| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/16/2014 - 01/17/2014 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!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). |
| 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). |
| 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." | |