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Event Notification Report for September 09, 2008

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
09/08/2008 - 09/09/2008

EVENT NUMBERS
444754456749946

Power Reactor
Event Number: 44475
Facility: PRAIRIE ISLAND
Region: 3     State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: BILL BODIN
HQ OPS Officer: JEFF ROTTON
Notification Date: 09/09/2008
Notification Time: 10:24 [ET]
Event Date: 09/09/2008
Event Time: 05:30 [CDT]
Last Update Date: 09/09/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
DAVE PASSEHL (R3)
Power Reactor Unit Info
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 DUE TO CAR ACCIDENT

"At approximately 0530 CDT hours, a car accident occurred on the driveway of the parking lot at the Prairie Island Nuclear Plant. The driver of the vehicle was not a plant employee. The driver left the scene of the accident. Plant security and local law enforcement are investigating. No press release is planned."

The licensee notified the NRC Resident Inspector, the Emergency Management agencies of Goodhue, Dakota, and Pierce counties, the State of Wisconsin and the Prairie Island Tribal council.


Power Reactor
Event Number: 44567
Facility: SUSQUEHANNA
Region: 1     State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/15/2008
Notification Time: 15:03 [ET]
Event Date: 09/09/2008
Event Time: 06:46 [EDT]
Last Update Date: 10/15/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
TODD JACKSON (R1)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 94 Power Operation 94 Power Operation
2 N Y 100 Power Operation 100 Power Operation
Event Text
INVALID ACTUATION OF CONTAINMENT ISOLATION VALVES

"On 09/09/08 at approximately 0646 hours, with both Susquehanna Units in Mode 1 (U1-94.4% power, U2-100% power), Susquehanna experienced a temporary loss of its Transformer 10 (T-10) offsite power source due to lightning storms in the area. The loss of T-10, combined with a failure of Tie Breaker OA105-02 automatic closure logic, (caused by a breaker contact problem that has subsequently been corrected) resulted in the de-energization of Startup Bus 10 (normally powered through T-10). With this electrical transient, some 4.16 kV emergency busses normally powered by Startup Bus 10 experienced a short (~0.5 sec) electrical perturbation as the busses transferred to their alternate (Startup Bus 20) power source. This momentary power disruption resulted in numerous containment isolations. These isolations, on both Unit 1 and Unit 2, included: (1) Reactor Building Chilled Water to the Reactor Recirculation pumps, (2) Reactor Water Sample valves, (3) Instrument Gas TIP Indexer Isolation valves, (4) Drywell Equipment Drain Tank/Drywell Floor Drain Isolation valves, and (5) the 'A' and 'B' Containment Radiation Monitors.

"Because plant conditions necessary to prompt a containment isolation were not present, this event constitutes an invalid system actuation and is reportable under 10 CFR 50.73(a)(2)(iv)(A). The condition meets the criteria of 10 CFR 50.73(a)(2)(iv)(B)(2) because the electrical anomaly affected containment isolation valves in more than one system. This notification is being provided via a 60-day optional phone call as permitted under 10 CFR 50.73(a)(1) in lieu of a written LER.

"Valves affected by the invalid signal fulfilled their isolation function by successfully closing. There were no challenges to the Reactor as a result of this event. Transformer 10 was successfully re-energized in under an hour. All affected 4.16 kV emergency busses were transferred back to their normal power supply within 78 minutes of the initial event."

The NRC Resident Inspector will be notified.


!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Non-Agreement State
Event Number: 49946
Rep Org: BOZEMAN DEACONESS HOSPITAL
Licensee: BOZEMAN DEACONESS HOSPITAL
Region: 4
City: BOZEMAN   State: MT
County:
License #: 25-10994-04
Agreement: N
Docket:
NRC Notified By: KARI CANN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/21/2014
Notification Time: 17:53 [ET]
Event Date: 09/09/2008
Event Time: 00:00 [MDT]
Last Update Date: 04/09/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
GREG PICK (R4DO)
FSME EVENTS RESOURCE (EMAI)
Event Text
THREE MEDICAL MISADMINISTRATION INCIDENTS

During a recent review of historical records, it was determined that three medical misadministration incidents had occurred. Two of these incidents occurred on September 9, 2008 and the third incident occurred on September 30, 2008.

The patients were being treated for prostate cancer and were receiving I-125 brachytherapy. Two patients were each prescribed a source activity of 0.269 mCi but received 0.341 mCi. The third patient was prescribed 0.340 mCi but received 0.439 mCi.

The patients have been followed elsewhere for the last few years. The licensee will assess the patients as soon as they are available. The licensee is in the process of notifying the patients of the misadministrations.

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.

* * * RETRACTION AT 0835 ON 4/9/14 FROM KARI CANN TO PETE SNYDER * * *

The RSO for the hospital has reevaluated this report and has determined, in consultation with NRC Region IV, that due to a lack of complete information this report is retracted. If later, when more complete information is available it is determined that a report needs to be made it will be made at that time.

Notified R4DO (Drake) and FSME EVENT RESOURCE (email).