| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/30/2014 - 07/01/2014 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 50218 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: RABA-KISTNER CONSULTANTS
Region: 4
City: AUSTIN State: TX
County:
License #: 01571
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/20/2014
Notification Time: 11:11 [ET]
Event Date: 06/19/2014
Event Time: [CDT]
Last Update Date: 06/20/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MICHAEL HAY (R4DO)
FSME EVENT RESOURCES (E-MA)
MEXICO (E-MA)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST MOISTURE DENSITY GAUGE
The following report was received via e-mail:
"On June 20, 2014, the Agency [Texas Department of Health] was notified by the licensee of the loss of a Humboldt model 5001EZ moisture density gauge, serial #4772, containing a 1.48 GBq (40 mCi) Am-Be source and a 0.3 GBq (8 mCi) Cs-137 source. The licensee stated a technician was working at a job site on June 19, 2014, when he rushed home for a family emergency. He failed to secure the gauge in the back of the truck and he left the tailgate down. The gauge fell off the truck between the job site and his home. The licensee stated they searched the job site and the route taken by the technician."
Texas event: I-9205
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Fuel Cycle Facility | Event Number: 50233 | Facility: NUCLEAR FUEL SERVICES INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
Region: 2
City: ERWIN State: TN
County: UNICOI
License #: SNM-124
Agreement: Y
Docket: 07000143
NRC Notified By: MICHAEL TESTER
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/27/2014
Notification Time: 15:22 [ET]
Event Date: 06/25/2014
Event Time: 23:48 [EDT]
Last Update Date: 06/27/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(1) - UNPLANNED CONTAMINATION
| Person (Organization):
DANIEL RICH (R2DO)
ANTHONY HSIA (NMSS)
FUELS GROUP (EMAI)
| Event Text UNPLANNED CONTAMINATION EVENT
"Event Text: At approximately 2348 hours (Eastern Time) on June 25, 2014, an employee dropped a container of radioactive material solution after removal from a glove box enclosure. The 2-liter poly container split, releasing contents to the floor and surrounding equipment. Operations in the area were placed in a safe condition at the time of the event, radiological controls implemented for personnel protection, and decontamination initiated. Extensive surface contamination surveys were performed to facilitate decontamination and the area was released to normal access by 1615 hours (ET) on June 26, 2014. At this time, the additional radiological controls implemented at the time of the event were removed. At 0245 hours (ET) on June 27, 2014, contamination was discovered to be weeping out of some facility and equipment surfaces in the area of the earlier spill. Radiological controls were reestablished, decontamination efforts resumed, and enhanced monitoring implemented. Since the cumulative time for access restrictions exceeded 24 hours, this is being reported to the operations center under 10 CFR 70.50.b (1).
"There were no actual or potential safety consequences to the public or the environment. There were no actual safety consequences to the workers. The potential safety consequences to the workers include exposure to uranyl nitrate solution.
"The licensee has notified the NRC Resident Inspector."
The radioactive material solution was Uranyl Nitrate containing 540 grams of Uranium-235. |
| Power Reactor | Event Number: 50238 | Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMES SHAW
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/30/2014
Notification Time: 07:50 [ET]
Event Date: 06/30/2014
Event Time: 07:30 [EDT]
Last Update Date: 06/30/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JULIO LARA (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 PLANNED MAINTENANCE ON TECHNICAL SUPPORT CENTER VENTILATION
"At 0730 EDT on Monday, June 30, 2014, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) charcoal filtration system was removed from service for scheduled maintenance. Under certain accident conditions, the TSC may become unavailable due to the inability of the charcoal filtration system to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary. TSC ventilation system maintenance and post maintenance testing is scheduled to be completed by 1500 EDT on Monday, June 30.
"The licensee has notified the NRC Resident Inspector."
* * * UPDATE FROM JAMES SHAW TO VINCE KLCO AT 1327 EDT ON 6/30/14 * * *
The charcoal filtration system was restored to service at 1245 EDT on 6/30/2014.
The licensee will notify the NRC Resident Inspector.
Notified the R3DO (McCraw). |
| Power Reactor | Event Number: 50241 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JOHN CLAIRE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/30/2014
Notification Time: 16:06 [ET]
Event Date: 06/30/2014
Event Time: 13:10 [EDT]
Last Update Date: 06/30/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JAMES NOGGLE (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text STACK HIGH RANGE RADIATION MONITOR OUT OF SERVICE FOR PLANNED MAINTENANCE
The Unit 2 stack high range radiation monitor was removed from service at 1310 EDT for planned maintenance. The monitor was returned to service at 1420 EDT after the completion of maintenance.
