| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/27/2010 - 05/28/2010 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 45949 | Rep Org: NORTH DAKOTA DEPARTMENT OF HEALTH
Licensee: WHEATHERFORD INTERNATIONAL LIMITED
Region: 4
City: WILLISTON State: ND
County: WILLIAM
License #: 33-46901-01
Agreement: Y
Docket:
NRC Notified By: DAN HARMAN
HQ OPS Officer: VINCE KLCO | Notification Date: 05/24/2010
Notification Time: 12:05 [ET]
Event Date: 05/21/2010
Event Time: 13:00 [MDT]
Last Update Date: 05/24/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MICHAEL SHANNON (R4DO)
ANGELA MCINTOSH (FSME)
CHUCK CAIN (R4)
| Event Text AGREEMENT STATE REPORT- CALIBRATION SOURCE NOT RETURNED TO ITS STORAGE HOLDER
The following information was received by e-mail:
"About 0930 Weatherford International, LTD. (ND Lic # 33-45901-01) reported that at about 1500, May 21, 2010, in Williston, Williams County, ND, a well logging tool was [returned to] the truck with the calibration source still in the tool. The calibration source is Cs-137, strength about 55.5 GBq. This error was discovered about 1500, May 21, 2010. The source, when in the tool is highly collimated, restricting significant potential dose to a limited volume. The dosimeter badges for those working in the vicinity of the truck and those in an adjacent office have been sent in to Landauer for analysis. Drawings and estimated doses will be forwarded to NRC as soon as received from Weatherford.
"ND Incident #: ND10003" |
| General Information or Other | Event Number: 45953 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: HILLIS-CARNES ENGINEERING ASSOCIATES
Region: 1
City: INDIANA State: PA
County:
License #: PA-1366
Agreement: Y
Docket:
NRC Notified By: DAVID ALLARD
HQ OPS Officer: JOE O'HARA | Notification Date: 05/25/2010
Notification Time: 18:37 [ET]
Event Date: 05/24/2010
Event Time: [EDT]
Last Update Date: 05/25/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DWYER (R1DO)
CHRISTEPHER MCKENNEY (FSME)
| Event Text AGREEMENT STATE REPORT - LOST AND RECOVERED TROXLER NUCLEAR GAUGE MODEL 3411; S/N 6343
The following report was received via fax:
"Event Description: On May 24, 2010, the licensee's nuclear gauge operator was working on the road leading to the Pinegrove State Correctional Institution (PSCI). The gauge operator left the jobsite and pulled onto Route 286. While the gauge operator was sitting in traffic, it was noticed that the tailgate was open and the gauge was gone. The gauge operator and local highway construction workers looked for the gauge.
"A guard from PSCI left work at 1400hrs. While traveling on SR 286 in Indiana County. The guard noticed the yellow transport box with radiation symbols along side of the roadway. The guard loaded the box onto a truck and took it to the Pennsylvania State Police (PSP) barracks in Indiana, PA. The label noted it contained Cesium-137, thus the PSP requested a local Hazardous Material Team come to the barracks and survey the container.
"Radiation levels appeared normal. The evening of May 24th the PSP, the licensee and a gauge service provider were contacted by DEP [Department of Environmental Protection] Bureau of Radiation Protection [BRP] to assess the situation at the barracks, secure the nuclear gauge, and arrange for the licensee to meet DEP/BRP staff at the PSP barracks the next day to examine the gauge and move it to the licensee's PA facility. Regional DEP staff met the licensee on [May 25th] to perform a radiation survey and conduct an interview. The gauge was released to the licensee by PSP.
"Cause of the Event: The gauge was not secured in the vehicle, and the tailgate was left open as the operator drove the vehicle.
"Actions: DEP performed an investigation on May 25, 2010. After the investigation, the PSP returned the gauge to the licensee. DEP will continue to review the licensee's actions related to this event."
