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Event Notification Report for January 6, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/03/2014 - 01/06/2014

** EVENT NUMBERS **


49676 49685 49690 49691

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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: 49685
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DARRELL LAPCINSKI
HQ OPS Officer: JEFF ROTTON
Notification Date: 12/31/2013
Notification Time: 14:51 [ET]
Event Date: 12/31/2013
Event Time: 09:33 [CST]
Last Update Date: 01/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
MICHAEL KUNOWSKI (R3DO)

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

Event Text

UNANALYZED CONDITION DUE TO REMOVAL OF MULTIPLE STEAM GENERATOR LATERAL SUPPORT SHIMS AND BUMPERS

"Prairie Island Unit 2 is currently in Mode 3 with RCS [Reactor Coolant System] at Tave 547 degrees and 2235 psig and preparing for reactor startup following steam generator replacement outage 2R28.

"At 0933 December 31, 2013 it was discovered that multiple upper lateral support shims and bumpers were removed from both 21 and 22 steam generators. This resulted in both loops being declared inoperable and entry into Tech. Spec. [Technical Specification] LCO [Limiting Condition of Operation] 3.4.5 Condition D. It also placed the Unit 2 Reactor Coolant System in an unanalyzed condition for Seismic and LOCA analyses and required this 8 hour report under 10 CFR 50.72(b)(3)(ii)(B).

"During this condition both reactor coolant loops were in operation, adequately removing decay heat and keeping Prairie Island in a safe condition.

"Tech Spec [LCO] 3.4.5 Condition D requires 3 immediate actions: 1. Place the rod control system in a condition incapable of rod withdrawal; action is completed. 2. Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet shutdown margin; action is completed. 3. Initiate action to restore one RCS loop to operable status and operation; action was immediately initiated.

"Actions have been initiated to reinstall all shims and bumpers in both steam generators. Once these actions are completed and verified the unanalyzed condition will be corrected and Technical Specification [LCO] 3.4.5 Condition D will be exited. These actions are expected to be completed by 1600 on December 31, 2013."

The licensee notified the NRC Resident Inspector.

* * * UPDATE AT 1653 EST ON 1/3/2014 FROM TERRY BACON TO MARK ABRAMOVITZ * * *

"Technical Specification 3.4.5 Condition D was exited on December 31, 2013 at 1728 [CST], when 21 and 22 Steam Generator Upper Lateral Supports were restored to the proper configuration to meet seismic acceptance criteria. Additionally, based on further analysis, it was determined that with both Reactor Coolant Loops inoperable that this condition is a loss of safety function and reportable under 50.72(b)(3)(v)(B).

"The licensee has notified the NRC Resident Inspector."

Notified the R3DO (Kunowski).

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Power Reactor Event Number: 49690
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROBERT CAMENISCH
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 01/03/2014
Notification Time: 22:07 [ET]
Event Date: 01/03/2014
Event Time: 15:00 [EST]
Last Update Date: 01/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
ROBERT HAAG (R2DO)

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

ABGTS POTENTIALLY INOPERABLE FOR BOTH UNITS UNDER WORST-CASE CONDITIONS

"At 1500 EST on 01/03/2014, TVA determined that during certain conditions, Service Air usage (air used for non-safety related tools/equipment) could result in introducing air into the Auxiliary Building Secondary Containment Enclosure that could, in worst-case conditions, exceed the margin required to maintain the Auxiliary Building Gas Treatment System (ABGTS) operable for Sequoyah Units 1 and 2. ABGTS is required to be operable for both units by Technical Specifications. This is an unanalyzed condition that could prevent both trains of ABGTS from performing [their] safety function[s]. Service air has been isolated to the Auxiliary Building and is under administrative controls until further analysis [is] complete. This is additional information discovered during follow-up evaluation regarding the issue identified in LER 50-327/2013-004. Further analysis will be performed to determine safety significance."

There is 1600 scfm margin in the ABSGTS. The Service Air compressors have an 1850 scfm capacity.

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 49691
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PAUL MARVEL
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/04/2014
Notification Time: 01:22 [ET]
Event Date: 01/03/2014
Event Time: 23:00 [EST]
Last Update Date: 01/04/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
RAY MCKINLEY (R1DO)

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

SIREN ACTIVATION CAUSED BY EQUIPMENT MALFUNCTION

"Limerick Generating Station Main Control Room was informed that a Limerick Emergency Preparedness Zone (EPZ) Siren located in South Coventry, Chester County Pennsylvania area was sounding by an off-duty plant employee and confirmed by the Chester County 911 Dispatch Center. Notification occurred at 2300 hours on 1/13/14. This notification is being made in accordance with SAF 1.9 due to a spurious actuation of Limerick Emergency Preparedness Zone (EPZ) Siren.

"The siren maintenance contractor has been contacted to investigate and silence the sounding alarm.

"No actual Plant emergency exists. The siren activation was caused by equipment malfunction.

"[The] remaining 164 of 165 Limerick EPZ Sirens remain functional, no other reportability threshold(s) have been met or exceeded."

The licensee has notified the NRC Resident Inspector and state and local authorities.

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