| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/23/2008 - 04/24/2008 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 44150 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: WALMART
Region: 4
City: CYPRESS State: TX
County:
License #: GLA
Agreement: Y
Docket:
NRC Notified By: LATISCHA HANSON
HQ OPS Officer: JASON KOZAL | Notification Date: 04/18/2008
Notification Time: 11:50 [ET]
Event Date: 03/13/2008
Event Time: [CDT]
Last Update Date: 04/23/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JEFFREY CLARK (R4)
MICHELLE BURGESS (FSME)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE - BROKEN TRITIUM EXIT SIGN
The State provided the following information via email:
"On April 17, 2008, the agency received written notification from the Radiation Safety Officer (RSO), reporting that during their routine inventory check they, accompanied by two of their health physics consultants, found the one tritium (H-3) exit signs in a non-public receiving area in their Cypress, Texas store, had a missing face plate, frame and label, red 'EXIT' cover and several H-3 tubes. The RSO reported that the remaining H-3 tubes were intact.
"The RSO reported that they conducted informal interviews with store managers and associates that revealed no additional information as to the date or circumstances of the damage to the sign. The RSO and their consultants stated that because available information does not suggest that the H-3 exit sign (TES) was recently damaged, Wal-Mart believes that no significant contamination currently exists at the site. Additionally, he stated that Wal-Mart reached this conclusion in consultation with consultant Certified Health Physicists (CHPs).
"The RSO stated that their long term corrective actions included: implementing protocols, which have been communicated to employees, for the proper handling of TES to ensure public health and safety and the protection of its employees. They report that they are in the process of inventorying all of the TES at its sites across the country to re-establish the accuracy of its records and to track the current locations of the TES, with the intent of ensuring that all TES are accounted for and handled properly.
"The RSO stated that the damaged TES will be packaged for shipment according to protocols established by their consultants and consistent with Nuclear Regulatory Commission (NRC) guidelines. Wal-Mart anticipates shipping the remnants of the damaged TES to a specific licensee or arranging for a waste broker to ship the TES to a specific licensee authorized to receive it within thirty-days of their report to the agency, which was dated April 10, 2008."
Texas report I-8507
* * * UPDATE PROVIDED BY LATISCHA HANSON VIA E-MAIL TO JASON KOZAL ON 04/23/08 AT 1449 * * *
"On 04/22/08:
"The agency received written notifications each dated April 17, 2008 that three more exit signs were found damaged at the following locations:
"1) 4700 East Palm Valley Blvd., Round Rock, Texas 78665-2580; Store # 5480
- Damaged exit sign discovered on 03/19/08
- approximately 11.5 Ci; Serial # unknown
- one damaged exit sign with the tubes in the letter "T" broken.
"2) 620 S IH-35, Georgetown, Texas 78628-4157; Store # 1303
- Damaged exit sign discovered on 03/18/08
- 20 Ci; Serial #289930
- one damaged exit sign uninstalled and stored in the manager's office, missing it's face plate, it's red "EXIT" cover and all H-3 tubes.
"3) 1030 Norwood Park Blvd., Austin, Texas 78753-6600; Store # 1185
- Damaged exit sign discovered on 03/19/08
- 20.0 Ci; Serial #274828
- one damaged exit sign with broken tubes, installed in the non-public receiving section of the store."
Notified R4DO (Cain), FSME EO (Hsueh).
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.
This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source |
| Power Reactor | Event Number: 44157 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: BRIAN JOHNSON
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/23/2008
Notification Time: 05:15 [ET]
Event Date: 04/23/2008
Event Time: 04:10 [CDT]
Last Update Date: 04/23/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JAMNES CAMERON (R3)
|
| 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 TSC VENTILATION SYSTEM CONSIDERED NON-FUNCTIONAL
"At 0410 CDT on 4/23/08 the Technical Support Center (TSC) Ventilation System was removed from service for scheduled maintenance on the Technical Support Center (TSC) cleanup fan. Without adequate flow rates through the TSC cleanup filter, the TSC ventilation system is considered non-functional. Due to the extent of planned work, prompt restoration of the ventilation system will not be available. Contingency plans are in place to utilize the TSC as long as radiological conditions allow. Procedure F3-6, 'Activation and Operation of the TSC', Section 7.6, directs TSC management to relocate TSC activities to a radiological safe area if necessary. The TSC Ventilation system expected return to service is 1200 CDT 4/23/2008."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM WAYNE EPPEN TO HOWIE CROUCH VIA TELECON AT 1538 EDT ON 4/23/08 * * *
The TSC ventilation system will remain out of service until approximately Friday, April 25, at 1500 CDT. This is due to unforeseen degradation of the ventilation fan motor.
