| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/22/2005 - 12/23/2005 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 42217 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN RYAN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 12/22/2005
Notification Time: 03:20 [ET]
Event Date: 12/22/2005
Event Time: 02:08 [EST]
Last Update Date: 12/22/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
BRIAN MCDERMOTT (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 67 | Power Operation | 58 | Power Operation | Event Text AFW START DURING MAIN FEEDWATER PUMP TRIP
"While performing a plant shutdown due to a packing leak on #24 Feedwater Regulating Valve on 12/22/05 at 0208 at about 67% power, #22 MBFP tripped while swapping lube oil coolers. #21 and #23 motor driven auxiliary feedwater pumps auto started. All systems responded properly. Entered appropriate abnormal operating procedure (2-AOP-FW-1, Loss of Main Feedwater). Reduced power to within the capacity of one MBFP and established conditions to shutdown and realign #21 and #23 ABFPs to Auto. On 12/22/05 at 0218, #21 and #23 ABFPs were shutdown and aligned for automatic operation."
The licensee notified the NRC Resident Inspector. |
| Hospital | Event Number: 42218 | Rep Org: PHYSICS ASSOCIATES
Licensee: SOUTHSIDE COMMUNITY HOSPITAL
Region: 1
City: FARMVILLE State: VA
County:
License #: 45-19782-01
Agreement: N
Docket:
NRC Notified By: LEE ANTHONY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 12/22/2005
Notification Time: 10:04 [ET]
Event Date: 12/01/2005
Event Time: [EST]
Last Update Date: 12/22/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
BRIAN MCDERMOTT (R1)
GREG MORELL (NMSS)
LANCE ENGLISH (TAS)
| Event Text IMPROPER DISPOSAL OF I-131 CAPSULES
On 12/01/2005, a technician at Southside Community Hospital in Farmville, VA disposed of six vials that had contained I-131. At least one patient had not received therapy that day and the vials contained at least two capsules of Iodine. On 12/08/2005, Stericycle Disposal in Baltimore, MD informed the hospital of radioactive material in two of their sharps disposal boxes. On 12/13/2005, RSO Inc. measured the radiation level on the sharps boxes of 50 mR/hr and 60 mR/hr. On 12/19/2005, RSO Inc. delivered the sharps boxes back to the hospital and the sharps radiation level was 10 mR/r and 15 mR/hr. On 12/21/2005 the vials were retrieved from the sharps boxes and the total activity was 479 microCuries.
An estimate of the dose received by the drivers was performed assuming the packages were one meter from the driver. The total dose received on 12/01/2005 was less than eight milliRem.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. |
| Power Reactor | Event Number: 42219 | Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: KELLY ROBINSON
HQ OPS Officer: JEFF ROTTON | Notification Date: 12/22/2005
Notification Time: 10:20 [ET]
Event Date: 12/22/2005
Event Time: 09:03 [EST]
Last Update Date: 12/22/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
BRIAN MCDERMOTT (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text HPCI DECLARED INOPERABLE
"The HPCI flow control current loop was found degraded in such a manner that HPCI would not perform its intended function. HPCI was declared inoperable per TS 3.5.E.2 (14 day LCO). Repair efforts have been initiated."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42220 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: DON CROULET
HQ OPS Officer: BILL HUFFMAN | Notification Date: 12/22/2005
Notification Time: 12:08 [ET]
Event Date: 12/22/2005
Event Time: 05:50 [EST]
Last Update Date: 12/22/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
BRIAN MCDERMOTT (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 5 | Startup | 5 | Startup | Event Text VALID ACTUATION SIGNAL DUE TO HIGH STEAM GENERATOR WATER LEVEL
"While performing a plant shutdown due to a packing leak on #24 Feedwater Regulating Valve [see event #42217] on December 22, 2005 at 0550 hours, Indian Point Unit 2 received a 22 Steam Generator Water High-High Level signal at 73% narrow range level. This resulted in tripping the standby 21 Main Boiler Feed Pump which then resulted in a start signal being sent to both motor driven Auxiliary Feedwater Pumps. Both of the motor driven Auxiliary Feedwater Pumps were already operating and feeding the steam generators when this start signal was received. Operators restored 22 Steam Generator Level to normal. All systems responded properly."