Event report number: PA100005 |
| General Information or Other | Event Number: 45954 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: UNKNOWN
Region: 1
City: MIDLAND State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID ALLARD
HQ OPS Officer: VINCE KLCO | Notification Date: 05/25/2010
Notification Time: 18:37 [ET]
Event Date: 05/21/2010
Event Time: [EDT]
Last Update Date: 05/25/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DWYER (R1DO)
CHRISTEPHER MCKENNEY (FSME)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST SOURCE FOUND IN SCRAP METAL
The following information was received by fax:
"On Friday May 21, 2010 radiation detectors alarmed due to a device containing 200 mCi of Americium [Am]-241 detected at the ATI [Allegheny Technologies Incorporated] Midland [Pennsylvania] facility prior to a charge being loaded into the furnace. On Monday May 24, 2010 an employee from Allegheny Raw Materials (ARM) saw part of a radiation symbol in the off-loaded metal scrap and contacted AHP [Applied Health Physics] when they got high radiation level readings. The scrap metal had passed thru two sets of radiation detection monitors prior to being detected by a rail detection system. When AHP responded, production was stopped at ATI (which uses an electric arc furnace), and AHP checked the three charge buckets, and other areas. The Am-241 gauge was reading about 150 mR/hr on contact. The manufacturer of the device is NDC systems, serial # 295. The device was sold to Magla Corp (NC) [in] January of 1976.
"The device [is] onsite and has been wrapped in lead by AHP. AHP and ATI have labeled the device with a 'caution radioactive material' sign and stored it in a secured room with two chains and two locks."
Pennsylvania Event Report ID No: PA100007
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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| General Information or Other | Event Number: 45955 | Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: HARSCO METALS AMERICAS
Region: 1
City: CRANBERRY TOWNSHIP State: PA
County:
License #: PA-G0038
Agreement: Y
Docket:
NRC Notified By: DAVID ALLARD
HQ OPS Officer: JOE O'HARA | Notification Date: 05/25/2010
Notification Time: 18:37 [ET]
Event Date: 05/14/2010
Event Time: [EDT]
Last Update Date: 05/25/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DWYER (R1DO)
CHRISTEPHER MCKENNEY (FSME)
| Event Text AGREEMENT STATE REPORT - ALLOY ANALYZER SHUTTER FAILURE
The following report was received from the Commonwealth of Pennsylvania via fax:
"Notifications: A letter from the Radiation Safety Officer dated May 17, 2010 was received May 21, 2010 by the Department of Environmental Protection explaining the event. Note: an initial review of the letter by PaDEP [Pennsylvania Department of Environmental Protection] and NRC Region I noted this was a 30-day NMED reporting [only] per 10CFR30.5(c)(5), but upon further review of 10CFR31.2 and 30.5(b)(2)(ii), it was concluded this event is a 24-hr report.
"Event Description: On May 14, 2010, Harsco Metals identified a failure of the shutter mechanism on a generally licensed portable alloy analyzer during the semi-annual test. The analyzer was a Niton model XLp818 (ser# 6500) with approximately 30 mCi (1.11 GBq) of Americium-241. A licensed contractor attempted to provide a radiation exposure survey and found the device could be operated without utilizing the [trigger switch] safety mechanism. No individuals were in contact with or exposed to the direct beam during this procedure.
"Cause of the Event: Equipment failure
"Actions: The device has been taken out of service and Harsco Metals will contact the device manufacturer for instruction on returning the instrument for repair or replacement. PaDEP considers this a closed incident at this time."
Event Report ID No: PA100006 |
| Power Reactor | Event Number: 45958 | Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ANDREW WISNIEWSKI
HQ OPS Officer: CHARLES TEAL | Notification Date: 05/27/2010
Notification Time: 08:31 [ET]
Event Date: 05/27/2010
Event Time: 02:00 [EDT]
Last Update Date: 05/27/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JAMES DWYER (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text LOSS OF COMMUNICATIONS
At 0200 EDT on 5/27/10, operators identified that the FTS 2000, NAS [Nuclear Alert System] and commercial phones systems were not functional. ERDS is not functional. The loss of communications appears to be weather related.
