| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/30/2004 - 02/02/2004 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 40489 | Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: JERRY RISTE
HQ OPS Officer: ERIC THOMAS | Notification Date: 01/30/2004
Notification Time: 13:26 [ET]
Event Date: 01/30/2004
Event Time: 11:30 [CST]
Last Update Date: 01/30/2004 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
PATRICK LOUDEN (R3)
TERRY REIS (NRR)
JIM CALDWELL (R3)
PAT HILAND (R3)
TIM MCGINTY (IRO)
ROB KIRSIK (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text UNUSUAL EVENT
At 1151 CST, the licensee declared an Unusual Event per chart P.
At approximately 1115 CST, while filling the CARDOX carbon dioxide (CO2) storage tank, the tank had reached the full mark and the operator requested the trucker to stop filling the tank. The operator verified tank filling had stopped and isolated the fill line at the tank. The operator then isolated the fill line at the truck bay. The fill line relief valve lifted, causing the vent line to bleed CO2 through a weep hole in the tank room.
At 1140 CST, the shift manager was informed that CO2 levels in the tank room were at life threatening levels (40,000 ppm at floor level, 30,000 ppm at waist level). At 1155 CST, the shift manager was informed that CO2 concentration had decreased below life threatening levels.
At 1215 CST, no further leakage of CO2 through the weep hole into the room was observed. At 1245 CST, CO2 levels in the CARDOX room and adjacent spaces had returned to at or near normal levels.
At 1343 EST, the NRC decided not to enter Monitoring mode.
The licensee notified the NRC senior resident inspector, along with state and local authorities.
* * * UPDATE AT 1454 EST ON 1/30 2004 FROM J. RISTE TO E. THOMAS * * *
At 1346 the Unusual Event was terminated by the licensee. CO2 levels in all areas of the plant have returned to normal working levels. The CO2 release was terminated at 1239 CST.
Notified P. Louden, T. McGinty, T. Reis, FEMA, DHS (D. Lewis) |
| Hospital | Event Number: 40490 | Rep Org: US DEPT OF VETERANS AFFAIRS
Licensee: VA BOSTON HEALTHCARE SYSTEM
Region: 1
City: BOSTON State: MA
County:
License #: 03-23853-01VA
Agreement: Y
Docket:
NRC Notified By: GARY WILLIAMS
HQ OPS Officer: STEVE SANDIN | Notification Date: 01/30/2004
Notification Time: 13:26 [ET]
Event Date: 01/30/2004
Event Time: 11:51 [EST]
Last Update Date: 01/30/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
| Person (Organization):
PATRICK LOUDEN (R3)
GLENN MEYER (R1)
TRISH HOLAHAN (NMSS)
| Event Text MEDICAL EVENT DUE TO ADMINISTERED DOSE EXCEEDING PRESCRIBED DOSAGE TO THE THYROID
"The medical event occurred at a medical broad-scope permittee authorized under the master materials license issued to the Department of Veterans Affairs, NRC License 03-23853-01VA. The permittee is VA Boston Healthcare System, Boston, Massachusetts.
"The medical event occurred on January 29, 2004, and was discovered the same day.
"The basis for the medical event is under 10 CFR 35.3045(a)(1)(ii) in that an administered dosage differed from the prescribed dosage by more than 20% and resulted in a dose of more than 50 rem to an organ.
"Specifically, the verbal order from the authorized user was for 5 microcuries Iodine 131 and the patient was given 500 microcuries Iodine 131. After the event was discovered, the patient was given a thyroid blocking solution. Based on the patient's resultant thyroid uptake, the permittee computed a dose to the thyroid of approximately 83 rem.
"The authorized user does not anticipate any adverse medical effects to the patient.
"The permittee has implemented initial corrective actions to prevent a recurrence of the circumstances that resulted in the medical event.
"The Department of Veterans Affairs will evaluate the circumstances related to the medical event and submit a written report to NRC, Region III, within 15 days." |
| Power Reactor | Event Number: 40491 | Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [ ] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: WARREN DEAGLE
HQ OPS Officer: ERIC THOMAS | Notification Date: 01/30/2004
Notification Time: 14:35 [ET]
Event Date: 01/30/2004
Event Time: 11:55 [CST]
Last Update Date: 01/30/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
PATRICK LOUDEN (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | A/R | Y | 97 | Power Operation | 0 | Hot Shutdown | Event Text RPS ACTUATION WHILE CRITICAL
Unit 3 experienced an automatic reactor scram due to a main turbine trip. The main turbine tripped due to low oil pressure, the cause of which is under investigation. Primary Containment Isolation System Group 2 and 3 isolations occurred as expected due to the reactor water level decrease following the scram.
After reactor water level was restored to normal (+30 inches), level continued to increase to the reactor feed pump high level trip setpoint. Reactor level was subsequently restored to normal and the reactor feed pumps were restarted and are currently supplying the reactor.
Decay heat is being removed by the main steam system via auxiliary loads. All other systems responded as expected. Current reactor pressure is 850 psi, and level is stable at 30 inches.