The licensee notified the NRC Resident Inspector, the Connecticut Department of Energy and Environmental Protection, and Waterford city of this event. |
| Power Reactor | Event Number: 50242 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATTHEW ROBERTSON
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/30/2014
Notification Time: 17:00 [ET]
Event Date: 06/30/2014
Event Time: 07:48 [EDT]
Last Update Date: 06/30/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
DANIEL RICH (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Under Construction | 0 | Under Construction | Event Text NON-LICENSED CONTRACT SUPERVISOR TESTED POSITIVE FOR ALCOHOL ON A RANDOM FITNESS-FOR-DUTY TEST
A non-licensed contract supervisor tested positive for alcohol on a random fitness for duty test. The supervisor's access to the facility has been terminated. The licensee has notified the NRC Resident Inspectors. |
| Power Reactor | Event Number: 50243 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: STEPHEN SPEIRS
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/30/2014
Notification Time: 17:55 [ET]
Event Date: 06/30/2014
Event Time: 16:05 [CDT]
Last Update Date: 06/30/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
AARON MCCRAW (R3DO)
PATRICK HILAND (NRR)
WILLIAM GOTT (IRD)
|
| 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 DISCOVERY OF AN AFTER-THE-FACT UNUSUAL EVENT
"This is a one hour report for the discovery of a condition that briefly met the emergency action level (EAL) for an Unusual Event but did not warrant declaration of an emergency classification. A detailed review of the conditions that existed during a thunderstorm that took place today revealed that the backup 50 meter wind speed briefly indicated 95.5 mph, which exceeds the HU 1.3 criteria of 95 mph. The primary 50 meter wind speed indicator did not exceed 89 mph. Operators in the control room did not observe wind speed exceed 80 mph on SPDS. This event is a one hour report based on the guidance in NUREG-1022 for a condition that met an emergency plan EAL and the basis for the emergency classification no longer existed at the time of discovery."
The NRC Resident Inspector has been informed. |
| Power Reactor | Event Number: 50244 | Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL HARRIS
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/30/2014
Notification Time: 23:11 [ET]
Event Date: 06/30/2014
Event Time: 22:46 [EDT]
Last Update Date: 06/30/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
DANIEL RICH (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 | Event Text UNANALYZED CONDITION THAT COULD HAVE RESULTED IN AN INCREASED MAXIMUM FLOOD LEVEL
"On June 27, 2014, TVA identified in a reanalyzed hydrologic analysis for Sequoyah Nuclear Plant (SQN) a deviation from the current hydrologic analysis. The flooding analysis in Section 2.4.3 of the SQN UFSAR assumes that the Watts Bar West Saddle Dike fails completely and instantaneously at approximately 1.5 feet of overtopping during a Peak Maximum Flood [PMF]. This assumption exists in the original design basis analysis and the revised analysis which supports SQN-TS-12-02, "Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis".
"The results of recent studies of the West Saddle Dike, conducted as part of the Fukushima Order 2.1 flooding review, indicate that the complete and instantaneous failure of the Watts Bar West Saddle Dike may not be a valid assumption. If the dike does not fail, analyses performed using the codes and methods consistent with those used in original plant design show that the east floodwall of the Watts Bar Dam would overtop. As a result of this overtopping, the east floodwall is assumed to fail. Based on this assumption and analysis, failure of the east floodwall of the Watts Bar Dam would result in an increase in the flood level at the SQN Plant Site. The current licensing basis PMF level for SQN is 719.6 feet as stated in Section 2.4.2.2 of the SQN UFSAR. In addition, it should be noted that by letter dated August 10, 2012, as supplemented by letters dated April 5, 2013 and January 16, 2014, TVA proposed a revised PMF level of 722.0 feet. Introducing non failure of the Watts Bar West Saddle Dike indicated a potential increase of approximately 1.5 feet over the revised PMF level.
"TVA performed additional analysis using current industry standard for flooding analysis. Specifically, TVA modeled the condition using the United States Army Corps of Engineers Hydrologic Engineering Center River Analysis System (HEC-RAS) tool. TVA's analysis of the condition using HEC-RAS determined that all required safety equipment for SQN would not be impacted and are considered operable based on a Prompt Determination of Operability completed on June 30, 2014.
