| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/16/2012 - 11/19/2012 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 48498 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: DANA-FARBER CANCER INSTITUTE
Region: 1
City: BOSTON State: MA
County:
License #: 60-0037
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/09/2012
Notification Time: 17:02 [ET]
Event Date: 11/07/2012
Event Time: [EST]
Last Update Date: 11/09/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GLENN DENTEL (R1DO)
FSME RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - DOSE TO EMBRYO/FETUS
The following information was obtained from the Commonwealth of Massachusetts via facsimile:
"A lung cancer patient [underwent] PET and CT [scans and received] a calculated dose of 2 Rem to [her] embryo. The patient was asked if she was pregnant and she replied no. The dose was calculated to be 8.8 mGy from CT and 11.5 mGy from PET."
The patient was notified. |
| Power Reactor | Event Number: 48508 | Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: WARREN WONKA
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 11/14/2012
Notification Time: 16:13 [ET]
Event Date: 11/14/2012
Event Time: 09:27 [EST]
Last Update Date: 11/17/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MALCOLM WIDMANN (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text RADIATION MONITOR OUT OF SERVICE
"This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability.
"On November 14, 2012, Radiation Monitor R-9, Letdown Line Radiation Monitor was removed from service at 0927 [EST] hours following failure of the internal and external source checks during performance of radiation monitor source checks. Both source checks failed high.
"This radiation monitor is used for accident assessment and is credited for Emergency Action Level (EAL) classification for an Unusual Event in the Robinson Nuclear Plant Emergency Plan. Additionally, this monitor is one of multiple indicators used to detect the loss of a fission product barrier. Inability to classify an EAL due to an out of service monitor is considered a loss of accident assessment capability and is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2. Actions are in place to restore the monitor to functional status.
"The NRC Resident Inspector has been notified."
* * * UPDATE ON 11/17/12 AT 0812 EST FROM GEORGE CURTIS TO DONG PARK * * *
At 1717 EST on 11/16/12, the Letdown Line Radiation Monitor was placed back in service and is functional.
The licensee has notified the NRC Resident Inspector. Notified R2DO (Widmann). |
| Power Reactor | Event Number: 48510 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DAVID MANKIN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 11/16/2012
Notification Time: 09:04 [ET]
Event Date: 11/16/2012
Event Time: 08:10 [CST]
Last Update Date: 11/16/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MICHAEL KUNOWSKI (R3DO)
|
| 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 SPDS OUT OF SERVICE DUE TO PLANNED MAINTENANCE
"A planned maintenance evolution at Duane Arnold Energy Center (DAEC) to replace a hard drive in the plant process computer will result in a loss of all SPDS indication for a duration of less than six hours.
"There is no planned maintenance affecting Primary Indications or Annunciators in the Control Room which would affect the plant's ability to assess or monitor an accident or transient in progress.
"This notification is being made pursuant to 10CFR50.72(b)(3)(xiii)."
The licensee will notify the NRC Resident Inspector.
* * * UPDATE AT 1433 EST ON 11/16/12 FROM MANKIN TO HUFFMAN * * *
The planned maintenance has been completed and SPDS returned to service at 1431 EST. The licensee has notified the NRC Resident Inspector. R3DO(Kunowski) notified. |
| Power Reactor | Event Number: 48511 | Facility: BYRON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT LAWLOR
HQ OPS Officer: DONALD NORWOOD | Notification Date: 11/16/2012
Notification Time: 10:58 [ET]
Event Date: 10/01/2012
Event Time: 14:03 [CST]
Last Update Date: 11/16/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
MICHAEL KUNOWSKI (R3DO)
|
| 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 60-DAY OPTIONAL TELEPHONIC NOTIFICATION OF INVALID SYSTEM ACTUATION
"In accordance with 10CFR50.73(a)(2(iv)(A), this telephone notification reports an invalid actuation of the Unit 1 train A (1A) Emergency Diesel Generator (DG) on October 1, 2012, at 1403 hours. At the time of the event Unit 1 was in Mode 5, Cold Shutdown. The 1A DG was undergoing a surveillance procedure that verifies a safety injection override signal when a technician actuated the incorrect under voltage relay which resulted in the inadvertent start of the 1A DG. The engine functioned successfully and ran unloaded, as expected. The cause is attributed to the technicians failing to verify they were actuating the correct relay. This condition was entered into the corrective action program."
