Event Notification Report for April 29, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/28/2010 - 04/29/2010
EVENT NUMBERS
458844588045881458824590845911
Fuel Cycle Facility
Event Number: 45884
Facility: WESTINGHOUSE ELECTRIC CORPORATION
Region: 2 State: SC
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
NRC Notified By: GERARD COUTURE
HQ OPS Officer: PETE SNYDER
Region: 2 State: SC
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
NRC Notified By: GERARD COUTURE
HQ OPS Officer: PETE SNYDER
Notification Date: 04/30/2010
Notification Time: 12:34 [ET]
Event Date: 04/29/2010
Event Time: 13:04 [EDT]
Last Update Date: 04/30/2010
Notification Time: 12:34 [ET]
Event Date: 04/29/2010
Event Time: 13:04 [EDT]
Last Update Date: 04/30/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(2) - LOSS OR DEGRADED SAFETY ITEMS
10 CFR Section:
PART 70 APP A (b)(2) - LOSS OR DEGRADED SAFETY ITEMS
Person (Organization):
GERALD MCCOY (R2DO)
MARISSA BAILEY (NMSS)
GERALD MCCOY (R2DO)
MARISSA BAILEY (NMSS)
HOT OIL SYSTEM EMERGENCY SHUTDOWN FAILS ANNUAL PREVENTATIVE MAINTENANCE CHECK
"It was reported to EH&S Management that on April 29, 2010, the annual preventative maintenance functional check on the hot oil system emergency shutdown system failed. This function is an Item Relied On For Safety (IROFS) and is identified in the Integrated Safety Analysis (ISA) Summary for the conversion area of the Columbia Fuel Fabrication Facility. This IROFS designation is ADUHOS-407 and this IROFS is a control applied to a fire related sequence. Information pertaining to the accident sequence can be found in the January 2010, ISA Summary 03 page 78. There were no actual fire incidents; there were no hazardous materials or special nuclear materials released.
"Current plant status: This functional test requires the conversion lines and associated hot oil dryer be shut down. The conversion lines which utilize the hot oil system protected by this function were in normal shutdown at the time of the functional check was performed. The Columbia Fuel Fabrication Facility is currently shutdown for performance of the annual inventory and associated maintenance outage.
"This notification is made base on 10 CFR 70 Appendix A (b)(2) 'Loss or degradation of items relied on for safety that results in failure to meet the performance requirements of 10 CFR 70.61.' The performance requirements for this accident sequence require the Overall Likelihood Index (OLI) be a -4, which corresponds to Highly Unlikely. With this control failure the sequence OLI is -3 which corresponds to Unlikely.
"Corrective Actions: The corresponding conversion lines and associated hot oil dryer systems are currently in a normal shutdown mode, and will remain so until appropriated troubleshooting and repairs are conducted and the IROFS is restored to an operable status."
"It was reported to EH&S Management that on April 29, 2010, the annual preventative maintenance functional check on the hot oil system emergency shutdown system failed. This function is an Item Relied On For Safety (IROFS) and is identified in the Integrated Safety Analysis (ISA) Summary for the conversion area of the Columbia Fuel Fabrication Facility. This IROFS designation is ADUHOS-407 and this IROFS is a control applied to a fire related sequence. Information pertaining to the accident sequence can be found in the January 2010, ISA Summary 03 page 78. There were no actual fire incidents; there were no hazardous materials or special nuclear materials released.
"Current plant status: This functional test requires the conversion lines and associated hot oil dryer be shut down. The conversion lines which utilize the hot oil system protected by this function were in normal shutdown at the time of the functional check was performed. The Columbia Fuel Fabrication Facility is currently shutdown for performance of the annual inventory and associated maintenance outage.
"This notification is made base on 10 CFR 70 Appendix A (b)(2) 'Loss or degradation of items relied on for safety that results in failure to meet the performance requirements of 10 CFR 70.61.' The performance requirements for this accident sequence require the Overall Likelihood Index (OLI) be a -4, which corresponds to Highly Unlikely. With this control failure the sequence OLI is -3 which corresponds to Unlikely.
"Corrective Actions: The corresponding conversion lines and associated hot oil dryer systems are currently in a normal shutdown mode, and will remain so until appropriated troubleshooting and repairs are conducted and the IROFS is restored to an operable status."
Power Reactor
Event Number: 45880
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DOUGLAS SHORTER
HQ OPS Officer: DONG HWA PARK
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DOUGLAS SHORTER
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/29/2010
Notification Time: 08:31 [ET]
Event Date: 04/29/2010
Event Time: 08:30 [EDT]
Last Update Date: 04/29/2010
Notification Time: 08:31 [ET]
Event Date: 04/29/2010
Event Time: 08:30 [EDT]
Last Update Date: 04/29/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
DAVID HILLS (R3DO)
DAVID HILLS (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 |
PLANT INTEGRATED COMPUTER SYSTEM OUTAGE DUE TO SCHEDULED MAINTENANCE
"Beginning at approximately 0830 hours EDT on April 29, 2010, Perry Plant personnel will be taking the plant Integrated Computer System (ICS) out of service for planned maintenance. During the time ICS is out of service, the Safety Parameter Display System (SPDS), the Emergency Response Data System (ERDS), and the automatic mode calculation of the Computer Aided Dose Assessment Program (CADAP) will be unavailable. The computer outage is scheduled for six hours.
