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Event Notification Report for June 8, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/07/2004 - 06/08/2004

** EVENT NUMBERS **


40789 40795

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General Information or Other Event Number: 40789
Rep Org: ALABAMA RADIATION CONTROL
Licensee: ALABAMA DEPARTMENT OF TRANSPORTATION
Region: 1
City: GUNTERSVILLE State: AL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JAMES L. McNEES
HQ OPS Officer: ARLON COSTA
Notification Date: 06/03/2004
Notification Time: 08:37 [ET]
Event Date: 06/03/2004
Event Time: 06:30 [CDT]
Last Update Date: 06/04/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
KENNETH JENISON (R1)
THOMAS ESSIG (NMSS)
ROBERTA WARREN (TAS)

Event Text

ALABAMA AGREEMENT STATE REPORT ON STOLEN GAUGE

"At 4:07 p.m. Gary Brunson of the Alabama Department of Transportation called and reported that a Campbell Pacific gauge, Model MC3, Serial # M32076686 had been discovered stolen from their Guntersville, Alabama Project Office at approximately 6:30 this morning, Thursday, June 3, 2004. Brunson stated the device contained approximately 10 mCi of Cs-137 and 50 mCi of Am-241/Be.

"Brunson further stated he had delayed notifying the Agency until he had a copy of the police report from the Guntersville Police Department, who had investigated the theft. Someone had apparently climbed the fence, then broke into the testing lab building and took a nuclear density gauge and an air flow meter. A Troxler Model 4640 nuclear gauge was sitting beside the Campbell Pacific gauge but was not taken. Because both an air gauge and a density gauge were taken, Mr. Brunson believes the thief was taking something to sell and not taking something from which a radioactive source could be removed, or else they would have taken both nuclear gauges.

"Mr. Brunson agreed that if the device is not located by mid morning tomorrow, Friday, June 4, 2004, that he would work with the Agency to distribute an information notice on the missing device to area law enforcement agencies."

* * * UPDATE 1143 EDT ON 6/4/04 EMAIL FROM J. MCNEES TO W. GOTT * * *

The First Division Office located in Guntersville, AL reported the incident, but the project was in Huntsville, AL, which is part of the First Division.

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Power Reactor Event Number: 40795
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [ ] [ ] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: DAVID OAKES
HQ OPS Officer: MIKE RIPLEY
Notification Date: 06/07/2004
Notification Time: 20:57 [ET]
Event Date: 06/07/2004
Event Time: 14:58 [MST]
Last Update Date: 06/07/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
JACK WHITTEN (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 A/R Y 99 Power Operation 0 Hot Standby

Event Text

REACTOR TRIP DUE TO MAIN TURBINE ELECTRO-HYDRAULIC CONTROL SYSTEM FAILURE

"On June 7, 2004, at approximately 14:58 Mountain Standard Time (MST) while at 99% RTP [rated thermal power], Palo Verde Unit 3 experienced an apparent electro-hydraulic control (EHC) system fault resulting in Combined Intercept Valve (CIV) closure. This plant upset was followed by a Reactor Power Cutback System (RPCS) initiation. Several seconds later the Reactor automatically tripped on Lo DNBR from approximately 65% RTP. Unit 3 was at normal temperature and pressure prior to the trip. All CEAs [control rod assemblies] inserted fully into the reactor core. This was an uncomplicated reactor trip. No emergency classification was required per the Emergency Plan. No automatic ESF actuations occurred and none were required. Safety related buses remained energized during and following the reactor trip. The Emergency Diesel Generators did not start and were not required. The offsite power grid is stable. No significant LCOs have been entered as a result of this event. No major equipment was inoperable prior to the event that contributed to the event.

"Unit 3 is stabilized at normal temperature and pressure at approximately 565 degrees F and 2250 psia in Mode 3. The reactor coolant system remains in normal forced circulation with heat removal via the steam bypass control system to the condenser and feedwater from the non-essential auxiliary feedwater system. The event did not result in any challenges to fission product barriers and there were no adverse safety consequences as a result of this event. The event did not adversely affect the safe operation of the plant or the health and safety of the public.

"The Senior Resident Inspector was informed of the Unit 3 reactor trip and this notification. The Senior Resident Inspector was on-site at the time of the reactor trip."

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