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Event Notification Report for December 19, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/16/2011 - 12/19/2011

** EVENT NUMBERS **


47473 47530 47531 47532 47533

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 47473
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: ROBERT KROS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 11/23/2011
Notification Time: 01:43 [ET]
Event Date: 11/22/2011
Event Time: 17:00 [CST]
Last Update Date: 12/16/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
RAY AZUA (R4DO)

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

Event Text

TEMPORARY LOSS OF SHUTDOWN COOLING

"During walkdown of scheduled work it was discovered that HCV-335 (Shutdown Cooling Heat Exchanger Inlet Header Isolation Valve) would not be able to be manually positioned open due to a missing idler gear key.

"Upon a loss of instrument air, HCV-335 would have failed closed, interrupting shutdown cooling flow with no ability to open HCV-335 manually.

"Alternate shutdown cooling pump and paths were available at the time of discovery. No loss of instrument air or interruption in shutdown cooling flow occurred while preparing to align alternate shutdown cooling. An 8 hour LCO under Technical Specification 2.8.1(3)2 was entered at 1700 CST. Alternate shutdown cooling was established on a containment spray pump as allowed by procedure. The 8 hour LCO was exited at 2306 CST. A replacement idler key has been fabricated for HCV-335."

The licensee notified the NRC Resident Inspector.

* * * RETRACTION FROM ERICK MATZKE TO PETE SNYDER AT 1654 EST ON 12/16/11 * * *

"Additional analysis has determined that the shutdown cooling system was capable of performing its design safety functions during the time that the idler key was missing. Therefore this event is being retracted."

The licensee notified the NRC Resident Inspector.

Notified R4DO (Walker).

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Power Reactor Event Number: 47530
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: GEORGE PICCARD
HQ OPS Officer: CHARLES TEAL
Notification Date: 12/16/2011
Notification Time: 16:37 [ET]
Event Date: 12/16/2011
Event Time: 10:17 [EST]
Last Update Date: 12/17/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BILLY DICKSON (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

LOSS OF SAFETY PARAMETER DISPLAY SYSTEM AND EMERGENCY RESPONSE DATA SYSTEM

"At 1017 EST on December 16, 2011, a loss of the Safety Parameter Display System (SPDS) and the Emergency Response Data System (ERDS) occurred due to a process computer malfunction. This loss in capability is being reported as a loss of assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii).

"Indications of related plant variable are available in the Main Control Center. The Visual Annunciator System (VAS) remains functional. Meteorological and process effluent radiological monitor indications are available and dose assessment capability is available and tested functional.

"In the event of a plant emergency, the Emergency Plan can be implemented as assessment capabilities are available under alternate means."

The NRC Resident Inspector has been informed.

* * * UPDATE AT 0022 EST ON 12/17/11 FROM GROFF TO HUFFMAN * * *

"At 2235 EST on December 16, 2011, the Safety Parameter Display System (SPDS) and the Emergency Response Data System (ERDS) were restored following the correction of the process computer malfunction. This loss in capability was reported under a loss of assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii). "

The licensee has notified the NRC Resident Inspector. R3DO (Dickson) notified.

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Fuel Cycle Facility Event Number: 47531
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: JOE BARLETTO
HQ OPS Officer: PETE SNYDER
Notification Date: 12/17/2011
Notification Time: 12:59 [ET]
Event Date: 12/17/2011
Event Time: 00:01 [CST]
Last Update Date: 12/17/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
SCOTT FREEMAN (R2DO)
GORDON BJORKMAN (NMSS)

Event Text

POSSIBLE DEGRADATION IN HIGH PRESSURE FIRE WATER SPRINKLER HEADS

"At 0001 CST, on 12-17-2011, the Plant Shift Superintendent was notified that the C-310 High Pressure Fire Water (HPFW) Sprinkler System #2 had been inspected by Fire Services and thirty-two (32) sprinkler heads had visible corrosion on them. The system configuration was evaluated using EN-C-822-99-047, 'Effects of Impaired Sprinkler Heads on System Operability' and determined that with these heads potentially impaired, a portion of the building would not have sufficient sprinkler coverage. The HPFW system is required to be operable according to TSR LCO 2.4.4.5. C-310 HPFW system #2 was declared inoperable and TSR LCO 2.4.4.5 Required Action B was implemented for the area without sprinkler coverage. Based on past testing results, there is a possibility that the heads would have been able to perform their specified safety function. Once the heads are removed from the system, testing will be performed to determine the actual affect on operability.

