| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/12/2014 - 05/13/2014 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 50082 | Rep Org: ALABAMA RADIATION CONTROL
Licensee: DUNN CONSTRUCTION
Region: 1
City: BIRMINGHAM State: AL
County:
License #: 812
Agreement: Y
Docket:
NRC Notified By: MYRON RILEY
HQ OPS Officer: JEFF ROTTON | Notification Date: 05/02/2014
Notification Time: 16:30 [ET]
Event Date: 05/02/2014
Event Time: 05:30 [CDT]
Last Update Date: 05/02/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WILLIAM COOK (R1DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
The following was provided by the State of Alabama via facsimile:
"On the morning of May 2, 2014 at approximately 0530 CDT, a CPN model MC-3 moisture density gauge, serial number M30129990, containing 10 millicuries of Cs-137 and 50 millicuries of Am-241:Be was damaged while in use at a temporary job site in Birmingham, Alabama when it was run over by a motorist. The licensee, Dunn Construction, notified the Alabama Office of Radiation Control at 0803 CDT. Dunn Construction is authorized to possess and use radioactive material under their Alabama Radioactive Material License No. 812. The licensee representative stated that the source rod became unattached, but was returned to the shielded position. Radiation levels around the gauge were found to be within the normal range. The gauge was placed back in the transport container and returned to the licensee's facility. The licensee was advised to perform a leak test of the gauge."
Alabama Incident 14-14 |
| Power Reactor | Event Number: 50105 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JAMES DEDIC
HQ OPS Officer: DONG HWA PARK | Notification Date: 05/11/2014
Notification Time: 16:00 [ET]
Event Date: 05/11/2014
Event Time: 08:02 [CDT]
Last Update Date: 05/12/2014 | 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 | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF THE METEOROLOGICAL TOWER COMPUTER SYSTEM
"This notification is being made due to a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii). At 0802 (CDT), on 05/11/2014, the meteorological tower computer system failed which resulted in a loss of meteorological data to the plant. Information Technology personnel have reported to the plant for investigation. Proceduralized compensatory measures for dose assessment include use of National Weather Service followed by historically determined default values.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 50106 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: TODD STRINGFELLOW
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 05/12/2014
Notification Time: 11:13 [ET]
Event Date: 05/12/2014
Event Time: 07:31 [EDT]
Last Update Date: 05/12/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DON JACKSON (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text UNIT 2 STACK HIGH RANGE RADIATION MONITOR REMOVED FROM SERVICE FOR PRE-PLANNED MAINTENANCE
The Unit 2 Stack High Radiation Monitor, RM-8168, was removed from service for pre-planned maintenance. There are no actuations associated with this Radiation Monitor.
Testing was completed and the radiation monitor was restored to operable at 1013 EDT, on 5/12/14.
The licensee has informed the NRC Resident Inspector and applicable State and Local authorities. |
| Power Reactor | Event Number: 50108 | 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: DAVID LEWIS
HQ OPS Officer: PETE SNYDER | Notification Date: 05/12/2014
Notification Time: 14:48 [ET]
Event Date: 05/12/2014
Event Time: 10:20 [EDT]
Last Update Date: 05/12/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
DON 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 | Event Text POSTULATED HOT SHORT FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT
"During a review from industry operating experience it was identified that there are three additional unprotected DC control circuits for non safety related DC motors which are routed from the turbine building to other separate fire areas (this is in addition to the one circuit that was previously identified and submitted under event #50059). Fuses used to protect the motor power conductors appear to be inadequate to protect the control conductors. The concern is that under fire safe shutdown conditions, it is postulated that a fire in one area can cause short circuits potentially resulting in secondary fires or cable fires in other areas where the cables are routed. The secondary fires or cable failures are outside the assumptions of the 10 CFR 50 Appendix R Safe Shutdown Analysis.
"This condition is reportable as an 8 hour ENS report in accordance with 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition. Compensatory measures (fire watches) have been implemented for affected areas of the plant.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 50109 | Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAN PIPKIN
HQ OPS Officer: PETE SNYDER | Notification Date: 05/12/2014
Notification Time: 16:57 [ET]
Event Date: 05/12/2014
Event Time: 15:00 [CDT]
Last Update Date: 05/12/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
VINCENT GADDY (R4DO)
|
| 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 TRITIUM CONFIRMED IN WATER SAMPLES ON-SITE UNDERGROUND
"On May 12, 2014, at 1458 CDT, River Bend Station management determined that tritium confirmed to be present in water samples taken from in-leakage into the below-ground elevation of the turbine building basement, through an underground pipe penetration, was reportable in accordance with NEI 07-07, Ground Water Protection Initiative. The leakage was tested for gamma and tritium activity. No gamma contamination was detected. Tritium was measured at 28,270 picocuries per liter. The source and volume of the radioactive in-leakage is unknown.
"The leakage into the plant is currently being contained, and actions are in progress to identify the source. The Louisiana Department of Environmental Quality was notified at 1500 CDT today [5/12/14]. This event is being reported in accordance with 10 CFR 50.72(b)(2)(xi) as an event requiring notification of the state government.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 50110 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAN HUNT
HQ OPS Officer: PETE SNYDER | Notification Date: 05/12/2014
Notification Time: 17:37 [ET]
Event Date: 05/12/2014
Event Time: 08:45 [CDT]
Last Update Date: 05/12/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
HIRONORI PETERSON (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 97 | Power Operation | 97 | Power Operation | Event Text PLANNED MAINTENANCE ON SAFETY PARAMETER DISPLAY SYSTEM
"At 0845 [CDT] during planned maintenance, the annunciators which would indicate flooding in the Emergency Core Cooling System (ECCS) Pump Rooms to the max safe water level in the rooms were disabled. These max safe water level alarms are used to assess the emergency action level (EAL) entry condition (HA4) for flooding (ALERT classification).
"Compensatory measures are in place to perform periodic walk downs of RHR A, RHR B, RHR C, HPCS, LPCS, RCIC rooms and the fuel building basement once per shift to verify no leakage. Additionally, the annunciator for max normal water level is operational and pump run times are still available in the Main Control Room to indicate increased leakage into the ECCS rooms. This max normal water level alarm is used to assess the EAL entry condition (HU4) for flooding (Unusual Event classification) and EOP-8 entry.
"Since the operator compensatory actions that were established are not proceduralized, then this is reportable as a loss of emergency assessment capability under 10 CFR 50.72(b)(3)(xiii).
"The expected return to service time of all alarms is 2300 CDT."
The licensee will notify the NRC Resident Inspector. | |