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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/21/2016 - 03/22/2016
** EVENT NUMBERS **
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| Agreement State |
Event Number: 51786 |
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: FROEHLING & ROBERTSON
Region: 1
City: KNIGHTSDALE State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: LEE COX
HQ OPS Officer: MARK ABRAMOVITZ |
Notification Date: 03/11/2016
Notification Time: 19:50 [ET]
Event Date: 03/11/2016
Event Time: 15:34 [EST]
Last Update Date: 03/11/2016 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI) |
Event Text
AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
The following report was received via e-mail:
"A private company reported a soil density meter was damaged and an increase in background radiation was detected due to possible shielding damage.
"Event terminated. Gauge has been safely transported back to the manufacturer, Instrotek at 1905 [EST]. Radiation surveys at the scene indicated sources were intact and not leaking. Swipes on the source rod, device and equipment confirmed no contamination at the scene. Scene has been released for general public use.
"Radioactive Material Licensee: Froehling & Robertson
Incident Location: 1202 Redwood Valley Lane, Knightdale, NC
Gauge: Instrotek 3500
Radioactive Material: 10 mCi Cesium 137; 40 mCi Americium 241, Beryllium
"Summary:
Radiation Protection Staff arrived on site at 1720 [EST].
Gauge housing was found to be damaged along with a bent source rod.
When staff approached the gauge, at 5 feet, the readings were 5mR/hr (milliRem per hour) indicating that sources were not properly shielded.
When staff surveyed the bottom of the gauge at the shutter, the source rod fell out backwards from the top of the device.
All items were moved to survey the area around where the accident occurred to see if the sources had fallen out in the compacted soil. They had not.
Readings were background for the area of 25 to 30 uR/hr (microRem per hour) indicating the sources were still in the source rod.
Staff put the source rod back in the gauge housing.
Readings at the bottom of the device with the source rod in place, showed readings of 150 to 200 mR/hr. This confirmed the sources were in the rod, but indicated the shutter shielding the sources was not functioning properly.
The reassembled gauge was placed back in the certified DOT shipping container and properly blocked and braced in the licensee's (Froehling & Robertson) truck.
Staff followed the licensee to Instrotek where the device was safely stored until the manufacturer can assess the damage.
US Nuclear Regulatory Commission notified via this email
Radiation Protection Section will continue its compliance investigation of why this event occurred.
Radiation Protection Section will update the National Material Event Database.
Pictures to be uploaded into event reporting.
No further updates will be given." |
| Agreement State |
Event Number: 51790 |
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: FOOTHILLS GEOTECHNICAL SERVICES
Region: 4
City: PLACERVILLE State: CA
County:
License #: 7448-09
Agreement: Y
Docket:
NRC Notified By: NIKA HEWADIKARAM
HQ OPS Officer: HOWIE CROUCH |
Notification Date: 03/14/2016
Notification Time: 16:05 [ET]
Event Date: 03/12/2016
Event Time: [PDT]
Last Update Date: 03/14/2016 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
GREG WARNICK (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
CNSNS (MEXICO) (FAX)
ILTAB (EMAI) |
Event Text
CALIFORNIA AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE
The following information was obtained from the State of California via email:
"On 03/14/16, RHB [California Department of Public Health - Radiologic Health Branch] was contacted via email by the California Office of Emergency Services (OES) to report a stolen moisture density gauge. This is a Troxler Model 3440, S/N T34436628, gauge containing 9 mCi of Cesium -137 and 44 mCi of Americium - 241. This gauge was stolen from the licensee's storage facility located in Placerville, CA on 03/12/16. [The licensee radiation safety officer] RSO had filed a report with the El Dorado County Sheriff's office. There is no report of damage to the device, however, the whereabouts of the gauge is unknown. RHB will be following up with this investigation."
California Report Number: 5010-031416 |
| Power Reactor |
Event Number: 51808 |
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: RODRICK JOHNSON
HQ OPS Officer: STEVEN VITTO |
Notification Date: 03/19/2016
Notification Time: 22:51 [ET]
Event Date: 03/19/2016
Event Time: 17:10 [CDT]
Last Update Date: 03/22/2016 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(B) - POT RHR INOP |
Person (Organization):
MARK HAIRE (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 |
| 2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
UNANALYZED CONDITION THAT COULD CHALLENGE RHR EQUIPMENT DURING FLOOD CONDITIONS
"Two (2) potentially degraded flood barriers at penetrations 0073-01-0034 and 0073-01-0063 were identified in the area between the Unit 1 Turbine Building and Auxiliary Building. The deficient barriers are a 'blockout section' of the floor designed to house multiple penetrations that transition from the Turbine Building to the Auxiliary Building. Attempts have been made to investigate the status of the flood barrier with no definitive results. Investigations and additional evaluations are continuing, however, it is currently unknown if the aggregate of these two flood barriers could potentially overwhelm and flood the Auxiliary Building which would challenge equipment necessary to remove residual heat and constitute an unanalyzed condition.
"Based on current conditions (i.e., no forecast flooding conditions), this condition does not present an immediate safety concern.
"This condition has been determined to be reportable per 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v)(B). This condition is a non-emergency condition. This condition has been entered into the Corrective Action Program.
"Compensatory measures have been prepared to allow placement of a seal over the identified deficient barriers. If required these seals can be installed well in advance of forecast flood conditions. Permanent repairs are currently being designed for installation."
The NRC Resident Inspector has been notified.
