| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/08/2004 - 01/09/2004 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 40403 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: CALVIN WARD
HQ OPS Officer: BILL GOTT | Notification Date: 12/20/2003
Notification Time: 13:00 [ET]
Event Date: 12/20/2003
Event Time: 09:49 [EST]
Last Update Date: 01/08/2004 | 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):
THOMAS DECKER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text RPS ACTUATION DUE TO LOSS OF TURBINE GENERATOR EXCITATION
On December 20, 2003, at 0949 hours, an automatic reactor trip occurred due to a loss of excitation of the turbine generator. All plant safety functions were maintained throughout the event. The plant was stabilized in Mode 3. All plant safety systems responded normally with the exception of the 2C Auxiliary Feedwater Pump (steam driven) which tripped on mechanical overspeed. The 2A and 2B Auxiliary Feedwater Pumps (electric driven) functioned normally to restore the 2A and 2B Steam Generator levels. Post trip system anomalies include RCS Letdown isolated, Steam Generator Blowdown isolation valves closed, Control Room ventilation system swapped to recirculation mode, and the Fuel Handling Building ventilation system swapped to the Shield Building. An Emergency Response Team has been formed to review these conditions prior to plant restart. This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to the automatic RPS Reactor Trip.
All controls inserted properly. Decay heat is being removed using the turbine bypass valves.
The Licensee notified the NRC Resident Inspector.
* * * UPDATE ON 1/08/04 @ 0625 B Y BRADY TO GOULD * * *
This update is provided to include the 10CFR50.72(b)(3)(iv)(A) notification criterion for the auxiliary feedwater actuation.
The NRC Resident Inspector was notified.,
Reg 2 RDO(Fredrickson) was informed. |
| General Information or Other | Event Number: 40427 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: VULCAN CHEMICALS
Region: 4
City: GEISMAR State: LA
County:
License #: LA-2848-L01
Agreement: Y
Docket:
NRC Notified By: SCOTT BLACKWELL
HQ OPS Officer: JEFF ROTTON | Notification Date: 01/06/2004
Notification Time: 11:40 [ET]
Event Date: 12/02/2003
Event Time: [CST]
Last Update Date: 01/06/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MIKE RUNYAN (R4)
DOUG BROADDUS (NMSS)
| Event Text AGREEMENT STATE REPORT CONCERNING LOST GAUGE
"A Kay-Ray Model 7063P gauge with serial number 12349 and a 500 milliCurie source of Cs-137 was not accounted for during the last Radiation Source Survey. The device has been stored in a locked warehouse with limited access since 1984. It was stored in a secured wooden crate with proper labeling. A search was conducted and interviews performed. As of December 2, 2003 the device has not been found. An email from Thermo Electron Corporation states that the source has decayed to 316.366 milliCurie. Vulcan also notified all of its scrap metal contractors to be on alert for the device." |
| Hospital | Event Number: 40431 | Rep Org: ASSOCIATES AND MEDICAL PHYSICS
Licensee: DOUGLAS CITY HOSPITAL
Region: 3
City: ALEXANDRIA State: MN
County:
License #: 22-167-66-01
Agreement: N
Docket:
NRC Notified By: SUSAN WIESS
HQ OPS Officer: RICH LAURA | Notification Date: 01/08/2004
Notification Time: 17:00 [ET]
Event Date: 03/22/2001
Event Time: 13:30 [CST]
Last Update Date: 01/08/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
| Person (Organization):
ANTON VEGEL (R3)
CHARLIE MILLER (NMSS)
| Event Text MEDICAL EVENT AT DOUGLAS CITY HOSPITAL IN MINNESOTA
Associates and Medical Physics reported 6 related medical events that occurred between 3/22/01 thru 5/14/03 at Douglas City Hospital located in Alexandria, Minnesota. The licensee used Samarium 153 to treat patients for bone pain. The highest intended source strength was 115 milli-curies. The licensee discovered that the patients were actually under-dosed by 34% due to an incorrect dose calibrator setting. There was no significant adverse effects to the patients. Corrective actions were taken to calibrate the dose calibrator. |
| Power Reactor | Event Number: 40432 | Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DENNIS BEAMIS
HQ OPS Officer: RICH LAURA | Notification Date: 01/08/2004
Notification Time: 18:45 [ET]
Event Date: 01/08/2004
Event Time: 17:58 [EST]
Last Update Date: 01/08/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
JAMES NOGGLE (R1)
|
| 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 OFFSITE NOTIFICATION AT SEABROOK
The licensee reported that the upper lights on the meteorological tower were not working. The licensee made an offsite notification to the FAA and will initiate corrective actions.
The licensee notified the NRC resident inspector. |
| Power Reactor | Event Number: 40433 | Facility: OCONEE
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: ROY SMITH
HQ OPS Officer: RICH LAURA | Notification Date: 01/08/2004
Notification Time: 19:12 [ET]
Event Date: 01/08/2004
Event Time: 19:02 [EST]
Last Update Date: 01/08/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
PAUL FREDRICKSON (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 28 | Power Operation | 17 | Power Operation | Event Text TS REQUIRED SHUTDOWN AT OCONEE 1 DUE TO UNIDENTIFIED RCS LEAKAGE
"Event Description: Reactor Coolant System, (RCS) Leakage in excess of TS limits. RCS leakage calculations have shown a gradual increase in leakage following Unit l start-up from a refueling outage. On 1/7/2004 @ 1800 hours an RCS leakage calculation was performed with the calculated leak rate at 0.300 gpm. On 1/8/2004 @ 1225 hours, with Reactor power at approximately 26% Rated Thermal Power (RTP), leakage had increased to 0.778 gpm. Personnel have entered containment and have determined the source to be within the A steam generator cavity. At 1312 hours a power reduction to 17% RTP was initiated to reduce dose sufficiently to allow entry into the cavity in an attempt to identify the exact leak source. On 1/8/2004 @ 1502 hours, the leak rate was calculated to be one gpm which exceeds the allowed leakage for unidentified leakage. Units 2 and 3 are unaffected and remain at 100% RTP.
"Initial Safety Significance: The measured leakage is well within the capacity of the normal RCS make-up system. The increase in leakage rate has been slow, and is not expected to increase significantly prior to completion of the TS required shutdown. The leakage is confined inside containment. At this time, there has been NO RADIOLOGICAL RELEASE associated with this event.
"NOTE: Entry into the emergency plan is not required unless the leakage is => 10 gpm unidentified or => 25 gpm identified, the current leakage is significantly below those limits.
"Corrective Action(s)= Unit shutdown per TS is in progress. Isolation or repair of the leak will be evaluated once the location of the leak source is determined. TS 3.4.13 allows 4 hours to reduce leakage within limits. If the source remains unidentified and leakage remains above limits, the TS requires shutdown to Mode 3 within 12 hours and to Mode 5 within 36 hours."
The NRC resident inspector was notified. | |