| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/30/2007 - 10/31/2007 ** EVENT NUMBERS ** |
 | Other Nuclear Material | Event Number: 42789 | Rep Org: SUPERIOR WELL SERVICES, INC.
Licensee: SUPERIOR WELL SERVICES, INC.
Region: 1
City: INDIANA State: PA
County:
License #: GL704677-7
Agreement: N
Docket:
NRC Notified By: JOHN SROCK
HQ OPS Officer: STEVE SANDIN | Notification Date: 08/20/2006
Notification Time: 18:30 [ET]
Event Date: 08/18/2006
Event Time: [EDT]
Last Update Date: 10/30/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
RAYMOND LORSON (R1)
BLAIR SPITZBERG (R4)
GARY JANOSKO (NMSS)
ILTAB (via email) ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text GENERAL LICENSE DENSITY GAUGE DISCOVERED MISSING
On 8/18/06 the Superior Well Services crew at a temporary worksite approximately 2 hours drive from Vernal, UT discovered that their Thermo MeasureTech Density Gauge was missing. The device, a Model #5192 - S/N B7000 containing a 200 mCi Cs-137 source, is normally stored in the back of their vehicle and was last used the day before on 8/17/06. The licensee is continuing their investigation to determine whether the device was stolen or fell off the back of the vehicle. The device itself weighs 150 pounds and is in a metal housing 36 inches in length (Sealed Source Registry No. TX0634D105B).
The licensee contacted the Utah Highway Patrol, the Vernal County Sheriff's Office and will contact the Utah Radiation Control Office. Also, a press release offering a $10,000.00 reward for return of the device will be issued.
* * * UPDATE FROM CRAIG JONES TO J. KNOKE AT 12:06 ON 10/30/07 * * *
Craig Jones from the state of Utah called to say that on 10/19/07 a member of the public located the Thermo MeasureTech Density Gauge South of Duchesne, UT along State Road 191. The licensee's RSO was notified and responded to the site. A leak test and survey was performed on the equipment and area, and the results were negative. The licensee indicated the person who found the gauge will be given the reward. Licensee now has the Thermo MeasureTech Density Gauge in their possession. The state of Utah will be conducting a follow-up meeting with the licensee in the near future.
Notified R1DO (Dentel), R4DO (Powers), FSME (M. Burgess), ILTAB (email)
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. |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 43633 | Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: TIM BUNKELMAN
HQ OPS Officer: JASON KOZAL | Notification Date: 09/11/2007
Notification Time: 20:33 [ET]
Event Date: 09/11/2007
Event Time: 14:39 [CDT]
Last Update Date: 10/30/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
SONIA BURGESS (R3)
|
| 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 AUXILIARY BUILDING SPECIAL VENTILATION AND SHIELD BUILDING VENTILATION SYSTEMS INOPERABLE
"At 1439 the Control Room received a Condition Report that identified an unanalyzed condition associated with the Auxiliary Building Special Ventilation and Shield Building Ventilation Systems which resulted in declaring this equipment inoperable. The issue was recirculation flow from Auxiliary Building Special Ventilation back to the Auxiliary Building added additional area heat gain resulting in exceeding the design capacity for the area fan coil units. Technical Specification LCO was entered per TS 3.6.c requiring a reactor shutdown within 12 hours. At 1654 Engineering provided information that if the control switch for Auxiliary Building Special Ventilation Train A was maintained in the off position, the area heat load was within the capacity of area fan coil units. This was completed and both trains of Shield Building Ventilation and Auxiliary Building Special Ventilation Train B was returned to operable. Technical Specification requirements to shutdown were exited. The plant remains in a 7 day Action Statement per TS 3.6.c with Auxiliary Building Special Ventilation Train A inoperable.
"This event is reportable under 10CFR50.72(b)(3)(v)(C), 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.' "
The licensee notified the NRC Resident Inspector.
* * * RETRACTION PROVIDED BY TIM BUNKELMAN TO JASON KOZAL AT 1657 ON 10/30/07 * * *
"On September 11, 2007 Kewaunee Power Station reported an unanalyzed condition associated with the Auxiliary Building Special Ventilation and Shield Building Ventilation Systems, which resulted in declaring the equipment inoperable. The issue involved recirculation flow from the Auxiliary Building Special Ventilation System back into the Auxiliary Building causing additional area heat gain resulting in exceeding the design capacity for the area fan coil units.