The NRC Senior Resident Inspector is in the control room. |
| Fuel Cycle Facility | Event Number: 40492 | Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: ERIC WALKER
HQ OPS Officer: ERIC THOMAS | Notification Date: 01/30/2004
Notification Time: 18:40 [ET]
Event Date: 01/30/2004
Event Time: 09:41 [CST]
Last Update Date: 01/30/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
GEORGE KUZO (R2)
TIM MCGINTY (IRO)
DANIEL GILLEN (NMSS)
| Event Text SAFETY EQUIPMENT FAILURE
At 0941 CST on 1/30/04, the Plant Shift Superintendent (PSS) was notified that High Pressure Fire Water System, C-1, in C-333 building was discovered to be in a potential frozen condition on the system main supply header standpipe. Frozen water in the standpipe could result in the restricted flow or complete loss of water supply to the sprinkler heads. The PSS declared the system inoperable and TSR LCO 2.4.4.5 actions were initiated to remove the system from service.
Freeze out of the system was due to extremely low outside ambient temperatures and a faulty filter room thermostat. The event is reportable as a 24 hour event, as required by 10 CFR 76.120(c)(2)(i); An event in which equipment is disabled or fails to function as designed when the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident. The equipment was required by TSR to be available and operable and no redundant equipment was available to perform the required safety function.
The faulty filter room thermostat was replaced, and the High Pressure Fire Water System was declared operable at 1500 CST. Operations personnel took compensatory measures by checking similar indicators in all process buildings.
The Senior NRC Resident Inspector has been notified of this event. |
| Power Reactor | Event Number: 40493 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: PAUL TELTHORST
HQ OPS Officer: STEVE SANDIN | Notification Date: 01/31/2004
Notification Time: 10:59 [ET]
Event Date: 01/30/2004
Event Time: 18:45 [CST]
Last Update Date: 01/31/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
| Person (Organization):
PATRICK LOUDEN (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 78 | Power Operation | 78 | Power Operation | Event Text CONTRACTOR SUPERVISOR TESTED POSITIVE FOR ALCOHOL
At 1845 hrs on 1/30/04 a contractor supervisor tested positive for alcohol during a for cause fitness-for-duty drug test. The test was administered prior to the individual entering the Protected Area (PA). Site access has been terminated and he was removed from plant access. There was no impact on the plant or plant systems due to this condition.
The licensee informed the NRC Resident Inspector and the Illinois Department of Nuclear Safety (IDNS) representative.
Contact the Headquarters Operations Center for additional details. |
| Power Reactor | Event Number: 40494 | Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: BILL HIGGINS
HQ OPS Officer: JOHN MacKINNON | Notification Date: 02/01/2004
Notification Time: 09:54 [ET]
Event Date: 02/01/2004
Event Time: 04:00 [CST]
Last Update Date: 02/01/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
PATRICK LOUDEN (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 96 | Power Operation | 96 | Power Operation | Event Text HIGH PRESSURE COOLENT INJECTION DECLARED INOPERABLE BUT REMAINS AVAILABLE.
During the Unit 3 scram on 01/30/04 the response of the feedwater level control system caused the RPV (Reactor Pressure Vessel) level to increase higher than expected. RPV level rose above the HPCI steam line. Calculations showed approximately 60 gallons of water entered the steam line.
This response could adversely affect the HPCI system should the same type of event occur and FWLC (Feedwater Level Control) respond the same way on Unit 2. Based on this information and no reasonable assurance that the same response will not occur, the Unit 2 HPCI system is conservatively being declared inoperable. HPCI remains available. Entering Tech Spec 3.5.1 Required Action F.1 (Isolation Condenser is OPERABLE) and F.2 (Restore HPCI to Operable status within 14 days).
A modification is being prepared to change the response of FWLC to preclude this adverse response during a transient.
The NRC Resident Inspector will be notified. |
| Power Reactor | Event Number: 40495 | Facility: LASALLE
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: THOMAS DEAN
HQ OPS Officer: JOHN MacKINNON | Notification Date: 02/02/2004
Notification Time: 02:25 [ET]
Event Date: 02/01/2004
Event Time: 22:34 [CST]
Last Update Date: 02/02/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
PATRICK LOUDEN (R3)
|
| 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 ONE HALF SCRAM SIGNAL DUE TO THE LOSS OF THE "B" REACTOR PROTECTION SYSTEM BUS.
This report is being made pursuant to 10 CFR50.72(b)(3)(iv)(A), system actuation not including Reactor Protection System; due to a trip of the "D" Electric Power Monitoring Assembly on the "B" Reactor Protection System Motor Generator set resulting in a trip of the "B" Reactor Protection System bus. The loss of "B" Reactor Protection System bus caused the actuation of multiple Primary Containment Isolation Systems. Station abnormal procedures have been entered and the plant stabilized. The system actuations that occurred have been verified and restorations of these systems are in progress. Troubleshooting plans are being developed to determine cause of the trip and to correct the deficient condition.
The NRC Resident Inspector was notified of this event by the Licensee. | |