| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/09/2011 - 09/12/2011 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 47201 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: BILL HUFFMAN | Notification Date: 08/26/2011
Notification Time: 16:23 [ET]
Event Date: 08/26/2011
Event Time: 13:00 [EDT]
Last Update Date: 09/09/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
MALCOLM WIDMANN (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | | 2 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text UNANALYZED CONDITION BASED ON SEISMIC ACTIVITY THAT POTENTIALLY EXCEEDED DESIGN BASIS EARTHQUAKE MAGNITUDE
"On August 23, 2011 at 1351 hours, North Anna Power Station experienced a seismic activity event which resulted in a loss of offsite power and automatic reactor trip of both units. At 1403 hours, an Alert was declared, based on Shift Manager judgment, due to significant seismic activity on the site. Subsequent to the earthquake, both units were stabilized and offsite power was restored. Following the event, seismic data was retrieved from the installed monitoring system and shipped to the vendor to determine the response spectrum for the event. On August 26, 2011 at 1340 hours, initial reviews of the data determined that the seismic activity potentially exceeded the Design Basis Earthquake magnitude value above 5 Hz. Therefore, this is reportable per 10CFR50.72(b)(3)(ii) (B) for the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.
"North Anna Unit 1 is currently in Cold Shutdown with the Residual Heat Removal System providing core cooling. North Anna Unit 2 is currently in Hot Shutdown and will be taken to Cold Shutdown with the Residual Heat Removal System providing core cooling. No significant equipment damage to Safety Related system (including Class 1 Structures) has been identified through site walk-downs nor has equipment degradation been detected through plant performance and surveillance testing following the earthquake. Therefore, there is reasonable assurance that the Safety Related systems are fully functional.
"The Spent Fuel Pit cooling system also remains fully functional and the temperature of the Spent Fuel Pit remained unchanged during the event.
"The vendor will complete the analysis of the seismic data and this information will be utilized to address the long term actions following the earthquake."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM DON TAYLOR TO PETE SNYDER AT 1739 EDT ON 9/9/11 * * *
"This is an update to EN 47201 reported on 8/26/2011 where It was reported that North Anna potentially exceeded the Design Basis Earthquake (DBE) magnitude value above 5 Hz.
"The vibratory motion from the 5.8 magnitude earthquake were recorded in all three orientations at several locations in the plant using two types of instruments: the Engdahl scratch plates that record 12 discrete spectral accelerations between 2 and 25.4 Hz, and the Kinemetrics analog recorders that recorded time histories of the accelerations. Based on evaluation of recorded plant data, it is concluded that the Central Virginia earthquake of 8/23/2011 exceeded the spectral accelerations for the Operational Basis Earthquake (OBE) and DBE of North Anna Plant.
"Extensive actions are underway to inspect. evaluate, test, and repair if necessary. systems and components to ensure they are capable of performing their required functions. To date, no significant damage to safety related structures, systems or components (SSC) has been identified."
The licensee notified the NRC Resident Inspector.
Notified R2DO (Rich). |
| Power Reactor | Event Number: 47240 | Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MICHAEL G. BRILL
HQ OPS Officer: STEVE SANDIN | Notification Date: 09/04/2011
Notification Time: 13:27 [ET]
Event Date: 09/04/2011
Event Time: 10:20 [EDT]
Last Update Date: 09/09/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MARVIN SYKES (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 | 95 | Power Operation | 95 | Power Operation | Event Text TECHNICAL SUPPORT CENTER LOST DUE TO FAILED BACKUP DIESEL GENERATOR SURVEILLANCE TEST
"A condition is being reported per Technical Requirements Manual 13.13.1 Emergency Response Facilities Action B.2. The Functionality of the Technical Support Center (TSC) has been lost due to a failure to pass a required surveillance of the backup diesel generator for TSC Support Systems. Alternate facilities are available to provide emergency response functions and actions are proceeding to return the TSC to FUNCTIONAL status with high priority.
"The NRC Resident Inspector has been notified."
* * * UPDATE FROM DANIEL MONAHON TO VINCE KLCO ON 9/9/2011 AT 1418 EDT* * *
The licensee has declared the TSC Operable. The licensee notified the NRC Resident Inspector.
Notified the R2DO (Rich). |
| Agreement State | Event Number: 47243 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: EQUISTAR CHEMICALS, LP
Region: 3
City: MORRIS State: IL
County:
License #: IL-01737-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: BILL HUFFMAN | Notification Date: 09/06/2011
Notification Time: 12:38 [ET]
Event Date: 09/02/2011
Event Time: [CDT]
Last Update Date: 09/06/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHRISTINE LIPA (R3DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE - FIXED PROCESS GAUGE FAILED SHUTTER CHECK
The following report was received from the State of Illinois via e-mail.
"While performing routine shutter checks of fixed gauges at the licensee's site, a device failed to perform as expected. As a result, the Radiation Safety Officer contacted the Agency and made the required report. The failed Ohmart/Vega Model SH-F2 gauge is used for level detection on a high temperature, high pressure vessel. The vessel is located on a roof 50 feet above grade with the nearest workstation approximately 300 feet away. The gauge was left in the 'on' position so as to allow continued routine operation of the process line. Shift supervisors and site personnel were advised of the situation and any entry into the vessel has been prohibited should the line become disabled or shut down. The manufacturer has been contacted and arrangements are pending for repair of the device at the first available opportunity. Should the gauge mounting fail and it become necessary, additional shielding material is available on-site to cover the open beam port and personnel have adequate training to perform that task. No threat to health and safety exist at this time and there are no associated exposures."