The licensee notified the NRC Resident Inspector and the Illinois Department of Nuclear Safety. |
| Power Reactor | Event Number: 48512 | Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CURTIS JENKINS
HQ OPS Officer: BILL HUFFMAN | Notification Date: 11/16/2012
Notification Time: 15:35 [ET]
Event Date: 11/16/2012
Event Time: 15:00 [EST]
Last Update Date: 11/16/2012 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
VICTOR MCCREE (R2 R)
TOM BERGMAN (NRR)
MALCOLM WIDMANN (R2DO)
JOSEPH GIITTER (NRR)
JASON KOZAL (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNUSUAL EVENT DECLARED BASED ON FIRE ALARM IN PROTECTED AREA
The licensee received a fire alarm in an auxiliary building tunnel (Zone 146) that could not be verified within 15 minutes. An unusual event was declared (EAL HU2) at 1500 EST. At 1505 EST the licensee fire responders were able to reach the location of the alarm and confirmed that there was no fire. The licensee has performed inspections of the area and do not yet know the cause of the fire alarm but are certain that it was not caused by an actual fire. The cause of the fire alarm is still under investigation. No offsite assistance was summoned for this event. Following restoration of fire protection system to a normal status the licensee terminated the unusual event at 1550 EST.
The licensee has notified State and local authorities and the NRC Resident Inspector. No press release is planned at this time.
Notified DHS SWO, FEMA, DHS NICC and NuclearSSA via email. |
| Power Reactor | Event Number: 48514 | Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DON CERNY
HQ OPS Officer: BILL HUFFMAN | Notification Date: 11/17/2012
Notification Time: 12:30 [ET]
Event Date: 11/17/2012
Event Time: 10:23 [CST]
Last Update Date: 11/17/2012 | 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):
JAMES DRAKE (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL
"At 1023 CDT Comanche Peak Unit 2 automatically tripped due to steam generator low level. The trip was uncomplicated. All control and shutdown rods fully inserted. Neither emergency diesel generator started. All safety systems functioned as designed. Both motor driven and the turbine driven AFW pumps started as required to restore steam generator level as a result of the trip. The turbine driven AFW pump was returned to auto-start status. The turbine driven AFW pump has been placed in pull-out as per procedure after verifying normal motor driven AFW pump operation.
"Currently Unit 2 is in Mode 3, (no-load Tave 557 - degrees Fahrenheit) with temperature being maintained with the AFW and steam dumps to the main condenser. Recovery actions will be planned. All electrical busses are powered from offsite power and grid conditions are stable.
"The initiating event appears to be a sheared instrument air tubing line that feeds the common heater drain pump discharge valve which will fail close resulting in loss of all heater drain flow."
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 48517 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JOE McKEE
HQ OPS Officer: PETE SNYDER | Notification Date: 11/17/2012
Notification Time: 22:16 [ET]
Event Date: 11/17/2012
Event Time: 20:00 [EST]
Last Update Date: 11/17/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MALCOLM WIDMANN (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | | 4 | N | N | 0 | Refueling | 0 | Refueling | Event Text AUTO-INITIATION FEATURE OF TECHNICAL SUPPORT CENTER VENTILATION IMPROPERLY INHIBITED
"In anticipation of core offload, the control room emergency ventilation system was placed in recirculation mode. As a result of a deficient procedure, an automatic initiation feature to the Technical Support Center (TSC) ventilation system was inhibited from 11/16/12 at 2325 [EST] to 11/17/12 at 1419 [EST].
"The Turkey Point TSC habitability design basis assumes that upon discovery of an accident condition, an initiation signal will automatically place both control room and TSC ventilation systems in recirculation.
"Contrary to the design basis, it was discovered on 11/17/12 at 2000 [EST] that when the TSC ventilation system was placed in the 'inhibited mode,' the automatic initiation feature to the TSC ventilation system recirculation mode was defeated. The TSC ventilation system otherwise remained functional and available.
"Upon discovery of this condition, the TSC inhibit switch was returned to enable which would allow the TSC to automatically go on recirculation from an automatic start signal. No accident conditions occurred that warranted a need to activate any emergency operations facilities.
"This notice is made in accordance with 10 CFR 50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 48518 | Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: MICHAEL MOORE
HQ OPS Officer: VINCE KLCO | Notification Date: 11/18/2012
Notification Time: 11:10 [ET]
Event Date: 11/18/2012
Event Time: 11:30 [EST]
Last Update Date: 11/18/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MALCOLM WIDMANN (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text LOSS OF ASSESSMENT CAPABILITY DUE TO INTEGRATED PLANT COMPUTER PLANNED MAINTENANCE
"On 11/18/2012 at approximately 1130 EST, the Summer Safety Parameter Display System (SPDS) and the Emergency Response Data System (ERDS) will be taken out of service for approximately 12 hours to support a planned maintenance on an inverter that feeds the station's Integrated Plant Computer System (lPCS). During this time frame. ERDS and SPDS will be unavailable. Should the need arise, plant status information will be communicated to the NRC using other available communication systems. SPDS and ERDS are expected to be restored on 11/18/2012 at 1800 EST. This event is reportable under 10 CFR 50.72(b)(3)(xiii).
"The NRC Resident Inspector has been notified." | |