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Event Notification Report for June 24, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/23/2005 - 06/24/2005

** EVENT NUMBERS **


41787 41788 41789 41790 41791 41792

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Power Reactor Event Number: 41787
Facility: LASALLE
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JOHN WASHKO
HQ OPS Officer: JOHN KNOKE
Notification Date: 06/22/2005
Notification Time: 05:56 [ET]
Event Date: 06/21/2005
Event Time: 23:40 [CDT]
Last Update Date: 06/23/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
BRUCE BURGESS (R3)

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

MULTIPLE SPECIFIED SYSTEMS ACTUATIONS DUE TO LOSS OF AC SAFETY RELATED BUSES

"At 23:40 CDST, LaSalle Unit 2 experienced a trip of the 4160 Volt AC feed breaker to 480 Volt AC Safety Related buses 235X & 235Y. As a result of this feed breaker trip, containment isolation valves closed in multiple systems. The systems which isolated included Containment Monitoring System, Drywell Floor Drains and Drywell Equipment Drains, Reactor Recirculation Flow Control Hydraulic System, Drywell Instrument Nitrogen System, Reactor Water Cleanup System, and Reactor Recirculation Sample System. This event is reportable under 10 CFR50.72(b)(3)(iv)(A). In addition to the- above mentioned system isolations, the following plant responses occurred due to the loss of these 480 Volt AC buses: Reactor Building Ventilation was lost due to the closure of the secondary containment isolation dampers; Multiple Division 1 containment isolation valves lost their AC power source, a 1/2-SCRAM occurred due to the loss of the 2A Reactor Protection System Motor-Generator set, the DC charger feed to the Division 1 DC Battery/Bus was lost, and the battery is currently maintaining availability of DC power to the bus. Troubleshooting has determined that the cause of the breaker trip was due to a defective neutral ground current protective relay. This relay has been replaced and the buses have been re-energized. System restoration is currently in progress."

The licensee informed the NRC Resident Inspector.


* * * UPDATE FROM JEFF WILLIAMS TO GERRY WAIG AT 1217 EDT ON 06/22/05 * * *

"The following is an update to EN# 41787. Restoration of all required safety systems with the exception of the Reactor Core Isolation Cooling (RCIC) system has been completed. The associated ECCS systems were filled, vented and restored to an available status at 0630 CDST and full operability established at 0803 CDST. The Division 1 DC battery was fully recharged and returned to an operable status at 0803 CDST. Restoration of the RCIC system and investigation into the cause of the relay failure is currently in progress."

The licensee has notified the NRC Resident Inspector.

Notified R3DO (Bruce Burgess).

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Power Reactor Event Number: 41788
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: DANIEL MALONE
HQ OPS Officer: GERRY WAIG
Notification Date: 06/23/2005
Notification Time: 10:40 [ET]
Event Date: 06/23/2005
Event Time: 08:20 [EDT]
Last Update Date: 06/23/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
BRUCE BURGESS (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

NON-LICENSED SUPERVISOR FAILED RANDOM FITNESS FOR DUTY TEST

A non-licensed employee supervisor tested positive for illegal drugs during a random test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41789
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: JOHN GUNN
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/23/2005
Notification Time: 18:33 [ET]
Event Date: 06/23/2005
Event Time: 08:23 [MST]
Last Update Date: 06/23/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
RUSSELL BYWATER (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

UNIT 2 AUX FEEDWATER TRAIN SEPARATION NOT MAINTAINED DURING OPERATION

"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.

"On 6/23/05 at approximately 08:23 MST, it was identified that the door between the 'A' and 'B' Train Aux Feedwater Pump rooms was open and unattended. The door was immediately closed and secured. This door is required to be maintained secured in the closed position (except for personnel ingress/egress) during Modes 1 through 4 to provide a barrier for protection from fire or internal flooding. Station procedures require compensatory measures to be established when this door is maintained open in Modes 1-4. The compensatory measures include stationing an individual with the responsibility to close the door in the event of internal flooding. Since this compensatory measure was not established, this condition is considered to be reportable as an unanalyzed condition per the criteria of 10CFR50.72(b)(3)(ii)(B).

