| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/30/2003 - 10/01/2003 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 40201 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: COMPUTALOG
Region: 4
City: FORT WORTH State: TX
County:
License #: L04286
Agreement: Y
Docket:
NRC Notified By: HELEN WATKINS
HQ OPS Officer: JOHN MacKINNON | Notification Date: 09/26/2003
Notification Time: 18:40 [ET]
Event Date: 09/26/2003
Event Time: 12:00 [CDT]
Last Update Date: 09/26/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG PICK (R4)
GARY JANOSKO (NMSS)
| Event Text LEAKING SEALED SOURCE FOUND: 5 CURIE AMERICIUM-241/BERYLLIUM
"A 5 curie AM-241/Be sealed source was found leaking during a routine leak test on September 26, 2003. The removable contamination was 0.081 microcuries. The source is a Gulf Nuclear model 71-1 serial # 71-1448B. The source was transported during September 2003 from the Licensee's Edinburg, TX site to the Ft. Worth site. The contamination was confined to the inside of the transport container and the source housing. A second source that had been stored as a companion in the same down hole storage in Edinburg also had a small amount of contamination on it (399 dpm found, below the 11,000 dpm limit). Therefore, the Edinburg downhole site will be checked by the Licensee for contamination. The storage facility in Edinburg has been taken out of service and off limits until proper surveys are made.
"An update will be provided when more information is available
"Transport vehicle description: Computalog company vehicle"
Texas Incident No: I-8059. |
| General Information or Other | Event Number: 40206 | Rep Org: FRAMATOME ANP
Licensee: EATON CUTLER HAMMER
Region: 1
City: CRANBERRRY TOWNSHIP State: PA
County:
License #:
Agreement: N
Docket:
NRC Notified By: FRAN STARR
HQ OPS Officer: ERIC THOMAS | Notification Date: 09/30/2003
Notification Time: 14:39 [ET]
Event Date: 08/19/2003
Event Time: [EDT]
Last Update Date: 09/30/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
EUGENE COBEY (R1)
MARK LESSER (R2)
JULIO LARA (R3)
JACK FOSTER (NRR)
| Event Text PART 21 REPORT
A potential safety concern was reported regarding failure of the Eaton Cutler-Hammer Freedom Series Heater Pack due to a possible defect in the weld which joins the screw terminal to the heater coil. The following conditions could potentially occur:
- Open circuit resulting in loss of current to a pole in the overload relay. If the load was not running at the time of failure, it would draw excessive current during its next attempted start, and either trip the overload or damage the load. If the load was running at the time of failure, it would slow to a stop while drawing excessive current, which would either trip the overload or damage the load.
- If two heaters failed in the same load, a shock hazard could develop due to voltage to ground on the remaining phase.
The affected Heater Packs are H2009B-3 through H2011B-3, and H2012B-3 through H2017B-3. The following NRC Licensees are affected: DC Cook, Vogtle, and Beaver Valley, Framatome-ANP Inc. in Lynchburg, VA.
Corrective actions by the supplier include daily inspection/replacement of weld electrodes, and destructive sample testing. Corrective actions by Framatome include dedication activities that address weld integrity acceptance.
Framatome recommends licensees replace all affected Heater Packs. |
| Other Nuclear Material | Event Number: 40207 | Rep Org: U.S. ARMY ROCK ISLAND, IL
Licensee: U.S. ARMY ROCK ISLAND, IL
Region: 4
City: TAHOE CITY State: NV
County:
License #: 12-00722-06
Agreement: Y
Docket:
NRC Notified By: THOMAS GIZICKI
HQ OPS Officer: ERIC THOMAS | Notification Date: 09/30/2003
Notification Time: 17:47 [ET]
Event Date: 09/19/2003
Event Time: 12:00 [PDT]
Last Update Date: 09/30/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
JULIO LARA (R3)
CHUCK CAIN (R4)
GARY JANOSKO (NMSS)
| Event Text PART 76.83 - TRANSFER OF RADIOACTIVE MATERIAL
On 9/19/03, the U.S. Army Base at Fort Wainwright, AK sent a shipment of five M-119 Howitzers to the National Forest Service in California to be used for avalanche control. Prior to shipment, the Tritium fire control devices were removed from the Howitzers and placed in boxes. The boxes containing the fire control devices were inadvertently shipped along with the Howitzers. Two boxes, containing a total of 19.4 curies of tritium, ended up at the Alpine Meadows ski resort in Tahoe City, CA. Another 3 boxes, containing a total of 28.2 curies of tritium, ended up at the Mammoth Mountain ski resort in Mammoth Lake, CA.
