| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/16/2010 - 08/17/2010 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 46170 | Rep Org: KANSAS DEPT OF HEALTH & ENVIRONMENT
Licensee: CODER X-RAY SERVICE
Region: 4
City: McPHERSON State: KS
County:
License #: 21-B165-01
Agreement: Y
Docket:
NRC Notified By: AARON SHORT
HQ OPS Officer: PETE SNYDER | Notification Date: 08/12/2010
Notification Time: 12:22 [ET]
Event Date: 02/13/2010
Event Time: [CDT]
Last Update Date: 08/16/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
NEIL OKEEFE (R4DO)
MICHELE BURGESS (FSME)
ILTAB via email ()
| Event Text AGREEMENT STATE REPORT - BREAK-IN AT RADIOGRAPHY SOURCE STORAGE LOCATION
On 2/13/2010, Coder X-Ray Services experienced a break-in at their of McPherson, KS business location. Local police responded within minutes. A laptop computer was stolen but there was no indication of attempted theft involving radioactive sources.
The licensee added additional security measures as part of their increased controls for radioactive materials.
The State of Kansas discovered this event on a recent inspection.
* * * UPDATE FROM AARON SHORT TO JOHN KNOKE AT 1603 EDT ON 8/16/10 * * *
The State of Kansas received a police report identifying the burglary at Coder X-ray and Welding in McPherson Kansas. The State also received a letter from the licensee outlining additional security measures they are taking at their facility.
Contact the Headquarters Operations Officer for further details.
Notified R4DO (Geoffrey Miller), FSME (Richard Turtil) and emailed ILTAB |
| Power Reactor | Event Number: 46178 | Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WALTER SMITH
HQ OPS Officer: DONG HWA PARK | Notification Date: 08/16/2010
Notification Time: 06:23 [ET]
Event Date: 08/16/2010
Event Time: 02:06 [CDT]
Last Update Date: 08/16/2010 | 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):
JAMNES CAMERON (R3DO)
JOHN THORP (NRR)
WILLIAM GOTT (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIPS AT BOTH UNITS
"Braidwood Unit 2 automatically tripped at 0206 [CST] due to a turbine generator trip due to generator lockout relay actuation. All systems responded as expected, with the auxiliary feed water pumps starting on Low-2 Steam Generator level. The Unit is stable in Mode 3, all primary systems are stable with the secondary heat sink being maintained via aux feed water and the steam dumps. Offsite power is supplying Unit 2, and both emergency diesel generators are available. Cause of generator lockout is under investigation.
"Braidwood Unit 1 automatically tripped at 0219 [CST] on a turbine trip caused by a loss of condenser vacuum. All systems responded as expected, with the auxiliary feed water pumps supplying steam generator levels. Secondary heat sink is steam generator PORVs. One steam generator safety valve is not fully seated. No steam generator tube leakage. Cause of the loss of vacuum is under investigation.
"For both Units all control rods fully inserted. There were no complications during the trip and all systems functioned as required. Offsite power remained available throughout the transient.
"The licensee notified the NRC resident inspector."
Braidwood Unit 1's loss of condenser vacuum was caused by the loss of an electrical bus supplying the circ water pumps. At the time of this report, both plants were in a normal shutdown electrical lineup with the exception of the deenergized bus supplying power to the circ water pumps on Unit 1. The steam generator safety valve that has not fully seated was characterized as weeping a small amount of steam. The licensee is uncertain if the Unit 1 trip is related to the Unit 2 trip. |
| Power Reactor | Event Number: 46179 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: RICKY GIVENS
HQ OPS Officer: JOHN KNOKE | Notification Date: 08/16/2010
Notification Time: 18:02 [ET]
Event Date: 08/16/2010
Event Time: 13:40 [CDT]
Last Update Date: 08/16/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
BINOY DESAI (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 50 | Power Operation | 45 | Power Operation | | 2 | N | Y | 50 | Power Operation | 45 | Power Operation | | 3 | N | Y | 50 | Power Operation | 45 | Power Operation | Event Text NPDES LIMIT WAS EXCEEDED FOR RIVER TEMPERATURE DISCHARGE REQUIREMENTS
"Browns Ferry Nuclear Plant inadvertently exceeded a limitation of its National Pollutant Discharge Elimination System (NPDES) Permit for Tennessee River temperature conditions which was reported to the Alabama Department of Environmental Management (ADEM) at 1340 Central Daylight Time, on August 16, 2010. As such, this is being reported in accordance with 10 CFR 50.72(b)(2)(xi) as 'Any event or situation, related to the health and safety of the public or on-site personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made.'
"The NPDES Permit requires that when the 24 hour ambient average river temperature exceeded 90 degrees Fahrenheit, the 24 hour average downstream river temperature may equal but not exceed the upstream value. The 24 hour average upstream temperature was found to be 90.4 (rounded to 90) degrees Fahrenheit and the downstream temperature was found to be 90.6 (rounded to 91) degrees Fahrenheit.
"Browns Ferry had been maintaining compliance with the NPDES permit. The departure is thought to be due to a summer storm cooling off the upstream temperature. With the time delay between upstream temperature changes and the ensuing rate at which the downstream temperature changes are observed, the resultant 24 hour average downstream river temperature exceeded the upstream value. Duration of this condition was found to be only several hours.