"In the event of an emergency, plant parameter data will be orally transmitted to the facilities through the Status Board Ring Down circuit with back-up by the Private Branch Exchange, Off-Premise Exchange, and various redundant intra-facility circuits throughout the emergency facilities. The dose assessment function will be maintained during the out of service time period by manual input of data into CADAP and, if required, by manual calculation. The ability to open and maintain an 'open line' using the Emergency Notification System will not be affected and will be the primary means of transferring plant data to the NRC as a contingency until the ERDS can be returned to service during the period of unavailability.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(xiii), as a condition that results in a major loss of offsite communications capability. A follow-up notification will be made when the maintenance activities are completed and the equipment is restored."
The NRC Resident Inspector has been notified.
* * * UPDATE AT 1036 EDT ON 04/29/10 FROM DOUGLAS SHORTER TO CHARLES TEAL * * *
The plant ICS has been returned to service and the system is functioning normally. The NRC Resident Inspector has been notified.
Notified R3DO (Hills).
"Beginning at approximately 0830 hours EDT on April 29, 2010, Perry Plant personnel will be taking the plant Integrated Computer System (ICS) out of service for planned maintenance. During the time ICS is out of service, the Safety Parameter Display System (SPDS), the Emergency Response Data System (ERDS), and the automatic mode calculation of the Computer Aided Dose Assessment Program (CADAP) will be unavailable. The computer outage is scheduled for six hours.
"In the event of an emergency, plant parameter data will be orally transmitted to the facilities through the Status Board Ring Down circuit with back-up by the Private Branch Exchange, Off-Premise Exchange, and various redundant intra-facility circuits throughout the emergency facilities. The dose assessment function will be maintained during the out of service time period by manual input of data into CADAP and, if required, by manual calculation. The ability to open and maintain an 'open line' using the Emergency Notification System will not be affected and will be the primary means of transferring plant data to the NRC as a contingency until the ERDS can be returned to service during the period of unavailability.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(xiii), as a condition that results in a major loss of offsite communications capability. A follow-up notification will be made when the maintenance activities are completed and the equipment is restored."
The NRC Resident Inspector has been notified.
* * * UPDATE AT 1036 EDT ON 04/29/10 FROM DOUGLAS SHORTER TO CHARLES TEAL * * *
The plant ICS has been returned to service and the system is functioning normally. The NRC Resident Inspector has been notified.
Notified R3DO (Hills).
General Information or Other
Event Number: 45881
Rep Org: NV DIV OF RAD HEALTH
Licensee: ROBINSON NEVADA MINING COMPANY
Region: 4
City: RUTH State: NV
County:
License #:
Agreement: Y
Docket:
NRC Notified By: SNEHA RAVIKUMAR
HQ OPS Officer: PETE SNYDER
Licensee: ROBINSON NEVADA MINING COMPANY
Region: 4
City: RUTH State: NV
County:
License #:
Agreement: Y
Docket:
NRC Notified By: SNEHA RAVIKUMAR
HQ OPS Officer: PETE SNYDER
Notification Date: 04/29/2010
Notification Time: 16:31 [ET]
Event Date: 04/29/2010
Event Time: 07:45 [PDT]
Last Update Date: 04/29/2010
Notification Time: 16:31 [ET]
Event Date: 04/29/2010
Event Time: 07:45 [PDT]
Last Update Date: 04/29/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JEFF CLARK (R4DO)
JAMES DANNA (FSME)
JEFF CLARK (R4DO)
JAMES DANNA (FSME)
AGREEMENT STATE REPORT - SHUTTER ON GAUGES FAILS TO FUNCTION
The following was received via email:
"While doing the shutter checks it was discovered that the shutters were inoperable on the following fixed gauges:
"Serial #1015GK, Cs-137, 50 mCi, Source holder SR-A, at the Pump House North Train;
"Serial #1017GK, Cs-137, 50 mCi, Source holder SR-A, at the Pump House Center Train.
"Density gauges are installed on the piping going to the tails impoundment. The pipes are in the pump house and are not readily accessible. [An] Ohmart representative will be there on 5/5/10 for the necessary repairs.
"All personnel have been briefed about the safety implications. The area has been cordoned off. No concerns of exposure to anyone. This is an ongoing investigation."
The following was received via email:
"While doing the shutter checks it was discovered that the shutters were inoperable on the following fixed gauges:
"Serial #1015GK, Cs-137, 50 mCi, Source holder SR-A, at the Pump House North Train;
"Serial #1017GK, Cs-137, 50 mCi, Source holder SR-A, at the Pump House Center Train.
