| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/27/2013 - 08/28/2013 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 49308 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: FRED SCHIZAS
HQ OPS Officer: PETE SNYDER | Notification Date: 08/27/2013
Notification Time: 04:10 [ET]
Event Date: 08/26/2013
Event Time: 23:05 [CDT]
Last Update Date: 08/27/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
BOB HAGAR (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text POST ACCIDENT MONITORING INSTRUMENTATION POWER SUPPLIES POTENTIALLY DEGRADED
"At 2305 on 26AUG13 the Shift Manager Declared PC-ES-1A and PC-ES-1B inoperable due to a Part 21 Notification that called the operability of the equipment into question. PAM [Post Accident Monitoring] Instrumentation LCO 3.3.3.1.A and 3.3.3.1.C were entered for Functions 1 (Reactor Pressure), 3 (Containment Level), and 7 (Containment Pressure). Both divisions are potentially affected. LCO 3.3.3.1.C represents a 7 Day shutdown LCO.
"CR-CNS-2013-6096 identified a Part 21 issue associated with Foxboro Power Supply PC-ES-1A and PC-ES-1B. The Part 21 issue identifies a potential failure mechanism in which the adhesive backing on aluminum tie-wrap base used in the power supply fails and the base becomes detached from the power supply case. The nylon tie-wrap affixed to these bases becomes brittle with age and fails releasing the aluminum base to fall into the power supply where it has the potential to short out electrical equipment and fail the power supply. The equipment affected is: PC-LRPR-1A, PC-LRPR-1B, NBI-PR-2A, and NBI-PR-2B. These power supplies affect both Control Room Reg. Guide 1.97 Cat A instruments and associated PMIS/SPDS points. This instrumentation is utilized for emergency plan actions (EALs) and EOP 3A actions in addition to monitoring the previously mentioned functions. The loss of this instrumentation represents a significant loss of emergency response capability. The affected instruments are for indication only and perform no active safety functions. All of the referenced instrumentation is currently functioning as required.
"This condition has been entered into the CNS Corrective Action Program.
"A 60 day Licensee Event Report is not required for this event."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 49311 | Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THOMAS GARRISON
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 08/28/2013
Notification Time: 03:20 [ET]
Event Date: 08/28/2013
Event Time: 01:48 [EDT]
Last Update Date: 08/28/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ANTHONY MASTERS (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 TECHNICAL SUPPORT CENTER VENTILATION SYSTEM OUT OF SERVICE DUE TO PLANNED MAINTENANCE
"This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the work activity affects the functionality of an emergency response facility. Planned maintenance activities are being performed on 08/28/13 in the Technical Support Center (TSC) HVAC.
"The work includes performance of planned outside air intake valve electrical troubleshooting. The planned work activity duration is approximately 16 hours.
"If an emergency is declared requiring TSC activation during period, the TSC will be staffed and activated using existing emergency planning procedure unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures.
"The Emergency Response Organization team has been notified of the maintenance and the possible need to relocate during an emergency.
"The NRC Resident Inspector has been notified.
"The event poses no threat to the public or station employees." |
| Power Reactor | Event Number: 49312 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: ANGEL BRAY
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 08/28/2013
Notification Time: 05:16 [ET]
Event Date: 08/27/2013
Event Time: 21:52 [CDT]
Last Update Date: 08/28/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
RICHARD SKOKOWSKI (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 94 | Power Operation | Event Text RECIRC PUMP RUNBACK AND POWER REDUCTION
"On August 27, 2013 at 2152 CDT, Monticello Nuclear Generating Plant (MNGP) experienced a runback of [the] 'B' Recirc pump from 87% speed to 71% speed. Operators took action to lock [the] 'B Recirc pump scoop tube. This runback resulted in a power reduction from 100% to 94% RTP [Rated Thermal Power]. With the resultant mismatch between total jet pump flows of the two loops greater than required limits, should a LOCA [Loss of Coolant Accident] occur, the core flow coastdown and resultant core response may not be bounded by the LOCA analyses. It has been determined that this is an unanalyzed condition as defined by 10CFR50.72(b)(3)(ii)(8).
"At 0121 CST on August 28, 2013, MNGP completed reducing power to 88% using 'A' Recirc pump to match total jet pump flows and [the plant] is no longer in an unanalyzed condition. The 'B' Recirc scoop tube remains locked pending investigation."
The licensee has notified the NRC Resident Inspector. | |