| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/29/2008 - 03/03/2008 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 44011 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: CIRCLE INCORPORATED
Region: 4
City: WESTWEGO State: LA
County:
License #: LA-6627-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/27/2008
Notification Time: 16:15 [ET]
Event Date: 02/27/2008
Event Time: [CST]
Last Update Date: 02/27/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
VIVIAN CAMPBELL (R4)
MICHELE BURGESS (NMSS)
ILTAB (E-MAIL) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - MISSING MOISTURE DENSITY GAUGE
The State provided the following information via facsimile:
"On February 27, 2008, Circle Inc. discovered that a Troxler nuclear gauge with a 9 mCi source of Cs-137 (s/n 50-9134) and a 44 mCi source of Am-241 (s/n 47-14943) was missing from a construction site on the levee near Nicole and Lapalco in Westwego, LA. The incident is under investigation and additional information will be forwarded once it is received."
Louisiana Event Report: LA080004
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. |
| Power Reactor | Event Number: 44016 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: DEWEY BARROW
HQ OPS Officer: BILL HUFFMAN | Notification Date: 02/29/2008
Notification Time: 05:40 [ET]
Event Date: 02/29/2008
Event Time: 04:51 [EST]
Last Update Date: 02/29/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
JOEL MUNDAY (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 4 | M/R | Y | 10 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO HIGH STEAM GENERATOR WATER LEVEL
"With the Unit 4 reactor in Mode 1 at approximately 10% power and immediately following main turbine start-up and synchronizing the main generator to the grid, the reactor and turbine were manually tripped due to 4A steam generator water level rising uncontrollably. The reactor was manually tripped prior to reaching the reactor protection trip point for high steam generator water level. An investigation is in progress to determine the cause of the high water level in the 4A steam generator."
All rods fully inserted upon the trip and all systems functioned as required. There were no complications and the 4A steam generator water level is currently within the normal water level band.
The licensee will be notifying the Resident Inspector. |
| Power Reactor | Event Number: 44017 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: PHIL SANTINI
HQ OPS Officer: BILL HUFFMAN | Notification Date: 02/29/2008
Notification Time: 11:05 [ET]
Event Date: 02/29/2008
Event Time: 10:40 [EST]
Last Update Date: 02/29/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
LAWRENCE DOERFLEIN (R1)
|
| 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 OFFSITE NOTIFICATION OF A SMALL OIL SPILL
"At approximately 1040 EST, a spill of approximately 4.5 gallons of hydraulic fluid from a small dry cask storage utility vehicle occurred. Approximately half the fluid spilled onto the asphalt roadway and half onto the soil. This is not a de-minimis spill and New York State Department of Environmental Conservation and the Westchester County Department of Health will be contacted. Clean-up of the spilled fluid is in progress and the leaking vehicle has a containment device under the leak. There is no impact to sewers or waterways. No operating equipment on Unit 2 or Unit 3 is affected."
The licensee notified the NRC Resident Inspector. |
| Fuel Cycle Facility | Event Number: 44020 | Facility: BWX TECHNOLOGIES, INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU FABRICATION & SCRAP
Region: 2
City: LYNCHBURG State: VA
County: CAMPBELL
License #: SNM-42
Agreement: N
Docket: 070-27
NRC Notified By: CHERYL GOFF
HQ OPS Officer: HOWIE CROUCH | Notification Date: 02/29/2008
Notification Time: 13:15 [ET]
Event Date: 02/28/2008
Event Time: 16:56 [EST]
Last Update Date: 02/29/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (c) - OFFSITE NOTIFICATION/NEWS REL
| Person (Organization):
JOEL MUNDAY (R2)
JOSEPH GIITTER (NMSS)
FUELS FOUO VIA EMAIL ()
| Event Text MEDIA/PRESS RELEASE CONCERNING BWXT ACTIVITIES
"In response to additional media inquiries regarding the NRC News Release No. II-08-002, BWXT will provide the attached information to media representatives contacting BWXT for additional information. In response to media inquiries concerning the possible use of Lynchburg city wastewater treatment plant to treat water from BWXT, BWXT will provide the attached information to media representatives contacting BWXT for additional information:
"Regarding NRC News Release No. II-08-002:
"Q: What are some of the corrective actions taken by the company? One NRC document I read referred to a corrective action of installing brackets onto the raschig ring vacuum cleaners for transport. Is that one of the corrective actions, and has it been completed? What other corrective actions have been taken?
"A: We developed a comprehensive list of corrective actions in response to last year incident. Currently, we are in the process of completing all corrective actions, and are on schedule to meet our commitments to the NRC.
"Q: The Company was given 30 days to pay the fine or appeal it. Which action was taken?
"A; The company paid the fine.
