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Event Notification Report for August 24, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/23/2004 - 08/24/2004

** EVENT NUMBERS **


40967 40974 40975 40977 40978

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General Information or Other Event Number: 40967
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: THE METHODIST HOSPITAL
Region: 4
City: HOUSTON State: TX
County:
License #: L00457
Agreement: Y
Docket:
NRC Notified By: JAMES OGDEN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 08/18/2004
Notification Time: 15:21 [ET]
Event Date: 07/28/2004
Event Time: [CDT]
Last Update Date: 08/18/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
WILLIAM JONES (R4)
SANDRA WASTLER (NMSS)

Event Text

SOURCE TRAIN DID NOT RETRACT

"After IVB therapy the source train did not retract due to a kink in the IVB catheter, did not retract to the remote Beta-Cath device. The IVB catheter was immediately withdrawn and placed in the Novoste emergency plexiglass storage safe and then in the IVB storage room. No overexposure was received by the patient or attending staff. Novoste has been notified of the malfunction. The Novoste Beta Cath was returned to the manufacture on August 2, 2004. The IVB manufacturer is Novoste Beth Cath, source Sr-90, 1.71 GBq (46 millicuries). Transfer device Serial No. 92917, and Source train Serial No. ZA543. The device was packaged and returned to the manufacturer on August 2, 2004. This agency did not receive notice of the event within 24-hours"

Texas Incident No.: I-8155

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Power Reactor Event Number: 40974
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: CHARLES SIBLEY
HQ OPS Officer: JEFF ROTTON
Notification Date: 08/22/2004
Notification Time: 14:23 [ET]
Event Date: 08/22/2004
Event Time: 10:10 [CDT]
Last Update Date: 08/23/2004
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):
GREG PICK (R4)
DAVID MATTHEWS (NRR)
PETER WILSON (IRD)
VICTOR DRICKS (R4PA)

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

REACTOR TRIP DURING SURVEILLANCE TEST

"At 1010 CDT on 8-22-2004, during the performance of STS IC-211B, 'ACTUATION LOGIC TEST TRAIN B SOLID STATE PROTECTION SYSTEM,' Control Room operators received a reactor trip concurrent with power range flux lo [low] setpoint trip and intermediate range hi [high] flux reactor trip alarms.

"All safety-related equipment operated as required. The Steam Dump valves, which function to remove excess heat as the secondary systems shutdown, did not initially operate as expected, resulting in the operation of the Steam Generator Atmospheric Relief Valves (ARVs) to control Reactor Coolant pressure for approximately three minutes following the reactor trip, at which time the Steam Dump valves responded as expected and the ARVs closed. The Steam Dumps are currently operating correctly in automatic.

"The Auxiliary Feedwater System actuated as designed.

"The plant is currently stable in Mode 3 at Normal Operating Temperature and Pressure while plant personnel investigate the causes of the reactor trip and formulate the repair/ restart plan.

"A press release is planned."

During the reactor trip, all control rods fully inserted. The electric plant is in a stable shutdown plant lineup. Plant personnel also intend to investigate the unusual response of the steam dump valves.

The licensee has notified the NRC Resident Inspector.

* * * Update on 08/23/04 at 1635 EDT by Steven Gifford taken by MacKinnon * * *

"Upon data review related to the operation of the Steam Dump valves and the Atmospheric Relief Valves (ARVs), plant staff has determined that the ARVs and Steam Dump valves operated as expected. The Steam Dump valves opened immediately following the reactor trip, as designed, due to the difference between their setpoint and the Reactor Coolant System (RCS) temperature at the time of the reactor trip. The Steam Dump valves remained open for approximately 20 to 30 seconds, at which time the RCS temperature had decreased to a value within the control range for the Steam Dump valves, causing them to close. The opening of the ARVs was in response, as designed, to the increase in Steam Generator pressure that resulted from the turbine trip shortly after the reactor trip."

NRC R4DO (Tom Farnholtz) notified.

The NRC Resident Inspector was notified of this update by the licensee

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Other Nuclear Material Event Number: 40975
Rep Org: DOMINION GEOTECHNICAL
Licensee: DOMINION GEOTHECNICAL
Region: 1
City: GARRISONVILLE State: VA
County: STAFFORD
License #: 45-30860-01
Agreement: N
Docket:
NRC Notified By: KEVIN PARRIS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/23/2004
Notification Time: 09:34 [ET]
Event Date: 08/20/2004
Event Time: 11:00 [EDT]
Last Update Date: 08/23/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
Person (Organization):
JOHN WHITE (R1)
LINDA PSYK-GERSEY (NMSS)

Event Text

DAMAGED TROXLER MOISTURE DENSITY GAUGE

The licensee reported that a Troxler Moisture Density Gauge, Model 3411, Serial Number 13101, was damaged when it was run over by a soil compacting roller. The gauge suffered a cracked housing and a bent handle but the source is retracted into the shield. The gauge contains 8 milliCuries of Cs-137 and 40 milliCuries of Am:Be. Leak test results are pending. Radiation readings taken 1 meter away from the gauge indicated 50 microRem/hr and reading taken on contact were 1.5 milliRem/hr.

The gauge is currently stored at the licensee's facility awaiting transfer to the vendor for repair or disposal.

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Power Reactor Event Number: 40977
Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: D. GOMEZ
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/23/2004
Notification Time: 17:20 [ET]
Event Date: 08/23/2004
Event Time: 13:22 [EDT]
Last Update Date: 08/23/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
EUGENE COBEY (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

Event Text

EMERGENCY SIRENS DID NOT ACTIVATE

"At 1322 hours during routine testing it was discovered that Monroe County Emergency Sirens (24 of 96 total) did not activate from the Monroe County Emergency Command Center . The affected sirens were tested and restored to operable status from an alternate site at 1404 hours."

The NRC Resident Inspector was notified of this event by the licensee.

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Fuel Cycle Facility Event Number: 40978
Facility: HONEYWELL INTERNATIONAL, INC.
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
Comments: UF6 CONVERSION (DRY PROCESS)
Region: 2
City: METROPOLIS State: IL
County: MASSAC
License #: SUB-526
Agreement: Y
Docket: 04003392
NRC Notified By: M. GINZEL
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/23/2004
Notification Time: 17:37 [ET]
Event Date: 08/23/2004
Event Time: 09:00 [CDT]
Last Update Date: 08/23/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
PAUL FREDRICKSON (R2)
GARY JANOSKO (NMSS)

Event Text

EMERGENCY DIESEL GENERATOR START FAILURE

The emergency diesel-driven backup power generator failed to automatically start during routine weekly testing. Production was shutdown in the Feeds Material Building while resolving the problem. The start failure was determined to be the result of a failed electronic card associated with the fuel supply solenoid valve. Because the solenoid can be over-ridden, the diesel generator remains capable of manual start.

The licensee notified NRC Region 2 (J. Hensen) and local NRC Inspector (B. Bartlett).

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