| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/21/2014 - 08/22/2014 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | 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: 08/21/2014 | 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."
* * * RETRACTION AT 1441 EDT ON 8/21/2014 FROM MATT LEENERTS TO MARK ABRAMOVITZ * * *
"On June 30, 2014, SQN reported (Event 50244) that during a re-analysis conducted as part of the Fukushima Order 2.1 flooding review, a probable maximum flood (PMF) design assumption that the Watts Bar Dam west saddle dike fails completely and instantaneously at approximately 1.5 feet of overtopping, was determined to be a non-conservative flood model assumption (i.e., invalid). As a result, TVA postulated that Watts Bar Dam's east floodwall would fail, increasing the site flood level at Sequoyah Nuclear Plant (SQN) by 1.5 feet; a condition that was beyond the current licensing basis.
"Through subsequent analysis, TVA has demonstrated that although the west saddle dike may not completely and instantaneously fail during a PMF (as previously assumed), the consequential increase in reservoir levels does not result in a failure of the Watts Bar Dam east floodwall and would not result in an increase in the flood level at SQN.
"Therefore, the previously reported 10 CFR 50.72(b)(3)(ii)(B) event is being retracted.
"The NRC Resident Inspector has been informed of this event retraction."
Notified the R2DO (Hickey). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | 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: 08/21/2014 | 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."
* * * RETRACTION AT 1705 EDT ON 8/21/2014 FROM MATTHEW ROBERTSON TO MARK ABRAMOVITZ * * *
"On June 30, 2014, TVA reported (Event 50245) that during a re-analysis conducted as part of the Fukushima Order 2.1 flooding review, a probable maximum flood (PMF) design assumption that the Watts Bar Dam west saddle dike fails completely and instantaneously at approximately 1.5 feet of overtopping, was determined to be a non-conservative flood model assumption (i.e., invalid). As a result, TVA postulated that Watts Bar Dam's east floodwall would fail, increasing the site flood level at Watts Bar Nuclear Plant (WBN) by 1.7 feet; a condition that was beyond the current licensing basis.
"Through subsequent analysis, TVA has demonstrated that although the west saddle dike may not completely and instantaneously fail during a PMF (as previously assumed), the consequential increase in reservoir levels does not result in a failure of the Watts Bar Dam east floodwall and would not result in an increase in the flood level at WBN.
"Therefore, the previously reported 10 CFR 50.72(b)(3)(ii)(B) event is being retracted.
"The NRC resident Inspector has been informed of this event retraction."
Notified the R2DO (Hickey). |
| Non-Agreement State | Event Number: 50365 | Rep Org: UNION ELECTRIC DBA AMEREN MISSOURI
Licensee: UNION ELECTRIC DBA AMEREN MISSOURI
Region: 3
City: ST. LOUIS State: MO
County:
License #: 24-02020-08
Agreement: N
Docket:
NRC Notified By: BRIAN HOLDERNESS
HQ OPS Officer: DONALD NORWOOD | Notification Date: 08/14/2014
Notification Time: 09:40 [ET]
Event Date: 08/13/2014
Event Time: 10:30 [CDT]
Last Update Date: 08/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(4) - FIRE/EXPLOSION
| Person (Organization):
MICHAEL KUNOWSKI (R3DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text PROCESS DENSITY GAUGE DAMAGED BY FIRE AND/OR HEAT
"On the morning of August 13, 2014 while cleaning up from a fire event on coal handling conveyer belt #2 at the Ameren Missouri (Ameren) Rush Island Energy Center it was observed that the nucleonic gauge located outside of the area of the original fire had some indications of potential damage. The gauge is located approximately 12 feet above the walkway near the ceiling of the room in an area that was not easily accessible. The gauge is a Ronan Engineering Model SA1-C10 containing 100 mCi of CS-137 in sealed solid form. Ameren contacted R. M. Wester (NRC Licensed maintenance vendor) to evaluate the nucleonic gauge on August 13, 2014 to determine if the gauge had been damaged due to the fire.
