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Event Notification Report for January 3, 2014

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Event Reports For
01/02/2014 - 01/03/2014

** EVENT NUMBERS **


49676 49687 49688

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Agreement State Event Number: 49676
Rep Org: OK DEQ RAD MANAGEMENT
Licensee: TAHLEQUAH CITY HOSPITAL
Region: 4
City: TAHLEQUAH State: OK
County: CHEROKEE
License #: OK-15626-01
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/26/2013
Notification Time: 14:35 [ET]
Event Date: 12/13/2013
Event Time: [CST]
Last Update Date: 12/26/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JACK WHITTEN (R4DO)
FSME EVENT RESOURCES (FSME)

Event Text

AGREEMENT STATE REPORT - PACKAGE DELIVERED TO INCORRECT ADDRESS

The following report was received via e-mail:

"This morning we [Oklahoma Department of Environmental Quality] were informed that a package containing a Siemens 20 mCi Ge-68 sealed source used for attenuation correction in a PET scanner was delivered to the wrong address by [a carrier] on Dec. 13. The package was signed for, but the person who signed is not an employee of the licensee: Tahlequah City Hospital (OK-15626-01). It is not presently known who the package was delivered to, but whoever it was realized that it was not intended for them and took it to the hospital where they left it on the loading dock without informing the hospital staff. The package remained on the loading dock until late afternoon on the 13th when it was noticed by shipping and receiving personnel who took it inside with the other deliveries. They did not notice the radiation labels on the package and did not inform radiology of its arrival. Instead it was placed in an unrestricted area until Dec. 20 when Siemens contacted the Nuclear Medicine staff to schedule a time to install the new source. The staff then searched Shipping/Receiving and found the package. The package was intact and had not been opened."

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Power Reactor Event Number: 49687
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BUD HINCKLEY
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 01/01/2014
Notification Time: 15:21 [ET]
Event Date: 01/01/2014
Event Time: 11:00 [EST]
Last Update Date: 01/02/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MICHAEL KUNOWSKI (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

TSC VENTILATION SYSTEM NON-FUNCTIONAL

"At 11:00 EST on Wednesday, January 1, 2014, during a scheduled functional test of the Cook Nuclear Plant (CNP) Technical Support Center (TSC) ventilation system, the following two dampers failed to properly open when the system was placed in emergency mode (ventilation flow directed through the emergency filtration unit):

12-HV-TSC-SD-5, TSC Ventilation Emergency Flow To & From Air Conditioner 12-HV-TSC-AC-1 Volume Damper
12-HV-TSC-SD-7, TSC Ventilation Emergency Filtration Unit 12-HV-TSC-FIL Inlet Volume Damper

"The TSC ventilation system is therefore non-functional. This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to an emergency response facility being non-functional. Repair activities are in progress for repair of the two dampers.

"Under certain accident conditions the TSC may become unavailable due to the inability of the air conditioning and charcoal filtration systems to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary.

"The licensee has notified the NRC Resident Inspector."

* * * UPDATE FROM DAN KURTH TO CHARLES TEAL AT 0220 EST ON 1/2/14 * * *

After repairs were completed, the TSC was restored to service at 0130 EST on 1/2/14.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 49688
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: REESE KILIAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/02/2014
Notification Time: 12:14 [ET]
Event Date: 11/03/2013
Event Time: 03:23 [EST]
Last Update Date: 01/02/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
ROBERT HAAG (R2DO)

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

Event Text

60-DAY REPORT INVOLVING AN INVALID PARTIAL ACTUATION OF UNIT 1 EDG "1A" DUE TO A FAILED RELAY

"This report is being made under 10 CFR 50.73(a)(2)(iv)(A) as an invalid actuation of Emergency Diesel Generator (EDG) 1A in lieu of a 60-day LER. Per NUREG-1022, the following information is provided:

"The specific train and system that were actuated:

"At 0323 hours [EST] on November 3, 2013, the St. Lucie Unit 1 train 'A' EDG automatically started. Troubleshooting revealed that the ESF-A group 7 actuation relay (K507A) failed, providing an invalid Engineered Safety Feature (ESF) 'start' signal to EDG 1A, and the EDG started and operated in the standby mode. The failed relay was replaced, and the post maintenance test was successful.

"Was train actuation complete or partial?

"This was a partial actuation of the 'A' train emergency power system as the 1A EDG output breaker did not close, by design, with power on the emergency busses.

"Did the system start and function correctly?

"The failed 7A actuation relay provided an invalid start signal to EDG 1A that properly responded to the start signal. The EDG output breaker closing logic prevented closure because the 4160 VAC emergency bus was energized at the time the actuation relay failed. The system started and functioned as would be expected for the existing plant conditions."

The licensee informed the NRC Resident Inspector. Notified R2DO (Haag).

Page Last Reviewed/Updated Wednesday, May 14, 2014
Wednesday, May 14, 2014