|
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/16/2010 - 11/17/2010
** EVENT NUMBERS **
|
| General Information or Other |
Event Number: 46412 |
Rep Org: MINNESOTA DEPARTMENT OF HEALTH
Licensee: MAYO CLINIC
Region: 3
City: ROCHESTER State: MN
County:
License #: 1047-206-55
Agreement: Y
Docket:
NRC Notified By: SHERRIE FLAHERTY
HQ OPS Officer: JOE O'HARA |
Notification Date: 11/10/2010
Notification Time: 18:02 [ET]
Event Date: 11/10/2010
Event Time: 11:00 [CST]
Last Update Date: 11/10/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
ANN MARIE STONE (R3DO)
PAUL MICHALAK (FSME) |
Event Text
AGREEMENT STATE REPORT - UNDERDOSAGE TO INTENDED TREATMENT AREA
The following was received via e-mail:
"At approximately 11:00 am on November 10, 2010, the Minnesota Department of Health was notified of a medical event that occurred at Mayo Clinic. Mayo Clinic reports during a biliary LDR treatment using Iridium-192, the catheter and guide wire moved and the radioactive sources moved out of position approximately 7 cm distal to the treatment location (still in the bile duct). The oncologist noticed the guide wire had moved at approximately 10:30 am on November 10, 2010, at that point the RSO was notified. It was determined that the intended treatment site received only 1.24 Gy of the intended dose of 20.0 Gy, making this a reportable event.
"MDH will continue to investigate and will do an on-site visit during the week of November 15. More information to follow."
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: 46421 |
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MICHAEL KOGELSCHATZ
HQ OPS Officer: JOHN SHOEMAKER |
Notification Date: 11/16/2010
Notification Time: 05:48 [ET]
Event Date: 11/16/2010
Event Time: 00:01 [EST]
Last Update Date: 11/17/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL |
Person (Organization):
HAROLD GRAY (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 |
Event Text
CONTROL ROOM ENVELOPE INOPERABLE DUE TO EXCESSIVE EMERGENCY CORE COOLING SYSTEM RELIEF VALVE LEAKAGE DURING ECCS PUMP SURVEILLANCE TESTING
"The Licensee identified that Emergency Core Cooling System (ECCS) leakage exceeded the allowable limit as described in the Updated Final Safety Analysis Report (UFSAR). This is being reported as an Unanalyzed Condition in accordance with 10CFR50.72(b)(3)(ii)(B) and 10CFR50.72(b)(3)(v)® Control of Rad Release.
"The leakage from the Low Head Safety Injection discharge relief valve occurred during Low Head Safety Injection Pump surveillance testing. Efforts to resolve the lifting of the Low Head Safety Injection discharge relief valve are in progress.
"At 0001 [EST] on 11/16/10, Beaver Valley Power Station Unit 1 determined that leakage from the Low Head Safety Injection system in conjunction with a postulated Design Basis Accident (DBA) Loss Of Coolant Accident (LOCA) with transfer to Safety Injection Recirculation would result in dose exceeding the Dose Analysis for the Exclusion Area Boundary (EAB) and the Control Room. The projected dose would exceed the 10CFR50.67 EAB dose limit, and the 10CFR50 GDC 19 Control Room limit, assuming the leakage continued during the postulated DBA event.
"Beaver Valley Units 1 & 2 share a common Control Room Envelope, which has been declared inoperable as a result of this condition. Technical Specification Limiting Condition for Operation 3.7.10, Condition B, has been applied.
"The Senior NRC Resident has been informed of the condition [by the Licensee]."
Notified R1DO (Harold Gray).
* * * UPDATE FROM DAVID SHARBAUGH TO DONALD NORWOOD AT 1448 EST ON 11/17/2010 * * *
"Actions have been completed to prevent leakage from the degraded Low Head Safety Injection System relief valve at BVPS Unit 1. Following successful completion of the post-maintenance test, the BVPS Unit 1 Low Safety Injection System was declared operable and applicable Technical Specification Actions at both BVPS Units were exited at 1545 hours on 11/16/1010.
"The Senior NRC Resident Inspector has been notified."
