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Event Notification Report for August 23, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/20/2004 - 08/23/2004

** EVENT NUMBERS **


40967 40969 40970 40973 40974

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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 The IVB catheter was immediately withdrawn and placed in the Novoste emergency plexiglass storage safe and then in the IVB storage room.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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Other Nuclear Material Event Number: 40969
Rep Org: TACOM
Licensee: US ARMY
Region: 4
City: FAIRBANKS State: AK
County:
License #: 12-00722-16
Agreement: N
Docket:
NRC Notified By: T. GIZICKI
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/20/2004
Notification Time: 17:32 [ET]
Event Date: 08/13/2004
Event Time: 01:30 [YDT]
Last Update Date: 08/20/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(4) - FIRE/EXPLOSION
Person (Organization):
GREG PICK (R4)
BRENT CLAYTON (R3)
GARY JANOSKO (NMSS)

Event Text

US ARMY RADIOACTIVE MATERIAL INVOLVED IN A FIRE.

On August 13, 2004 and aircraft hanger located on Fort Wainwright, East of Fairbanks, burned to the ground. Three chemical detectors containing a total activity of 70 millicuries of Nickel-63 were stored inside a metal wall locker within the aircraft hanger. The aircraft hanger has been cordoned off and a US. Army Radiation Safety Officer (RSO) is on the scene. One ICAM, and Two M22 Acada chemical detectors were stored in the metal wall locker.

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Power Reactor Event Number: 40970
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RONALD FRY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 08/20/2004
Notification Time: 17:48 [ET]
Event Date: 08/20/2004
Event Time: 12:15 [EDT]
Last Update Date: 08/20/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
JOHN WHITE (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

RAILROAD ACCESS PROCESS RADIATION MONITORS ACTUATION CAPABILITY WAS INADVERTENTLY DEFEATED

At 12:15 PM on 8/20/04, it was discovered that actions performed on 7/16/04 in support of Dry Fuel Storage activities to defeat the Railroad Access Area Radiation Monitor alarm horn had also defeated the actuation capability of the Railroad Access Process Radiation monitors. Per Technical Specifications, the process monitors are required to be operable "during movement of irradiated fuel assemblies within the Railroad Access Shaft, and above the Railroad Access Shaft with the Railroad Access Shaft Equipment Hatch open." Contrary to the Tech Spec requirement, two loaded Dry Fuel Storage Casks were lowered in the Railroad Shaft, one on 8/2/04 and the second on 8/16/04, with the radiation monitors inoperable. During this period the automatic isolation and re-alignment of Reactor Building Zone lll, automatic start of Reactor Building Recirculation Fans, and the automatic starts of SGTS and CREOASS would not have actuated from a HI-HI Radiation condition in the Railroad Access Shaft. Actual radiological conditions observed during the transfer of the casks in the railroad shaft would not have resulted in the need for system actuation. All other instruments in the Reactor Building ventilation system which actuate these systems were operable as required by Tech Specs. The jumpers which defeated the actuation capability were removed on 8/20/04 at 1400 [hrs.].

This event is considered reportable under 50.72(b)(3)(v)(C) as a loss of safety function.

The NRC Resident Inspector was notified.

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Power Reactor Event Number: 40973
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [ ] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: WILLIAM DALTON
HQ OPS Officer: GERRY WAIG
Notification Date: 08/22/2004
Notification Time: 01:12 [ET]
Event Date: 08/21/2004
Event Time: 20:00 [EDT]
Last Update Date: 08/22/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JOHN WHITE (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 90 Power Operation 90 Power Operation

Event Text

ACCIDENT MITIGATION - HIGH PRESSURE COOLANT INJECTION SYSTEM FLOW CONTROLLER MALFUNCTION

The following information was provided by the licensee via facsimile:

"[The] High Pressure Coolant Injection (HPCI) flow controller malfunctioned resulting in the inability of the HPCI to perform its safety function as a single train system under 10 CFR 50.72 (b)(3)(v). The failure mode for the flow controller is suspected to be a power supply issue, however, the cause has not been confirmed at this time. Unit 2 is in a 14 day technical specification [T.S.] limitation which if exceed results in a unit shutdown ( T.S. 3.5.1 Condition C)."

The licensee has notified the NRC Resident Inspector.

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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: 08/22/2004
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.

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