| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/01/2010 - 12/02/2010 ** EVENT NUMBERS ** |
 | General Information | Event Number: 46422 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: DUKE UNIVERSITY AND MEDICAL CENTER
Region: 1
City: DURHAM State: NC
County:
License #: 032-0247-4
Agreement: Y
Docket:
NRC Notified By: PAUL HUGGINS
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 11/16/2010
Notification Time: 11:01 [ET]
Event Date: 11/13/2010
Event Time: [EST]
Last Update Date: 12/02/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
HAROLD GRAY (R1DO)
GLENDA VILLAMAR (FSME)
| Event Text AGREEMENT STATE REPORT - PATIENT RECEIVED A THYROID IMAGING DOSE OF I-123 THAT WAS CONTAMINATED WITH I-131
The following report was received from the State of North Carolina via email:
"This is to notify you about a medical event under the regulation .0364, i.e., within 24-hr notification requirement after discovery. The following summarizes the medical event.
"Event: Contamination of I-123 thyroid imaging dose with I-131 (WRONG RADIONUCLIDE).
"Dose: 380 rad (3.8 Gy) to the thyroid gland (EXCEEDS 50-RAD THRESHOLD FOR ORGAN DOSE)
"Notification: Patient's parent and referring physician have been notified.
"A detailed report will follow within 15 days."
This event occurred sometime on Friday 11/13/10 and was discovered on Monday 11/15/10 at 1535 hrs. The patient was a child and potential adverse effects have not been determined at this time.
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.
* * * UPDATE RECEIVED FROM PAUL HUGGINS TO JOHN SHOEMAKER VIA EMAIL ON 11/22/10 @ 0954 * * *
"DESCRIPTION OF THE EVENT:
A patient was administered 0.389 mCi of iodine-123 orally for a thyroid uptake and scan procedure. Upon imaging at 4 hours, the technologist noted excessive background in the image. The acquisition computer showed an additional peak at 364 keV, consistent with presence of iodine-131 contamination. The iodine-131 thyroid burden at 21 hours was estimated to be about 43 microcuries. Based upon an iodine-123 uptake of 30%, the intake of iodine-131 was estimated to be about 143 microcuries. The absorbed dose to the thyroid, as estimated on 11/15/2010, was about 3.8 Gy (380 rad), or an equivalent dose of 3.8 Sv (380 rem), assuming age-specific reference values for thyroid mass and effective half-life.
"An intake of 143 mCi of iodine-131 is comparable to activities that were administered in the past for diagnostic thyroid imaging, and no adverse effects are expected.
"WHY THE EVENT OCCURRED:
Interviews with staff and assaying the equipment used for the iodine-123 administration indicate that the screw-cap on the vial was the likely source of the contamination. It is unclear whether the screw-cap removal device, or improper handling of the cap, was the cause of the contamination.
"STEPS BEING TAKEN TO PREVENT A RECURRENCE:
The Authorized User and senior technical staff have educated staff about proper handling of radioiodine. To prevent a recurrence, we have changed our procedure as follows:
1) Only one radioiodine dose will be kept in the 'dosing hood' at any time.
2) The vial will be opened only when the patient and necessary staff are in the hot lab.
3) A separate cap remover will be used for each radionuclide.
4) Only one technologist will be involved with preparing dosing area, dosing the patient, cleaning up the dosing area and surveying post therapy."
North Caroline Incident #: NC 10-50
Notified R1DO - R. Conte and FSME - G. Villamar
* * * UPDATE FROM PAUL HUGGINS TO ERIC SIMPSON AT 0936 EST ON 12/2/10 * * *
The I-131 intake is being corrected to 143 microcuries, instead of 143 millicuries, as reported previously.
Notified the R1DO (Schmidt) and FSME (Villamar). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | General Information | Event Number: 46439 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: PROTECHNICS
Region: 4
City: HOUSTON State: TX
County:
License #: L03835
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/26/2010
Notification Time: 12:33 [ET]
Event Date: 11/26/2010
Event Time: [CST]
Last Update Date: 12/01/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TOM ANDREWS (R4DO)
GLENDA VILLAMAR (FSME)
| Event Text AGREEMENT STATE REPORT - VEHICLE TRANSPORTING WELL LOGGING SOURCES INVOLVED IN ACCIDENT WITH FATALITY
The Texas Department of Health, Radiation Branch, received notification from the licensee that their truck, transporting well logging sources, was involved in a rollover accident in which the driver was killed. During the accident, the overpack carrying the sources was torn loose from the vehicle but remained intact. The overpack did sustain some damage but the source boxes appear to be intact and accounted for. A U.S. Border Patrol officer was on scene and performed surveys of the overpack and surrounding area and did not detect any abnormal background readings. The sources are currently under the control of the Texas Department of Public Safety officers (Texas State Troopers) at the scene awaiting recovery and transport by the licensee.
