| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/09/2013 - 04/10/2013 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 48874 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: TERRACON, INC.
Region: 4
City: COLORADO SPRINGS State: CO
County:
License #: 664-02
Agreement: Y
Docket:
NRC Notified By: MARK DATER
HQ OPS Officer: DONG HWA PARK | Notification Date: 04/02/2013
Notification Time: 10:55 [ET]
Event Date: 03/29/2013
Event Time: 10:06 [MDT]
Last Update Date: 04/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY KELLAR (R4DO)
FSME EVENTS RESOURCE ()
| Event Text AGREEMENT STATE REPORT - DAMAGED TROXLER MOISTURE DENSITY GAUGE
The following information was received from the State of Colorado via email:
"At 10:06 am on Friday, March 29, 2013 the Emergency Response Duty Officer was notified that there was an incident involving a portable moisture density gauge that had been run over by a piece of heavy construction equipment. The [Colorado] Department [of Public Health and Environment] responded by phone and contacted the RSO [Radiation Safety Officer] for Terracon, Inc., who was on site supervising the incident. The RSO reported that the gauge had been backed over by a Bobcat loader. The Bobcat loader had a counter balance weight on the rear of the equipment and this contacted the gauge damaging the outer casing. The RSO reported that the source had been fully retracted and was in the safe (shielded position). The RSO conducted a survey and the reading was 0.2 mr/hr at 1 foot. The gauge was loaded into the transport box and readied for transport back to storage at the Tarracon facility. The transport index on the box was 0.1 mr/hr and the RSO was given permission to transport gauge back to storage and perform a leak test before sending off for repair. The leak tests proved negative and the gauge was [shipped] for repair. This licensee will be issued a Notice of Violation of Part 4.26.1: 'The licensee shall control and maintain constant surveillance of licensed or registered radioactive material that is in an unrestricted area and that is not in storage or in a patient.'
"Licensee causing incident: Terracon, Inc., Colo. License number 664-02
"Density gauge model and serial number: Troxler model 3430 s/n 28184
"Isotopes in gauge: Cs-137 (9mCi); Am-241 (40mCi)
"Survey meter used by RSO: Radiation Alert Monitor 4, s/n 42585, Cal. Date: August 7, 2012"
Incident number: I13-03 |
| Agreement State | Event Number: 48875 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: GOODYEAR TIRE & RUBBER COMPANY
Region: 1
City: FAYETTEVILLE State: NC
County:
License #: 026-0352-0G
Agreement: Y
Docket:
NRC Notified By: WILLIAM JOHNSON
HQ OPS Officer: PETE SNYDER | Notification Date: 04/02/2013
Notification Time: 13:24 [ET]
Event Date: 03/30/2013
Event Time: 17:08 [EDT]
Last Update Date: 04/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DWYER (R1DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - FIRE IN PLANT MAY HAVE DAMAGED TWO PROCESS GAUGES
The following information was received via facsimile:
Two process gauges containing Sr-90 (approximately 50 mCi ea.) at the Goodyear Tire and Rubber Company facility in Fayetteville, NC may have sustained damage as a result of a fire. No leakage is reported. The gauges were mounted in a "LOW - Minimal or Low risk area."
The State of North Carolina will be investigating.
NC Incident No. 13-06. |
| Non-Agreement State | Event Number: 48876 | Rep Org: RAPID CITY REGIONAL HOSPITAL
Licensee: RAPID CITY REGIONAL HOSPITAL
Region: 4
City: RAPID CITY State: SD
County:
License #: 40-00238-04
Agreement: N
Docket:
NRC Notified By: JAMES McKEE
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/02/2013
Notification Time: 14:50 [ET]
Event Date: 02/26/2013
Event Time: [MDT]
Last Update Date: 04/02/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
| Person (Organization):
RAY KELLAR (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text MEDICAL EVENT INVOLVING DELIVERED DOSE EXCEEDING PRESCRIBED DOSE >20%
During a review of post implant dosimetry for prostate cancer treatment at 0800 hours [MDT] on 4/02/13, it was discovered that a patient received 145 gray vice 110 gray prescribed as a "boost" treatment. The prescribing physician will inform the patient and consult with the urologist. The error occurred due to not taking into account that the prescribed dose was a "boost" to the previously delivered 45 gray on 2/14/13, and used the default value of 145 gray for initial treatment. The physician is evaluating any potential adverse consequences for the patient.
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| Power Reactor | Event Number: 48900 | Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: JOHN PULS
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/09/2013
Notification Time: 09:05 [ET]
Event Date: 04/09/2013
Event Time: 07:30 [CDT]
Last Update Date: 04/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DAVE PASSEHL (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 AUXILIARY BUILDING VENT MONITOR OUT OF SERVICE FOR PLANNED MAINTENANCE
"On April 9, 2013, at approximately 0730 hours [CDT], the Kewaunee Power Station declared the Auxiliary Building Vent Special Particulate Iodine Noble Gas 'SPING' Radiation Monitor (Mid and Hi Range) nonfunctional for planned maintenance. The Emergency Response Organization (ERO) team has been notified of the Auxiliary Building Vent SPING nonfunctionality due to planned maintenance.
