| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/16/2004 - 04/19/2004 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 40677 | Facility: OCONEE
Region: 2 State: SC
Unit: [ ] [2] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: MICHAEL DUNTON
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/16/2004
Notification Time: 08:47 [ET]
Event Date: 04/16/2004
Event Time: 01:05 [EDT]
Last Update Date: 04/16/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
| Person (Organization):
STEPHEN CAHILL (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text TRANSPORT OF POTENTIALLY CONTAMINATED PERSON TO OFFSITE MEDICAL FACILITY
A vendor received a possible ankle fracture while working in the Unit 2 Reactor Building (RB). The injured person was descending a ladder and stepped on a roll of poly material and injured his ankle when the roll shifted.
Onsite medical assistance team responded and removed the individual from the RB and prepared him for transport to Oconee Memorial Hospital using a hospital ambulance. Due to the nature of the injury, the individual was unable to stand in the whole body frisker and was transported to the hospital as potentially contaminated. A licensee Radiation Protection Technician (RPT) accompanied the injured person in the ambulance to the hospital where it was determined that the individual was not contaminated.
At this time, there is no media/press interest and no press release is expected by the licensee.
The NRC Resident Inspector was notified by the licensee. |
| General Information or Other | Event Number: 40678 | Rep Org: WESTINGHOUSE NUCLEAR SERVICES
Licensee: WESTINGHOUSE NUCLEAR SERVICES
Region:
City: State:
County:
License #:
Agreement: N
Docket:
NRC Notified By: JIM GRESHAM
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/16/2004
Notification Time: 10:14 [ET]
Event Date: 04/16/2004
Event Time: [EST]
Last Update Date: 04/16/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
STEPHEN CAHILL (R2)
| Event Text PART 21 NOTIFICATION DUE TO POTENTIAL CRACKING IN B4C HYDRID CONTROL RODS
This issue concerns the potential for cracking in the tips of the Westinghouse designed B4C Hybrid Rod Cluster Control Assembly (RCCA) while in operation. Westinghouse supplied B4C Hybrid RCCAs are currently in use in the U.S. only at Tennessee Valley Authority's (TVA) Watts Bar Nuclear Plant.
Cracks in the hybrid RCCAs could result in a potential loss of B4C [a neutron absorber] from the RCCA if left uncorrected.
Westinghouse will review and revise its guidelines on the use and expected life of B4C Hybrid RCCAs to assure that this information is accurately reflected and communicated to its customers. |
| Power Reactor | Event Number: 40680 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: Dann R. Dailey
HQ OPS Officer: JAMIE HEISSERER | Notification Date: 04/17/2004
Notification Time: 13:57 [ET]
Event Date: 04/17/2004
Event Time: 07:26 [MST]
Last Update Date: 04/18/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
DALE POWERS (R4)
VICTOR DRICKS (R4)
ART HOWELL (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text OFFSITE NOTIFICATION - SMALL FIRE AT PALO VERDE 1: TWO EMPLOYEES INJURED, NO PLANT EQUIPMENT DAMAGE
"On Saturday, April 17, 2004, at approximately 07:26 [MST], a fire in the Palo Verde Nuclear Generating Station Unit 1 turbine building resulted in two injuries due to burns. Both individuals were transported offsite for treatment. One of the two was airlifted with suspected second degree burns. Neither involved any radioactive contamination.
"No press release is planned, but media attention has already been observed in response to media monitoring communications on local police/fire scanners. Calls have been received from several TV stations. One local station broadcast the fire and injuries at approximately 09:40 (MST).
"Palo Verde Unit 1 is shutdown and defueled in its eleventh refueling outage. The fire was associated with pre-heating for welding in the turbine building. It is suspected that solvent vapor in the vicinity of the pre-heating activity may have flashed. The fire was extinguished in less than 15 minutes and no emergency plan classification was declared or required as a result of the fire.
"The NRC Resident Inspector has been notified of the event and this ENS notification."
The fire occurred near the Main Feed Pump Turbine Alpha, which was dismantled at the time. There appears to be no physical damage to any plant equipment, although some nearby cleaning rags were partially burned.
* * * * UPDATE FROM D. DAILEY TO M. RIPLEY 1635 ET 04/18/04 * * * *
"1) Both workers received facial burns. One was treated and released at approximately 11:00 MST on Saturday, April 17, 2004. The other was released during the morning of Sunday, April 18, 2004.
"2) There was no equipment damage as a result of the fire. The apparent cause of the fire in the "A" main feed pump turbine lower shell was residual isopropyl alcohol in a drain hole. The alcohol is used to clean solvent residue to have the turbine shell oil-free for NDE (non-destructive examination) purposes.
"The NRC Resident Inspector has been notified of this ENS update."