The licensee will be notifying the NRC Resident Inspector. Notified R3DO (Jamnes Cameron) |
| Fuel Cycle Facility | Event Number: 44158 | Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: MATT MAURER
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/23/2008
Notification Time: 08:45 [ET]
Event Date: 04/22/2008
Event Time: 09:00 [CDT]
Last Update Date: 04/23/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
CHARLIE PAYNE (R2)
CHRISTOPHER REGAN (NMSS)
| Event Text IMPROPERLY INSTALLED STEEL ANGLE SUPPORTS ON FREEZER SUBLIMER VESSEL
"At 0900 CDT on 04-22-08, the Plant Shift Superintendent (PSS) was notified that the weight monitoring systems on vessels 2 on C-333 Unit 1 Cell 9, Unit 2 Cell 2, Unit 4 Cell 2 and Unit 4 Cell 9 freezer-sublimers showed weight changes when improperly installed steel angle supports welded to the vessel inlet piping were cut free. Each freezer sublimer vessel has a weight monitoring and trip system (high-high weight trip system) that prevents the over-filling of UF6 into the vessel. The high-high weight trip system is required by TSR 2.4.3.1 to prevent overfilling the freezer-sublimer vessels when in mode F/S 1 (freeze) or F/S 3 (cold standby). At the time of discovery, each freezer sublimer was in a non-applicable TSR mode F/S 6 (out-of-service). However, each freezer-sublimer has been routinely operated in TSR modes F/S 1 and F/S 3 over several years with the steel angle supports installed.
"The steel angle supports were likely installed to facilitate piping alignment during freezer-sublimer construction over fifteen years ago. The steel angle supports were not removed after construction. The presence of the steel angle supports may affect the performance the high-high weight trip system specified in TSR 2.4.3.1. All other installed freezer-sublimers were inspected and no additional steel angle supports were similarly connected. Engineering personnel are conducting a formal stress analysis to determine the stresses the steel supports may have had on the weight monitoring and trip system. There is no evidence that the weight limits specified in TSR 2.4.3.1 have been exceeded as a result of this issue.
"Pending further analysis, this event is conservatively being reported as a 24 hour event in accordance with 10 CFR 76.120(c)(2)(i). This is an event in which equipment is disabled or fails to function as designed when: a.) the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident; b.) the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and c.) no redundant equipment is available and operable to perform the required safety function. "
PGDP Assessment and Tracking Report No. ATRC-08-l 183; PGDP Event Report No. PAD-2008-12; Worksheet No. 44158
The NRC Senior Resident Inspector has been notified of this event, |
| Other Nuclear Material | Event Number: 44159 | Rep Org: LOUISIANA GLOBAL XRAY AND TESTING
Licensee: LOUISIANA GLOBAL XRAY AND TESTING
Region: 4
City: State: LA
County:
License #: LA-0577-L01
Agreement: Y
Docket:
NRC Notified By: WILLIAM JOHNSTON
HQ OPS Officer: JOE O'HARA | Notification Date: 04/23/2008
Notification Time: 10:51 [ET]
Event Date: 03/01/2008
Event Time: [CDT]
Last Update Date: 04/23/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2202(a)(1) - PERS OVEREXPOSURE/TEDE >= 25 REM
| Person (Organization):
CHUCK CAIN (R4)
DUNCAN WHITE (FSME)
| Event Text POTENTIAL OVEREXPOSURE GREATER THAN 1000 RADS
Louisiana Global X-ray and Testing called to report a potential overexposure after consulting with Region IV. Apparently, Landauer notified them that a dosimetry badge worn by one of their employees in the month of March 2008 read greater than 1000 Rads. The licensee is launching an investigation as to where the potential overexposure may have occurred. The affected employee worked both in the State of Louisiana and offshore.
