| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/22/2006 - 02/23/2006 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 42347 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: SCHLUMBERGER TECHNOLOGY CORPORATION
Region: 4
City: SONORA State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: LATISCHA M. HANSON
HQ OPS Officer: MIKE RIPLEY | Notification Date: 02/17/2006
Notification Time: 16:08 [ET]
Event Date: 02/17/2006
Event Time: [CST]
Last Update Date: 02/17/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID GRAVES (R4)
SANDRA WASTLER (NMSS)
| Event Text TEXAS AGREEMENT STATE REPORT - WELL LOGGING SOURCES STUCK DOWNHOLE
"Event date and time of occurrence:
- Stuck 1/12/06 @1:35
- Multiple recovery attempts from 1/12/06 to 1/26/06
- Request to Abandon Source made by telephonic contact 1/25/06 @ 12:30 CST to Texas DSHS.
- Written notification to DSHS dated 1/26/06.
"Date notified of event by licensee: Incident Investigation received the written notification dated 02/06/06.
"Radionuclide, activity:
(1) - Cs-137 @ 1.7 Ci
(1) - Am241Be @ 16 Ci
"Sealed source, device, etc, (make, model #, serial #): Well logging tool - sealed neutron generator tube
"Leak test information, when applicable:
(1) Cs -137 - 1/12/06 - 9.48E-06 microcuries
(2) Am241BE - 1/12/06 - 1.52E-01 microcuries
"Equipment (make, model #, serial #), and clear description of any equipment problems:
(1) Cs- 137 - Amersham Corp., M# CDC.CY3, S# A5006
(2) Am241BE - Gammatron, Inc., M# NSR-F (AN-HP) S# G5044
"Cause, and contributing factors
While logging down at a location 14 miles West South-West of Sonora, Texas (Sawyer Canyon Field), the logging unit had multiple failures, causing a free spool of tools & 18,000 feet of cable to enter into the hole. The hole was drilled on AIR & was never loaded with fluid. Fishing tool company attempted ~11 runs to recover tools. Hole cemented on 1/27/06 @ 18:00
"Licensee corrective actions:
(1) Cs- 137 Density Source abandoned @ 8,607 feet.
(2) Am241BE Neutron Source abandoned @ 8,590 feet.
Abandonment plaque constructed with the relevant abandonment depth location information. Well depth: 8, 625 feet. Special instructions to not enter the well before contacting Radiation Control - DSHS.
"Provide status through resolution (update record when found):
Well sealed with cement & abandoned 1/27/06. Dominion E&P, Inc., Sutton County, Texas"
Texas Incident No.: Texas, I-8306
Abandoned in accordance with 10CFR39.77[c]. |
| Power Reactor | Event Number: 42348 | Facility: LASALLE
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: DAN COVEYOU
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/20/2006
Notification Time: 02:14 [ET]
Event Date: 02/20/2006
Event Time: 00:23 [CST]
Last Update Date: 02/22/2006 | Emergency Class: SITE AREA EMERGENCY
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
JULIO LARA (R3)
PETER WILSON (IRD)
JAMES LYONS (NRR)
JIM CALDWELL (R3)
TOM BLOUNT (IRD)
MEL LEACH (IRD)
HOLLY HARRINGTON (PAO)
WILLIAM KANE (NRR)
ANGELA COGGINS ()
WILLIAM ORDERS ()
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 6 | Power Operation | 0 | Hot Shutdown | Event Text SITE AREA EMERGENCY - REACTOR SCRAM
"While shutting down Unit 1 IAW LGP-2-1 with the main turbine off line the plant experienced a turbine control system (EHC) malfunction. This resulted in opening all main turbine bypass valves and subsequent reactor low pressure condition. The low pressure condition resulted in a closure of all main steam isolation valves (MSIV's) and automatic reactor scram. Three rods failed to indicate fully inserted on the scram. Plant emergency operating procedures were entered. All ECCS and plant systems operated as expected. All control rods are fully inserted and the ATWS emergency operating procedure has been exited."
The main turbine had been taken off line prior to this event and shutdown was being conducted with heat removal on the bypass valves. Pressure control is currently by using the steam line drains with the Safety Relief Valves in manual. Level is being maintained using normal feedwater. The electrical grid is stable though the plant is not yet on backfeed. Diesel generators are operable.
The licensee will notify the NRC Resident Inspector.
The NRC entered Monitoring Mode at 0243.
Notified R4DO (Graves), DHS (SWO), FEMA (J Kanupp), DOE (S. Morrone), EPA(NRC) (Nowak), USDA (Amanda), HHS (Kleiman).
* * * UPDATE AT 0402 ON 2/20/2006 * * *
In addition to the initial notification, La Salle is reporting a group 1 isolation in accordance with 10CFR50.72(b)(3)(iv)(a).
* * * UPDATE AT 0435 ON 2/20/2006 * * *
The site exited the Site Area Emergency and entered the recovery phase.
* * * UPDATE AT 05:59 ON 2/20/2006 * * *
"At the time of the scram @ 0023 hours rod 38-43 showed position 24 and rods 26-15 and 34-47 showed unknown. Based on more than one rod out condition, it is unanalyzed until shutdown margin can be verified."
* * * UPDATE AT 0655 ON 2/20/2006 * * *
NRC exited Monitoring Mode.
Notified IRD (Wilson), NRR EO (J. Lyons), R3DO (Lara), R4DO (Graves), NRR (Dyer), DHS (SWO), FEMA (Eerwin), DOE (Joe Stambaugh), NRC (does not take updates), USDA (Jim Brzostek), HHS (SOC) (Lt Hrynyshen).
