| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/09/2010 - 06/10/2010 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 45457 | Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: SOUTHERN SCRAP
Region: 4
City: BLYTHEVILLE State: AR
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KAYLA AVERY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 10/23/2009
Notification Time: 11:18 [ET]
Event Date: 10/20/2009
Event Time: 15:00 [CDT]
Last Update Date: 06/09/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
NEIL OKEEFE (R4DO)
ANGELA MCINTOSH (FSME)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - RADIUM SOURCE FOUND IN SCRAP METAL
The following information was received from the state via e-mail:
"Nucor-Yamato Steel in Blytheville, Arkansas reported to the Arkansas Radiation Control Program on October 20, 2009, that they believed a source had been found in a load of scrap metal received at their facility. The shipper for this load of scrap metal was Southern Scrap, Baton Rouge, Louisiana.
"Radiation surveys conducted by steel mill personnel indicated an on contact reading of 5.0 mR/hr.
"Health Physicists from the Arkansas Radiation Control Program responded to Nucor-Yamato Steel in Blytheville, Arkansas on Tuesday, October 20, 2009 arriving at 3:00 p.m.
"The device is 20 inches long and 6 inches square. The only identifying marks are a plate labeled 'MFD BY S.H. COUCH CO INC' and appears to be a type of selector switch containing a Radium-226 backlight. The switch can select 'AFT STA' or 'WHEEL HSE.'
"Survey readings at the selector switch were 5.5 mR/hr. Removable contamination (not quantified) was found on smears of the device taken in the field.
"The device was packaged and transported to the Arkansas Department of Health and is currently in a secured storage area. The Department continues to investigate this incident to determine the identity of the device as well as the owner."
* * * UPDATE FROM KAYLA AVERY TO HOWIE CROUCH VIA EMAIL AT 1627 EDT ON 6/9/10 * * *
"An employee of American Radiation Services, Inc. (ARS) arrived in Little Rock on March 19, 2010 to retrieve the unknown source. The source was packaged and transported to Port Allen, Louisiana where ARS determined that it was a Radium-226 source of approximately 2.4 mCi. The manufacturer, model number and serial number are still unknown. ADCO Services, Inc. picked up the source from ARS on April 30, 2010 and transported it to Tinley Park, Illinois where it is waiting disposal.
"The Arkansas Department of Health considers this incident to be closed."
Notified R4DO (Powers) and FSME (Mauer).
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 |
| General Information or Other | Event Number: 45777 | Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: NUCOR-YAMATO STEEL
Region: 4
City: BLYTHEVILLE State: AR
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: KAYLA AVERY
HQ OPS Officer: DONALD NORWOOD | Notification Date: 03/19/2010
Notification Time: 12:26 [ET]
Event Date: 03/17/2010
Event Time: [CDT]
Last Update Date: 06/09/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WAYNE WALKER (R4DO)
ANGELA MCINTOSH (FSME)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - DISCOVERY OF A SEALED SOURCE IN A LOAD OF SCRAP METAL
The following information was received via E-mail:
"The following are the findings of the Arkansas Department of Health, Radioactive Materials Program, concerning Event Number 03-10-01 involving an unknown radioactive source at Nucor-Yamato Steel in Blytheville, Arkansas. The Department was contacted on March 17, 2010 indicating that a sealed source had been discovered in a load of scrap metal. The isotope/activity of the sealed source is unknown at this time. It was also stated that survey readings were 50 mR/hr. Health Physicists from the Arkansas Department of Health went to Nucor-Yamato Steel. [Upon discovery], the cylinder-shaped source had been placed in a metal bucket and then put in a 55 gallon metal drum. Readings inside the barrel with the survey meter probe close to the source, the actual readings were 100-140 mR/hr. After all the shielding was in place, a survey was taken with the highest reading being 0.7 mR/hr at the surface of the drum, and the T.I. index [transport index] was 0.2 mR/hr. The drum containing the source was secured in the back of the state vehicle and transported to the Arkansas Department of Health, Radiation Control in Little Rock, Arkansas.
