| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/03/2013 - 01/04/2013 ** EVENT NUMBERS ** |
 | Non-Agreement State | Event Number: 48606 | Rep Org: US GEOLOGICAL SURVEY
Licensee: US GEOLOGICAL SURVEY
Region:
City: State:
County:
License #:
Agreement: N
Docket:
NRC Notified By: CRAIG HENDRICKSON
HQ OPS Officer: CHARLES TEAL | Notification Date: 12/19/2012
Notification Time: 14:17 [ET]
Event Date: 11/20/2012
Event Time: 15:07 [EST]
Last Update Date: 12/20/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
| Person (Organization):
BLAIR SPITZBERG (R4DO)
FSME EVENT RESOURCE (EMAI)
MEXICO (FAX)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text POTENTIAL LOST OR STOLEN C-14 SOURCE
The licensee is reporting approximately 1.35 mCi of C-14 in liquid form that is missing it's Menlo Park facility.
On March 18, 1991 it was reported by the licensee to the Menlo Park Radiation Safety Committee that they had in their possession 9.3 mCi of C-14 which exceeded their maximum possession limit for the permit. At the time they recorded that they had ordered or logged as ordered 5 mCi and 0.25 mCi of C-14. However, the licensee could not find any records that those isotopes were actually received.
The RSO believes that the cause of the discrepancy from the quantity that they have and what was found is due to a bookkeeping error. On November 7, 1990 the records show that they transferred 1.725 mCi which would leave a balance of 2.171 mCi. This transfer does not show up on the records until August 20, 1991. The quantity was adjusted on the record to 2.173 mCi. They believe that back in 1991 they misreported the amount of Carbon-14 that they actually had in inventory and the error was carried forward.
The licensee is going to start doing physical inventories of all isotopes on a 6-month basis as a corrective action.
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: 48645 | Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BEN HUFFMAN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 01/03/2013
Notification Time: 02:01 [ET]
Event Date: 01/03/2013
Event Time: 03:00 [EST]
Last Update Date: 01/03/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RICHARD SKOKOWSKI (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 UNAVAILABILITY OF TSC VENTILATION SYSTEM DUE TO SCHEDULED MAINTENANCE
"At 0300 EST on Thursday, January 3, 2013, the DC Cook Nuclear Plant (CNP) Technical Support Center (TSC) air conditioning and charcoal filtration systems will be removed from service for scheduled maintenance.
"Under certain accident conditions the TSC may become unavailable due to the inability of the air conditioning and charcoal filtration systems to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary.
"TSC ventilation system maintenance and post maintenance testing is scheduled to be completed by 2200 EST on January 3, 2013.
"The licensee has notified the NRC Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to the loss of an emergency response facility."
* * * UPDATE FROM GREGORY KANDA TO S. SANDIN ON 1/3/13 AT 2202 EST * * *
"The TSC ventilation system maintenance and testing was completed satisfactorily and the system was restored to service at 2115 EST on 1/3/13.
"The licensee has notified the NRC Resident Inspector."
Notified R3DO (Skokowski). |
| Power Reactor | Event Number: 48646 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JIM ODELL
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 01/03/2013
Notification Time: 09:28 [ET]
Event Date: 01/03/2013
Event Time: 09:00 [EST]
Last Update Date: 01/03/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.55(e) - CONSTRUCT DEFICIENCY
| Person (Organization):
BINOY DESAI (R2DO)
NRR Part 50.55 Group ()
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Under Construction | 0 | Under Construction | Event Text COMMERCIAL GRADE DEDICATION PROGRAM DEGRADED
"WBN [Watts Bar Nuclear] Unit 2 (under construction) has determined that certain equipment components have been installed that may not meet the requirements of the commercial grade dedication process. This condition has the potential to create a substantial safety hazard had it remained uncorrected. Evaluations are being performed to determine if the installed equipment would have still performed their safety functions. No specific cases of a substantial safety hazard have been found to date, but until evaluations are completed, the safety significance of this condition remains indeterminate. Therefore, this condition is conservatively being reported by WBN Unit 2 under 10 CFR 50.55(e)."
This programmatic issue encompasses approximately 500 evaluations.
The licensee will contact the NRC Resident Inspector. |
| Power Reactor | Event Number: 48648 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DOUGLAS PETERSON
HQ OPS Officer: STEVE SANDIN | Notification Date: 01/03/2013
Notification Time: 15:03 [ET]
Event Date: 01/03/2013
Event Time: 09:30 [CST]
Last Update Date: 01/03/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RICHARD SKOKOWSKI (R3DO)
ERDS GROUP (EMAI)
CAT GROUP (EMAI)
|
| 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 ERDS CAPABILITY
"At 0930 [CST] on January 03, 2013 NextEra Energy Duane Arnold discovered that the Emergency Response Data System (ERDS) was no longer capable of transmitting plant data to the NRC. The loss of ERDS is reportable per 50.72(b)(3)(xiii).
"At 1151 [CST] on January 03, 2013 Information Management personnel restored ERDS to working status.
"The NRC Resident [Inspector] has been notified."
The licensee has the cause under investigation.
* * * UPDATE AT 2136 EST ON 01/03/13 FROM STEPHEN SPEIRS TO S. SANDIN * * *
"At 1725 [CST] on January 03, 2013 NextEra Energy Duane Arnold experienced a four minute interruption of the Emergency Response Data System (ERDS). During this time, ERDS was not capable of transmitting plant data to the NRC. The loss of ERDS is reportable per 10 CFR 50.72(b)(3)(xiii).
"The interruption of ERDS is related to a previous problem with the system reported under EN #48648. Troubleshooting of ERDS continues to ensure long-term reliability. Additional interruptions of ERDS are possible during this troubleshooting, and a follow-up notification will be made when ERDS reliability is assured."
The licensee informed the NRC Resident Inspector. Notified R3DO (Skokowski), ERDS Group and CAT Group via email. |
| Power Reactor | Event Number: 48649 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: STEVE GIFFORD
HQ OPS Officer: HOWIE CROUCH | Notification Date: 01/03/2013
Notification Time: 17:32 [ET]
Event Date: 01/03/2013
Event Time: 06:04 [CST]
Last Update Date: 01/03/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RAY AZUA (R4DO)
|
| 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 SAFTEY PARAMETER DISPLAY SYSTEM (SPDS)
"On 01/03/13 at 0604 CST, the Wolf Creek Generating Station Nuclear Plant Information System (NPIS) computer was removed from service for scheduled maintenance.
"The NPIS computer being removed from service results in a loss of functionality of the SPDS. Due to SPDS being lost for longer than a short period of time, Wolf Creek Nuclear Operating Corporation is making this ENS notification pursuant to the criteria of 10 CFR 50.72(b)(3)(xiii). There was no other loss of emergency assessment capability concurrent with the ongoing loss of SPDS. When the equipment was removed from service, plant personnel entered the appropriate Off-Normal procedure and obtained local readings for the equipment that is normally monitored by SPDS and NPIS during the loss of the plant computer.
"NPIS computer was restored to service and declared functional at 1541 CST. The return of the NPIS computer to a functional condition restored the SPDS assessment capability function.
"The licensee notified the NRC Resident Inspector." | |