| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/26/2013 - 02/27/2013 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 48768 | Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: K & S ASSOCIATES, INC.
Region: 1
City: NASHVILLE State: TN
County:
License #: R-19136-B15
Agreement: Y
Docket:
NRC Notified By: LAURA TURNER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 02/19/2013
Notification Time: 15:00 [ET]
Event Date: 02/18/2013
Event Time: [EST]
Last Update Date: 02/19/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TODD JACKSON (R1DO)
FSME EVENTS RESOURCE (E-MA)
| Event Text AGREEMENT STATE REPORT - BEAM IRRADIATOR EQUIPMENT FAILURE
The following event notification was received from Tennessee Division of Radiological Health via e-mail:
"On Monday, February 18, 2013, the Division of Radiological Health received notification regarding K&S's Eldorado 78 device, and the failure of the source drawer not moving to the ON position. After the Eldorado device was turned on, the console indicated all interlocks were clear, however, when the beam was activated the source drawer did not move to the ON position. A Foss Therapy Technician was contacted and will make a service call on Wednesday February 20, 2013. The device is identified as Foss Therapy Services, Inc., Eldorado 78 Beam Irradiation Device, containing an International Isotopes Idaho, Inc. Co-60 source. Model and Serial No., INIS-SF-X.X-YY-Z.
"A written report is being prepared and will be sent to the Tennessee Division of Radiological Health."
Tennessee Report: TN-13-028 |
| Power Reactor | Event Number: 48783 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: LEE GOLDSTIEN
HQ OPS Officer: HOWIE CROUCH | Notification Date: 02/26/2013
Notification Time: 09:32 [ET]
Event Date: 02/26/2013
Event Time: 09:00 [EST]
Last Update Date: 02/26/2013 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
GERALD MCCOY (R2DO)
HAROLD CHERNOFF (NRR)
DAN DORMAN (NRR)
VICTOR MCCREE (R2RA)
WILLIAM GOTT (IRD)
|
| 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 | 94 | Power Operation | 94 | Power Operation | Event Text UNUSUAL EVENT DECLARED DUE TO TOXIC GAS LEAK
"At 0900, the Brunswick Steam Electric Plant (BSEP) declared an Unusual Event due to a release of Freon from the 2A Turbine Building Chiller. The classification of the Unusual Event is based on Emergency Action Level (EAL) HU3.1, 'Toxic, corrosive, asphyxiant or flammable gases in amounts that have or could adversely affect normal plant operations.' Actions have been taken to secure the chiller and isolate the release of Freon; however, Freon continues to be released. The release is only affecting the area immediately surrounding the 2A Turbine Building Chiller. No other plant areas are being impacted.
"There is no impact on the health and safety of the public."
The licensee notified Brunswick Warning Point, Hanover Warning Point, State Warning Point and the NRC Resident Inspector.
Notified DHS, FEMA, DHS NICC and NuclearSSA (email).
* * * UPDATE AT 1555 EST ON 2/26/13 FROM ERIC WHITE TO S. SANDIN * * *
At 1545 EST on 2/26/13, Brunswick terminated their Unusual Event based on the fact that the entry conditions no longer existed. A temporary patch has been installed on the 2A Turbine Building Chiller and work is in progress to evacuate residual Freon from the chiller unit.
The licensee notified state and local agencies and the NRC Resident Inspector. Notified R2DO (Musser), IRD (Kozal) and NRR (Chernoff).
Notified DHS, FEMA, DHS NICC and NuclearSSA (email). |
| Power Reactor | Event Number: 48785 | Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DANNY WILLIAMSON
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/26/2013
Notification Time: 16:59 [ET]
Event Date: 02/26/2013
Event Time: 14:30 [CST]
Last Update Date: 02/26/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
DON ALLEN (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Refueling | Event Text STATE AND LOCAL AGENCIES NOTIFIED OF INADVERTENT TRITIUM RELEASE DUE TO OVERFLOWING SUMP
"On February 25, 2013 at approximately 1030 CST, plant personnel discovered that a sump within a concrete berm area adjoining the condensate storage tank was overflowing. Water from the sump was entering an open excavation within the berm, and was soaking into the dirt underneath. At approximately 1400 [CST] that day, the sump level was pumped down to terminate the overflow. A portable tank has been staged in the area should any further pumping be required.
