United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for October 22, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/19/2012 - 10/22/2012

** EVENT NUMBERS **


47892 48426 48427 48428 48429

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 47892
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: NATHAN SEID
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/02/2012
Notification Time: 19:02 [ET]
Event Date: 05/02/2012
Event Time: 11:55 [CDT]
Last Update Date: 10/19/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
GREG WERNER (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

POTENTIAL UNANALYZED CONDITION WITH CONTAINMENT PRESSURE INSTRUMENTS

"While investigating operating experience from another station it was determined that Fort Calhoun Station (FCS) is subject to similar conditions. The operating experience involved setpoint drift of safety related pressure switches beyond what had been accounted for in the station's safety analyses.

"Following investigation and evaluation, it was determined that pressure switches that provide safety related signals for high containment pressure to the reactor protection system (RPS) and engineered safeguards actuation circuitry may be similarly affected at FCS. The impact of the potential drift was evaluated, and it was determined that neither RPS nor the engineered safeguard circuitry may actuate at the required containment pressure of 5 psig. An evaluation determined that the actuation may not occur until slightly higher than the required pressure. Other systems are currently being evaluated to see if this same condition applies.

"The station is in MODE 5, refueling shutdown condition, and there is no immediate safety concern."

The pressure instruments are located in the penetration area which is subject to elevated temperatures.

The licensee notified the NRC Resident Inspector.

* * * RETRACTION AT 1616 EDT ON 10/19/2012 FROM LUKE JENSEN TO MARK ABRAMOVITZ * * *

"The condition was initially determined to be reportable under 10CFR50.72(b)(3)(ii)(B), plant in unanalyzed condition, based on a conservative assumption that the error introduced violated not only the Technical Specification limit (5.0 psig) but also the safety analysis limit of 5.4 psig, USAR Table 14.1-1. Subsequent evaluation of actual data concluded that the safety analysis limit was not exceeded and therefore not reportable under 10 CFR 50.72(b)(3)(ii)(B).

"LER 2012-004-1 reported this condition under 10CFR50.73(a)(2)(i)(B), 10CFR50.73(a)(2)(ix)(A), and 10CFR50.73(a)(2)(v)(A,B,C,D). Revision 2 of the LER will correct the reporting criteria."

The NRC Resident Inspector was notified by the licensee.

Notified the R4DO (Pick).

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Power Reactor Event Number: 48426
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: OWEN SHOGER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/20/2012
Notification Time: 15:09 [ET]
Event Date: 10/20/2012
Event Time: 11:00 [CDT]
Last Update Date: 10/20/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
STEVE ORTH (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
3 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION DUE TO A POTENTIAL INADVERTENT RELEASE OF TRITIUM

"The notification is being made pursuant to 10 CFR 50.72(b )(2)(xi) due to the fact that Exelon Nuclear has informed the Illinois Emergency Management Agency (lEMA) and the Illinois Environmental Protection Agency (IEPA) of the discovery of a hole in the 'A' Waste Sample Tank resulting in a potential inadvertent release of tritium at Dresden Station. Any release is currently contained within the plant's restricted area. The notifications to lEMA and IEPA were made at 1340 hours CDT on October 20, 2012.

"The tank was out of service and had been emptied for internal inspection. Therefore at the time of discovery, there was no active leak.

"The IEPA/lEMA regulations require notification when newly occurring, event-related unpermitted releases of radionuclides are identified. A release has not been confirmed but is suspected. A review of the historical groundwater monitoring well data trends and trending analysis from wells in proximity to the tank indicates no impact on groundwater. Further investigation of the groundwater in the area of the tank is ongoing to determine if an actual release has occurred. The potential leak was not released to an unrestricted area; therefore there is no anticipated adverse impact to the health and safety of the public.

"Since there was no release to an unrestricted area, 10 CFR Part 20 limits were not impacted.

"The licensee has notified the NRC Resident Inspector."

The Waste Sample Tank normally contains processed rad waste water. The hole was found at the bottom of the tank.

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Power Reactor Event Number: 48427
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: REMZI MERTOGUL
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/21/2012
Notification Time: 03:25 [ET]
Event Date: 10/21/2012
Event Time: 00:09 [PDT]
Last Update Date: 10/21/2012
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
GREG PICK (R4DO)
ELMO COLLINS (R4)
BRUCE BOGER (NRR)
JEFFERY GRANT (IRD)

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

UNUSUAL EVENT DECLARED DUE TO SEISMIC EVENT

"HU1.1 Seismic event identified by earthquake felt in plant and US Geological Survey (USGS)."

