| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/27/2013 - 09/30/2013 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Fuel Cycle Facility | Event Number: 49341 | Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
LEU FABRICATION
LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: SCOTT MURRAY
HQ OPS Officer: BILL HUFFMAN | Notification Date: 09/13/2013
Notification Time: 10:55 [ET]
Event Date: 09/13/2013
Event Time: 10:45 [EDT]
Last Update Date: 09/27/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (a)(4) - ALL SAFETY ITEMS UNAVAILABLE
| Person (Organization):
SCOTT SHAEFFER (R2DO)
MERAJ RAHIMI (NMSS)
WILLIAM GOTT (IRD)
| Event Text ITEM RELIED ON FOR SAFETY MAY NOT BE RELIABLE
"At about 1045 EDT on 9/13/13, it was discovered that the feed tube level sensor on a press operation is not fail safe upon loss of signal. The sensor is a sole IROFS [Item Relied On For Safety] for a particular sequence. Criticality controls remained in place. Affected equipment has been shut down. No unsafe condition exists. Feed tube level sensor is in place for the sequence to limit mass. At no time was the mass limit exceeded. We are reporting under Part 70, Appendix A, (a)(4) which states that credited IROFS must remain available and reliable. We cannot evaluate reliability in the time required for a 1 hour report. In addition, the affected equipment has been secured. An investigation is underway to determine corrective actions and extent of condition."
The license will notify NRC Region 2.
* * * RETRACTION FROM SCOTT MURRAY TO DANIEL MILLS ON 9/27/2013 AT 1003 EDT * * *
"On 9/13/13, GNF-A conservatively made a 1 hour event notification (EN 49341) due to a discovery that a feed tube level sensor is not fail safe upon loss of signal. After further review, it has been determined that the control remained available, reliable and continued to meet performance requirements. As a result, the event notification is retracted."
The licensee has notified NRC Region 2.
Notified R2DO (Sykes), NMSS EO (Rubenstone), and IRD (Grant). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 49353 | Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHNATHAN ZARNDT
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 09/18/2013
Notification Time: 11:15 [ET]
Event Date: 09/18/2013
Event Time: 05:10 [CDT]
Last Update Date: 09/27/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
KENNETH RIEMER (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Defueled | 0 | Defueled | Event Text BOROSCOPIC INSPECTION OF REACTOR VESSEL HEAD DETERMINED EVIDENCE OF BOUNDARY LEAKAGE
"Boroscopic inspection of the reactor head assembly during refuel outage A1R17 has determined that white powder residue observed at reactor head penetrations 41, 49, 61, 65, and 73 is evidence of past Reactor Coolant System pressure boundary leakage at one or more of these locations. This determination was made today at 0510 [CDT] after completion of boroscopic inspections and consultation with the reactor head vendor. These reactor head penetrations are control rod drive mechanism (CRDM) penetrations. The location of the identified leakage is suspected to be the omega seal welded threaded connection on one or more of these CRDM penetrations. Further inspections must be performed to confirm the exact leakage location. This condition will be repaired before U-1 returns to mode 4."
The licensee has notified the NRC Resident Inspector.
* * * RETRACTION ON 9/27/13 AT 1529 EDT FROM MATTHEW HENSON TO DONG PARK * * *
"The purpose of this report is to retract ENS report #49353 (September 18, 2013). This report was made after boroscopic inspection of the Unit 1 reactor head assembly during refueling outage A1R17 determined that white powder residue observed at five Reactor Pressure Vessel (RPV) head penetrations was evidence of past Reactor Coolant System (RCS) pressure boundary leakage at one or more of these locations.
"At 1400 CDT on Wednesday, September 25, 2013, the Braidwood Nuclear Power Station (BNPS) concluded that the prior ENS notification could be retracted because the Plant Operations Review Committee had concluded that the white powder residue observed at five Unit 1 RPV head penetrations was not evidence of past RCS pressure boundary leakage. A detailed examination plan was implemented, which included a disassembly of the Digital Rod Position Indication (DRPI) and Control Rod Drive Mechanism (CRDM) coils for all five penetrations and a detailed visual examination using remote video equipments. The visual examinations used remote video equipments to inspect the lower and intermediate canopy seal weld areas for the five CRDMs. In addition, an examination of the upper canopy seal weld areas and a bare-metal inspection of the Reactor Pressure Vessel Head did not identify any evidence of boric acid leakage. Based on these inspections and a review of available photos from previous outages, BNPS concluded that the white residues were from incomplete cleaning in prior outages.