The Ohmart Gauge Model SH-F2, Serial Number 7306GK contains an 0.3 Ci sealed Cs-137 source.
Illinois Report Number IL11120 |
| Agreement State | Event Number: 47245 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: IRIS NDT INC
Region: 4
City: DEER PARK State: TX
County:
License #: 04769
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 09/06/2011
Notification Time: 17:42 [ET]
Event Date: 09/06/2011
Event Time: [CDT]
Last Update Date: 09/06/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DRAKE (R4DO)
PAUL MICHALAK (FSME)
| Event Text AGREEMENT STATE - RADIOGRAPHY CAMERA SOURCE DISCONNECT FROM DRIVE CABLE
The following event was provided by the State of Texas Health Services Radiation Branch via facsimile:
"On September 6, 2011, the [State of Texas Radiation Branch] was notified by the licensee that while using a Spec 150 radiography camera (serial number 1154, containing a 47.2 Curie Iridium -192 source), the source disconnected from the drive cable. The licensee's Radiation Safety Officer stated the radiographer was starting to crank the source out for the eighth shoot of the day when he noted that the guide tube had come loose from the camera and that the drive cable had began to spool in front of the camera. The radiographer attempted to return the source to the locked position in the camera, but it would not lock. The radiographer went to investigate at the front of the camera and saw the source lying on the ground in front of the camera. The radiographer contacted the RSO and a source recovery team went to the location. Lead shot was placed over the source to reduce the area dose rates. The source recovery team was able to reconnect the source to the drive cable and return the source into the camera and lock it in place. The licensee has returned the camera to its storage location and will conduct a leak test of the source and inspect the guide tube and crank-outs. The RSO stated that it appears that the quick disconnect on the camera failed. No significant exposure was received by the source recovery team or any member of the general public. Additional information will be supplied as it is received in accordance with SA-300."
Texas Report Number I-8882 |
| Power Reactor | Event Number: 47253 | Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: TIM LOVE
HQ OPS Officer: VINCE KLCO | Notification Date: 09/09/2011
Notification Time: 14:01 [ET]
Event Date: 09/09/2011
Event Time: [EDT]
Last Update Date: 09/09/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
TODD JACKSON (R1DO)
|
| 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 OFFSITE NOTIFICATION DUE TO LEAKING A SMALL QUANTITY OF DIESEL FUEL OIL
"A temporary diesel generator has emitted droplets of oil to the ground which was washed to a storm drain. The exhaust droplets were contained in secondary containment. An oil-only absorbent boom was placed around the storm drain to capture residual oil and prevent oil to the storm drain."
It is estimated that 0.05 gallons of diesel fuel entered a storm drain.
The licensee notified the Maryland Department of Environment, National Response Center, U.S. Coast Guard and the NRC Resident Inspector. |
| Non-Agreement State | Event Number: 47255 | Rep Org: DEEP GREEN WEST VIRGINIA INC
Licensee: DEEP GREEN WEST VIRGINIA INC
Region: 1
City: PAGETON State: WV
County:
License #: GL
Agreement: N
Docket:
NRC Notified By: ALLEN ROBINSON
HQ OPS Officer: VINCE KLCO | Notification Date: 09/09/2011
Notification Time: 17:03 [ET]
Event Date: 09/08/2011
Event Time: 10:00 [EDT]
Last Update Date: 09/09/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
TODD JACKSON (R1DO)
PAUL MICHALAK (FSME)
| Event Text FIXED GAUGE SHUTTER FAILURE
"On 9/8/2011, during site cleanup activities, workers at the Greenfields coal processing facility near Pageton, WV unexpectedly discovered two generally licensed, fixed-type gauges in a remote, back lot area of the plant property. One of the gauges had a stuck open shutter. The gauges are currently clamped to pipes, roped off in an area restricted from personnel access, at about a 300 foot distance from personnel. No threat to health and safety exists at this time.
"The gauges are designed to be affixed to piping for industrial process control, but were found among various discarded metal parts.
"An inspector from the West Virginia Radiological Health Program took survey measurements and verified there was no spread of contamination. Dose rates outside of the gauge casing are about 0.4 mRem/hr. Dose rates inside of the pipes are about 40 mRem/hr, which indicates that the shutters are likely open.
"Facility personnel will take photos of the gauges and send to NRC Region I. Additionally, they intend to place the gauges with the piping in a locked gang box that will be chained and locked to a fixed metal structure.
"The facility owner, Deep Green, is taking steps to have the material removed from the site.
"Gauge information: [2] Berthold Technologies gauges, Model No. LB 7440 D; 30 mCi, Cs-137 source (Sep. 21, 2001); Source serial # HE681 manufactured by AEA Technologies, model CDC.p4; SSD Safety Evaluation No. TN-1031-D-101-B." | |