Event Notification Report for January 27, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/26/2010 - 01/27/2010
EVENT NUMBERS
45667456644566545666
Other Nuclear Material
Event Number: 45667
Rep Org: US ARMY
Licensee: US ARMY
Region: 3
City: WARREN State: MI
County:
License #: 21-01222-05
Agreement: N
Docket:
NRC Notified By: KAREN McGUIRE
HQ OPS Officer: STEVE SANDIN
Licensee: US ARMY
Region: 3
City: WARREN State: MI
County:
License #: 21-01222-05
Agreement: N
Docket:
NRC Notified By: KAREN McGUIRE
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/28/2010
Notification Time: 15:20 [ET]
Event Date: 01/27/2010
Event Time: 00:00 [EST]
Last Update Date: 01/28/2010
Notification Time: 15:20 [ET]
Event Date: 01/27/2010
Event Time: 00:00 [EST]
Last Update Date: 01/28/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
CHRISTINE LIPA (R3DO)
MARK THAGGARD (FSME)
CHRISTINE LIPA (R3DO)
MARK THAGGARD (FSME)
MOSITURE DENSITY GAUGE RECEIVED WITH INOPERABLE LOCKING MECHANISM
The Army Depot in Stockton, CA received at 1401 PST on 01/27/10 a CPN Moisture Density Gauge shipped from a field unit. Upon receipt inspection, they identified that the locking mechanism was separated from the guide tube. The source was in the shielded position at the time of discovery. The field unit which shipped the device on 01/26/10 was contacted and asserts that the unit was intact at the time of shipment. The device is a CPN, Model MC-1, S/N M1712089, manufactured in the 1970's containing two sources; 10 millicuries Cesium-137 and 50 millicuries Americium-241/Be. The damaged device is currently in secure storage and scheduled for disposal.
The Army Depot in Stockton, CA received at 1401 PST on 01/27/10 a CPN Moisture Density Gauge shipped from a field unit. Upon receipt inspection, they identified that the locking mechanism was separated from the guide tube. The source was in the shielded position at the time of discovery. The field unit which shipped the device on 01/26/10 was contacted and asserts that the unit was intact at the time of shipment. The device is a CPN, Model MC-1, S/N M1712089, manufactured in the 1970's containing two sources; 10 millicuries Cesium-137 and 50 millicuries Americium-241/Be. The damaged device is currently in secure storage and scheduled for disposal.
Power Reactor
Event Number: 45664
Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: THOMAS WAECHTER
HQ OPS Officer: DONG HWA PARK
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: THOMAS WAECHTER
HQ OPS Officer: DONG HWA PARK
Notification Date: 01/27/2010
Notification Time: 07:39 [ET]
Event Date: 01/27/2010
Event Time: 07:30 [EST]
Last Update Date: 01/27/2010
Notification Time: 07:39 [ET]
Event Date: 01/27/2010
Event Time: 07:30 [EST]
Last Update Date: 01/27/2010
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):
SAM HANSELL (R1DO)
SAM HANSELL (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 |
ELECTRICAL POWER TEMPORARILY REMOVED FROM THE EMERGENCY OPERATIONS FACILITY FOR MAINTENANCE
"This is an eight hour report per 10 CFR 50.72(b)(3)(viii). Seabrook Station will be implementing a modification to improve reliability of the electrical system serving the Emergency Operations Facility (EOF). Specifically, the existing manual transfer switch between the backup power diesel generator and the EOF building will be replaced with an automatic transfer switch.
"This work will require that the main power feed to the EOF building be removed for a period of approximately 3 hours today. During this time, a secondary power feed will remain in service which can supply some building loads. A second 3-hour period of 'partial power' may be necessary to complete the job; it is currently anticipated that this second 'partial power' period, if needed, will occur tomorrow, January 28.
"Power to all EOF loads will be available in between the two 3-hour periods discussed above. In addition, should an emergency be declared during one of the 3-hour periods, full power to the facility can be restored within approximately 2 hours. As a compensatory measure, the TSC will perform the key planning standard functions assigned to the EOF during the two 'partial power' time periods should the EOF be unable to do so; this includes offsite dose projections, development of protective action recommendations and offsite notifications. Emergency plan implementing procedures for the TSC contain the instructions necessary for TSC responders to perform functions.
"During the 2-day period that this work is being performed, there will be no backup power source for the EOF.
"All work associated with this switch upgrade will be performed in an expeditious manner consistent with the goal of minimizing EOF unavailability.
"All EOF responders have been briefed on this work and expected contingent actions.
"This job will start at approximately 0730 am this morning. We anticipate that all work will be completed by sometime tomorrow afternoon. We will provide a notification update upon completion of the job."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM MIKE TAYLOR TO JOE O'HARA AT 1738 ON 01/27/10 * * *
"Seabrook station has completed the installation of the automatic transfer switch at the Emergency Operations Facility (EOF). There is no planned work affecting EOF availability."