An earthquake was felt onsite at approximately 0000 PDT. The licensee stated that two out of three methods for determining if an Unusual Event should be declared were met (i.e. the earthquake was felt in the plant and the earthquake was monitored by the USGS). The licensee characterized the earthquake as a "very mild" event. The licensee stated that, at the present time, there was no indication of damage to either unit and that both units remain at 100% power. The licensee is in the process of conducting walkdowns to confirm there was no damage to the plant.

The USGS classified the magnitude of the earthquake as 5.3.

The licensee notified state and local authorities and the NRC Resident Inspector. Notified other federal agencies (FEMA, DHS, DHS NICC and Nuclear SSA via email).

* * * UPDATE FROM HENRY CLARDY TO VINCE KLCO ON 10/21/12 AT 1448 EDT * * *

As of 1142 PDT on 10/21/12, the licensee terminated from the Unusual Event based on review of completed plant walkdowns. No damage was identified. Both Units are stable and in normal plant operations.

The licensee notified state and local authorities and will notify the NRC Resident Inspector. Notified the R4DO (Pick), NRR EO (Bahadur), IRD MOC (Grant) and federal agencies (FEMA, DHS, DHS NICC and Nuclear SSA via email).

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Power Reactor Event Number: 48428
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: CHARLES HAIDAR
HQ OPS Officer: VINCE KLCO
Notification Date: 10/21/2012
Notification Time: 13:03 [ET]
Event Date: 10/21/2012
Event Time: 08:05 [PDT]
Last Update Date: 10/21/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
GREG PICK (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Hot Shutdown 0 Hot Shutdown

Event Text

OFFSITE NOTIFICATION DUE TO HYDROGEN LEAKAGE

"The control room was notified that an unknown quantity of H2 gas (classified as a minor coupling leak [identified with Snoop liquid leak detector]) is currently being released to the air from the Unit 2 Full Flow Hydrogen skid.

"The Environmental Protection Group reported the leak to the California Emergency Management Agency (Cal EMA) at 0809 PDT and the San Diego Department of Environmental Health at 0812 PDT lAW [plant] procedure S0123-XV-17.3, 'Spill Contingency Plan'. The Hydrogen Gas leak is currently still in progress. There is no gas collection areas. Maintenance is in the process of taking action to terminate the leak."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 48429
Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JOHN MYERS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/22/2012
Notification Time: 03:49 [ET]
Event Date: 10/22/2012
Event Time: 00:10 [CDT]
Last Update Date: 10/22/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
GREG PICK (R4DO)

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

Event Text

POTENTIAL CONDITION COULD BYPASS FLOODING BARRIERS AND AFFECT RESIDUAL HEAT REMOVAL EQUIPMENT

"During a walkdown evaluating potential for adverse consequences of site flooding, per 10CFR50.54(f) request, a condition was identified which had the potential to adversely impact the ability to address external flooding conditions. The old Emergency Offsite Facility (which currently houses information technology offices) has a drain pipe which connects to Sump AA in the Augmented Radwaste (ARW) building and bypasses the flooding barriers erected per maintenance procedure 7.0.11 in the event of site flooding.

"Per the USAR, the basis for site flooding is a flood with concurrent surge effects on exposed safety related structures reaching an elevation of 905 feet. This elevation is 2.0 feet above the grade elevation of 903 feet. Flooding protection for important site facilities is provided by installing temporary barriers protecting to elevation 906 feet. Primary and Secondary Flood Barriers are installed at the ARW building external entrances on the 903 feet elevation to protect the Reactor Building from external flood water. The drain piping from the old EOF floor drain and shower is piped directly to Sump AA in the ARW building basement. This is a 3 inch pipe which drains by gravity. There are no isolation features on the pipe, and no barriers to flooding are provided for this facility, thus the potential exists to bypass the flood barriers which would be erected around the ARW Building. Flooding of the building basement could result, disabling processing equipment. If the basement fills up, flood waters could enter the Reactor Building through the internal entrance, which has no additional protection installed. Floodwaters could then affect equipment which is required to remove residual heat.

"This condition has been determined to be reportable per 50.72(b)(3)(v) - Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of SSCs that are needed to remove residual heat. The potential condition was identified on 10/20/2012. Evaluation of the condition and the potential impact was completed and reportability determined on 10/22/2012. The condition has been entered into the Corrective Action Program."

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Monday, October 22, 2012
Monday, October 22, 2012