* * * UPDATE FROM DAN COVEYOU TO JOE O'HARA AT 0700 ON 02/22/06 * * *
"Post trip evaluations have confirmed that all control rods were fully inserted within four minutes of the reactor scram. A review of the post-trip data suggests that there were only control rod indication problems on the three subject rods and all control rods were fully inserted immediately at the time of the reactor scram. Follow-up evaluations also demonstrated that even if the three subject control rods remained fully withdrawn in a cold shutdown condition, the reactor would have remained adequately shutdown. Additional confirmatory evaluations are continuing."
The licensee issued a press release on this event. The licensee notified the NRC Resident Inspector.
R3DO(Hills) has been notified. |
| General Information or Other | Event Number: 42349 | Rep Org: KANSAS DEPT OF HEALTH & ENVIRONMENT
Licensee: MCAFEE, HENDERSON AND STRICK INC
Region: 4
City: WINCHESTER State: KS
County:
License #: 22-B834
Agreement: Y
Docket:
NRC Notified By: DAVID WHITFILL
HQ OPS Officer: BILL GOTT | Notification Date: 02/20/2006
Notification Time: 10:03 [ET]
Event Date: 02/19/2006
Event Time: [CST]
Last Update Date: 02/20/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID GRAVES (R4)
E. WILLIAM BRACH (NMSS)
TAS (email) ()
| Event Text AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE
Between Saturday February 18, 2006 and Sunday morning February 19, 2006, a Troxler (Model 3440, S/N 31113, containing two sources; i.e., 0.3GBq [8 mCi] Cs-137 and 1.48 GBq [40 mCi] Am-241:Be) moisture density gauge was stolen from the operator's residence. The residence was the normal storage location for this gauge. The gauge was stolen along with other equipment from the operator's residence. The event was reported to local law enforcement.
Case Number: KS060001
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. |
| General Information or Other | Event Number: 42350 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: NONDESTRUCTIVE & VISUAL INSPECTION
Region: 4
City: HARVEY State: LA
County:
License #: LA-5601-L01
Agreement: Y
Docket:
NRC Notified By: SCOTT BLACKWELL
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/20/2006
Notification Time: 15:35 [ET]
Event Date: 12/31/2005
Event Time: [CST]
Last Update Date: 02/20/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID GRAVES (R4)
E. WILLIAM BRACH (NMSS)
| Event Text AGREEMENT STATE REPORT INVOLVING POTENTIAL OVEREXPOSURE OF THREE EMPLOYEES
The State of Louisiana submitted the following report via fax:
"Event Date and Time: December 2005
"Nondestructive & Visual Inspection had three overexposures at the end of 2005. [The first employee] had a dose of 8445 mRem for the year 2005. He was questioned by the RSO and Vice President of the company but could not explain the readings. He was ordered to retake the 40 hour radiation safety course and finished it on February 9, 2006. [The second employee] received a dose of 5221 mRem, for the year 2005. 2092 mRem of this exposure came in September, but the September badge report did not reach Nondestructive Inspection until the end of December because of mail problems after Hurricane Katrina. The mail problem has been addressed by sending the badges to a different location. [The third employee] received a dose of 5221 mRem for the year 2005. [The third employee's] overexposure is still under investigation. The facility is still in the process of reviewing the circumstances that caused the overexposures and are implementing procedures to stop them from re-occurring."
LA Event Report ID No.: LA060002 |
| Power Reactor | Event Number: 42356 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: DARYL CLARK
HQ OPS Officer: JEFF ROTTON | Notification Date: 02/22/2006
Notification Time: 04:51 [ET]
Event Date: 02/22/2006
Event Time: 01:22 [CST]
Last Update Date: 02/22/2006 | 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):
DAVID HILLS (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 85 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM DUE TO VALID MAIN TURBINE LOAD REJECT SIGNAL
"At 0122 hours (CST) on February 22, 2006, the Unit 1 reactor automatically scrammed from 85% power due to a valid turbine-generator load reject signal. The maximum reactor pressure was approximately 1050 PSIG during the event. All control rods inserted to their full-in position. Reactor water level decreased to approximately -10 inches, which resulted in automatic Group 2 and 3 isolations as expected. All systems responded properly to the event. Unit 1 is in Mode 3, maintaining reactor pressure, and reactor water level in the normal level band. An investigation into the Unit 1 scram and load reject is in progress.
"Unit 2 remains at 85% power.
"This report is being made in accordance with 10CFR 50.72(b)(2)(iv)(B) and 10 CFR50.72(b)(3)(iv)(A)."
No SRVs opened during the transient. Post shutdown electrical lineup is normal with the exception of the loss of one offsite power supply. Decay heat is being removed via the turbine bypass valves to the main condenser and feedwater being provided via main feedwater. Unit 2 is in a Tech Spec LCO for Loss of One Offsite power source.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42365 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: KEITH DROWN
HQ OPS Officer: JEFF ROTTON | Notification Date: 02/23/2006
Notification Time: 04:29 [ET]
Event Date: 02/23/2006
Event Time: 03:31 [EST]
Last Update Date: 02/23/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
PAMELA HENDERSON (R1)
|
| 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 ACCIDENT INVOLVING TRANSPORTATION OF RADIOACTIVE MATERIAL
At 0331 EST on 2/23/06, a tractor trailer truck delivering new fuel assemblies backed into the Fuel Handling Building roll up door. The door was 4 feet from the full up position. The upper fuel transport container was pushed into the door but had no visible damage. The truck sustained no damage also. The Fuel Handling Building roll up door had slight damage. This door is only required as a barrier during spent fuel handling which is not in progress. No release of radioactivity occurred.
The licensee notified the NRC Resident Inspector. | |