| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/19/2005 - 01/20/2005 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 41324 | Rep Org: NV DIV OF RAD HEALTH
Licensee: TERRACON
Region: 4
City: LAS VEGAS State: NV
County:
License #: 00-11-0326-01
Agreement: Y
Docket:
NRC Notified By: STAN MARSHALL
HQ OPS Officer: JANELLE BATTISTE | Notification Date: 01/12/2005
Notification Time: 12:01 [ET]
Event Date: 01/11/2005
Event Time: 05:30 [PST]
Last Update Date: 01/20/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RUSSELL BYWATER (R4)
LINDA GERSEY (NMSS)
TAS (via email) ()
| Event Text AGREEMENT STATE REPORT INVOLVING STOLEN TROXLER GAUGE
During the time frame of 11:00 pm on January 11, 2005 and 5:30 a.m. on January 12, 2005, a Troxler Model 3430 portable gauge containing 9 mCi of Cs-137 and 44 mCi of Am-241/Be was reported stolen. The serial number on the Troxler gauge is not known at this time. The device was reported as fully locked, with all sources in the storage positions. The Nevada Health Division, Radiological Health Section, was notified by the licensee on January 12, 2005 at approximately 7:00 a.m.
The individual involved was instructed by corporate RSO to notify local police. No other information is known at this time. An investigation is being conducted.
Event Report ID No. NV-05-001
***** UPDATE AT 13:08 EST ON 1/19/05 FROM S. MARSHALL TO M. ABRAMOVITZ *****
The initial information incorrectly identified the gauge as Troxler, Model 3430. The correct Troxler Model is 3450, Serial # 000863. The Event Report ID No. NV-05-001 was incorrect, it should have read Event Report ID No. NV-05-002.
The gauge was found on Friday, 01/14/05, by a private citizen on the curb at a local supermarket. The citizen called the licensee to advise them of the location of the gauge. The licensee will leak test the gauge before returning it to service.
Notified R4DO (Clark), NMSS (Essig), and TAS (Hahn). |
| Power Reactor | Event Number: 41344 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: FREDERICK SMITH
HQ OPS Officer: JOHN MacKINNON | Notification Date: 01/19/2005
Notification Time: 05:54 [ET]
Event Date: 01/19/2005
Event Time: 02:37 [EST]
Last Update Date: 01/19/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ANNE MARIE STONE (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE DUE TO AN UNANALYZED CONDITION
"The environmental temperature of the tornado missile enclosure for the Emergency Diesel Generators during an accident condition when all three testable rupture disks open is expected to exceed the limiting temperature for the structural concrete. A detailed analysis of the capability of the tornado missile enclosure concrete to meet that standard cited in the USAR section 3.8.3.3.7 has not been located. At 0237 on 19 January 2005, Division 1,2 & 3 Diesel Generators were declared inoperable. Actions of Technical Specification 3.8.2 were directed and compliance verified."
NRC Resident Inspector was notified of this event by the licensee. |
| Other Nuclear Material | Event Number: 41345 | Rep Org: GREEN BAY PACKAGING
Licensee: GREEN BAY PACKAGING
Region: 1
City: WINCHESTER State: VA
County:
License #: 48-24598-02
Agreement: N
Docket:
NRC Notified By: MIKE DICKEY
HQ OPS Officer: STEVE SANDIN | Notification Date: 01/19/2005
Notification Time: 11:08 [ET]
Event Date: 01/19/2005
Event Time: 10:30 [EST]
Last Update Date: 01/19/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
HAROLD GRAY (R1)
THOMAS ESSIG (NMSS)
| Event Text FIXED GAUGE OHMART INSTRUMENT SHUTTER LAMP INDICATOR FAILURE
At approximately 10:30 EST on 1/19/05, an Ohmart fixed gauge with a source BAL holder located on an OD-120 scanning platform experienced failure of the shutter lamp indicator circuit. The licensee suspects failure of the micro switch. The source holder contains 300 millicuries of Kr-85 gas. The gauge is used to scan a 60" wide paper web for coating thickness. The licensee confirmed that the shutter is closed. The service company, i.e., Honeywell Measurex located approximately 2 hours driving distance from their facility, has been contacted for repairs. This particular gauge had the source holder, including the shutter, replaced on 11/11/04. |
| Power Reactor | Event Number: 41346 | Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK CRIM
HQ OPS Officer: JOHN MacKINNON | Notification Date: 01/19/2005
Notification Time: 11:08 [ET]
Event Date: 01/18/2005
Event Time: 12:55 [EST]
Last Update Date: 01/19/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
HAROLD GRAY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text 24-HOUR CONDITION OF LICENSE REPORT FOR POTENTIAL NON-COMPLIANCE OF THE FIRE PROTECTION PROGRAM
"The notification is being made pursuant to Unit 2 Operating License for potential non-compliance of the Fire Protection Program.
"At 12:55 on January 18, 2005 following the review of Operating Experience for Wolf Creek (ENS 41327), it was discovered that the pilot lines to the manual pneumatic actuator pilot lines on the Halon bottles for the Halon System for the Auxiliary Equipment Room were incorrectly piped. In accordance with TRM 3.7.6.4 a continuous fire watch was established in the area.
"This event resulted in a condition that could have rendered the Halon System for the Unit 2 Auxiliary Equipment Room inoperable during a fire. The Unit 1 Auxiliary Equipment Room Halon System was not affected and remained operable.
"At this time the cause of this condition is not currently known, and an investigation is ongoing."
NRC Resident Inspector was notified of this event by the licensee.
HOO NOTE: See ENs # 41326 and 41327 for similar reports. |
| Power Reactor | Event Number: 41347 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: GARY OLMSTEAD
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 01/19/2005
Notification Time: 15:54 [ET]
Event Date: 01/19/2005
Event Time: 12:51 [CST]
Last Update Date: 01/19/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
JEFFERY CLARK (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text CALLAWAY AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR LEVEL
"Unit experienced an automatic reactor trip following a momentary loss of power to a process control system power supply that resulted in a low Steam Generator water level. This event is being reported in accordance with 10CFR50.72(b)(2)(iv)(B) due to an automatic Reactor Trip and subsequent Aux Feedwater actuation and Feedwater isolation. On 1/19/2005 at 12:51 CST with Callaway plant at 100% reactor power, a Reactor Trip occurred on low Steam Generator 'A' level due to an apparent momentary loss of power in Control Cabinet [Relay Panel] RP043.
"A failed Primary Power Supply to RP043 replacement was in progress at the time of the trip. A momentary power spike on the in-service backup power supply caused the Main Feedwater Regulating valve [MFRV] 'A' to shut and both Main Feedwater Pumps [MFPs] went to their low speed stops. Attempts by the Reactor Operator to take manual control of 'A' MFRV and the MFPs were unsuccessful resulting in the Reactor Trip.
"Following the reactor trip all systems responded as designed with no abnormal responses.
"The plant is currently stable in Mode 3 with RCS pressure at 2237 psig and RCS temperature at 557.8 F. The Auxiliary Feedwater is currently supplying the Steam Generators with steam flow to the Main Condenser for decay heat removal. All control rods fully inserted.
"Both NRC Resident Inspectors were contacted and responded to the Control Room. Corporate Communications will be providing public information on the plant trip to the media." | |