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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/12/2012 - 03/13/2012
** EVENT NUMBERS **
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| Non-Agreement State |
Event Number: 47722 |
Rep Org: INDIANA UNIVERSITY MEDICAL CENTER
Licensee: INDIANA UNIVERSITY MEDICAL CENTER
Region: 3
City: INDIANAPOLIS State: IN
County:
License #: 13-02752-03
Agreement: N
Docket:
NRC Notified By: MACK RICHARDS
HQ OPS Officer: JOHN KNOKE |
Notification Date: 03/07/2012
Notification Time: 14:45 [ET]
Event Date: 07/05/2011
Event Time: [EST]
Last Update Date: 03/07/2012 |
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE |
Person (Organization):
MARK RING (R3DO)
ANGELA MCINTOSH (FSME) |
Event Text
MEDICAL EVENT - DOSAGE DELIVERED TO PATIENT DIFFERED BY 20% FROM PRESCRIBED DOSAGE
On 7/5/11 a male patient receiving treatment for prostate cancer was supposed to receive 52 Iodine-125 seeds to the prostate. The physician conducting the surgery injected 21 of the 52 seeds to an area outside the target volume. Only 31 of the 52 seeds were injected into the targeted area.
The physician and patient will be advised of the disparity in dosage.
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. |
| Power Reactor |
Event Number: 47730 |
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: CHRIS BURKE
HQ OPS Officer: PETE SNYDER |
Notification Date: 03/12/2012
Notification Time: 08:55 [ET]
Event Date: 03/12/2012
Event Time: 08:27 [EDT]
Last Update Date: 03/12/2012 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
GEORGE HOPPER (R2DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
N |
0 |
Cold Shutdown |
0 |
Cold Shutdown |
| 2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
PLANNED MAINTENANCE WINDOW ON TECHNICAL SUPPORT CENTER VENTILATION
"Planned preventive maintenance activities are being performed on the Hatch Nuclear Plant's Technical Support Center (TSC) Emergency Ventilation System on Monday, March 12, 2012. These maintenance activities include the performance of absorber charcoal replacement and DOP testing per 42SV-X75-001-1, 'Testing of TSC Filter Train.' These work activities are planned to be completed within the (12) hour day shift on 03/12/2012.
"During the time these activities are being performed, the TSC Emergency Ventilation System will be inoperable. As such, the TSC HVAC will be rendered non-functional during the performance of these work orders. If an emergency is declared requiring activation of the TSC during the time these work activities are being performed, then the contingency plans call for utilization of the TSC as long as habitability and radiological conditions allow. Procedure 73EP-EIP-063-0, 'Technical Support Center Activation,' provides instructions to direct TSC management to the Control Room and TSC support personnel to the Simulator Building to continue TSC activities if it is necessary to relocate from the primary TSC so that TSC functions can be continued.
"This event is reportable per 10CFR50.72 (b)(3)(xiii) as described in NUREG-1022, Rev. 1 since this work activity affects an emergency response facility for the duration of the evolution."
The licensee notified the NRC Resident Inspector. |
| Fuel Cycle Facility |
Event Number: 47732 |
Facility: WESTINGHOUSE ELECTRIC CORPORATION
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 to UO2)
COMMERCIAL LWR FUEL
Region: 2
City: COLUMBIA State: SC
County: RICHLAND
License #: SNM-1107
Agreement: Y
Docket: 07001151
NRC Notified By: GERARD F. COUTURE
HQ OPS Officer: STEVE SANDIN |
Notification Date: 03/12/2012
Notification Time: 10:44 [ET]
Event Date: 03/11/2012
Event Time: 09:00 [EDT]
Last Update Date: 03/12/2012 |
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (c) - OFFSITE NOTIFICATION/NEWS REL |
Person (Organization):
GEORGE HOPPER (R2DO)
ROBERT JOHNSON (NMSS) |
Event Text
OFFSITE NOTIFICATION TO STATE REQUIRED BY NPDES PERMIT FOR A BYPASS DISCHARGE
"Facility: Westinghouse Electric Company LLC (WEC), Commercial Fuel Fabrication Facility, Columbia SC, low enriched (less than or equal to 5.0 wt.% U-235) fuel fabricator for commercial light water reactors. License: SNM-1107.
"Time and Date of Event: March 11, 2012 approximately 0900
"Reason For Notification:
"On March 12, 2012, the Westinghouse Environmental Engineer was notified that the level readings of the South Lagoon indicated that a leak has developed in the South Lagoon liner. This liner was recently replaced. The South Lagoon is one of the lagoons used for settling solids from treated process wastewater prior to discharge. As the lagoons are located downstream of the Columbia plant wastewater radiological treatment systems, the wastewater in the lagoons is below the 10 CFR Part 20 radioactive materials discharge limits. However, the final discharge monitoring station required by the permit for chemicals are located downstream of the settling lagoons and such a leak is therefore an unanticipated bypass. The current sample analysis of the South Lagoon wastewater reflect the activity is < 4.6 x10 (-7) ÁCi / ml and chemical results are within permit limits.
