Event Notification Report for March 20, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/19/2002 - 03/20/2002
Other Nuclear Material
Event Number: 38787
Rep Org: U.S. AIR FORCE
Licensee: U.S. AIR FORCE
Region: 1
City: OTIS AFB State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: RAM BHAT
HQ OPS Officer: RICH LAURA
Licensee: U.S. AIR FORCE
Region: 1
City: OTIS AFB State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: RAM BHAT
HQ OPS Officer: RICH LAURA
Notification Date: 03/20/2002
Notification Time: 11:22 [ET]
Event Date: 03/20/2002
Event Time: 00:00 [EST]
Last Update Date: 03/20/2002
Notification Time: 11:22 [ET]
Event Date: 03/20/2002
Event Time: 00:00 [EST]
Last Update Date: 03/20/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RICHARD CONTE (R1)
DALE POWERS (R4)
LARRY CAMPER (NMSS)
RICHARD CONTE (R1)
DALE POWERS (R4)
LARRY CAMPER (NMSS)
REPORT FROM AIR FORCE ON CHEMICAL AGENT DETECTOR FOUND IN BRIDGEWATER, MA.
The U.S. Air Force Headquarters reported that children playing in the woods in West Bridgewater, MA found a chemical agent detector. The detector was turned over to the local fire department and then passed on to the Otis Air Force. The device was sealed and contains 250 microcuries of Americium 241. The serial number of the device is 203D-31535 and is from lot number DDD086E00.133.
The U.S. Air Force Headquarters reported that children playing in the woods in West Bridgewater, MA found a chemical agent detector. The detector was turned over to the local fire department and then passed on to the Otis Air Force. The device was sealed and contains 250 microcuries of Americium 241. The serial number of the device is 203D-31535 and is from lot number DDD086E00.133.
Power Reactor
Event Number: 38788
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MARK FELTNER
HQ OPS Officer: GERRY WAIG
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MARK FELTNER
HQ OPS Officer: GERRY WAIG
Notification Date: 03/20/2002
Notification Time: 14:27 [ET]
Event Date: 03/20/2002
Event Time: 12:30 [CST]
Last Update Date: 03/20/2002
Notification Time: 14:27 [ET]
Event Date: 03/20/2002
Event Time: 12:30 [CST]
Last Update Date: 03/20/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DALE POWERS (R4)
DALE POWERS (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
EMERGENCY DIESEL GENERATOR TURBOCHARGER FIRE
While operating the Division 1 emergency diesel generator (EDG) for monthly surveillance testing, an operator noticed a small fire in the vicinity of the turbocharger. The EDG was immediately (manually) unloaded and secured. The fire was reported to be out in less than one minute of the initial report. The affected EDG had been at full load for approximately 35 minutes at the time of the event. No personnel were injured as a result of this event. Offsite fire department assistance was NOT requested. The diesel has been declared inoperable and the station has entered the applicable technical specification LCO. The back-up EDG is available. Further inspection and investigation of the EDG fire is being conducted at this time.
The licensee has notified the NRC Resident Inspector.
While operating the Division 1 emergency diesel generator (EDG) for monthly surveillance testing, an operator noticed a small fire in the vicinity of the turbocharger. The EDG was immediately (manually) unloaded and secured. The fire was reported to be out in less than one minute of the initial report. The affected EDG had been at full load for approximately 35 minutes at the time of the event. No personnel were injured as a result of this event. Offsite fire department assistance was NOT requested. The diesel has been declared inoperable and the station has entered the applicable technical specification LCO. The back-up EDG is available. Further inspection and investigation of the EDG fire is being conducted at this time.
The licensee has notified the NRC Resident Inspector.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 38790
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PETER A. GARDNER
HQ OPS Officer: GERRY WAIG
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PETER A. GARDNER
HQ OPS Officer: GERRY WAIG
Notification Date: 03/20/2002
Notification Time: 22:56 [ET]
Event Date: 03/20/2002
Event Time: 15:43 [EST]
Last Update Date: 04/03/2002
Notification Time: 22:56 [ET]
Event Date: 03/20/2002
Event Time: 15:43 [EST]
Last Update Date: 04/03/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RICHARD CONTE (R1)
RICHARD CONTE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 2 | Startup | 2 | Startup |
UNIT-1 HPCI SYSTEM FAILED TO MEET REQUIRED RESPONSE TIME DURING SURVEILLANCE TESTING
"On 3/20/02 at 15:43 the Unit-1 HPCI system failed to meet required system response time during surveillance testing. Testing was being performed to establish HPCI operability during reactor startup with reactor steam dome pressure at 204 psig. The HPCI system failed to achieve rated system flow within the required time from system initiation. Troubleshooting is currently in progress and a determination is underway to determine if this problem was related to maintenance activities performed during the refueling outage.
"This report is being made in pursuant to 10CFR50.72(b)(3)(v)(D) for failure of a single train accident mitigation system."
The licensee notified the NRC Resident Inspector.
***UPDATE (EVENT RETRACTION) 4/3/02 at 1533 from Stan Gamble to Rich Laura***
"This is a retraction of the event notification made on 3/20/02 at 22:56 hours. This event (#38790) was initially reported as a safety system functional failure under the requirement of 10CFR50.72(b)(3)(v)(D). Unit 1 High Pressure Coolant Injection (HPCI) failed to meet the required system maximum response time during surveillance testing. Testing was being performed during reactor startup with reactor steam dome pressure at 204 psig.
"Rated flow was not achieved within the 59-second maximum response time specified in the test due to motor operated valve (MOV) and flow controller manipulations performed during the unsatisfactory testing. The test was re-performed successfully and the system was declared operable on 2/21/02 at 02:15 hours. System repair was not required.
"The system response was verified to be as designed considering the test conditions. A condition did not exist at the time of discovery that could have prevented the fulfillment of the safety function."
Notified R1DO (G. Meyer)
"On 3/20/02 at 15:43 the Unit-1 HPCI system failed to meet required system response time during surveillance testing. Testing was being performed to establish HPCI operability during reactor startup with reactor steam dome pressure at 204 psig. The HPCI system failed to achieve rated system flow within the required time from system initiation. Troubleshooting is currently in progress and a determination is underway to determine if this problem was related to maintenance activities performed during the refueling outage.
"This report is being made in pursuant to 10CFR50.72(b)(3)(v)(D) for failure of a single train accident mitigation system."
The licensee notified the NRC Resident Inspector.
***UPDATE (EVENT RETRACTION) 4/3/02 at 1533 from Stan Gamble to Rich Laura***
"This is a retraction of the event notification made on 3/20/02 at 22:56 hours. This event (#38790) was initially reported as a safety system functional failure under the requirement of 10CFR50.72(b)(3)(v)(D). Unit 1 High Pressure Coolant Injection (HPCI) failed to meet the required system maximum response time during surveillance testing. Testing was being performed during reactor startup with reactor steam dome pressure at 204 psig.
"Rated flow was not achieved within the 59-second maximum response time specified in the test due to motor operated valve (MOV) and flow controller manipulations performed during the unsatisfactory testing. The test was re-performed successfully and the system was declared operable on 2/21/02 at 02:15 hours. System repair was not required.
"The system response was verified to be as designed considering the test conditions. A condition did not exist at the time of discovery that could have prevented the fulfillment of the safety function."
Notified R1DO (G. Meyer)