| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/31/2005 - 11/01/2005 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 42085 | Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: COLUMBIA IRON AND METAL
Region: 3
City: GIRARD State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MICHAEL SNEE
HQ OPS Officer: STEVE SANDIN | Notification Date: 10/27/2005
Notification Time: 11:04 [ET]
Event Date: 10/26/2005
Event Time: [EDT]
Last Update Date: 10/27/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHRISTINE LIPA (R3)
MICHELE BURGESS (NMSS)
| Event Text SOURCE DISCOVERED AT METAL SCRAP YARD
The State provided the following information via facsimile:
Gauge containing a Sr-90 sealed source was discovered at a metal scrap yard in Girard, Ohio. The gauge is a Betamike model manufactured by Taylor Instruments (Model 015020; Serial 781-35). The activity as of 8/70 was 100 mCi (millicuries). The activity as of 10/27/05 was calculated to be 44 mCi (millicuries). The Ohio Department of Health dispatched an inspector to the scrap yard on October 26. The gauge is secure and a leak test of the source showed no removable contamination. Radiation levels are 5 mR/hr (milliRem per hour) on contact and 1 mR/hr at 30 cm. Disposal options for the device are being investigated.
Ohio Report OH05-134
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. |
| General Information or Other | Event Number: 42086 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: PHARMACY SERVICES OF PEORIA
Region: 3
City: PEORIA State: IL
County:
License #: IL-01874-01
Agreement: Y
Docket:
NRC Notified By: DAREN PERRERO
HQ OPS Officer: BILL GOTT | Notification Date: 10/27/2005
Notification Time: 13:46 [ET]
Event Date: 10/26/2005
Event Time: 14:00 [CDT]
Last Update Date: 10/27/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHRISTINE LIPA (R3)
MICHELE BURGESS (NMSS)
| Event Text AGREEMENT STATE REPORT - LOOSE SURFACE CONTAMINATION AND CONTAMINATED PERSONNEL
"At 6:40 PM, October 26, 2005, the Agency's Duty Officer received a call from the dispatch center to contact Pharmacy Services of Peoria (IL-01874-01) at their Peoria facility regarding a contaminated package they had transported back from Proctor Hospital, Peoria, IL (IL-01188-01) earlier that afternoon. Pharmacy Services of Peoria reported that the package was contaminated on the surface with Tc-99m. Direct measurements yielded 3 milliR/hr and 4.9 million DPM. The package was immediately set aside in their waste area and secured. The driver was surveyed and contamination was found on one hand. His hand was decontaminated until readings were approximately 0.04 milliR/hr and no removable contamination remained. The pharmacy vehicle was subsequently surveyed and decontaminated to the extent practicable below releasable limits. Pharmacy Services of Peoria went on to state that he had contacted the hospital as well when the contamination was discovered that afternoon.
"The Duty Office then contacted, a technician of Proctor Hospital who indicated that a syringe of Tc-99m had partially vented which resulted in the contamination of her glove and the exterior of the retrieved pharmacy container. She stated that following notification from the pharmacy around 2 pm that afternoon, she had surveyed the hot lab for contamination and discovered loose radioactive contamination on the counter, the floor and the gloves she had been using at the time. She successfully decontaminated the floor and changed the counter absorbent covering. No other contamination had been found in the Department.
"On October 27, 2005 a Division representative called both individuals to follow-up and discuss reporting requirements. Pharmacy Services of Peoria advised that the courier had visited one other facility that afternoon following the collection of the briefcase containing empty lead containers at Proctor Hospital. Representatives from the pharmacy had called the second facility the previous afternoon to advise them of the potential for contamination. The second facility investigated and then reported back that their monitoring had revealed no contamination of the items dropped off. The pharmacy subsequently visited the site themselves later that same day to retrieve some empty containers and confirmed no contamination was present on any of the packages involved. He went on to report that the driver involved was monitored when he reported for work on the morning of the 27th and no additional removable contamination was discovered on his hands and as a further precaution the vehicle that had been used was set aside for the day and would not be driven.