"Liquid discharges from the Columbia Plant are regulated with regard to chemical pollutants through the SC-DHEC/EPA administered NPDES (National Pollutant Discharge Elimination System) permit SC#0001848. Westinghouse is required to notify SC-DHEC of unanticipated bypass conditions in accordance with Permit.
"Notification to NRC is being made based on 10 CFR70 Appendix A, Section (c) Concurrent Reports:
"' Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made shall be reported to the NRC Operations Center concurrent to the news release or other notification.'
"As Found Condition: See reason for notification.
"Summary of Activity:
- Liquid inflows to the South Lagoon have been rerouted to other authorized locations
- Westinghouse is emptying the South Lagoon through the normal monitored effluent discharge point.
- The liner vendor has been contacted and arrangements are in progress for the vendor to conduct necessary inspections and repairs as soon as practicable.
- Westinghouse has initiated additional monitoring of the wells in close proximity of the South Lagoon to better assess any potential environmental impact.
- The event has been entered into the plant's Corrective Action Process and a thorough review will be performed to identify the cause of the event.
"Conclusions
- The problem was identified by Westinghouse personnel.
- At no time was the health or safety to any employee or member of the public in jeopardy.
- SC-DHEC has been notified." |
| Power Reactor |
Event Number: 47733 |
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MICHAEL QUITTER
HQ OPS Officer: JOHN KNOKE |
Notification Date: 03/12/2012
Notification Time: 11:51 [ET]
Event Date: 03/12/2012
Event Time: 07:42 [PDT]
Last Update Date: 03/12/2012 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION |
Person (Organization):
CHUCK CAIN (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 |
| 2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
OFFSITE NOTIFICATION - NON-WORK RELATED ON-SITE FATALITY
"At 0742 PDT on March 12, 2012, a non-work related on-site fatality occurred at the Diablo Canyon Power Plant. The fatality was not related to the health and safety of the public or on-site personnel. Specifically, a contractor for Pacific Gas and Electric (PG&E) was found in the Engineering Offices before work hours with no pulse or life signs. The individual was promptly attended to by Diablo Canyon Industrial Fire Officers and a transfer to a local hospital by ambulance was completed. The individual was pronounced dead at the hospital.
"The individual was outside of the Radiological Controlled Area and no radioactive material or contamination was involved . The work location was outside of the Protected Area.
"PG&E has not observed any heightened public, media, or government concern as a result of the fatality. Because the fatality is unrelated to Diablo Canyon Power Plant industrial or radiological health and safety, no news release is planned.
"Because the fatality was not work-related, nor the result of an accident, no notification to other government agencies was made at the time. However, PG&E may make a notification to the California Occupational Safety and Health Administration due to a cardiac arrest on-site. Thus this ENS notification is in response to a notification to another government agency in accordance with 10CFR50.72(b)(2)(xi).
"The deceased person worked for Enercon Services.
"The licensee notified the NRC Resident Inspector." |
| Part 21 |
Event Number: 47735 |
Rep Org: ENERSYS
Licensee: ENERSYS
Region: 1
City: READING State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: WILLIAM ROSS
HQ OPS Officer: PETE SNYDER |
Notification Date: 03/12/2012
Notification Time: 15:33 [ET]
Event Date: 03/12/2012
Event Time: [EDT]
Last Update Date: 03/13/2012 |
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION |
Person (Organization):
GEORGE HOPPER (R2DO)
NRR PART 21 GROUP (EMAI) |
Event Text
INTERIM REPORT CONCERNING BATTERY CELLS WITH POTENTIALLY REDUCED DISCHARGE CAPACITY
"This letter will serve as the interim report to the Commission as pursuant to 10CFR21.21 (a) (2). The notification is in regards to a 2GN-23 battery manufactured by EnerSys and installed as part of Station Battery 2-2 at the Dominion Virginia Power, North Anna Station. Battery verification testing performed at North Anna indicated that although the battery was able to meet North Anna's 2 hour discharge requirements, cell #59 appeared to show reduced capacity. As a result, Dominion returned cells #59 and #60 to EnerSys. The cells were received at the EnerSys Corporate Laboratory under Return for Analysis (RFA) ENS-11204.
"During our analysis, which consisted of float charging, discharge testing at the 3 hour rate and an internal inspection it was determined that the cell was unable to meet the defined technical requirements for discharge capacity. Following the determination a series of analytical tests were ordered to perform more in depth analyses of the internal components. Testing on the component samples is currently underway. At this time we have not yet been able to determine if a "defect" as defined in Part 21 exists and therefore this interim report has been prepared. It is expected that the current tests will be completed by May 11, 2012. However, it should be noted that further analysis including the return of additional cells may be required to determine the cause and the reportability under Part 21 reporting."
"Throughout the return and analysis processes EnerSys has been in contact with representatives of the North Anna Station. They have been made aware of the electrical test results and recently of the internal inspection results. They are also aware that there has been no cause determination at this time. Station personnel have also been notified that this interim report has been issued." |
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