"This report addresses a condition as described in 10 CFR 50.72 (b)(3)(ii)(B). TVA is making this report consistent with the guidance of NUREG-1022 regarding the application of engineering judgment to the evaluation of reportability of an unanalyzed condition.
"The NRC Resident Inspector has been notified of this condition." |
| Power Reactor | Event Number: 50245 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAMON FEGLEY
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/30/2014
Notification Time: 23:24 [ET]
Event Date: 06/30/2014
Event Time: 22:46 [EDT]
Last Update Date: 06/30/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
DANIEL RICH (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 | Event Text UNANALYZED CONDITION THAT COULD HAVE RESULTED IN AN INCREASED MAXIMUM FLOOD LEVEL
"On June 27, 2014, TVA identified in a reanalyzed hydrologic analysis for Watts Bar Nuclear Plant (WBN) a deviation from the current hydrologic analysis. The flooding analysis in Section 2.4.3 of the WBN UFSAR assumes that the Watts Bar West Saddle Dike fails completely and instantaneously at approximately 1.5 feet of overtopping during a Peak Maximum Flood [PMF]. This assumption exists in the original design basis analysis and the revised analysis which supports WBN-UFSAR-12-01 (Application to Revise Watts Bar Nuclear Plant Unit 1 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis).
"The results of recent studies of the West Saddle Dike, conducted as part of the Fukushima Order 2.1 flooding review, indicate that the complete and instantaneous failure of the Watts Bar West Saddle Dike may not be a valid assumption. If the dike does not fail, analyses performed using the codes and methods consistent with those used in original plant design show that the east floodwall of the Watts Bar Dam would overtop. As a result of this overtopping, the east floodwall is assumed to fail. Based on this assumption and analysis, failure of the east floodwall of the Watts Bar Dam would result in an increase in the flood level at the WBN Plant Site. The current licensing basis PMF level for WBN is 734.9 feet as stated in Section 2.4.3.5 of the WBN UFSAR. In addition, it should be noted that by letter dated July 19, 2012, TVA proposed a revised PMF level of 739.2 feet. Introducing non failure of the Watts Bar West Saddle Dike indicated a potential increase of approximately 1.7 feet over the revised PMF level.
"TVA performed additional analysis using current industry standard for flooding analysis. Specifically, TVA modeled the condition using the United States Army Corps of Engineers Hydrologic Engineering Center River Analysis System (HEC-RAS) tool. TVA's analysis of the condition using HEC-RAS determined that all required safety equipment for WBN would not be impacted and are considered operable based on a Prompt Determination of Operability completed on June 30, 2014.
"This report addresses a condition as described in 10 CFR 50.72 (b)(3)(ii)(B). TVA is making this report consistent with the guidance of NUREG-1022 regarding the application of engineering judgment to the evaluation of reportability of an unanalyzed condition.
"The NRC Resident Inspector has been notified of this condition." |
| Power Reactor | Event Number: 50246 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DOUG PETERSON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/30/2014
Notification Time: 23:54 [ET]
Event Date: 06/30/2014
Event Time: 19:13 [CDT]
Last Update Date: 07/01/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
AARON MCCRAW (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 98 | Power Operation | 98 | Power Operation | Event Text AUTO-START OF STANDBY DIESEL GENERATORS DUE TO A GRID DISTURBANCE
"This report is being made under 10CFR50.72(b)(3)(iv)(A), 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of this section' due to an auto start of 'A' and 'B' Standby Diesel Generators. At 1913 CDT, a grid disturbance during a local thunderstorm caused a valid bus undervoltage condition that resulted in the auto start of both the 'A' and 'B' Standby Diesel Generators. The 'A' and 'B' Standby Diesel Generator supply breakers did not close onto their respective buses as they remained powered by their normal power supply, the 1X003 Startup Transformer, during and after the event. NextEra Duane Arnold personnel inspections revealed no issues with breakers in the switchyard. Ltc (Iowa Transmission Company) reported a fault on a 161 Kv line in the NextEra Duane Arnold vicinity. Offsite power remained Operable during and following the event.
"As designed the 'A' and 'B' Emergency Service Water systems auto started when the diesel generators auto started. The Emergency Service Water systems and both Standby Diesel Generators have been returned to standby/readiness condition. All ECCS [Emergency Core Cooling System] systems were available before the event and have remained available following the event."
The licensee notified the NRC Resident Inspector. | |