| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/19/2014 - 09/22/2014 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 50447 | Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: HOOD CONTAINER CORPORATION
Region: 1
City: WAVERLY State: TN
County:
License #: R-43003-J14
Agreement: Y
Docket:
NRC Notified By: CHARLES ARNOTT
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 09/11/2014
Notification Time: 11:59 [ET]
Event Date: 09/10/2014
Event Time: [EDT]
Last Update Date: 09/11/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TODD JACKSON (R1DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - GAUGE SHUTTER STUCK IN OPEN POSITION
The following report was received from the Tennessee Department of Environment and Conservation Division of Radiological Health via email;
"The licensee and gauge service representative called [the Tennessee Department of Environment and Conservation Division of Radiological Health] to report a gauge shutter stuck in the open position. The gauge is an Ohmart Model SHRM, SN 3307, with a 35 mCi Cs-137 Model A-5771 source. The gauge remains in the installed position. It will be replaced in the future by the service representative. The gauge will be shielded as needed if the shutter is not able to be closed before transport."
There were no over exposures and additional information will be provided, as it is received, from the State of Tennessee.
Tennessee Event Number: TN-14-172 |
| Agreement State | Event Number: 50451 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: AMERICAN X-RAY AND INSPECTION SERVICES INC.
Region: 4
City: MIDLAND State: TX
County: REEVES
License #: 05974
Agreement: Y
Docket:
NRC Notified By: IRENE CASARES
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 09/12/2014
Notification Time: 10:42 [ET]
Event Date: 09/11/2014
Event Time: 12:00 [CDT]
Last Update Date: 09/12/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY AZUA (R4DO)
FSME EVENTS RESOURCE (E-MA)
|
| This material event contains a "Category 2 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE STUCK OUTSIDE THE CAMERA
The following information was received via e-mail:
"On September 11, 2014, at 1241 hours [CDT], the Agency [Texas Department of State Health Services] was notified by the licensee's Radiation Safety Officer (RSO) that one of their radiography crews reported they were unable to fully retract a 46 curie iridium - 192 source into a SPEC 150 exposure device. The RSO stated the radiographers had completed an exposure and cranked the source back to the exposure device. The radiographer picked up their dose rate meter and observed the reading was 30 millirem an hour. The radiographer also observed that the locking mechanism had not tripped. The radiographer contacted the RSO. An individual qualified to perform source retrieval was sent to the scene. The radiographer did not approach the exposure device. The RSO stated the source retrieval person should reach the location in about an hour. Awaiting information from RSO. Update will be provided in accordance with SA-300."
Texas Report #: I-9232
THIS MATERIAL EVENT CONTAINS A "CATEGORY 2" LEVEL OF RADIOACTIVE MATERIAL
Category 2 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. These sources are typically used in practices such as industrial gamma radiography, high dose rate brachytherapy and medium dose rate brachytherapy. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Non-Agreement State | Event Number: 50453 | Rep Org: NOVELIS
Licensee: NOVELIS
Region: 1
City: FAIRMONT State: WV
County:
License #: 47-13348-02
Agreement: N
Docket:
NRC Notified By: MICHAEL ROSSANA
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 09/12/2014
Notification Time: 16:30 [ET]
Event Date: 09/12/2014
Event Time: 11:30 [EDT]
Last Update Date: 09/15/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
TODD JACKSON (R1DO)
FSME EVENTS RESOUCE (EMAI)
| Event Text FIXED GAUGE SHUTTER STUCK IN CLOSED POSITION
The licensee RSO (Radiation Safety Officer) reported that the shutter on a fixed gauge was stuck in the closed position. An authorized technician was able to repair the shutter and the gauge has been returned to service. There were no exposures involved with this event. The gauge is an ABB/IRMS, source model S18 containing a Y-90 300 mCi source. This report is being made per 10CFR30.50(b)(2)(i).
* * * UPDATE FROM MICHAEL ROSSANA TO JOHN SHOEMAKER AT 1250 EDT ON 9/13/14 * * *
The licensee RSO reported that around 0000 EDT on 9/13/14, an electrician performing routine checks found the gauge shutter stuck in the open position. The technician who performed maintenance on the previous day had caused the shutter to stick in the open position because of a mis-positioned screw. Repairs were completed and the gauge shutter is now functioning normally. This gauge is scheduled to be replaced during the upcoming Christmas shutdown. There were no exposures involved with this event.
Notified R1DO (Jackson) and FSME Events Resource via email.
* * * UPDATE FROM MICHAEL ROSSANA TO JOHN SHOEMAKER AT 1224 EDT ON 9/15/14 * * *
The following report was received from the Novelis Corporation RSO via email;
"This email serves as [the licensee's] formal notification to follow up the two telephone notifications made by [the licensee's RSO] on September 12, 2014. Both occurrences were related to shutter failures on the same thickness gauge. These notifications were made to satisfy the NRC Regulation 10 CFR 30.50 reporting requirement.
"On Friday, September 12, 2014, at approximately 1300 [EDT], the shutter on the Novelis Fairmont #1 Mill thickness gauge failed in the closed position. An employee who has received non-routine maintenance training per NUREG-1556, Volume 4, Appendix G & N, took it upon himself to remove the side of the gauge and perform an investigation and repair the stuck shutter. It was determined that the pneumatic cylinder for the shutter was not functioning properly and replaced. A radiation survey was performed and the surrounding area was taped off with caution tape. There was no over exposure to radiation. The gauge was put back into service at approximately 1400 [EDT] that same afternoon.