"R. M. Wester examination of the source housing showed the exterior to be in good condition with some minor scorching. The shutter check performed showed smooth operation and good beam strength with the shutter open (greater than 200 mR/hr) and good shielding with the shutter closed (1.5 mR/hr). Wipes of the source and the area below the source indicated no contamination or leakage from the source.
"An area radiation survey did indicate that some of the lead inside of the source housing had potentially melted and shifted. The on contact readings of the back (0.2 mR/hr), sides/bottom (0.3 mR/hr), and shutter (1.5 mR/hr) were all consistent with expected readings. The 30 cm readings from the source back, sides, and bottom were also as expected (approximately 0.03 mR/hr). The readings on top of the source were higher than expected with a reading of 6 mR/hr on contact and 0.4 mR/hr at 30 cm. These readings on the top of the source do not present an immediate radiological hazard due to their low intensity and the fact that the source is mounted very close to the ceiling in the room. The ceiling support beam and water deflection shield make it difficult to even get a reading 30 cm from the top of the source.
"R. M. Wester's recommendation was that the gauge is functional and it could continue to be use until a replacement device could be procured and installed." |
| Agreement State | Event Number: 50366 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: MISTRAS GROUP INC
Region: 4
City: DEER PARK State: TX
County:
License #: 06369
Agreement: Y
Docket:
NRC Notified By: ARTHUR TUCKER
HQ OPS Officer: JEFF ROTTON | Notification Date: 08/14/2014
Notification Time: 11:07 [ET]
Event Date: 08/13/2014
Event Time: [CDT]
Last Update Date: 08/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
VIVIAN CAMPBELL (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE - RADIOGRAPHY CAMERA SOURCE WOULD NOT RETRACT
The following information was provided by the State of Texas via email:
"On August 14, 2014, the Agency [Texas Department of State Health Services] was notified by the licensee's Radiation Safety Officer (RSO) that on August 13, 2014, a radiography crew using a 50 foot crank out device could not retract a 54 curie iridium-192 source to the fully retracted and locked position in a QSA 880D exposure device (camera). The RSO stated the radiographer had completed an exposure at a temporary field site and was retracting the source when he felt the resistance to movement in the crank out handle disappear and he could no longer move the source. The radiographer noted the dose rates were still higher than those for a fully shielded source. The radiographer contacted the RSO and increased the control area. The radiographer placed two bags of lead on the guide tube where he believed the source was located. The RSO stated the radiographer was in the area of the source for just a few seconds. The radiographer checked his self reading dosimeter after placing the lead at the source and found it off scale.
"The RSO and a recovery team went to the location to retrieve the source. The RSO had additional lead placed on the guide tube and the dose rates at the crank out device dropped to less than 2 millirem per hour. The RSO disconnected the drive cable housing from the broken in two at crank out device. The RSO grabbed the drive cable inside the drive cable housing with a set of pliers and was able to pull the drive cable and return the source to the fully shielded position.
"The personnel dosimeter for the radiographer who had approached the guide tube was sent to the licensee's dosimetry processor for processing and the radiographer has been removed from all work involving exposure to radiation until the results for their badge has been received. The RSO stated that based on the exposure rates and the time the radiographer was in the area of the source he did not believe the radiographer received
a significant exposure from the event. The RSO received 8 millirem by pocket dosimeter from the event. No other individuals received any significant exposure in this event.
"The crank out and drive cable will been sent to the manufacturer for inspection. The RSO stated he examined the drive cable, but did not see anything that would indicate why the cable failed. The RSO stated they performed a flex test of the drive cable and it passed. The RSO stated the camera and guide tube were inspected and returned to service. Additional information will be provided in accordance with SA-300."
Texas Incident #: I-9219 |
| Agreement State | Event Number: 50367 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: THERMO SCIENTIFIC - PORTABLE SCIENTIFIC INSTRUMENTS
Region: 1
City: TEWKSBURY State: MA
County:
License #: 55-0238
Agreement: Y
Docket:
NRC Notified By: DOUG CULLEN
HQ OPS Officer: CHARLES TEAL | Notification Date: 08/14/2014
Notification Time: 14:16 [ET]
Event Date: 08/11/2014
Event Time: [EDT]
Last Update Date: 08/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
SILAS KENNEDY (R1DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - LEAKING SEALED SOURCE
The following was received from the State of Massachusetts via email:
"Thermo Scientific received a total of 15 sealed sources, Model XFB-3, manufactured by Eckert & Ziegler Isotope Products, containing Cd-109, each with an activity of 40 mCi. As part of Thermo's inspection protocol, individual sealed sources were leak tested, and one source, serial number TR3042 tested greater than the leak test limit of 0.005 microcuries.
