| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/14/2006 - 03/15/2006 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 42401 | Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: CARDINAL HEALTH - WAUWATOSA
Region: 3
City: WAUWATOSA State: WI
County:
License #: 079-1311-01
Agreement: Y
Docket:
NRC Notified By: MIKE WELLING
HQ OPS Officer: MIKE RIPLEY | Notification Date: 03/09/2006
Notification Time: 15:15 [ET]
Event Date: 03/03/2006
Event Time: 06:45 [CST]
Last Update Date: 03/09/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMNES CAMERON (R3)
TOM ESSIG (NMSS)
| Event Text WISCONSIN AGREEMENT STATE REPORT - UNPLANNED CONTAMINATION EVENT
The State provided the following information via email:
"On Friday, March 3, 2006 at 6:45 am a vial containing 890 mCi of Tc-99m Cardiolite ruptured while in a heating block. Two employees entered the area immediately, visually confirming the rupture through a window in the heating box and with a survey meter. The employees unplugged the heating box and shut the door. They returned 15 minutes later after the heating box and vial had cooled. The heating box was cleaned and waste was placed in a lead shielded container for decay. No individuals were contaminated. Wipes were taken each day until 3/07/06 when contamination levels were reduced to 2-3 times background. This event will be followed up by DHFS on the next inspection.
"Media attention: None"
Wisconsin Event Report ID No. 35 |
| General Information or Other | Event Number: 42402 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: OCEANEERING INTERNATIONAL, INC.
Region: 4
City: INGLESIDE State: TX
County:
License #: L04463
Agreement: Y
Docket:
NRC Notified By: RAY JISHA
HQ OPS Officer: PETE SNYDER | Notification Date: 03/09/2006
Notification Time: 14:05 [ET]
Event Date: 02/28/2006
Event Time: [CST]
Last Update Date: 03/09/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHUCK CAIN (R4)
M. WAYNE HODGES (NMSS)
| Event Text TEXAS AGREEMENT STATE REPORT - POTENTIAL OVEREXPOSURE
The agreement state submitted the following report via e-mail:
"Texas Incident No.: I-8311
"Event date and time: February wear period
"Report Received Date: March 9, 2006
"Event location: Brown and Root construction site, 14035 Industrial Road, Houston, TX
"Event type: Presumptive badge overexposure
"A radiographer trainee was working with a trainer at a construction site in Houston, TX when he noticed that his badge had fallen off approximately 6 feet from a 95 Ci, model G-60 Ir-192 source (S/N NA0502), SPEC model 150 camera (S/N 750). It is uncertain whether the trainee [name deleted] failed to report the incident to the radiographer, supervisor, or RSO.
"The incident was thought to have occurred in late February. The trainee is assigned other duties not involving exposure to radiation and the company is considering having cytogenetic testing performed. A second reading of the dosimeter by the company processing the device rendered an inconclusive result.
"The radiography company and DSHS staff are performing an investigation although the company is presuming the situation is a badge only exposure since the pocket dosimeters and processed dosimeter worn by the trainer were consistent with their typical monthly exposures of approximately 100 mRem."
The film badge read 25.343 Rem. The state will be following up on this incident. |
| Power Reactor | Event Number: 42403 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: ANTHONY PETRELLI
HQ OPS Officer: JEFF ROTTON | Notification Date: 03/10/2006
Notification Time: 00:58 [ET]
Event Date: 03/09/2006
Event Time: 22:14 [EST]
Last Update Date: 03/14/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
JOHN WHITE (R1)
|
| 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 DUE TO LOSS OF CONDENSER VACUUM TURBINE TRIP
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) RPS Actuation (scram) for Nine Mile Point Unit 2 which states 'Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.' On 03/09/2006 at 2214 while operating at approximately 85 % reactor power (coast down to refueling) a condenser low vacuum condition resulted in a turbine trip and a subsequent reactor scram. A loss of sealing steam most probably caused the loss of condenser vacuum and an investigation is in progress. Special Operating procedure N2-SOP-101 C was entered. All control rods inserted [fully] as expected. Condenser vacuum has been stabilized and the main steam isolation valves are open. The plant is stable and recovery actions are in progress."
Decay heat is being removed via the turbine bypass valves to the main condenser. The condensate and feedwater system is in operation maintaining reactor vessel level. The electric plant is in a normal shutdown lineup and there was no effect from this transient on Unit 1.
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 0035 EST ON 3/14/06 FROM P. WALSH TO W. GOTT * * *
"This update is being made to provide additional information to EN# 42403 which was communicated via ENS on 3/10/06 at 0058 hours. During the scram that occurred at Nine Mile Point Unit 2 on 3/9/06 at 2214 hours, a primary containment isolation signal to RHR Shutdown Cooling, RHR Head Spray and RHR sample valves was received as designed. No components repositioned as the valves are normally closed during plant operations."
The licensee will notify the NRC Resident Inspector.
