| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/07/2014 - 03/10/2014 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 49863 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: CALFRAC WELL SERVICES CORP
Region: 4
City: SAN ANTONIO State: TX
County:
License #: 02439
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/28/2014
Notification Time: 16:35 [ET]
Event Date: 02/24/2014
Event Time: [CST]
Last Update Date: 02/28/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BOB HAGAR (R4DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - OPERATING ARM FOR NUCLEAR GAUGE BROKEN
The following was received from the State of Texas via email:
"On February 28, 2014, the Agency [State of Texas] received a reciprocity request from a company from the State of Tennessee to perform emergency repairs on a Berthold model LB 8010 nuclear gauge containing a 20 milliCurie cesium-137 source at a generally licensed facility in Texas. The Agency [State of Texas] contacted the Texas licensee and asked if there had been a shutter problem with the gauge. The licensee stated on February 24, 2014, while they were moving the gauge from one location to another, one of their employees noted the operating arm on the shutter appeared bent. The employee attempted to straighten the operating arm and it broke off the gauge. The gauge was placed in the licensee's storage location. The licensee contacted the manufacturer who repaired the gauge shutter on February 25, 2014. The licensee stated no personnel received any significant exposure from the event. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident #: I-9159 |
| Power Reactor | Event Number: 49882 | Facility: SUMMER
Region: 2 State: SC
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: BRYAN BARWICK
HQ OPS Officer: DANIEL MILLS | Notification Date: 03/07/2014
Notification Time: 15:26 [ET]
Event Date: 03/07/2014
Event Time: 13:58 [EST]
Last Update Date: 03/07/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
STEVE ROSE (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Under Construction | 0 | Under Construction | | 3 | N | N | 0 | Under Construction | 0 | Under Construction | Event Text FITNESS-FOR-DUTY REPORT INVOLVING A NON-LICENSED SUPERVISOR
A construction supervisor failed a random fitness-for-duty test. The employee's access to the plant has been revoked.
The NRC Resident Inspector has been notified.
Notified R2DO (Rose). |
| Power Reactor | Event Number: 49884 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DOUGLAS LAMARCA
HQ OPS Officer: JEFF ROTTON | Notification Date: 03/08/2014
Notification Time: 10:25 [ET]
Event Date: 03/08/2014
Event Time: 03:25 [EST]
Last Update Date: 03/08/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
FRED BOWER (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 93 | Power Operation | 93 | Power Operation | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text UNIT 2 LOSS OF SECONDARY CONTAINMENT DUE TO DISCHARGE DAMPER FAILURE
"On March 8, 2014 at 0325 [EST], Secondary Containment Zone 2 (Unit 2 Reactor Building) differential pressure went to 0.0 inches WG [water gauge] following a routine transfer of Unit 2 Reactor Protection System (RPS) Power supplies. Upon restoration from the RPS power supply transfer, one of the Reactor Building Exhaust Fans tripped due to a malfunction of its discharge damper. Zone 2 HVAC was restored at 0335 by placing the other train of fans in service. Zone I (Unit 1 Reactor Building) and III (Common Refuel Floor Area) ventilation remained in service and stable.
"Zone 2 differential pressure recovered to SR 3.6.4.1.1 requirements of 0.25 inches WG within a few minutes and was verified to be stable. LCO 3.6.4.1 was entered at 0325 and exited at 0354. Tech Spec for Secondary Containment Operability requires a negative pressure of at least 0.25 inches water gauge for all three Reactor Building Ventilation Zones.
"There have been no further perturbations in differential pressure and secondary containment remains operable.
"This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a safety function. There is no redundant Susquehanna Secondary Containment System."
The licensee notified the NRC Resident Inspector. | |