| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/18/2006 - 10/19/2006 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 42903 | Rep Org: SC DIV OF HEALTH & ENV CONTROL
Licensee: CAROLINA TECHNICAL SERVICES, INC
Region: 1
City: NEWBERRY State: SC
County:
License #: 558
Agreement: Y
Docket:
NRC Notified By: MARK WINDHAM
HQ OPS Officer: BILL GOTT | Notification Date: 10/13/2006
Notification Time: 10:34 [ET]
Event Date: 10/12/2006
Event Time: 15:40 [EDT]
Last Update Date: 10/13/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHRISTOPHER CAHILL (R1)
SANDRA WASTLER (NMSS)
| Event Text AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
The State provided the following information via facsimile:
"The SC Department of Health and Environmental Control was notified on Thursday, October 12, 2006, at 3:45 p.m., that a CPN Model MC-1-DRP had been damaged at 3:40 p.m., on October 12, 2006. The RSO stated that the gauge had been run over by a dump truck during a soil compaction test. The SC Department of Health and Environmental Control Duty Officer responded to the scene and arrived at 5:15 p.m. and found the area properly roped off. The source rod was extended and the gauge had sustained considerable damage. The inspector and licensee personnel were able to retract the source rod to the shielded position and place the gauge in the transport container. The inspector advised the RSO to return the gauge to the storage location, secure it from further use, and to contact the gauge manufacturer for further instruction regarding disposal."
A typical CPN Model MC-1-DRP moisture density gauge contains 10 millicuries Cs-137 and 50 millicuries Am-241/Be. |
| General Information or Other | Event Number: 42905 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: SCHLUMBERGER
Region: 4
City: BATON ROUGE State: LA
County:
License #: LA-2783-L01
Agreement: Y
Docket:
NRC Notified By: RICHARD PENROD
HQ OPS Officer: STEVE SANDIN | Notification Date: 10/13/2006
Notification Time: 16:05 [ET]
Event Date: 09/21/2006
Event Time: [CDT]
Last Update Date: 10/13/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JACK WHITTEN (R4)
THOMAS ESSIG (NMSS)
| Event Text AGREEMENT STATE REPORT INVOLVING ABANDONMENT OF TWO SEALED WELL LOGGING SOURCES
The following information was received via fax:
"Event Report ID No.: LA060019
"Event Date and Time: September 21, 2006
"Event Location: East Baton Rouge Parish
"Event Type: Abandonment down hole
"Notifications: LA DEQ
"Event Description: Schlumberger abandoned two sealed radioactive sources down hole. The AEA 63 GBq Cs-137 source, serial number A2371, was abandoned at a depth of 18,887 feet. The Gamatron 592 GBq Am-241:Be source, serial number G4040, was abandoned at a depth of 18,855 feet. Many attempts were made to retrieve the sealed sources from 9/7-21/06. The sealed sources are covered with Premium cement and a cement retainer was set at 18,246 feet. A whipstock was placed on top of the cement retainer at 18,246 feet. An abandonment plaque will be placed on the well. |
| Power Reactor | Event Number: 42917 | Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DAVE HELD
HQ OPS Officer: JASON KOZAL | Notification Date: 10/18/2006
Notification Time: 00:19 [ET]
Event Date: 10/17/2006
Event Time: 21:00 [EDT]
Last Update Date: 10/18/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
| Person (Organization):
RICHARD BARKLEY (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text REACTOR VESSEL HEAD NOZZLE WELD AREA FLAW
"During the performance of NDE examinations of the Beaver Valley Unit 2 (BV-2) reactor pressure vessel (RPV) closure head Alloy 600 Control Rod Drive Mechanism (CRDM) penetrations required by NRC Order (EA-03-009), indications were identified in penetrations #16, #56, and #61. The ultrasonic examination (UT) signal for the three (3) penetrations were in the J-groove weld area and extend into the CRDM tube base material.
"Confirmatory eddy current testing (ECT) was performed on penetrations #16, #56 and #61. Liquid Penetrant (PT) examinations were performed on penetrations #56 and #61 and displayed indications that required further investigation. Following minor excavation of the weld surface in the area of the indications on both penetrations (#56 and #61), additional PT examinations were performed. The result of these examinations on 10/17/06 at 2100 confirmed the presence of flaws in the weld that do not meet acceptance criteria. Penetration #16 is in the state of discovery at this time through PT examination techniques.
"Based upon the preliminary analysis, it is expected that these indications would not be acceptable under ASME standards. Although this condition does not exceed the specific 10 CFR 50.72(b)(3)(ii)(A) criteria since there was no leakage as addressed in ASME Table IWB-3410-1 acceptance criteria and the component structures defined in the ASME IWB-3600 acceptance guidance do not address the J-groove weld configuration, reporting under voluntary considerations is appropriate.
"BV-2 is planning to repair penetrations #56 and #61. Penetration #16 will also be repaired if warranted through the discovery process. All repairs will be completed prior to returning the RPV head to service."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42918 | Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JEFF SCHWARTING
HQ OPS Officer: JOE O'HARA | Notification Date: 10/18/2006
Notification Time: 15:27 [ET]
Event Date: 10/18/2006
Event Time: 09:38 [CDT]
Last Update Date: 10/18/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
| Person (Organization):
MICHAEL SHANNON (R4)
JOHN THORP (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 91 | Power Operation | 91 | Power Operation | Event Text FITNESS FOR DUTY - LICENSED REACTOR OPERATOR FAILS CHEMICAL DEPENDENCY EVALUATION
A licensed reactor operator has his access to the plant blocked based upon an adverse, chemical dependency evaluation and interview performed through the licensee's Employee Assistance Program (EAP). The individual was not scheduled to work when the evaluation interview was performed.
The individual was referred to the licensee by concerned colleagues via the licensee's Human Resources Office and is still employed by the licensee pending senior management review.
The licensee notified the NRC Resident Inspector. Contact the Headquarters Operations Officer for additional details. | |