"The source is awaiting pickup by American Radiation Services for transport to their storage location in New Orleans, Louisiana. Further information and identification of the isotope and activity are pending the report from the vendor.
"The State of Louisiana has been notified."
* * * UPDATE FROM KAYLA AVERY TO HOWIE CROUCH VIA EMAIL @ 1627 EDT ON 6/9/10 * * *
"An employee of American Radiation Services, Inc. (ARS) arrived in Little Rock on March 19, 2010 to retrieve the unknown source. The source was packaged and transported to Port Allen, Louisiana where ARS determined that it was a Cesium-137 source of approximately 0.61 mCi. The manufacturer, model number and serial number are still unknown. ADCO Services, Inc. picked up the source from ARS on April 30, 2010 and transported it to Tinley Park, Illinois where it is waiting disposal.
"The Arkansas Department of Health considers this incident to be closed."
Notified R4DO (Powers) and FSME EO (Mauer).
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 |
| General Information or Other | Event Number: 45978 | Rep Org: NEW MEXICO RAD CONTROL PROGRAM
Licensee: LOVELACE MEDICAL CENTER
Region: 4
City: ALBUQUERQUE State: NM
County:
License #: MI 210 94
Agreement: Y
Docket:
NRC Notified By: CARL SULLIVAN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 06/04/2010
Notification Time: 15:20 [ET]
Event Date: 05/11/2010
Event Time: [MDT]
Last Update Date: 06/04/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WERNER (R4DO)
ANGELA MCINTOSH (FSME)
CYNDI JONES (NSIR)
| Event Text AGREEMENT STATE REPORT - MEDICAL MISADMINISTRATION
A patient was treated in early May with a vaginal applicator using three doses of High Dose Rate (HDR) brachytherapy. On May 11, 2010, the patient contacted the doctor's office and complained of skin irritation to her leg. On May 18, 2010, the patient again called to report continued skin irritation. On both of these dates, the patient could not come in to see the doctor. On May 26, 2010, the patient was seen by the doctor and radiation irritation was evident on her leg. Initial estimates of the leg dose are greater than 50 REM. Both the patient and doctor have been notified of this event.
The source was Yttrium (unknown strength).
The state is investigating this event.
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. |
| General Information or Other | Event Number: 45983 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: TARGET ENGINEERING GROUP, INC.
Region: 1
City: MIAMI State: FL
County: MIAMI-DADE
License #: 3366-1
Agreement: Y
Docket:
NRC Notified By: STEVE FURNACE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/07/2010
Notification Time: 14:26 [ET]
Event Date: 06/07/2010
Event Time: [EDT]
Last Update Date: 06/07/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
PAMELA HENDERSON (R1DO)
ANGELA MCINTOSH (FSME)
ILTAB via email ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text FLORIDA AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE
The following information was obtained from the State of Florida via facsimile:
"[The State of Florida] received a report from the company's RSO [Radiation Safety Officer] that a soil moisture density gauge and case was stolen. The licensee parked their truck and left the gauge unattended. Owner still has keys to case and gauge. Unknown as of yet if gauge was chained and locked to vehicle. Licensee will offer a reward. Local police have been notified and licensee is currently awaiting their arrival. Incident assigned to Miami Inspection Office for investigation."
The gauge was a Troxler Moisture Density gauge, model 3440, serial number 37225. The gauge has a 40 mCi AmBe-141 source and a 8 mCi Cs-137 source.
Florida incident number: FL10-070
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: 45984 | Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: WEST SHORE PIPE LINE COMPANY
Region: 3
City: GREEN BAY State: WI
County:
License #: GENERAL709614
Agreement: Y
Docket:
NRC Notified By: MARK PAULSON
HQ OPS Officer: BILL HUFFMAN | Notification Date: 06/07/2010
Notification Time: 15:07 [ET]
Event Date: 06/07/2010
Event Time: [CDT]
Last Update Date: 06/07/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
PATTY PELKE (R3DO)
ANGELA MCINTOSH (FSME)
| Event Text WISCONSIN AGREEMENT STATE REPORT - STUCK OPEN PROCESS GAUGE SHUTTER
The following information was received from the State via facsimile:
"On June 7, 2010 a representative of West Short Pipe Line Company notified Wisconsin Radiation Protection Section of a stuck shutter. This was discovered during a routine six-month shutter check. The device is a Ronan SA1 containing 500 mCi of Cs-137. The general licensee performed a radiation survey and radiation levels were normal. Licensee also performed routine leak test, results are pending. Normal operation for the device is with the shutter open. The device is located in a restricted area that is fenced off. The nearest personnel access point is 600 ft away from the device. The licensee will contact the manufacturer for service.
