| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/02/2013 - 04/03/2013 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 48848 | Rep Org: ALABAMA RADIATION CONTROL
Licensee: IIG, MINWOOL, LLC
Region: 1
City: PHENIX CITY State: AL
County:
License #: 986
Agreement: Y
Docket:
NRC Notified By: DAVID WALTER
HQ OPS Officer: DONALD NORWOOD | Notification Date: 03/25/2013
Notification Time: 12:05 [ET]
Event Date: 03/25/2013
Event Time: 08:20 [CDT]
Last Update Date: 03/25/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
PAUL KROHN (R1DO)
FSME EVENT RESOURCES (EMAI)
| Event Text AGREEMENT STATE REPORT - INTERNAL LEAD SHIELDING OF GAUGE SOURCE HOLDERS MELTED
The following information was received via facsimile:
"The Alabama Office of Radiation Control received a call at 0820 CDT on 3/25/13 from Dr. Michael Hensley of RSO Services (AL license No. 1482), a gauge service company. He had been contacted by IIG, MinWool, LLC in Phenix City, AL (AL license No. 986) to assist them with an issue. The licensee melts rock in a cupola to make insulation. The cupola has two Ohmart Model SR-A devices, one at the top and one at the bottom of the cupola, each containing a 100 mCi Cesium-137 source. The cupola was superheated to about 3,500 degrees Fahrenheit above the operating limits for the Model SR-A devices. It is believed the lead shielding in the devices liquefied, but because the source holders are sealed, the lead was contained inside the devices and did not leak out.
"Dr. Hensley surveyed the devices and found a maximum reading of 2.5 mR/hr at 12 inches from the back of the device which was located at the top of the cupola. This is lower than the design maximum exposure of 4.8 mR/hr with a 100 mCi source per the SSDR. The shutters on both devices were still operable, and were closed and locked. Dr. Hensley will remove the devices and prepare them for shipment to Ohmart."
Alabama Incident No.: 13-09 |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 48860 | Facility: SURRY
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JON FORD
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/28/2013
Notification Time: 00:43 [ET]
Event Date: 03/27/2013
Event Time: 22:45 [EDT]
Last Update Date: 04/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
DEBORAH SEYMOUR (R2DO)
|
| 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 ONE EMERGENCY WARNING SIREN ENERGIZED FOR A SHORT TIME
"At 2245 [EDT] on 3/27/2013, Surry Power Station (SPS) Operations Department received a report from Virginia State Emergency Operations Center (VEOC) that a concerned citizen had called James City County (JCC) law enforcement to report that an Early Warning System (EWS) siren, #62 in James City County NW side of Route 682, was sounding. VEOC reported JCC police received call at 2240 [EDT] from a concerned citizen that an EWS siren was sounding. SPS Security contacted JCC police and subsequently reported that JCC police responded approximately 10 minutes later to the site of the siren, but the siren was no longer sounding. Maintenance will investigate in the morning. All plant conditions/parameters are normal and no releases to the environment have occurred.
"The site NRC Resident Inspectors have been notified.
"This notification is being transmitted due to notification of other Government Agencies in accordance with 10CFR50.72(b)(2)(xi)."
The licensee also notified the state and local governments.
* * * UPDATE FROM JASON SWEATMAN TO STEVE SANDIN ON 4/2/2013 AT 1710 HOURS * * *
"This report is being retracted based upon the following:
"On 3/28/13, an activation verification test was performed. The results of the test indicated EWS siren #62 did not activate. In addition, when a siren activates, the battery voltage decreases. A review of the battery voltage trend for siren #62 found no such decrease, verifying no activation occurred. Maintenance staff reported to the siren location and confirmed the siren did not activate. They also found no indication of tampering or intrusion. Three local homeowners were interviewed and stated they did not hear any siren activation.
"By all available indications, EWS siren #62 was functional and did not activate on 03/27/13.
"NRC Site Resident Inspectors have been notified of the retraction."
Notified R2DO (McCoy). |
| Power Reactor | Event Number: 48869 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: PHILLIP FORE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 03/31/2013
Notification Time: 11:57 [ET]
Event Date: 03/31/2013
Event Time: 10:33 [CDT]
Last Update Date: 04/02/2013 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
GREG PICK (R4DO)
ART HOWELL (R4RA)
JENNIFER UHLE (NRR)
ALLEN HOWE (NRR)
WILLIAM GOTT (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text NOTIFICATION OF UNUSUAL EVENT DECLARED DUE TO A BREAKER EXPLOSION IN THE PROTECTED AREA
"At 0750 [CDT] on 3/31/2013, during movement of the Unit 1 Main Turbine Generator Stator (~500 tons), the Unit 1 turbine temporary lift device failed. This caused a loss of all off-site power on Unit 1. The ANO Unit 1 #1 and #2 EDG [Emergency Diesel Generator] have started and are supplying A-3 4160V switchgear and A-4 4160V switchgear. P-4A Service Water pump and P-4C Service Water pump has been verified running. Unit 1 has entered [procedures] 1202.007 - Degraded Power, 1203.028 - Loss of Decay Heat, and 1203.050 - Spent Fuel Emergencies. Unit 1 is in MODE 6.
"ANO-1 entered TS 3.8.2 A, 'One Required Offsite Circuit Inoperable'. All required actions are complete. The event caused a loss of decay heat removal on ANO Unit 1 which was restored in 3 minutes and 50 seconds.
"Unit 2 tripped and is in MODE 3. Emergency Feed Water was initiated on Unit 2 and Unit 2 was in [Technical Specification] 3.0.3 from 0817 [CDT] to 0848 [CDT] due to Emergency Feedwater. Unit 2 is being powered by off-site. Unit 2 Startup 3 [transformer] lock out at 0921 [CDT]. [Bus] 2A1 is on Start up 2 [transformer] and [bus] 2A3 is on #2 EDG.
