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Event Notification Report for May 13, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/12/2010 - 05/13/2010

** EVENT NUMBERS **


45909 45910 45911 45912 45918 45919 45920 45921 45922

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General Information or Other Event Number: 45909
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: H&H X-RAY SERVICES, INC
Region: 4
City: RINGOLD State: LA
County:
License #: LA-2970-L01
Agreement: Y
Docket:
NRC Notified By: ANN TROXLER
HQ OPS Officer: ERIC SIMPSON
Notification Date: 05/07/2010
Notification Time: 09:10 [ET]
Event Date: 04/26/2010
Event Time: 12:00 [CDT]
Last Update Date: 05/07/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - STUCK/DAMAGED RADIOGRAPHY SOURCE

Received this report from the State of Louisiana via facsimile:

"On April 26, 2010, at a temporary job site a field crew was performing an X-Ray on a pipeline when the X-Ray source could not be returned to the shielded position. Using their survey meters, the crew determined the source was exposed and could not be retrieved. They called the Assistant Radiation Safety Officer who came and did a source retrieval and [received] a 150 mrem exposure. With the source shielded, the licensee transported the camera to QSA Global in Baton Rouge, LA for analysis. The equipment was a Sentinel, model 660B, S/N 82187, loaded with 69.5 Ci of Ir-l92, S/N 60611B. QSA Global observed the source and performed further evaluation. The results were that the weld on the source cracked and the capsule was catching on the exit port of the camera. QSA Global put out a recall for that particular lot of sources and forwarded the damaged camera to QSA Global in Burlington, MA."

This event is Louisiana report # LA1000004

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General Information or Other Event Number: 45910
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: LANTHEUS MEDICAL IMAGING
Region: 1
City: NORTH BILLERICA State: MA
County:
License #: 60-0088
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: ERIC SIMPSON
Notification Date: 05/07/2010
Notification Time: 14:35 [ET]
Event Date: 04/23/2010
Event Time: 14:45 [EDT]
Last Update Date: 05/10/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WILLIAM COOK (R1DO)
GREG SUBER (FSME)

Event Text

AGREEMENT STATE REPORT - EXTERNAL RADIATION LEVELS EXCEED LIMITS

The following was received via email from the Commonwealth of Massachusetts:

"Lantheus Medical Imaging (LMI) received a customer complaint on 4/23/10 from a customer (GE Healthcare in Tampa, FL) reporting a reading of 310 mR/hr on a Tc-99m generator that was manufactured on 4/22/10 at the facility in Billerica, MA. On 4/27/10, LMI was able to clarify that the reading was on the package surface rather than on the generator itself.

"The customer reported the situation to the Florida Bureau of Radiation Control on 4/28/10. LMI has been investigating and have not yet found any evidence of a problem with this generator in their manufacturing records. LMI will continue to investigate and will be receiving the generator back from the customer in the next week or so. They will then examine it directly."

The R1DO (Cook) and FSME (Suber) have been notified.

* * * UPDATE FROM JOHN SUMARES TO JOE O'HARA VIA FAX AT 1041 ON 5/10/10 * * *

The Commonwealth clarified their report that the TC-99m generator is actually a Mo-99 generator.

Notified R1DO (Gray) and FSME (McIntosh).

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General Information or Other Event Number: 45911
Rep Org: COLORADO DEPT OF HEALTH
Licensee: MERCY MEDICAL CENTER
Region: 4
City: DURANGO State: CO
County:
License #: 5-01
Agreement: Y
Docket:
NRC Notified By: JAMES DeWOLFE
HQ OPS Officer: PETE SNYDER
Notification Date: 05/07/2010
Notification Time: 15:49 [ET]
Event Date: 04/29/2010
Event Time: [MDT]
Last Update Date: 05/07/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
GREG SUBER (FSME)

Event Text

AGREEMENT STATE REPORT - POTENTIAL DOSE TO EMBRYO OR FETUS

The State of Colorado provided the following information via email:

"In accordance with [Colorado Code] 7.23.1 [similar to 10 CFR 35.3047], Mercy Medical Center, Durango, CO is reporting a dose to an embryo/fetus in excess of 5 mSv."

