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Event Notification Report for August 29, 2003

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/28/2003 - 08/29/2003

** EVENT NUMBERS **


40102 40110 40111 40113 40114

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General Information or Other Event Number: 40102
Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: PHELPS-DODGE, INC.
Region: 4
City: BAGHDAD State: AZ
County:
License #: AZ-13-005
Agreement: Y
Docket:
NRC Notified By: AUBREY V. GODWIN
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/25/2003
Notification Time: 18:22 [EST]
Event Date: 08/25/2003
Event Time: 09:30 [MST]
Last Update Date: 08/25/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL RUNYAN (R4)
E. WILLIAM BRACH (NMSS)

Event Text

3 CURIE COBALT-60 SOURCE DISCOVERED DISCONNECTED

"At approximately 9:30 AM MST August 25, 2003, the Agency was informed by the Licensee that they had discovered a source had disconnected from a rod in the Process Leaching Vessel. The source contains 3 Curies of Cobalt 60 as of October 2001. The licensee has made measurements and determined the radiation levels outside the vessel are not excessive. The device is a ThermoMeasure Tech Model 5031 L SN B43. Even though the source is disconnected, because it is trapped within a sealed source guide tube, it is still secure from inadvertent removal. The estimated date for full repair is October 21, 2003. Repair will be made by the device manufacturer. The Licensee has agreed not to drain the vessel without Agency notice and approval.

"The Agency continues to investigate this incident."

The Agency is: ARIZONA RADIATION REGULATORY AGENCY.

First Notice: 03-13

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Power Reactor Event Number: 40110
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: MIKE BEARD
HQ OPS Officer: BILL GOTT
Notification Date: 08/28/2003
Notification Time: 11:27 [EST]
Event Date: 08/28/2003
Event Time: 07:50 [CDT]
Last Update Date: 08/28/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MICHAEL RUNYAN (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

Event Text

LOSS OF POWER TO EMRGENCY OPERATIONS FACILITY

"The Emergency Operations Facility (EOF) for Grand Gulf was lost when power was removed from the facility and the EOF diesel generator failed to start. Power had to be removed due to the loss of one phase of the local power supply. Actual plant operations are not affected. The power phase problem and failure of the EOF diesel generator to start are being investigated at this time. The Backup EOF is available if needed."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 40111
Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: NORENA ROBINSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 08/28/2003
Notification Time: 12:08 [EST]
Event Date: 08/28/2003
Event Time: 07:00 [CDT]
Last Update Date: 08/28/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
MICHAEL RUNYAN (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

Event Text

FITNESS FOR DUTY

"At 0700 a non-licensed contract supervisor failed a for cause fitness-for-duty test. The individual tested positive for alcohol, and the results of the drug portion of the test have not yet been received.

"Immediate Corrective Action: The individual's unescorted site access was denied at 0717 CST on August 28, 2003, and appropriate notifications have been completed in accordance with the station's Fitness-For-Duty Program.

"Safety Significance: None. There is no reason to believe there have been any adverse consequences from this event. The employee had been cleared for unescorted access; however, had never obtained his badge for access to the protected area of the site. This event is not considered to have impacted operation of the plant in any way.

"The licensee informed the NRC Resident Inspector.

"Contact the Headquarters Operations Officer for additional details."

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Power Reactor Event Number: 40113
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF EPPERSON
HQ OPS Officer: NATHAN SANFILIPPO
Notification Date: 08/28/2003
Notification Time: 17:01 [EST]
Event Date: 08/28/2003
Event Time: 16:04 [EDT]
Last Update Date: 08/28/2003
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CAROLYN EVANS (R2)
JAMES LYONS (NRR)
NADER MAMISH (IRO)
LUIS REYES (R2)
TERRY REIS (NRR)
BILL BORCHARDT (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A Y 100 Power Operation 0 Hot Standby