"The licensee has notified the NRC Resident Inspector."
Notified R3DO (Dickson). |
| Agreement State | Event Number: 49360 | Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: B & J PARTNERSHIP
Region: 4
City: LINCOLN State: NE
County:
License #: GL0747
Agreement: Y
Docket:
NRC Notified By: TRUDY HILL
HQ OPS Officer: CHARLES TEAL | Notification Date: 09/19/2013
Notification Time: 14:56 [ET]
Event Date: 06/25/2013
Event Time: [CDT]
Last Update Date: 09/19/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RICK DEESE (R4DO)
FSME EVENT RESOURCE (EMAI)
DENNIS ALLSTON (ILTA)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS
The following was received from the State of Nebraska via facsimile:
"B & J Partnership purchased two Isolite model SLX60 exit signs with 6.2 curies of H3 in each sign on December 8, 2011. On September 19, 2013 the Department [Nebraska Department of Health and Human Services] was notified that the General Licensee did not know where the exit signs were after an extensive search."
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
THIS MATERIAL EVENT CONTAINS A "NOT RECORDED" LEVEL OF RADIOACTIVE MATERIAL
|
| Agreement State | Event Number: 49366 | Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: CLEVELAND CLINIC
Region: 3
City: CLEVELAND State: OH
County:
License #: 02110180013
Agreement: Y
Docket:
NRC Notified By: KARL VON AHN
HQ OPS Officer: HOWIE CROUCH | Notification Date: 09/20/2013
Notification Time: 11:58 [ET]
Event Date: 05/09/2013
Event Time: [EDT]
Last Update Date: 09/20/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
KENNETH RIEMER (R3DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text MEDICAL EVENT INVOLVING DOSE TO THE WRONG ORGAN
The following information was obtained from the State of Ohio via email:
"At 1000 [EDT] on Sept 20, 2013 the Cleveland Clinic Foundation (CCF) RSO called the Ohio Department of Health (ODH) Bureau of Radiation Protection to report the determination of a medical event based on the back calculations from a symptomatic patient that had received a Y-90 microsphere treatment on May 9, 2013. The patient received a treatment of Y-90 SIR-Spheres to both the left and right lobes of the liver.
"The vessel to the stomach area was coiled to prevent shunting. At the time of the treatment, the patient complained of some abdominal pain. The post-treatment scan was inconclusive regarding the shunting to the stomach area. The AU [authorized user] and interventional radiologist concluded that a shunt was unlikely.
"The patient continued to complain of stomach pain and returned to the CCF on Sept 5, 2013 for an endoscopy. The endoscopy revealed ulcers in the potentially affected areas.
"After additional review of the post-treatment scan by the licensee, it was not abundantly apparent, but possible, that shunting did occur. Based on the assumption that shunting did occur, the licensee determined that the gastric antrum, an unintended treatment area, received a dose of 62 Gy.
"The ODH Bureau of Radiation will be conducting an onsite investigation.
"This incident was assigned ODH incident report number 2013-011."
NMED Item Number: OH130014
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. |
| Agreement State | Event Number: 49367 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: EQUISTAR CHEMICALS LP
Region: 3
City: MORRIS State: IL
County:
License #: IL-01737-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: CHARLES TEAL | Notification Date: 09/20/2013
Notification Time: 12:17 [ET]
Event Date: 09/18/2013
Event Time: [CDT]
Last Update Date: 09/20/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
KENNETH RIEMER (R3DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - STUCK SHUTTER ON PROCESS GAUGE
The following was received by the State of Illinois via email:
"On September 18, 2013, Equistar Chemical's Radiation Safety Officer contacted the Agency [Illinois Emergency Management Agency] to report that a shutter on a fixed gauge could not be closed at their Morris, Illinois facility. The shutter on the fixed level gauge, manufactured by Vega America, could not be closed during a routine shutter check. The gauge is located on a vessel that is not routinely accessible to personnel due to temperatures on their hot particle line. The gauge normally operates in the constant 'open' position. It remains in its normal operational configuration at this time. This situation does not pose an immediate threat to health or safety unless an emergency shutdown condition were necessary requiring access to the vessel. At the time of discovery, a consultant was on-site performing the shutter checks and he immediately performed a dose rate survey of the device with no unusual measurements noted. This device was last checked and found to be operational in June 2013. The manufacturer was contacted to arrange service of the device on-site.
