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Event Notification Report for February 14, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/11/2005 - 02/14/2005

** EVENT NUMBERS **


41387 41388 41393 41402 41403 41404 41405 41406 41407 41408

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Other Nuclear Material Event Number: 41387
Rep Org: HALLIBURTON ENERGY SERVICES
Licensee: HALLIBURTON ENERGY SERVICES
Region: 4
City: HOUSTON State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DWAINE BROWN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 02/08/2005
Notification Time: 16:42 [ET]
Event Date: 02/08/2005
Event Time: 11:30 [CST]
Last Update Date: 02/13/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
BLAIR SPITZBERG (R4)
JAMES TRAPP (R1)
GEORGE PANGBORN (R1)
LONNIE LACEY (DHS)
CHUCK CAIN (R4)
MR CREWS (DOT)
THOMAS YATES (DOE)
JOSEPHINE PICCONE (STP)
JACK RAMSEY (IP)
JACK CRLENJAK (IRD)

Event Text

LICENSEE REPORTED A SHIPMENT THEY WERE TO RECEIVE IS UNACCOUNTED FOR

Halliburton Energy Services had shipped a well logging source and calibrating source containing 18.5 curies of Am-241 Be and .5 curies of Am-241 from Nizhnevartovsk, Russia to Houston TX. Both sources were in a 18" dia 23" long cylindrical type "A" container which weighed 83kg. The sources went through Amsterdam to JFK in New York and cleared customs in New York on 10/09/04. After clearing customs they have not been able to track the package to any of the transport companies that were scheduled to handle it. An ongoing search is still being conducted.


* * * UPDATE ON 02/09/05 @ 1751 FROM RICHARD ARSENAULT TO CHAUNCEY GOULD * * *

The licensee was notified at 1621 CT that the unaccounted for sources were located at the Forward Freight facilities in Boston, MA. It appears that they were trucked to Boston after a Boston label was inadvertently placed on the package at the Newark facility of Forward Freight. The licensee stated the package appears to be intact and the are sending a rep to Boston on 2/10/05.

Notified Regs 1 & 4, NMSS, PAO, DHS, DOT, DOE, IP, TAS, STP

* * * UPDATE ON 02/10/05 @ 1358 HRS. EST FROM ARSENAULT TO CROUCH * * *

A representative from Halliburton Energy Services has verified that the sources and packaging are intact and all source material is accounted for. Forward Air Freight is scheduled to ship the package to Halliburton in Houston, TX.

Notified R1DO (Cobey), R4DO(Whitten), R4 (Cain) and NMSS (Essig).

* * * UPDATE ON 2/13/05 @ 2348 EST BY S. SANDIN * * *

During administrative review of this report, two (2) corrections were made; the previously shown notification time of 1921 EST was corrected to read 1642 EST, and the 10 CFR Section citation of 20.2201(a)(1)(ii) was corrected to read to show 20.2201(a)(1)(i).

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General Information or Other Event Number: 41388
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee:
Region: 4
City: Placentia State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGOR
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/08/2005
Notification Time: 20:36 [ET]
Event Date: 02/08/2005
Event Time: 12:00 [PST]
Last Update Date: 02/08/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BLAIR SPITZBERG (R4)
C.W. (BILL) REAMER (NMSS)
CNSNS (MEXICO) (FAX)

Event Text

CALIFORNIA AGREEMENT STATE REPORT- LOST RADIOACTIVE MATERIAL

The California Radiation Health Bureau reported that a radiopharmaceutical carrier had lost 112 milliCuries of Thallium-201. The shipment of thallium was picked up at the airport in Burbank, CA and was in transport to Loma Linda, CA when it was discovered missing. The carrier had made two stops after picking up the product in Burbank, CA. The carrier reported that when they left Placentia, CA, (the second stop) their truck tailgate was closed. When they reached Loma Linda, CA, they discovered that the tailgate was open. It is believed that the package with the thallium fell out on the interstate between Placentia and Loma Linda.

The carrier searched the route twice without success. The State of California did notify the California Highway Patrol of the missing package.

California incident number is 020805.