"On the same night, Friday, September 12, 2014, at approximately 2330 [EDT], the shutter on the same thickness gauge failed again. This time the shutter failed in the open position. Once the shutter was determined to be in the open position, the foreman on shift notified [the RSO]. [The RSO] spoke with the shift electrician and had him perform a radiation survey and tape off the area with caution tape. The shift electrician has received non-routine maintenance training per NUREG-1556, Volume 4, Appendix G & N. [The RSO] was on site at approximately 0030 [EDT] Saturday morning, September 13, 2014. [The RSO] verified that the shutter was in the open position by performing a radiation survey. Additionally, the light identifying the shutter position was RED indicating the shutter was open. The same individual that replaced the pneumatic cylinder was on site and he investigated the failure. It was determined that the shutter appeared to be on a bind and the screws that hold the pneumatic cylinder in place were adjusted and the shutter was free to move as intended.
"With the side off of the gauge, next to the shutter assembly, at 6 inches, the measured mR/H was approximately 1 mR/h. Directly beside the shutter mechanism approximately 2 mR/h was measured. The employee worked for about 30 minutes to adjust the shutter mechanism. During this repair, there was no over exposure to radiation."
Notified R1DO (Lilliendahl) and FSME Events Resource via email. |
| Power Reactor | Event Number: 50474 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DAVID LANTZ
HQ OPS Officer: HOWIE CROUCH | Notification Date: 09/19/2014
Notification Time: 16:35 [ET]
Event Date: 09/19/2014
Event Time: 11:34 [CDT]
Last Update Date: 09/19/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
TOM ANDREWS (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 | Event Text UNANALYZED CONDITION DUE TO A POSTULATED HOT-SHORT FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT
"From review of Event Notification 50468 made by Wolf Creek Nuclear Operating Company on 9/18/2014, which in turn was based on review of INPO Event Report 14-33, 'Direct Current Circuits Challenge Appendix R Fire Analysis,' it was determined that portions of the control circuits for the main turbine-generator direct-current (DC) Emergency Lube Oil Pump and the Emergency DC Seal Oil Pump at Callaway Plant are not properly fused to prevent overload and possible secondary fires. The review found that a fire at the motor starter cabinet in the turbine building could cause specific 'smart' hot shorts that could cause overheating of the control cable and result in secondary fires outside the turbine building, including the Control Building, thereby potentially affecting safe shutdown capability for the plant. Based on this information, it has been determined that this condition is unanalyzed, and on a conservative basis, is reportable per 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition that significantly degrades plant safety.
"As compensatory measures, hourly fire watches are in place in the affected areas of the Turbine Building and Control Building. These compensatory measures, in addition to automatic fire detection and suppression capability in these fire areas, ensure protection of the potentially affected equipment.
"The NRC Resident Inspector has been notified."
The licensee continues to evaluate other control circuits to identify if this condition exists elsewhere. |
| Power Reactor | Event Number: 50475 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DARRELL LAPCINSKI
HQ OPS Officer: HOWIE CROUCH | Notification Date: 09/19/2014
Notification Time: 17:54 [ET]
Event Date: 09/19/2014
Event Time: 13:53 [CDT]
Last Update Date: 09/19/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| 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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNANALYZED CONDITION DUE TO MISSING FIRE BARRIERS
"As part of an extent of condition review related to ENS report 50362 (Unanalyzed Condition Due to Lack of Appropriate Fuse Protection), it was identified that, within the past three years, three additional examples existed of missing fire barriers that could have impacted separation of redundant safe shutdown trains. For the affected areas associated with each of the three missing barriers, compensatory measures (hourly fire watches) had been in place for three years prior to the discovery of the condition. However, it was determined the missing barriers met the reporting criteria for 10 CFR 50.72(b)(3)(ii)(B) as unanalyzed conditions that significantly degraded plant safety.
"The first condition was the use of rodofoam material in Auxiliary Building seismic joint seals. Rodofoam is a combustible foam material and does not provide a fire rating equivalent to the barriers in which it was used. This issue was corrected in a plant modification.
"The second condition is the lack of required fire dampers in ventilation supply ducts to the Aux. Feedwater (AFW) Pump Rooms (Fire areas 31 and 32). An engineering change package has been approved to implement a plant modification to install the required dampers as part of the NFPA-805 transition.
"The third condition is a gap where the ventilation duct passes through the wall from the Bus 150/160 room into the AFW pump room. An engineering change package has been approved to implement a plant modification to correct this condition as part of the NFPA-805 transition.
"The protection of the health and safety of the public was not affected by this issue. In all cases, compensatory measures existed to ensure the protection of safe shutdown equipment.
"The license has notified the NRC Senior Resident Inspector." |
| Power Reactor | Event Number: 50476 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: JEREMY SHARKEY
HQ OPS Officer: DANIEL MILLS | Notification Date: 09/20/2014
Notification Time: 07:42 [ET]
Event Date: 09/19/2014
Event Time: 23:59 [EDT]
Last Update Date: 09/20/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
JOHNATHAN LILLIENDAH (R1DO)
|
| 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 LOSS OF SECONDARY CONTAINMENT INTEGRITY
"At approximately 2359 EDT a temporary modification plug was found to be removed from a floor drain in the Outboard MSIV Room (Trunnion Room). The purpose of the temporary modification plug is to ensure that secondary containment remains intact during outages where the trunnion room door is required to be open. The trunnion room door was open when the plug was found to be removed. The plug was immediately reinstalled, restoring the safety function of the secondary containment.
"Per [10 CFR] 50.72(b)(3)(v)(C), Oyster Creek is reporting an event that could have prevented the fulfillment of the safety function of a system needed to control the release of radioactive material."
The licensee has notified the NRC Resident Inspector. | |