| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/17/2009 - 04/20/2009 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 44847 | Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: NUCOR STEEL COMPANY
Region: 4
City: ARMOREL State: AR
County:
License #: ARK-078603120
Agreement: Y
Docket:
NRC Notified By: KATIA GRAY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/12/2009
Notification Time: 11:41 [ET]
Event Date: 01/20/2009
Event Time: [CST]
Last Update Date: 04/17/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GEOFFREY MILLER (R4)
ANGELA McINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - SOURCE SHUTTER STUCK OPEN
The following report was received from the state via e-mail:
"Nucor Steel Company informed the [Arkansas] Department [of Health] that they had a stuck shutter on one of their caster sources. The licensee utilized a lifting mechanism that allowed the technicians to lift and move the source without being near the source. The source and source holder were placed in an appropriate container and surveys were performed. The highest reading on the storage container with the shutter open at contact was 120 MicroR/hour.
"The storage container was relocated to a remote area on the casting deck and surveys were performed. A source service provider was contacted and arrived on site the next day to evaluate the problem.
"Source: Berthold Model LB 300 MLT, Serial number 730-4-97, 36 mCi of Co-60 used for mold level control.
"On 02/12/2009, at 10:01 AM the licensee provided the Department with a more detailed description of the steps taken by the technicians during the event, storage of the source, exposure reading at the source, and security of the source at this time. The licensee is currently awaiting feedback from the gauge service provider.
"The Department will leave this report open pending receipt of a final written report from the licensee, due in 30 days."
Arkansas Report: 09-02-01
* * * UPDATE FROM ROBERT PEMBERTON (VIA EMAIL) TO HOWIE CROUCH ON 4/17/09 @ 1119 EDT * * *
"The following are the findings of Arkansas Department of Health [ADH], Radioactive Materials Program, concerning event Number 44847 at NUCOR Steel in Armorel, AR. From information provided by NUCOR Steel and JENDCO Corporation, the Department [ADH] has determined this event was caused by a small metal chip that interfered with the rotation of the shutter. The Department has concluded that the root cause of this incident is mechanical failure. The Department considers this incident to be closed."
Notified FSME (Flannery) and R4DO (Whitten). |
| General Information or Other | Event Number: 44987 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: GLOBAL LABORATORIES
Region: 4
City: WEST MONROE State: LA
County:
License #: LA-7211-L01A
Agreement: Y
Docket:
NRC Notified By: ANN TROXLER
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/14/2009
Notification Time: 12:20 [ET]
Event Date: 04/13/2009
Event Time: [CDT]
Last Update Date: 04/17/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JACK WHITTEN (R4)
ANGELA MCINTOSH (FSME)
ILTAB email ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - THEFT OF A TROXLER NUCLEAR GAUGE
State submitted this report via email:
"The owner of Global Laboratories, called the Louisiana Department of Environmental Quality on April 14, 2009 to report the theft of a work truck that had a Troxler Nuclear Gauge chained in the back of the truck. The Troxler Gauge 3440 (s/n 27805) contained 40 mCi of Am-241 (s/n 47-24434) and 8 mCi of Cs-137 (s/n 750-1721). According to Mr. Kent, the gauge was locked in the case and the case was doubled chained in the bed of the truck. Mr. Kent reported the theft to the West Monroe Police Department on April 13. 2009 at approximately 3:30PM and also contacted the Ouachita Sheriffs Office. Mr. Kent is offering a $500.00 reward for the return of the Troxler Nuclear Gauge. An investigation is ongoing and any further information will be forwarded to the NRC."
Transport vehicle description: White 2000 GMC Z71 license plate number B412958
Event Report ID No. LA090012
* * * UPDATE FROM SCOTT BLACKWELL TO HOWIE CROUCH ON 4/17/09 @ 1512 EDT * * *
The State of Louisiana reports that the stolen work truck has been recovered but the gauge is still missing. Law enforcement agencies continue to investigate.
Notified R4DO (Whitten), FSME (Einberg) and ILTAB via 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. |
| General Information or Other | Event Number: 44990 | Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: ENERGY SOLUTIONS, LLC
Region: 4
City: HELPER State: UT
County:
License #: UT 2300249
Agreement: Y
Docket:
NRC Notified By: JULE FAUSTO
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/14/2009
Notification Time: 15:40 [ET]
Event Date: 03/31/2009
Event Time: 16:45 [MDT]
Last Update Date: 04/14/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JACK WHITTEN (R4)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - LEAKING TANK TRAILER WITH TOTAL ACTIVITY OF VARIOUS RADIONUCLIDES OF 20 MILLICURIES
The State submitted the following report via fax:
"This event involved a leaking Tank Trailer containing a total activity of radionuclides of 742.88 MBq (20 mCi), primarily of H-3 (738 MBq) and Tc-99 (3.88 MBq). Small contribution from U-233, U234, U235, U236 and U238. The licensee filled the tank trailer and classed the material as an RQ, of UN 1992, Waste, Flammable Liquids, toxic, nos., (n-butyl alcohol, penol), 3 (6.1), PGIII, Marine Pollutant, (PCB's benzene).
