| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/27/2007 - 03/28/2007 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43254 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: CIRCLE INCORPORATED
Region: 4
City: ST. CHARLES PARISH State: LA
County:
License #: LA-6627-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: BILL HUFFMAN | Notification Date: 03/22/2007
Notification Time: 12:00 [ET]
Event Date: 03/03/2007
Event Time: [CDT]
Last Update Date: 03/22/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG PICK (R4)
GREG MORELL (FSME)
| Event Text AGREEMENT STATE - LOUISIANA - TROXLER GAUGE MALFUNCTION
The State provided the following information via facsimile:
"On March 5, 2007 there was a malfunction with a Troxler gauge. After performing a moisture/density test, the technician squeezed the release handle, pulled up the rod, and walked away from the test location. While walking towards the truck, an assistant told the technician that he had dropped something. When the technician looked, [he] realized that the object that had fallen was the bottom piece on the Troxler gauge rod. The technician told the assistant to stay away from the broken piece. The technician then carefully picked up the piece with a shovel from the truck and placed it on the tailgate. A brief observation of the broken rod was taken by the technician to assure that the [source] pellet was still in place and not dropped on the ground. He then noticed that the weld on the rod was the main cause of the problem. At this time the technician immediately staked out the area and called his equipment manager - a repair technician [redacted] with Gamma-Tron, and his Supervisor [redacted]. He then shoveled the broken rod into the containment box were the gauge was located. It was locked and secured as he transported it to the company equipment container were it was placed and double locked for safety. A sign was placed at the container to keep other employees from disturbing the gauge. All of the previously mentioned personnel were contacted and made aware of the situation. On March 6, 2007, [the technician] from Gamma-Tron placed the source back into the safe position. [The technician from Gamma-Tron] assured the facility that the radioactivity was controlled. [The technician] then took the gauge to QSA Global so the unit could be disposed of properly."
LA report number LA070008 |
| Power Reactor | Event Number: 43259 | Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JASON HANCOCK
HQ OPS Officer: JASON KOZAL | Notification Date: 03/28/2007
Notification Time: 01:51 [ET]
Event Date: 03/27/2007
Event Time: 20:50 [EDT]
Last Update Date: 03/28/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
ANTHONY DIMITRIADIS (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text LOW STEAM GENERATOR WATER LEVEL INITIATED AUXILIARY FEEDWATER SIGNAL AND A REACTOR TRIP SIGNAL
"This 8-hour notification is being made to report that an Auxiliary Feedwater (AFW) system actuation signal was generated and a Reactor Protective Signal (RPS) generated with the reactor subcritical.
"On March 27, 2007 at approximately 2050, Salem Unit 1 was in Mode 3 following a planned manual reactor trip to begin a scheduled refueling outage. Operators had established initial Reactor Coolant System cooldown using the steam dumps for heat removal and the 11, 12, and 13 AFW pumps for steam generator make-up. All three pumps had been previously placed in-service in accordance with plant procedures. As plant cooldown proceeded, narrow range levels in 11, 12, and 13 Steam Generators reached the low steam generator setpoint trip, resulting in a valid ESF actuation (i.e., start signal to the AFW pumps); however all AFW pumps were already in-service.
"The actuation signal also generated a reactor trip signal to be initiated by the reactor protection system; however, the plant was already in a shutdown condition with the reactor trip breakers open.
"The lowest level during this transient occurred in 13 Steam Generator and was 11.3% narrow range level. Steam generator water level was restored to a normal value and the RCS cooldown recommenced. There were no equipment failures that contributed to this event.
"The NRC Resident has been informed." | |