| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/08/2004 - 04/09/2004 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 40645 | Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: LAMPKIN CONSTRUCTION COMPANY
Region: 1
City: VICKSBURG State: MS
County:
License #: MS-964-01
Agreement: Y
Docket:
NRC Notified By: Mark Langston, MS DRH
HQ OPS Officer: DICK JOLLIFFE | Notification Date: 04/05/2004
Notification Time: 16:41 [ET]
Event Date: 04/05/2004
Event Time: 13:30 [CDT]
Last Update Date: 04/05/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LAWRENCE DOERFLEIN (R1)
SCOTT MOORE (NMSS)
DONNA-MARIE PEREZ (TAS)
| Event Text MS AGREEMENT STATE REPORT - STOLEN TROXLER MOISTURE DENSITY GAUGE
At 1641 EDT on 04/05/04, a MS Division of Radiological Health representative reported that at 1330 CDT on 04/05/04, a representative of Lampkin Construction Company, Vicksburg, MS, reported that between 1700 CDT on 04/02/04 and 0800 CDT on 04/05/04 a Troxler Moisture Density Gauge, locked in its transport case was stolen from a storage building at their office in Vicksburg, MS. A window had been broken and a door was forced open at the storage building. The Troxler Gauge, Model #3430, Serial #22349 contains an 8 millicurie Cs-137 source and a 40 millicurie Am-241-Be source. The licensee notified the MS Emergency Management Agency and the Warren County Sheriff. The licensee is planning to issue a press release. |
| Power Reactor | Event Number: 40655 | Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PATRICK LEAHY
HQ OPS Officer: BILL GOTT | Notification Date: 04/08/2004
Notification Time: 12:16 [ET]
Event Date: 04/08/2004
Event Time: 08:45 [EDT]
Last Update Date: 04/08/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
THOMAS DECKER (R2)
|
| 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 OFF SITE NOTIFICATION
"On 04/08/04 at 0845 EDT, 24-hour notification was made to the Tennessee Department of Environment and Conservation (Division of Water Pollution Control) to report a potential upset of the Sequoia (SQN) National Pollution Elimination Discharge System Permit. Additional follow up evaluation is underway.
"On 04/07/04 at approximately 0830, a field report was received that a possible break or breach in one of the two 15 feet diameter out fall discharge diffuser pipes where the plant discharge returns to the Tennessee River. SQN inserted a 'stop log' gate in the suspected discharge path and confirmed that the #1 (South) diffuser pipe is breached. The breached portion of the pipe is underwater on the river bottom approximately 100 feet from shore.
"Concurrently, SQN placed both cooling towers in service with six of the available seven cooling tower lift pumps in service to minimize the potential for, or any adverse impacts from, exceeding any of the site's discharge limits. Repair actions for the pipe including initial inspections are in progress with divers on site at this time.
"The Site Environmental Group, in conjunction with the Tennessee Valley Authority Corporate Environmental Group, are evaluating any potential thermal non-compliance issues."
The Licensee does not consider this to be a security issue.
The Licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40656 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: STEVE FULLER
HQ OPS Officer: BILL GOTT | Notification Date: 04/08/2004
Notification Time: 12:58 [ET]
Event Date: 04/08/2004
Event Time: 12:55 [EDT]
Last Update Date: 04/08/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
LAWRENCE DOERFLEIN (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 PRESS RELEASE REGARDING LAW SUITE SETTLEMENT
"Oyster Creek station is making a press release regarding a settlement with the State of New Jersey related to and environmental event which occurred on September 23, 2002. The press release contains the following information:
"'FORKED RIVER, NJ. - The Oyster Creek Generating Station and the State of New Jersey agreed today to settle and resolve all matters related to the Sept. 23, 2002, water permit violation at the station. Under the terms of the agreement reached with the New Jersey Department of Environmental Protection and the Attorney General's office, Oyster Creek will pay a total of $1 million that will be distributed to several state organizations and environmental causes.
"'The settlement resolves the 2002 event that resulted in the loss of nearly 6,000 fish. The event occurred because the station equipment was out of service for planned maintenance which caused the discharge water temperatures to rise resulting in the fish kill.'"
The Licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40657 | Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN MILLIFF
HQ OPS Officer: BILL GOTT | Notification Date: 04/08/2004
Notification Time: 14:06 [ET]
Event Date: 04/08/2004
Event Time: 09:44 [CDT]
Last Update Date: 04/08/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
BLAIR SPITZBERG (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 OFFSITE NOTIFICATION OF A FATALITY
"The purpose of this report is to notify the NRC of a fatality involving a contract worker at the South Texas Project. Specifically, at 0810 (CDT), the South Texas Project Unit 1 Control Room was notified that an individual located outside of Unit 2 in a non-radiological area had lost consciousness. The site emergency medical team responded and an ambulance was requested at 0812. At 0836, the worker left the site in an ambulance. At 0944, South Texas Project was notified that the individual passed away at Matagorda General Hospital. This fatality was the result of a medical emergency and was not occupationally related. South Texas Project has notified OSHA of the fatality. A press release is not planned."
