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Event Notification Report for September 20, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/17/2004 - 09/20/2004

** EVENT NUMBERS **


40997 41018 41042 41046 41047 41048 41049 41050 41051 41053 41054 41056

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Other Nuclear Material Event Number: 40997
Rep Org: ATLANTIC GEOTECHNICAL SERVICES
Licensee: ATLANTIC GEOTECHNICAL SERVICES
Region: 1
City: ASHLAND State: VA
County:
License #: 45-25191-01
Agreement: N
Docket:
NRC Notified By: EDITH POPP
HQ OPS Officer: ARLON COSTA
Notification Date: 08/30/2004
Notification Time: 07:35 [ET]
Event Date: 08/30/2004
Event Time: [EDT]
Last Update Date: 09/17/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
EUGENE COBEY (R1)
JOHN HICKEY (NMSS)
JIM WHITNEY (TAS)

Event Text

STOLEN TROXLER GAUGE

Licensee technician reported to Richland, VA police that his vehicle (SUV) was stolen from his home possibly early this morning and that a Troxler gauge model 3430 (S/N 30179) was stored in the vehicle. The gauge was double locked in its casing and contains a Cesium 137 source (S/N 750-1869, current activity 7.4 millicuries) and a Americium 241:Beryllium source (S/N 47-271-56, current activity 39.7 millicuries). The licensee is contacting the Richland police once again to raise their awareness that this gauge contains radioactive materials.

* * * UPDATE 1000 EDT ON 9/17/04 FROM EDITH POPP TO S. SANDIN * * *

The stolen Troxler gauge was recovered intact late in the evening of 9/16/04 and returned to the custody of the licensee. The licensee verified that there were no leaks. Notified R1DO (Doerflein) and NMSS (Miller).

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 41018
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JOHN COLVIN
HQ OPS Officer: BILL GOTT
Notification Date: 09/04/2004
Notification Time: 05:40 [ET]
Event Date: 09/04/2004
Event Time: 01:56 [EDT]
Last Update Date: 09/17/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
JOEL MUNDAY (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 21 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO STEAM GENERATOR LEVEL OSCILLATIONS

"While reducing power in response to expected severe weather conditions from hurricane Frances, the reactor was manually tripped from 21% reactor power. The reactor was tripped because of significant swings in the 'B' Steam Generator level caused by erratic operation of the 'B' Feedwater Regulating Valve (FRV). All Control Element Assemblies fully inserted. Decay heat is currently being removed by Main Feedwater using the low power FRV bypass valves and Steam Bypass Control System (SBCS), maintaining RCS temperature at 532 degrees Fahrenheit. The unit will be maintained in a shutdown condition until repairs to the FRV are completed and the severe weather from Hurricane Frances abates.

"All primary and secondary systems performed as expected with the exception of the SBCS. The SBCS consists of five pressure control valves, PCV-8801 through PCV-8805 with PCV-8801 a larger capacity valve and designed to open first. The remaining valves are designed to open in series with overlap through their operating ranges. PCV-8801 failed to open and PCV-8802, 8803, and 8804 did not appear to properly control RCS temperature. PCV-8805 was operated in manual to control [steam generator] pressure.

The Licensee notified the NRC Resident Inspector.

* * * RETRACTION FROM K. FREHAFER TO W. GOTT AT 1549 EDT ON 9/17/04 * * *

"Florida Power and Light (FPL) is retracting this notification because the feedwater issues during the shutdown were not causal to the manual reactor trip. The St. Lucie Emergency Plan, requires that the units be taken offline prior to the onset of hurricane force winds onsite. In accordance with these requirements, St. Lucie Unit 2 was being taken offline prior to the arrival of hurricane Frances. Although automatic feedwater issues occurred during the downpower, the operators successfully took manual control of the main feedwater system. A reactor trip was not necessary to mitigate the condition, and continued operation and on-line troubleshooting would have been practical had the plant not been required to be shutdown for the approaching hurricane. The main feedwater control issues were not relevant factors during the planned plant shutdown/manual reactor trip. Therefore FPL is retracting this notification."

