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Event Notification Report for October 24, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/21/2011 - 10/24/2011

** EVENT NUMBERS **


47354 47364 47365 47366 47367

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Power Reactor Event Number: 47354
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: KEVIN HUBER
HQ OPS Officer: PETE SNYDER
Notification Date: 10/19/2011
Notification Time: 16:22 [ET]
Event Date: 10/19/2011
Event Time: 10:00 [CDT]
Last Update Date: 10/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ROBERT DALEY (R3DO)

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

Event Text

TECHNICAL SUPPORT CENTER EMERGENCY DIESEL NON-FUNCTIONAL

"At 1000 (CDT), on October 19, 2011, the Duane Arnold Energy Center (DAEC) Technical Support Center (TSC) Emergency Diesel Generator (EDG) was declared non-functional due to its failure to maintain required voltage during routine testing. The plant is currently in the process of determining the cause of the failure. Normal power to the TSC is currently available."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM KEVIN HUBER TO VINCE KLCO ON 10/21/2011 AT 1502 EDT * * *

"The TSC Emergency Diesel Generator failure has been identified and corrected. The unit has been successfully tested, restoring the TSC Emergency Diesel Generator and TSC to a functional status."

The licensee has notified the NRC Resident Inspector.

Notified the R3DO (Hills).

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Power Reactor Event Number: 47364
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: TOM PROELL
HQ OPS Officer: VINCE KLCO
Notification Date: 10/21/2011
Notification Time: 16:42 [ET]
Event Date: 10/21/2011
Event Time: 12:50 [CDT]
Last Update Date: 10/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DAVID HILLS (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM DUE TO LOCKOUT OF AUXILIARY POWER TRANSFORMER

"The station experienced a lockout of the 2R Auxiliary Power Transformer. The resulting transient caused an automatic actuation of the RPS system. All control rods fully inserted. A Group 2 Primary Containment isolation occurred. Both 11 and 12 Emergency Diesel Generators started on a loss of voltage signal. Equipment response was that the 11 ESW [Emergency Service Water] pump (cooling for the #11 Emergency Diesel) failed to develop required pressure. The #13-4160V non-safety related bus failed to restore after the transient [and feed the Division 1 Essential Bus]. Additionally, the #15 bus transferred to the 1AR transformer [and is feeding the Essential Bus]."

The #11 Emergency Diesel Generator is currently tagged out of service. Electrical supply is being provided by offsite power. Reactor heat is being removed through the main steam line to the main condenser and reactor water inventory is being provided by the feedwater system. The SRVs lifted and reseated. The HPCI system was manually place into a pressure control mode.

The Minnesota Pollution Control Agency is being notified due to the licensee violating the site discharge canal temperature rate of change limit.

The licensee notified the NRC Resident Inspector.

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Fuel Cycle Facility Event Number: 47365
Facility: LOUISIANA ENERGY SERVICES
RX Type:
Comments: URANIUM ENRICHMENT FACILITY
                   GAS CENTRIFUGE FACILITY
Region: 2
City: EUNICE State: NM
County: LEA
License #: SNM-2010
Agreement: Y
Docket: 70-3103
NRC Notified By: CHARLES SLAMA
HQ OPS Officer: PETE SNYDER
Notification Date: 10/21/2011
Notification Time: 17:05 [ET]
Event Date: 08/24/2011
Event Time: [MDT]
Last Update Date: 10/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
MARK LESSER (R2DO)
DOUG WEAVER (NMSS)
PART 21 GROUP (EMAI)

Event Text

POTENTIALLY UNDERSIZED WELDS ON CENTRIFUGE T-COLUMN BASE PLATE CONNECTORS

Name of the firm constructing or supplying the basic component which contains the deviation or fails to comply:

Engineered Products Department
PO Box 2138
Carlsbad, NM 88221

Description of the deviation or failure to comply which is being evaluated :

Undersized welds were identified on centrifuge T-column to base plate connectors which are still in construction. The welds do not comply with AWS 01.1 and are currently being evaluated for the potential to cause substantial safety hazards. An extent of condition is in progress to identify any further conditions and to provide weld dimensions to the design agent for engineering analysis. This analysis will determine the ability of the steelwork to perform per design requirements.

The date on which the information of suspect deviation defect or failure to comply was obtained:
24 August, 2011

The date on which the evaluation is expected to be complete:
23 November, 2011

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Power Reactor Event Number: 47366
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAVID STANLEY
HQ OPS Officer: VINCE KLCO
Notification Date: 10/21/2011
Notification Time: 20:25 [ET]
Event Date: 10/21/2011
Event Time: 17:20 [EDT]
Last Update Date: 10/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
OTHER UNSPEC REQMNT
Person (Organization):
DAVID HILLS (R3DO)

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

Event Text

OFFSITE NOTIFICATION DUE TO FUEL OIL SPILL

"This event is being reported in accordance with 10CFR50.72(b)(2)(xi). On October 21, 2011, at approximately 1723 hours EDT, notification of a fuel oil spill was made to the US Environmental Protection Agency (EPA), National Response Center. At the time of the event, the plant was in Mode 1 at 100 percent rated thermal power. The fuel oil spill was caused by a leak in an underground pipe outside the protected area, but inside the owner controlled area. The spill is estimated between 1000 to 1500 gallons and is contained onsite. However, a certified wetlands specialist was contacted and determined the area met the criteria for wetlands designation, which in turn made the event reportable. Clean Harbors Incorporated is assisting with the onsite clean-up and remediation.

"Additionally, the Ohio EPA: State Emergency Response Commission, Perry Township Fire Department, Lake County Emergency Planning Committee, and the U.S. Coast Guard were notified in accordance with plant procedures. This event is also being reported in accordance with the plant's Operating License, Appendix B, Environmental Protection Plan, which states, in part, that any occurrence of an unusual or important event that indicates or could result in significant environmental impact causally related to plant operation shall be recorded and reported to the NRC within 24 hours followed by a written report."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 47367
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: JOE O'HARA
Notification Date: 10/22/2011
Notification Time: 01:56 [ET]
Event Date: 10/21/2011
Event Time: 08:57 [EDT]
Last Update Date: 10/22/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
BLAKE WELLING (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 99 Power Operation 99 Power Operation
2 N Y 99 Power Operation 99 Power Operation

Event Text

FITNESS FOR DUTY RULE NOT MET

"At 0857 on 10/21/2011 a condition was reported identifying that 10CFR Part 26 requirement for the FFD Lab Director to be subject to the FFD Rule was not met for the period of 12/12/2010 to 4/28/2011.

"10CFR 26.4(g), 'FFD program applicability to categories of individuals,' provides specific requirements for FFD program personnel.

"Contrary to the above, the FFD Lab Director was not included in the [licensee's] random drug testing program as required by the regulation.

"This event is reportable under 10CFR26.719(b)4 requiring a 24 hour ENS notification."

The NRC Resident Inspector has been notified.

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