"The three Browns Ferry units, which had already been derated to approximately 50 percent rated thermal power in order to maintain compliance with the NPDES Permit river temperature limits, were further derated to achieve compliance with the NPDES Permit.
"There is no corresponding requirement for written follow-up in accordance with 10 CFR 50.73."
The licensee has notified the NRC Resident Inspector. |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 46182 | Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: LEON RAFNER
HQ OPS Officer: JOE O'HARA | Notification Date: 08/17/2010
Notification Time: 13:56 [ET]
Event Date: 08/17/2010
Event Time: 03:00 [PDT]
Last Update Date: 09/14/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
GEOFFREY MILLER (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNANALYZED CONDITION DUE TO POTENTIAL WIRING DISCREPANCY
"On August 16, 2010, at about 0100 PDT, SONGS Unit 2 Train 'A' Emergency Diesel Generator (EDG) 2G002 was removed from service for planned maintenance. Train 'A' EDG is the Appendix R protected Train.
"At about 1545 the same day, Southern California Edison (SCE) discovered a potential wiring discrepancy in the electronic governor. At 0300 on August 17, 2010, SCE determined two wires on a fire isolation fuse were confirmed to be terminated differently than specified in plant drawings and that the discrepancy would prevent the fuse and associated fire isolation switch from performing its Appendix R fire isolation function for the Train 'A' EDG. In accordance with NUREG-1022, Rev. 2, SCE is reporting this occurrence in accordance 10CFR50.72(b)(3)(ii)(B).
"While the incorrect wiring impacted the Appendix R qualifications of the Train 'A' EDG, it did not impact its other design functions and the EDG was capable to fulfill its safety function for all other Design Basis Events. Therefore, SCE considers the safety significance of the condition to be minimal.
"In accordance with LCS specification 3.7.113.1 Condition A, SCE will implement hourly Fire Watches for the impacted plant areas until such time that the wiring on the Unit 3 Train 'A' Emergency Diesel Generator 3G002 is conformed to be correct or has taken actions to correct any wiring discrepancy. An evaluation will be conducted to determine the cause of this condition.
"At the time of this occurrence, Unit 2 and Unit 3 were both at 100% power."
"The NRC Resident Inspector will be notified of this occurrence and will be provided with a copy of this report."
* * * RETRACTION FROM KELMENSON TO KLCO ON 9/14/10 @ 1528 [EDT]* * *
The licensee is retracting the event based on the following:
"Upon further investigation, SCE determined the suspected wiring discrepancy was only an issue with an elementary diagram that was used for circuit verification. SCE had already flagged this elementary diagram as requiring revision and a change to the diagram was pending and had not been released to the field. The fire isolation fuse was wired correctly."
"Consequently, SCE is retracting the 8-Hour Telephone Notification made to the NRC on August 17, 2010 (Event Log No. 46182)."
"The NRC Resident Inspector will be notified of and will be provided with a copy of this retraction."
Notified the R4DO (Clark) |
| Power Reactor | Event Number: 46183 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOEL HOWARD
HQ OPS Officer: JOE O'HARA | Notification Date: 08/17/2010
Notification Time: 16:32 [ET]
Event Date: 08/17/2010
Event Time: 07:35 [EDT]
Last Update Date: 08/17/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
BINOY DESAI (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 EMPTY BEER CAN FOUND INSIDE THE PROTECTED AREA
"On August 17, 2010, an empty beer can was discovered in a recycle container inside the Protected Area (PA). The can has been removed from the PA. Further investigation as to how the can was introduced into the PA is in progress. No personnel fitness-for-duty issues related to the consumption of alcohol have been identified. The presence of alcohol with the PA is being reported in accordance with 10CFR26.719(b)(1)."
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 46184 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: CURT STEFFES
HQ OPS Officer: JOE O'HARA | Notification Date: 08/17/2010
Notification Time: 16:54 [ET]
Event Date: 08/17/2010
Event Time: 14:14 [CDT]
Last Update Date: 08/17/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
NICK VALOS (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM INITIATED DUE TO RECIRCULATION PUMP TRIP
"On August 17, 2010, at 1414 hours, a manual scram was inserted on Unit 2 due to rising reactor water level. The water level increase was caused by a trip of the 2B Recirculation Pump. Restoration of the 2B Recirculation Pump Programmable Logic Controller (PLC) on the 2B Adjustable Speed Drive (ASD) was in progress at the time of the event. Following the reactor scram, reactor water level decreased to approximately minus 15 inches, which resulted in automatic Group II and III isolations as expected. All systems responded properly to the event. The cause of the event is still under investigation.
"Unit I was unaffected by the event and remains at 100% power.
"This report is being made in accordance with 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A)."
All control rods inserted on the scram. No ECCS initiations occurred. No safety or relief valves lifted. The unit is stable in Mode 3 at 926 psig and 530 degrees Fahrenheit. Pressure is being controlled on the turbine bypass system.
The licensee notified the NRC Resident Inspector and the Illinois Department of Nuclear Safety. | |