| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/03/2012 - 05/04/2012 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 47681 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: CHERIE SONODA
HQ OPS Officer: JOHN KNOKE | Notification Date: 02/21/2012
Notification Time: 11:38 [ET]
Event Date: 02/21/2012
Event Time: 00:55 [PST]
Last Update Date: 05/03/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RICK DEESE (R4DO)
|
| 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 DATA PROCESSING NETWORK FAILURE IMPACTED EMERGENCY RESPONSE DATA SYSTEM
"At 0055 PST on 2/21/12, it was discovered that portions of the data processing network (eDNA) had failed. This failure resulted in the Emergency Response Data System (ERDS) entering a mode of operation that caused an interruption of the ability of the ERDS transmission capabilities. At approximately 0213 PST on 2/21/12, actions were taken and all transmission capabilities were restored. The total outage time was determined to be 78 minutes. During the period that ERDS was not available, backup communications were available,
"This is determined to be a partial, but major loss of emergency assessment capability, and is reportable under 10 CFR 50,72(b)(3)(xiii) as 'Any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portions of control room indication, Emergency Notification System, or offsite notification system)'."
"The cause of the data processing network (eDNA) and ERDS failure is under investigation."
The licensee will notify the NRC Resident Inspector.
* * * RETRACTION FROM RICHARD GARCIA TO PETE SNYDER AT 1950 EDT ON 5/3/12 * * *
"This event was revisited for a formal reportability assessment and concluded to be not reportable since the capability to transmit data of interest to the NRC was available via the ENS at all times during the ERDS outage. In addition the ERDS system is noted as a supplement to the ENS in 10 CFR 50, Appendix B. Given the limited duration of the event and availability of ENS for data transmission, no major loss of emergency assessment capability occurred."
The licensee notified the NRC Resident Inspector. |
| Agreement State | Event Number: 47867 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: LANTHEUS MEDICAL IMAGING
Region: 1
City: NORTH BILLERICA State: MA
County:
License #: 60-0088
Agreement: Y
Docket:
NRC Notified By: TONY CARPENITO
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/26/2012
Notification Time: 14:02 [ET]
Event Date: 03/14/2012
Event Time: [EDT]
Last Update Date: 04/26/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DWYER (R1DO)
ANGELA MCINTOSH (FSME)
ILTAB via email ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text MASSACHUSETTS AGREEMENT STATE REPORT - MISSING THALLIUM-201 SHIPMENT
The following information was obtained from the Commonwealth of Massachusetts via email:
"On 4/5/12, [the] licensee reported as missing a 1.78 GBq (48.1 mCi) Thallium-201 package that was shipped from its site on 3/12/12, was scanned in at the carrier's Nashville, TN, transportation hub on 3/13/12 and reported to the licensee as missing by the carrier on 3/13/12. Licensee in communication with the carrier in ongoing effort to locate missing package. After a reasonable search time had passed, licensee reported missing package to this Agency [MA Radiation Control Program].
"Last known location was in Nashville, TN. The subject radioactive material is 7 ml of liquid solution held within a vial inside a lead pig inside a sealed plastic container inside a styrofoam insert within a corrugated cardboard box. Subject radioactive material has a 73 hour (~3 days) half-life and has decayed well past 10 half-lives since its original shipping date.
"Licensee remains in communication with carrier in ongoing effort to locate missing RAM and has requested return of package to licensee if found.
"The Agency considers this event to be CLOSED."
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. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source |
| Power Reactor | Event Number: 47894 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: TIM ENGLISH
HQ OPS Officer: JOHN KNOKE | Notification Date: 05/03/2012
Notification Time: 07:59 [ET]
Event Date: 05/03/2012
Event Time: 08:30 [EDT]
Last Update Date: 05/03/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DEBORAH SEYMOUR (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text PREPLANNED MAINTENANCE ON TSC VENTILATION SYSTEM
"At approximately 0830 EDT on 5/3/12, preplanned maintenance will be performed on the Technical Support Center (TSC) ventilation system. This maintenance will be performed for TSC Fan OA-2 for a motor replacement. This maintenance is planned to be performed and completed within 8 hours. If an emergency condition should occur that would require evacuation of the TSC, the Harris Nuclear Plant (HNP) emergency plan has procedural guidance for use of an alternate location.
"This event is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, Rev. 2 since this work activity affects an emergency response facility for the duration of the maintenance."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM TIM ENGLISH TO DONALD NORWOOD AT 1713 EDT ON 5/3/2012 * * *
Maintenance work has been completed and the TSC is considered operable as of 1713 EDT.
