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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/18/2005 - 05/19/2005
** EVENT NUMBERS **
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| General Information or Other |
Event Number: 41696 |
Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: ENBRIDGE PIPELINE LLC
Region: 3
City: SUPERIOR State: WI
County:
License #: 031-2006-01
Agreement: Y
Docket:
NRC Notified By: MIKE WELLING
HQ OPS Officer: WESLEY HELD |
Notification Date: 05/13/2005
Notification Time: 10:29 [ET]
Event Date: 05/12/2005
Event Time: [CDT]
Last Update Date: 05/13/2005 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
ANNE MARIE STONE (R3)
CHARLES COX (NMSS) |
Event Text
AGREEMENT STATE REPORT - NUCLEAR GAUGE FAILS TO FUNCTION AS DESIGNED
The State provided the following information via facsimile:
"The RSO contacted the DHFS, Radiation Protection Section on May 12, 2005 to report a damaged shutter on a fixed gauge at their facility. The gauge is a Berthold Model LB7400D containing 350 mCi of Cs-137, SN DW954A.
"The licensee discovered the problem when they were preparing to do some maintenance work on the gauge. The detector was giving erroneous readings. The licensee observed higher radiation levels (12 mR/hr on contact with the source holder) with the shutter in the 'closed' position than the 'open' position, (6 mR/hr on contact with the source holder.) The licensee assumed that the shutter had failed.
"Berthold has been contacted and will provide a service visit on May 17 or 18. The gauge is in the same configuration as in operations. Access is restricted by a fence around the area, including a lock with keypad entry. The inspector who recently visited the licensee confirms that access is restricted. The gauge is on Line 5 at the Superior Terminal, Enbridge Pipeline.
"The licensee will send the required report following the service visit." |
| General Information or Other |
Event Number: 41699 |
Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: ASHER ENGINEERING INC.
Region: 1
City: LOUISVILLE State: KY
County:
License #: 5634-07
Agreement: Y
Docket:
NRC Notified By: RICK HORKY
HQ OPS Officer: MARK ABRAMOVITZ |
Notification Date: 05/14/2005
Notification Time: 19:55 [ET]
Event Date: 05/13/2005
Event Time: 10:30 [CDT]
Last Update Date: 05/14/2005 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
JOHN KINNEMAN (R1)
THOMAS ESSIG (NMSS)
JIM WHITNEY (e-mail) (TAS) |
Event Text
AGREEMENT STATE - STOLEN MOISTURE DENSITY GAUGE
A CPN moisture density gauge fell off the back of the company pickup truck. The case was not secured to the truck, the case was not locked, and the gauge handle was not locked. The truck drove 40 miles to the next job site and the truck tailgate was found down and the gauge was discovered missing. Upon return to the original job site (Notting Hill development in Edgewood, KY), the case was found but the gauge was missing. The licensee contacted local law enforcement, the fire department and ambulances to help recover the gauge. A reward has been offered.
CPN Moisture Density Gauge model MC1DR, Serial #MD50402557
Sources: CS-137 10 milliCuries, Am-241:Be 50 milliCuries |
| Power Reactor |
Event Number: 41705 |
Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DEAN RAASCH
HQ OPS Officer: BILL GOTT |
Notification Date: 05/17/2005
Notification Time: 17:08 [ET]
Event Date: 05/17/2005
Event Time: 09:05 [CDT]
Last Update Date: 05/18/2005 |
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY |
Person (Organization):
CHRISTINE LIPA (R3) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
| 2 |
N |
N |
0 |
Refueling |
0 |
Refueling |
Event Text
FITNESS FOR DUTY
A non-licensed contract employee found a can of beer in his lunch box. The licensee's investigation determined that the introduction of alcohol into the Protected Area was not an intentional act. The contract employee's access was restored. The licensee notified the NRC Resident Inspector. Contact the Headquarters Operations Officer for additional details.