"This event is reportable under 10 CFR 76.120(c)(2) as an event in which equipment required by the TSR is disabled or fails to function as designed."

The site instituted compensatory measures included performing a fire patrol walkdown of the area within the first two hours after discovery of the potential degradation and hourly fire patrols thereafter.

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

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Power Reactor Event Number: 47532
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: JIM PETERSON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/18/2011
Notification Time: 09:47 [ET]
Event Date: 12/18/2011
Event Time: 01:19 [CST]
Last Update Date: 12/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BILLY DICKSON (R3DO)

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

EMERGENCY RESPONSE DATA SYSTEM OUT OF SERVICE

"On 12/18/11 at approximately 0119 CST, Clinton Power Station commenced work to repair a failed hard drive on the server that provides data to the Emergency Response Data System (ERDS) link. At 0130, it was determined that the server had a hardware issue. IT personnel are currently in the process of making repairs to re-establish the link. It is estimated that this link will be restored at approximately 1030 CST.

"This event is reportable due to the major loss of emergency assessment capability per 10CFR50.72 (b)(3)(xiii).

"The NRC Resident Inspector has been notified."

* * * UPDATE AT 1229 EST ON 12/18/2011 FROM JIM PETERSON TO MARK ABRAMOVITZ * * *

ERDS was restored at 1122 CST on 12/18/2011.

Notified R3DO (Dickson).

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Power Reactor Event Number: 47533
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DALE SHELTON
HQ OPS Officer: CHARLES TEAL
Notification Date: 12/18/2011
Notification Time: 18:08 [ET]
Event Date: 12/18/2011
Event Time: 09:30 [CST]
Last Update Date: 12/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
BILLY DICKSON (R3DO)

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

Event Text

LOSS OF RHR COOLING DUE TO INCORRECT REACTOR WATER LEVEL INDICATION

"On 12/18/11 at approximately 0930 CST, with the plant in Mode 4, while Operations was lowering reactor water level as part of restoration activities following the Reactor Pressure Vessel hydrostatic test, an automatic reactor scram and Residual Heat Removal (RHR) 'A' pump trip occurred due to a valid Reactor Water Level Low (Level 3) signal. The cause of the low level appears to be due a significant disparity between the Upset and Shutdown Range level instrumentation and the Level 3 RPS [Reactor Protection System] instrumentation. No rod motion occurred during the reactor scram as all control rods were fully inserted at the time of the event. Operations immediately entered the station off-normal procedures for Loss of Shutdown Cooling and Reactor Scram. The 'A' RHR pump was restored at 0956 CST. Reactor coolant temperature increased from approximately 128.7 deg F to 131.7 deg F during the event. At 1112 CST, the scram was reset and at 1216 CST, the off-normal procedures were exited.

"Following the event as part of trouble shooting, maintenance personnel performed a fill and vent of reactor water level transmitter, 1B21N027. At the completion of this fill and vent, indicated water level changed from 195" to 86" on Shutdown Range and from off-scale high (>180") to 103"on Upset Range. No change in other reactor water level indication was observed.

"This event is reportable under 10 CFR 50.72 (b)(3)(v)(B), as an event or condition that could have prevented the fulfillment of a safety function needed to remove residual heat, and 10 CFR 50.72 (b)(3)(iv)(A), event or condition that results in a valid actuation of the reactor protection system (RPS)."

The licensee has notified the NRC Resident Inspector.

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