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Event Notification Report for November 4, 2009

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/03/2009 - 11/04/2009

** EVENT NUMBERS **


45471 45474 45475 45476

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General Information or Other Event Number: 45471
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TICONA POLYMERS, INC
Region: 4
City: BISHOP State: TX
County:
License #: L-02441
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOHN KNOKE
Notification Date: 10/30/2009
Notification Time: 14:26 [ET]
Event Date: 09/22/2009
Event Time: [CDT]
Last Update Date: 10/30/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DALE POWERS (R4DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - STUCK SHUTTER ON GAUGE

The following was received via E-mail:

"On October 30, 2009, the Agency [Texas Department of State Health Services] was notified by the licensee that they were reporting a stuck gauge event. The licensee stated that they realized that they needed to report the event after they reviewed a letter sent out by this Agency [Texas Department of State Health Services] regarding the reporting of stuck shutters on gauges. The stuck shutter was found during a routine inspection on September 22, 2009. The gauge is stuck in the open position, which is the normal operating position for this gauge. Dose rates in the area were measured and found to be normal. The gauge is a Thermo Fisher model SH-F2 containing a 100 millicurie Cesium (Cs) - 137. The gauge is installed on the side of a vessel and does not pose any additional risk to their workers. The Licensee has contacted a repair service to repair the shutter. This Agency [Texas Department of State Health Services] will provide additional information as it is received."

Texas Incident number I-8683

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Power Reactor Event Number: 45474
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: DAN LYON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 11/02/2009
Notification Time: 23:55 [ET]
Event Date: 11/02/2009
Event Time: 22:41 [EDT]
Last Update Date: 11/03/2009
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):
RICHARD BARKLEY (R1DO)

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

Event Text

REACTOR TRIP DUE TO TURBINE TRIP CAUSED BY A GENERATOR LOCK-OUT RELAY ACTUATION

"At 2242 on November 2, 2009 Indian Point Unit 2 reactor tripped from 100% due to a turbine trip. The turbine tripped due to a generator lockout relay actuation. The investigation into the relay actuation is ongoing. All systems responded as expected. Auxiliary feed water is providing steam generator feed and levels are being maintained. No steam safeties opened and no coolant system relief or safety valves actuated. The reactor plant is in mode 3 and stable. Unit 3 was unaffected and remains at 100%."

The trip was characterized as uncomplicated. All rods fully inserted and stabilized at the normal mode 3 no-load Tave and pressure. The shutdown electrical lineup is normal and the unit was not in any significant LCOs at the time of the trip. The licensee stated that they were not performing any maintenance or surveillances at the time of the trip. Initial investigation has not revealed any obvious generator electrical system issues but a detailed investigation is ongoing.

The licensee has notified State and local authorities and the NRC Resident Inspector.

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Power Reactor Event Number: 45475
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: CHRIS KENT
HQ OPS Officer: ERIC SIMPSON
Notification Date: 11/03/2009
Notification Time: 14:23 [ET]
Event Date: 11/03/2009
Event Time: 06:09 [CDT]
Last Update Date: 11/03/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
RICHARD SKOKOWSKI (R3DO)

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

Event Text

DEGRADED CONDITION DUE TO WELD ISSUE

"On 11/3/09 a walkdown of the Unit 2 Drywell identified a leak on a 3/4" ASME Code Class 1 pipe weld near the 2-0202-5B valve, 2B Recirc Pump Discharge valve. The weld is at an elbow in the pipe leading to the 2-220-35B valve. Unit 2 is currently in Mode 5. The weld will be repaired prior to unit startup."

No safety function was lost due to this weld issue. The estimated restart date is 11/26/2009.

The licensee has notified NRC Resident Inspector.

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Power Reactor Event Number: 45476
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [ ] [ ]
RX Type: [3] CE
NRC Notified By: JOHN JARRELL
HQ OPS Officer: VINCE KLCO
Notification Date: 11/03/2009
Notification Time: 23:32 [ET]
Event Date: 11/03/2009
Event Time: 19:03 [CDT]
Last Update Date: 11/03/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
MICHAEL HAY (R4DO)

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

Event Text

FITNESS FOR DUTY - EMPLOYEE TESTED POSITIVE FOR ALCOHOL.

An employee had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's unescorted access to the plant has been suspended. Contact the Headquarters Operations Officer for additional details.

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012