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Event Notification Report for July 24, 2006

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/21/2006 - 07/24/2006

** EVENT NUMBERS **

!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor	Event Number: 42657
Facility: HATCH Region: 2 State: GA Unit: [ ] [2] [ ] RX Type: [1] GE-4,[2] GE-4 NRC Notified By: ED BURKETT HQ OPS Officer: JOHN MacKINNON	Notification Date: 06/21/2006 Notification Time: 02:36 [ET] Event Date: 06/21/2006 Event Time: 00:15 [EDT] Last Update Date: 07/21/2006
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION	Person (Organization): SCOTT SHAEFFER (R2)

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 COOLANT INJECTION (HPCI) DECLARED INOPERABLE DUE EXCESSVIE AUX OIL PUMP MOTOR CURRENT

"During routine weekly operation of High Pressure Coolant Injection (HPCI) Auxiliary Oil Pump (AOP), 2E41C002-3, the pump displayed indications of excessive motor current after the pump had been inservice for approximately 45 minutes. The pump was secured and, following review of electrical diagrams and consultation with Electrical Maintenance, the operating current of the AOP was checked and determined to be excessive. The AOP was declared inoperable, with the AOP inoperable, the HPCI system cannot be considered operable. The HPCI System is a single train ECCS system. Investigation into the cause of the high motor current is ongoing."

All other Emergency Core Cooling Systems are fully operable including Reactor Core Isolation Cooling (RCIC).

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

*** UPDATE FROM A. DISMUKE TO J. KNOKE AT 0933 ON 07/21/06 ***

"Retraction of NRC Event # 42657: After further review and evaluation it has been determined that the eight hour call made June 21, 2006 per the guidance of 50.72(b)(3)(v)(D) should be retracted.

"On 06/21/2006 at approximately 0015 EDT, Unit 2 was at 100 percent Rated Thermal Power. During routine weekly operation of the High Pressure Coolant Injection (HPCI) Auxiliary Oil Pump, 2E41-C002-3, the pump displayed indications of excessive motor current after the pump had been in-service for approximately 45 minutes. Investigation revealed the running amps to be 46 amps with nameplate data running amps shown as 27 amps.

"An evaluation was performed for the as-found condition that considered the cause and effects of the increased running amps on the ability of the auxiliary oil pump to perform its design function. Specifically, the effect of a shunt resistor short to open was reviewed. Areas reviewed for impact were motor speed, system over pressurization, motor insulation, Environmental Qualification, and motor service life. The results of the evaluation showed that significant margin existed to ensure the auxiliary oil pump design function was maintained. Therefore, the auxiliary oil pump operability was maintained and HPCI operability was also maintained. The HPCI system was immediately removed from service using normal plant procedures; a work order initiated, and the existing motor was replaced to ensure continued long term reliability."

The licensee notified the NRC Resident Inspector. Notified R2DO (Ernstes)

Power Reactor	Event Number: 42715
Facility: LIMERICK Region: 1 State: PA Unit: [1] [2] [ ] RX Type: [1] GE-4,[2] GE-4 NRC Notified By: DAN SEMETER HQ OPS Officer: STEVE SANDIN	Notification Date: 07/19/2006 Notification Time: 01:07 [ET] Event Date: 07/18/2006 Event Time: 22:00 [EDT] Last Update Date: 07/21/2006
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): JOHN KINNEMAN (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

LOSS OF EMERGENCY SIREN CAPABILITY DUE TO ADVERSE WEATHER

"48 of 165 offsite sirens are not functioning due to loss of power/equipment problems because of recent storm. Efforts are in progress to restore power to the affected sirens."

The affected sirens are located in Chester County. Compensatory measures are in effect to alert the public should the need arise.

The licensee informed the NRC Resident Inspector.

*** UPDATE FROM C. PEAKS TO J. KNOKE AT 08:40 EDT ON 07/21/06 ***

The licensee reported that only 22 of 165 sirens are now inoperable. This is less than the reportable (25%) amount of 41 sirens.

The licensee notified the NRC Resident Inspector. Notified R1DO (Kinneman).