* * * UDATED ON 5/18/05 TO CORRECT UNIT 2 PLANT STATUS INFORMATION * * * |
| Power Reactor |
Event Number: 41706 |
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: ARNIE CRIBB
HQ OPS Officer: ARLON COSTA |
Notification Date: 05/18/2005
Notification Time: 09:27 [ET]
Event Date: 05/18/2005
Event Time: 01:54 [EDT]
Last Update Date: 05/18/2005 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION |
Person (Organization):
CHARLES R. OGLE (R2) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
N |
0 |
Cold Shutdown |
0 |
Cold Shutdown |
Event Text
LOSS OF BALANCE OF PLANT POWER DUE TO TRANSFORMERS LOCKOUT
"At 0154, 5/18/2005, during performance of relay testing, differential lockout 86T3 was manually actuated resulting in lockout of transformers XTF 31 and XTF 32. This resulted in a loss of all balance of plant (BOP) buses, loss of vital bus 1DB, an auto start of 'B' Diesel Generator (DG), and the sequencing of required ESF loads.
"At 0154, during relay testing, the 86T3 differential lockout was actuated. This resulted in a total isolation of XTF0031/32 which de-energized all of the BOP power to the plant and the XSW1 DB switchgear.
"Plant Engineered Safeguards Features (ESF) systems responded per design as the 'B' DG started and sequenced ESF loads. There were no major problems due to the event; however, the Diesel Fire Pump did not start as expected on a loss of BOP bus 1 C2.
"The Control Room entered AOP-304.3, 'Loss of All Balance of Plant Buses' and SOP-306, Section B, 'Operation of Diesel Generator 'B' After An Automatic Start And Load'.
"Preliminary review of plant response shows the RHR flow was in the process of coasting down and was restored to full flow within 20 seconds. The inlet temperature of the Residual Heat Removal (RHR) Heat Exchanger increased approximately 0.3 °F due to this event. There was no change in Reactor Coolant System level. V. C. Summer is currently shutdown in Mode 5 during Refueling Outage 15."
All plant systems are currently restored to normal configuration for Mode 5 refueling activities and there were no reported reactivity issues associated with this incident.
The licensee notified the NRC Resident Inspector and will notify the State, local and other government agencies. |
| Other Nuclear Material |
Event Number: 41710 |
Rep Org: PHYSICS ASSOCIATES
Licensee: PHYSICS ASSOCIATES
Region: 1
City: MONTVALE State: VA
County:
License #: 45-17344-01
Agreement: N
Docket:
NRC Notified By: JAMES NUNN
HQ OPS Officer: BILL HUFFMAN |
Notification Date: 05/18/2005
Notification Time: 14:48 [ET]
Event Date: 05/13/2005
Event Time: [EDT]
Last Update Date: 05/18/2005 |
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X |
Person (Organization):
RONALD BELLAMY (R1)
RICHARD CORREIA (NMSS) |
Event Text
RECOVERY OF STRONTIUM-90 SOURCE (APPROXIMATELY 4 MILLICURIES) FROM SCRAP YARD
Radioactive material was detected in scrap metal waste delivered to a scrap yard (Shredded Products, Montvale VA) on 5/13/05. The scrap yard notified the State of Virginia Department of Health. The State Department of Health, with the assistance of a contractor (Physics Associates) located the radioactive material. The radioactive material was a sealed source of Strontium-90 used in a thickness measuring gauge.
Identification marking on the Strontium-90 source indicate that it was a 10 millicurie source in 1967. Based on current radiation measurements, the source strength is estimated at about 4 millicuries. The source has been verified to be intact and not leaking and is safely in possession of Physics Associates (licensed to posses this material).