The licensee notified the NRC Resident Inspector. Notified R2DO (Seymour). |
| Part 21 | Event Number: 47895 | Rep Org: ENERGY SOLUTIONS
Licensee: ENERGY SOLUTIONS
Region: 4
City: SALT LAKE CITY State: UT
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAN SHRUM
HQ OPS Officer: PETE SNYDER | Notification Date: 05/03/2012
Notification Time: 11:02 [ET]
Event Date: 05/03/2012
Event Time: [MDT]
Last Update Date: 05/03/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
GREG WERNER (R4DO)
RICHARD CONTE (R1DO)
DEBORAH SEYMOUR (R2DO)
MARK RING (R3DO)
PART 21 REACTOR GRP (EMAI)
PART 21 MATERIALS GR (EMAI)
| Event Text SHIPPING CASKS TAKEN OUT OF SERVICE FOR ACCIDENT SCENARIO NOT PREVIOUSLY ANALYZED
"This serves as notification of a regulatory compliance issue with the 10-160B Type B Cask (Certificate of Compliance #9204) and the 8-120B Type B Cask (Certificate of Compliance #9168). This notification is being made in accordance with 10 CFR Part 21.21(d)(3)(i). These casks have been administratively placed out of service as Type B Packages until a complete determination can be made by Energy Solutions and the Nuclear Regulatory Commission (NRC).
"As part of the relicensing of new 8-120B Casks, Energy Solutions identified a hypothetical accident scenario required by 10 CFR 71 which was not previously analyzed as part of the original or ongoing licensing activities. This analysis confirmed that the current cask design does not comply with the Type B package requirement for this specific accident scenario. The 10-160B has a similar design. As such, the casks have been placed out of service. Energy Solutions initiated Condition Report ENG-CR12-018 to track this issue.
"In accordance with 10 CFR Part 21.21(d)(4), Energy Solutions will provide written notification to the NRC within 30 days with additional information including corrective actions." |
| Power Reactor | Event Number: 47896 | Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: RUSS PARKER
HQ OPS Officer: PETE SNYDER | Notification Date: 05/03/2012
Notification Time: 18:12 [ET]
Event Date: 05/03/2012
Event Time: 08:31 [CDT]
Last Update Date: 05/03/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
MARK RING (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OPERATOR FAILS FITNESS FOR DUTY TEST
"A licensed operating supervisor tested positive in a for-cause test for alcohol. The operator was not on shift during the day of the test. The operator's access to the plant has been suspended. A review of the operators work is being performed."
The license has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 47897 | Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [ ] [ ]
RX Type: [3] CE
NRC Notified By: JESSE BOHNENKAMP
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/03/2012
Notification Time: 21:07 [ET]
Event Date: 05/03/2012
Event Time: 16:13 [CDT]
Last Update Date: 05/03/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
GREG WERNER (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text BOTH TRAINS OF THE CONTROLLED VENTILATION AREA SYSTEM INOPERABLE
"This is a non-emergency 8 hour notification being made in accordance with 10CFR50.72(b)(3)(ii) Degraded or Unanalyzed Condition and 10CFR50.72(b)(3)(v) Prevented Safety Function. Both trains of the Controlled Ventilation Area System (CVAS) were considered inoperable from 1613 to 1641 CDT on 5/3/2012.
"Waterford 3 was performing planned maintenance on CVAS Train A with the train declared inoperable. Operations supervision was informed by maintenance personnel that an electrical conduit near the work area and not related to the work in progress had been found with a conduit connection unthreaded and separated. The contained wires could be seen and appeared intact. Investigation by engineering personnel determined that the conduit was associated with CVAS Train B. Operations declared CVAS Train B inoperable and entered Technical Specification (TS) 3.0.3 at 1613 hours.
"Operations personnel were already restoring CVAS Train A following completion of maintenance. After performing the planned retest, Operations declared CVAS Train A operable and exited TS 3.0.3 at 1641 hours. No actions were taken to commence a power reduction or reactor shutdown.
"The CVAS is required following a design basis accident to draw all exhaust air from the CVAS areas of the Reactor Auxiliary Building through HEPA and charcoal filters before discharge to the atmosphere. The CVAS areas contain equipment such as the shutdown cooling heat exchangers, safety injection pumps and other areas with containment penetrations. The CVAS is credited in accident analysis for limiting the radiological release under a Loss of Coolant Accident condition.
"Following repair of the conduit connection, Operations declared CVAS Train B operable at 1956 hours.
"Waterford 3 remained stable at 100% power during the condition. Both trains of offsite and onsite electrical sources, ECCS, and Containment Cooling safety systems remained operable during the condition."
The licensee notified the NRC Resident Inspector. | |