"The next day, the Radiation Safety Officer reported that following several additional attempts, they had been able to close the shutter. Per the manufacturer, the gauge shutter and handle shaft were sprayed with a light penetrating oil and after some time spent partially rotating the shutter, it will now rotate 90 degrees and allow the licensee to close the gauge if necessary. Arrangements were made with the manufacturer's field engineering group to have a shutter repair kit sent to the site within the next week when a field technician can perform the necessary repairs. The licensee believes that since all of the symptoms were very similar to previous device issues at the facility in the same area of the plant, water and resulting corrosion are inside of the gauge housing which is binding the shutter."
Illinois NMED Number: IL13029 |
| Fuel Cycle Facility | Event Number: 49368 | 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: RANDY SHACKELFORD
HQ OPS Officer: HOWIE CROUCH | Notification Date: 09/20/2013
Notification Time: 12:18 [ET]
Event Date: 09/20/2013
Event Time: 08:00 [EDT]
Last Update Date: 09/20/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
DEBORAH SEYMOUR (R2DO)
KING STABLEIN (NMSS)
| Event Text SUPERVISOR TESTED POSITIVE FOR ALCOHOL ON A FOR CAUSE TEST
A facility supervisor tested positive for alcohol on a for-cause fitness for duty test. The supervisor's access to the facility has been restricted.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49388 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MARK HOESCHEN
HQ OPS Officer: CHARLES TEAL | Notification Date: 09/27/2013
Notification Time: 09:33 [ET]
Event Date: 09/27/2013
Event Time: 08:20 [CDT]
Last Update Date: 09/27/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BILLY DICKSON (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 TECHNICAL SUPPORT CENTER PLANNED MAINTENANCE
"On 9/27/13, Monticello Nuclear Generating Plant's Technical Support Center power supply will be isolated to perform a planned maintenance activity. The maintenance activity may require implementation of compensatory measures to maintain TSC functionality during the activity. The compensatory measures include having the Emergency Director report to the Control Room and co-locating the remaining TSC staff at the EOF should an event be declared requiring ERO activation. The ERO has previously successfully demonstrated the ability to implement these compensatory measures. The maintenance activity is scheduled to be completed with the TSC returned to full functionality by the end of the dayshift on 9/27/13. The Site Emergency Response Organization has been notified of the maintenance activity.
"The licensee has notified the NRC Resident Inspector."
* * * UPDATE ON 9/27/13 AT 1916 EDT FROM MARK IHLENFELDT TO DONG PARK * * *
"On 9/27/13, Monticello Nuclear Generating Plant's Technical Support Center power supply was isolated to perform a planned maintenance activity. The maintenance activity required implementation of compensatory measures to maintain TSC functional during the activity. Maintenance activity is completed and TSC is fully functional and returned to service. Site Emergency Response Organization has been notified. The licensee has notified the NRC Resident Inspector."
Notified R3DO (Dickson). |
| Power Reactor | Event Number: 49389 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN MCILNAY
HQ OPS Officer: DONG HWA PARK | Notification Date: 09/27/2013
Notification Time: 13:35 [ET]
Event Date: 09/27/2013
Event Time: 12:45 [EDT]
Last Update Date: 09/27/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
MARVIN SYKES (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 CALCULATION ERROR RESULTED IN UNANALYZED CONDITION FOR APPENDIX R EVENT
"On July 18, 2012, TVA identified that a calculation error resulted in the inability to establish Essential Raw Cooling Water (ERCW) supply to the Component Cooling System (CCS) heat exchanger within the required time to ensure cooling is available to Reactor Coolant System (RCS) seal injection water during an Appendix R event. TVA promptly established fire watches as a compensatory measure to prevent initiation of fires in the areas of concern. Subsequently, abnormal operating instructions were revised to take action to ensure that adequate time is available to establish ERCW cooling to CCS, and ensure cooling to [Reactor Coolant Pump] RCP seal injection water.