The licensee notified the NRC Resident Inspector.

Notified R2DO(Boland).

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General Information or Other Event Number: 41042
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: BBC&M ENGINEERING, INC.
Region: 3
City: DUBLIN State: OH
County:
License #: OH31210250006
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/15/2004
Notification Time: 11:34 [ET]
Event Date: 09/14/2004
Event Time: [EDT]
Last Update Date: 09/15/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
KENNETH RIEMER (R3)
SCOTT MOORE (NMSS)
AARON DANIS (TAS)

Event Text

AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER GAUGE

"BBC&M Engineering, Ohio License # 31210 25 0006, reported to ODH/BRP that a Troxler moisture density gauge was stolen from a tool trailer at a temporary job site sometime during the overnight period between Tuesday evening, 9/14/04, to Wednesday morning, 9/15/04.

"Other work tools belonging to the licensee were also taken from the trailer. The theft was discovered when workers returned to work on Wednesday morning.

"The job site was at the I-270/SR-161 highway construction site in northeast Columbus, Ohio. Police have been notified.

"The gauge was a Troxler Model 3430, Serial number 21035, containing an 8 mCi Cs-137 source and a 40 mCi Am-241 source. The gauge was stored in its locked storage case and the source was locked within the device. The storage case was stored in a locked tool trailer at the work site and was chained to the frame of the trailer. The locks to the trailer and storage case were broken and the gauge was taken from the storage case."

OH report No.: OH040004

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Power Reactor Event Number: 41046
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: FRANK KICH
HQ OPS Officer: GERRY WAIG
Notification Date: 09/17/2004
Notification Time: 00:37 [ET]
Event Date: 09/16/2004
Event Time: 23:18 [EDT]
Last Update Date: 09/17/2004
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
2 N Y 8 Power Operation 8 Power Operation

Event Text

OFFSITE NOTIFICATION TO PUBLIC SERVICE COMMISSION

The following was received from the licensee via facsimile:

"Indian Point Unit 2 synchronized to the grid at 2318 on September 16, 2004. NRC notification required per Item 44 of IP-SMM-LI-108, Event Notification and Reporting, due to notification of other government agencies of Indian Point Unit 2 synchronizing to the grid. This is a 4-hour non-emergency event notification per 10 CFR 50.72 (b)(2)(xi)."

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 41047
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: GERRY WAIG
Notification Date: 09/17/2004
Notification Time: 10:43 [ET]
Event Date: 09/17/2004
Event Time: 06:24 [CDT]
Last Update Date: 09/17/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
DALE POWERS (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 TO ARMY CORPS OF ENGINEERS

"Utilization of the Missouri river water in support of the dry cask storage (ISFSI) project by Hawkins Construction Company was done in violation of national permitting requirements. Two tubes were placed in the river connected to two pumps: One small line (about 2.5 in.) used to supply water for the cure wetting of the concrete pours and one large line (6-8 in.) connected to a large pump for filling of water trucks for dust suppression and other utility uses.

"The United States Army Corps of Engineers, who manages the river and its utilization, requires approval of such uses through a national permitting process.

"This condition was identified during a routine site and environs tour. The Omaha Public Power District environmental affairs group has contacted the Army Corps of Engineers on the issue. The use of Missouri river water by the contractor has been terminated. Another source of water will be used to complete the project."

The licensee informed the U.S. Army Corps of Engineers and the NRC Resident Inspector.

