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Event Notification Report for June 27, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/24/2005 - 06/27/2005

** EVENT NUMBERS **


41792 41793 41794 41795 41796 41797 41798 41799 41800

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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).

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Power Reactor Event Number: 41793
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TOM GARRISON
HQ OPS Officer: MIKE RIPLEY
Notification Date: 06/24/2005
Notification Time: 09:59 [ET]
Event Date: 06/24/2005
Event Time: 08:45 [EDT]
Last Update Date: 06/24/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
CAROLYN EVANS (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

OFFSITE NOTIFICATION - FUEL OIL SPILL ON LAKE WYLIE NEAR PLANT INTAKE

"At 0741 the control room was notified that a barge that was being used to support drilling activities near the plant intake on Lake Wylie had partially sunk. The barge was supporting a diesel fuel engine used for drilling operations. The fuel oil tank (maximum capacity of 6 gallons) was submerged under the surface of Lake Wylie. At 0840 the duty hazmat personnel on the scene notified the control room that there was fuel oil on the surface of the lake. At approximately 0845 the York County South Carolina 911 telecommunicator was called and informed of the fuel oil spill on Lake Wylie. This notification is being made as a 4-hour non-emergency notification as a result of notifying an offsite agency of the fuel oil spill on Lake Wylie. Efforts are currently underway to secure / contain the fuel oil. No offsite assistance has been requested."

The licensee notified the NRC Resident Inspector.

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General Information or Other Event Number: 41794
Rep Org: GE ENERGY
Licensee: GE ENERGY
Region: 1
City: WILMINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JASON S. POST
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/24/2005
Notification Time: 13:35 [ET]
Event Date: 04/26/2005
Event Time: [EDT]
Last Update Date: 06/24/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
JAMES DWYER (R1)
CAROLYN EVANS (R2)
BRUCE BURGESS (R3)
RUSSELL BYWATER (R4)
OMID TABATABAI (NRR)

Event Text

PART 21 NOTIFICATION - CRITICAL POWER DETERMINATION FOR GE14 AND GE12 FUEL WITH ZIRCALOY SPACERS

The following is a portion of a facsimile received on June 24, 2005 from GE Energy, reference - MFN 05-058 Rev 1:

ATTACHMENT 2 - 60-Day interim Report Notification per 21.21(a)(2), and Transfer of Information per 21.21(b)

(i) Name and address of the individual informing the Commission: J. S. Post, Manager, Engineering Quality &Safety Evaluations, GE Energy - Nuclear, 3901 Castle Hayne Road, Wilmington, NC 28401.

(ii) Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States, which may fail to comply or contain a defect: The affected and potentially affected plants are identified in Attachment 1. This concern is limited to plants that have fresh or once-burned GE14 or GE12 fuel with Zircaloy spacers. GE12 fuel with Inconel spacers is not affected.

(iii) Identification of the firm constructing the facility or supplying the basic component, which may fail to comply or contain a defect: Global Nuclear Fuel-Americas, LLC, Wilmington, NC.

(iv) Nature of the defect or failure to comply and safety hazard, which could be created by such defect or failure to comply: During review of GE14 ATLAS critical power tests results, it was discovered that springs on the Zircaloy test spacers used in the GE14 and GE12 critical power testing were deformed, possibly during the testing. This resulted in a potentially non-conservative critical power determination for fuel bundle corner pin locations. This non-conservatism potentially impacts the calculated margin to the Operating Limit Minimum Critical Power Ratio (OLMCPR), the Safety Limit MCPR (SLMCPR), the Rod Withdrawal Error (RWE) analysis, and the R-factors used in the on-line 3D core simulator. GE has completed the evaluation of the impact on the critical power determination, and has completed the evaluation of the impact on the R-factors. GE has performed a preliminary evaluation of the impact on the margin to the OLMCPR, the impact on the SLMCPR, and the impact on the RWE event. Potentially affected plants have been informed and have taken appropriate compensatory actions.