"A subsequent engineering review concluded that required equipment in the Auxiliary Building Fan Floor area would have remained functional during a design basis accident provided service water temperature does not exceed 78.14 degrees Fahrenheit. A review of service water temperatures over the past three years did not identify any occurrences exceeding this value. Therefore, the safety function of the systems would have been met. Based on the analysis performed, Event Notification EN# 43633 is hereby retracted.
"The Auxiliary Building Special Ventilation and Shield Building Ventilation Systems remain in a non-conforming condition because the maximum service water design temperature is 80 degrees Fahrenheit. Service water temperature is being administratively limited to 71 degrees Fahrenheit pending final corrective action.
"The licensee has notified the Point Beach NRC Senior Resident Inspector."
Notified R3DO (Madera). |
| Power Reactor | Event Number: 43678 | Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 10/01/2007
Notification Time: 14:17 [ET]
Event Date: 10/01/2007
Event Time: 13:15 [CDT]
Last Update Date: 10/30/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
REBECCA NEASE (R4)
TOM KARDARAS (NSIR)
|
| 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 REPLACING THE EMERGENCY RESPONSE FACILITY COMPUTER SYSTEM
"The Plant Process computer system (Emergency Response Facility Computer System) will be taken out of service for approximate 3 week period starting October 1, 2007, to implement a planned modification. The current ERFCS is being replaced and a computer outage is required for the installation of the new ERFCS. During this time period Emergency Response Data System (ERDS) and Safety Parameter Display System (SPDS) functions will not be available. However, the Qualified Safety Parameter Display System (QSPDS) will still be operable in the Control Room. This notification is being made to inform the NRC that the ERDS will be unavailable until this modification is complete. The operation of the plant systems will not be affected due to this planned action. ERDS and SPDS parameters will be monitored by control board indications. All contingency actions required by ERFCS-3, ERFCS Maintenance Outage Plant Mode 1, have been taken. Meteorological data to support the Emergency Response Organization (ERO) will be obtained from the local national weather service (if needed) as described in our Radiological Response Plan. A follow up notification, to the NRC will be given once ERDS and SPDS are returned to service. The NRC Resident Inspector has been informed."
* * * UPDATE FROM KEVIN BOSTON TO J. KNOKE AT 1820 ON 10/30/07 * * *
The licensee completed planned modifications and fully restored the Plant Process computer system (Emergency Response Facility Computer System).
The licensee notified the NRC Resident Inspector. Notified R4DO (Powers) , T. Kardaras (email). |
| General Information or Other | Event Number: 43745 | Rep Org: OK DEQ RAD MANAGEMENT
Licensee: KLEINFELDER CENTRAL, INC
Region: 4
City: TULSA State: OK
County:
License #: OK-27597-02
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: JOHN KNOKE | Notification Date: 10/25/2007
Notification Time: 11:20 [ET]
Event Date: 10/25/2007
Event Time: 10:00 [CDT]
Last Update Date: 10/25/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHUCK CAIN (R4)
GREG MORELL (FSME)
ILTAB EMAIL ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN SOIL DENSITY GAUGE
State called indicating licensee reported a Humboldt soil density gauge, Model 5001B (s/n 2978) was stolen from the back of an employee's pickup truck sometime during the night of 10/24/07. The gauge was chained down (but was cut) while parked at the employee's personal residence. The source activity is 44 mCi of Am-241/Be and 11 mCi of Cs-137. A police report was filed with the Tulsa police department, Report # 2007-074-103.
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. |
| General Information or Other | Event Number: 43751 | Rep Org: KANSAS DEPT OF HEALTH & ENVIRONMENT
Licensee: TULSA GAMMA RAY
Region: 4
City: TULSA State: OK
County:
License #: 2007-013
Agreement: Y
Docket:
NRC Notified By: JAMES HARRIS
HQ OPS Officer: STEVE SANDIN | Notification Date: 10/26/2007
Notification Time: 16:37 [ET]
Event Date: 10/23/2007
Event Time: [CDT]
Last Update Date: 10/26/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHUCK CAIN (R4)
LAWRENCE KOKAJKO (FSME)
| Event Text AGREEMENT STATE REPORT INVOLVING AN IMPROPERLY CONNECTED CAMERA SOURCE
The following information was received via fax:
"Tulsa Gamma Ray was doing some radiography work at the Coffeyville refinery and had a source hang-up on October 23. The Tulsa Gamma Ray RSO was called. He came up from Tulsa and was able to return the source to the shield after about 10 minutes using a rod to push the source.
"Tulsa Gamma Ray RSO performed an investigation and discovered the radiographer did not properly attach the drive cable to the source assembly. The source was able to be pushed out but did not allow the source to be retracted. The equipment did not fail. The event occurred [due] to human error.
