| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/31/2005 - 06/01/2005 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 41732 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: SOUTHWEST INSPECTION AND TESTING
Region: 4
City: SYLMER State: CA
County:
License #: 5957-19
Agreement: Y
Docket:
NRC Notified By: C.J. SALGADO
HQ OPS Officer: MIKE RIPLEY | Notification Date: 05/27/2005
Notification Time: 22:02 [ET]
Event Date: 05/17/2005
Event Time: 20:00 [PDT]
Last Update Date: 05/27/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GARY SANBORN (R4)
M. WAYNE HODGES (NMSS)
MEXICO CNSNS (FAX) ()
TAS (EMAIL) ()
| Event Text CALIFORNIA AGREEMENT STATE REPORT - STOLEN NUCLEAR GAUGE
A Troxler moisture density gauge was stolen from the back of a pickup truck parked at a licensee employee's residence sometime between 2000 PDT 05/17/05 and 0550 PDT on 05/18/05. The gauge was in its transportation case and the case was strapped down (vice chained) in the back of the truck. The employee delayed notification to the licensee until 5/26/05. The licensee notified the State at 1100 PDT on 05/27/05. The Los Angeles Police Department was notified and the licensee is offering a reward for return of the gauge. The licensee also notified the gauge manufacturer's local representative.
The Troxler was a model 3440, Serial Number 29792, with an 8 milliCuries Cs-137 and a 44 milliCuries Am-241/Be source. |
| Power Reactor | Event Number: 41736 | Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: NED DENNIN
HQ OPS Officer: BILL HUFFMAN | Notification Date: 05/31/2005
Notification Time: 17:22 [ET]
Event Date: 05/31/2005
Event Time: 10:31 [EDT]
Last Update Date: 05/31/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
MARVIN SYKES (R1)
PATRICK HILAND (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 98 | Power Operation | Event Text OPERATION AT GREATER THAN LICENSED POWER LEVER (106% RATED) DUE TO RECIRC PUMP MOTOR GENERATOR SET FAULT
"On Tuesday May 31, 2005, Limerick Unit 2 was operating at 100% power at 10:31 hours when the 2A Reactor Recirculation Motor-Generator speed increased to the high-speed stop. Reactor power increased to approximately 106% and three main steam bypass valves opened as designed to control pressure. Operators reduced power to 98% as directed by emergency operating procedures using the 2B Reactor Recirculation Pump.
"This event caused thermal power to exceed the 100% rated maximum power level of 3458 megawatts thermal specified in section 2.C.(1.) of the Limerick Unit 2 operating license. Therefore, this event is being reported via ENS within 24 hours with a written followup within 30 days as required by section 2.E of the Limerick Unit 2 operating license."
The licensee stated that power level exceeded 100% for approximately 1 minute during the event transient. Both the mechanical and electrical overspeed stops on the MG set were actuated. The licensee reviewed the transient and it does not appear that any other thermal limits were exceeded and there is no indication of any affect on the core or the fuel. Although trouble-shooting of the problem is still in progress, the licensee currently believes that the event was caused by the MG set controller. The licensee plans to remain at approximately 97% power until the problem is resolved.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41737 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: CRAIG SLY
HQ OPS Officer: MIKE RIPLEY | Notification Date: 05/31/2005
Notification Time: 20:26 [ET]
Event Date: 05/31/2005
Event Time: 10:00 [PDT]
Last Update Date: 05/31/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MIKE RUNYAN (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text LOSS AND SUBSEQUENT RESTORATION OF EMERGENCY RESPONSE DATA SYSTEM (ERDS)
"At about 10:00 (PDT) on May 31, 2005, plant personnel discovered that the plant's Emergency Response Data System (ERDS) was not able to transmit data to the NRC. The problem was discovered during a scheduled test to validate changes to the Columbia Generating Station ERDS data point library. This proposed test included initiating the ERDS and synchronizing to the NRC system.
"During the initiation of this test, plant personnel discovered that the ERDS was not able to initiate a connection with the NRC system. The ERDS was subsequently returned to service at 17:15 PDT on May 31, 2005."
The licensee notified the NRC Resident Inspector. | |