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General Information or Other Event Number: 41393
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: TREADWELL & ROLLO
Region: 4
City: SAN FRANCISCO State: CA
County:
License #: 5917-38
Agreement: Y
Docket:
NRC Notified By: KENT PRENDERGAST
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/09/2005
Notification Time: 19:12 [ET]
Event Date: 02/09/2005
Event Time: 09:30 [PST]
Last Update Date: 02/09/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JACK WHITTEN (R4)
C.W. (BILL) REAMER (NMSS)

Event Text

CALIFORNIA AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

The following information was obtained from California Department of Health Services, Radiation Health Branch - Berkeley / Region 3 via facsimile:

"A CPN Model MC-1DRR-P moisture density gauge was run over at a construction site at Valencia Street between 14th and 15th Street in San Francisco, CA approximately at 9:30 am. The gamma source rod was in the extended position at the time of the incident. The source tip rod containing 10 [milliCuries of] Cs-137 was intact but was slightly bent and could not be retracted into the safe position. The 50 [milliCurie] Am-241/Be source was intact as designed. Mr. [DELETED] from CPN was at the site after the incident. A screen leak test performed by Mr. [DELETED] did not indicate any contamination. Gauge was picked up by CPN at the site and held for disposal."

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Power Reactor Event Number: 41402
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: DAVID NIX
HQ OPS Officer: MIKE RIPLEY
Notification Date: 02/11/2005
Notification Time: 00:16 [ET]
Event Date: 02/10/2005
Event Time: 23:00 [EST]
Last Update Date: 02/11/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
MALCOLM WIDMANN (R2)
JACK CRLENJAK (IRD)
WILLIAM BECKNER (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 90 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO LOSS OF ELECTRICAL POWER SOURCES

"Event: At 23:00 [EST] on 2-10-05, Oconee Unit 1 initiated a plant shutdown as required by its Technical Specifications. Technical Specification 3.8.1 Condition M, Required Action M.1 requires Oconee Unit 1 to enter Mode 3 by 03:06 on 2-11-05 due to Keowee Hydro Unit 2 and CT-1 inoperable. Keowee Hydro Unit 2 is inoperable due to a planned outage, with restoration in progress. CT-1 is inoperable due to experiencing a lockout at 12:12 on 2-10-05 during testing to restore Keowee.

"Initial Safety Significance: Oconee Unit 1 is being shut down in accordance with Technical Specifications. Unit auxiliaries will be powered from the Standby busses and a Lee Combustion Turbine. When the turbine is tripped, the Unit will enter into the natural circulation mode of cooling due to loss of Reactor Coolant Pumps.

"Corrective Action(s):
1) Restoration of Keowee Hydro Unit 2 is in progress.
2) A Unit Threat Team has been assembled and is investigating the cause of the lockout on CT-1. CT-2 cross connect is in progress to allow the unit, if tripped, to avoid loss of Reactor Coolant Pumps."

The licensee notified the NRC Resident Inspector.

* * * * UPDATE FROM D. NIX TO M. RIPLEY 0016 EST 02/11/05 * * * *

At the time of the initial notification, Oconee reported that, at 2346 EST on 02/10/05, the CT-2 cross connect has been completed, allowing the unit, if tripped, to avoid a loss of Reactor Coolant Pumps. The power reduction to enter Mode 3 by 03:06 continues. Restoration of Keowee Hydro Unit 2 and investigation into the cause of the lockout on CT-1 remain in progress. The licensee notified the NRC Resident Inspector.

Notified R2 DO (M. Widman), IRD (Crlenjak), and NRR EO (W. Beckner).

* * * * UPDATE FROM J. COLLINS TO W. HUFFMAN 0045 EST 02/11/05 * * * *

At 0033 EST 02/11/05, restoration of Keowee Hydro Unit 2 to operable status was completed and Technical Specification 3.8.1 Condition M, Required Action M.1 requiring Oconee Unit 1 to enter Mode 3 by 03:06 on 2-11-05 was exited. The power reduction was stopped with power at 85% at 0034 EST. Technical Specification 3.8.1, Condition A, which was entered on 1106 EST on 02/10/05, requires restoration of CT-1 by 2306 on 02/11/06. The licensee notified the NRC Resident Inspector.

Notified R2 DO (M. Widman), IRD (Crlenjak), and NRR EO (W. Beckner).