"Tank Trailer number E-112178, total gross weight of 46,765 pounds of flammable liquids, toxic, nos, with radioactive condensate.
"This incident is still under investigation, a written report is pending."
Event Report ID No: UT 090003 |
| Power Reactor | Event Number: 44995 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DARON ZAKARIAN
HQ OPS Officer: VINCE KLCO | Notification Date: 04/17/2009
Notification Time: 09:22 [ET]
Event Date: 04/17/2009
Event Time: 02:07 [EDT]
Last Update Date: 04/17/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RAY POWELL (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text PLANNED MAINTENANCE ON SPDS AND ERDS
"At 0207 hours on 04/17/2009, the SPDS [Safety Parameter Display System] and ERDS [Emergency Response Data System] was removed from service to support activities for a planned maintenance outage on the UPS power supply. The duration of work is expected to be approximately 48 hours. During this time, Control Room indications and alternate methods will be available. Since the SPDS computer system will be unavailable for greater than 8 hours, this is considered a Loss of Emergency Assessment Capability and reportable under 10CFR50.72(b)(3)(xiii).
"The plant is in Op. Con. 5 [Refueling], Reactor Coolant Temperature is 87 [degrees] F and 'A' RHR is in shutdown cooling.
"The licensee will notify the NRC Resident Inspector." |
| Power Reactor | Event Number: 44996 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: DAVID EICHENBERGER
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/17/2009
Notification Time: 18:07 [ET]
Event Date: 04/17/2009
Event Time: 11:00 [CDT]
Last Update Date: 04/17/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
JACK WHITTEN (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text FITNESS FOR DUTY INVOLVING A NON-LICENSED SUPERVISOR
A non-licensed employee supervisor had a confirmed positive for alcohol during a random 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. |
| Fuel Cycle Facility | Event Number: 44997 | Facility: AREVA NP INC RICHLAND
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION
FABRICATION & SCRAP
COMMERCIAL LWR FUEL
Region: 2
City: RICHLAND State: WA
County: PENTON
License #: SNM-1227
Agreement: Y
Docket: 07001257
NRC Notified By: ROBERT LINK
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/17/2009
Notification Time: 18:44 [ET]
Event Date: 04/16/2009
Event Time: 16:00 [PDT]
Last Update Date: 04/17/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION
| Person (Organization):
MALCOLM WIDMANN (R2)
LAWRENCE KOKAJKO (NMSS)
| Event Text UNANALYZED CONDITION DUE TO POSSIBLE UNFAVORABLE GEOMETRY
"During a routine NRC inspection, the inspector questioned the adequacy of a 5-gallon limit on liquids allowed in certain process areas to prevent accidental nuclear criticality if the other controls in place are missing.
"While further investigation is underway, this event is being reported per 10CFR70 Appendix (b)(1) on a conservative basis.
"SAFETY SIGNIFICANCE: The safety significance is low
"POTENTIAL CRITICALITY PATHWAYS: Liquid from 5-gallon container would have to spill and all enter normally closed equipment, or uranium dioxide powder spilled from the equipment.
"CONTROLLED PARAMETERS: Controlled parameters are moderation
"CORRECTIVE ACTIONS: A prohibition of spillable liquids exceeding 3-gallons was established in the affected areas."
The licensee will be notifying the NRC Region 2 Senior Inspector. |
| Power Reactor | Event Number: 44998 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/18/2009
Notification Time: 08:38 [ET]
Event Date: 04/18/2009
Event Time: 01:20 [EDT]
Last Update Date: 04/18/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RAY POWELL (R1)
TIM McGINTY (NRR)
BRIAN McDERMOTT (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text COURTESY NOTIFICATION MADE TO STATE OF MASSACHUSETTS INVOLVING AN EMPLOYEE FATALITY
"On April 18, 2009 an informational notification was made to the US NRC.
"At approximately 0120 EDT on April I8, 2009, the Pilgrim main control room received an emergency medical call stating that a Pilgrim employee had been found unconscious inside the radiologically controlled area of the plant. The individual was treated by the on-site first responders who administered CPR and AED treatment. Off site medical assistance was requested and the individual was transported to the local hospital.
"At approximately 0230 EDT, Pilgrim was notified that the individual had died of an apparent heart attack.
"A courtesy notification was made to the Massachusetts Emergency Management Agency.
"The NRC Resident Inspector has been notified.
"The event had no adverse effect to the health and safety of the public."