Notified R1DO (Gray). |
| Power Reactor |
Event Number: 46424 |
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHNNIE EDWARDS
HQ OPS Officer: DONALD NORWOOD |
Notification Date: 11/16/2010
Notification Time: 23:43 [ET]
Event Date: 11/16/2010
Event Time: 22:10 [EST]
Last Update Date: 11/16/2010 |
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):
DEBORAH SEYMOUR (R2DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
M/R |
Y |
26 |
Power Operation |
0 |
Hot Standby |
Event Text
MANUAL REACTOR TRIP BASED ON DECREASING STEAM GENERATOR LEVEL
"At 2210 EST on 11/16/2010, the Unit 1 reactor was manually tripped based on decreasing S/G level in Loop 4. Prior to the reactor trip power was at 26% and ascending following completion of a scheduled refueling outage. Moisture Separator Reheater 1C1 safety valve lifted and would not reseat. Turbine was tripped at 2206 EST to isolate steam leak. Following the Turbine trip, automatic S/G level control did not maintain S/G level. Manual control was taken however, S/G level could not be recovered. A manual reactor trip was initiated due to low narrow range S/G level. All other plant systems responded as expected."
All rods fully inserted into the core during the trip. The reactor is at normal operating pressure and temperature and operators are removing decay heat via the steam dumps to condenser. As expected, the auxiliary feedwater system actuated during the transient. The grid is stable and the plant is in its normal shutdown electrical lineup. There is no known primary-to-secondary leakage. Plant response to the trip was considered normal and uncomplicated. Unit 2 was not affected by this event.
The licensee has notified the NRC Resident Inspector. |
| Other Nuclear Material |
Event Number: 46425 |
Rep Org: ABERDEEN TEST CENTER
Licensee: U.S. ARMY
Region: 1
City: ABERDEEN PROVING GROUNDS State: MD
County:
License #: SUB-834
Agreement: Y
Docket:
NRC Notified By: JAMES DILLARD
HQ OPS Officer: HOWIE CROUCH |
Notification Date: 11/17/2010
Notification Time: 10:10 [ET]
Event Date: 11/16/2010
Event Time: 11:00 [EST]
Last Update Date: 11/17/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(1) - UNPLANNED CONTAMINATION |
Person (Organization):
HAROLD GRAY (R1DO)
MARK THAGGARD (FSME)
JAMNES CAMERON (R3DO) |
Event Text
CONTAMINATION OUTSIDE BOUNDARY AREA DUE TO A PROJECTILE OFF FLIGHT PATH
The licensee was conducting live fire exercises at the Ford Farms section of the Aberdeen Test Center when a depleted uranium (DU) projectile went off its flight path and struck metal causing the projectile to shatter and become friable. Ford Farms is an indoor hard target facility that is targeted from weapons outside of the facility. The projectile shattered outside of Ford Farms thus the contamination is outside the facility.
Initial surveys indicate contamination levels as high as 400 cpm > background. The licensee has roped off the contaminated area and is sampling the air continuously while they formulate a cleanup plan. They estimate cleanup will take approximately two weeks with an additional week required for post-cleanup surveys.
The licensee has made notification to the USNRC Region I office. |
| Power Reactor |
Event Number: 46426 |
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN WEISINGER
HQ OPS Officer: MARK ABRAMOVITZ |
Notification Date: 11/17/2010
Notification Time: 18:26 [ET]
Event Date: 11/18/2010
Event Time: 03:00 [EST]
Last Update Date: 11/18/2010 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
HAROLD GRAY (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 |
| 2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
PLANNED TECHNICAL SUPPORT CENTER VENTILATION CORRECTIVE MAINTENANCE
"This ENS is being issued in advance of a planned activity.
"On November 18th 2010 at 0300, Limerick Generating Station [will apply] a clearance to perform corrective maintenance associated with MD-1 (Outside Air Damper). During the time that the block is applied, the TSC ventilation system will not be available to be restored in a time period required to staff and activate the TSC ERO [Emergency Response Organization].
"This work is expected to be complete on 11/18/10 at 1800. If an emergency is declared requiring TSC activation, the TSC will be staffed and activated using emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation becomes necessary the Station Emergency Director will relocate the TSC staff to an alternate TSC location in accordance with applicable site procedures.
"This notification is being made in accordance with 10CFR50.72(b)(3) due to the loss of an emergency response facility (ERF) because of unavailability of the emergency ventilation system.
"An update will be provided when the TSC ventilation has been restored to normal operation. The NRC resident has been notified."
* * * UPDATE FROM PAUL MARVEL TO DONG PARK AT 1729 EST ON 11/18/10 * * *
Planned work on the TSC ventilation system has been completed at 1700 on November 18, 2010. The TSC has been restored to normal status.
The licensee will notify the NRC Resident Inspector.
Notified R1DO (Gray). |
|