"When the technician of Proctor Hospital was contacted she reported that she believed the contamination on the package resulted from a procedure where she was preparing a diagnostic tracer from a kit. Based on the initial amount involved and the subsequent diagnostic procedure she believed that no more than 0.5 milliCi of Tc-99m could have been involved. Circumstances in the hot lab and with available personnel lead to an uncommon situation where the package to be retrieved by the pharmacy courier was in the dose preparation area leading to its eventual contamination. Although routine procedure is to monitor all items removed from the radioactive work area of the hot lab, this was not performed on this occasion as it was unusual for the package to be in the dose preparation area. The licensee indicated that similar circumstances are very unlikely to be repeated so the potential for second occurrence is negligible."
State Report: IL050052 |
| Power Reactor | Event Number: 42099 | Facility: HADDAM NECK
Region: 1 State: CT
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: RALPH COX
HQ OPS Officer: BILL GOTT | Notification Date: 10/31/2005
Notification Time: 12:48 [ET]
Event Date: 10/31/2005
Event Time: 09:00 [EST]
Last Update Date: 10/31/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
CLIFFORD ANDERSON (R1)
MICHELE BURGESS (NMSS)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Decommissioned | 0 | Decommissioned | Event Text OFFSITE NOTIFICATION
Haddam Neck uncovered evidence of Spent Fuel Pool leakage below ground. The leakage was discovered when removing soil east of the Spent Fuel Building. Consequently, the site notified the Connecticut Department of Environmental Protection. The quantity of water leaked is unknown. Estimates based on historic Spent Fuel Pool evaporation data indicate that the leak was small - on the order of a few gallons per day. Based on readings from down-gradient monitoring wells, there is no travel beyond the property line.
The licensee notified the NRC Resident Inspector. |
| Other Nuclear Material | Event Number: 42100 | Rep Org: EPSILON PRODUCTS COMPANY
Licensee: EPSILON PRODUCTS COMPANY
Region: 1
City: MARCUS HOOK State: PA
County:
License #: 37-28586-01
Agreement: N
Docket:
NRC Notified By: WAYNE APPLEGATE
HQ OPS Officer: BILL GOTT | Notification Date: 10/31/2005
Notification Time: 15:34 [ET]
Event Date: 10/31/2005
Event Time: [EST]
Last Update Date: 10/31/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
CLIFFORD ANDERSON (R1)
MICHELE BERGESS (NMSS)
| Event Text DEFECTIVE GAUGE
The shutter of an OMART Level Gauge (Model SHD s/n66437 80 millicuries Cs-137) failed in the closed position. The manufacturer has been notified and will pick up the gauged for repairs. The gauge shutter failed in a safe position. |
| Power Reactor | Event Number: 42101 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: STEVE SMITH
HQ OPS Officer: BILL GOTT | Notification Date: 10/31/2005
Notification Time: 15:38 [ET]
Event Date: 10/31/2005
Event Time: 12:02 [MST]
Last Update Date: 10/31/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
THOMAS FARNHOLTZ (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text MEDIA INTEREST
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On October 31, 2005, at approximately 12:02 PM Mountain Standard Time (MST) the Palo Verde Nuclear Generating Station was informed of a request to conduct a media interview with a clearinghouse that provides newsworthy input to local media regarding an emergency preparedness exercise to commence tomorrow. No press release is planned by Palo Verde, but the interview is indication of media interest. The State of Arizona and Maricopa County will be performing an ingestion pathway emergency preparedness exercise on November 1, 2005 through November 3, 2005. The exercise will be evaluated by the Federal Emergency Management Agency (FEMA).
"Although this exercise will involve significant participation by State and County agencies, Palo Verde participation is expected to be limited to a small control cell of personnel to simulate communication with the State and County.
"There has been some media interest.
"There have been no official press releases posted by Maricopa County or the State of Arizona, although the Governor's calendar for November 1, 2005 indicates that the Honorable Janet Napolitano will participate.
"Resident NRC inspectors are not expected to participate in this exercise, but Palo Verde understands that two NRC Region IV personnel (Messrs. T. Andrews and W. Maier) are expected to support FEMA evaluation of the exercise.
"Palo Verde Unit 1 is in a refueling outage with all fuel assemblies offloaded to the spent fuel pool.
