| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/25/2013 - 04/26/2013 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 48942 | Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: SABIC
Region: 4
City: BAY ST. LOUIS State: MS
County:
License #: MS-689-01
Agreement: Y
Docket:
NRC Notified By: BRANDY FRAISER
HQ OPS Officer: JOHN SHOEMAKER | Notification Date: 04/18/2013
Notification Time: 17:07 [ET]
Event Date: 03/16/2013
Event Time: [CDT]
Last Update Date: 04/18/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DRAKE (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - MALFUNCTIONING GAUGE SHUTTER
The following report was received via email:
"The licensee RSO [Radiation Safety Officer] notified [Mississippi] DRH [Division of Radiological Health] of malfunctioning gauge shutter discovered upon leak testing on 3/16/13. The gauge is a Kay Ray 7700 J, Source Model Kay Ray 7064 and is mounted on functioning pipe and is currently in use, however, the shutter will not close. The [licensee] RSO, stated a technician was on-site to deliver an estimate to be received by the following week. Until then, the licensee stated the gauge would continue to be used as usual.
"Update: On 4/5/13, [the license RSO] called to notify [Mississippi] DRH the gauge is still being used, he has received the quote for the repair, and is waiting for the appointment scheduled by the technician (3 weeks from this date).
"Update: Formal report received by SABIC on 4/17/13 which includes description of the incident, as stated above. At this time, [the licensee RSO] is still awaiting the appointment for repair or replacement of the gauge."
Mississippi Report #: MS-13001 |
| Power Reactor | Event Number: 48966 | Facility: LASALLE
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: MICHAEL FITZPATRICK
HQ OPS Officer: DONALD NORWOOD | Notification Date: 04/25/2013
Notification Time: 12:23 [ET]
Event Date: 04/18/2013
Event Time: 13:25 [CDT]
Last Update Date: 04/25/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DAVID HILLS (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text LOW PRESSURE CORE SPRAY INOPERABLE
"On 4/18/2013, while attempting to raise Unit 1 reactor level with the Low Pressure Core Spray (LPCS) system, LPCS injection valve 1E21-F005 failed to open as required when the associated control switch was held in the 'OPEN' position. The Unit Supervisor declared the LPCS system inoperable, and the appropriate Technical Specification time clocks were entered. Troubleshooting determined that the problem was a faulty control switch.
"The control switch has been replaced and LPCS returned to an operable status.
"Initial review of this event determined that it was not reportable; however, subsequent review caused the event to be re-evaluated and classified as reportable under 10CFR50.72(b)(3)(v)(D) and 50.73(a)(2)(v)(D) as an event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.
"The station is continuing to evaluate the reportability of this event."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 48968 | Facility: FARLEY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOSH CARROLL
HQ OPS Officer: BILL HUFFMAN | Notification Date: 04/25/2013
Notification Time: 20:51 [ET]
Event Date: 04/25/2013
Event Time: 17:18 [CDT]
Last Update Date: 04/25/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MARVIN SYKES (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text VENT STACK RADIATION MONITORS DE-ENERGIZED FOR SHORT DURATION DURING PRE-PLANNED MAINTENANCE
"This is a report of a loss of emergency assessment capability as required by 10 CFR 50.72(b)(3)(xiii).
"On April 25, 2013 at 1718 CDT, with Unit 2 in Mode 6 during a refueling outage, power was interrupted to all Unit 2 vent stack radiation monitors as part of a pre-planned activity to connect the radiation monitors to an alternate temporary power supply to support de-energizing the normal power source for preventative maintenance. The connection to the alternate supply was completed and power was restored to the vent stack radiation monitors at 1845 CDT. While the radiation monitors were without power, pre-planned compensatory measures were implemented to monitor vent stack discharge and to minimize activities that posed a potential for release.
"At the completion of the preventive maintenance on the normal power supply, power to the vent stack radiation monitors will again be briefly interrupted to reconnect the normal power source to the monitors. The pre-planned compensatory measures will again be utilized during this power interruption. An update to this report will be provided following the restoration of normal power to the radiation monitors.
"The NRC Resident inspector has been informed." |
| Power Reactor | Event Number: 48969 | Facility: LASALLE
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: TODD GRANLUND
HQ OPS Officer: BILL HUFFMAN | Notification Date: 04/25/2013
Notification Time: 22:23 [ET]
Event Date: 04/25/2013
Event Time: 20:19 [CDT]
Last Update Date: 04/25/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
DAVID HILLS (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 57 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM FOLLOWING TRIP OF CIRC WATER PUMPS
"This report is being made pursuant to 10CFR50.72(b)(2)(iv)(B), RPS Actuation (scram). At 2019 CDT on April 25, 2013, LaSalle Unit 2 was manually scrammed due to a loss of Condenser Circulating Water. The Unit was manually scrammed after the condenser circulating water pumps tripped due to high level in the turbine building condenser pit. The high level in the condenser pit was caused by a leak on the upper manway of the condenser water box during a maintenance activity. MSIV's were isolated due to loss of heat sink. The safety relief valves were used in pressure control mode. Current plant status: reactor level is stable and reactor pressure is stable. The condenser water box manway leak has been isolated. The plant will remain in hot shutdown pending investigation and repairs."
Reactor Core Isolation Cooling (RCIC) is being used in the pressure control mode.
The licensee has notified the NRC Resident Inspector. | |