
Early results of NRC inquiries pointed to the U.S. Navy as the probable owner of the IBIS device. A preliminary investigation by the Navy has found that the these devices are routinely returned to the manufacturer (General Nucleonics) for refurbishing, where they may be resold, through the Defense Logistic Agency to the Navy, the Marine Corp, the Army, or the Coast Guard. The Navy's preliminary investigation also found that these devices are also used on some commercial aircraft. The Navy's preliminary investigation verified that the Navy possessed the device until at least 1989, but found no conclusive data or documentation to show that the device was returned to the manufacturer after that time. Therefore, the Navy has accepted responsibility for the device.
The Navy's preliminary investigation was unable to determine how the IBIS device came to be located on private property.
The Navy has contacted the State of Connecticut, and has initiated actions to retrieve the device for proper disposal or facilitate its return to the manufacturer.
The Navy will follow-up with a 30 day report as required by 10 CFR 20.2201. United States Navy General Radioactive Material license number is 45-23645-01NA.
R1DO (Della Greca) & NMSS (Roberto Torres) notified.
The item was found adjacent to a house in a wooded area in East Lyme, CT. It was a cylinder measuring 6 inches in length and 2 inches in diameter. The bottom of the cylinder had the following serial number: M2477. It was a general licensed strontium-90 source. The source was contained inside a metal box with a radioactive material symbol on the outside. The State response personnel conducted a radiological survey. The source read 250 millirem per hour on contact for gamma. The source read 3.2 rem per hour on contact for beta. At 12 inches, the source measured 5 millirem per hour. At one meter the source measured less than 1 millirem per hour. The State took the source to a secure locked location for followup on Monday to try to determine the owner.
* * * UPDATE 0900 ON 3/29/04 MOSS (NMSS) TO GOTT * * *
The item was identified as a component to a helicopter In-flight Blade Inspection System. Notified Mark Evetts at the Homeland Security Operations Center.
* * * UPDATE 1120 ON 05/07/04 USNA Capt. Dave Farrand TO John MacKinnon * * *
U.S. NRC, Region I (Mr. Jim Schmidt) informed the U. S. Navy (NAVSEADET RASO) on March 31, 2004 that an IBIS device (serial number 2397) containing 500 microCi of Sr-90 was found on private property in East Lyme, Connecticut, on March 28, 2004. The NRC also informed the Navy that the IBIS device was confiscated by the State of Connecticut, and placed in safe and secure storage.
Early results of NRC inquiries pointed to the U.S. Navy as the probable owner of the IBIS device. A preliminary investigation by the Navy has found that the these devices are routinely returned to the manufacturer (General Nucleonics) for refurbishing, where they may be resold, through the Defense Logistic Agency to the Navy, the Marine Corp, the Army, or the Coast Guard. The Navy's preliminary investigation also found that these devices are also used on some commercial aircraft. The Navy's preliminary investigation verified that the Navy possessed the device until at least 1989, but found no conclusive data or documentation to show that the device was returned to the manufacturer after that time. Therefore, the Navy has accepted responsibility for the device.
The Navy's preliminary investigation was unable to determine how the IBIS device came to be located on private property.
The Navy has contacted the State of Connecticut, and has initiated actions to retrieve the device for proper disposal or facilitate its return to the manufacturer.
The Navy will follow-up with a 30 day report as required by 10 CFR 20.2201. United States Navy General Radioactive Material license number is 45-23645-01NA.
R1DO (Della Greca) & NMSS (Roberto Torres) notified.
Power Reactor
Event Number: 40615
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT DORMAN
HQ OPS Officer: BILL GOTT
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT DORMAN
HQ OPS Officer: BILL GOTT
Notification Date: 03/28/2004
Notification Time: 00:30 [ET]
Event Date: 03/27/2004
Event Time: 22:05 [EST]
Last Update Date: 03/28/2004
Notification Time: 00:30 [ET]
Event Date: 03/27/2004
Event Time: 22:05 [EST]
Last Update Date: 03/28/2004
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):
RUDOLPH BERNHARD (R2)
RUDOLPH BERNHARD (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 35 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO LOSS OF FEEDWATER PUMP SPEED CONTROL
"On 3/27/2004, the Unit 1 Reactor was manually tripped when the 1B Main Feedwater Pump speed could not be controlled in automatic or manual. An unexpected increase in Main Feedwater Pump speed was observed which increased the Main Feedwater header pressure to higher than expected values. An attempt was made to manually control the speed of the 1B Main Feedwater Pump from the various controllers in the Main Control Room. Preparations to start the 1A Main Feedwater Pump were initiated. The speed of the 1B Main Feedwater Pump continued to increase to a point where level control of the Steam Generators and overspeed of the 1B Main Feedwater Pump became a concern. At this point the Reactor was manually tripped and the 1B Main Feedwater Pump was tripped. An Auxiliary Feedwater System automatic actuation occurred on the trip a the 1B Main Feedwater Pump as expected because the 1A Main Feedwater Pump was also tripped at the time due to being at a low power level. All systems responded as expected on the Reactor Trip. The plant is currently stable in Mode 3. An Event Review Team will be performing a review of the event and making recommendations related to restarting the Reactor."
All control rods fully inserted. Decay heat is being removed using the steam dumps and auxiliary feedwater. Plant pressure is 2235 psig and temperature is 557 degrees F.
The licensee notified the NRC Resident Inspector.
"On 3/27/2004, the Unit 1 Reactor was manually tripped when the 1B Main Feedwater Pump speed could not be controlled in automatic or manual. An unexpected increase in Main Feedwater Pump speed was observed which increased the Main Feedwater header pressure to higher than expected values. An attempt was made to manually control the speed of the 1B Main Feedwater Pump from the various controllers in the Main Control Room. Preparations to start the 1A Main Feedwater Pump were initiated. The speed of the 1B Main Feedwater Pump continued to increase to a point where level control of the Steam Generators and overspeed of the 1B Main Feedwater Pump became a concern. At this point the Reactor was manually tripped and the 1B Main Feedwater Pump was tripped. An Auxiliary Feedwater System automatic actuation occurred on the trip a the 1B Main Feedwater Pump as expected because the 1A Main Feedwater Pump was also tripped at the time due to being at a low power level. All systems responded as expected on the Reactor Trip. The plant is currently stable in Mode 3. An Event Review Team will be performing a review of the event and making recommendations related to restarting the Reactor."
All control rods fully inserted. Decay heat is being removed using the steam dumps and auxiliary feedwater. Plant pressure is 2235 psig and temperature is 557 degrees F.
The licensee notified the NRC Resident Inspector.