| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/20/2011 - 04/21/2011 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 46747 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: JOE O'HARA | Notification Date: 04/12/2011
Notification Time: 14:34 [ET]
Event Date: 04/12/2011
Event Time: 09:15 [CDT]
Last Update Date: 04/20/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
GEOFFREY MILLER (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text UNSEALED FLOOD BARRIER PENETRATION
"During investigations of flood barrier penetrations, a flood barrier sealing a diesel driven fire pump exhaust was found to be cracked. This exhaust pipe penetrates the west wall of the intake structure. Flooding through the penetration could have impacted the ability of the station's raw water pumps to perform their design accident mitigation functions.
"This eight-hour notification is being made pursuant to 10 CFR 50.72 (b)(3)(v).
"The penetration is at an approximate elevation of 1012 feet mean sea level (MSL). The river level has been less than 997 feet MSL since prior to December 1, 2010. The raw pumps are operable. There are not any indications of conditions that might result in a flood. Actions are in progress to plug the penetration."
The NRC Resident Inspector has been notified.
* * * UPDATE FROM ERICK MATZKE TO JOE O'HARA AT 1641 ON 4/20/11 * * *
"This event is being retracted.
"Additional review and evaluation determined that the seal flaw is above the station design flood level of 1014 feet mean sea level, and is therefore, not reportable."
The NRC Resident Inspector has been notified.
Notified R4DO (Hay). |
| Hospital | Event Number: 46753 | Rep Org: MEMORIAL HEALTHCARE HOSPITAL
Licensee: MEMORIAL HEALTHCARE HOSPITAL
Region: 3
City: OWOSSO State: MI
County:
License #: 21-11475-01
Agreement: N
Docket:
NRC Notified By: ART EWALD
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/14/2011
Notification Time: 12:02 [ET]
Event Date: 02/23/2010
Event Time: [EDT]
Last Update Date: 04/14/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
| Person (Organization):
STEVE ORTH (R3DO)
ANGELA MCINTOSH (FSME)
| Event Text MEDICAL EVENT - BRACHYTHERAPY UNDERDOSE TO PROSTATE GLAND
On 2/23/10, a patient went to Memorial Healthcare Hospital for brachytherapy treatment to the prostate gland. The prescribed treatment was 125 Gy (75 seeds) to the prostate gland. Due to swelling, the enlarged organ resulted in a lower radiation dose within the prostate. Even though all 75 seeds were implanted, the actual dose to the patient was 81.07 Gy. On 4/12/10 the physician notified the patient of the underdose and made arrangements for a second treatment. On 5/4/10 the second brachytherapy treatment of 57.26 Gy (8 seeds) was performed on the patient. In evaluating the patient's second treatment results, no further action was required.
This event is being reported due to a finding from an NRC audit.
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. |
| Agreement State | Event Number: 46754 | Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: VIRGINIA HOSPITAL CENTER
Region: 1
City: Arlington State: VA
County:
License #: 013-220-1
Agreement: Y
Docket:
NRC Notified By: CHARLES COLEMAN
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 04/14/2011
Notification Time: 13:59 [ET]
Event Date: 01/11/2011
Event Time: [EDT]
Last Update Date: 04/14/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
PAMELA HENDERSON (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE- UNDER DOSE ADMINISTERED TO PATIENT
The following was received via facsimile.
"In January 2011 a patient was administered 1.58 millicuries of (Iodine) I-I31 for a whole body scan. The written directive specified a 2.0 millicurie dosage. The difference was discovered during a routine audit by the licensee's health physics consultant in March 2011. Calculations by the health physicist indicated the difference between the written directive and the administered dose differed by more than 20 percent, that the difference in the effective dose exceeded 5 rem and that the difference in the dose to the thyroid exceeded 50 rem. A report dated March 24, 2011 was received by (Virginia Department of Health) VDH on April 4, 2011. An on-site investigation by VDH was performed on April 8, 2011. The licensee indicated that the quality of the whole body scan was not compromised and that because the administered dose was less than the written directive, there is no radiological hazard to the patient."
Virginia Radioactive Materials Program Event Report ID.: VA-11-01
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: 46771 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ED TIEDEMANN
HQ OPS Officer: JOE O'HARA | Notification Date: 04/20/2011
Notification Time: 18:05 [ET]
Event Date: 04/20/2011
Event Time: 09:15 [CDT]
Last Update Date: 04/20/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
MONTE PHILLIPS (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 97 | Power Operation | 97 | Power Operation | Event Text WATERTIGHT DOORS LEFT AJAR SIMULTANEOUSLY DURING ROOM CHECKS
"During the performance of operator rounds in the Lake Screenhouse Safe Shutdown System (SX) pump rooms, two water tight doors were left opened simultaneously during the room checks. These two doors opened simultaneously [which] allowed for communication between the Division 1 SX room and Division 2 SX pump room. The operator was in constant attendance in the Division 2 SX pump room during the performance of the equipment checks.
"During site review, it was determined that a flood in either the Division 1 or Division 2 SX pump rooms would not be isolated to the initiating room, but potentially affect both trains of SX. This could result in a loss of cooling for both Residual Heat Removal systems, therefore, a condition that could have prevented fulfillment of a safety function under 10CFR50.72(b)(3)(v)(B).
"The NRC Senior Resident has been notified."
Offsite power is normal and emergency diesel generators are operable and available. |
| Power Reactor | Event Number: 46772 | Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL DUNN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 04/20/2011
Notification Time: 20:45 [ET]
Event Date: 04/20/2011
Event Time: 17:34 [EDT]
Last Update Date: 04/20/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
JONATHAN BARTLEY (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP
"At 1734 EDT, [Vogtle] unit one automatically tripped from 100% power. No significant activities were in progress that should have challenged the Reactor Protection System. All control rods fully inserted. AFW system actuated as expected on S/G Lo-Lo-Level and AMSAC [ATWS Mitigation System Actuation]. System responses allowed for an uncomplicated reactor trip response. Plant is stable and will remain in Mode 3 during cause investigation.
"Cause of the reactor trip is under investigation."
The plant is in its normal shutdown electrical lineup. Decay heat is being sent to the main condenser through the turbine bypass valves. The steam generators are being fed from auxiliary feedwater. There was no effect on unit two.
The licensee informed the NRC Resident Inspector. | |