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Event Notification Report for October 28, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/27/2004 - 10/28/2004

** EVENT NUMBERS **


41146 41150 41151 41152 41153 41154

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General Information or Other Event Number: 41146
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: SIEMENS MEDICAL SOLUTIONS USA
Region: 4
City: BELLEVUE State: WA
County:
License #: WN-I030-1
Agreement: Y
Docket:
NRC Notified By: ARDEN SCROGGS
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/25/2004
Notification Time: 19:10 [ET]
Event Date: 10/21/2004
Event Time: 15:00 [PDT]
Last Update Date: 10/25/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GARY SANBORN (R4)
ELMO COLLINS (NMSS)
JIM WHITNEY (TAS)
CNCS (FAX)

Event Text

AGREEMENT STATE REPORT - STOLEN RADIOACTIVE SOURCES

Received via email from Washington Department of Health, Office of Radiation Protection

"The licensee possesses and uses sealed sources for calibrating nuclear medical instrumentation. Two sources, Cobalt-57 and Americium-241 each assay activity of about 74 megabecquerel (2 millicurie), were contained in lead pigs kept in the service technician's toolbox. The toolbox was reported as "probably" locked. The toolbox was not secured in the vehicle. The vehicle was parked in the driveway of the technician's home. The toolbox and two boxes of spare parts were reported stolen. The theft was reported to Liberty Lake Police Department between 3:00 and 4:00 p.m. [PDT]."

Washington Event Report #: WAC 246-221-240

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Power Reactor Event Number: 41150
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: CLAY WILLIAMS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/27/2004
Notification Time: 13:05 [ET]
Event Date: 10/26/2004
Event Time: 13:56 [PDT]
Last Update Date: 10/27/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
GARY SANBORN (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation
3 N N 0 Refueling 0 Refueling

Event Text

RANDOM FITNESS FOR DUTY TEST

Illegal drug use was detected during a random drug test of a non-licensed employee. The employee's access to the plant has been terminated. Contact the HOO for additional details.

The NRC Resident Inspector was notified by the licensee.

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Power Reactor Event Number: 41151
Facility: MCGUIRE
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF THOMAS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/27/2004
Notification Time: 13:55 [ET]
Event Date: 10/19/2004
Event Time: 20:20 [EDT]
Last Update Date: 10/27/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
BRIAN BONSER (R2)

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

INVALID TURBINE DRIVEN AUXILIARY FEEDWATER ACTUATION

"On October 19, 2004, McGuire Nuclear Station Unit 2 experienced an inadvertent actuation of the Turbine Driven Auxiliary Feedwater (TDCA) Pump. This event occurred when the steam supply valve to the pump failed open due to low pressure in the nitrogen supply to the valve's actuator. Further evaluation determined that the inadvertent actuation of the TDCA Pump was not in response to actual plant conditions or parameters satisfying the requirements for actuation of the pump. Since the TDCA Pump was not started in response to a valid signal, this represented an invalid actuation reportable per the requirements of 10 CFR 50.73 (a) (2) (iv) (A). However, as per 10 CFR 50.73(a)(1), McGuire is providing a telephone notification of this invalid actuation instead of submitting a written LER.

"The following additional information is being provided as part of the telephone notification of this event:
- The Unit 2 TDCA Pump actuated and injected water into all four of the Unit 2 Steam Generators
- The actuation of the Unit 2 TDCA Pump was successful and complete."

The licensee stated the total injection time was approximately 16 minutes and that a very small power increase was observed during the event.

The NRC Resident Inspector has been notified by the licensee.

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Power Reactor Event Number: 41152
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: GARY HARRINGTON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/27/2004
Notification Time: 15:21 [ET]
Event Date: 09/15/2004
Event Time: 09:11 [CDT]
Last Update Date: 10/27/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
RONALD GARDNER (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

INVALID ACTUATION OF CONTAINMENT ISOLATION VALVES

"In accordance with the requirements and guidance of 10 CFR 50.73(a)(1), a telephonic report of an invalid signal affecting containment isolation valves in more than one system is being submitted. This report is being made under 10 CFR 50.73(a)(2)(iv)(A), automatic actuation of a system listed in paragraph (a)(2)(iv)(B), in lieu of a written LER.

