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Event Notification Report for June 12, 2008

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/11/2008 - 06/12/2008

** EVENT NUMBERS **


44156 44275 44279 44280 44283 44284 44287 44289

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General Information or Other Event Number: 44156
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: PERMA-FIX NORTHWEST RICHLAND, INC.
Region: 4
City: RICHLAND State: WA
County:
License #: WN-I0393-1
Agreement: Y
Docket:
NRC Notified By: MIKEL ELSEN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/22/2008
Notification Time: 19:40 [ET]
Event Date: 04/17/2008
Event Time: [PDT]
Last Update Date: 06/11/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHUCK CAIN (R4)
KEVIN HSUEH (FSME)

Event Text

WASHINGTON AGREEMENT STATE REPORT - EXTERNAL CONTAMINATION ON A TRANSPORT TRAILER

The following information was received from the State of Washington via e-mail:

"Tritium (H-3) contamination was found on a trailer in the outside storage area of Perma-Fix Northwest (PFNW), a radioactive material licensee in Richland Washington on April 17. A DOH inspector noticed liquid dripping from a trailer that had just been unloaded. The trailer had hauled empty radioactive waste drums from Atomic Energy Limited Canada (Chalk River facility in Ontario). The transport vehicle entered the United States at Sault Ste. Marie, Michigan under a Nuclear Regulatory Commission (NRC) import license and entered Washington at Spokane. The shipment had arrived at the PFNW facility in late February. It was manifested as a plastic fiber bag with drums inside. Initial surveys on February 28 noted tritium contamination inside the plastic fiber bag, but no contamination was noted outside the bag or on the trailer. Tritium was a primary radionuclide on the manifest. During off-loading of the drums and plastic liner on April 17, liquid was found in and on the drums (one drum is suspected of being at least partially filled with liquid). After off-loading, standing liquids were noticed by the licensee on the inside trailer bed, but not on the outer trailer floor and skin. After the truck was returned to the storage yard, liquid droplets were found dripping from the front of the trailer by the DOH inspector. Initial contamination levels (up to 1.8 million dpm of tritium) on the trailer front were substantially above the U.S. Dept of Transportation limits; but due to the limited quantity (less than one gallon of liquid), does not pose a health risk. There is no indication of leakage during the actual shipment.

"The manifest indicated the total shipment contained H-3 (6.59 mCi) and Cs-137 (7.79 mCi) as the predominant radionuclides. Only tritium contamination has been noted."

WA Report # WA-08-025

* * * UPDATE FROM MIKEL ELSEN TO KARL DIEDERICH VIA E-MAIL AT 1538 ON 6/11/08 * * *

The trailer was decontaminated and the associated waste will be disposed or processed. The soil under the trailer was removed and packaged for treatment or disposal. The shipper and broker were issued notices of violation. The cause of this incident was poor oversight during packaging.

Notified R4DO (G. Miller) and FSME EO (A. Mauer).

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Hospital Event Number: 44275
Rep Org: BON SECOURS VIRGINIA HEALTH SOURCE
Licensee: BON SECOURS VIRGINIA HEALTH SOURCE
Region: 1
City: RICHMOND State: VA
County:
License #: 45-25187-01
Agreement: N
Docket:
NRC Notified By: JUDY CHIN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 06/06/2008
Notification Time: 15:07 [ET]
Event Date: 05/01/2008
Event Time: 10:00 [EDT]
Last Update Date: 06/06/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
PAMELA HENDERSON (R1)
LYDIA CHANG (FSME)

Event Text

MEDICAL EVENT - EXCESS SKIN EXPOSURE DURING TREATMENT


A women was prescribed a breast cancer treatment using an HDR mammosite balloon brachytherapy. The dose was delivered in 10 fractions using Iridium - 192 seeds. During administration of the first fraction, the physicist received an alarm from the HDR computer, the alarm was overridden based on the judgment of the physicist at the time of the event and the treatment was completed. Additional fraction treatments were also completed as intended.

Subsequent review of the first treatment and the cause of the alarm indicated that a medical event may have occurred. The alarm was indicating that the seed placement was dislodged by 2 centimeters. The physicist thought at the time that the alarm was indicating the seed dislodged by only 2 millimeters. The treatment calculations were revisited and the dislodgment of the seed by 2 centimeters put the seed at the skin entry point of the application catheter. This resulted in an under dose to the target site and an overdose to the skin. Preliminary calculations estimate that the skin in a 7 mm diameter around the catheter entry point may have received a dose of 3700 centigrays based on the strength of the seed (4.47 curies) and the dwell time.

The patient will be notified of the event. The patient's doctor will continue to monitor the skin for any ill effects.



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.