Due to the nature of the accident, all paperwork pertaining to the sources is scattered around the accident scene. Paperwork recovered at the scene indicate that the truck was carrying Iridium-192, Scandium-46 and Antimony-124 with total activity of all packages at approximately 726 mCi.
The accident occurred 4 miles outside of Encinal, TX on State Highway 44.
* * * UPDATE AT 1708 EST ON 11/26/10 FROM KAREN BLANCHARD TO S. SANDIN * * *
The licensee has arrived on-scene, confirmed that there was no release of radioactive material and taken possession of the following packages containing 240 mCi Iridium-192, 160 mCi Scandium-46 and 320 mCi Antimony-124 for return to their Alice, TX office.
Notified R4DO (Andrews) and FSME (Piccone).
* * * RETRACTION AT 1722 EST ON 12/1/10 FROM KAREN BLANCHARD TO P. SNYDER * * *
The State of Texas provided the following information via e-mail:
"It was determined after all information was collected that the incident does not meet any reporting requirement.
"The Agency [Texas Department of Health] is requesting that this event be retracted."
Notified R4DO (Powers) and FSME (Danna). |
| Power Reactor | Event Number: 46443 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: ERIC SWAIN
HQ OPS Officer: ERIC SIMPSON | Notification Date: 12/01/2010
Notification Time: 15:14 [ET]
Event Date: 12/01/2010
Event Time: 14:55 [EST]
Last Update Date: 12/01/2010 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
WAYNE SCHMIDT (R1DO)
JOHN THORP (NRR)
WILLIAM GOTT (IRD)
BRUCE BOGER (NRR)
BILL DEAN (R1 R)
DORA HEYMAN (FEMA)
TERRY FIELD (DHS)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 25 | Power Operation | 25 | Power Operation | Event Text UNUSUAL EVENT DECLARED DUE TO EXCESSIVE RCS LEAKAGE FROM "B" RECIRC PUMP SEAL
"Oyster Creek has declared an Unusual Event (MU7) due to Reactor Coolant System leakage greater than 10 gpm. Leakage has been determined to be from the 'B' reactor recirculation pump seals. The 'B' Reactor Recirculation Loop was isolated and leakage stopped."
The plant remained in the normal electrical lineup and no safety systems actuated during this evolution.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM ERIC SWAIN TO ERIC SIMPSON AT 1548 ON 12/1/10 * * *
At 1537 EST, "Oyster Creek has terminated from an Unusual Event. Event terminated due to isolating leakage from the 'B' Reactor Coolant Loop."
The licensee notified the NRC Resident Inspector.
Notified R1DO (Schmidt), IRD (Gott), NRR EO (Nelson), DHS and FEMA. |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Fuel Cycle Facility | Event Number: 46444 | Facility: HONEYWELL INTERNATIONAL, INC.
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
Comments: UF6 CONVERSION (DRY PROCESS)
Region: 2
City: METROPOLIS State: IL
County: MASSAC
License #: SUB-526
Agreement: Y
Docket: 04003392
NRC Notified By: MARK WOLF
HQ OPS Officer: STEVE SANDIN | Notification Date: 12/01/2010
Notification Time: 15:20 [ET]
Event Date: 11/30/2010
Event Time: 05:00 [CST]
Last Update Date: 12/20/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
SCOTT SHAEFFER (R2DO)
KING STABLEIN (NMSS)
| Event Text LOSS OF POWER TO INSTRUMENTATION IN THE OPERATING UNITS OF THE FEED MATERIALS BUILDING
"Description of the Event: This report is performed pursuant to 10 CFR 40.60(b)(2) reporting requirements.
"On Tuesday, November 30, 2010, at approximately 0500, the failure of F-Substation caused a loss of instrumentation in operating units in the Feed Materials Building. At 0505, various weight, temperature and pressure indications were not available.
"Due to the loss of power to a load cell component, the UF6 Vaporizer weight exceeded the administrative limit. During the power loss the vessel's weight measurement was not available to the operator.
"At 0538, power was restored and instrumentation readings returned to normal. The loss of the Vaporizer weight control did not have any safety consequences.
"Isotope, Quantities and Chemical Form: No material release.
"Personnel Radiation Exposure Date (if applicable): No additional exposure to radiation or radioactive materials."
The licensee will inform the NRC Region II Office.