(v) The date on which the information of such a potential defect or failure to comply was obtained: This concern was identified in the GE safety evaluation program on April 26, 2005.

(vi) In the case of a basic component which may contain a defect or failure to comply, the number and locations of all such components in use at, supplied for, or being supplied for one or more facilities or activities subject to the regulations in this part: The basic component that may contain a defect is the critical power determination for fresh and once-burned GE14 and GE12 fuel with Zircaloy spacers. GE12 fuel with Inconel spacers and other GNF fuels are not affected. In the US, only GE14 is affected since all GE12 designs in the US have Inconel spacers.

(vii) The corrective action which has been, is being, or will be taken: the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action (note, these are actions specifically associated with the identified Potential Reportable Condition evaluation): GE has completed the evaluation of the impact on the critical power determination and has completed the evaluation of the impact on the R-factors. GE has performed a preliminary evaluation of the impact on the margin to the OLMCPR, the impact on the SLMCPR, and the impact on the RWE event.

Plants that may have non-conservative process computer calculated OLMCPR margins have taken compensatory action as necessary based on the magnitude of the non-conservatism to prevent inadvertently exceeding the OLMCPR during plant operating maneuvers.

Additional corrective actions planned are as follows:

1. Complete the current-cycle analyses to confirm the non-conservative MFLCPR impact (September 20, 2005).

2. Complete the analysis for previous cycle(s) extending to the previous three years of operation to determine which plants may have a non-conservative MFLCPR (December 15, 2005).

3. Complete the analyses to confirm that no plant has a SLMCPR impact greater than or equal to the reportable threshold of 0.01 (September 20, 2005).

4. Determine and provide the necessary data for plants that perform their own SLMCPR calculations, or that operate with fresh fuel batches of non-GE fuel along with second cycle affected GE14 fuel (September 30, 2005).

5. Complete the evaluation to confirm that the RWE analyses do not impact the OLMCPR (September 20, 2005).

6. Provide bundle R-factor and software updates for the on-line 30 core simulator (beginning in August 2005, and extending through the balance of 2005).

(viii) Any advice related to the potential defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees: Affected plants should continue to work with their GE Customer Account Leader to obtain information as plant-specific calculations are completed.

ATTACHMENT 1 - Affected and Potentially Affected Plants for Current Operating Cycle [ABSTRACTED]

(a) Impact on MFLCPR: Transfer of Information; preliminary analysis indicates MFLCPR impact, GE does not have sufficient information to determine if the OLMCPR could have been exceeded

Clinton, Brunswick 1 & 2, Nine Mile Point 2, Fermi 2, FitzPatrick, Dresden 2, LaSalle 1 & 2, Limerick 1 & 2, Peach Bottom 2 & 3, Quad Cities 2, Perry 1, Cooper, Duane Arnold, Monticello, and Hope Creek.

(b) Impact on SLMCPR: Transfer of Information; GE does not have sufficient information to determine if there is an impact on the SLMCPR greater than or equal to 0.01

Browns Ferry 2 & 3

(c) Impact of Rod Withdrawal Error (RWE) on OLMCPR: Transfer of Information; GE does not do the analysis for RWE (info provided via telephone during notification to Ops Center)

Browns Ferry 2 & 3

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General Information or Other Event Number: 41795
Rep Org: ENGINEERING CONSULTANT SERVICES
Licensee: ENGINEERING CONSULTANT SERVICES
Region: 1
City: CHANTILLY State: VA
County:
License #: 45-24974-01
Agreement: N
Docket:
NRC Notified By: OMER DUZYOL
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/24/2005
Notification Time: 16:15 [ET]
Event Date: 06/24/2005
Event Time: 15:15 [EDT]
Last Update Date: 06/24/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
Person (Organization):
JAMES DWYER (R1)
LAWRENCE KOKAJKO (NMSS)