"Investigation is in progress to determine the duration and reason that this door was inappropriately open."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41790
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: FRED SCHILL
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/23/2005
Notification Time: 18:50 [ET]
Event Date: 06/23/2005
Event Time: 13:46 [PDT]
Last Update Date: 06/23/2005
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):
RUSSELL BYWATER (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 25 Power Operation 0 Hot Shutdown

Event Text

UNIT EXPERIENCED AN AUTOMATIC REACTOR SCRAM DUE TO A LOSS OF FEEDWATER FLOW

"On June 23, 2005 at 1348 PDT Columbia Generating Station experienced a Reactor Protection System (RPS) actuation and closure of all Main Steam Isolation Valves (MSIV) while operating at approximately 25% power. Currently, Reactor Pressure Vessel (RPV) level is being controlled using the Reactor Core Isolation Cooling (RCIC) system and RPV pressure is stable at approximately 800 psi. There was no automatic ECCS system injection. At this time, the plant is stable and indications show that the RPS actuation and closure of MSIVs was initiated in response to a valid low RPV water level signals that occurred because of a loss of feedwater flow. Determination of the cause of the loss of feedwater flow is ongoing at this time."

All control rods fully inserted.

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 41791
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: DAN DALY
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/23/2005
Notification Time: 22:08 [ET]
Event Date: 06/23/2005
Event Time: 15:49 [CDT]
Last Update Date: 06/23/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BRUCE BURGESS (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 99 Power Operation 99 Power Operation
3 N Y 99 Power Operation 99 Power Operation

Event Text

OFFSITE POWER SOURCE DECLARED INOPERABLE DUE TO LOW VOLTAGE

"At 15:49 hours Central Daylight Savings Time, June 23, 2005, entered DOA 6500-12, Low Switchyard Voltage. Bulk Power Operations reported predicted post Unit trip with LOCA switchyard voltage for Unit 2 is 342.5 KV and for Unit 3 is 342.3 KV. This rendered both Unit 2 AND Unit 3 offsite electrical power sources inoperable. This predicted voltage is the value required to support Loss Of Coolant Accident (LOCA) loading. Entered applicable Technical Specification required actions for both Units due to both offsite power sources being declared inoperable for Unit 2 and Unit 3.

"As of 1744 hours, restored Unit 2 offsite electrical power source to operable status by performing Transformer 86 Tap Changer adjustment per applicable procedure. TR 86 [transformer 86] supplies Unit 2 offsite electrical power.

"As of 1948 hours, switchyard voltage was restored to operable limits. This restored Unit 3 offsite electrical power source to operable status.

"This notification is provided in accordance with 10CFR 50.72(b)(3)(v)(D) to report a condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident."

The licensee will notify the NRC Resident Inspector and the state.

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Power Reactor Event Number: 41792
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: DARRELL FUJIYOSHI
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 06/24/2005
Notification Time: 02:57 [ET]
Event Date: 06/23/2005
Event Time: 23:21 [PDT]
Last Update Date: 06/24/2005
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
RUSSELL BYWATER (R4)
MICHAEL CASE (NRR)
SUSAN FRANT (IRD)
DAVID BARDEN (FEMA)
S. CEASAR (DHS)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Hot Shutdown 0 Hot Shutdown

Event Text

LICENSEE DECLARED AN UNUSUAL EVENT DUE TO DETECTION OF A FLAMMABLE GAS IN THE GENERAL SERVICES BUILDING

An NOUE was declared at the site at 2327 PDT due to the discovery of flammable gas in the General Services Building (office space) which is attached to the turbine and reactor building. The source and type of gas has not been identified and investigation is ongoing by HAZMAT trained personnel. The highest level of flammability measured is 50% of LEL (Lower Explosive Limit). The building has been evacuated.

The NRC Resident Inspector will be notified and State local and other Gov agencies have been notified.

* * * UPDATE FROM D. FUJIYOSHI TO M. RIPLEY 0527 EDT 06/24/05 * * *

"EAL # 9.3.U.3 - Report or detection of toxic or flammable gases that could enter or have entered within the Protected Area Boundary in amounts that could affect the health of plant personnel or safe plant operation.

"The event has been terminated based on a thorough survey of the building by HAZMAT personnel. The building in question has been determined to be free of any flammable gases.

"Probable source of gas is from a sewage treatment plant. The gas was carried by a stable breeze to the building's air intake. Immediately prior to the event, initial reports of odorous gas from several building occupants was confirmed using portable instrumentation. The highest flammable gas levels were found at a building air intake. Dissipation of gas concentration was accomplished using normal building ventilation."

The NRC Resident Inspector will be notified and State local and other Gov agencies have been notified. Notified R4 DO (R. Bywater), NRR EO (M. Case), IRD Manager (S. Frant), DHS (Ceasar), and FEMA (Sullivan).

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