* * * RETRACTION FROM MICHAEL GREENO TO JOE O'HARA AT 1659 ON 12/20/10 * * *
"On December 1, 2010, Honeywell Metropolis Works made notification of Event #46444 to the NRC Operations Center. This November 30, 2010 incident occurred due to the loss of power to a load cell component. During the power loss the weight measurement was not available to the operator, and the UF6 Vaporizer weight exceeded the administrative limit.
"This twenty-four hour report was made following 10 CFR 40.60(b)(2) reporting requirements:
"Each licensee shall notify the NRC within 24 hours after the discovery of any of the following events involving licensed material: ...
"(2) An event in which equipment is disabled or fails to function as designed when:
(i) The equipment is required by regulation or license condition to prevent releases exceeding regulatory limits, to prevent exposures to radiation and radioactive materials exceeding regulatory limits, or to mitigate the consequences of an accident;
(ii) The equipment is required to be available and operable when it is disabled or fails to function; and
(iii) No redundant equipment is available and operable to perform the required safety function.
"As determined by Honeywell's safety analysis, potential UF6 release may occur due to failure to control process resulting in process vessel failure. UF6 Vaporizer load cells, which are identified in the safety analysis as a safety feature to control the total weight in this vessel, were not operable during the incident. However, load cells are not the only component designed to perform the equivalent safety function - to prevent UF6 Vaporizer failure. Thus, UF6 Vaporizer failure due to over-pressurization is prevented by the existing relief system which is designed to relieve at a pressure below the maximum allowable working pressure. This Vaporizer relief system was available and operable during the event.
"As a result of these additional considerations, Honeywell determined that the redundant equipment (Vaporizer relief system) was available and operable to perform the required safety function (Vaporizer failure prevention), and therefore the initially reported incident (# 46444) does not meet the reporting requirement (iii). Since this incident does not constitute a reportable event, Honeywell requests to withdraw its event notification #46444."
Notified R2DO(Henson) and NMSS EO(Davis) |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 46445 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: PETER SCHOETTLER
HQ OPS Officer: ERIC SIMPSON | Notification Date: 12/01/2010
Notification Time: 17:40 [ET]
Event Date: 12/01/2010
Event Time: 13:59 [EST]
Last Update Date: 12/02/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
WAYNE SCHMIDT (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 | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION OF PETROLEUM SPILL INTO THE SUSQUEHANA RIVER
"On 12/01/10, at 1359 EST, Peach Bottom Atomic Power Station reported a petroleum product spill in the discharge canal. Total quantity of substance is less than 1 quart. Lewis Environmental agency has been contacted to aid in containment and cleanup of the spill.
"This report is being submitted pursuant to 10 CFR 50.72(b)(2)(xi) and 10 CFR 72.75(b)(2)."
The spill did not reach Comprehensive Environmental Response Compensation and Liability Act (CERCLA) reportable quantities. The licensee notified the Pennsylvania Department of Environmental Protection, United States Coast Guard, and EPA Region 3.
The NRC Resident Inspector has been notified.
* * * RETRACTION FROM E. WRIGHT TO V. KLCO ON 12/2/10 AT 1354 EST * * *
The licensee is retracting the event due to the quantity of substance released to the environment is less than the reportable quantity.
The licensee will notify the NRC Resident Inspector.
Notified R1DO (Schmidt). |
| Non-Agreement State | Event Number: 46446 | Rep Org: GEOCONCEPTS ENGINEERING, INC
Licensee: GEOCONCEPTS ENGINEERING, INC
Region: 1
City: ASHBURN State: VA
County:
License #: 45-25467-01
Agreement: Y
Docket:
NRC Notified By: DREW THOMAS
HQ OPS Officer: ERIC SIMPSON | Notification Date: 12/02/2010
Notification Time: 16:25 [ET]
Event Date: 12/02/2010
Event Time: 14:00 [EST]
Last Update Date: 12/14/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
WAYNE SCHMIDT (R1DO)
JAMES DANNA (FSME)
ILTAB VIA EMAIL ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text THEFT OF TROXLER MOISTURE DENSITY GAUGE
A Troxler moisture density gauge being used at Fort Meade (Maryland) was found to be stolen along with other industrial equipment at 1400 on 12/2/10. The Troxler gauge was last seen on Monday afternoon, 11/29/10, when it was secured in a temporary storage location inside a lock-box and chained to a sea container. Other items stolen included crane mats, a generator and miscellaneous tools.
The nuclear gauge is a Troxler Model 3430, S/N 37672, which contains two radioactive sources. One source is 44 mCi of Am-241/Be (S/N 78-2430). The other source is 9 mCi of Cs-137 (S/N 77-4907).
The licensee will notify base police to begin an investigation into the theft.