"The Radiation Protection Section will continue to monitor the situation and will request information concerning the cause of the stuck shutter."
Wisconsin Report No: WI100007 |
| Power Reactor | Event Number: 45990 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: WALTER MILLER
HQ OPS Officer: DONALD NORWOOD | Notification Date: 06/09/2010
Notification Time: 07:58 [ET]
Event Date: 06/09/2010
Event Time: 03:31 [CDT]
Last Update Date: 06/09/2010 | 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):
REBECCA NEASE (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 Shutdown | Event Text REACTOR SCRAM DUE TO CLOSURE OF MAIN STEAM ISOLATION VALVES
"At 0331 CDT on 6/9/10, the Unit 2 reactor automatically scrammed due to closure of the Main Steam Isolation Valves (MSIVs). Operating Instruction 2-OI-99 section 8.1, Reactor Protection System (RPS) Bus B Transfer from Motor Generator to Alternate, was in progress for planned maintenance. The MSIVs closed during the RPS power transfer. The cause of the closure of the MSIVs is under investigation.
"All systems responded as expected to the reactor scram. Safety Relief Valves (SRVs) opened automatically as designed to limit the pressure transient. No Emergency Core Cooling System (ECCS) or Reactor Core Isolation Cooling system (RCIC) reactor water level initiation set points were reached and all expected containment isolation and initiation signals were received. Reactor pressure control was established by manually operating one SRV then maintained using the Main Steam Line Drain Valves. RCIC and the High Pressure Coolant Injection system (HPCI) were manually initiated to control reactor water level. The scram was reset, MSIVs were opened, and the Main Condenser was established as a heat sink. Reactor water level control was established with the Reactor Feedwater System and RCIC and HPCI were returned to standby readiness.
"At 0408 CDT on 6/9/10, a full scram signal was received when 2F Intermediate Range Monitor (IRM) spiked momentarily followed by a spike on 2C IRM. The reactor was stable and operating in Mode 3, Hot Shutdown. No ECCS or RCIC initiation set points were reached. No additional containment isolation signals or initiation set points were received. The cause of the 2C and 2F IRM spikes is under investigation.
"The scram event from critical is reportable within 4 hours per 10CFR 50.72(b)(2)(iv)(B), 'any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' It is also reportable within 8 hours per 10CFR 50.72(b)(3)(iv)(A) and requires an LER within 60 days per 10CFR 50.73(a)(2)(iv)(A). The scram received at 0408 CST is reportable within 8 hours 10CFR 50.72(b)(3)(iv)(A), 'any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B), except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation,' and requires an LER within 60 days per 10CFR 50.73(a)(2)(iv)(A).
"The NRC Resident Inspector was notified."
All rods fully inserted as a result of the first reactor scram. The plant is currently in a normal, post-trip electrical line-up. All SRVs did reseat. There was no impact to the other two units. |
| Power Reactor | Event Number: 45992 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN SIZEMORE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/09/2010
Notification Time: 14:30 [ET]
Event Date: 06/09/2010
Event Time: 11:12 [PDT]
Last Update Date: 06/09/2010 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
DALE POWERS (R4DO)
JACK GROBE (NRR)
WILLIAM GOTT (IRD)
ART HOWELL (R4RA)
JOHN THORP (NRR)
JAY KETTLES (DHS)
KEVIN O'CONNEL (FEMA)
|
| 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 UNUSUAL EVENT DECLARED DUE TO TOXIC GAS/CHEMICAL SPILL IN THE PROTECTED AREA
"Toxic gas in the Owner Controlled Area that adversely affects normal operations."