The licensee confirmed that the employee transported offsite was not radiologically contaminated. No press release is planned.
* * * UPDATE FROM BRUCE CHENARD TO HOWIE CROUCH ON 4/18/09 @ 1300 EDT * * *
"While Pilgrim does not plan to issue a news release regarding this event, it is anticipated that media coverage of the event will ensue based upon the off-site response to the medical emergency. This 10 CFR 50.72(b)(3)(xi) notification is conservatively being made in advance of any media attention."
Notified R1DO (Powell). |
| Power Reactor | Event Number: 44999 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MIKE HIMEBAUCH
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/19/2009
Notification Time: 23:38 [ET]
Event Date: 04/19/2009
Event Time: 23:15 [EDT]
Last Update Date: 04/19/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
LAURA KOZAK (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text SAFETY PARAMETER DISPLAY SYSTEM AND EMERGENCY RESPONSE DATA SYSTEM OUT OF SERVICE FOR PLANNED MAINTENANCE
"On 4/19/09 at 2315 EDT, Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) were removed from service to support activities for a planned maintenance outage on the UPS vital bus power supply. The duration of work is expected to be approximately 24 hours. During this time, the majority of the Control Room indications remain available to the plant staff, and will be used for emergency response, if needed. Information will be communicated to the NRC using other available communication systems, if needed. The plant is currently in Mode 5, and will remain in Mode 5, for the duration of the SPDS and ERDS unavailability. Since the unavailability will last greater than 8 hours, this is considered a Loss of Emergency Assessment Capability, and reportable under 10CFR50.72(b)(3)(xiii).
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 45000 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: GEORGE E. STOROLIS
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/20/2009
Notification Time: 05:09 [ET]
Event Date: 04/20/2009
Event Time: 01:15 [EDT]
Last Update Date: 04/20/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
RAY POWELL (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text AUXILIARY FEEDWATER ACTUATION ON VALID STEAM GENERATOR HI-HI SIGNAL DURING SHUTDOWN
"On April 20,2009 at 01:15 during Beaver Valley Power Station Unit 1 shutdown and cooldown in support of the 19th refueling outage, Unit 1 experienced an Engineered Safety Feature (ESF) actuation P-14 due to Steam Generator (SG) HI-HI water level in the 'B' Steam Generator. This ESF actuation initiated automatic actions resulting in full feedwater isolation, trip of the only operating 'B' main feed and the start of two Auxiliary Feedwater System pumps. The unplanned automatic initiation of the Auxiliary Feedwater system [was] due to the Main Feedwater pump trip. The P-14 automatic ESF features properly closed the main and bypass feedwater regulating valves and [caused the] closure of the Feedwater Containment Isolation valves. A turbine trip signal was generated but the turbine was not on-line. The automatic start of the MDAFW pumps from this valid signal is reportable under 10CFR50.72(b)(3)(iv)(A).
"The cause of the steam generator high level transient is the failure of the FCV-1FW-489, 'B' steam generator feed water bypass level control to automatically maintain level. Attempts to control the level manually were not successful. Additional investigation is in progress.
"P-14 ESF actuation reset actions are being performed. Unit one cooldown continues using the MDAFW pumps and controls. AFW continues to be injected into the steam generators.
"The licensee notified the NRC resident Inspector." |
| Power Reactor | Event Number: 45001 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: GEORGE E. STOROLIS
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/20/2009
Notification Time: 05:09 [ET]
Event Date: 04/20/2009
Event Time: 01:53 [EDT]
Last Update Date: 04/20/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
RAY POWELL (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text UNEXPECTED START OF THE STEAM DRIVEN AUXILIARY FEEDWATER PUMP DURING PLANT COOLDOWN
"On 4/20/09 at 0153 hours, while in Mode 3 performing a plant cooldown for a refueling outage, a control room operator noted that the 'B' train steam supply (TV-1MS-105B) to the steam driven auxiliary feedwater pump, FW-P-2, was open. This caused the steam driven auxiliary feedwater pump to start and inject auxiliary feedwater into the steam generators. This was an unexpected condition. The start of the FW-P-2 auxiliary turbine driven feedwater pump is reportable under 10CFR50.72(b)(3)(iv)(A).
"At 0209, TV-1MS-105B was closed. The steam driven auxiliary feedwater pump was declared inoperable and Technical Specification action statements were entered. Technical Specification 3.7.5 Condition B requires the pump to be restored to operable status within 72 hours or be in Mode 4 within the following 18 hours.
"Mode 4 was entered on 4/20/09 at 0347 hours. The steam drive auxiliary feedwater pump is not required to be operable in Mode 4. Technical Specification 3.7.5 Condition B was exited on 4/20/09 at 0347.
"Investigation is in progress to determine the cause of TV-1MS-105B opening.
"The licensee notified the NRC Resident Inspector." | |