[The licensee] validated microwave communication with ISO New England and NRC is available. Cell phone communication is functional. The NRC and state were contacted using alternate means.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM ANDREW WISNIEWSKI TO VINCE KLCO ON 5/27/2010 AT 1459 * * *
Notified by the licensee that FTS 2000, NAS, commercial phone systems and ERDS are functional. The licensee will notify the NRC Resident Inspector.
Notified the R1DO (Dwyer). |
| Power Reactor | Event Number: 45960 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BRIAN SCOTT
HQ OPS Officer: CHARLES TEAL | Notification Date: 05/28/2010
Notification Time: 03:43 [ET]
Event Date: 05/28/2010
Event Time: 00:03 [EDT]
Last Update Date: 05/28/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
ROBERT HAAG (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DUE TO LOSS OF REACTOR COOLANT PUMP
"A Unit-2 reactor trip was initiated by a loss of the Unit-2 'B' station service bus. The loss of the 'B' station service bus caused a reactor trip due to the loss of flow on one-of-three loops due to the loss of the 'B' Reactor Coolant Pump. The Auxiliary Feed Water system actuated as expected due to the reactor trip. The plant was stabilized in Mode 3 using the appropriate emergency procedure.
"During the transient, the 'B' Reserve Station Service Transformer de-energized and the Unit-2 'H' Emergency Diesel Generator was previously tagged out for planned maintenance. This resulted in the Unit-2 'H' emergency bus being de-energized. The alternate AC diesel generator has been placed in service and is providing power to the Unit-2 'H' emergency bus. The automatic tap changer for the 'C' reserve station service transformer did not work in automatic and had to be manually adjusted to control voltage. Unit-2 'C' Reactor Coolant Pump remains in service.
"All control rods fully inserted on the trip and no relief valves lifted or safety valves lifted in either the primary or secondary systems. The turbine drive and 'B' motor driven Auxiliary Feed Water pumps automatically started and injected into the 'A' and 'B' steam generators on a low level signal. The 'A' motor driven Auxiliary Feed Water pump failed to start due to the loss of the 'H' emergency bus. The 'C' steam generator is being controlled with main feed water though the 'C' main feed regulating valve bypass valve. Decay heat removal is via the condenser steam dumps.
"The licensee has notified the NRC Resident Inspector." |
| General Information or Other | Event Number: 45961 | Rep Org: C&D TECHNOLOGIES INC
Licensee: C&D TECHNOLOGIES INC
Region: 1
City: BLUE BELL State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KRIS TUFAROLO
HQ OPS Officer: CHARLES TEAL | Notification Date: 05/28/2010
Notification Time: 11:23 [ET]
Event Date: 05/28/2010
Event Time: [EDT]
Last Update Date: 05/28/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
JAMES DWYER (R1DO)
ROBERT HAAG (R2DO)
KENNETH RIEMER (R3DO)
MICHAEL SHANNON (R4DO)
PART 21 GROUP (EMAI)
| Event Text POST CORROSION ON DCU BATTERIES
The following was received via fax:
C&D Technologies, Inc. (C&D) received a report from a non-domestic customer who is not a U.S. licensee concerning cracks in positive post seals in C&D 3DCU-9 batteries. As a precautionary measure, C&D has chosen to treat this customer's report in the same manner as if the report involved a defect claim by parties regarding matters subject to 10 CFR Part 21. This defect is believed to affect DCU product line batteries 3DCU-7, 2DCU-9, and 3DCU-9, manufactured in the period January 1993 through May 2008. These batteries are used in class 1E applications.
The facilities affected by this are DC Cook, Nine Mile Point, Grand Gulf, Susquehanna, Columbia, and Sequoyah. | |