The licensee notified Region IV (Leonard Wert) and the State of Louisiana. |
| Power Reactor | Event Number: 44160 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE BRANDON
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/23/2008
Notification Time: 13:44 [ET]
Event Date: 02/23/2008
Event Time: [EDT]
Last Update Date: 04/23/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
CHARLIE PAYNE (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text 60-DAY VERBAL NOTIFICATION OF INVALID SPECIFIED SYSTEM ACTUATION
"On February 23, 2008, a control room operator was aligning the Containment Purge system for Train B operation and triggered an invalid Containment Vent Isolation (CVI) and Auxiliary Building Isolation (ABI). The operator was removing Train A of the system from operation in accordance with system Operating Instruction (SOI) 30.02, 'Containment Purge System'. The operator made an incorrect assumption that a portion of SOI 90.02, 'Gaseous Process Radiation Monitors', that would have properly blocked and aligned power to the Purge Radiation Monitors had been performed. Therefore, when the operator proceeded with the next step in realigning the radiation monitors, a spike occurred on Radiation Monitor 1-RM-90-131. This caused an invalid actuation of Train B of the CVI and ABI systems. Operators verified the isolation and its cause, and suspended movement of irradiated fuel within the Spent Fuel Pool in response to the Train B CVI/ABI signal. The ABI/CVI signal was reset and Auxiliary Building ventilation was restored in accordance with SOI 30.05, 'Auxiliary Bldg HVAC Systems'.
"The following information addresses the criteria for a 60 day verbal report defined in Section 3.2.6, 'System Actuation' of NUREG 1022, 'Event Reporting Guidelines 10 CFR 50.72 and 50.73'. This telephone notification is being made in accordance with 10 CFR 50.73(a)(2)(iv)(A).
"(a) The specific train(s) and system(s) that were actuated: The spike on the Radiation Monitor initiated an invalid actuation of Train B of the CVI system and ABI system.
(b) Whether each train actuation was complete or partial: The Train B CVI and ABI actuation was complete.
(c) Whether or not the system started and functioned successfully: The system started and functioned successfully, and all components operated as expected."
The licensee has notified the NRC Resident Inspector. |
| Fuel Cycle Facility | Event Number: 44161 | 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: PHILLIP OLLIS
HQ OPS Officer: BILL HUFFMAN | Notification Date: 04/23/2008
Notification Time: 15:46 [ET]
Event Date: 04/23/2008
Event Time: 10:00 [EDT]
Last Update Date: 04/23/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(5) - DEV FROM ISA
| Person (Organization):
CHARLIE PAYNE (R2)
CHRISTOPHER REGAN (NMSS)
| Event Text NON CRITICAL-SAFE CONTAINER BROUGHT INTO SAFE STORE AREA
"A 35 quart mop bucket was brought into a safe store, cleaning area where clean up work is being done to decontaminate old, previously cleaned (safe store), equipment for removal from the facility. This mop bucket is unauthorized for use in this area.
"The mop bucket was removed from the area and a review of the facility is being conducted for the presence of additional unauthorized mop buckets.
"GNF is making this 24-hour report in accordance with 10 CFR 70, Appendix A, (b)(1) - Any event or condition that results in the facility being in a state that was not analyzed, was improperly analyzed, or is different from that analyzed in the Integrated Safety Analysis, and which results in failure to meet the performance requirements of � 70.61.
"There were no actual or potential safety consequences to workers, the public, or the environment.
"[The licensee considers this event is of] minor safety significance. No safety equipment impacted. Investigation of event and implementation of additional corrective actions pending."
The licensee plans to notify the State and NRC Regional Office. |
| Power Reactor | Event Number: 44162 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAVID WELLS
HQ OPS Officer: BILL HUFFMAN | Notification Date: 04/23/2008
Notification Time: 16:03 [ET]
Event Date: 04/23/2008
Event Time: 12:08 [CDT]
Last Update Date: 04/23/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
JAMNES CAMERON (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 97 | Power Operation | 97 | Power Operation | Event Text OFFSITE ASSISTANCE REQUESTED DUE TO UTILITY POLE FIRE OUTSIDE THE PROTECTED AREA
"On April 23. 2008 at 1150, Clinton Power Station (CPS) Main Control Room received notification from a site employee that a utility pole on the 138 KV line North of the main parking lot was on fire. Ameren/IP was contacted.
"At 1155, Ameren/IP de-energized the 138kV line.
"Offsite assistance was requested from the Local Fire Department at time 1206.
"At time 1256, the offsite Fire Department extinguished the fire.
"Clinton Power Station remained online at full electrical load during the event and remains stable. Repairs are in progress, with an expected completion this evening.
"The NRC Resident Inspector has been informed." | |