Region 1 (Ragland) provided additional information on the Sr-90 source based on information received from the State of Virginia. The gauge is believed to be a Model 32-19-001, Serial Number 384-41044, manufactured by Avionics Corporation. The origin of the scrap shipment is reported to be from a scrap yard in Salem, Virginia. |
| Other Nuclear Material |
Event Number: 41711 |
Rep Org: MISTRASS HOLDING GROUP
Licensee: MISTRASS HOLDING GROUP
Region: 1
City: PHILADELPHIA State: PA
County:
License #: 12-16559-02
Agreement: N
Docket:
NRC Notified By: SCOTT KVASNICKA
HQ OPS Officer: BILL HUFFMAN |
Notification Date: 05/18/2005
Notification Time: 15:15 [ET]
Event Date: 05/17/2005
Event Time: 16:30 [EDT]
Last Update Date: 05/18/2005 |
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2202(b)(2) - EXCESSIVE RELEASE |
Person (Organization):
RONALD BELLAMY (R1)
RICHARD CORREIA (NMSS)
CHRISTINE LIPA (R3) |
Event Text
LOSS OF CONTROL OF RADIOGRAPHY CAMERA
A radiography crew had completed activities at a location at the Sun Refinery in Philadelphia Pennsylvania at approximately 1630 EDT on 5/17/05. The radiography camera used by the crew was an AEA Model 660B, containing a 32 Curie Ir-192 source (serial number B3762). The source was safely retracted and locked in its shielded position in the camera. The radiographer believed that the camera was in the possession of the assistant radiographer. The assistant radiographer believed the camera was in the possession of the radiographer. The camera was actually left unattended on a scaffolding at the Sun Refinery job site. At 2040 EDT on 5/17/05, Sun Refinery personnel discovered the camera while preparing to remove scaffolding at the job site. The licensee was immediately contacted and recovered the camera. The licensee stated that there is no indication that anyone had disturbed or worked in the vicinity of the camera while it was unattended. |
| Hospital |
Event Number: 41712 |
Rep Org: BOONE HOSPITAL
Licensee: BOONE HOSPITAL
Region: 3
City: COLUMBIA State: MO
County:
License #: 24-01565-01
Agreement: N
Docket:
NRC Notified By: L. DOTSON
HQ OPS Officer: JOHN MacKINNON |
Notification Date: 05/18/2005
Notification Time: 16:21 [ET]
Event Date: 05/18/2005
Event Time: 11:30 [CDT]
Last Update Date: 05/18/2005 |
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X |
Person (Organization):
CHRISTINE LIPA (R3)
LARRY CAMPER (NMSS) |
Event Text
EIGHT IODINE-125 SEEDS LOST DOWN A SINK
Radiation Safety Officer for Boone Hospital located in Columbia, MO., reported the following event:
A pre-loaded cartridge containing 15 Iodine-125 seeds, activity of each seed is 0.31 millicuries, was sent to the sterilization room of the hospital. Upon arrival the person handling the pre-loaded cartridge, not familiar with handling the cartridge, unscrewed the cap to the cartridge and the 15 seeds inside the cartridge fell out. Some of the seeds went down the drain of the sink and the rest ended up inside a tray or on the counter around the sink. Seven of the Iodine-125 seeds were recovered. Eight of the seeds that went down the sink were not recovered. Radiation surveys were performed in the sterilization room and no other seeds were found. Total activity of the missing eight Iodine-125 seeds is 2.48 millicures.