"Units 2 and 3 are operating in Mode 1 at approximately 100% power, at normal operating temperature and pressure."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42102 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [ ] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TODD BOHANAN
HQ OPS Officer: MIKE RIPLEY | Notification Date: 10/31/2005
Notification Time: 17:37 [ET]
Event Date: 10/31/2005
Event Time: 13:18 [CST]
Last Update Date: 10/31/2005 | 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):
STEPHEN CAHILL (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM DUE TO TRIP OF MAIN TURBINE
"At 1318 [CST] on 10/31/05 with Unit 3 at 100% power, a full reactor scram signal (RPS) was received due to a turbine trip. Unit 2 was also at 100% power and was unaffected by the event. Reactor water level lowered to approximately minus 6 inches as expected and was recovered with normal feedwater flow. All expected PCIS isolations, Group 2 (RHR Shutdown Cooling), Group 3 (RWCU), Group 6 (Ventilation), and Group 8 (TIP) were received along with the auto start of CREVs and 3 SBGT trains.
"This event is reportable as a 4-hour and 8-hour non-emergency notification along with a 60-day written report in accordance with 10 CFR 50.72(b)(2)(iv)(B), 10 CFR 50.72(b)(3)(iv)(A) and 10 CFR 50.73(a)(2)(iv)(A) as 'any event or condition that results in valid actuation of RPS or PCIS'."
The licensee stated that the turbine trip was most likely caused by bus transfer evolutions in the 500 kv switchyard. The licensee stated that all control rods fully inserted, the electrical grid is stable, the EDGs and ESF systems remain available, and that decay heat is being removed via the turbine bypass valves to the main condenser. The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42104 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: DAVID FUNK
HQ OPS Officer: MIKE RIPLEY | Notification Date: 10/31/2005
Notification Time: 23:02 [ET]
Event Date: 10/31/2005
Event Time: 22:27 [EST]
Last Update Date: 10/31/2005 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
STEPHEN CAHILL (R2)
TOM BLOUNT (IRD)
JOHN HANNON (NRR)
J. FROST (DHS)
L. BISCOE (FEMA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 4 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text UNUSUAL EVENT DECLARATION: LOSS OF OFFSITE POWER DUE TO LOSS OF STARTUP TRANSFORMER
"Unusual event category 10A on Unit 4. Loss of offsite power to Unit 4 due to loss of Unit 4 Startup Transformer. Auto AFW actuation. Auto starting and loading of both Unit 4 Emergency Diesel Generators."
The licensee stated that the plant is stable in Mode 3 at approximately 700 psi and 380 deg F. The plant was experiencing electrical grid instabilities at the time of the trip of the Startup Transformer. The exact cause of the transformer trip is being investigated. The grid instabilities were associated with the plant's Northwest Bus, therefore, Unit 3 is not affected and continues to operate at approximately 60% power.
The licensee notified the State of Florida and will notify the NRC Resident Inspector |
| Power Reactor | Event Number: 42105 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: POUL CHRISTIANSEN
HQ OPS Officer: BILL HUFFMAN | Notification Date: 11/01/2005
Notification Time: 02:14 [ET]
Event Date: 10/31/2005
Event Time: 22:23 [EST]
Last Update Date: 11/01/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
STEPHEN CAHILL (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text CONTAINMENT EVACUATION AND SMOKE INHALATION TREATMENT DUE TO SMALL FIRE
"On October 31, 2005, at 22:23 fire and smoke was reported in the Unit 1 Reactor Containment Building. Unit 1 is currently shut down for a refueling outage. Investigation into the cause of the fire continues. The fire appears to have been caused by slag from cutting/grinding work contacting a temporary ventilation hose. The containment evacuation alarm and fire alarm was sounded. The fire was reported extinguished at 22:25. The fire team and first aid team responded. First aid team reported several people were overcome by smoke inhalation. The Unit 1 control room called '911' to request ambulance and EMT assistance. Eight people have been transported to local hospitals for treatment of smoke inhalation. None of the people transported offsite were contaminated. 29 CFR 1904.8 requires notification of the Occupational Safety and Health Administration (OSHA) within eight hours of this event because it resulted in the hospitalization of three or more employees as a result of a work related incident. This NRC notification is being made in accordance with 10 CFR 50.72(b)(2)(xi) due to the notification of offsite governmental agencies via '911' as well as the OSHA notification."
Unit 2 is at 100% power and was not impacted by this event. The licensee notified the NRC Resident Inspector. | |