Event Text

NUCLEAR DENSITY GAUGE DAMAGED AT JOBSITE

At approximately 1515 EDT on 6/24/05, a CPN Nuclear Gauge, Model NC1DRP, S/N MD00505618 containing two (2) sources, i.e., 10 millicuries Cs-137 and 50 millicuries Am-241:Be, was run over by a loader at a jobsite near the intersection of Olley Lane and Little River Turnpike in Fairfax County, VA. The area was isolated and rad surveys conducted by the RSO confirmed that the source was not exposed (a radiation level of .4mR/hr was measured at a distance of 1 meter). The RSO will package the damaged gauge and return it to the manufacturer for evaluation. No assistance from any HAZMAT/Fire Department personnel was requested or needed.

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Power Reactor Event Number: 41796
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: CLAY REED
HQ OPS Officer: JEFF ROTTON
Notification Date: 06/24/2005
Notification Time: 20:11 [ET]
Event Date: 06/24/2005
Event Time: 15:30 [CDT]
Last Update Date: 06/24/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RUSSELL BYWATER (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

SAFETY PARAMETER DISPLAY SYSTEM FAILURE IN EMERGENCY OPERATIONS FACILITY

"At 1530, on June 24, 2005, Training personnel reported a problem with the Safety Parameter Display System (SPDS) screens at the Emergency Operations Facility (EOF). Subsequent investigation determined that data was being updated, but the SPDS screens would not respond to keyboard or touch screen commands. SPDS was declared inoperable at 1630.

"The SPDS computer system is designed to monitor and display a concise set of parameters from which the safety status of both units can be readily and reliably determined. The system provides plant status information to the Unit-1 and Unit-2 control rooms, the Technical Support Center (TSC), and the Emergency Operating Facility (EOF).

"The controls and displays in the computer room, both Control Rooms and the TSC were unaffected by this condition.

"A bad communications card was found and replaced at the EOF. SPDS operability was restored at 1735."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41797
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: TOM CHALMERS
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/26/2005
Notification Time: 01:03 [ET]
Event Date: 06/25/2005
Event Time: 20:42 [CDT]
Last Update Date: 06/26/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
BRUCE BURGESS (R3)
LANCE ENGLISH (email (TAS)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 96 Power Operation 96 Power Operation

Event Text

OFFSITE ASSISTANCE REQUESTED DUE TO SWITCHYARD CIRCUIT BREAKER FAILURE

"On June 25, 2005 at 2042, Clinton Power Station received indications of loss of the Reserve Auxiliary Transformer (RAT). Upon investigation, it was discovered that Gas Circuit Breaker (GCB) 4522 had suffered catastrophic failure resulting in a lockout of the North Bus, which supplies the RAT.

"Offsite assistance was requested, as a precautionary measure, from the Local Law Enforcement Agency, Medical, and Fire Departments. The onsite Operations Fire Brigade extinguished the fire in the GCB 4522.

"Clinton Power Station remained online at full electrical load during the event and is stable. Restoration and recovery is now in progress.

"The NRC Resident Inspector has been informed."

The licensee stated that local law enforcement (Dewitt County Sheriff) departed the site at 2130 CDT and that nothing of a suspicious nature was found. The incident is considered to be solely the result of a component failure.

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Power Reactor Event Number: 41798
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [ ] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: CLAY WILLIAMS
HQ OPS Officer: BILL GOTT
Notification Date: 06/26/2005
Notification Time: 14:52 [ET]
Event Date: 06/26/2005
Event Time: 04:17 [PDT]
Last Update Date: 06/26/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RUSSELL BYWATER (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 100 Power Operation

Event Text

EDG INOPERABLE DUE TO LOOSE ELECTRICAL CONNECTION

"On June 25, 2005, at about 1335 PDT, during a test of Unit 3 Emergency Diesel Generator (EDG) 3G003, Emergency Supply Fan 3A276 did not start. SCE's investigation found a loose electrical connection at the thermal overload auxiliary switch contact for that fan. A similar condition was found on Emergency Supply Fan 3A277. SCE declared 3G003 inoperable and initiated a common cause investigation required by the EDG Technical Specifications. SCE tightened the affected electrical connections and after successfully start testing 3G003, declared 3G003 operable at 0406 PDT on June 26, 2005.