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Power Reactor Event Number: 41048
Facility: CATAWBA
Region: 2 State: SC
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MICHAEL T LEE
HQ OPS Officer: GERRY WAIG
Notification Date: 09/17/2004
Notification Time: 11:31 [ET]
Event Date: 09/17/2004
Event Time: 10:00 [EDT]
Last Update Date: 09/17/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
ANNE BOLAND (R2)
TERRY REIS (NRR)

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

Event Text

APPARENT PRESSURE BOUNDARY LEAKAGE IDENTIFIED ON STEAM GENERATOR BOWL DRAINS

"On September 16, 2004 examinations of the steam generator (SG) bowl drains (SGBDs) for the 2A, 2C and 2D SGs were performed as part of the Alloy 600 program during 2EOC13. These examinations determined that the 2C and 2D SGBDs had leakage and the leakage appeared to be pressure boundary leakage. The 2A SGBD examination determined that the ASME code acceptance limits were satisfied. An evaluation of the leakage indications determined that the leakage had existed for some time prior to the Unit 2 shutdown. The evaluation of this condition on September 17, 2004, determined that this met the reportability criteria of 10 CFR 50.72 (b)(3)(ii)(A). Unit 2 is currently in MODE 6 and this event has no impact on current plant operation. Engineering and plant management are evaluating repair methods to be completed during this refueling outage. This event is not applicable to Unit 1 because the Unit 1 steam generators are of a different design and do not have a drain line in the bottom channel head."

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 41049
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: R. O'REAR
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/17/2004
Notification Time: 11:45 [ET]
Event Date: 09/17/2004
Event Time: 05:00 [EDT]
Last Update Date: 09/17/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ANNE BOLAND (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

Event Text

LOSS OF EMERGENCY SIREN CAPABILITY AND NOTIFICATION OF OFFSITE AGENCY

"On Sept. 17, 2004, with Watts Bar Unit 1 at 100% power, the main control room was notified that the 99 sirens which make up the Public Prompt Notification System were not functional. The system uses two repeaters to control the sirens. As the remnants of Hurricane Ivan were passing through the Tennessee River Valley one of the repeaters (Pone Knob) was found to be without power around midnight. The siren system operators confirmed the second repeater (Grandview) was still functioning. Approximately 5:00 a.m., however, communications were lost with the second repeater. A maintenance crew was dispatched to the second repeater on loss of communications and they determined the radio transmitter was not functioning at 0955 and Watts Bar was immediately notified. This event is reportable under 10 CFR 50.72(b)(3)(xiii) as a loss of emergency preparedness capability.
.
"As a result of the above siren loss, TVA notified the Tennessee Emergency Management Agency (TEMA) at 10:13a.m. Sept. 17, 2004. This government agency notification is reportable under 10 CFR 50.72(b)(2)(xi). No TVA press release is planned and TVA is not aware of any specific actions planned to be taken by TEMA. Maintenance activities to restore power to the first repeater station by the use of a portable generator are underway."

The 99 sirens constitute 100% of the emergency siren capability. The licensee had no estimate for completion of repairs and restoration of the siren capability. The licensee informed the State of Tennessee and the NRC Resident Inspector.

* * * * UPDATE FROM S. SMITH TO M. RIPLEY 1350 ET 09/17/04 * * * *

Restoration of power by use of a portable generator has been completed, reducing the number of non-functional sirens to seven of ninety-nine. The licensee informed local and State authorities, and the NRC Resident Inspector.

Notified R2 DO (A. Boland).

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Power Reactor Event Number: 41050
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: MARTY STASNY
HQ OPS Officer: BILL GOTT
Notification Date: 09/17/2004
Notification Time: 12:19 [ET]
Event Date: 09/17/2004
Event Time: 10:30 [EDT]
Last Update Date: 09/17/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ANNE BOLAND (R2)
ERIC WEISS (NSIR)

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
3 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF SIREN CAPABILITY

"[Oconee is] unable to activate the siren system from the Oconee Law Enforcement Center due to the loss of power. The siren system can be activated from the backup location at Oconee Nuclear Station."

Oconee is working to restore power.

