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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/13/2004 - 02/16/2004
** EVENT NUMBERS **
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| General Information or Other |
Event Number: 40511 |
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee:
Region: 1
City: HAVERHILL State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MARIO IANNACCONE
HQ OPS Officer: CHAUNCEY GOULD |
Notification Date: 02/10/2004
Notification Time: 11:12 [ET]
Event Date: 02/10/2004
Event Time: [EST]
Last Update Date: 02/10/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
KENNETH JENISON (R1)
ROBERTO TORRES (NMSS) |
Event Text
LOAD OF WASTE ARRIVING AT A WASTE-TO-ENERGY FACILITY SET OFF RADIATION MONITORS
A load of waste or recycle materials that had been transported to Covanta Haverhill, Inc (a waste-to-energy facility) in Haverhill, MA had a radiation measurement of 0.13 mrem/hr when it entered the facility. The driver of the truck was told to return the load back to its origin, BFI facilities, in Peabody, MA without any stops. Once at the origin of the shipment, the load is to be isolated until mitigation by a consultant. A report detailing material identification and disposition shall be submitted to the MA Radiation control Program. |
| General Information or Other |
Event Number: 40514 |
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: CARDINAL HEALTH, INC.
Region: 1
City: CHATTANOOGA State: TN
County:
License #: R-33111
Agreement: Y
Docket:
NRC Notified By: JOHN POLITTE
HQ OPS Officer: JOHN MacKINNON |
Notification Date: 02/11/2004
Notification Time: 15:25 [ET]
Event Date: 02/04/2004
Event Time: 12:00 [EST]
Last Update Date: 02/12/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
CLIFFORD ANDERSON (R1)
GARY JANOSKO (NMSS) |
Event Text
AGREEMENT STATE REPORT INVOLVING A SPILL OF IODINE-131 (UNPLANNED CONTAMINATION EVENT)
"TDRH was notified on 02/11/04 of a spill involving I-131 at the Cardinal Health pharmacy in Chattanooga, TN. This event occurred during the afternoon on 02/04/04. An employee was transferring a stock bottle containing 97 millicuries of I-131 from the glove box to the fume hood. The employee dropped the lead pig and the contents of the vial were spilled. Two employees cleaned the area for approximately 20 minutes. Air samples were collected and bioassays of the workers were performed. The room was immediately closed off and access by personnel limited to once a day to collect air sampling media. The initial bioassay results were above the licensee's action limits but below regulatory limits. As of 02/10/04, bioassays results were below the licensee's action limits. The initial air sample collected 18 hours after the spill indicated a stack concentration of 6.5E-08 microcuries/ml. The area will remain restricted, under negative pressure, with fume hoods running. TDRH was notified by the Senior Manager of Health Physics from the corporate office in California. A written report from the licensee will be submitted within 30 days. This incident is reportable under 1200-2-5-.141©1(i) of" State Regulations for Protection Against Radiation".
Event Report ID No: TN-04-013
Media attention: None
* * * UPDATE FROM SHULTS TO GOTT AT 0905 (EST) ON 2/12/04 * * *
"The correct license number is R-33111. The correct reference in 'State Regulations for Protection Against Radiation' should be 1200-2-5-.141 (2) (c) 1. (i)." |
| Power Reactor |
Event Number: 40517 |
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: EDWIN TAYLOR
HQ OPS Officer: BILL GOTT |
Notification Date: 02/13/2004
Notification Time: 11:00 [ET]
Event Date: 02/13/2004
Event Time: 08:10 [CST]
Last Update Date: 02/13/2004 |
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):
CHUCK CAIN (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
RPS ACTUATION DUE TO LOW STEAM GENERATOR LEVEL
"At 0810 CST on 2-13-2004, all four Steam Generators alarmed with Steam Flow/Feed Flow Mismatch alarms, followed by indication of decreasing level in "D" Steam Generator. The reactor tripped approximately 20 seconds later on Lo-Lo level at 23.5% in "D" Steam Generator, as required. The cause of the loss of feedwater flow to "D" Steam Generator is under investigation.
"All plant safety related systems operated as required. The Steam Dumps, which function to remove excess heat as the secondary systems shutdown, exhibited control problems resulting in operation of the Steam Generator Atmospheric Relief Valves (ARVs) until the steam dump controller setpoint was adjusted and the steam dumps began to operate normally. The steam dumps are currently operating in automatic. The Steam Generator ARVs closed when the steam dumps began to operate.