* * * UPDATE AT 0044 EDT ON 3/22/2016 FROM KEITH LEDBETTER TO MARK ABRAMOVITZ * * *
"This is an 8 hour non-emergency supplemental notification to previously issued Event Notification number 51808. In EN 51808, two non-functional barriers were identified and reported, and during an extent of condition review, a third barrier has been identified that does not conform to expected flood barrier standards
"A potentially degraded flood barrier at 'blockout' penetration 0073-01-9018 was identified in the area between the Unit 1 Turbine Building and Auxiliary Building. The deficient barrier is a 'blockout section' of the floor designed to house multiple penetrations that transition from the Turbine Building to the Auxiliary Building. Attempts have been made to investigate the status of the flood barrier with no definitive results. Investigations and additional evaluations are continuing; however, it is currently unknown if this flood barrier could potentially be overwhelmed and flood the Auxiliary Building which would challenge equipment necessary to remove residual heat and constitute an unanalyzed condition.
"Based on current conditions (i.e., no forecast flooding conditions), this condition does not present an immediate safety concern.
"This condition has been determined to be reportable per 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v)(B). This condition is a non-emergency condition. This condition has been entered into the Corrective Action Program.
"Compensatory measures have been prepared to allow placement of a seal over the identified deficient barrier. If required this seal can be installed well in advance of forecast flood conditions. Permanent repairs are currently being designed for installation."
The NRC Resident Inspector was notified earlier in the evening that this event would be updated.
Notified the R4DO (Haire). |
| Power Reactor |
Event Number: 51809 |
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN HARKINS
HQ OPS Officer: VINCE KLCO |
Notification Date: 03/20/2016
Notification Time: 23:51 [ET]
Event Date: 03/20/2016
Event Time: 21:54 [EDT]
Last Update Date: 03/21/2016 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(ii)(A) - DEGRADED CONDITION |
Person (Organization):
JAMES NOGGLE (R1DO)
SCOTT MORRIS (NRR)
BERNARD STAPLETON (IRD) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
Y |
15 |
Power Operation |
15 |
Power Operation |
Event Text
TECHNICAL SPECIFICATION (TS) REQUIRED SHUTDOWN DUE TO PRESSURE BOUNDARY LEAKAGE
"During a planned Unit 1 shutdown for a refueling outage, a 0.5 gpm 'pressure boundary leak' was identified on a 1 inch pipe connected to the '1A' RHR-Shutdown Cooling return line by the drywell leak inspection team during a drywell inspection at approximately 15% power. The leak exceeded the TS 3.4.3.2 'Operational Leakage' LCO of no pressure boundary leakage. TS action 'a' was entered which requires to be in at least Hot Shutdown within 12 hours and Cold Shutdown within the next 24 hours. Therefore, the event is reportable within 4 hours per 10CFR50.72(b)(2)(i) due to the initiation of a plant shutdown required by the plant's TS.
"The event is also reportable within 8 hours per 10CFR50.72(b)(3)(ii) due to an event that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.
"TS 1.28 defines Pressure Boundary Leakage as leakage through a nonisolable fault in a reactor coolant system component body, pipe wall or vessel wall; therefore, the leak is a 'pressure boundary leak' as defined in TS."
The licensee notified the NRC resident Inspector. |
| Part 21 |
Event Number: 51810 |
Rep Org: FISHER CONTROLS INTERNATIONAL, LLC
Licensee: FISHER CONTROLS INTERNATIONAL, LLC
Region: 3
City: MARSHALLTOWN State: IA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: LYNN SANDERS
HQ OPS Officer: DONG HWA PARK |
Notification Date: 03/21/2016
Notification Time: 14:02 [ET]
Event Date: 01/22/2016
Event Time: [CDT]
Last Update Date: 03/21/2016 |
Emergency Class:
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE |
Person (Organization):
SHAKUR WALKER (R2DO)
PART 21/50.55 REACT (EMAI) |
Event Text
PART 21 - PLUG/STEM ASSEMBLY
The following is a summary of an email provided by Fisher Controls International:
"Items subject to this Fisher Information Notice (FIN) were provided to Tennessee Valley Authority (TVA) Watts Bar Nuclear Plant per TVA Order 702507 (Fisher Order Number 025-N230331922). Specifically, this FIN applies to a plug/stem assembly that Fisher Controls International LLC (Fisher) supplied to TVA, item number 15A2560X072 (Equipment). In this equipment, the essential-to-function groove pin was erroneously provided as commercial-grade.
"Fisher Information Notice: FIN 2016-03
"Fisher requests that the recipient of this FIN review it and take appropriate action in accordance with 10 CFR 21. If there are any technical questions or concerns, please contact:
Ben Ahrens
Quality Manager
Emerson Process Management
Fisher Controls International LLC
301 South First Avenue
Marshalltown, lA 50158
Phone: (641) 754-2249
Benjamin.ahrens@emerson.com" |
| Power Reactor |
Event Number: 51811 |
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: REGGIE PICKENS
HQ OPS Officer: DONG HWA PARK |
Notification Date: 03/21/2016
Notification Time: 17:28 [ET]
Event Date: 03/21/2016
Event Time: 12:10 [EDT]
Last Update Date: 03/21/2016 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL |
Person (Organization):
SHAKUR WALKER (R2DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
N |
0 |
Cold Shutdown |
0 |
Cold Shutdown |
Event Text
OFFSITE MEDICAL TREATMENT REQUIRED
"At 1152 EDT, a contractor employee working in the Containment Building in a potentially contaminated area was found passed out and unresponsive. At 1210 EDT, the individual was transported to Carolinas Medical Center, Charlotte, NC. Radiation Protection had not yet fully determined if the individual was contaminated. At 1300 EDT, Radiation Protection determined the individual was not contaminated. The determination was made after arrival to the hospital.
"The licensee notified the NRC Resident Inspector." |
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