"On March 16, 2010 1110 MBq (30 mCi) of I-131 was administered to a 31 [year old] female patient."

"A serum blood [pregnancy] test was taken prior to administration and was negative. On April 26, 2010 the patient, thinking she might be pregnant, took a home urine [pregnancy] test that showed positive. Pregnancy was confirmed by blood serum test on April 27, 2010. Patients OB/GYN physician estimates conception occurred on March 13, 2010."

"Fetal dose was estimated to be approximately 80 mGy (8 rem). At this dose level and administration time in relation to fetal development (still in blastogenesis), there will likely be no impact upon subsequent fetal development or subsequent health risks. The patient has been notified as such."

The Department has begun an investigation of this incident and will keep the NRC informed of the status of our investigation. The licensee stated that all procedures to prevent this occurrence were followed. Human chorionic gonadotropin (Hcg) is not detectable in the blood until 7 - 12 days post conception. The licensee is considering including additional questions during the screening process.

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General Information or Other Event Number: 45912
Rep Org: ALABAMA RADIATION CONTROL
Licensee: STERNS TECHNICAL TEXTILES
Region: 3
City: CINCINATTI State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID TURBERVILLE
HQ OPS Officer: VINCE KLCO
Notification Date: 05/10/2010
Notification Time: 09:37 [ET]
Event Date: 05/05/2010
Event Time: [EDT]
Last Update Date: 05/10/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HAROLD GRAY (R1DO)
ANGELA MCINTOSH (FSME)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - FOUND GENERAL LICENSE DEVICE

The following information was received via facsimile:

"On the afternoon of May 5, 2010, the Alabama Office of Radiation Control received a phone call from a representative of ELG Metals in Mobile, Alabama advising the [Alabama Office of Radiation Control] Agency of the discovery of a device containing Am-241. The Agency was advised that the device was in two pieces. A member of the Department's Expanded Radiological Emergency Response Team was dispatched to verify if the sealed source was intact. On the afternoon of May 5, 2010, a field leak test was performed and its was determined that the sealed source was intact. The device was isolated at that time. On the morning of May 7, 2010, a representative of the Alabama Office of Radiation Control visited ELG Metals in Alabama to determine the condition of the device and assist in identifying the source of radiation. The source of radiation was identified as a NDC model 102, serial number 3572 containing 150 millicuries of Am-241. The investigation determined that the device was last owned by United Nonwoven in Mobile and was originally distributed as a General License device to Stems Technical Textiles in Cincinnati, OH. United Nonwoven in Mobile is no longer in business. The source of radiation was isolated and preliminary leak test results in the field indicate that the source is not ruptured.

"This is all the information that [Alabama Office of Radiation Control] Agency has at this time and is current as of 8:30 am central time, May 10, 2010."

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

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

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Power Reactor Event Number: 45918
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAVE DUESING
HQ OPS Officer: BILL HUFFMAN
Notification Date: 05/12/2010
Notification Time: 03:12 [ET]
Event Date: 05/11/2010
Event Time: 23:18 [EDT]
Last Update Date: 05/12/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
MARK RING (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 100 Power Operation 0 Hot Shutdown

Event Text

MANUAL REACTOR SCRAM DUE TO LOSS OF CONTROL ROD DRIVE CHARGING WATER HEADER PUMPS

"On May 11, 2010, at approximately 2318 hours, a manual Reactor Protection System (RPS) actuation was initiated as required by Technical Specification (TS) Limiting Condition for Operation (LCO) 3.1.5 'Control Rod Scram Accumulators.' Control Rod Drive (CRD) charging water header pressure was less than 1520 psig (i.e., no CRD pumps operating) and there were multiple accumulator faults on withdrawn control rods. At the time of the event, the plant was in Mode 1 at 100% power. All control rods are inserted into the core and the plant is currently stable, in Mode 3 (Hot Shutdown) with reactor pressure at approximately 930 psig. No Emergency Core Cooling Systems were required or utilized to respond to the event and there were no other 10 CFR 50.72 reportable actuations. Reactor coolant level is being maintained in its normal band by the feedwater system and decay heat is being removed by the condenser. The plant is in a normal electrical line-up with all three Emergency Diesel Generators operable and available if needed.

