| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/28/2014 - 08/29/2014 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 49566 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: STEVE SPEIRS
HQ OPS Officer: DANIEL MILLS | Notification Date: 11/21/2013
Notification Time: 10:38 [ET]
Event Date: 11/21/2013
Event Time: 02:29 [CST]
Last Update Date: 08/28/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DAVID HILLS (R3DO)
|
| 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 DIESEL GENERATOR INOPERABILITY
"Following preplanned maintenance on the inoperable 'A' Standby Diesel Generator (SBDG), the operability surveillance (STP-3.8.1-04A Slow Start from Normal Air) was in progress. While securing the 'A' SBDG, the 'B' SBDG control power failure annunciator was received.
"The 'B' Standby Diesel Generator was declared inoperable and Technical Specification 3.8.1.B was entered for the 'B' SBDG. Additionally, Technical Specification 3.8.1.D was entered for two Standby Diesel Generators inoperable. Technical Specification 3.8.1.D allows 2 hours to restore 1 SBDG to operable.
"At 0343 [CST], the 'A' SBDG was restored to operable and Technical Specification 3.8.1.D was exited.
"This condition is reported under 50.72(b)(3)(v)(D), any event or condition at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.
"The NRC Resident Inspector was informed."
* * * RETRACTION FROM BOB MURRELL TO DONALD NORWOOD AT 1348 EDT ON 8/28/2014 * * *
"The purpose of this notification is to retract a previous report made on 11/21/2013 at 1038 EST (EN 49566). Notification of the event to the NRC was initially made as a result of declaring both trains of the Emergency Diesel Generator (EDG) System inoperable due to receiving the 'B' EDG control power failure annunciator while the 'A' EDG was inoperable for pre-planned maintenance.
"Subsequent to the initial report, NextEra Energy Duane Arnold (NextEra) has determined that the 'B' EDG system was capable of performing its safety function and was fully operable, but degraded during the period that the 'A' EDG was inoperable for pre-planned maintenance. The cause of the annunciator was from an open fuse in the control power circuit that affected the annunciator system logic and did not affect the actual EDG control logic.
"This event is not considered a Safety System Functional Failure and is not reportable to the NRC as a Licensee Event Report (LER) per 10 CFR 50.73.
"The NRC Senior Resident Inspector has been notified."
Notified R3DO (Stone). |
| Agreement State | Event Number: 50388 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: TESTAMERICA LABORATORIES, INC.
Region: 4
City: ARVADA State: CO
County:
License #: CO 486-03
Agreement: Y
Docket:
NRC Notified By: JAMES GRICE
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 08/21/2014
Notification Time: 10:25 [ET]
Event Date: 08/12/2014
Event Time: [MDT]
Last Update Date: 08/21/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DRAKE (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - LEAKING ELECTRON CAPTURE DEVICE SEALED SOURCE
The following report was received from the State of Colorado via email:
"Event description: The Department [Colorado Department of Public Health and Environment] was notified via e-mail on 8/13/2014, by TestAmerica Laboratories Inc (license # CO 486-03), that a leak test result for a Ni-63 Electron Capture Device [ECD] source had shown counts exceeding 185 Bq.
"The licensee has removed the source from service, decontaminated the instrument that the ECD was mounted on and sent the unit, containing the source, to the manufacturer for repair and source replacement.
"The email was sent to the department pursuant to Section 4.58 of the Colorado Regulations.
"The Department has requested a few additional details regarding specifics of the source (serial Number, manufacturer, etc.) at this time and will populate the NMED database as soon as they are received."
Colorado Event Report ID No.: CO14-I14-21 |
| Power Reactor | Event Number: 50411 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOHN LAUDENBACH
HQ OPS Officer: HOWIE CROUCH | Notification Date: 08/28/2014
Notification Time: 10:09 [ET]
Event Date: 08/28/2014
Event Time: 09:00 [CDT]
Last Update Date: 08/28/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ANN MARIE STONE (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 89 | Power Operation | 89 | Power Operation | Event Text BOTH DISCHARGE CANAL RADIATION MONITORS REMOVED FROM SERVICE FOR PLANNED MAINTENANCE
'Planned preventive maintenance will render both divisions of discharge canal radiation monitors non-functional. As a result, this represents a loss of emergency assessment capability and is reportable under 10 CFR 50.72(b)(3)(xiii). The planned maintenance is expected to last two hours. During this time, alternate plant parameters will be monitored and sampling performed if needed. The health and safety of the public remains protected as the plant is operating in a normal condition.
"The NRC Resident Inspector was notified prior to removing the discharge canal radiation monitors from service." |
| Power Reactor | Event Number: 50413 | Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JASON DEPRIEST
HQ OPS Officer: DONALD NORWOOD | Notification Date: 08/28/2014
Notification Time: 18:26 [ET]
Event Date: 08/28/2014
Event Time: 12:27 [CDT]
Last Update Date: 08/28/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ANN MARIE STONE (R3DO)
|
| 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 AUXILIARY ELECTRIC EQUIPMENT ROOM HVAC INOPERABLE
"This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to Mitigate the Consequences of an Accident. While the 'B' train of Auxiliary Electric Equipment Room HVAC was inoperable and out of service for emergent repairs due to an oil leak, the 'A' train of Auxiliary Electric Equipment Room HVAC became inoperable due to a failure of the liquid line solenoid valve. The Main Control Room Envelope consists of the Main Control Room and the Auxiliary Electric Equipment Room. Both the Control Room HVAC and the Auxiliary Electric Equipment Room HVAC systems are required to be operable in the current mode.
"This is a loss of safety function for a system that is intended to mitigate the consequences of an accident and is discussed in chapter 6 of the UFSAR and is Tech Spec required and is safety related. Also, the system, structure, or component (SSC) is inoperable in a required mode in the Tech Spec applicability and there is no redundant equipment in the same system that is operable.
"The required actions of Tech Spec 3.7.5 were entered for this event. Online Risk remains Green. The station is currently pursuing repairs to both trains."
The licensee notified the NRC Resident Inspector. | |