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Power Reactor Event Number: 44279
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/10/2008
Notification Time: 01:29 [ET]
Event Date: 06/10/2008
Event Time: 02:00 [EDT]
Last Update Date: 06/11/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
PATTY PELKE (R3)

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

EMERGENCY RESPONSE DATA SYSTEM WILL BE TAKEN OUT OF SERVICE

"The Perry Nuclear Power Plant will be taking the ERDS out of service for scheduled maintenance. From approximately 0200 hours EDT, on June 10, 2008, until 2000 hours EDT, on June 10, 2008, personnel will be performing cleaning and inspection activities on the 120 VAC Emergency Response Information System (ERIS) Computer Power Center. During this planned preventive maintenance, the Integrated Computer System, the Safety Parameter Display System (SPDS), and the automatic mode calculation of the Computer Aided Dose assessment program (CADAP) will incur approximately two periods of unavailability of approximately two hours each. The unavailability periods are necessary to align a temporary power supply and reconnect the 120 VAC ERIS Computer Power Center upon completion of the activities.

"The dose assessment function will be maintained during the brief out of service time periods by manual input of data into CADAP and, if required, by manual calculation. In the event of an emergency, plant parameter data will be orally transmitted to the facilities through the Status Board Ring Down circuit with back-up by the Plant Branch Exchange, the Off Premise Exchange, and various redundant intra-facility circuits throughout the emergency facilities. The ability to open and maintain on 'open line' using the Emergency Notification System will not be affected and will be the primary means of transferring plant data to the NRC as a contingency until the ERDS can be returned to service during the two periods of unavailability. This event is being reported in accordance with 10 CFR 50.72(b)(3)(xiii), as a condition that results in a major loss of offsite communications capability. A follow-up notification will be made when the activities are completed and the equipment is restored. The Resident Inspector has been notified."

* * * UPDATE FROM DAVE O'DONNELL TO JOE O'HARA AT 1514 ON 6/10/08 * * *

ERDS is still in service and will not be restored to normal until tomorrow 6/11/08. The scheduled maintenance on the normal power supply today was delayed.

Notified R3DO(Lipa)

* * * UPDATE FROM DAVE O'DONNELL TO KARL DIEDERICH AT 1710 ON 6/11/08 * * *

ERDS was on a temporary power supply. ERDS restored to normal power supply at 1650.

Notified R3DO (Louden).

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Power Reactor Event Number: 44280
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: JIM KONRAD
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/10/2008
Notification Time: 01:52 [ET]
Event Date: 06/09/2008
Event Time: 20:07 [EDT]
Last Update Date: 06/12/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
PATTY PELKE (R3)

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

EMERGENCY OPERATIONS FACILITY POWER OUTAGE

"The Emergency Operations Facility (EOF) became unavailable when a storm took down the power line supplying the building that houses the EOF. The emergency diesel generator failed to start, leaving the EOF without power. Notification being made in accordance with 10CFR50.72(b)(3)(xiii). If EOF actuation is necessary, the alternate EOF will be utilized."

The licensee is investigating the failure of the backup emergency diesel generator to start.

The licensee notified the NRC Resident Inspector.

* * * UPDATE AT 0335 ON 6/12/2008 FROM JIM KONRAD TO MARK ABRAMOVITZ * * *

Power had been restored to the EOF at the time of the initial notification. Power was unavailable on 6/9/2008 from 2007 to 2312, a period of three hours and five minutes.

The licensee notified the NRC Resident Inspector.

Notified the R3DO (Louden).

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Power Reactor Event Number: 44283
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JEAN BROILLET
HQ OPS Officer: PETE SNYDER
Notification Date: 06/11/2008
Notification Time: 00:59 [ET]
Event Date: 06/10/2008
Event Time: 22:55 [EDT]
Last Update Date: 06/11/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ROBERT SUMMERS (R1)

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

54 OF 165 EMERGENCY SIRENS INOPERABLE DUE TO POWER OUTAGE

"On June 10, 2008, at 2255 hours it was determined that 54 of the 165 Limerick Generating Station's Emergency Offsite Sirens were inoperable due to a loss of power. The loss was a result of heavy storms which passed through the area resulting in power outages throughout the region. Efforts are underway to restore power to the affected sirens."

The licensee notified the NRC Resident Inspector

* * * UPDATE FROM BRANDON SHULTZ TO HOWIE CROUCH AT 1709 EDT ON 6/11/08 * * *

"On June 11, 2008 at 1645 restoration efforts have recovered 44 of the 54 sirens rendered inoperable by the storm. The remaining 10 inoperable sirens no longer represents a major loss of emergency preparedness capabilities. Restoration of power to the remaining inoperable sirens continues under normal prioritization and using routine siren operating and maintenance procedures."

No completion time was provided concerning repair of the remaining sirens.

The licensee will be notifying the NRC Resident Inspector. Notified R1DO (Summers).