Notified R1DO(Hansell).
"This is an eight hour report per 10 CFR 50.72(b)(3)(viii). Seabrook Station will be implementing a modification to improve reliability of the electrical system serving the Emergency Operations Facility (EOF). Specifically, the existing manual transfer switch between the backup power diesel generator and the EOF building will be replaced with an automatic transfer switch.
"This work will require that the main power feed to the EOF building be removed for a period of approximately 3 hours today. During this time, a secondary power feed will remain in service which can supply some building loads. A second 3-hour period of 'partial power' may be necessary to complete the job; it is currently anticipated that this second 'partial power' period, if needed, will occur tomorrow, January 28.
"Power to all EOF loads will be available in between the two 3-hour periods discussed above. In addition, should an emergency be declared during one of the 3-hour periods, full power to the facility can be restored within approximately 2 hours. As a compensatory measure, the TSC will perform the key planning standard functions assigned to the EOF during the two 'partial power' time periods should the EOF be unable to do so; this includes offsite dose projections, development of protective action recommendations and offsite notifications. Emergency plan implementing procedures for the TSC contain the instructions necessary for TSC responders to perform functions.
"During the 2-day period that this work is being performed, there will be no backup power source for the EOF.
"All work associated with this switch upgrade will be performed in an expeditious manner consistent with the goal of minimizing EOF unavailability.
"All EOF responders have been briefed on this work and expected contingent actions.
"This job will start at approximately 0730 am this morning. We anticipate that all work will be completed by sometime tomorrow afternoon. We will provide a notification update upon completion of the job."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM MIKE TAYLOR TO JOE O'HARA AT 1738 ON 01/27/10 * * *
"Seabrook station has completed the installation of the automatic transfer switch at the Emergency Operations Facility (EOF). There is no planned work affecting EOF availability."
Notified R1DO(Hansell).
General Information or Other
Event Number: 45665
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: JEWISH HOSPITAL OF CINCINNATI
Region: 3
City: CINCINNATI State: OH
County:
License #: 02120310029
Agreement: Y
Docket:
NRC Notified By: MICHAEL SNEE
HQ OPS Officer: JOE O'HARA
Licensee: JEWISH HOSPITAL OF CINCINNATI
Region: 3
City: CINCINNATI State: OH
County:
License #: 02120310029
Agreement: Y
Docket:
NRC Notified By: MICHAEL SNEE
HQ OPS Officer: JOE O'HARA
Notification Date: 01/27/2010
Notification Time: 15:39 [ET]
Event Date: 01/27/2010
Event Time: 00:00 [EST]
Last Update Date: 01/27/2010
Notification Time: 15:39 [ET]
Event Date: 01/27/2010
Event Time: 00:00 [EST]
Last Update Date: 01/27/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
CHRISTINE LIPA (R3DO)
MARK THAGGARD (FSME)
CHRISTINE LIPA (R3DO)
MARK THAGGARD (FSME)
AGREEMENT STATE REPORT - POTENTIAL MEDICAL EVENT INVOLVING A BRACHYTHERAPY UNDERDOSE EVENT
The following was received via e-mail:
"The BRP [Bureau of Radiation Protection] was informed on January 26, 2010 of a medical event that occurred at The Jewish Hospital of Cincinnati on December 28, 2009. A patient received a prostate I-125 seed implant on December 28, 2009. The post implant CT showed no problems but a follow-up CT performed on January 26, 2010 showed that the patient only received 75% of the prescribed dose to the prostate."
The intended dose was 144 Gy (14400 rad) and the actual received dose was 108 Gy (10800 rad). I-125 activity was 0.032 Ci per seed. The total dose delivered differs from the prescribed dose by twenty five percent. The state is investigating the matter.
Item Number: OH100002
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.
The following was received via e-mail:
"The BRP [Bureau of Radiation Protection] was informed on January 26, 2010 of a medical event that occurred at The Jewish Hospital of Cincinnati on December 28, 2009. A patient received a prostate I-125 seed implant on December 28, 2009. The post implant CT showed no problems but a follow-up CT performed on January 26, 2010 showed that the patient only received 75% of the prescribed dose to the prostate."
The intended dose was 144 Gy (14400 rad) and the actual received dose was 108 Gy (10800 rad). I-125 activity was 0.032 Ci per seed. The total dose delivered differs from the prescribed dose by twenty five percent. The state is investigating the matter.
