| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/13/2005 - 10/14/2005 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 42049 | Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: CMT
Region: 3
City: DES MOINES State: IA
County:
License #: 0299-1-77PG
Agreement: Y
Docket:
NRC Notified By: DONALD A. FLATER
HQ OPS Officer: STEVE SANDIN | Notification Date: 10/10/2005
Notification Time: 15:55 [ET]
Event Date: 10/10/2005
Event Time: 09:35 [CDT]
Last Update Date: 10/11/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BRUCE BURGESS (R3)
E. WILLIAM BRACH (NMSS)
| Event Text AGREEMENT STATE REPORT INVOLVING A DAMAGED TROXLER MOISTURE DENSITY GAUGE
At approximately 0930 CDT on 10/10/05, a Troxler moisture density gauge, Model 3430 containing both a 8-9 mCi Cs-137 and 44 mCi Am-241:Be source, was run over by a bulldozer at the new NASCAR track construction site south of I-80 Exit 168 near Newton, IA. The State of Iowa responded to the incident and determined that the source was not breached and that there was no spread of contamination. The damaged gauge was boxed up and transported by the licensee to their office in Des Moines. The State has requested that the manufacturer, i.e., Troxler, examine the gauge at the licensee's facility before shipment to a Troxler repair facility.
The State of Iowa does not plan a press release.
* * * UPDATE FROM D. FLATER TO M. RIPLEY 0715 ET 10/11/05 * * *
The State reported that the serial number of the damaged gauge is 32198.
Notified R3 DO (B. Burgess) and NMSS EO (T. Essig) |
| Power Reactor | Event Number: 42053 | Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: GEORGE SLEEPER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/12/2005
Notification Time: 21:55 [ET]
Event Date: 10/12/2005
Event Time: 17:09 [EDT]
Last Update Date: 10/13/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DAVE PASSEHL (R3)
|
| 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 PARTIAL LOSS OF PLANT PROCESS COMPUTER
"Portions of the Palisades Plant Process Computer (PPC) including the Emergency Response Data System (ERDS) became inoperable due to failure of a plant inverter (EY-210). The failed inverter supplies power to portions of the PPC. The inverter failed for unknown reasons. Options for bypassing the inverter and inverter repairs are being evaluated."
The licensee notified the NRC Resident Inspector.
* * *UPDATE PROVIDED BY MULFORD TO ROTTON AT 0511 EDT ON 10/13/05 * * *
At 0500 the Palisades Plant Process Computer (PPC) including ERDS was declared operable after bypassing plant inverter EY-210 per plant procedure and restoring power to equipment.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42054 | Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK CRIM
HQ OPS Officer: JEFF ROTTON | Notification Date: 10/12/2005
Notification Time: 23:55 [ET]
Event Date: 10/12/2005
Event Time: 22:24 [EDT]
Last Update Date: 10/13/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
JAMES DWYER (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC SCRAM DUE TO REACTOR HIGH PRESSURE SIGNAL
"Unit 2 Reactor automatically scrammed at 2224 [EDT] as a result of an RPS actuation due to Reactor High Pressure. All control rods inserted. The plant is stable. No ECCS or SRV actuation occurred. This report is made pursuant to 50.72(B)(2)(iv)(B). An investigation into the cause is currently in progress."
Electric plant lineup is in a normal stable lineup. Reactor water level is being maintained via main feedwater system and removing decay heat via the steam bypass valves to the main condenser. This event had no effect on Unit 1.
The licensee notified the NRC Resident Inspector, Pennsylvania Emergency Management Agency (PEMA), and the Berks, Chester, and Montgomery County emergency agencies. | |