| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/01/2007 - 10/02/2007 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43665 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: GEO-ENVIRONMENTAL, INC.
Region: 4
City: IRVINE State: CA
County:
License #: 7116-30
Agreement: Y
Docket:
NRC Notified By: DONELLE KRAJEWSKI
HQ OPS Officer: JASON KOZAL | Notification Date: 09/26/2007
Notification Time: 15:01 [ET]
Event Date: 09/25/2007
Event Time: 18:15 [PDT]
Last Update Date: 09/26/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CLAUDE JOHNSON (R4)
MICHELE BURGESS (FSME)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST / RECOVERED MOISTURE DENSITY GAUGE
"On September 25, 2006 at approximately 6:15 P.M., a gauge user from Geo-Environmental, Inc., had returned to the office to return Troxler gauge 3440, S/N 34036 (9 mCi Cs-137, 44 mCi Am-241:Be) to it's storage location, when he noticed that the gauge was missing and immediately contacted the RSO to report the incident. After the RSO had spoken with the gauge user, the RSO received a call from the office manager that the gauge had been recovered by the Irvine Police Department on Jamboree Rd. in Irvine near the intersection of Jamboree Rd., and Richter Ave. The gauge was returned to the Geo-Environmental, Inc., office at approximately 6:45 P.M. The gauge most likely was out of the control of the licensee for approximately one hour. The gauge case was intact with a single scuff mark. The gauge was inspected by the licensee and found to be intact. The RSO then contacted RHB [DELETED] by phone to report the incident by voice mail. At approximately 9:00 A.M. on September 26, 2007, [RHB] spoke with the RSO about the incident and instructed him to have the gauge inspected and leak tested by a service provider and the RSO stated that he would take the gauge to Maurer Technical Services to be inspected and leak tested. [RHB] also instructed the RSO to provide, within 30 days, a written report, in accordance to 10 CFR 20.2201 (a)(1)(i). The RSO stated that the gauge user involved was allowed to transport the gauge in an open bed truck and with two chains and two locks and with two locks on the gauge case. He also stated that the gauge was transported with only a single lock to secure both chains."
CA report number: 092607
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: 43669 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: MATRIX METALS LLC
Region: 4
City: RICHMOND State: TX
County:
License #: L00312
Agreement: Y
Docket:
NRC Notified By: RAY JISHA
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 09/27/2007
Notification Time: 15:15 [ET]
Event Date: 09/27/2007
Event Time: 10:30 [CDT]
Last Update Date: 09/28/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CLAUDE JOHNSON (R4)
ROBERT PIERSON (FSME)
| Event Text AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE WILL NOT RETRACT INTO CAMERA
"At 1030 hours the licensee reported that a Sentinel model 676AE (S/N AE1017) radiography camera with a 69 Ci Co-60 source (Make 424-13; S/N 2612) failed to retract to the safe position. After several attempts to retract the source and after a close inspection of the crank device, the Agency was notified and advice sought for authorized personnel who could safely retrieve the source. At 1400 hrs., the RSO had made arrangements with the manufacturer to provide a team equipped to deal with the emergency. The licensee is authorized for fixed site radiography for the facility that he owns. Due to Increased controls, surveillance will be maintained by additional security personnel until the retrieval team is on-site, either late tonight or early tomorrow, Friday 09/28/07."
Texas event report: I-8445
* * * UPDATE RECEIVED VIA E-MAIL FROM RAY JISHA TO MARK ABRAMOVITZ AT 1139 ON 9/28/07 * * *
"Update, @ 0800hrs., Friday, September 28, 2007. The RSO for Matrix Metals called to report that the manufacturer's specialist arrived on the scene at ~2230hrs last night, Thursday, September 28, 2007 and the source was retracted to the save position within 20 minutes. As the source was in a shooting bay at this fabrication facility, no significant public or personnel exposures occurred. The RSO for the licensee and another authorized user remained at the facility to ensure constant surveillance as per IC requirements. Upon a more thorough inspection of the camera by the manufacturer's representative, a few mechanical issues were determined to be in need of further investigation so the device and source are being over packed today and returned to the manufacturer. A full report from the licensee will be filed" [with the state of Texas].
