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Event Notification Report for April 12, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/09/2004 - 04/12/2004

** EVENT NUMBERS **


40647 40649 40654 40660 40661 40662 40664 40665 40666 40667

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40647
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GARY R. BRINSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/05/2004
Notification Time: 20:46 [ET]
Event Date: 04/05/2004
Event Time: 19:16 [EDT]
Last Update Date: 04/09/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOEL MUNDAY (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

BRIEF LOSS OF NOAA WEATHER RADIO CAPABILITY

"Site experienced a momentary loss of the NOAA Weather Radio System from 1916 to 1918 EST. During the time that this system was out of service, a major loss of offsite communication capability is considered. Site emergency planning personnel were notified and will investigate this momentary loss. The system is in service and functioning properly."

The licensee notified both state/local agencies and will inform the NRC Resident Inspector.

* * * RETRACTION AT 1700 ON 4/9/04 RUSSELL TO GOTT * * *

"After further investigation, a determination has been made that there was no major loss of offsite notification capability of the Hatch Prompt Notification System (NOAA Weather Radio System). The momentary losses reported were caused by testing of the primary audio feed line utilizing a tone generator while investigating the loss of this feed. The secondary audio feed from Jacksonville NWS remained operable during the time of testing."

The Licensee notified the NRC Resident Inspector.

Notified R2DO (Decker)

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40649
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GREG JOHNSON
HQ OPS Officer: MIKE RIPLEY
Notification Date: 04/06/2004
Notification Time: 06:43 [ET]
Event Date: 04/06/2004
Event Time: 00:10 [EDT]
Last Update Date: 04/09/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JOEL MUNDAY (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

MOMENTARY LOSS OF NOAA WEATHER RADIO SYSTEM

"The Plant Site detected a momentary loss of the NOAA Weather Radio System from 00:10 am on 04/06/04 to 00:14 am on 04/06/04. During this time interval of inoperability for this system, a major loss of off site notification capability is considered. Site Emergency Planning personnel were notified and will investigate this momentary loss of system capability. The NOAA Weather Radio System is currently in service and functioning properly."

The licensee will notify the NRC Resident Inspector.

* * * RETRACTION AT 1700 ON 4/9/04 RUSSELL TO GOTT * * *

"After further investigation, a determination has been made that there was no major loss of offsite notification capability of the Hatch Prompt Notification System (NOAA Weather Radio System). The momentary losses reported were caused by testing of the primary audio feed line utilizing a tone generator while investigating the loss of this feed. The secondary audio feed from Jacksonville NWS remained operable during the time of testing."

The Licensee notified the NRC Resident Inspector.

Notified R2DO (Decker)

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General Information or Other Event Number: 40654
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: OWENSBY AND KRITIKOS INC
Region: 4
City: GRETNA State: LA
County:
License #: LA-2243-L01
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: BILL GOTT
Notification Date: 04/07/2004
Notification Time: 21:45 [ET]
Event Date: 04/07/2004
Event Time: 20:00 [CDT]
Last Update Date: 04/07/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BLAIR SPITZBERG (R4)
C.W. (BILL) REAMER (NMSS)
DONNA-MARIE PEREZ (TAS)

Event Text

LOUISIANA AGREEMENT STATE REPORT - LOST RADIOGRAPHY CAMERA IN THE GULF OF MEXICO

While passing a SPEC 150 Industrial Radiography Camera from a boat to an Apache Corporation Petroleum platform in the Gulf of Mexico, the radiography camera fell into the water. The water depth is 60 to 70 feet and is located approximately 50 to 70 miles from the coast of LA. The lost camera was a SPEC 150 S/N 223 with a 24 Curie Ir-192 source S/N 12433B. The radiography camera was in a Type B shipping container. The licensee plans on using divers to retrieve the radiography camera.

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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.

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Power Reactor Event Number: 40661
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: DARIN RODABAUGH
HQ OPS Officer: BILL GOTT
Notification Date: 04/09/2004
Notification Time: 17:14 [ET]
Event Date: 04/09/2004
Event Time: 12:30 [PDT]
Last Update Date: 04/09/2004
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
2 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION OF CHEMICAL SPILL

"On 419/04 at 1230 hours, Energy Northwest contacted Washington State Emergency Management Division (1-800-258-5990) to report a spill of pHreeGuard-4500 (a water treatment scale inhibitor) at the Columbia Generating Station Circulating Water Pump House. Washington State Emergency Management Division assigned Incident No. 04-0721 to this report. It is estimated as much as 60 gallons of the water treatment chemical could have been released to the concrete tank pedestal, asphalt apron, and adjoining soil over a period of several hours from a leaking expansion joint at the tank outlet. The leak was detected at about 0830 hrs. The leaking material is captured and redirected to the Circulating water basin. Washington State Emergency Management Division is relaying the information to the on-call responder in the Washington State Department of Ecology's Central Region Office.

" This event is being reported under 10 CFR 50.72 (b)(2)(xi), any event or situation, related to the health and safety of the public or on-site personnel, or protection if the environment, for which a news release is planned or notification to other government agencies has been or will be made."

The Licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 40662
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: ROBERT PACE
HQ OPS Officer: BILL GOTT
Notification Date: 04/09/2004
Notification Time: 17:33 [ET]
Event Date: 04/09/2004
Event Time: 16:30 [EDT]
Last Update Date: 04/09/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
LAWRENCE DOERFLEIN (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 93 Power Operation 93 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF POWER TO EOF

At 1630 on 4/9/04, it was discovered the Emergency Operating Facility had lost power. It is still without power. The cause was the backup facility diesel generator started and attempted to power the facility while normal offsite power was still applied. The electrical transfer switch was damaged. The time to repair is unknown. A space normally used as a media center is used as an alternate EOF.

The Licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 40664
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: JOEL BARNETT
HQ OPS Officer: BILL GOTT
Notification Date: 04/10/2004
Notification Time: 16:54 [ET]
Event Date: 04/10/2004
Event Time: 11:50 [PDT]
Last Update Date: 04/10/2004
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):
BLAIR SPITZBERG (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 97 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO LOSS OF BOTH MAIN FEEDWATER PUMPS

San Onofre Unit 2 was manually tripped from 97% power due to the loss of feed water pumps. After both feedwater pumps tripped, the operators manually tripped the reactor. Both trains of the emergency feed water system actuated as expected due to the initial power level. The plant is stable at NOP/NOT. The cause of the feed water pump trips is being evaluated. All control rods fully inserted and all safety systems worked properly. The steam generators are discharging steam to the main condenser using the turbine bypass valves. AFW pumps are running to maintain steam generator water levels.

The Licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 40665
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF MARTIN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 04/11/2004
Notification Time: 04:43 [ET]
Event Date: 04/11/2004
Event Time: 00:23 [EDT]
Last Update Date: 04/11/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
LAWRENCE DOERFLEIN (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling

Event Text

PLANT HAD A VALID ESF SIGNAL TO START 1C EMERGENCY DIESEL GENERATOR

"THIS IS AN 8-HOUR NOTIFICATION TO REPORT A VALID ESF SIGNAL TO START 1C EMERGENCY DIESEL GENERATOR THAT OCCURRED ON 4/11/04 AT 0023. Salem Unit 1 is defueled. The spent fuel pool cooling system is providing decay heat removal. Spent fuel pool temperature is being maintained at 106 degrees. RCS temperature is 75 degrees. The RCS is vented to atmosphere. Reactor level is 97.5 feet. 1C emergency diesel generator is cleared and tagged for maintenance. 13 station power transformer was returned to service on 4/10/04 at 2347. The operating crew briefed expected response and abnormal procedures if the 4kv vital bus did not transfer during the retest of 13 station power transformer. Operations successfully retested 1A and 1B 4kv vital bus transfer from 14 station power transformer to 13 station power transformer and back to 14 station power transformer in accordance with station operating procedures. Operations attempted to retest the 1C 4kv vital bus transfer from 14 station power transformer to 13 station power transformer. When the operator attempted to close 13CSD infeed breaker, the 14CSD infeed breaker opened as designed, but 13CSD breaker failed to close. The 1C 4kv vital bus deenergized due to both offsite power source infeed breakers opening and 1C emergency diesel generator unavailable. An ESF signal to start the 1C emergency diesel generator was provided by the safeguards equipment cabinet {SEC}. Since the 1C emergency diesel was cleared and tagged for maintenance, it did not start. The cause of the failure to transfer is not known at this time. The operating crew implemented the appropriate abnormal operating procedures for the de-energized 1C 4kv vital bus. Operator and plant response was as expected. Decay heat continues to be removed by the spent fuel pool cooling system. Outage incident response team is evaluating and troubleshooting the cause of the loss of power to 1C 4kv vital bus. ORAM risk remains yellow. There were no personnel injured during the event."

The licensee will inform Lower Alloways Creek (LAC) Township and the NRC Resident Inspector.

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Power Reactor Event Number: 40666
Facility: FARLEY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: RICK LULLING
HQ OPS Officer: DICK JOLLIFFE
Notification Date: 04/11/2004
Notification Time: 12:47 [ET]
Event Date: 04/11/2004
Event Time: 11:05 [CDT]
Last Update Date: 04/11/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
THOMAS DECKER (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 0 Startup 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP FOR UNKNOWN REASONS DURING PLANT STARTUP

At 1247 EDT on 04/11/04, the licensee reported that at 1105 CDT on 04/11/04, control room operators were performing low power physics testing in accordance with FNP-2-STP-101 during startup of Unit 2 following a refueling outage. With reactor power at 10E-8 amps in the intermediate range in Mode 2, the 'B' reactor trip breaker opened for unknown reasons. All control rods inserted completely. The licensee is investigating the cause. The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 40667
Facility: FARLEY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: SCOTT SMITH
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/12/2004
Notification Time: 05:25 [ET]
Event Date: 04/12/2004
Event Time: 03:47 [CDT]
Last Update Date: 04/12/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
THOMAS DECKER (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 0 Startup 0 Hot Standby

Event Text

UNIT 2 EXPERIENCED A REACTOR TRIP DURING STARTUP DUE TO AN INVALID SR TRIP SIGNAL

"Unit 2 reactor tripped during low power physics testing. Trip appeared to be from an invalid source range [SR] trip signal in one train of solid state protection system. All systems responded properly. The Unit is currently stable in mode 3."

The licensee informed the NRC Resident Inspector.

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