Alert

Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

Event Notification Report for December 22, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/21/2004 - 12/22/2004

** EVENT NUMBERS **

41217

41275

41276

!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor	Event Number: 41217
Facility: ARKANSAS NUCLEAR Region: 4 State: AR Unit: [1] [2] [ ] RX Type: [1] B&W-L-LP,[2] CE NRC Notified By: CHUCK OLSON HQ OPS Officer: STEVE SANDIN	Notification Date: 11/23/2004 Notification Time: 12:07 [ET] Event Date: 11/23/2004 Event Time: 09:45 [CST] Last Update Date: 12/21/2004
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): JEFFERY CLARK (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

LOSS OF EMERGENCY ASSESSMENT CAPABILITY DUE TO FAILURE OF SPDS

The Safety Parameter Display System (SPDS) is not transmitting data to the Technical Support Center. The cause of the failure is unknown at the present time. The Computer Support Group is attempting to restore transmission capability.

The licensee will inform the State of Arkansas as a courtesy and has informed the NRC Resident Inspector.

* * * RETRACTION FROM R. SCHELDE TO J. MACKINNON 1523 ET 12/21/04 * * *

"On 11/23/2004, at 1207 EST, Arkansas Nuclear One notified the NRC Operations Center that the Safety Parameter Display System (SPDS) was not transmitting data to the Technical Support Center (TSC) for a time period greater than 1 hour. Subsequent investigation determined that the SPDS was, in fact, operable during the time it was believed to be inoperable. Specifically, the Ramtek display was in service and updating normally during the time that SPDS was suspected to be inoperable. Although the SPDS consoles in the TSC were inoperable during this time, data was retrievable via the SPDS monitor touch screens."

The licensee notified the NRC Resident Inspector.

Notified R4 DO (B. Spitzberg)

Research Reactor	Event Number: 41275
Facility: TEXAS A&M UNIVERSITY RX Type: 1000 KW TRIGA (CONVERSION) Comments: Region: 4 City: COLLEGE STATION State: TX County: BRAZOS License #: R-83 Agreement: Y Docket: 05000128 NRC Notified By: WARREN REECE HQ OPS Officer: JOHN MacKINNON	Notification Date: 12/21/2004 Notification Time: 14:47 [ET] Event Date: 12/21/2004 Event Time: 12:45 [CST] Last Update Date: 12/21/2004
Emergency Class: UNUSUAL EVENT 10 CFR Section: 50.72(a) (1) (i) - EMERGENCY DECLARED	Person (Organization): BLAIR SPITZBERG (R4) PAT MADDEN (NRR) PETER WILSON (IRD) SANDRA WASLTER (NMSS) KAREN (DHS) KEVIN (FEMA)

Event Text

UNUSUAL EVENT DECLARED DUE TO A GRASS FIRE.

A small grass fire started near Texas A&M Gamma Shack and headed away from the Gamma Shack and away from Texas A&M TRIGA Reactor Confinement building (located 100 yards away from the fire). The grass fire did not threaten the Gamma Shack or the Reactor Confinement building. Licensee entered an unusual event per Standard Operating Procedure Section 9, Procedure D.1 (major fire - major fire is a fire that cannot not be extinguished with one fire extinguisher). The reactor was scrammed at 1249 CST and all 5 rods fully inserted into the core (reactor was at 1000 KW when it was scrammed). Local Fire Department and local police responded. Fire Department extinguished the fire. No damage to the Gamma Shack. Gamma Shack is used to store cesium-137 and cobalt-60 calibration sources (sources were stored down in their respective wells). Licensee exited the Unusual Event at 1347 CST after the fire was extinguished by the local fire department. The TRIGA reactor will be restarted later this afternoon. No releases or injuries due to the fire.

Power Reactor	Event Number: 41276
Facility: ARKANSAS NUCLEAR Region: 4 State: AR Unit: [ ] [2] [ ] RX Type: [1] B&W-L-LP,[2] CE NRC Notified By: STEPHENIE PYLE HQ OPS Officer: JOHN MacKINNON	Notification Date: 12/21/2004 Notification Time: 15:48 [ET] Event Date: 12/20/2004 Event Time: 15:30 [CST] Last Update Date: 12/21/2004
Emergency Class: NON EMERGENCY 10 CFR Section: OTHER UNSPEC REQMNT	Person (Organization): BLAIR SPITZBERG (R4)

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

SUSPECTED FAILED FUEL ASSEMBLIES

"Arkansas Nuclear One (ANO) was verbally notified at 1530 CST on 12/20/04 by Framatone ANP, Inc. that a secondary review of preliminary results of fuel UT data evaluations resulted in conservative reclassifications of assemblies as now being suspect of containing a failed pin. This verbal notification was documented in subsequent correspondence received from Framatone on 12/21/04. Specifically, rods are now suspected of being failed in ANO Unit 2 fuel assemblies AKC401, AKC504, AKD001, AKF103, and AKF110, which were previously identified as clear of fuel failures based on re-scan data as determined in the preliminary report. The identified assemblies were loaded in Holtec Cask Numbers 10, 11, 12, and 13, during the November and December, 2004 cask loading campaign.

"Appendix B, Section 2.1.1, of the Certificate of Compliance (CoC) Number 1014 for the Holtec HI-STORM 100 allows for the loading of "intact" fuel assemblies. Based on the new information from Framatone, the suspect fuel assemblies do not meet the requirements of "intact". Section 2.2 of the Holtec CoC requires a 24-hour Notification for the failure to meet fuel specifications or loading conditions."

The licensee notified the NRC Resident Inspector.

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