"The cause of the event initiator, an invalid Division 2 Loss of Coolant Accident (LOCA), i.e., High Drywell Pressure/Low Reactor Vessel Water Level, signal, is currently under investigation. Prior to the manual RPS Actuation, the invalid LOCA signal resulted in invalid actuations of Division 2 equipment and systems including, the Division 2 Emergency Diesel Generator (EDG), (which started but did not load onto the bus), Low Pressure
Coolant Injection B and C subsystems (which started the pumps but did not inject into the vessel), discharge of the Suppression Pool Makeup subsystem B into the suppression pool, startup of the Control Room Emergency Recirculation subsystem B, and isolation of Group 2B Containment isolation valves which included the Nuclear Closed Cooling System Containment Return Isolation valve that was not already closed. The affected equipment is being restored in accordance with plant procedure. The NRC Resident Inspector has been notified."

The licensee experienced an instrumentation rack loss of power which appears to have resulted in the inadvertent Division 2 initiation. The initiator of this event also and led to a loss of power to both control rod drive charging water header pumps resulting in charging water header pressure less than required and related accumulator faults which placed the licensee in a technical specification required shutdown condition. The action statement allows only 20 minutes to restore the condition which was insufficient time for the licensee to correct the condition so a manual scram was initiated from 100% power. The scram was characterized as an uncomplicated scram and all system responses (not related to the initial instrument fault) functioned as required.

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Fuel Cycle Facility Event Number: 45919
Facility: WESTINGHOUSE ELECTRIC CORPORATION
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 to UO2)
                   COMMERCIAL LWR FUEL
Region: 2
City: COLUMBIA State: SC
County: RICHLAND
License #: SNM-1107
Agreement: Y
Docket: 07001151
NRC Notified By: CARL SNYDER
HQ OPS Officer: CHARLES TEAL
Notification Date: 05/12/2010
Notification Time: 13:47 [ET]
Event Date: 05/12/2010
Event Time: 12:20 [EDT]
Last Update Date: 05/12/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (c) - OFFSITE NOTIFICATION/NEWS REL
Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
KING STABLEIN (NMSS)

Event Text

OFFSITE NOTIFICATION

"On May 11, 2010, Westinghouse reviewed the vendor chemical laboratory analysis for the Total Suspended Solids (TSS) parameter result for the April 28, 2010, NPDES [National Pollutant Discharge Elimination System] liquid effluent 24-hour composite sample. The sample result indicated that the wastewater discharged from the Westinghouse Columbia plant to the Congaree River during the 24-hour period preceding the April 28th sampling contained 93.16 pounds of TSS, which exceeds the daily maximum permit limit of 64.0 pounds per day. The April 28, 2010 result also produced a monthly average of 46.39 pounds, which exceeds the monthly average permit limit of 32.0 pounds per day. [The] investigation regarding the cause of this high TSS result is still ongoing.

"Liquid discharges from the Columbia Plant are regulated with regard to chemical pollutants through the SC-DHEC/EPA [South Carolina - Department of Health and Environmental Control/Environmental Protection Agency] administered NPDES permit SC#0001848. WEC [Westinghouse Electric Company] is required to notify SC-DHEC of non-compliance conditions which exceed any effluent limitation."

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Power Reactor Event Number: 45920
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: KEVIN UMPHREY
HQ OPS Officer: CHARLES TEAL
Notification Date: 05/12/2010
Notification Time: 15:35 [ET]
Event Date: 05/12/2010
Event Time: 13:51 [EDT]
Last Update Date: 05/12/2010
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):
HAROLD GRAY (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby

Event Text

RPS ACTUATION - LOAD REJECT

"At 1351 hrs. EDT on May 12, 2010, a Calvert Cliffs Unit 1 Reactor trip was generated by a complete load rejection when a main generator output breaker opened while its redundant breaker was opened for planned maintenance.