"Analysis of the water within the berm found tritium activity of 1.135 million picocuries per liter. Additionally, total gamma activity of 1.145 E-6 microcuries per milliliter was present in the sample. The estimated volume of water reaching the open excavation was approximately 380 gallons.
"Notification of this event has been made to local and state governmental agencies in accordance with NEI 07-07, Industry Ground Water Protection Initiative. The initial notifications were made at approximately 1430 CST today.
"This event is being reported in accordance with 10CFR50.72(b)(2)(xi) as a condition for which local and state governmental agencies have been notified. The station has also notified the NRC Resident Inspector, as well as NRC Region 4 personnel." |
| Power Reactor | Event Number: 48786 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN STERMER
HQ OPS Officer: VINCE KLCO | Notification Date: 02/26/2013
Notification Time: 19:20 [ET]
Event Date: 02/26/2013
Event Time: 16:30 [PST]
Last Update Date: 02/26/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DON ALLEN (R4DO)
ERDS GRP (email) ()
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Defueled | 0 | Defueled | Event Text LOSS OF ASSESSMENT CAPABILITY DUE TO VITAL INVERTER MAINTENANCE
"At approximately 1630 PST on February 26, 2013, Pacific Gas & Electric (PG&E) will be performing repairs on a vital inverter. The clearance will remove power from various inputs to the Safety Parameter Display System (SPDS), Emergency Response Data System (ERDS), and Emergency Response Data and Recall Recorder Subsystem (ERFDS).
"PG&E expects to have the equipment repaired and returned to service within 12 hours. During this time, a dedicated licensed operator will be available to provide plant data to the NRC's Emergency Operations Center.
"DCPP is making this 8-hour, non-emergency notification under 10 CFR 50.72(b)(3)(xiii) as any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 48787 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: BILL HUFFMAN | Notification Date: 02/27/2013
Notification Time: 00:55 [ET]
Event Date: 02/26/2013
Event Time: 20:12 [CST]
Last Update Date: 02/27/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
DON ALLEN (R4DO)
|
| 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 RELAY BACKING PLATE FASTENERS DISCOVERED TO BE AT LESS THAN SPECIFIED TORQUE
"During a follow-up review of off-site testing of a sample of General Electric model HFA relays, it was discovered that some of these relays did not pass testing for full qualification in their as-found condition. Additional torquing of the relay backing plate mounting screws was required to fully meet the required qualification. Further investigation into the as-found condition of these relays installed in the plant continues at this time. The relays in question are installed in Engineered Safeguards Features, Auxiliary Feed Water, and 4160 volt systems and are used in protective and actuation functions. "
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 48788 | Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL DUNN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 02/27/2013
Notification Time: 02:07 [ET]
Event Date: 02/26/2013
Event Time: 23:02 [EST]
Last Update Date: 02/27/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
RANDY MUSSER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 94 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO EXCESSIVE REACTOR COOLANT PUMP SEAL LEAKOFF FLOW
"At 2302 EST, Vogtle Unit Two was manually tripped in response to excessive Reactor Coolant Pump #4, seal #1 leakoff flow. Seal leakoff flow exceeded the procedural limits for continued operation of the pump. Following the reactor trip, RCP #4 was shutdown per procedure guidance.
All systems operated correctly in response to the reactor trip. All control rods fully inserted. The Auxiliary Feed Water (AFW) system automatically actuated as expected. System responses allowed for an uncomplicated reactor trip response. The plant is stable in Mode 3 during cause investigation.
"The NRC Senior Resident was notified and is enroute to the plant for investigation."
AFW is supplying the steam generators and decay heat removal is to the condenser via steam dumps. No safety valves or relief valves lifted during the transient. The unit is in a normal post-trip electrical line-up. There was no impact on Unit One. | |