The person opening the pre-loaded cartridge did not receive any dose according to the Radiation Safety Officer. |
| Other Nuclear Material |
Event Number: 41713 |
Rep Org: DEPT OF NAVY RADIATION SAFETY CMTE
Licensee: DEPT OF NAVY RADIATION SAFETY CMTE
Region: 1
City: CRYSTAL CITY State: VA
County:
License #: 45-93645-01NA
Agreement: N
Docket:
NRC Notified By: COMMANDER FRAGOSA
HQ OPS Officer: BILL HUFFMAN |
Notification Date: 05/18/2005
Notification Time: 17:31 [ET]
Event Date: 05/16/2005
Event Time: [EDT]
Last Update Date: 05/18/2005 |
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X |
Person (Organization):
RONALD BELLAMY (R1)
LARRY CAMPER (NMSS) |
Event Text
CHEMICAL AGENT DETECTORS MISSING FROM DEPARTMENT OF NAVY INVENTORY
A representative for the Navy's master materials license reported several chemical agent detectors missing based on the most recent inventory cycle. Specifically, 4 Chemical Agent Monitors (CAMs) are missing, with each CAM utilizing a 10 milliCurie Nickel-63 plated source (SSND# NR-1129-D-103-S) [40 millicuries of Ni-63 total]. In addition, 1 Automatic Chemical Agent Detector Alarm (ACADA) containing two 10 milliCurie Ni-63 plated sources (SSND# NR-1129-D-101-S) is also missing [20 millicuries of Ni-63 total]. These detectors have been reported missing from Marine Corp units deployed in Iraq. Details of the times, locations, and circumstances under which the detectors went missing are still under investigation by the Navy . |
| Power Reactor |
Event Number: 41714 |
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: SCOTT BAHNSEN
HQ OPS Officer: BILL HUFFMAN |
Notification Date: 05/18/2005
Notification Time: 19:27 [ET]
Event Date: 05/18/2005
Event Time: 18:50 [EDT]
Last Update Date: 05/18/2005 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION |
Person (Organization):
CHRISTINE LIPA (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
IDENTIFICATION OF DESIGN AND OPERATING PROCEDURE DEFICIENCIES RELATED TO APPENDIX R EVENTS
"During a review of the dedicated shutdown procedure (20.000.18), several possible design and operating procedure deficiencies were identified affecting Appendix R events. BOP Battery Charger 2C-1 is relied upon to feed post fire emergency shutdown loads. It was determined that although a circuit breaker supplying power to battery charger 2C-1 was re-closed by procedure, an additional action was required to place the battery charger in service. The BOP battery charger 2C-1 contactor circuit logic requires the control switch first be returned to the off-reset position, before the contactor can be re-energized. That control switch and associated control wiring is located in the control room envelope that is evacuated in an Appendix R fire scenario. Furthermore, the dedicated shutdown logic does not isolate this control switch circuitry from cables in the fire affected zone which is a requirement of the Appendix R circuit design.
"In addition to the same issues identified for battery charger 2C-1, it was determined that the dedicated shutdown procedure did not provide for closure of the circuit breaker feeding power to battery charger 2C1-2. Battery charger 2C1-2 is required to power 260VDC motor operated valves used by the standby feedwater system to provide reactor cooling water and to control reactor water level after a shutdown due to an Appendix R fire. For both of these problems, power would be initially supplied by the associated batteries, but the batteries are not sized to provide power for the entire duration of the Appendix-R event. Therefore, when the plant must be shutdown from outside of the control room, a safe shutdown cannot be assured using the dedicated shutdown panel. This event is being reported as an unanalyzed condition under 50.72(b)(3)(ii)(B).
"The affected Appendix R equipment was declared inoperable, and procedure changes to address this issue are being considered to address these conditions. The NRC Resident Inspector has been notified." |
| Power Reactor |
Event Number: 41715 |
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JAMES HURCHALLA
HQ OPS Officer: ARLON COSTA |
Notification Date: 05/19/2005
Notification Time: 04:37 [ET]
Event Date: 05/18/2005
Event Time: 20:59 [EDT]
Last Update Date: 05/19/2005 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION |
Person (Organization):
CHARLES R. OGLE (R2) |
| 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
INADVERTENT DE-ENERGIZATION OF 4160 V SAFETY RELATED A.C. BUS WITH EDG AUTO START
"On 5/18/05 at 20:59 the 1A3 4160 V safety related A.C. bus inadvertently de-energized and the 1A Emergency Diesel Generator [EDG] automatically started and loaded onto the bus. The inadvertent de-energization of the 1A3 4160 V bus appears to have resulted from testing of the 4160 V undervoltage relays. Currently, normal power has been restored to the 1A3 4160 V bus and the 1A Emergency Diesel Generator has been secured.
"This notification is being made pursuant to 10 CFR 50.72(b)(3)(iv)(A) to be completed within 8 hours as a safety systems actuation of the 1A3 4160 V undervoltage relaying and inadvertent start and load of the 1A Emergency Diesel Generator."
The licensee notified the NRC Resident Inspector. |
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