United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for March 14, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/13/2012 - 03/14/2012

** EVENT NUMBERS **


47722 47730 47735 47736 47739

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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.

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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: 03/13/2012
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.

* * * UPDATE FROM CHRIS BURKE TO JOHN KNOKE AT 1644 EDT ON 3/13/12 * * *

"During post Preventive Maintenance [PM] activity testing, the TSC emergency filter train bypass valve 1X75F005 damper failed to meet leakage criteria (CR 422749). PM activities were halted and a corrective maintenance Work Order SNC377526 initiated at approximately 2030 EDT to investigate, repair and retest the bypass valve damper. Repair work to the TSC emergency filter train bypass valve was completed. The retest and verification was performed and the TSC HVAC system returned to service at 1550 EDT on 3/13/12."

The licensee has notified the NRC Resident Inspector. Notified the R2DO (Eugene Guthrie)

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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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Power Reactor Event Number: 47736
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: FRANK GILLIAM
HQ OPS Officer: PETE SNYDER
Notification Date: 03/13/2012
Notification Time: 08:10 [ET]
Event Date: 03/13/2012
Event Time: 08:00 [EDT]
Last Update Date: 03/13/2012
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 Y 100 Power Operation 100 Power Operation

Event Text

EMERGENCY OPERATIONS FACILITY PLANNED MAINTENANCE

"At approximately 0800 EDT on March 13, 2012, preplanned maintenance will be performed on the Emergency Operations Facility (EOF) ventilation system. This maintenance will be performed for charcoal sampling and filter testing. This maintenance is planned to be performed and completed within 10 hours. If an emergency condition should occur that would require activation of the EOF, the Harris Nuclear Plant (HNP) emergency plan has procedural guidance for use of an alternate location.

"This event is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2 since this work activity affects an emergency response facility for the duration of the maintenance."

The licensee notified the NRC Resident Inspector.

* * * UPDATE AT 1707 EDT ON 3/13/2012 FROM RICHARD VANDENBERG TO MARK ABRAMOVITZ * * *

Maintenance was completed and the system tested operable at 1645 EDT. The licensee notified the NRC Resident Inspector.

Notified the R2DO (Guthrie).

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Power Reactor Event Number: 47739
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ALAN MARZLOFF
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/13/2012
Notification Time: 17:58 [ET]
Event Date: 03/13/2012
Event Time: 14:00 [CDT]
Last Update Date: 03/13/2012
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 OF A SEWAGE LEAK

"A Sewage Lift Station overflow occurred due to equipment failure. The overflow was discovered at 1400 CDT and terminated shortly thereafter. CPNPP Environmental notified TCEQ (Texas Commission on Enviornmental Quality) Region 4 (DFW) at 1441 CDT. This is reportable as a bypass of untreated wastewater as defined in the TPDES [Texas Pollution Discharge Elimination System] Permit. CPNPP Environmental personnel have completed disinfection of the affected area."

The licensee estimated the leak to be between 100 and 200 gallons with a small portion reaching the lake. The equipment failure is suspected as being a failed level indicating system. The licensee will notify the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012