United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for May 24, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/23/2012 - 05/24/2012

** EVENT NUMBERS **


47777 47951 47953

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 47777
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [ ] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: BRENT EFIRD
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/27/2012
Notification Time: 23:11 [ET]
Event Date: 03/27/2012
Event Time: 20:20 [CDT]
Last Update Date: 05/23/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
THOMAS FARNHOLTZ (R4DO)

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

SPENT FUEL HANDLING MACHINE NOT FULLY QUALIFIED FOR A SEISMIC EVENT

"The following condition is being reported by Arkansas Nuclear One, Unit 2 (ANO-2) in accordance with 10CFR 50.72(b)(3)(ii)(B), 'Unanalyzed Condition.' Conservative engineering analysis has determined that the Spent Fuel Handling Machine (2H-3) is not qualified in a design basis earthquake event. Current seismic analysis is indicating a lack of margin for several structural parts of the machine.

"The Spent Fuel Handling Machine (2H-3) is currently parked and de-energized in a safe position and administratively prohibited from being moved over any irradiated fuel assemblies in the spent fuel pool. Until further engineering evaluation or modifications can occur the Spent Fuel Handling Machine (2H-3) will remain in its current position and de-energized."

The licensee has notified the NRC Resident Inspector.

* * * RETRACTION FROM STEVEN COFFMAN TO PETE SNYDER AT 1104 EDT ON 5/23/12 * * *

"The purpose of this notification is to retract the previous Event Notification Report #47777 made by Arkansas Nuclear One, Unit 2 on 03/27/2012. The initial report indicated that the Spent Fuel Handling Machine (2H-3) may not have been qualified during a design basis earthquake event due to seismic analysis indicating a lack of margin for several structural parts of the machine. 2H3 was parked and de-energized in a safe position, and the condition was reported in accordance with 10 CFR 50.72(b)(3)(ii)(B), 'Unanalyzed Condition.'

"Since the initial report, Engineering has completed a new seismic analysis which demonstrates that the discovered conditions of the Spent Fuel Handling Machine structural parts were adequate to preclude structural failure of the machine in the area of the Spent Fuel Pool. References to the calculations that formulate the basis for this conclusion are documented in the Licensee's corrective action program.

"Based on the new seismic analysis, the condition initially reported in EN #47777 did not result in 'an unanalyzed condition that significantly degrades plant safety' and is therefore retracted.

"The NRC Resident Inspector has been briefed on the seismic analysis results and informed of this retraction."

Notified R4DO (Spitzberg).

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Power Reactor Event Number: 47951
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: PATRICK HAARHOFF
HQ OPS Officer: PETE SNYDER
Notification Date: 05/23/2012
Notification Time: 09:34 [ET]
Event Date: 05/22/2012
Event Time: 10:13 [CDT]
Last Update Date: 05/23/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
DAVID HILLS (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

FITNESS FOR DUTY - PERSONNEL ACCESS DENIED

"On May 22, 2012, at approximately 1013 hours CDT, access was denied to an individual who is licensed under Part 10 CFR Part 55 to operate a power reactor. The denial was due to the individual violating the company's Fitness for Duty policy.

"This condition is being reported pursuant to 10 CFR 26.719(b)(2)(ii)."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 47953
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: AMY BURKHART
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/23/2012
Notification Time: 19:54 [ET]
Event Date: 05/23/2012
Event Time: 16:00 [CDT]
Last Update Date: 05/23/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
BLAIR SPITZBERG (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

CRACK IDENTIFIED IN PRESSURIZER HEATER

"During inspections to determine the physical integrity of a failed pressurizer heater it was determined that the heater (number 26) was cracked. Due to the location of the pressurizer heater crack, this is considered a degradation of the RCS Barrier. The initial visual inspection of heater 26 in November of 2011, did not identify the cracking. During efforts to remove the heater, a crack was observed on May 21, 2012. The crack is above and below the heater support plate. The crack is an axial crack showing some branching. The crack is about an inch above and inch below the heater support plate. These inspections were being performed as a result of the operating experience at the Sizewell B reactor in the United Kingdom."

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, May 24, 2012
Thursday, May 24, 2012