The licensee has notified the State of Maryland of the theft.
* * * UPDATE FROM DREW THOMAS TO JOE O'HARA AT 0948 ON 12/14/10 * * *
On 12/10/10, FT. Meade U.S. Army base police officers informed the licensee that the stolen container had been "dumped" back onto the jobsite. The licensee responded to the site and discovered the missing gauge inside the container. The source was in the locked and shielded position inside the gauge and the gauge doesn't appear to have been damaged. The gauge has been recovered and is now in the custody of the licensee. A leak test of the gauge is scheduled to be performed.
Notified R1DO(Holody), FSME(Reis) and ILTAB.
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 |
| Fuel Cycle Facility | Event Number: 46447 | Facility: AREVA NP INC RICHLAND
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION
FABRICATION & SCRAP
COMMERCIAL LWR FUEL
Region: 2
City: RICHLAND State: WA
County: PENTON
License #: SNM-1227
Agreement: Y
Docket: 07001257
NRC Notified By: ROBERT LINK
HQ OPS Officer: JOE O'HARA | Notification Date: 12/02/2010
Notification Time: 17:39 [ET]
Event Date: 12/02/2010
Event Time: 07:15 [PST]
Last Update Date: 12/02/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(2) - LOSS OR DEGRADED SAFETY ITEMS
| Person (Organization):
SCOTT SHAEFFER (R2DO)
KING STABLEIN (NMSS)
| Event Text URANIUM CONCENTRATION GREATER THAN EXPECTED IN GAS STRIPPER SYSTEM FOLLOWING AN ACID WASH
"Background:
The purpose of the Ammonia Recovery Facility (ARF) facility is to recover ammonia from the ammonium diuranante (ADU) process effluent by use of a stripper column. The feed of effluent to ARF has a uranium concentration is typically less than 1 ppm. Two uranium analyzers provide assurance that the effluent uranium concentration is less than 100 ppm prior to discharge to the Ammonia Recovery process feed tank V-621.
"The ISA Summary for this process states that only minute quantities of radioactive material are present in the feed to the ARF and that there are no credible accident sequences that result in intermediate or high consequences.
"Event Description:
On 12/02/2010 at 0715, a Process Engineer informed Nuclear Criticality Safety (NCS) that he had confirmed that an acid wash of ARF stripper column had recovered 8 kg of Uranium (U). The acid wash is expected to have removed all significant amounts of Uranium from the system. This resulted in a review of the adequacy of the ISA treatment for the ARF stripper column.
"Safety Significance of Event:
The safety significance is low. The amount of Uranium recovered, approximately 8 kg, is less than 25% of a minimum critical mass in spherical geometry. The concentration of the liquid is about 1 g U/liter. The 8 kg constitutes an approximate ten year accumulation since the last column acid wash in 2001. Based on the accumulation rate over the past 10-years, another 40 years of accumulation would be required without any removal during maintenance before achieving a critical mass.
"The system was down for maintenance at the time of discovery. Maintenance activities were suspended and will remain suspended until an appropriate processing path is identified to process this material and appropriate controls are established. The system will not be restarted until the system has been reanalyzed and appropriate controls are verified to be in place to meet 10CFR70.62 performance criteria.
"Potential Criticality Pathways Involved (Brief Scenarios of how criticality could occur):
Criticality is possible if material in the ARF equipment exceeds a minimum critical concentration and a minimum critical mass for a given geometry.
"Controlled Parameters:
The controlled parameters are upstream of the ARF process and are based on concentration of the feed material. The uranium concentration in ARF feed is typically less than 1 ppm. Two uranium analyzers provide assurance that the ADU effluent uranium concentration is less than 100 ppm prior to discharge to the Ammonia Recovery process.
"Estimated Amount, Enrichment, Form of Licensed Material and % of worst case Critical Mass:
The facility is only licensed to 5 wt.% U-235. The material present in the stripper column prior to being dissolved was likely ammonium diuranate. Once dissolved, the material is uranyl nitrate. The mass in the system is expected to have been less than 25% of a minimum critical mass in spherical geometry.
"When equipment geometry is taken into account, much higher masses are required to obtain a critical condition. For example, the ARF feed tank with a uniform slab of U02-H20 would require an areal density exceeding 10 kg U/ft2 (more than 500 kg U).
"Nuclear Criticality Controls) or Control System(s)) and Description of the Failure Deficiencies:
The upstream controls on concentration performed as required. The material plate-out within the stripper column was greater than anticipated.
