| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/14/2011 - 10/17/2011 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 46194 | Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: CLINT SIX
HQ OPS Officer: DONALD NORWOOD | Notification Date: 08/21/2010
Notification Time: 11:41 [ET]
Event Date: 08/21/2010
Event Time: 11:00 [EDT]
Last Update Date: 10/14/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
JOHN WHITE (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 | Event Text FLOOD BARRIERS NEEDED TO PROTECT SAFETY RELATED EQUIPMENT MISSING
"On August 21, 2010 an inspection of the Air Intake Tunnel (AIT) sump identified missing flood barriers needed to protect safety related equipment in the plant. If enough flood water had entered into the AIT, water could have entered into the Auxiliary Building (AB) through the ventilation ductwork that connects the AIT and the AB. If flood water continued to enter the AB, then safety related equipment in the AB could have been affected.
"This condition could have resulted in the unavailability of equipment in the Auxiliary Building including the 1A and 1B Decay Heat pumps, the 1A and 1B Building Spray pumps and 1A, 1B and 1C Make-up Pumps. This is reportable as an 8 hour ENS notification under 10CFR50.72(b)(3)(v)(B) and 10CFR50.72(a)(1)(ii) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to remove residual heat.
"Flood protection barriers have been established for the affected penetrations. Inspections of the flood protection barriers are ongoing. Further engineering review is being performed to determine the impact of the potential water intrusion into the AIT and AB."
The licensee notified the NRC Resident Inspector. The licensee will notify the Pennsylvania Bureau of Radiation Protection.
* * * RETRACTION FROM MICHAEL FITZWATER TO JOHN SHOEMAKER AT 1437 EDT ON 10/19/10 * * *
"EN# 46194 made on August 21, 2010 at 1100 EDT is being retracted. Upon further Engineering review it was determined that the external flood barrier design deficiency in the Air Intake Tunnel (AIT) did not result in a condition that could have prevented the fulfillment of the safety function needed to remove residual heat. The AIT sump pump is in the cavity that had the degraded barrier where the in leakage of concern enters through conduits from yard electrical vaults. This pump starts automatically and has capacity in excess of the in leakage during the Probable Maximum Flood (PMF). The AIT sump pump's functional capability was confirmed to be available over the past three years. Therefore the ability to prevent flood water from the AIT reaching and impacting safety related equipment needed to remove residual heat was maintained. The event is therefore NOT reportable."
The Licensee has notified the Resident Inspector.
Notified R1DO. |
| Agreement State | Event Number: 47339 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: METCO
Region: 4
City: Houston State: TX
County:
License #: 03018
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOE O'HARA | Notification Date: 10/12/2011
Notification Time: 08:30 [ET]
Event Date: 10/10/2011
Event Time: 07:00 [CDT]
Last Update Date: 10/12/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHUCK CAIN (R4DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - MISALIGNMENT IN THE CRANKOUT DEVICE
The following was received via fax:
"On October 11, 2011, the Agency [state] was notified by the licensee that on October 10, 2011 while performing radiography operations in one of their shooting bays, they were unable to retract an 89 Curie Iridium - 192 source into a SPEC model 150 camera. The licensee used their video surveillance cameras to verify that nothing had fallen on the guide tube to prevent movement of the source. No obstructions were observed. A technician approved for source retrieval inspected the camera and associate equipment and determined that the crankout being used was not working correctly. The crankout was disassembled and the drive cable was pulled by hand until the source returned to the fully shielded and locked position. The licensee inspected the crankout device and found that there was a slight misalignment between the drive cable and the gear. The device was adjusted, tested and operates smoothly. The crankout device will be sent to the manufacturer for further evaluation. No
additional exposure was received by any individual during this event."
Texas Incident No. I-8890 |
| Power Reactor | Event Number: 47343 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: RICHARD GARCIA
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/13/2011
Notification Time: 20:21 [ET]
Event Date: 10/11/2011
Event Time: 09:50 [PDT]
Last Update Date: 10/16/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JACK WHITTEN (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 98 | Power Operation | 100 | Power Operation | Event Text EMERGENCY RESPONSE DATA SYSTEM INOPERABLE
"At 0915 on 10-11-2011, Columbia Generating Station's (CGS) Emergency Response Data System (ERDS) system was taken out of service for planned maintenance activities. Assessment of the ERDS outage considered the anticipated duration of the outage along with the knowledge that the system would not be recoverable within an hour of a declared event (Alert or higher) during this maintenance period. Station personnel concluded the planned maintenance to be reportable 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 (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system).' To that end, a call was made to the NRC's Headquarters Operational Office (HOO) at 09:22 PDT on 10-11-2011. Feedback received during that call was that the event was a loggable entry but not recordable and no EN number was assigned.
"Efforts to fully restore ERDS following the maintenance have not yet been successful and the actual duration of the work has substantially exceeded initial estimates for planned duration. Work is ongoing to restore the system to full capability. Restoration plans include a functional test coordinated with the NRC ERDS center to demonstrate the system performs as required.
"This follow-up call is made to update the original call placed 10-11-2011 and to affirm that the current lack of a functional ERDS system represents a major loss of emergency preparedness capability consistent with 10 CFR 50.72(b)(3)(xiii). Previously credited compensatory measures remain in effect and rely on existing CGS Emergency Response procedures to provide plant data via the Emergency Notification System to the NRC Operations Center until the ERDS can be returned to service. Members of the CGS Emergency Response Organization have been trained on contingencies required during an Emergency Plan activation with loss of ERDS capability. No other emergency response functions are impacted by this ongoing work. The resident inspector has been briefed. A follow up notification will be made when the maintenance work has been completed."
* * * UPDATE FROM BRUCE HUGO TO DONALD NORWOOD AT 0601 EDT ON 10/16/2011 * * *
The licensee returned ERDS to service at 0245 PDT on 10/16/2011.
The licensee notified the NRC Resident Inspector.
Notified R4DO (Whitten). |
| Power Reactor | Event Number: 47345 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DON TAYLOR
HQ OPS Officer: STEVE SANDIN | Notification Date: 10/14/2011
Notification Time: 15:30 [ET]
Event Date: 10/14/2011
Event Time: 14:40 [EDT]
Last Update Date: 10/14/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
MIKE ERNSTES (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 | Cold Shutdown | 0 | Cold Shutdown | Event Text BEARING COOLING WATER DISCHARGE INTO LAKE
"On 10/14/2011 at 0322 [EDT], Operations identified during operator rounds that the bearing cooling tower basin was overflowing. Earlier in the night the control room had received a bearing cooling basin high level alarm, verified that the bearing cooling tower basin was not overflowing and was monitoring the level from control room indications. The Control Room indications of bearing cooling basin level had remained steady. The overflow condition was due to leak by from a motor operated valve (MOV) which had been used earlier to add water to the bearing cooling basin. The leaking MOV was manually torqued shut which isolated the overflow discharge. Investigation of the inaccurate level indication is ongoing.
"Samples of the bearing cooling water were analyzed by Chemistry. All chemical parameters analyzed were within VPDES (Virginia Pollutant Discharge Elimination System) limits. Bearing Cooling chemistry is maintained to ensure compliance with the North Anna VPDES permit. It is estimated that 272 gallons may have been discharged to the lake.
"At 1440 hours on October 14, 2011, a 24-hour notification of the unusual discharge was made to the Virginia Department of Environmental Quality In accordance with the North Anna VPDES permit.
"This issue is being reported per 10CFR50.72(b)(2)(xi) as an event where notification of other government agencies has been made."
The licensee informed the NRC Resident Inspector. | |