"At 0911 hours, on 09/15/2004, while operating at full power, the plant experienced a loss of power to eight process radiation monitors. The loss of power was caused by the failure of an internal radiation monitor system power supply, PS-100. The affected radiation monitors actuated, where applicable, their associated safety and non-safety related components. The safety related components affected included eight containment isolation valves and the plant's auxiliary building special ventilation system equipment. The containment isolation valves were:

"- 4 steam generator blowdown system isolation valves (inside and outside containment isolation valves for each of the plant's two, 'A' and 'B' steam generators).

"- 4 steam generator sampling system isolation valves (inside and outside containment isolation valves for each of the plant's steam generators' sample system lines).

"All the components affected operated as designed. The effect on plant operation was not significant. The power supply was replaced and the ventilation systems, sampling and blowdown piping systems were realigned to normal.

"The power supply failure and subsequent closure signal to the noted containment isolation valves is an example of an invalid signal. No full or partial containment isolation signal was generated. None of the valve closures were needed to mitigate the consequences of the power supply failure. The investigation to determine the cause of the power supply failure continues."

The licensee has informed the NRC Resident Inspector.

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Other Nuclear Material Event Number: 41153
Rep Org: DEPARTMENT VETERANS AFFAIRS
Licensee: DEPARTMENT VETERANS AFFAIRS
Region: 4
City: NEW ORLEANS State: LA
County:
License #: 03-23853-01VA
Agreement: Y
Docket:
NRC Notified By: GARY WILLIAMS
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/27/2004
Notification Time: 18:16 [ET]
Event Date: 10/26/2004
Event Time: [CDT]
Last Update Date: 10/27/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
GARY SANBORN (R4)
PATRICIA HOLAHAN (NMSS)
RONALD GARDNER (R3)

Event Text

LOST RADIOACTIVE MATERIAL

RSO for the VA Medical Center, New Orleans, LA was notified at 0900 CDT on 10/27/04 of a missing shipment of I-125 (10 millicuries) that had been received by that facility on 10/26/04. The RSO is conducting an investigation into the missing radioactive material.

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Power Reactor Event Number: 41154
Facility: CATAWBA
Region: 2 State: SC
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GLENN HORNE
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/28/2004
Notification Time: 03:29 [ET]
Event Date: 10/28/2004
Event Time: 00:52 [EDT]
Last Update Date: 10/28/2004
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):
BRIAN BONSER (R2)

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

Event Text

MANUAL REACTOR TRIP AFTER SHUTDOWN BANK DROPPED INTO CORE

"At 0052 on 10/28/04 the Unit 2 reactor was manually tripped after an electrical fault caused Shutdown Bank D control rods to drop into the core. An automatic start of the Auxiliary Feedwater system occurred when water levels in all four Steam Generators reduced to the Lo-Lo level setpoint. A letdown isolation occurred on Lo Pressurizer level resulting from the cooldown of the primary system after the Auxiliary Feedwater system start. Reactor Coolant system temperature has been recovered and the plant has been stabilized at Hot Shutdown conditions."

The licensee stated that there were no complications during the trip. All systems functioned as required. No significant safety systems were out of service when the trip occurred. No primary or secondary relief valves lifted during the transient. Decay heat is currently being removed using aux feedwater to the steam generators steaming to the main condenser. Tave dropped to a low point of 540 degrees F during the transient. The reactor was manually tripped in approximately 18 seconds after the shutdown bank dropped. The licensee plans to remain in mode 3.

The licensee will notify the NRC Resident Inspector. The licensee will also notify state and local authorities in North and South Carolina.

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Friday, March 30, 2012