"Corrective Actions to Restore Safety Systems and When Each Was Implemented:
The system was down for maintenance at the time of discovery. Maintenance activities were suspended and will remain suspended until an appropriate processing path is identified to process this material and appropriate controls are established. The system will not be restarted until the system has been reanalyzed and appropriate controls are verified to be in place."
The licensee initiated the acid wash of the gas stripper as a result of concerns over the differences in the inlet and outlet pressures of the system, which indicated that the system was becoming less efficient. The licensee briefed Region 2 management and Region 2 fuel cycle facility inspectors about this event. |
| Power Reactor | Event Number: 46448 | 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: VINCE KLCO | Notification Date: 12/02/2010
Notification Time: 18:32 [ET]
Event Date: 12/02/2010
Event Time: 16:10 [EST]
Last Update Date: 12/02/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
SCOTT SHAEFFER (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 OFFSITE NOTIFICATION DUE TO AN INDIVIDUAL CONTAMINATION
"TVA notified TN Dept of Environment and Conservation [TDEC] of an incident at Watts Bar as follows:
"On December 2, 2010, a contractor employee of PAR-Westinghouse was processing in through Watts Bar Nuclear Plant Radiological Protection Program for his first day of work. He was discovered to have been previously contaminated with radioactive material from another worksite. It is clear that the radioactive contamination did not come from any TVA source and was found before he entered the rad control area.
"The contamination was discovered during required in-processing activities for workers by TVA's radiation monitoring and detection equipment. The contamination was found to be a particle on the individual's shoe.
"The individual's clothing was also found to contain measurable contamination and was confiscated. The radioactive contamination found on the individual has been safely contained.
"TDEC Division of Radiological Health was notified of this event as of 1610 Eastern Time and this notification under 10 CFR 50.72(b)(2)(xi) is for that Government Agency notification. TVA has notified the NRC Resident Inspector and Regional Administrator of this incident." |
| General Information | Event Number: 46449 | Rep Org: ROSEMOUNT NUCLEAR
Licensee: ROSEMOUNT NUCLEAR
Region: 3
City: CHANHASSEN State: MN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MARC BUMGARNER
HQ OPS Officer: JOE O'HARA | Notification Date: 12/02/2010
Notification Time: 20:15 [ET]
Event Date: 11/22/2010
Event Time: [CST]
Last Update Date: 12/02/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
WAYNE SCHMIDT (R1DO)
SCOTT SHAEFFER (R2DO)
MARK RING (R3DO)
DALE POWERS (R4DO)
PART 21 GRP ()
| Event Text ANOLMALY DISCOVERED ON ROSEMOUNT MODEL 1152 DIFFERENTIAL PRESSURE TRANSMITTERS WITH OUTPUT CODE "L" 10-50 mA ELECTRONICS
The following was received via fax:
Rosemount Nuclear discovered an anomaly in Model 1152 differential pressure transmitters while troubleshooting a separate, unrelated issue. The anomaly is related to the pressure transmitters response during a overpressure condition. Normally, under a low side overpressure condition, the output will go off-scale and remain off scale for conditions less than 10 mA. Rosemount has discovered that some detectors may go off-scale and then return to on-scale between 10mA and 50 mA, rather than remain off scale under 10mA. This is caused by a change made to operational amplifier components in March 2001. Rosemount recommends all customers evaluate the safety impact of this anomaly on their plants. No field failures have been reported to date.
The following sites are affected: Browns Ferry, Brunswick, Cook, Dresden, Duane Arnold, Fermi, Fort Calhoun, Ginna, Hatch, Indian Point, Kewaunee, Millstone, Nine Mile Point, Oyster Creek, Palisades, Pilgrim, Quad Cities, Sequoyah, Vermont Yankee, and Watts Bar. |
| Non-Agreement State | Event Number: 46450 | Rep Org: ACUREN
Licensee: ACUREN
Region: 4
City: NORTH SLOPE State: AK
County:
License #: 42-32443-01
Agreement: N
Docket:
NRC Notified By: ROBERT MCCALL
HQ OPS Officer: VINCE KLCO | Notification Date: 12/02/2010
Notification Time: 20:19 [ET]
Event Date: 12/02/2010
Event Time: 10:00 [YST]
Last Update Date: 12/02/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
DALE POWERS (R4DO)
JAMES DANNA (FSME)
| Event Text SOURCE FAILED TO RETRACT DUE TO ICE BUILD-UP
A radiography crew working on the Prudhoe Bay North Slope experienced a malfunction of the source retraction portion of their Sentinel Delta 880 radiography device due to ice intrusion. The device source is Ir-192 with a 99 Curie activity.
The radiography crew was able to retract the source into the shielded position using the device crank.
Based on pocket dosimetry readings, there were no personnel over-exposures during this incident. | |