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Event Notification Report for December 10, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/07/2007 - 12/10/2007

** EVENT NUMBERS **


43798 43828 43829 43830

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Power Reactor Event Number: 43798
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: DAVE FUNK
HQ OPS Officer: JEFF ROTTON
Notification Date: 11/21/2007
Notification Time: 09:15 [ET]
Event Date: 11/21/2007
Event Time: 03:30 [EST]
Last Update Date: 12/07/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAY HENSON (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
4 N Y 100 Power Operation 100 Power Operation

Event Text

ERDADS COMPUTER SYSTEM FAILURE

"At 0330 on 11/21/07, Unit 4 ERDADS computer system failed and subsequently would not display any data. The plant's other Computer display system continues to show data. However, it has been determined the Emergency Response Data System (ERDS) link from Unit 4 is inoperable. Troubleshooting is in progress and a follow up notification will be made when the Unit 4 Emergency Response Data System is operable.

"The Unit 3 Emergency Response Data System remains operable."

The licensee notified the NRC Resident Inspector.

* * * UPDATE AT 1145 ON 12/7/2007 FROM EDWARD NIELSEN TO JEFF ROTTON * * *

"Repairs are complete and the Unit 4 ERDS link was available at 2321 on 12/1/2007. Subsequent testing and evaluation is complete and the ERDS link has been declared operable at 0800 on 12/7/2007."

The licensee notified the NRC Resident Inspector.

Notified the R2DO (Musser).

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Fuel Cycle Facility Event Number: 43828
Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
                   6903 ROCKLEDGE DRIVE
                   BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: BILLY WALLACE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 12/07/2007
Notification Time: 15:42 [ET]
Event Date: 12/06/2007
Event Time: 15:50 [CST]
Last Update Date: 12/07/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(1) - UNPLANNED CONTAMINATION
OTHER UNSPEC REQMNT
Person (Organization):
RANDY MUSSER (R2)
JOSEPH GIITTER (FSME)

Event Text

UNPLANNED SAFETY SYSTEM ACTUATION AND CONTAMINATION EVENT

"On 12/06/2007 at 1550 [CST] the C-337 unit 5 cell 3 PGLD (process gas leak detection) head in the C-337 unit 5 cell 3 housing actuated and would not clear. Response to the alarm by operators revealed a haze above the cell indicating a UF6 release inside the cell housing. While the operators were responding to the unit 5 Cell 3 alarm, two other PGLD heads actuated in C-337 unit 5 cell 5. To stop the release both cells 3 and 5 were taken below atmospheric pressure. Investigation indicated that a UF6 release had occurred. The amount of material released has not been determined.

"The actuated PGLD heads are Q safety system components. At the time of the incident the cell was operating in a mode which required the system to be operational. This is being reported based on SAR 6.9 Table 1, J2 (unplanned actuation of a Q safety system) and 10 CFR 76.120 (c) (1) (i) (unplanned contamination event).

"The NRC Resident Inspector has been notified of this event."

There was no release to the environment and no personnel contaminations reported.

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Fuel Cycle Facility Event Number: 43829
Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
                   6903 ROCKLEDGE DRIVE
                   BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: BILLY WALLACE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 12/07/2007
Notification Time: 15:47 [ET]
Event Date: 12/06/2007
Event Time: 20:44 [CST]
Last Update Date: 12/07/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(1) - UNPLANNED CONTAMINATION
OTHER UNSPEC REQMNT
Person (Organization):
RANDY MUSSER (R2)
JOSEPH GIITTER (FSME)

Event Text

UNPLANNED SAFETY SYSTEM ACTUATION AND CONTAMINATION EVENT

"On 12/06/2007 at 2042 [CST] C-337 unit 5 cell 5 was being charged and placed on stream and had just gone above atmospheric pressure. At 2044 hours two PGLD (process gas leak detection) heads in the C-337 unit 5 cell 5 actuated and would not clear indicating a potential UF6 release. To stop the release the cell was immediately taken back below atmospheric pressure. Investigation revealed that a UF6 release had occurred causing the PGLD actuation. The amount of material released has not yet been determined.

"The PGLD heads are Q safety system components. At the time of the incident the cell was operating in a mode which required the system to be operational. This is being reported based on SAR 6.9 Table 1, J2 (unplanned actuation of a Q safety system) and 10 CFR 76.120 (c) (1) (i) (unplanned contamination event).

"The NRC Resident Inspector has been notified of this event."

There was no release to the environment and no personnel contaminations reported.

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Power Reactor Event Number: 43830
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: KENT MILLS
HQ OPS Officer: JEFF ROTTON
Notification Date: 12/08/2007
Notification Time: 07:54 [ET]
Event Date: 12/08/2007
Event Time: 00:50 [EST]
Last Update Date: 12/08/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
RICHARD BARKLEY (R1)

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

REACTOR POWER INADVERTENTLY INCREASED ABOVE ACCIDENT ANALYSIS LIMIT

"On December 8, 2007 at 0050, during plant maneuvers to return Unit Two from 84% to 100% reactor power following main turbine control valve testing, the two-minute instantaneous thermal power was inadvertently increased above the accident analysis thermal power limit of 2735.1 thermal megawatts while adjusting main turbine load to maintain Reactor Coolant temperature on program. The maximum power level attained was 2741 thermal megawatts. This is a potentially unanalyzed condition. Prompt operator action was taken to restore reactor power to within limits. Reactor thermal power was restored to within limits [below 2735.1 thermal megawatts] eight minutes later at 0058."

The two-minute instantaneous thermal power was restored to below 2700 thermal megawatts (100% rated thermal power) at 0105.

The licensee notified the NRC Resident Inspector.

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