Event Text

ALERT DECLARED DUE TO REACTOR PROTECTION SYSTEM FAILURE

At 1618 EDT on 08/28/03, an Alert was declared at Sequoyah Unit 1 due to a failure of the Reactor Protection System (RPS) to auto-trip the reactor following a turbine trip. Turbine oil trip testing was in progress when at 1604, the main turbine tripped. The reactor trip breakers were opened by manual operator action approximately 20 seconds after the valid reactor trip signal. Following the trip, all systems operated as required. The main steam isolation valves were manually closed based on indication of steam flow and a throttled steam dump valve. No primary system or steam generator safety valves opened. The unit is currently stable with temperature controlled using atmospheric relief valves. The Auxiliary Feedwater System received an auto-start signal and successfully operated. All control rods were fully inserted into the core. There was no release of radioactive material.

The licensee has initiated an investigation into the cause of the incident.

The NRC Resident Inspector and the State of Tennessee were notified by the licensee. The NRC notified FEMA (Steiner), DOE (Morroni), USDA (Beers-Block), HHS (Williams), DHS (Glick), and DOT/EPA/NRC (Threatt).

The NRC entered monitoring phase of normal mode with Region 2 in the lead at 1735 EDT.

* * * UPDATE ON 08/28/03 AT 2044 EDT, KEVIN WILKES TO NATHAN SANFILIPPO * * *

At 2030 EDT on 08/28/03, the licensee terminated the Alert at Sequoyah Unit 1. The reactor is stable and in Mode 3, Hot Standby. This termination is based upon containment integrity, Emergency Core Cooling System and Engineered Safety Features operability, availability of heat sink, onsite and offsite electrical system and Emergency Diesel Generator operability, radiation monitor operability, availability of technical support personnel, and activation of a forced outage recovery team. Reactor coolant samples were taken, which showed no increase in activity.

The NRC notified FEMA (Austin), DOE (Morroni), USDA (Beers-Block), HHS (Hogan), DHS (Van Buskirk), and DOT/EPA/NRC (White).

The NRC exited monitoring phase of normal mode at 2045 EDT.

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Power Reactor Event Number: 40114
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE LEE
HQ OPS Officer: GERRY WAIG
Notification Date: 08/29/2003
Notification Time: 05:40 [EST]
Event Date: 08/29/2003
Event Time: [EDT]
Last Update Date: 08/29/2003
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):
CAROLYN EVANS (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 95 Power Operation 0 Hot Standby

Event Text

CATAWBA UNIT 1 AUTOMATIC REACTOR TRIP DUE TO REACTOR PROTECTION SYSTEM ACTUATION

Unit 1 tripped on Over Temperature Delta T (OTDT) protection. Channel 1 Over Temperature Delta T was in trip due to a reactor coolant hot leg temperature problem. Per Technical Specifications, this required Channel 1 OTDT to be placed in the tripped condition. Channel 2 Pressurizer pressure failed low at 0203 EDT. This input caused channel 2 Over Temperature Delta T to enter a trip condition. With 2 of 4 Over Temperature Delta T channels in the trip condition, a reactor trip signal was generated by the reactor protection system resulting in an automatic reactor trip. After the reactor trip occurred, RCS (Reactor Coolant System) letdown was lost on the chemical and volume control system due to low Pressurizer level (~17%). 1NV-1A (Reactor Coolant Letdown Isolation Valve) did not close as required. This necessitated the alignment of the excess letdown flowpath to maintain the desired Pressurizer level. ESF functions operated as designed. Auxiliary feedwater auto started and main feedwater isolated as designed.

All control rods fully inserted on the reactor trip. Station service electrical systems, emergency diesel generators, and ESF equipment are available. Catawba Unit 2 was unaffected by the trip of Unit 1.

The licensee has notified the NRC Resident Inspector and will be notifying state and local officials.

Page Last Reviewed/Updated Friday, March 30, 2012
Friday, March 30, 2012