Notified NRC Region 4 Duty Officer (D. Powers) |
| Other Nuclear Material | Event Number: 40681 | Rep Org: CONSTRUCTION TESTING & ENGINEERING
Licensee: CONSTRUCTION TESTING & ENGINEERING
Region: 1
City: MANASSAS State: VA
County:
License #: 4525554-01
Agreement: N
Docket:
NRC Notified By: FARID VESSAL
HQ OPS Officer: JAMIE HEISSERER | Notification Date: 04/17/2004
Notification Time: 19:37 [ET]
Event Date: 04/17/2004
Event Time: 12:00 [EDT]
Last Update Date: 04/17/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
| Person (Organization):
BRIAN MCDERMOTT (R1)
ROBERT PIERSON (NMSS)
FRANK COSTELLO (R1)
| Event Text DAMAGED TROXLER MOISTURE DENSITY GAUGE
The licensee RSO reported that at 1200 EDT, a Troxler Moisture Density Gauge, Model #3440 (Serial #32741 containing 40 millicuries Am-241/Be and 8 millicuries Cs-137) was run over by heavy equipment on a residential construction site in Vienna, VA. A 20 square foot area around the location of the incident was cordoned off, and the damaged equipment was transported to the company's laboratory in Manassas, VA. According to the RSO, the device was damaged, but the source remained intact.
At 2020 EDT the Fairfax County, VA HazMat team was directed to the construction site, and conducted testing to see if any contamination occurred. At 2125 EDT, the HazMat responders reported that no radiation above normal background was found at the site, and they were following up with the operator of the device to check for personal contamination. At 2208 EDT, the team reported that no contamination was found on either the individual who operated and transported the device, or his clothing. |
| Power Reactor | Event Number: 40682 | Facility: VOGTLE
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THOMAS PETRAK
HQ OPS Officer: JAMIE HEISSERER | Notification Date: 04/18/2004
Notification Time: 15:31 [ET]
Event Date: 04/18/2004
Event Time: 12:38 [EDT]
Last Update Date: 04/18/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
STEPHEN CAHILL (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text AUXILIARY FEEDWATER SYSTEM ACTUATION DUE TO MAIN FEED PUMP TRIPS
"An Auxiliary Feedwater [AFW] actuation occurred with the plant in Mode 3, Main Feedwater out of service and a cooldown in progress. An AFW actuation was received when both main feed pumps tripped due to low condenser vacuum. AFW was already in service with both motor-driven pumps running and discharge valves throttled to maintain steam generator level. A surveillance to test AFW actuation on the trip of main feedwater pumps was in progress. The main feed pump trip signal was generated when condenser vacuum was broken prior to completing the test and blocking the actuation signal from the main feed pumps to AFW. Steam generator blowdown and sample valves isolated and MDAFW [Motor Driven AFW] discharge valves opened as expected. Operators took action to throttle AFW feed to the steam generators. No adverse affects on the plant occurred. The AFW actuation signal from the trip of main feed pumps has been blocked as allowed by plant conditions."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40684 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: DAVE RICHARDSON
HQ OPS Officer: ARLON COSTA | Notification Date: 04/18/2004
Notification Time: 23:45 [ET]
Event Date: 04/18/2004
Event Time: 18:30 [EDT]
Last Update Date: 04/18/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
BRIAN MCDERMOTT (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text RESIDUAL HEAT REMOVAL SYSTEM ISOLATION DUE TO A RISE IN REACTOR PRESSURE
"At 1830 hours on 18 April 2004, Nine Mile Point Unit 2 was restoring from reactor pressure vessel leakage test.
"Reactor pressure was ~82 psi, temperature ~178 degrees, reactor level was solid with both reactor recirculation pumps running in slow speed per the leak test procedure.
" 'B' residual heat removal system was being warmed up in preparation for going in to service. Reactor water cleanup reject from the vessel was secured to maintain RPV [Reactor Pressure Vessel] pressure stable in order to provide driving head for flow through the residual heat removal discharge line to radwaste. The line is warmed up from the reactor, back through the Shutdown cooling isolation valve, to radwaste prior to placing shutdown cooling in service. When warm-up criteria are met, the operating procedure directs securing flow.
When flow was secured, this effectively isolated the solid reactor vessel, resulting in a rise in reactor pressure. Pressure peaked at ~146 psi before operators established reactor water cleanup reject flow.
"When RPV pressure reached 128 psi, the residual heat removal system isolation was automatically initiated as designed. The shutdown cooling injection valve, which was open to support piping warm-up, closed as designed. All other shutdown cooling valves were closed prior to the event per the warm-up lineup."
RPV is currently depressurized with shutdown cooling in service. All systems are functioning as expected.
The licensee notified the NRC Resident Inspector. | |