"The auxiliary feedwater system actuated as designed, and a Feedwater Isolation signal was generated as designed on Lo-Lo Steam Generator Level.
"The plant is currently stable in Mode 3 at NOP and NOT while plant personnel investigate the causes of the trip and formulate the repair/restart plan."
Decay heat is currently being removed via the steam dumps. The plant electrical system responded normally and all emergency diesel generators remain in standby. There are no primary to secondary leaks. The licensee notified the NRC Resident Inspector. |
| Power Reactor |
Event Number: 40518 |
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: LT. ANDERSON
HQ OPS Officer: JOHN MacKINNON |
Notification Date: 02/13/2004
Notification Time: 11:49 [ET]
Event Date: 02/13/2004
Event Time: 07:30 [CST]
Last Update Date: 02/13/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION |
Person (Organization):
ERIC DUNCAN (R3) |
| 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
LOSS OF OFFSITE COMMUNICATIONS
At 0730, Monticello Nuclear Generating Plant became aware of the loss of incoming phone call capability. Investigation determined loss of ENS, HPN (FTS) lines were inoperable as well as the State of MN dedicated line. Commercial incoming calls (inoperable) out calls were operable. By 0930 CST all phone system were restored and determined operable. NRC Operations Center was notified of inoperable ENS phone via backup commercial line.
NRC Resident Inspector was notified of this by the licensee. |
| Power Reactor |
Event Number: 40519 |
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [ ] [ ]
RX Type: [3] CE
NRC Notified By: GREG SCOTT
HQ OPS Officer: ERIC THOMAS |
Notification Date: 02/13/2004
Notification Time: 20:32 [ET]
Event Date: 02/13/2004
Event Time: 05:25 [CST]
Last Update Date: 02/13/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT |
Person (Organization):
CHUCK CAIN (R4) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 3 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
24 HOUR NOTIFICATION PER LICENSEE CONDITION 2.F
"On February 13, 2004, Waterford 3 reactor power reached an estimated maximum reactor power level of 101.9% due to Atmospheric Dump Valve #2 (ADV#2) failing full open. ADV#2 failed open due to the control system setpoint failing low. Operations personnel promptly responded to the condition by reducing turbine load (5 megawatts per minute ) and manually closing ADV#2, to restore plant power. ADV#2 was open for less than a minute. Per the FSAR, this transient is an analyzed event and is bounded by the safety analyses. This event is being reported in accordance with Waterford 3 event notification and reporting procedure, UNT-006-010, which is more conservative than the guidance provided in NRC Inspection Procedure 61706. This event is being reported pursuant to Waterford 3 License Condition 2.F as a 24 hour notification."
The licensee notified the NRC Resident Inspector. |
| Power Reactor |
Event Number: 40521 |
Facility: HATCH
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GREG JOHNSON
HQ OPS Officer: BILL GOTT |
Notification Date: 02/15/2004
Notification Time: 11:16 [ET]
Event Date: 02/15/2004
Event Time: 08:22 [EST]
Last Update Date: 02/15/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL |
Person (Organization):
MARK LESSER (R2) |
| 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
CONTAMINATED AND INJURED EMPLOYEE TRANSPORTED TO OFFSITE MEDICAL FACILITY
No System or Plant affect.
At 08:22 AM EST, an injured Contractor worke[r] who was potentially contaminated was transported by ambulance to an offsite medical facility. The Contract employee fell approximately 15 to 20 feet in the Unit 1 Circulation Water box which is located in the Condenser Bay area. Unit 1 is presently in Cold Shutdown and in Mode 4 for a scheduled Refueling Outage. The employee received cuts to the forehead and nose and an injury to the arm and also some back pain. In an effort to provide medical treatment as the first priority, decontamination efforts were not completed on site and the individual was transported as potentially contaminated. The injured cont[r]act employee was also accompanied by a Health Physics Technician. Upon arrival at the hospital and while receiving medial care, the Health Physics technicians did discover a 500 dpm/cm2 spot of contamination on the back of the head of the injured person. Decontamination efforts are underway while medical treatment is rendered.
