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Event Notification Report for January 25, 2008

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/24/2008 - 01/25/2008

** EVENT NUMBERS **


43917 43927 43931 43932

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Hospital Event Number: 43917
Rep Org: DEPARTMENT OF VETERANS AFFAIRS
Licensee: DEPARTMENT OF VETERANS AFFAIRS
Region: 1
City: BOSTON State: MA
County:
License #: 03-23853-01VA
Agreement: Y
Docket:
NRC Notified By: GARY WILLIAMS
HQ OPS Officer: JASON KOZAL
Notification Date: 01/18/2008
Notification Time: 15:20 [ET]
Event Date: 01/17/2008
Event Time: [EST]
Last Update Date: 01/18/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(2) - DOSE > SPECIFIED EFF LIMITS
Person (Organization):
EUGENE COBEY (R1)
HIRONORI PETERSON (R3)
KEITH McCONNELL (FSME)

Event Text

POTENTIAL OVEREXPOSURE

"The possible medical event occurred at a broad-scope permittee authorized under the master materials license issued to the Department of Veterans Affairs, NRC License 03-23853-01VA. The permittee is VA Boston Healthcare System, Boston, Massachusetts.

"The possible medical event occurred on January 17, 2008, and was discovered the same day. The basis for the possible medical event is under 10 CFR 35.3045(a)(2) and involved administration of radiopharmaceutical that might have resulted in more than 50 rem to tissue and involved a wrong route of administration.

"Specifically, a F-18 FDG injection of approximately 3.6 millicuries was infiltrated into a patient's arm.

"The Department of Veterans Affairs and permittee are reviewing the possible medical event circumstances and the dose calculation methods.

"The permittee informed the patient and referring physician."

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Power Reactor Event Number: 43927
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: THOMAS LAPORTE
HQ OPS Officer: JOE O'HARA
Notification Date: 01/23/2008
Notification Time: 18:31 [ET]
Event Date: 01/23/2008
Event Time: 17:05 [CST]
Last Update Date: 01/24/2008
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
CLAUDE JOHNSON (R4)
MICHAEL CASE (NRR)
ELMO COLLINS (RA)
ROY ZIMMERMAN (NSIR)
THOMAS BLOUNT (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling

Event Text

UNUSUAL EVENT - TOXIC GASES IN THE TURBINE BUILDING

"Detection of toxic gases (CO) inside the turbine building.

"Source not identified.

"Initial Readings were greater than 50 parts per million in turbine building lower elevations.

"EALHU5.1

"Detected by safety department random sampling.

"Turbine building has been evacuated, all personnel have been accounted for with no injures.

"Follow-up notification will be made with determination of cause of event.

"The unit is currently defueled. The carbon monoxide source is being investigated."

The NRC Resident Inspector as well as state and local authorities were notified.

* * * UPDATE FROM ERIC PICKRELL TO JOE O'HARA AT 1932 EST ON 1/23/08 * * *

"Notified J. O'Hara of termination of the declared NOUE. Termination is based on subsequent air monitoring sampling revealing normal Oxygen levels and no detectable Carbon Monoxide levels.

"(unknown) Source of abnormal sample readings is not yet determined. Believed to be result of Hydrogen Water Chemistry system purge which was in progress at the time of sampling."

Licensee terminated the declaration of notification of unusual event at 1827 CST following two subsequently satisfactory air samples.

Notified R4DO(Johnson), NRR(Case), and IRD(Blount)


* * UPDATE FROM TIM SCHENK TO JOHN KNOKE AT 1515 EST ON 01/24/08 * *

"It has been determined that hazardous levels of toxic gases (Carbon Monoxide) inside the turbine building did not exist at the time of emergency declaration. Actual carbon monoxide levels were less than detectable. Gas sensor cross contamination led to false readings of high carbon monoxide level (60 ppm), when actual gas measurements were reading hydrogen levels of 20 ppm. This level of hydrogen is well below the 40,000 ppm Lower Explosive Limit for hydrogen. The source of the hydrogen readings was attributed to a leaking ventilation rig for the Hydrogen Water Chemistry system during system purge with Nitrogen."


The licensee notified the NRC Resident Inspector. Notified R4DO (C. Johnson).

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Power Reactor Event Number: 43931
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: GUY FORD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/24/2008
Notification Time: 17:45 [ET]
Event Date: 01/24/2008
Event Time: 12:45 [CST]
Last Update Date: 01/24/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
LAURA KOZAK (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 79 Power Operation 79 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

CONFIRMED POSITIVE FITNESS FOR DUTY TEST ON A CONTRACT SUPERVISOR

A non-licensed contract employee supervisor had a confirmed positive for illegal drugs during a fitness-for-duty test. The employee's access to the plant has been suspended. Contact the Headquarters Operations Officer for additional details.

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Power Reactor Event Number: 43932
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: ARNIE CRIBB
HQ OPS Officer: HOWIE CROUCH
Notification Date: 01/24/2008
Notification Time: 18:59 [ET]
Event Date: 01/24/2008
Event Time: 16:04 [EST]
Last Update Date: 01/24/2008
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):
BINOY DESAI (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 100 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO FAILURE OF THE "C" FEEDWATER FLOW CONTROL VALVE

"At 1604 [EST], VC Summer Nuclear Station was manually tripped due to rapidly decreasing level in 'C' Steam Generator. The decreasing Steam Generator level was due to a failure of the 'C' Feedwater Flow Control Valve. All systems responded as required. All Emergency Feedwater Pumps automatically started on Lo-Lo Steam Generator level. The Steam Generator levels recovered quickly. The Pressurizer Level Control System cycling resulted in lifting the Letdown System Relief Valve due to high temperature and pressure. The Letdown Relief Valve reseated with no further problems. One Moisture Separator Reheater Relief Valve lifted momentarily and reseated.

"Presently, the plant is in Mode 3 with normal RCS pressure and temperature. Decay heat is being removed by dumping steam to the condenser. The plant will remain in Mode 3 until repairs are completed on the 'C' Feedwater Flow Control Valve."

During the trip, all control rods fully inserted into the core. The electrical grid is stable and emergency power is being supplied from offsite via the station start-up transformer. There is no known primary to secondary leakage.

The licensee has notified the NRC Resident Inspector and will be notifying State and local agencies.

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