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Power Reactor Event Number: 41403
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: PHIL SANTINI
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/11/2005
Notification Time: 19:54 [ET]
Event Date: 02/11/2005
Event Time: 19:30 [EST]
Last Update Date: 02/11/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
EUGENE COBEY (R1)

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

NOTIFICATION TO NEW YORK STATE PSC INVOLVING RADWASTE SHIPMENT INCIDENT OFFSITE

"Notified by Barnwell Waste Management Facility that the filter liner sent to the Facility had arrived and that they found 'waste outside the liner.' This is a violation of the Barnwell license.

"This notification is made in accordance with the New York State PSC [Public Service Commission] requirements per corporate procedure.

"Ref: CR-IP2-2005-00613"

The licensee will inform the State of New York and had informed the NRC Resident Inspector.

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Power Reactor Event Number: 41404
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [ ] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: WILLIAM BAKER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/11/2005
Notification Time: 20:29 [ET]
Event Date: 02/11/2005
Event Time: 16:29 [CST]
Last Update Date: 02/11/2005
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):
MALCOLM WIDMANN (R2)

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

Event Text

AUTOMATIC REACTOR SCRAM DUE TO A LOAD REJECTION

The following text was obtained from the licensee via facsimile:

"At 1629 [hrs. CST] on 02/11/05, Unit 3 reactor scrammed from 100% power when the output breaker tripped causing a load reject. The breaker tripped due to a corresponding switchyard breaker 5268 tripping when a PK block was re-installed before the trip cutout (TCO) switches were placed in TCO. All rods inserted. Unit 2 was also at 100% power and was unaffected by this event. Water level lowered to +1" as expected and was recovered by normal feed water flow. All expected PCIS [Primary Containment Isolation System] isolations, Group 2 (RHR S/D [Residual Heat Removal] cooling), Group 3 (RWCU [Reactor Water Clean Up]), Group 6 (ventilation), and group 8 (TIP [Transverse Incore Probe]) were received along with the auto start of CREV [Control Room Emergency Ventilation] and the 3 SGT [Standby Gas Treatment] trains. Four MSRV's [Main Steam Safety Relief Valves] lifted momentarily to stabilize reactor pressure.

"This event is reportable as a 4-hour and 8-hour Non-Emergency Notification along with a 60-day written report in accordance with 10CFR50.72(b)(2)(iv)(B), 10CFR50.72(b)(3)(iv)(A) and 10CFR50.73(a)(2)(iv)(A) as 'Any event or condition that results in a valid actuation of RPS [Reactor Protection System] and PCIS .."

The plant was performing restoration from switchyard maintenance at the time of the scram. All safety relief valves that lifted properly re-seated. Decay heat is being removed via the steam bypass valves to condenser. The electrical grid is stable.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 41405
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: RICKY PATTERSON
HQ OPS Officer: BILL GOTT
Notification Date: 02/11/2005
Notification Time: 23:44 [ET]
Event Date: 02/11/2005
Event Time: 19:59 [CST]
Last Update Date: 02/12/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(iv)(A) - ECCS INJECTION
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
1 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

RPS ACTUATION

The following text was obtained from the licensee via facsimile:

"At approximately 1959 hours Central Standard Time, Grand Gulf Nuclear Station experienced a loss of Electrical Bus 11R. This caused a loss of additional electrical buses, and a subsequent reactor scram on low reactor water [level]. The feedwater system was lost, and reactor low level 2 was reached. The Reactor Core Isolation Cooling System and High Pressure Core Spray System injected into the reactor and restored reactor water level. A primary containment, secondary containment, and drywell isolation occurred as expected. The Division 1 Diesel started and picked up the Division 1 bus. The Division 3 Diesel Generator started on the reactor low water level 2. The condenser is removing decay heat. The plant status currently is stable, with normal reactor water level and feedwater restored. All control rods inserted. The cause for the loss of Bus 11R is under investigation. Safety systems appeared to function as designed."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41406
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: AL PROKASH
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/12/2005
Notification Time: 04:09 [ET]
Event Date: 02/11/2005
Event Time: 22:26 [CST]
Last Update Date: 02/12/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
ERIC DUNCAN (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

POSTULATED LOSS OF AFW PUMPS FOLLOWING TORNADO DAMAGE TO CONDENSTATE STORAGE TANK

"Plant engineering staff discovered that the auxiliary feedwater (AFW) system discharge pressure trip protective equipment may not operate to protect the AFW pumps from condensate storage tanks (CST) failing from a tornado event. The AFW system protection design uses discharge pressure switches to protect the AFW pumps from a loss of suction pressure. The AFW system is required equipment to support a plant shutdown which is also assumed to occur as a result of a tornado.