The licensee notified the NRC Resident Inspector. |
| Power Reactor |
Event Number: 40522 |
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: HOPE BRADLEY
HQ OPS Officer: HOWIE CROUCH |
Notification Date: 02/15/2004
Notification Time: 20:18 [ET]
Event Date: 02/15/2004
Event Time: 15:19 [CST]
Last Update Date: 02/16/2004 |
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):
CHUCK CAIN (R4) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
A/R |
Y |
20 |
Power Operation |
0 |
Hot Standby |
Event Text
AUTOMATIC REACTOR TRIP WITH AUXILIARY FEEDWATER ACTUATION
The following information was received from the licensee via facsimile:
"At 1519 [CDT] on 2-15-04, the plant was at 20 power, increasing load. During the transfer from the bypass feedwater regulating valves to the main feedwater regulating valves, the main turbine tripped due to a P-14 S/G Hi-Hi level signal. The P-14 signal also caused a Feedwater Isolation Signal (FWIS), which resulted in a Motor Driven Aux Feedwater Actuation (MDAFAS), and Steam Generator Blowdown Isolation Signal.
"Steam Generator levels subsequently shrunk to low levels causing a Steam Generator low level reactor trip at 1524 [hrs]. Sometime after the turbine trip, the turbine driven aux feed pump [(TDAFP)] was manually started to help restore S/G levels. The pump was later manually secured, but then received a subsequent auto-start signal and tripped on overspeed. The TDAFP was declared inoperable at 1535 [hrs]. With the exception of the TDAFP, all safety systems operated properly.
"The plant is currently stable in Mode 3, with the primary plant at 557 deg F and 2235 psig, and pressurizer level at 25%."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 0031 EST ON 2/16/04 HOPE BRADLEY TO GOTT * * *
The following information was received from the licensee via facsimile as a "rewrite of above paragraph 2."
"Sometime after the turbine trip, the Turbine Driven Aux Feedwater Pump (TDAFP) was manually started to help restore S/G levels. Due to decreasing reactor coolant system (RCS) temperature, it was decided to stop the TDAFP since it is a steam load. The steam supply valves were remote manually closed from the control room. At the same time the steam supply valves were closing, the steam generator levels shrunk to low levels causing a Steam Generator low level reactor trip and Turbine Driven Aux Feedwater Actuation (TDAFAS) at 1524. The steam supply valves immediately reopened due to the TDAFAS. It is postulated that this transient in the steam supply caused the pump to overspeed trip. The TDAFP was declared inoperable at 1535. With the exception of the TDAFP, all safety systems operated properly."
The licensee notified the NRC Resident Inspector.
Notified R4DO (Cain). |
| Power Reactor |
Event Number: 40523 |
Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: JAMES WHITE
HQ OPS Officer: DICK JOLLIFFE |
Notification Date: 02/16/2004
Notification Time: 02:58 [ET]
Event Date: 02/16/2004
Event Time: 02:25 [EST]
Last Update Date: 02/16/2004 |
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED |
Person (Organization):
JAMES TRAPP (R1)
JOHN HANNON (NRR)
SUSAN FRANT (IRO)
KEN SWEETSER (FEMA)
JOHN FROST (DHS) |
| 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
UNUSUAL EVENT DECLARED DUE TO SERVICE AIR COMPRESSOR CONTROLLER EXPLODING
At 0225 EST on 02/16/04, the licensee declared an Unusual Event due to the instrument air/service air system service air compressor controller exploding due to an electrical fault. Instrument air compressor alarm #H-16 actuated. The backup ' A' and 'B' instrument air compressors autostarted. The licensee immediately electrically isolated the service air compressor controller. The licensee declared the Unusual Event in accordance with EAL 8.3.2, an explosion or detection of explosion affecting plant equipment or structures within plant protected area boundaries. No other plant equipment or structures were affected. The plant is stable at 100% power. There is no indication of tampering or foreign objects inside the controller. The licensee is investigating the cause. The licensee notified the NRC Resident Inspector and State and Local Officials. The licensee does not plan to issue a press release.
* * * Update at 0425 EST on 02/16/04 from John White to Jolliffe * * *
At 0420 EST on 02/16/04, the licensee terminated the Unusual Event based on the service air compressor controller being electrically isolated and removed from service and the surrounding area secured. The licensee is continuing to investigate the cause of the electrical fault. Plant security personnel determined in accordance with their security tampering procedure that this event is clearly not security related. The licensee notified the NRC Resident Inspector and State and Local Officials of the termination of the Unusual Event. Notified R1DO James Trapp, NRR EO John Hannon, DIRO Susan Frant, FEMA Ken Sweetser, DHS John Frost. |
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