Notified R1DO (P. Krohn). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 42405 | Facility: LASALLE
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: TERRY NANCE
HQ OPS Officer: BILL GOTT | Notification Date: 03/11/2006
Notification Time: 06:36 [ET]
Event Date: 03/11/2006
Event Time: 00:30 [CST]
Last Update Date: 03/15/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
JAMNES CAMERON (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 UNANALYZED CONDITION
"This report is being made pursuant to 10CFR50.72(b)(3)(ii)(B), Degraded or Unanalyzed Condition. During Division 1 Core Standby Cooling System (CSCS) valve replacement work, it was discovered that temporary seismic supports required to maintain this piping within the Safe Shutdown Earthquake (SSE) design envelope were not installed. This condition was discovered during the restoration phase of the maintenance and the requirements for the temporary supports no longer exist. At the time of discovery, the required permanent seismic qualified support system had been re-established. The Division 1 CSCS System is common to both units and circulates lake water from the Ultimate Heat Sink (UHS) to the Division 1 Residual Heat Removal (RHR) heat exchangers, Division 1 Diesel Generator cooler, Division 1 Emergency Core Cooling System (ECCS) area room coolers, Division 1 RHR Pump seal coolers, and the Low Pressure Core Spray (LPCS) motor coolers. During the period with the required seismic supports not installed, both Unit 1 and Unit 2 were in an unanalyzed condition due to the inability of the Division 1 CSCS piping to meet its seismic qualification. A postulated structural failure of the Division 1 CSCS piping during an SSE could affect areas containing redundant equipment due to flooding."
The licensee is investigating the failure to install the supports. The supports were only needed during the maintenance.
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 0025 EST ON 3/15/06 FROM T. NANCE TO W. GOTT * * *
"On March 11, 2006, it was identified that temporary seismic supports required to maintain the Core Standby Cooling System piping within the Safe Shutdown Earthquake (SSE) envelope during valve replacement activities were not installed. This was reported under 10 CFR 50.72 (b)(3)(ii)(B) as a degraded or unanalyzed condition that significantly degrades plant safety.
"Subsequent evaluations have been performed to demonstrate that the piping remained within the SSE envelope with the missing supports. These evaluations have concluded that the remaining supports were sufficient to ensure that piping would remain intact during an SSE. As such, this event notification is being retracted."
The licensee notified the NRC Resident Inspector.
Notified R3DO (D. Passehl) |
| Power Reactor | Event Number: 42416 | Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: STUART BRANTLEY
HQ OPS Officer: PETE SNYDER | Notification Date: 03/14/2006
Notification Time: 13:42 [ET]
Event Date: 03/14/2006
Event Time: 09:30 [EST]
Last Update Date: 03/14/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
| Person (Organization):
PAUL KROHN (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 99 | Power Operation | 99 | Power Operation | Event Text LICENSED SRO FAILED RANDOM FITNESS FOR DUTY TEST
A licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been put on administrative hold, and the individual has been escorted offsite. Contact the Headquarters Operations Officer for additional details.
The licensee has informed the NRC Resident Inspector.
* * * * UPDATE ON 3/14/06 AT 1534 FROM S. BRANTLEY TO P. SNYDER * * * *
The licensee will be issuing a press release on this event. The licensee has informed the NRC Resident Inspector. |
| General Information or Other | Event Number: 42417 | Rep Org: TRIAD ENGINEERING
Licensee: TRIAD ENGINEERING
Region: 1
City: WINCHESTER State: VA
County:
License #: 47-17742-01
Agreement: N
Docket:
NRC Notified By: LLOYD WINTERS
HQ OPS Officer: ARLON COSTA | Notification Date: 03/14/2006
Notification Time: 13:32 [ET]
Event Date: 03/14/2006
Event Time: 08:00 [EST]
Last Update Date: 03/14/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
| Person (Organization):
PAUL KROHN (R1)
MICHELLE BURGESS (NMSS)
STEPHEN CAHILL (R2)
| Event Text TROXLER MOISTURE DENSITY GAUGE FALLS FROM TRUCK
As a licensee employee was leaving the office in Purcellville, VA in his truck, he was stopped at an intersection nearby by bystanders. They informed him that an object (a Troxler gauge in its case) had fallen from the open tailgate of his truck. Local police responded to the incident and contacted the fire marshal who told the officer that the device in its case was designed for that type of an impact. The gauge remained intact and no radiation exposures were reported. The Troxler moisture density gauge is a model # 3411, containing Am-241 (40 millicuries) and Cs-137 (8.7 millicuries). The employee loaded and secured the case containing the gauge and proceeded to the job site. The licensee will perform a leak test on the gauge. The licensee is holding mandatory gauge refresher training for their employees as a corrective action to this incident.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. |
| Power Reactor | Event Number: 42422 | Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: EDWARD CASULLI
HQ OPS Officer: JOE O'HARA | Notification Date: 03/14/2006
Notification Time: 20:21 [ET]
Event Date: 03/14/2006
Event Time: 16:59 [EST]
Last Update Date: 03/14/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
PAUL KROHN (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 LOSS OF CONTROL ROOM EMERGENCY FILTRATION
"On 03/14/06 at 1655 hours, the 'A' Control Room Emergency Filtration (CREF) system was removed from service to address a high oil level and subsequent high bearing drain oil temperatures. The 'A' CREF train was declared inoperable and a 7-day LCO was entered. While placing the 'B' CREF train in-service the chiller did not respond as expected. The chiller failed to properly load and supply cooling. At 1659 hours the 'B' CREF train was declared inoperable. This resulted in both 'A' and 'B' trains of CREF [being] unable to perform their design safety function and thus unable to mitigate the consequences of an accident. This failure placed the Hope Creek Station in a Technical Specification 3.0.3 condition requiring a unit shutdown. Oil level was restored to normal band for the 'A' CREF train at 1732 hours and the 3.0.3 condition was exited prior to any actions being initiated to start reducing reactor power to achieve a Hot Shutdown condition.
"A 8 hour report is being made under ECG Section 11.2.2.b, an Event/Condition could have prevented certain safety functions IAW 10.CFR50.72(b)(3)(v).
"At the time of event all safety systems were operable. The license has notified the NRC resident inspector." | |