"10CFR50.72 (b)(3)(iv)(A) - 4-hr. notification due to the ES [Engineered Safeguard Feature] actuation on both Unit 1 and Unit 2.
10CFR50 72 (b)(2)(iv)(B) - 4-hr. notification due to RPS [Reactor Protection System] actuation on Unit 2.
10CFR50.72 (b)(2)(xi) - 4-hr. notification due to Government Notification.
29CFR1904.39a - [OSHA] 8-hr. notification due to death on site.
"At 1033 [CDT] on 3/31/2013, Unit 2 entered a Notification of Unusual Event based on EAL HU4 due to damage in 2A1 switchgear. Notification of the NUE will be made lAW Emergency Plan requirements. Follow-up notifications will be made as appropriate."
At this time, the full extent of structural damage on Unit 1 is not known. There was one known fatality and 4 known serious injuries to workers. The local coroner is on site for the fatality and the injured personnel have been transported offsite to local hospitals. Investigation into the cause of the failure and extent of damage is ongoing.
On Unit 2, all rods inserted during the trip. The core is being cooled via natural circulation. Decay heat is being removed via steam dumps to atmosphere. There is no known primary to secondary leakage.
The licensee has notified the State of Arkansas, local authorities, OSHA and the NRC Resident Inspector.
Notified DHS SWO, DHS NICC, FEMA and Nuclear NSSA (via email).
* * * UPDATE FROM DAVID THOMPSON TO HOWIE CROUCH AT 1934 EDT ON 3/31/13 * * *
The licensee terminated the NOUE at 1821 CDT. The basis for termination was that the affected bus (2A2) is de-energized and no other equipment on Unit 2 was damaged.
The licensee has notified the state and local authorities and will be notifying the NRC Resident Inspector.
Notified R4DO (Pick), NRR EO (Howe), IRD (Gott), DHS SWO, DHS NICC, FEMA and Nuclear SSA (via email).
* * * UPDATE FROM STEVE COFFMAN TO HOWIE CROUCH AT 1054 EDT ON 4/2/13 * * *
The licensee made the following edits to the third paragraph of their original report (edits in quotes):
Unit 2 tripped and is in MODE 3. Emergency Feed Water initiated on Unit 2. Unit 2 was in [Technical Specification] 3.0.3 from 0817 [CDT] to 0848 [CDT] due to Emergency Feedwater "being procedurally overridden." Unit 2 "was initially" being powered by off-site. Unit 2 Startup 3 Lock out occurred at 0921. 2A1 is now on Startup 2, and "2A4" is on #2 EDG.
Notified R4DO (Kellar) via email. |
| Power Reactor | Event Number: 48877 | Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN FINLAY
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/02/2013
Notification Time: 15:52 [ET]
Event Date: 04/02/2013
Event Time: 13:45 [CDT]
Last Update Date: 04/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
ROBERT DALEY (R3DO)
|
| 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 REPORT INVOLVING DISCOVERY OF AN ALCOHOL CONTAINER INSIDE THE PROTECTED AREA
During remodeling of a bathroom on the third floor of the Administrative Building which is located inside the Protective Area, workers discovered a very old container of gin after removing the ceiling tiles. This item will be entered into the licensee corrective actions program for follow up.
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 48878 | Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THOMAS GARRISON
HQ OPS Officer: PETE SNYDER | Notification Date: 04/02/2013
Notification Time: 16:25 [ET]
Event Date: 04/02/2013
Event Time: [EDT]
Last Update Date: 04/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
GERALD MCCOY (R2DO)
|
| 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 TECHNICAL SUPPORT CENTER VENTILATION SYSTEM OUT OF SERVICE DUE TO PLANNED MAINTENANCE
"This is a non emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the work activity affects the functionality of an emergency response facility.
"Planned maintenance activities are being performed on 4/3/13 to be Technical Support Center (TSC) HVAC. The work includes removal of a pressurizing ventilation fan and opening ventilation system ductwork. The planned work activity duration is approximately 48 hours.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures. The Emergency Response Organization team has been notified of the maintenance and the possible need to relocate during an emergency.
"The NRC Resident Inspector has been notified. The State of North Carolina will be notified." |
| Power Reactor | Event Number: 48879 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: TIM HOLLAND
HQ OPS Officer: PETE SNYDER | Notification Date: 04/02/2013
Notification Time: 20:30 [ET]
Event Date: 04/02/2013
Event Time: 17:07 [CDT]
Last Update Date: 04/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RAY KELLAR (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 88 | Power Operation | 88 | Power Operation | Event Text OFFSITE NOTIFICATION DUE TO ELECTRICAL FAULT IN SWITCHYARD RESULTING IN PERSONNEL INJURIES
"At 1707 CDT on 4/2/13 an arc flash occurred at the 'B' safeguards transformer (XMDV24) in the plant switchyard at Callaway. At the time of the flash, ground straps were being placed on the 'B' safeguards transformer which had been removed from service for maintenance. The event resulted in a loss of power to areas/buildings outside the power block. There was no impact to equipment and systems in the plant.
"Four workers were injured or affected by the flash. The extent of the electrical-related injuries has not been determined. However, based on reports from the scene, all of the workers were conscious and walked away from the scene. One person was transported by helicopter and two by ambulance to a local hospital. The fourth person experienced only a minor injury.
"The hazard has been isolated and investigation of the cause is in progress.
"Notifications of this event are planned to be made to OSHA and the Missouri Public Service Commission."
The licensee notified the NRC Resident Inspector. | |