"Regarding Wastewater Treatment inquiry:
"Q: I just learned that the city's wastewater treatment plant is studying the idea of treating water from the B&W facility, and that B&W is paying for the study. Could you provide information, or connect me with someone in the company who can offer a comment on this study? Has B&W been treating its own water before? Why is the company interested in possibly having the city treat the water instead?
"A: A number of new regulations have been issued in recent years to address discharges of nutrients to the Chesapeake Bay and its tributaries. To meet the new requirements, B&W is studying a variety of options, including the possibility of constructing a new pipeline to allow us to discharge a portion of our wastewater into the city's waste water treatment plant. We are working with the Lynchburg Regional Wastewater Treatment Facility and Campbell County to perform a feasibility study for this option to ensure that the city's treatment plant can handle our flow without impacting their current treatment parameters. It's important to note that these wastewaters are non-radioactive. However, the project is still very much in the preliminary stages and a decision on whether or not to pursue this option wont be made for some time."
The licensee will be notifying the NRC Resident Inspector. Notified R2DO (Munday), NMSS EO (Giitter) and Fuels OUO via email. |
| Other Nuclear Material | Event Number: 44023 | Rep Org: SABIA CORPORATION
Licensee: SABIA CORPORATION
Region: 4
City: IDAHO FALLS State: ID
County:
License #: 11-27727-01
Agreement: N
Docket:
NRC Notified By: JAMES MILLER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 02/29/2008
Notification Time: 17:52 [ET]
Event Date: 02/29/2008
Event Time: [MST]
Last Update Date: 02/29/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2202(a)(2) - EXCESSIVE RELEASE
30.50(b)(1) - UNPLANNED CONTAMINATION
| Person (Organization):
VIVIAN CAMPBELL (R4)
PATRICE BUBAR (FSME)
| Event Text STRONTIUM-90 SOURCE LEAKAGE LEADS TO UNPLANNED CONTAMINATION OF WORKER
While disassembling industrial gauges for source disposal, a Sr-90 source was breached causing contamination of the work area and one worker performing the task. Prior to disassembly, the source was leak tested with no leakage found. The size of the source is unknown at this time.
The licensee contacted Region IV materials personnel to discuss this event and it was suggested by the region that the contaminated individual undergo urine bioassay. Region IV has an inspector in the area who will be at the Sabia facility in the morning.
Notified R4DO (Campbell) and FSME EO (Bubar).
* * * UPDATE FROM J. MILLER TO HOWIE CROUCH ON 02/29/08 @ 1956 HRS. * * *
The licensee reports that the source came from a NER 592 gauge, source S/N 1265 manufactured on 8/9/84. The original strength was 100 mCi. Current source strength is 57 mCi. |
| Power Reactor | Event Number: 44024 | Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] B&W-L-LP
NRC Notified By: BRYAN WOOTEN
HQ OPS Officer: BILL HUFFMAN | Notification Date: 03/01/2008
Notification Time: 09:52 [ET]
Event Date: 03/01/2008
Event Time: 04:27 [EST]
Last Update Date: 03/01/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
JOEL MUNDAY (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 20 | Power Operation | 20 | Power Operation | Event Text EMERGENCY FEEDWATER ACTUATION WHILE SHUTTING DOWN
"On 03/01/2008 a pre-planned unit shutdown was in progress to repair a reactor coolant pump seal. At approximately 20% reactor power, a main feedwater flow perturbation occurred. This flow perturbation resulted in an Emergency Feedwater actuation at 0427 [EST]. Both Emergency Feedwater system trains started automatically on low levels in the Once Through Steam Generators as designed. Main feedwater system recovered and continued to supply inventory with levels stabilized at the required low level setpoint. Following plant stabilization, Emergency Feedwater was secured and the pre-planned unit shutdown was resumed. This event is reportable under the requirements of 10 CFR 50.72 (b)(3)(iv)(A)."
The cause of the feedwater flow perturbation is still under investigation. The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 44025 | Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: KYLE GARNISH
HQ OPS Officer: JOE O'HARA | Notification Date: 03/01/2008
Notification Time: 14:34 [ET]
Event Date: 03/01/2008
Event Time: 13:15 [EST]
Last Update Date: 03/01/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
LAWRENCE DOERFLEIN (R1)
|
| 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 OFFSITE NOTIFICATION DUE TO STEAM LEAK AFFECTING ASBESTOS LAGGING
"An emergency asbestos project notification was made to NYS [New York State] Department of Labor in accordance with NYS Code Rule 56. The amount of damaged insulation has been identified as a minor project. The emergency asbestos project is a result of a Moisture Separator Reheater 1A level control system steam leak, which occurred at 0535 3/1/08. No visible damage to permanent structures or equipment, beyond the steam leak, is evident."
A cap blew off a level transmitter which wetted and dislodged the surrounding asbestos insulation which subsequently fell to the floor below. The steam leak has been isolated. There were no injuries or adverse impacts on plant operations.
The licensee will notify the NRC Resident Inspector. | |