"The personnel were instructed to properly connect the drive cable to the source assembly and verify the connection by attempting to pull the connection apart. The personnel have been given additional radiation safety training."
The camera is an Amersham Model 880B (S/N 1568) containing a 73 Curie Ir-192 source. The RSO received a dose of approximately 150 mrem while reattaching the source. Tulsa Gamma Ray is an Oklahoma licensee (License No. OK-17178-02) performing work in Kansas under reciprocity permit No. 2007-013. The Coffeyville Refinery is located in Coffeyville, KS.
Kansas Reference No.: KS070009 |
| Power Reactor | Event Number: 43757 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JAMES PRIEST
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 10/30/2007
Notification Time: 01:44 [ET]
Event Date: 10/29/2007
Event Time: 19:30 [EDT]
Last Update Date: 10/30/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
GLENN DENTEL (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text LOSS OF POWER TO TECHNICAL SUPPORT CENTER (TSC)
"On 10/29/07 at 1930 hours, it was determined that the Hope Creek TSC has been unavailable for greater than 8 hours as a result of a scheduled electrical bus outage. Although SPDS, the radiation monitoring system, and communications capabilities remain unaffected, and adequate contingency measures are in place to utilize the Salem Generating Station TSC if required, the loss of normal lighting, computers, CRIDS [Control Room Integrated Display System] and dose assessment capabilities have impaired the effective and efficient use of the Hope Creek TSC. A causal investigation to determine why the impact of the electrical bus outage was not pre-identified has been directed. The plant is currently stable in Operational Condition 5. This report is being made pursuant to 10CFR50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector and the Lower Alloways Creek Township government. |
| Power Reactor | Event Number: 43759 | Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: JAMES BOYLE
HQ OPS Officer: JOHN KNOKE | Notification Date: 10/30/2007
Notification Time: 17:36 [ET]
Event Date: 10/30/2007
Event Time: 13:42 [CDT]
Last Update Date: 10/30/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
DALE POWERS (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 75 | Power Operation | 75 | Power Operation | Event Text INADVERTENT ACTIVATION OF OFFSITE EMERGENCY SIRENS
"River Bend Station is making a 4 hour report in accordance with 10 CFR 50.72 (b)(2)(xi) of an event that occurred at approximately 1342 hours on October 30, 2007 when the offsite emergency sirens for River Bend located in West Feliciana Parish were inadvertently activated. The siren activation was not related to any condition or event at River Bend. The sirens sounded for approximately 1 minute. River Bend has notified West Feliciana Parish and the Governors Office of Homeland Security and Emergency Preparedness of the inadvertent siren activation.
"The site NRC resident inspector's office has been informed of the inadvertent activation and that a 4 hour notification is being made.
"The cause of the inadvertent activation is not precisely known at this time, but occurred in conjunction with vendor testing of a new siren control system. This activation of the sirens has been entered into the site corrective action program to determine the cause and the actions necessary to prevent recurrence.
"There was no impact on River Bend due to the activation of the offsite sirens located in West Feliciana Parish, Louisiana. The River Bend alert and notification system remained operable for the duration of the event.
"The Governors Office of Homeland Security and Emergency Preparedness is making notification to the public of the inadvertent siren activation using the emergency alert system. A press release from Entergy is not planned at this time." |
| Power Reactor | Event Number: 43760 | Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: JAMES PAULES
HQ OPS Officer: PETE SNYDER | Notification Date: 10/30/2007
Notification Time: 23:57 [ET]
Event Date: 10/30/2007
Event Time: 23:30 [EDT]
Last Update Date: 10/31/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
GLENN DENTEL (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling Shutdown | 0 | Refueling Shutdown | Event Text OUTAGE OF SAFETY PARAMETER DISPLAY SYSTEM (SPDS) AND EMERGENCY RESPONSE DATA
SYSTEM (ERDS)
"At 2330 hours, on 10/30/2007, the SPDS and ERDS system was removed from service to support activities from a planned maintenance outage on the 'C' vital bus power supply. The duration of work is expected to be approximately 12 hours. (Scheduled for completion at 11:30 hours on 10/31/2007). During this time, Control Room indications and alternate methods will be available.
"Since the SPDS computer system will be unavailable for greater than 8 hours, this is considered a Loss of Emergency Assessment Capability and reportable under 10CFR50.72(b)(3)(xiii)."
The licensee will notify the NRC Resident Inspector. Notified R1DO (Dental). | |