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Event Notification Report for September 27, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/24/2010 - 09/27/2010

** EVENT NUMBERS **


46267 46274 46276 46279 46280

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General Information or Other Event Number: 46267
Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: MID-AMERICA LOUISA GEN STATION
Region: 3
City: MUSCATINE State: IA
County:
License #: 0040-1-70-FG
Agreement: Y
Docket:
NRC Notified By: MELANIE RASMUSSEN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/22/2010
Notification Time: 13:26 [ET]
Event Date: 09/21/2010
Event Time: 17:30 [CDT]
Last Update Date: 09/22/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
ANGELA MCINTOSH (FSME)

Event Text

AGREEMENT STATE REPORT - DAMAGED FIXED GAUGE

The State of Iowa was notified by Louisa Generating Station, a coal-fired electrical generating plant, that a fixed gauge source had been damaged.

"The facility has two 50 mCi Cs-137 sources attached to coal crushers. The gauges are used as low level alarm detection devices and detect whether or not coal is in the hopper at any given time. At approximately 5:30 p.m. on 9.21.10 there was a machine failure. [The licensee] suspects that as a result of the failure there was vibrational damage to one of the gauges (manufactured by Texas Nuclear, housing model 5192, serial number B2724). The gauge was visibly damaged but has not resulted in elevated rad levels. No employees were exposed as a result of this event. The gauges are mounted 15 ft from the floor in a building that is not occupied by staff. The machine (coal crusher) remains out of service since the time of failure on 9.21.10.

"Again, [the licensee] reports no source damage. Their calibrated instrument reads 0.5-1.0 mrem 1 ft from the source, 0.2-0.3 mrem at 2 ft and 0.1 mrem at 3 ft from the source.

"A technician out of Illinois is scheduled to arrive at the facility on Tuesday, September 28th for further testing and possible repair."

The gauge is located in a contained building. The shutter is normally open and the suspected vibration damage resulted in being unable to close the shutter.

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Power Reactor Event Number: 46274
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: MIKE HOUGH
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 09/23/2010
Notification Time: 17:52 [ET]
Event Date: 09/23/2010
Event Time: 17:14 [EDT]
Last Update Date: 09/24/2010
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):
GEORGE HOPPER (R2DO)

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

Event Text

REACTOR TRIP DUE TO INADVERTENT ENERGIZATION GENERATOR TRIP

"Unit 3 reactor and turbine tripped due to Inadvertent Energization Generator Trip. All systems functioned as normal with the exception of Control Rod G5 in Control Bank A which remains at 18 steps. Entered and exited E-0 Reactor Trip and entered ES-0.1 Reactor Trip Response. All 4kV buses have power from the Unit 3 Start Up Transformer."

Heavy weather conditions existed at the time of the reactor trip and is suspected as the cause for the Inadvertent Energization Generator Trip. Aux feed initiated during the trip recovery due to low steam generator level. Decay heat is being removed using condenser steam dumps and atmospheric steam dumps. There is no primary to secondary leakage. The plant is in its normal shutdown electrical lineup. There was no affect on unit-4 which is shutdown.

The licensee will notify the NRC Resident Inspector.

* * * UPDATE AT 2106 ON 9/24/2010 FROM TIM SEILKOP TO MARK ABRAMOVITZ * * *

"Control Rod G5 in Control Bank A has been verified to be fully inserted. The Rod Position Indicator for Rod G5 currently indicates zero steps after being adjusted."

The licensee will notify the NRC Resident Inspector.

Notified the R2DO (Hopper).

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Power Reactor Event Number: 46276
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: KEVIN DOUGHERTY
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/24/2010
Notification Time: 11:18 [ET]
Event Date: 09/24/2010
Event Time: 10:58 [EDT]
Last Update Date: 09/24/2010
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
DAVID LEW (R1RA)
JACK GROBE (NRR)
JANE MARSHALL (IRD)
LAURA PEARSON (ILTA)
MIKE CHEOK (NRR)
FRED HILL (DHS)
DENNSI VIA (FEMA)
73.71 GROUP (EMAI)

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

UNUSUAL EVENT DECLARED BASED ON SHORT DURATION LOSS OF SECURITY EQUIPMENT

The licensee declared an Unusual Event at 1053 EDT based on a short duration loss of a security system. The basis for the Unusual Event is Emergency Action Level (EAL AU6.1.1.) for a security process issue. Compensatory issues were implemented. The equipment has been restored and proper function is being verified.

The licensee has notified the NRC Resident Inspector, State and local authorities. Contact the HOO for additional details.

* * * UPDATE AT 1323 ON 9/24/2010 FROM JAMES HUBER TO MARK ABRAMOVITZ * * *

The licensee exited the Unusual Event at 1315 EDT on 9/23/2010.

Notified the R1DO (Dentel), NRREO (Lee), IRD (Marshall), ILTAB (Pearson), DHS (Hill), FEMA (Biscoe), and 73.71 group (e-mail).

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Power Reactor Event Number: 46279
Facility: LASALLE
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JOHN KEENAN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/25/2010
Notification Time: 10:24 [ET]
Event Date: 09/25/2010
Event Time: 02:10 [CDT]
Last Update Date: 09/25/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RICHARD SKOKOWSKI (R3DO)

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

HIGH PRESSURE CORE SPRAY SYSTEM ROOM COOLING FANS FOUND NOT OPERATING

"This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D), event or condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident. During steady state operations 2VD05C, Division 3 Switchgear Room / Core Standby Cooling System (CSCS) Pump Room Supply Fan and 2VD07C, Division 3 Switchgear Room / Core Standby Cooling System (CSCS) Pump Room Return Fan were found not operating. Division 3 ventilation supplies cooling to the High Pressure Core Spray System (HPCS), which is a single-train system. At the time of this discovery, there was not assurance that the HPCS would fulfill its safety function without mitigating manual actions due to the fan failure, and thus this condition is reportable. Operators are now briefed to manually operate the fan if needed to maintain proper temperature conditions until maintenance begins, thus restoring system function."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 46280
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: RYAN RICHARDS
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/25/2010
Notification Time: 11:30 [ET]
Event Date: 09/25/2010
Event Time: 02:57 [CDT]
Last Update Date: 09/25/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RICHARD SKOKOWSKI (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 95 Power Operation 95 Power Operation

Event Text

LOSS OF ERDS, SPDS AND TSC PHONE LINES DUE TO UNINTERUPTABLE POWER SUPPLY FAILURE

"On 9/25/10 at approximately 0237 CDT, the site experienced a loss of the Uninterruptable Power Supply UPS Y91. This resulted in a loss of power to the Safety Parameter Display System (SPDS) and site computer servers which disabled the Emergency Response Data System (ERDS). In addition, in-house Technical Support Center (TSC) telephones were lost [the NRC phone lines in the TSC are still available] rendering the TSC non-functional. The alternate TSC is functional and will be used, if needed, to implement the Emergency Plan (EOF Phones were unaffected). Alternate assessment capability is fully functional and will meet necessary requirements to implement the Emergency Plan. Troubleshooting efforts are underway. This event is reportable under 10 CFR 50.72(b)(3)(xiii)."

The licensee stated that the Y91 UPS supplies a non-vital 125 volt dc bus and has no safety impact on plant operation and is not subject to any technical specification LCO.

The NRC Resident Inspector has been notified.

* * * UPDATE FROM MARTIN RAJKOWSKI TO PETE SNYDER AT 1656 ON 9/25/10 * * *

All equipment noted as out of service above has been returned to service as of 1541 CDT on 9/25/10.

Notified R3DO (Skokowski).

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