"The generator output breaker trip caused Reactor Coolant System (RCS) pressure to rise to the Reactor Protection System (RPS) High Pressure setpoint, which opened both Power Operated Relief Valves (PORVs). Both PORVs reclosed when RCS pressure was reduced to normal.

"All Control Rods fully inserted on the trip. Normal heat removal methods are currently in progress."

Unit 1 is in a normal shutdown electrical lineup and there was no impact on Unit 2.

The NRC Resident Inspector has been notified by the licensee.

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General Information or Other Event Number: 45921
Rep Org: DRESSER-RAND
Licensee: DRESSER RAND
Region: 1
City: WELLSVILLE State: NY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JOE MENICHINO
HQ OPS Officer: CHARLES TEAL
Notification Date: 05/12/2010
Notification Time: 18:39 [ET]
Event Date: 05/12/2010
Event Time: [EDT]
Last Update Date: 05/12/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
GREG PICK (R4DO)
PART 21 GROUP (EMAI)

Event Text

LUGS ON DIGITAL FILTER IMPROPERLY SOLDERED

A faulty Digital Control System Output Filter was discovered at Farley Nuclear Power station while installing it on the emergency feedwater Terry Steam Turbine. The problem only affects two plants: Farley Nuclear Power Station and San Onofre Nuclear Power Station. Farley replaced the filter before use. San Onofre had installed and used the filter, but they are replacing it.

"Description of Defect:

"Eyelets inserted into the printed circuit (p.c.) board to make connections from one side of the board to the other side were not soldered on the top side where the terminal block is installed. This may result in the connection being broken during tightening of the wire lug on the terminal block or if other stresses are applied to the p.c. board or terminal block. This defect is limited to output filter serial numbers 10009, 10010, 10011, and 10012.

"Engineering Evaluation and Recommendations:

"Failure can occur during assembly. The results of a seismic event are unknown. All 4 filters must be recovered and repaired. Locations of the 4 filters include Dresser-Rand, Farley Nuclear Station, and San Onofre Nuclear Generating Station."

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Power Reactor Event Number: 45922
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: HERBERT TRITT
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/13/2010
Notification Time: 05:00 [ET]
Event Date: 05/13/2010
Event Time: 05:00 [EDT]
Last Update Date: 05/13/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HAROLD GRAY (R1DO)

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

PARTIAL LOSS OF ERDS AND SPDS DUE TO PLANNED MAINTENANCE

"A partial loss of ERDS [Emergency Response Data System] and SPDS [Safety Parameter Display System] capability will occur while a planned replacement of the site's plant process computer power supplies is performed:

"The following is a list of the inputs to ERDS that will be lost:

IRM 14 PERCENT OF RANGE
SRM 24 NEUTRON FLUX
TORUS WIDE RANGE LEVEL
CORE SPRAY SYSTEM 1 AND 2 FLOWS
MAIN STEAM LINE BAND C RAD LEVELS
DW [Dry Well] WIDE RANGE PRESS
STACK RAGEMS [Radioactive Gas Effluent Monitoring System] LOG LO RNG CH 2

"The following is a list of the SPDS inputs that will be lost:

CORE SPRAY SYSTEM 1 AND 2 FLOWS
EMRV [Electromatic Relief Valves] AND SAFETY VALVE INDICATIONS
DW PRESSURE
MS [Main Steam] A,B,C, AND D RAD MONITORS
DW 02 CONCENTRATION

"ERDS and SPDS are expected to be returned to full functionality by 2000 EDT"

Emergency plan contingency measures are in place to transmit data should it be required during the maintenance period.

The licensee has notified the NRC Resident Inspector.

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Thursday, March 29, 2012