The licensee will notify the NRC Resident Inspector. |
| Other Nuclear Material | Event Number: 42221 | Rep Org: McDOWELL AND ASSOCIATES
Licensee: McDOWELL AND ASSICIATES
Region: 3
City: FERNDALE State: MI
County:
License #: 21-18724-01
Agreement: N
Docket:
NRC Notified By: JOHN KALISZ
HQ OPS Officer: ARLON COSTA | Notification Date: 12/22/2005
Notification Time: 14:10 [ET]
Event Date: 12/21/2005
Event Time: [EST]
Last Update Date: 12/22/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
HIRONORI PETERSON (R3)
GREG MORELL (NMSS)
JIM WHITNEY (email) (TAS)
| Event Text STOLEN TROXLER MOISTURE DENSITY GAUGE
A licensee's employee had his 1988 Cadillac Brougham stolen while it was parked in front of his house in Westland, MI and a Troxler moisture density gauge was inside the vehicle (Model 3440, S/N 13815, containing 8 millicuries of Cs-137 and 40 millicuries of Am-241:Be). The gauge was locked in its wired down casing. The vehicle was stolen sometime between 1900 and 0400 hours on 12/21/05 and 12/22/05 respectively. The licensee contacted NRC Region III, the Westland Police (report No.0542989) and the State Police who subsequently contacted the State Homeland Security.
* * * UPDATE AT 1705 ON 12/22/05 FROM J. KALISZ TO A. COSTA * * *
The licensee reported that the automobile was taken away at the owner's location by a car repossession company. The gauge and its case were intact inside the car and have been recovered by the licensee.
Notified R3 DO (Peterson), NMSS EO (Camper) and TAS (email).
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. |
| Power Reactor | Event Number: 42222 | Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: TIM SCHENK
HQ OPS Officer: ARLON COSTA | Notification Date: 12/22/2005
Notification Time: 15:03 [ET]
Event Date: 12/22/2005
Event Time: 06:25 [CST]
Last Update Date: 12/22/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
| Person (Organization):
MARK SHAFFER (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 | Event Text FITNESS FOR DUTY
A licensed supervisor had a confirmed positive for alcohol during a "for cause" fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42224 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MICHAEL HIMEBAUCH
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 12/23/2005
Notification Time: 02:22 [ET]
Event Date: 12/22/2005
Event Time: 22:25 [EST]
Last Update Date: 12/23/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
HIRONORI PETERSON (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text EECW TEMPERATURE CONTROL VALVE NOT FULLY OPEN
"While performing Div. 1 & 2 Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) Valve Lineup Verification surveillance on 12/22/05, the temperature control valve (TCV) on both divisions of EECW were found to be approximately 95% open rather than their required full open position. The system design requires that the TCV, or the associated TCV bypass valve, be in the full open position during system startup to avoid a potentially damaging pressure transient from occurring. Both divisions of EECW and all supported systems (including HPCl, both divisions Core Spray, and both divisions of RHR) were declared INOPERABLE at 2225 EST. Multiple LCO Required Actions were entered, including entry into LCO 3.0.3. At 2250 EST, Div. 1 EECW was restored to OPERABLE status by fully opening the TCV bypass valve and isolating the TCV, and LCO 3.0.3 was exited. At 2252 EST, Div. 2 EECW was restored to OPERABLE status by fully opening the TCV bypass valve and isolating the TCV, and all associated LCO Required Actions were exited. Reactor power remained at 100% throughout the event. The NRC resident inspector has been notified. This report is being made pursuant to 10CFR50.72(b)(3)(ii)(B) as an unanalyzed condition and 10CFR50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of a safety function needed to mitigate the consequences of an accident."
The licensee is investigating the cause of the valve not being fully open. | |