The licensee declared an Unusual Event under EAL HU3.1 at 1112 PDT. During sodium hydroxide (NaOH) transfer operations on site, a drain valve leak occurred in the condensate polisher buttress area. Onsite personnel responded and stopped the leak. There were no injuries to personnel, no equipment damage and no offsite assistance required.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM SIZEMORE TO CROUCH @ 1517 EDT ON 6/9/10 * * *
Responder access to area has been restored. Approximately 5 gallons of NaOH have been contained. NOUE exit criteria will be that normal access to the polisher buttress is restored.
The licensee has notified the NRC Resident Inspector. Notified IRD (Gott), NRR EO (Thorp) and R4DO (Powers).
* * * UPDATE FROM SIZEMORE TO CROUCH @ 1557 EDT ON 6/9/10 * * *
The licensee has terminated from the Unusual Event at 1241 PDT. Normal access to all plant areas has been restored.
Notified IRD (Gott), NRR EO (Thorp), R4DO (Powers), DHS (Kettles) and FEMA (O'Connel). |
| Power Reactor | Event Number: 45994 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRAIN SIZEMORE
HQ OPS Officer: PETE SNYDER | Notification Date: 06/09/2010
Notification Time: 16:56 [ET]
Event Date: 06/09/2010
Event Time: 11:12 [PDT]
Last Update Date: 06/09/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
DALE POWERS (R4DO)
|
| 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 PRESS RELEASE CONCERNING A CAUSTIC SPILL
"On June 9, 2010, at 10:32 PDT, a caustic spill occurred in the DCPP Unit 1 Turbine Building buttress area. On June 9, 2010, at 10:59 PDT the area was restricted for normal access with SCBAs required for entry into the area. On June 9, 2010, at 11:12 PDT an Unusual Event was declared for DCPP Unit 1. The DCPP Unit 1 reactor remains at full power. No safety related equipment has been impacted.
"The Unusual Event was declared based on EP G-1 Attachment 2 - 'HU3.1 Report or detection of toxic, corrosive asphyxiant or flammable gases that have entered or could enter the Owner Controlled Area in amounts that can adversely affect normal plant operations.'
"The spill amount was reported as 5 gallons.
"The spill was due to a ruptured delivery hose. The hose was isolated initially at the delivery truck and the tank being filled. Hose continued to drain due to residual caustic in the hose. It was reported as 'confined' on June 9, 2010 at 11:02 PDT.
"The spill was reported as 'contained' on June 9, 2010 at 11:44 PDT. Access to the immediate area of the spill is still restricted."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 45997 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEVE INGALLS
HQ OPS Officer: PETE SNYDER | Notification Date: 06/09/2010
Notification Time: 20:02 [ET]
Event Date: 06/09/2010
Event Time: 11:35 [CDT]
Last Update Date: 06/09/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
| Person (Organization):
MONTE PHILLIPS (R3DO)
|
| 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 BATTERY ROOMS DECLARED INOPERABLE DUE TO POTENTIAL FLOODING
"At 1135 CDT, during a plant walkdown, it was observed that the battery room doors to the Unit 1 and Unit 2 turbine building bottom gap seals were not in contact with their respective door thresholds. The gap was approximately 0.25 inches. It is necessary for each of the door seals to be in contact with the thresholds for the plant to be in the configuration assumed by the turbine building High Energy Line Break (HELB) flooding evaluation.
"An analysis was performed of the flood height that would be attained in the battery rooms during a postulated HELB induced flooding event. The result of this analysis was estimated to be a water depth above the limit to maintain operability of safety related components in the battery rooms. This critical flood height would be attained in approximately 30 minutes following a HELB which causes damage to cooling water piping.
"These postulated water levels could have potentially resulted in a loss of safety function for Unit 1 and Unit 2 components between 1135 and 1250 CDT.
"The condition was repaired and the battery rooms were declared operable at 1250 CDT."
The licensee notified the NRC Resident Inspector. | |