"The SPING is expected to be out of service for approximately 3 hours.
"Although manual 'grab samples' could be used as a backup, this condition is being reported in accordance with 10CFR50.72(b)(3)(xiii) as an event that results in a major loss of emergency assessment capability (unable to sufficiently identify the upper two emergency action levels for offsite radiation conditions).
"The NRC Resident Inspector has been notified."
See similar EN #48881 and 48891.
* * * UPDATE FROM GARY AHRENS TO HOWIE CROUCH AT 1018 EDT ON 4/9/13 * * *
SPING was returned to service at 0819 CDT. The licensee informed the NRC Resident Inspector.
Notified R3DO (Passehl). |
| Power Reactor | Event Number: 48901 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MATTHEW BUSCH
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/09/2013
Notification Time: 09:42 [ET]
Event Date: 04/09/2013
Event Time: 02:35 [EDT]
Last Update Date: 04/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
HAROLD GRAY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 98 | Power Operation | 98 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text POWER LOST TO METEOROLOGICAL INSTRUMENTATION
"At 0235 EDT on 4-9-13, due to an offsite power transformer fault, power was lost to site support buildings and all meteorological instrumentation. This event is being reported under 10CFR50.72(b)(3), major loss of emergency assessment capabilities.
"At 0455 EDT, power was restored to meteorological instrumentation in the control room. During the power outage, limited meteorological data remained available via telephone from the National Weather Service and the Fitzpatrick site met tower. Plant operations at both units 1 and 2 were not affected. Both units remain at full power."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 48904 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [ ] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TODD CHRISTENSEN
HQ OPS Officer: VINCE KLCO | Notification Date: 04/09/2013
Notification Time: 17:07 [ET]
Event Date: 02/11/2013
Event Time: 06:13 [CDT]
Last Update Date: 04/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
MALCOLM WIDMANN (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text MANUAL INITIATION OF REACTOR CORE ISOLATION COOLING SYSTEM
"On February 11, 2013, at 0613 hours [CDT], the Reactor Core Isolation Cooling (RCIC) system was manually started during a planned Unit 3 reactor shutdown. A Reactor Feedwater recirculation piping separation resulted in the loss of condenser vacuum and subsequent unavailability of the Main Turbine Bypass Valves. The RCIC system was manually started at 9.2" of condenser vacuum in order to control reactor water level in anticipation of loss of Reactor Feedwater Pumps (RFPs) which occurs at 7" of condenser vacuum. Safety Relief Valves (SRVs) were manually operated to maintain reactor pressure. The reactor water level was controlled in the normal band by RCIC, and Reactor Pressure was controlled with a combination of Reactor Core Isolation Cooling (RCIC) system and SRV manual operation. All systems operated as designed and Reactor water level was maintained in the prescribed band. No Emergency Core Cooling System (ECCS) or Reactor Core Isolation Cooling (RCIC) reactor water level initiation set points were reached. RCIC operation was secured at 1449 [CDT] on 2/11/2013.
"This event is reportable within 8 hours per 10CFR50.72(b)(3)(iv)(A). During a review of operating logs it was identified that this event met reporting requirements and had not been reported. Therefore, this report does not comply with the 8 hour requirement. This condition has been entered into the corrective action program. Additionally, an LER is required within 60 days per 10CFR50.73(a)(2)(iv)(A).
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 48905 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: KENNETH P. BRESLIN
HQ OPS Officer: STEVE SANDIN | Notification Date: 04/09/2013
Notification Time: 17:08 [ET]
Event Date: 04/09/2013
Event Time: 13:15 [EDT]
Last Update Date: 04/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JAMES TRAPP (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 LOSS OF EMERGENCY NOTIFICATION SYSTEM TELEPHONE
"On April 9, 2013 at 1315 [EDT] Hope Creek Operations personnel identified that the NRC ENS phone line was unavailable for Hope Creek Generating Station. The loss of the NRC ENS line was verified by the Hope Creek Shift Manager via backup land line communication to the NRC Operation Center at 1355 [EDT]. At that time, the NRC Operations Center submitted a repair ticket to the phone service provider. NRC ENS phone availability was verified restored to service at 1618 [EDT] with the NRC Operations Center.
"The loss of the phone line had no effect on plant operations and the unit remains at 100% power.
"Additionally, Emergency Response Data System (ERDS) capability was verified to remain intact during this time period and was available to transmit data.
"No personnel injuries resulted from the event.
"The NRC Resident Inspector has been notified." | |