Item Number: OH100002
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: 45666
Rep Org: SULZER PUMPS INC
Licensee: SULZER PUMPS INC
Region: 1
City: CHATTANOOGA State: TN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TOMMY CRAIG
HQ OPS Officer: JOE O'HARA
Licensee: SULZER PUMPS INC
Region: 1
City: CHATTANOOGA State: TN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TOMMY CRAIG
HQ OPS Officer: JOE O'HARA
Notification Date: 01/27/2010
Notification Time: 16:28 [ET]
Event Date: 01/27/2010
Event Time: 00:00 [EST]
Last Update Date: 01/27/2010
Notification Time: 16:28 [ET]
Event Date: 01/27/2010
Event Time: 00:00 [EST]
Last Update Date: 01/27/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
MALCOLM WIDMANN (R2DO)
S. PANNIER (EMAIL) (NRR)
J. THORP (EMAIL) (NRR)
O. TABATABAI (EMAIL) (NRO)
MALCOLM WIDMANN (R2DO)
S. PANNIER (EMAIL) (NRR)
J. THORP (EMAIL) (NRR)
O. TABATABAI (EMAIL) (NRO)
DEFECT IN PUMP SHAFT JOURNAL COATING CAUSED SERVICE WATER PUMP (2E) FAILURE AT FARLEY NUCLEAR STATION
The following was received via fax:
"1. Name and address of the individual or individuals informing the Commission:
Response: General Manager, Nuclear Services 4126 Caine Lane Chattanooga, TN 37421
"2. Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains defect:
Response: Facility: Farley Nuclear Plant; Basic Component: Unit 2 Service Water Pump (2E)
"3. Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect:
Response: Sulzer Pumps (US) Inc, Chattanooga Nuclear Service Center
"4. Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply:
Response: Defect of pump shaft journal coating resulting in failure of basic component (Service Water Pump 2E) .
"5. The date on which the information of such defect or failure to comply was obtained:
Response: December 5, 2009
"6. In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, being supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part:
Response: Sulzer Pumps (US) Inc, Chattanooga Service Center received Farley Purchase Order QP060449 for eleven (11) Service Water Pumps. The following table outlines current status of the pumps on this order:
Serial Number Status Ship Date Location
08C02139 Shipped 12/18/07 Farley
08C02140 Shipped 5/19/08 Farley
08C02141 Shipped 11/5/08 Farley
08C02142 In Manufacturing N/A Sulzer Chattanooga
08C02143 In Manufacturing N/A Sulzer Chattanooga
08C02144 In Manufacturing N/A Sulzer Chattanooga
08C02145 Failed in Plant - Originally Shipped 11/14/06 for evaluation to Sulzer Chattanooga
08C02146 Shipped 8/3/07 Farley
08C02147 Shipped 7/30/08 Farley
08C02148 In Manufacturing N/A Sulzer Chattanooga
08C02149 In Manufacturing N/A Sulzer Chattanooga
"7. The corrective action which has been, is being , or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action:
Response : A joint root cause evaluation has been completed by Sulzer Pumps (US) and Farley. Corrective actions will include replacement parts with updated and corrected design. Sulzer is developing a manufacturing schedule to implement the corrective actions (estimated completion for schedule, 1st Quarter 2010).
"8. Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been. Is being or will be given to purchasers or licensees:
Response: A comprehensive root cause report has been jointly developed and accepted by Sulzer and Farley."
The following was received via fax:
"1. Name and address of the individual or individuals informing the Commission:
Response: General Manager, Nuclear Services 4126 Caine Lane Chattanooga, TN 37421
"2. Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains defect:
Response: Facility: Farley Nuclear Plant; Basic Component: Unit 2 Service Water Pump (2E)
"3. Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect:
Response: Sulzer Pumps (US) Inc, Chattanooga Nuclear Service Center
"4. Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply:
Response: Defect of pump shaft journal coating resulting in failure of basic component (Service Water Pump 2E) .
"5. The date on which the information of such defect or failure to comply was obtained:
Response: December 5, 2009
"6. In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, being supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part:
Response: Sulzer Pumps (US) Inc, Chattanooga Service Center received Farley Purchase Order QP060449 for eleven (11) Service Water Pumps. The following table outlines current status of the pumps on this order:
Serial Number Status Ship Date Location
08C02139 Shipped 12/18/07 Farley
08C02140 Shipped 5/19/08 Farley
08C02141 Shipped 11/5/08 Farley
08C02142 In Manufacturing N/A Sulzer Chattanooga
08C02143 In Manufacturing N/A Sulzer Chattanooga
08C02144 In Manufacturing N/A Sulzer Chattanooga
08C02145 Failed in Plant - Originally Shipped 11/14/06 for evaluation to Sulzer Chattanooga
08C02146 Shipped 8/3/07 Farley
08C02147 Shipped 7/30/08 Farley
08C02148 In Manufacturing N/A Sulzer Chattanooga
08C02149 In Manufacturing N/A Sulzer Chattanooga
"7. The corrective action which has been, is being , or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action:
Response : A joint root cause evaluation has been completed by Sulzer Pumps (US) and Farley. Corrective actions will include replacement parts with updated and corrected design. Sulzer is developing a manufacturing schedule to implement the corrective actions (estimated completion for schedule, 1st Quarter 2010).
"8. Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been. Is being or will be given to purchasers or licensees:
Response: A comprehensive root cause report has been jointly developed and accepted by Sulzer and Farley."