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 41051
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: BOB MARTIN
HQ OPS Officer: MIKE RIPLEY
Notification Date: 09/17/2004
Notification Time: 13:30 [ET]
Event Date: 09/17/2004
Event Time: 11:15 [EDT]
Last Update Date: 09/17/2004
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
2 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION - COLIFORM BACTERIA FOUND IN DRINKING WATER

"Positive coliform in Eagles Den drinking water [unused, onsite building]. Confirmed by backup sample."

The licensee notified the Maryland Department of the Environment and the NRC Resident Inspector.

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Power Reactor Event Number: 41053
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: PAUL CHRISTIANSEN
HQ OPS Officer: JOHN MacKINNON
Notification Date: 09/19/2004
Notification Time: 00:26 [ET]
Event Date: 09/18/2004
Event Time: 20:09 [EDT]
Last Update Date: 09/19/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ANNE BOLAND (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 80 Power Operation 80 Power Operation

Event Text

LOSS OF SAFETY PARAMTER DISPLAY SYSTEM (SPDS)

"On 09/18/04, Units 1 & 2 a simultaneously lost their control room's Safety Parameter Display System monitors for approximately 70 minutes before their were returned to service. This is considered a major loss of assessment and communication capability for greater than one hour. This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(3)(xiii)."

The NRC Resident Inspector will be notified of this event by the licensee.

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Power Reactor Event Number: 41054
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICK O REAR
HQ OPS Officer: GERRY WAIG
Notification Date: 09/19/2004
Notification Time: 07:46 [ET]
Event Date: 09/19/2004
Event Time: 04:56 [EDT]
Last Update Date: 09/19/2004
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):
ANNE BOLAND (R2)

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

Event Text

MANUAL REACTOR TRIP IN RESPONSE TO INDICATION OF DROPPED CONTROL RODS

The following was received from the licensee via facsimile:

"While operating at 100% power, the Watts Bar Unit 1 reactor was manually tripped at approximately 0456 EDT on September 19, 2004, in response to an apparent four dropped rods in control bank 'B'. The cause of the dropped rods is being investigated.

"Safety systems functioned as expected in response to the trip. All control rods inserted properly in response to the reactor trip. The Auxiliary Feedwater (AFW) System actuated as designed in response to the trip. One reactor coolant pump (RCP) did not transfer to its alternate power supply.

"The manual actuation of the Reactor Protection System (RPS) is being reported as a four hour report under 10 CFR 50.72 (b)(2)(iv). The actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv). Notification to NRC was made by Rick O'Rear at 0744 EDT.

"The NRC Senior Resident Inspector was notified of this event."

The licensee also reported that the reactor is being maintained at the normal temperature and pressure for this condition. All station service electrical systems and the emergency diesel generators are available and in normal configuration. All emergency core cooling systems are available. Decay heat is being removed using steam dump to the main condenser and feedwater to the steam generators is being provided by the electric main feedwater pump.

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Power Reactor Event Number: 41056
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: CRYSTAL GARBE
HQ OPS Officer: BILL GOTT
Notification Date: 09/19/2004
Notification Time: 12:03 [ET]
Event Date: 09/19/2004
Event Time: 09:34 [CDT]
Last Update Date: 09/19/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
ANTHONY GODY (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

OFFSITE NOTIFICATION DUE TO SIREN ACTIVATION

"At 0934 CDT on 9/19/2004, the Unit 1 and Unit 2 Control Rooms began receiving phone calls reporting an actuation of emergency sirens in the Russellville area. A phone call was made to the Arkansas Department of Health, who controls actuation of the sirens, and the reported that they had indications of the sirens alarming. They suspect that power fluctuations in the area led to the inadvertent alarms.

This report is being made in accordance with ANO Reporting Guidelines "News Release or Government Agency Notification" and 10CFR50.72(b)(2)(xi) since there was a notification of state/county agencies of inadvertent actuation of part of the public notifications."

The licensee notified the NRC Resident Inspector.

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