| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/02/2012 - 05/03/2012 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 47860 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: RENEGADE TESTING & INSPECTION, INC.
Region: 1
City: TAMPA State: FL
County:
License #: 3891-2
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/24/2012
Notification Time: 14:03 [ET]
Event Date: 04/06/2012
Event Time: [EDT]
Last Update Date: 04/24/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TODD JACKSON (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text FLORIDA AGREEMENT STATE REPORT - POTENTIAL OVEREXPOSURE TO RADIOGRAPHER
The following information was obtained from the State of Florida via email:
"On April 16, [a licensee] employee notified [the] RSO that his 0-200 pocket detector had gone off scale ten days earlier. His film badge was immediately sent to Rad Detection Services for processing. It was reported to have 25 Rem whole body exposure. This office [Florida Bureau of Radiation Control] was informed on 24 April. The RSO has tried to recreate the scenario but he can't come up with a 4.5 minute exposure scenario. RSO is considering a blood test. Licensee will provide a written report. Florida is investigating."
FL Incident No. FL 12-039
The camera involved was an INC IR-100 Model 32, serial number R887, with a 65 Ci Ir-192 source. |
| Power Reactor | Event Number: 47887 | Facility: OCONEE
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: STEPHEN NEWMAN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/02/2012
Notification Time: 12:18 [ET]
Event Date: 05/02/2012
Event Time: 10:05 [EDT]
Last Update Date: 05/02/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
| Person (Organization):
DEBORAH SEYMOUR (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 | | 3 | N | N | 0 | Refueling Shutdown | 0 | Refueling Shutdown | Event Text POTENTIALLY CONTAMINATED INDIVIDUAL TRANSPORTED OFFSITE
"On 5/2/2012 at approximately 0914 hours, a Duke Energy contract worker performing activities in the Unit 3 reactor basement (currently defueled in a planned refueling outage), experienced dizziness and subsequently experienced a loss of consciousness. Upon discovery, the plant emergency medical team was dispatched to aid the individual. The individual soon regained consciousness but was immediately transported, via ambulance, to a local hospital for treatment. Accompanying the individual were two (2) radiation protection and one (1) Duke energy Public Affairs individuals. The individual was transported out of the protected area at approximately 1005 hours. Because the potentially contaminated individual's back could not be surveyed prior to being transported offsite, the individual was considered potentially contaminated. As such, this event is being reported as an 8-hour prompt report pursuant to 10CFR50.72(b)(3)(xii).
"On 5-2-2012 at approximately 1100 hours, the radiation protection personnel that accompanied the individual to the medical facility reported that the individual was determined not to be contaminated. As a result, no follow-up status report is planned.
"The licensee notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 47888 | Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: CHRIS GIAMBRONE
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/02/2012
Notification Time: 13:15 [ET]
Event Date: 05/02/2012
Event Time: 07:24 [EDT]
Last Update Date: 05/02/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
RICHARD CONTE (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 MANUAL INITIATION OF SECONDARY CONTAINMENT ISOLATION
"In response to a trip of Unit 1 reactor enclosure [secondary containment] HVAC and subsequent loss of reactor enclosure delta-p, a Unit 1 manual secondary containment isolation was initiated per station procedures. This manual initiation also resulted in an isolation signal to containment atmosphere control (CAC) system valves and primary containment instrument gas (PCIG) system valves. System responses were as expected.
"Unit 1 secondary containment delta-p was restored via standby gas treatment system (SGTS), and Unit 1 secondary containment integrity remains intact and operable.
"Investigation of the trip of Unit 1 reactor enclosure HVAC is ongoing.
"This is being reported under 50.72(b)(3)(iv) for containment isolation signal affecting containment isolation valves in more than one system."
The licensee notified the NRC Resident Inspector. |
| Non-Agreement State | Event Number: 47889 | Rep Org: ESCANABA PAPER COMPANY
Licensee: ESCANABA PAPER COMPANY
Region: 3
City: ESCANABA State: MI
County:
License #: 21-17630-01
Agreement: N
Docket:
NRC Notified By: DARREN HENDON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/02/2012
Notification Time: 14:16 [ET]
Event Date: 05/02/2012
Event Time: [EDT]
Last Update Date: 05/02/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
MARK RING (R3DO)
ANGELA MCINTOSH (FSME)
| Event Text DENSITY GAUGE SHUTTER STUCK OPEN
The shutter on a Kay Ray model 7063PS, S/N S99F1501, was determined to be stuck open during its annual shutter check. The gauge shutter was last tested satisfactorily on 5/6/2011. The gauge measures density in a line kiln and the shutter is normally open. The area is not normally accessible to personnel i.e. the open shutter does not pose a risk to the operators. The source is a 50 mCi Cs-137 source. |
| Power Reactor | Event Number: 47892 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: NATHAN SEID
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 05/02/2012
Notification Time: 19:02 [ET]
Event Date: 05/02/2012
Event Time: 11:55 [CDT]
Last Update Date: 05/02/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
GREG WERNER (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling Shutdown | 0 | Refueling Shutdown | Event Text POTENTIAL UNANALYZED CONDITION WITH CONTAINMENT PRESSURE INSTRUMENTS
"While investigating operating experience from another station it was determined that Fort Calhoun Station (FCS) is subject to similar conditions. The operating experience involved setpoint drift of safety related pressure switches beyond what had been accounted for in the station's safety analyses.
"Following investigation and evaluation, it was determined that pressure switches that provide safety related signals for high containment pressure to the reactor protection system (RPS) and engineered safeguards actuation circuitry may be similarly affected at FCS. The impact of the potential drift was evaluated, and it was determined that neither RPS nor the engineered safeguard circuitry may actuate at the required containment pressure of 5 psig. An evaluation determined that the actuation may not occur until slightly higher than the required pressure. Other systems are currently being evaluated to see if this same condition applies.
"The station is in MODE 5, refueling shutdown condition, and there is no immediate safety concern."
The pressure instruments are located in the penetration area which is subject to elevated temperatures.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 47893 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: LEE GOLDSTEIN
HQ OPS Officer: PETE SNYDER | Notification Date: 05/02/2012
Notification Time: 22:12 [ET]
Event Date: 05/02/2012
Event Time: 17:58 [EDT]
Last Update Date: 05/02/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DEBORAH SEYMOUR (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 37 | Power Operation | 37 | Power Operation | Event Text HIGH PRESSURE COOLANT INJECTION INOPERABLE DUE TO ERRATIC GOVERNOR OPERATION
"On 5/2/2012 at 1758 EDT, the Unit 1 High Pressure Coolant Injection (HPCI) System was declared inoperable in accordance with Technical Specification 3.5.1 due to the flow controllers inability to maintain stable system flow and discharge pressure. This failure was discovered during the high steam pressure operability run (i.e., within 48 hours of achieving adequate test pressure following a scheduled refueling/maintenance outage) required by Technical Specification Surveillance 3.5.1.7 following refueling outage B119R1.
"This report is being made in accordance with 10 CFR 50.72(b)(3)(v)(D), as a condition that at the time of discovery could have prevented the fulfillment of the safety function of systems that are needed to mitigate the consequences of an accident.
"The safety significance of this event is considered minimal. The Reactor Core Isolation Cooling (RCIC) system, Automatic Depressurization System (ADS) and Low Pressure Emergency Core Cooling Systems (ECCS) remain operable at this time. Actions have been taken to protect redundant safety systems.
"The NRC Resident Inspector has been notified." | |