United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2014 > January 17

Event Notification Report for January 17, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/16/2014 - 01/17/2014

** EVENT NUMBERS **


49710 49717 49732

To top of page
!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 49710
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: DAN LIVERMORE
Notification Date: 01/10/2014
Notification Time: 06:39 [ET]
Event Date: 01/09/2014
Event Time: 23:17 [CST]
Last Update Date: 01/16/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
WAYNE WALKER (R4DO)

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

Event Text

DEGRADED FITTINGS CONNECTED TO CONTAINMENT PENETRATION

"During an engineering walk down inside containment a minor leak from a pipe fitting was discovered on the primary sampling piping connected to penetration M-45. There was previously identified minor leakage from a fitting on this same penetration outside of containment in the auxiliary building. The containment isolation valves are currently tagged closed."

The licensee notified the NRC Resident Inspector.

* * * UPDATE FROM SCOTT MOECK TO JOHN SHOEMAKER AT 1320 EST ON 1/16/14 * * *

"Additional testing was performed on penetration M-45 which determined that the penetration met the required leakage limits. Therefore this issue does not represent a degraded condition for the containment and is not reportable. The previous notification is being retracted."

The licensee has notified the NRC Resident Inspector.

Notified the R4DO (Kellar).

To top of page
Power Reactor Event Number: 49717
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: RYAN ALEXANDER
Notification Date: 01/12/2014
Notification Time: 06:44 [ET]
Event Date: 01/12/2014
Event Time: 03:23 [CST]
Last Update Date: 01/16/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
WAYNE WALKER (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 0 Startup 0 Hot Standby

Event Text

MANUAL REACTOR TRIP FOLLOWING CONTROL ROD POSITION DEVIATION

"After achieving criticality a deviation between control rods was observed by plant personnel. When attempting to level the control rods, one rod could not insert to the level of the rest of the group. A manual reactor trip was initiated by the operating crew. All tripable control rods fully inserted into the core."

The trip was uncomplicated and the licensee is investigating the cause of the control rod position deviation.

The licensee has notified the NRC Resident Inspector.

* * * UPDATE FROM SCOTT MOECK TO JOHN SHOEMAKER AT 1320 EST ON 1/16/14 * * *

Report was updated to indicate 8-hour reportable criteria for Valid Specified System Actuation (Reactor Protection System).

The licensee will notify the NRC Resident Inspector.

Notified the R4DO (Kellar).

To top of page
Power Reactor Event Number: 49732
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: KYLE KOLLER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/16/2014
Notification Time: 15:50 [ET]
Event Date: 11/17/2013
Event Time: 10:00 [CST]
Last Update Date: 01/16/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
RICHARD SKOKOWSKI (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling
3 N Y 100 Power Operation 100 Power Operation

Event Text

60-DAY REPORT FOR INVALID SYSTEM ACTUATION OF EMERGENCY DIESEL GENERATORS

"The following 60-day report is being made under 10 CFR 50.73(a)(2)(iv)(A) for an invalid actuation of the Unit 2, Division 1 and Division 2, Emergency Diesel Generators (EDG) that occurred on November 17, 2013, at 1000 CST. As allowed by 10 CFR 50.73(a)(1) this notification is being made via telephone.

"(a) The specific train(s) and system(s) that were actuated.

"On November 17th, during the required twenty-two year replacement of the ATWS [anticipated transient without scram] level transmitters, the Unit 2, Division 1 and Division 2, Emergency Diesel Generators (EDG) auto-started as a result of maintenance activities. The failure to remove trip relays, in addition to the sequence for the timing of the replacements, resulted in an unexpected and invalid low water level trip. Subsequently, this resulted in an automatic initiation of the Unit 2, Division 1 and 2, EDGs.

"(b) Whether each train actuation was complete or partial.

"Upon receiving the invalid low water level signal, both divisions of EDGs responded as expected for existing plant conditions. Therefore, the actuation was considered a complete actuation of both Division 1 and Division 2 EDGs.

"(c) Whether or not the system started and functioned successfully.

"Both Divisions of EDGs auto-started, achieved rated speed, and idled based upon offsite power being available to the safety related busses. Therefore, this is being considered a successful actuation of the Division 1 and Division 2 EDGs.

"The NRC Resident Inspector has been notified."

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