The individual was a contractor working in a temporary tool storage area outside Unit 2.
The Licensee notified the NRC Resident Inspector. |
| General Information or Other | Event Number: 40658 | Rep Org: ABB, Inc
Licensee: ABB, Inc
Region: 1
City: Coral Springs State: FL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROY BALL
HQ OPS Officer: DICK JOLLIFFE | Notification Date: 04/08/2004
Notification Time: 15:49 [ET]
Event Date: 04/08/2004
Event Time: 15:00 [EDT]
Last Update Date: 04/08/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
| Person (Organization):
Tom Decker (R2)
Vern Hodge (NRR)
| Event Text INFORMATION CALL - POTENTIAL 10CFR PART 21
At 1549 EDT on 04/08/04, the Quality Manager of ABB, Inc, Coral Springs, FL, reported that he has determined that a potential defect exists regarding the potential overheating of overcurrent instantaneous units in protective relays in high power transformers, generators, and circuit breakers in various electrical power systems. The Quality Manager plans to determine the list of equipment affected and power plants and customers affected by this potential defect, including Duke Power Corporation, and provide written notification to the NRC of this potential defect within the next 2 to 4 weeks. |
| Power Reactor | Event Number: 40659 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ANTHONY CHITWOOD
HQ OPS Officer: BILL GOTT | Notification Date: 04/08/2004
Notification Time: 17:02 [ET]
Event Date: 04/08/2004
Event Time: 13:00 [PDT]
Last Update Date: 04/08/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
BLAIR SPITZBERG (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text DEGRADED CONDITION - GREATER THAN ONE PERCENT OF STEAM GENERATOR TUBES DEFECTIVE
"On April 08, 2004, during the Unit 1 twelfth refueling outage (1R12), analysis of eddy current data on [Steam Generator] SG 1-4 indicated that greater than one percent of the total tubes inspected in SG 1-4 were defective. Approximately ninety (90) defective tubes in SG 1-4 were detected and are being plugged. Most of the pluggable indications are due to circumferential primary water stress corrosion cracking in the Rows 5 to 8 U-bend region. Results of the SG tube inspection fall into Category C-3, which requires a four-hour non-emergency report in accordance with Technical Specification (TS) Table 5.5.9-2 and 10 CFR 50.72(b)(3)(ii) (an 8-hour requirement replacing the former (b)(2)(iii)(C), 4-hour requirement).
"An NRC teleconference in accordance with TS 5.6.10.d to report the results of the voltage-based repair criteria implemented for the tube support plate intersections is currently scheduled for Wednesday April 14, 2004, at 1300 EDT.
"A Special Report in accordance with TS 5.6.10.a and e will be submitted prior to returning Unit 1 to power operation.
"A Licensee Event Report in accordance with 10 CFR 50.73(a)(2)(v)(C) will be submitted within 60 days."
The Licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40660 | Facility: COOK
Region: 3 State: MI
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DEAN BRUCK
HQ OPS Officer: ARLON COSTA | Notification Date: 04/09/2004
Notification Time: 01:47 [ET]
Event Date: 04/08/2004
Event Time: 22:16 [EDT]
Last Update Date: 04/09/2004 | 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):
BRENT CLAYTON (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 50 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DUE TO A FEEDWATER FLOW TRANSIENT
"On April 8, 2004, at about 2215, Cook Unit 2 experienced a feedwater flow transient resulting in oscillating flows to Nr. 22, 23, & 24 steam generators. At 2216, the high level turbine trip setpoint was reached in Nr. 24 steam generator resulting in [a] main turbine trip signal. The main turbine trip signal caused a turbine trip resulting in an RPS [Reactor Protection System] actuation (reactor trip). At the time of the RPS actuation, Cook Unit 2 was at about 50 percent power and lowering power to facilitate turbine control maintenance. The cause of [the] feedwater transient is unknown and under investigation at this time.
"Following the RPS actuation, the Auxiliary Feedwater System automatically started on low-low Steam Generator levels. This constituted a valid unplanned actuation of the Engineered Safeguards Feature (ESF). Operators stabilized the Plant using Condenser Steam Dumps and Auxiliary Feedwater. Unit 2 is currently in Mode 3 with Reactor Coolant System conditions stable at normal operating temperature and pressure. No other ESF systems actuated.
"During the response to the RPS actuation by the operating crew, it was noted that the Main generator output breaker remained closed requiring a manual trip signal to open the output breakers. Another condition identified was a leak from a crack in the side of the 'C' South condenser near the condensate booster pumps' recirculation line inlet. The operating crew removed the condensate booster pumps from service to stop condenser hotwell outleakage; the main condenser remains in service. The causes for the above items are unknown and [are] under investigation at this time."
All control rods fully inserted into the core in response to the automatic reactor trip and heat sink is currently been maintained using Auxiliary Feedwater Pumps and the Main Steam Dumps. Except as noted, all other systems functioned as required.
The licensee notified the NRC Resident Inspector. | |