"On June 26, 2005, at about 0417 PDT, SCE found similar loose connections for EDG 3G002. Components affected were the EDG radiator fan and an EDG Emergency Supply Fan. Because SCE could not conclusively determine if the loose connections would have caused 3G002 to be inoperable, SCE conservatively declared 3G002 inoperable. (SCE currently plans to start test the Unit 2 EDGs today to confirm the Unit 2 EDGs remain operable.)

"Because it appears that both Unit 3 EDGs could have been inoperable at the same time, SCE is reporting this occurrence in accordance with 10CFR50.72(b)(3)(v)(D) as an event or condition that could have prevented fulfillment of a safety function.

"At the time of this occurrence, Unit 2 was operating at about 99 percent power and Unit 3 was at about 100 percent power. SCE has notified the NRC Resident Inspectors about this occurrence and will provide them with a copy of this report."

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Power Reactor Event Number: 41799
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MIKE McDONNELL
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/26/2005
Notification Time: 15:30 [ET]
Event Date: 06/26/2005
Event Time: 10:55 [EDT]
Last Update Date: 06/26/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JAMES DWYER (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

EMERGENCY DIESEL GENERATORS INOPERABLE DUE TO HIGH AMBIENT TEMPERATURE

"The report is being made in accordance with 10 CFR 50.72(b)(3) due to both Emergency Diesel Generators (EDGs) being declared inoperable. [This is a 24-hour LCO.] The EDGs were declared inoperable due to indicated outside air temperature exceeding the established operability limit of 95F for two short periods of time. Indicated outside air temperature went above 95F during the following time frames: 10:55 to 11:00 and 12:15 to 12:20. Indicated outside air temperature subsequently decreased to less than 95F following these spikes. Both EDGs are currently operable. Outside ambient temperatures are continuing to be monitored. Offsite power is available.

"Further evaluation of this event is ongoing."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41800
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JIM SPEICHER
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 06/27/2005
Notification Time: 04:19 [ET]
Event Date: 06/27/2005
Event Time: 03:16 [EDT]
Last Update Date: 06/27/2005
Emergency Class: UNUSUAL EVENT
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
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
CAROLYN EVANS (R2)
MICHAEL CASE (NRR)
SUSAN FRANT (IRD)
JOEL MUNDAY (R2)
TOD KUZIA (FEMA)
STEVE HASELTON (DHS)

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

Event Text

DECLARATION OF AN UNUSUAL EVENT DUE TRANSFORMER FIRE >10 MINUTES

UNUSUAL EVENT (EAL #16 - Fire) declared at 0327 on 6/27/05 due to uncontrolled fire in the Unit 4 Main Transformer lasting longer than 10 minutes. Unit 4 experienced an automatic reactor trip from 100% on a turbine trip due to a fire in the Main Transformer. The fire was extinguished after approximately 25 minutes. On-site fire brigade and Miami-Dade fire department responded. The cause of the fire is under investigation.

The reactor is stable in Mode 3. No safety systems were affected. All rods fully inserted, no ECCS actuations, no relief valves lifted and no personnel injuries occurred. Offsite power is still available and no emergency diesels auto started, however, there was an auxiliary feedwater actuation.

Hazardous Material response is being implemented due to discharge of transformer oil. There may be a possible press release on this event.

The NRC Resident Inspector was notified along with State and local agencies.


* * * UPDATE ON 06/27/05 @ 05:13 BY SPEICHER TO GOULD * * *

The NOUE was terminated at 05:00 due to the fire being extinguished and the emergency no longer existing.

The NRC Resident Inspector was notified.

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