Power Reactor	Event Number: 42720
Facility: INDIAN POINT Region: 1 State: NY Unit: [ ] [3] [ ] RX Type: [2] W-4-LP,[3] W-4-LP NRC Notified By: JAMES READY HQ OPS Officer: BILL GOTT	Notification Date: 07/21/2006 Notification Time: 11:06 [ET] Event Date: 07/21/2006 Event Time: 10:30 [EDT] Last Update Date: 07/21/2006
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): JOHN KINNEMAN (R1)

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

Event Text

MANUAL REACTOR TRIP DUE TO SPARKS FROM UNDER MAIN GENERATOR

"At 1031 hours on July 21, 2006, the reactor operator manually tripped the reactor from 100% power resulting in turbine trip and actuation of auxiliary feedwater. This is reportable under 10 CFR 50.72(b)(2)(iv)(B). 31 Reactor Coolant Pump tripped after the reactor trip. All other systems operated as expected. Steam is being condensed by the condenser. The reactor was tripped due to an abnormal condition under the main generator; electrical arcing/sparking was observed. The reactor will remain shutdown until the cause of the arcing/sparking is identified and corrected."

There was no indication of fire but the fire brigade was called out. The observed arcing and sparking from underneath the main generator secured after the turbine trip.

All control rods fully inserted on the reactor trip. The electric plant is in a normal shutdown lineup and the EDGs are operable. The unit is stable and Unit 2 was not affected.

The licensee notified the NRC Resident Inspector and the New York Public Service Commission.

* * * UPDATE PROVIDED BY DON CROULET TO JEFF ROTTON AT 1416 EDT ON 07/21/06 * * *

Licensee reported the AFW actuation as a Specified System Actuation per 10 CFR 50.72(b)(3)(iv)(A).

The licensee notified the NRC Resident Inspector.

Notified the R1DO (Kinneman)

Other Nuclear Material	Event Number: 42722
Rep Org: TEAM INDUSTRIAL SERVICES Licensee: TEAM INDUSTRIAL SERVICES Region: 4 City: ALVIN State: TX County: License #: 42-32219-01 Agreement: Y Docket: NRC Notified By: CHRIS SMITH HQ OPS Officer: JEFF ROTTON	Notification Date: 07/22/2006 Notification Time: 15:24 [ET] Event Date: 07/22/2006 Event Time: 12:00 [CDT] Last Update Date: 07/22/2006
Emergency Class: NON EMERGENCY 10 CFR Section: 30.50(b)(2) - SAFETY EQUIPMENT FAILURE	Person (Organization): JOHN KINNEMAN (R1) LAWRENCE KOKAJKO (NMSS)

Event Text

RADIOGRAPHY CAMERA SOURCE UNABLE TO RETRACT

While performing radiography on a new tank located in the northeast corner of the Milford Power Plant, 55 Shelland Lane, Milford, CT, the magnetic stand fell on the guide tube and crimped the tube and the source cannot be properly retracted into the shielded position. The radiography camera is a model AEA 60B, serial number - B3562 containing a 62 Curie Ir-192 source, serial number - 28814B. The radiography crew established a boundary around the source at a distance where the exposure rate is less than 2 mrem/hr. Access to the boundary is being controlled by the radiography crew through visual surveillance. QSA-Global in Burlington, MA has been contacted to assist in retrieving the source and should be onsite at approximately 1930 EDT on 07/22/06. There are no indications of any abnormal radiation exposures due to this event at this time.

* * * UPDATE ON 7/22/06 AT 2012 EDT FROM C. SMITH TO A. COSTA * * *

QSA-Global personnel were able to remove the kinks from the guide tube and then manually return the source to the device's shielded position. The highest dose received during the procedure, which was complete at 1940 hrs, was 65 mrem to the whole body as measured by pocket dosimetry. Extremity dose measurement will be available after finger dosimetry is processed. The radiography camera will be sent to QSA-Global for evaluation, repairs and leak test.

Notified R1 (J. Kinneman) and NMSS (L. Kokajko).