The National Forest Service will keep the tritium fire control devices in a secure storage location overnight, and they will be picked up by the Radiation Safety Officer from Hawthorne Army Depot on the morning of 10/1/03. |
| Power Reactor | Event Number: 40208 | Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: STEENBERGEN
HQ OPS Officer: ERIC THOMAS | Notification Date: 09/30/2003
Notification Time: 22:52 [ET]
Event Date: 09/30/2003
Event Time: 21:34 [EDT]
Last Update Date: 09/30/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
JULIO LARA (R3)
GENE IMBRO (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | N | 0 | Hot Standby | 0 | Hot Standby | Event Text VALID SPECIFIED SYSTEM ACTUATION
At 2134 EDT on 9/30/03, a reactor trip occurred on RPS (Reactor Protection System) shutdown high pressure. The plant was in Mode 3 performing a cooldown to Mode 4. RCS (Reactor Coolant System) pressure was 1788 psig on the cooldown pressure indicator.
Group 1 safety rods were withdrawn prior to the trip. All other safety and regulating rods were already fully inserted.
All systems performed as required, and the plant is stable in Mode 3. RCS pressure is 1755 psig, and RCS temperature is 526 degrees F.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40209 | Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: SALGADO
HQ OPS Officer: JOHN MacKINNON | Notification Date: 09/30/2003
Notification Time: 23:11 [ET]
Event Date: 09/30/2003
Event Time: 20:14 [CDT]
Last Update Date: 09/30/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
JULIO LARA (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 85 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM ON LOW REACTOR VESSEL WATER LEVEL.
Dresden Unit 2 automatically scrammed on low reactor vessel water level after "2C" reactor feed pump tripped (1 of 2 running). All systems responded as required (all rods fully inserted). Investigation into reactor feed pump trip cause has begun.
The NRC Resident Inspector will be notified of this event by the licensee. |
| Power Reactor | Event Number: 40210 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MIKE HIMEBAUCH
HQ OPS Officer: GERRY WAIG | Notification Date: 10/01/2003
Notification Time: 00:43 [ET]
Event Date: 09/30/2003
Event Time: 20:50 [EDT]
Last Update Date: 10/01/2003 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JULIO LARA (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 84 | Power Operation | Event Text PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS DUE TO INOPERABLE CONTROL CENTER HVAC
"With the plant in Mode 1 and 100% reactor power at 2043 [EDT] on September 30, 2003, while shifting divisions of Control Center HVAC (CCHVAC), the Division 1 chiller failed to start and Division 1 CCHVAC was declared INOPERABLE. At 2050, a restart of Division 2 CCHVAC was attempted and the Division 2 chiller failed to start. Division 2 CCHVAC was declared INOPERABLE, and the plant entered LCO 3.0.3 as required by LCO 3.7.4 Condition D. Plant shutdown was initiated at 2146. Division 1 CCHVAC was declared OPERABLE at 2315, and LCO 3.0.3 was exited. Plant shutdown was terminated at 2315 with the reactor at 84% power. Division 2 CCHVAC remains INOPERABLE and under investigation, with plant operating under LCO 3.7.4 Condition A. Plans are to return to 100% reactor power. All ECCS systems remained OPERABLE during this event.
"The NRC Resident Inspector has been notified. This report is being made pursuant to 10 CFR 50.72(b)(2)(i) and 10 CFR 50.72(b)(3)(v)(D)." | |