Notified the R4DO (Johnson) and FSME (Wastler). |
| Power Reactor | Event Number: 43677 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAN NIMICK
HQ OPS Officer: JOHN MacKINNON | Notification Date: 10/01/2007
Notification Time: 00:57 [ET]
Event Date: 09/30/2007
Event Time: 19:58 [PDT]
Last Update Date: 10/01/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
CLAUDE JOHNSON (R4)
|
| 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 UNEXPECTED AUTOMATIC START OF THE 2-1 EMERGENCY DIESEL GENERATOR (EDG)
"A problem with voltage sensing circuit for 4 KV Bus G Startup power supply caused Diesel Generator 2-1 to automatically start. Loss of Startup voltage to a vital bus is an automatic start signal for the associated diesel generator. Startup power has been declared inoperable to 4 KV Bus G. All indications for Startup power to the other 2 vital busses remain normal. All systems functioned correctly in response to the sensed undervoltage condition. Unit 2 is in a 72 hour shutdown action statement per T. S. 3.8.1. An automatic start of a Diesel Generator is reportable per 10CFR50.72(B)(1)(iv)(A). The Diesel Generator has been shutdown per the annunciator response procedure and remains operable."
One of the four undervoltage relay starting power fuses for EDG 2-1 was found blown.
The NRC Resident Inspector was notified of this event by the licensee. |
| Power Reactor | Event Number: 43678 | Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 10/01/2007
Notification Time: 14:17 [ET]
Event Date: 10/01/2007
Event Time: 13:15 [CDT]
Last Update Date: 10/01/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
REBECCA NEASE (R4)
TOM KARDARAS (NSIR)
|
| 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 REPLACING THE EMERGENCY RESPONSE FACILITY COMPUTER SYSTEM
"The Plant Process computer system (Emergency Response Facility Computer System) will be taken out of service for approximate 3 week period starting October 1, 2007, to implement a planned modification. The current ERFCS is being replaced and a computer outage is required for the installation of the new ERFCS. During this time period Emergency Response Data System (ERDS) and Safety Parameter Display System (SPDS) functions will not be available. However, the Qualified Safety Parameter Display System (QSPDS) will still be operable in the Control Room. This notification is being made to inform the NRC that the ERDS will be unavailable until this modification is complete. The operation of the plant systems will not be affected due to this planned action. ERDS and SPDS parameters will be monitored by control board indications. All contingency actions required by ERFCS-3, ERFCS Maintenance Outage Plant Mode 1, have been taken. Meteorological data to support the Emergency Response Organization (ERO) will be obtained from the local national weather service (if needed) as described in our Radiological Response Plan. A follow up notification, to the NRC will be given once ERDS and SPDS are returned to service. The NRC Resident Inspector has been informed." |
| General Information or Other | Event Number: 43679 | Rep Org: FIRSTENERGY NUCLEAR OPERATING CO.
Licensee: FIRSTENERGY NUCLEAR OPERATING CO.
Region: 1
City: SHIPPINGPORT State: PA
County:
License #:
Agreement: N
Docket:
NRC Notified By: PETER SENA III
HQ OPS Officer: JOHN KNOKE | Notification Date: 10/01/2007
Notification Time: 16:34 [ET]
Event Date: 08/02/2007
Event Time: [EDT]
Last Update Date: 10/01/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
RAY POWELL (R1)
JERRY DOZIER (NRR)
PART 21 GROUP EMAIL ()
| Event Text PART 21 REPORT - POPPET NUT AND STEM ASSEMBLY DEGRADATION ON MSIV
"In accordance with 10 CFR 21.21(d)(3)(ii), FirstEnergy Nuclear Operating Company (FENOC) is providing the required written notification of a concern regarding the potential for vibration inducted wear on the pilot poppet nut and stem assemblies provided for use in the Beaver Valley Power Station Unit No. 2 (BVPS-2) Main Steam System Isolation Valves [MSIV] that if uncorrected could potentially create a significant safety hazard. FENOC evaluated the concern via a Prompt Operability Determination and concluded that there is reasonable assurance that currently installed valve components at BVPS-2 are operable and plans to replace the affected components during the next BVPS-2 refueling outage."
Valve manufacturer of defective valve components is Weir Valves and Controls USA Inc. in Salem, MA.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 43680 | Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: HARDY FARRIS
HQ OPS Officer: JEFF ROTTON | Notification Date: 10/02/2007
Notification Time: 04:28 [ET]
Event Date: 10/01/2007
Event Time: 22:20 [CDT]
Last Update Date: 10/02/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
REBECCA NEASE (R4)
|
| 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 EXHAUST VENTILATION STACK FLOW AND ACCIDENT RADIATION MONITORS DUE TO PLANT DATA MULTIPLEXER FAILURE
"On 10/01/2007 the failure of a plant data multiplexer (MUX) resulted in the loss of Control Room indication of all plant building exhaust ventilation stack flows and accident radiation monitors. The stack flows and accident radiation monitors are normally accessed by the plants Emergency Response Organization offsite dose calculation application but cannot be accessed at this time. Alternate means of offsite dose projections are available. The duration of the plant data MUX outage is currently unknown. Follow-up notification will be made after restoration of the plant data MUX."
The cause of the failure is being investigated.
The licensee notified the NRC Resident Inspector. | |