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Power Reactor Event Number: 44284
Facility: LASALLE
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: MICHAEL FITZPATRICK
HQ OPS Officer: KARL DIEDERICH
Notification Date: 06/11/2008
Notification Time: 18:48 [ET]
Event Date: 06/11/2008
Event Time: 17:03 [CDT]
Last Update Date: 06/11/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
PATRICK LOUDEN (R3)

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

HPCS DECLARED INOPERABLE

"This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident. During steady state operations, a Division 3 AC ground alarm was received, followed by a trip of the 2VD05C Division 3 switchgear room / Core Standby Cooling System (CSCS) Pump Room Supply Fan. Division 3 supplies power to the High Pressure [Core Spray] (HPCS), which is a single-train system. Although the system remained functional and capable of vessel injection following the failure, the HPCS system and its associated power supplies were declared inoperable based on long-term temperature considerations. At 1703, the circuit breaker for the HPCS injection valve, which is a Primary Containment Isolation Valve (PCIV), was opened and the valve deenergized in the closed position to comply with Technical Specifications. Disabling the injection valve affects the safety function of the system (HPCS), and this is reportable as an 8-hour ENS notification.

"The cause of the ventilation fan motor trip has been determined to be a motor fault. Replacement of the fan motor is in progress."

This event places the plant in a 14-day LCO per Technical Specification 3.5.1. Repairs are expected to be completed by 0700 on 6/12/08. The Reactor Core Isolation Cooling (RCIC) system is operable.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 44287
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KEN JOHNSTON
HQ OPS Officer: PETE SNYDER
Notification Date: 06/11/2008
Notification Time: 23:48 [ET]
Event Date: 06/11/2008
Event Time: 14:05 [PDT]
Last Update Date: 06/12/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
GEOFFREY MILLER (R4)

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

IDENTIFICATION OF A POTENTIAL ISSUE WITH ACCUMULATOR DRAIN VALVES

"On June 11, 2008 at 14:05 PDT licensed plant operators entered Technical Specification (TS) 3.0.3 on Units 1 and 2 due to identification of a potential ASCO solenoid valve failure that could initiate draining if the safety injection system accumulators following a small break Loss-of-Coolant-Accident (LOCA).

"ASCO Model 8316 and 8321 pilot operated solenoid valves over 12 years old are susceptible to a potential shuttle ("insert" per vendor documentation) malfunction. The malfunction is that with greater than 12 years of service and a loss of minimum operating pressure differential (MPOD), the shuttle (or insert) could reposition and fail to return to the desired position. This MPOD related reposition could result following instrument air pressure loss and subsequent restoration to containment following a postulated small break LOCA. Diablo Canyon Power Plant (DCPP) Units 1 and 2 each have four susceptible ASCO solenoid valve locations used as drain valves for each of the four safety injection system accumulators per unit.

"DCPP is reviewing the performance of the ASCO solenoids based on a plant problem report and subsequent discussion with the vendor. The safety significance of this event is low as there was no actual accumulator drain valve failure. Although PG&E is still evaluating the potential degradation mechanism and failure mode of these valves, TS 3.03 was conservatively entered base on the potential for malfunction of these valves.

"On June 11, 2008, at 16:10 PDT licensed plant operators exited TS 3.0.3 following isolation of the suspect accumulator drain lines. A licensee event report will be issued for this event.

"The NRC Resident Inspector has been notified."

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Research Reactor Event Number: 44289
Facility: KANSAS STATE UNIVERSITY
RX Type: 250 KW TRIGA MARK II
Comments:
Region: 4
City: MANHATTAN State: KS
County: RILEY
License #: R-88
Agreement: Y
Docket: 05000188
NRC Notified By: PAUL WHALEY
HQ OPS Officer: PETE SNYDER
Notification Date: 06/12/2008
Notification Time: 01:21 [ET]
Event Date: 06/12/2008
Event Time: 00:21 [CDT]
Last Update Date: 06/12/2008
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
GEOFFREY MILLER (R4)
JOHN LUBINSKI (NRR)
WILLIAM GOTT (IRD)
ERIC LEEDS (NRR)
ELMO COLLINS (R4)
GOMEZ (DHS)
KEVIN BISCOE (FEMA)
JULIA MUSE (DOE)
DAVID TIMMONS (USDA)
LEE MILLER (HHS)

Event Text

ALERT DECLARED DUE TO TORNADO IMPACTING REACTOR BUILDING ONSITE

The research reactor building at the Kansas State University was damaged due to a tornado onsite. There is extensive damage to the building. The reactor was shutdown properly earlier in the day. There is no damage to the reactor. There is a loss of power onsite however, this type of reactor requires no active cooling. The reactor is shutdown and stable.

* * * UPDATE AT 0555 ON 6/12/08 FROM PAUL WHALEY TO PETE SNYDER * * *

The Alert condition at the site has been terminated. Conditions requiring entry into the Alert have been rectified.

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