"Current analysis predicts substantial damage to the CSTs caused by a tornado. The CSTs are aligned as the AFW pumps' initial/preferred water source. The tank damage is predicted to result in a rapid, near complete, loss of water inventory due to a tornado. The CST volume loss quickly causes air to enter the pump suction piping to all three AFW pumps. Under the postulated conditions, the current discharge pressure switch design does not act fast enough to trip the pumps before significant pump damage can occur, it appears that the original design analyses failed to consider the consequences of a loss of suction source causing air to enter the pump suction.

"The design basis for AFW pump discharge pressure switches, in part, is assumed to protect the AFW pumps from damage due to a tornado. Given the event postulated as described, the pressure switches may not meet this design basis assumption. Therefore, all three AFW pump discharge pressure switches were declared inoperable at 2226 on 2/11/2005.

"To ensure the AFW Pumps are protected in the event of a tornado, compensatory actions were incorporated in Operating Procedure E-0-05 Response to Natural Events. At the earliest indication of a tornado threat (i.e. Tornado Watch, Warning or Strike) operators are directed to align Service Water to the AFW Pump Suction to ensure adequate NPSH In the event of a loss of the CST supply. These actions do not replace the automatic function but ensure the pumps are protected against loss of NPSH. Based on the proceduralized compensatory actions put in place, the AFW Pump Low discharge Pressure Trips were declared Operable but Non-Conforming at 0056 on 2/12/2005."

The licensee has notified the NRC Resident Inspector.

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Other Nuclear Material Event Number: 41407
Rep Org: MID-PACIFIC TESTING & INSPECT SVC
Licensee: MID-PACIFIC TESTING & INSPECTION SERVICES, INC.
Region: 4
City: WAIPAHU State: HI
County: HONOLULU
License #: 53-29044-01
Agreement: N
Docket:
NRC Notified By: JAMES MERRIMAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 02/13/2005
Notification Time: 12:20 [ET]
Event Date: 02/13/2005
Event Time: [HST]
Last Update Date: 02/11/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
BLAIR SPITZBERG (R4)
C.W. (BILL) REAMER (NMSS)

Event Text

TROXLER MOISTURE DENSITY GAUGE STOLEN FROM BED OF PICKUP TRUCK

Sometime between the late afternoon on Friday, 2/11, and Sunday at 0600 HST, 2/13, a Troxler Moisture Density Gauge Model 3440, S/N 25490, and its case were stolen from the bed of the company pickup while parked in the Kalihi area of Honolulu, HI. Both the chain and cable securing the case were cut. The Model 3440 contains two (2) radioactive sources; 8 millicuries Cs-137 and 40 millicures Am-241/Be.

The licensee contacted the Honolulu Police Department and will offer a reward for its return.

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Power Reactor Event Number: 41408
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOHN COUTO
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/13/2005
Notification Time: 22:16 [ET]
Event Date: 02/13/2005
Event Time: 19:00 [EST]
Last Update Date: 02/13/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
EUGENE COBEY (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

HIGH PRESSURE COOLANT INJECTION SYSTEM (HPCI) DECLARED INOPERABLE

The following text report was received from the licensee via facsimile:

"The High Pressure Coolant Injection (HPCI) system was declared inoperable on 2-13-05 at 19:00 EST due to loss of position indication to MO-2301-8 (HPCI injection valve #2) in the control room and at the system alternate shutdown panel. The other ECCS [Emergency Core Cooling] Systems remain operable. Position indication was restored after control power fuses were replaced. HPCI was returned to operable status at 21:50 EST, 2-13-05."

The licensee has notified the NRC Resident Inspector and will be notifying Massachusetts Emergency Management Agency.

Page Last Reviewed/Updated Friday, March 30, 2012
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