"Following the initial leak test, two additional leak test measurements were made and all three measurements were found to be in excess of the 0.005 microcurie limit, with measurements ranging from 0.0126 to 0.0184 microcuries.
"Eckert and Ziegler was notified immediately by Thermo Scientific, a return authorization was provided, and Thermo returned the sealed source via [common carrier] to Eckert and Ziegler on 08/11/14.
"The licensee reports that the area where the leaks tests were obtained was surveyed thoroughly and no contamination was found.
"The Agency [State of Massachusetts] considers this event open."
MA Docket #: 20-1427 |
| Agreement State | Event Number: 50368 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: COLORADO STATE UNIVERSITY
Region: 4
City: FORT COLLINS State: CO
County:
License #: CO 002-19
Agreement: Y
Docket:
NRC Notified By: JAMES GRICE
HQ OPS Officer: DANIEL MILLS | Notification Date: 08/14/2014
Notification Time: 17:16 [ET]
Event Date: 08/14/2014
Event Time: 14:45 [MDT]
Last Update Date: 08/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
VIVIAN CAMPBELL (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - INOPERABILITY OF THE ACCESS CONTROL SYSTEM
The following was received from the State of Colorado via email:
"CDPHE [Colorado Department of Public Health] received telephone notification of an inoperability of the access control system on 8/14/2014 at approximately 1445 [MDT]. Colorado State University, a research licensee, reported that a radiation monitor provided to detect the presence of high radiation levels in the radiation room of a panoramic irradiator was alarming when there was no [abnormal] radiation level present. One of the irradiator users noticed the audible alarm when their work was complete and they were leaving the area. The RSO responded and suspected a stuck source. Using a hand held radiation detection instrument, the irradiator door was opened and the irradiator room was entered. As the RSO entered the room there was no indication of radiation levels above what was expected when the source is in its shielded position, and as a result, it was determined that the source was in its shielded position. The room radiation monitor was reset but shortly after again alarmed without any [abnormal] radiation field present. The irradiator has been taken out of service and the monitor has been removed for repair."
Colorado event report ID: CO14-I14-22 |
| Non-Agreement State | Event Number: 50369 | Rep Org: BOTSFORD HOSPITAL
Licensee: BOTSFORD HOSPITAL
Region: 3
City: FARMINGTON HILLS State: MI
County:
License #: 21-08892-01
Agreement: N
Docket:
NRC Notified By: TEAMOUR NURUSHEV
HQ OPS Officer: CHARLES TEAL | Notification Date: 08/14/2014
Notification Time: 17:17 [ET]
Event Date: 07/10/2014
Event Time: 13:20 [EDT]
Last Update Date: 08/14/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(3) - DOSE TO OTHER SITE > SPECIFIED LIMITS
| Person (Organization):
MICHAEL KUNOWSKI (R3DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text PATIENT RECEIVED LESS THAN PRESCRIBED DOSE
A patient undergoing High Dose Rate Brachytherapy using Ir-192 was prescribed 700 cGy per fraction and only received 700 cGy to 60% of the planned volume.
The patient was scheduled for two treatments. The first treatment was successfully administered to the patient on 6/26/14. When the patient returned for the second treatment on 7/10/14 the HDR afterloader was loaded with the treatment plan for the original treatment instead of the second treatment. This resulted in the patient not receiving the full prescribed treatment.
The licensee discovered the problem during an audit when the number of catheters did not match.
There are no adverse health effects expected as a result of this treatment.
The licensee has contacted the vender to determine a way to remove old treatment plans from the machine to ensure this does not happen in the future.