"The calculation error was identified on July 18, 2012, however, it was not recognized at the time that an unanalyzed condition existed that was reportable under 10 CFR 50.72(b)(3)(ii)(B). This report documents that the condition that existed until fire watches were established is reportable under 10 CFR 50.72(b)(3)(ii)(B).
"The NRC Resident Inspector has been notified of this condition." |
| Power Reactor | Event Number: 49390 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JON LAUDENBACH
HQ OPS Officer: VINCE KLCO | Notification Date: 09/27/2013
Notification Time: 17:42 [ET]
Event Date: 09/27/2013
Event Time: 13:30 [CDT]
Last Update Date: 09/27/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BILLY DICKSON (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 LOSS OF EMERGENCY ASSESSMENT CAPABILITY DUE TO RADIATION MONITORS OUT OF SERVICE
"On 9/27/13, Monticello Nuclear Generating Plant personnel identified that when the Service Water Radiation Monitor or the Discharge Canal Radiation Monitors are removed from service for planned maintenance activities, a loss of emergency assessment capability may occur. The adequacy of compensatory measures for when these radiation monitors are removed from service is under evaluation.
"The Service Water Radiation Monitor is taken out of service weekly for flushing. This last occurred at 0221 [CDT] on 9/26/13. The Discharge Canal Radiation Monitors are taken out of service approximately once a year for cleaning. The last time these monitors were removed from service was at 1250 [CDT] on 9/18/13.
"In accordance with 10CFR50.72(b)(3)(3)(xiii) these past occurrences are being reported as a loss of emergency assessment capability.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 49391 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CARL JONES
HQ OPS Officer: DONG HWA PARK | Notification Date: 09/28/2013
Notification Time: 19:25 [ET]
Event Date: 09/28/2013
Event Time: 12:13 [EDT]
Last Update Date: 09/29/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BLAKE WELLING (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 DIGITAL RADIATION MONITOR LOW SAMPLE FLOW ALARM RECEIVED
"At 1213 EDT on September 28, 2013 Nine Mile Point Unit 2 received [Digital Radiation Monitor System] DRMS low sample flow alarm and monitor status of sample pump off for 2SWP*RE146A. The chemistry department was notified to collect and analyze grab samples per [Offsite Dose Calculation Manual] ODCM 3.3.1 as a compensatory measure with the service water radiation monitor 2SWP*CAB146A out of service. 2SWP*RE146A was restarted at 1517 EDT and declared functional.
"At 1548 EDT on September 28, 2013 Nine Mile Point Unit 2 received DRMS low sample flow alarm and monitor status of sample pump off for 2SWP*RE146B. Chemistry was again notified to collect and analyze grab samples per ODCM 3.3.1 as a compensatory measure with the service water radiation monitor 2SWP*CAB146B out of service.
"The service water radiation monitors are necessary for accident assessment and are credited for Emergency Action Level (EAL) classification. The inability to classify an EAL due to an out of service monitor is considered a loss of assessment capability per CFR 50.72(b)(3)(xiii). This condition does not affect the health or safety of the public or the operation of the facility. Compensatory actions remain in place to sample per the requirements of the ODCM.
"The NRC Resident Inspector has been notified."
* * * UPDATE FROM CARL JONES TO CHARLES TEAL AT 0122 EDT ON 9/29/13 * * *
"The Service Water radiation monitors have been restored to service and declared functional. 2SWP*CAB146B restored after maintenance Saturday, 09/28/13 at 2243 EDT. 2SWP*CAB146A was removed from service for maintenance at 2243 EDT on 09/28/13, restored to service and declared functional Saturday, 09/28/13 at 2337 EDT."
The NRC Resident Inspector will be notified. Notified R1DO (Welling).
* * * UPDATE FROM CARL CRAWFORD TO CHARLES TEAL AT 1040 EDT ON 09/29/13 * * *
Update to notification:
"Received subsequent DRMS low sample flow alarm and sample pump trip at 0619 on 9/29/13 for Service Water Radiation monitor 2SWP*CAB146B. The sample pump was returned to service and subsequently tripped again. The monitor has been declared non-functional and Compensatory Actions are being taken per ODCM. Maintenance is engaged for resolution. Investigation includes potential impact from Service Water Mollusk Biocide Treatment which concluded 9/26/13."
The licensee informed the NRC Resident Inspector. Notified R1DO (Welling). | |