"Density gauges are installed on the piping going to the tails impoundment. The pipes are in the pump house and are not readily accessible. [An] Ohmart representative will be there on 5/5/10 for the necessary repairs.
"All personnel have been briefed about the safety implications. The area has been cordoned off. No concerns of exposure to anyone. This is an ongoing investigation."
Power Reactor
Event Number: 45882
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: ARNIE CRIBB
HQ OPS Officer: JOHN KNOKE
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: ARNIE CRIBB
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/29/2010
Notification Time: 20:30 [ET]
Event Date: 04/29/2010
Event Time: 18:30 [EDT]
Last Update Date: 04/29/2010
Notification Time: 20:30 [ET]
Event Date: 04/29/2010
Event Time: 18:30 [EDT]
Last Update Date: 04/29/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
GERALD MCCOY (R2DO)
GERALD MCCOY (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 |
IDENTIFIED WIRING DISCREPANCY IN "B" EDG
"While performing a walkdown of the 'B' emergency diesel generator remote shutdown circuitry, a wiring discrepancy was identified that could have disabled the Appendix R function of the circuitry. The wiring discrepancy could have prevented complete isolation of the 'B' emergency diesel generator breaker closure circuitry from a postulated fire in the Control Building.
"This configuration causes the Appendix R function of the 'B' emergency diesel generator to be inoperable.
"A roving firewatch has been established and a 7 day action statement has been entered in accordance with the applicable fire protection procedure. Corrective actions are being evaluated to resolve this issue."
The licensee has notified the NRC Resident Inspector.
"While performing a walkdown of the 'B' emergency diesel generator remote shutdown circuitry, a wiring discrepancy was identified that could have disabled the Appendix R function of the circuitry. The wiring discrepancy could have prevented complete isolation of the 'B' emergency diesel generator breaker closure circuitry from a postulated fire in the Control Building.
"This configuration causes the Appendix R function of the 'B' emergency diesel generator to be inoperable.
"A roving firewatch has been established and a 7 day action statement has been entered in accordance with the applicable fire protection procedure. Corrective actions are being evaluated to resolve this issue."
The licensee has notified the NRC Resident Inspector.
General Information or Other
Event Number: 45908
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: CHEVRON USA PRODUCTS COMPANY
Region: 4
City: RICHMOND State: CA
County:
License #:
Agreement: Y
Docket: 0490-07
NRC Notified By: KENT PRENDERGAST
HQ OPS Officer: CHARLES TEAL
Licensee: CHEVRON USA PRODUCTS COMPANY
Region: 4
City: RICHMOND State: CA
County:
License #:
Agreement: Y
Docket: 0490-07
NRC Notified By: KENT PRENDERGAST
HQ OPS Officer: CHARLES TEAL
Notification Date: 05/07/2010
Notification Time: 02:39 [ET]
Event Date: 04/29/2010
Event Time: 00:00 [PDT]
Last Update Date: 05/07/2010
Notification Time: 02:39 [ET]
Event Date: 04/29/2010
Event Time: 00:00 [PDT]
Last Update Date: 05/07/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
ANGELA MCINTOSH (FSME)
MEXICO VIA FAX
THOMAS FARNHOLTZ (R4DO)
ANGELA MCINTOSH (FSME)
MEXICO VIA FAX
AGREEMENT STATE REPORT - POSSIBLE LOST X-RAY ANALYZER
The following was received from the State of California via email:
On May 5, 2010 the California Radiologic Health Branch (RHB) was informed by the alternate Radiation Safety Officer (RSO) of Chevron USA that they may have lost a Niton, XLP 818, S/N 13354, containing a 30 mCi Am241/Be sealed source.
According to the alternate RSO, the Niton XLP was lost and was reported to him by the Material Inspection Group supervisor on April 29, 2010. This incident was not reported to RHB because the licensee was looking for the Niton XLP until the date of this report.
CA Report #: 050610
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
The following was received from the State of California via email:
On May 5, 2010 the California Radiologic Health Branch (RHB) was informed by the alternate Radiation Safety Officer (RSO) of Chevron USA that they may have lost a Niton, XLP 818, S/N 13354, containing a 30 mCi Am241/Be sealed source.
According to the alternate RSO, the Niton XLP was lost and was reported to him by the Material Inspection Group supervisor on April 29, 2010. This incident was not reported to RHB because the licensee was looking for the Niton XLP until the date of this report.
CA Report #: 050610
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: 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
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: 00:00 [MDT]
Last Update Date: 05/07/2010
Notification Time: 15:49 [ET]
Event Date: 04/29/2010
Event Time: 00:00 [MDT]
Last Update Date: 05/07/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
GREG SUBER (FSME)
THOMAS FARNHOLTZ (R4DO)
GREG SUBER (FSME)
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.
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.