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: 50386 | Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DEAN BRUCK
HQ OPS Officer: CHARLES TEAL | Notification Date: 08/21/2014
Notification Time: 04:03 [ET]
Event Date: 08/21/2014
Event Time: 02:10 [EDT]
Last Update Date: 08/21/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| 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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION DUE TO SUSPECTED FUEL OIL LEAK TO THE ENVIRONMENT
"At 0210 EDT on August 21, 2014, D.C. Cook made notifications to the State of Michigan, local authorities and the National Response Center due to a suspected release of approximately 8,700 gallons of diesel fuel oil to the environment. The level in the buried fuel oil storage tank for the Train B Emergency Diesel Generator was found to be approximately 8,700 gallons less than measurements taken within the last 24 hours. The tank is located within the plant protected area. At this time the suspected fuel oil plume has not left the site.
"The NRC Resident Inspector was notified.
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(xi) and NUREG 1022 section 3.2.12, due to notification of offsite agencies." |
| Power Reactor | Event Number: 50389 | Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JOHN WALKOWIAK
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/21/2014
Notification Time: 12:00 [ET]
Event Date: 08/21/2014
Event Time: 08:50 [EDT]
Last Update Date: 08/21/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RAY MCKINLEY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 50 | Power Operation | 50 | Power Operation | Event Text INADVERTENT ACTUATION OF ONE EMERGENCY SIREN
"The purpose of this report is to provide a telephone notification under 10 CFR 50.72(b)(2)(xi) to notify the NRC of the inadvertent actuation of one Oswego County emergency notification siren at approximately 0850 [EDT] on 08/21/14. Thunderstorms in the area are believed to have caused a lightning strike and the spurious activation. Siren repair personnel have been dispatched to isolate the siren and begin repair work. The siren has since been silenced. Alternate notification of the public in the area is through Hyperreach.
"The Oswego County Emergency Management Office issued a news release identifying the inadvertent actuation of the emergency siren.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 50390 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: MARK GREER
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/21/2014
Notification Time: 12:04 [ET]
Event Date: 08/21/2014
Event Time: 08:50 [EDT]
Last Update Date: 08/21/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
RAY MCKINLEY (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 INADVERTENT ACTUATION OF ONE EMERGENCY SIREN
"One of the 37 Prompt Notification System sirens surrounding the James A Fitzpatrick (JAF) / Nine Mile Point (NMP) sites spuriously activated at 0850 EDT. The Oswego County Emergency Operations Center notified Nine Mile Point via RECS [Radiological Emergency Communications System] that siren #13 had inadvertently activated. Repair technicians have de-activated and silenced the faulty siren as of 0943 EDT. Siren #13 is currently out of service and the backup method for siren #13 has been verified to be functional. The cause of the inadvertent siren activation is believed to be a lightning strike.
"The issue has been entered into the site's Corrective Action Program.
"The Oswego County Emergency Management Office issued a News Release identifying the inadvertent actuation of the emergency siren.
"The NRC Resident Inspector has been notified. |
| Fuel Cycle Facility | Event Number: 50391 | Facility: HONEYWELL INTERNATIONAL, INC.
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
Comments: UF6 CONVERSION (DRY PROCESS)
Region: 2
City: METROPOLIS State: IL
County: MASSAC
License #: SUB-526
Agreement: Y
Docket: 04003392
NRC Notified By: ROSS LINDBERG
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/21/2014
Notification Time: 14:31 [ET]
Event Date: 08/21/2014
Event Time: 09:10 [CDT]
Last Update Date: 08/21/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(3) - MED TREAT INVOLVING CONTAM
| Person (Organization):
JAMES HICKEY (R2DO)
ROBERT JOHNSON (NMSS)
| Event Text CONTAMINATED INJURED INDIVIDUAL
"An employee with an injured knee reported to the on-site dispensary this morning. First aid was administered. A whole body survey of the employee and plant clothing was performed; the maximum amount of contamination present was on the employee's work boots, 96,000 dpm/100cm2. All contaminated clothing was removed from the employee. An additional whole body survey of the employee was performed prior to leaving the restricted area; no contamination above background levels was detected. The employee was sent to an offsite medical facility for further evaluation and/or treatment."
The licensee notified the NRC Resident Inspector. | |