| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/05/2010 - 03/08/2010 ** EVENT NUMBERS ** |
 | Other Nuclear Material | Event Number: 45735 | Rep Org: COVIDIEN-MALLINCKRODT
Licensee: COVIDIEN-MALLINCKRODT
Region: 3
City: MARYLAND HEIGHTS State: MO
County:
License #: 24-04206-01
Agreement: N
Docket:
NRC Notified By: JIM SCHUH
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/01/2010
Notification Time: 10:47 [ET]
Event Date: 03/01/2010
Event Time: 09:15 [CST]
Last Update Date: 03/05/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
JOHN GIESSNER (R3DO)
ANGELA MCINTOSH (FSME)
DENNIS ALLSTON (ILTA)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text TECHNETIUM GENERATOR LOST IN TRANSIT
Covidien was shipping a Molybdenum/Technetium generator to Bermuda on 2/12/2010. It was being transshipped in Atlanta for air delivery to Bermuda on one of Delta Airlines twice weekly flights. On 2/14/2010, the shipment was bumped to the next flight and on 2/18/2010 it was again bumped. The recipient was contacted and declined the shipment. Delta was contacted and stated that they could no longer locate the shipment.
The initial activity was 3 Ci of Mo-99m which would have decayed to 41 mCi on 3/1/2010.
* * * UPDATE ON 3/5/10 AT 1030 EST FROM DAN HOFFMAN TO PETE SNYDER * * *
On March 3, 2010, Covidien was notified by Delta that they had located the package at their Bermuda Cargo Facility. Delta will return the package to Covidien.
Notified R3DO (Giessner) and FSME (McIntosh).
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 |
| General Information or Other | Event Number: 45741 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: M/A-COM TECHNOLOGY SOLUTIONS, INC.
Region: 1
City: LOWELL State: MA
County:
License #: G0230
Agreement: Y
Docket: 03-8913
NRC Notified By: J. THOMAS COULOMBE
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/03/2010
Notification Time: 12:24 [ET]
Event Date: 03/03/2010
Event Time: [EST]
Last Update Date: 03/03/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JOHN WHITE (R1DO)
ANGELA MCINTOSH (FSME)
ILTAB via email ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - MISSING STATIC ELIMINATION DEVICE
The following information was received from the State via facsimile:
"The current general licensee, M/A-COM Technology Solutions, Inc., at the same location of the former, original general licensee, Tyco Electronics M/A-COM, at 100 Chelmsford Street, in Lowell, Massachusetts has no knowledge of the location of one static elimination device. The device had been used in a process that was terminated in 2007. The facility has been searched and employees and past employees have been questioned. The general licensee has declared the device as missing. The Agreement State has contacted the distributor and determined that the device was not returned to them.
"Source: 10mCi, Po-210
"Manufacture: NRD, Inc.
"Model Number: P-2021
"Serial Number: 114186"
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 |
| General Information or Other | Event Number: 45742 | Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: AMEC EARTH & ENVIRONMENT, INC.
Region: 4
City: MIDVALE State: UT
County:
License #: UT1800164
Agreement: Y
Docket:
NRC Notified By: GWYN GALLOWAY
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/03/2010
Notification Time: 16:25 [ET]
Event Date: 02/23/2010
Event Time: 16:35 [MST]
Last Update Date: 03/03/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
CHUCK CAIN (R4DO)
MARK DELLIGATTI (FSME)
| Event Text AGREEMENT STATE REPORT - DAMAGED TROXLER
The following information was received from the State via facsimile:
"A Troxler Electronic Laboratories, Inc. Model 3430, portable gauging device [serial number 17906, containing approximately 8.0 millicuries of cesium-137 (source serial number 750-7391), and approximately 40 millicuries of americium-241/beryllium (source serial number 47-13347)] was hit by an excavator at a temporary jobsite. The Cs-137 source was in the safe shielded position when it was hit and the source remained shielded after it was struck by the excavator. A leak test was performed and no leakage was detected from either source."
Utah Event Number: UT-10-0001 |
| Power Reactor | Event Number: 45745 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: DONALD NORWOOD | Notification Date: 03/05/2010
Notification Time: 03:25 [ET]
Event Date: 03/05/2010
Event Time: 00:07 [CST]
Last Update Date: 03/05/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
CHUCK CAIN (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text SPECIFIED SYSTEM ACTUATION - FEEDWATER ISOLATION DUE TO HIGH STEAM GENERATOR WATER LEVEL
"A Turbine trip and Feedwater Isolation Signal was generated as a result of high level in 'A' Steam Generator. At approximately 0007 CST, a turbine trip and Feedwater Isolation Signal was generated when the level in the 'A' Steam Generator exceeded the initiation set point of 78%. Steam Generator level returned below the initiation setpoint at approximately 0008 CST. Steam Generator 'A' high level resulted from swell of the Steam Generator after opening the 'A' Main Steam Isolation Valve. Level was approximately 50% prior to the event and returned to approximately 50% within one minute.
"The turbine was already in the tripped condition due to the plant trip that occurred at 1458 CST on 03/02/2010 (Reference EN# 45739).
"Steam Generators are being fed with the motor driven startup Feedwater pump. Decay heat removal is via the Steam Generator Atmospheric Relief Valves and steam dumps. The plant is in Mode 4 with Reactor Coolant System pressure at approximately 500 psig and temperature at approximately 332 degrees F.
"Two Main Feedwater isolation valves did not fully close but the actuators were being supplied with auxiliary medium (air) at the time of the actuation. Feedwater isolation valves are not required to be operable in Mode 4."
The licensee will notify the NRC Resident Inspector. |
| Other Nuclear Material | Event Number: 45746 | Rep Org: NASA AMES RESEARCH CENTER
Licensee: NASA AMES RESEARCH CENTER
Region: 4
City: MOFFETT FIELD State: CA
County:
License #: 04-07845-04
Agreement: Y
Docket:
NRC Notified By: PATRICK MULDOON
HQ OPS Officer: HOWIE CROUCH | Notification Date: 03/05/2010
Notification Time: 13:29 [ET]
Event Date: 02/03/2010
Event Time: [PST]
Last Update Date: 03/05/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
CHUCK CAIN (R4DO)
MARK DELLIGATTI (FSME)
ILTAB VIA EMAIL ()
MEXICO VIA FAX ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text TWO MISSING TRITIUM EXIT SIGNS
During their biannual inventory, the licensee could not account for two tritium exit signs. Both signs were accounted for in the previous inventory. The first sign was installed in a wind tunnel that was transferred to the Air Force in 2006. After obtaining the wind tunnel, the Air Force claims to have removed the sign and, after a period of storage, recycled the sign with the others that were removed from the tunnel. The sign was manufactured on 7/20/94 by SRB Technologies (serial number 174501). The initial tritium load was 20 Ci. Calculated content on 2/26/10 was 8.33 Curies.
The second sign was installed in a building on Moffitt Field that is currently undergoing renovation. It is believed that the sign is under the control of the renovation contractor after is was removed during the painting process. The sign was manufactured on 5/1/91 by SRB Technologies (serial number 526854). The initial tritium load was 20 Ci. Calculated content on 2/26/10 was 6.95 Curies.
Both signs have contact information for the licensee attached. The licensee is conducting a search for both signs. They have notified Region 4 (Campbell).
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: 45747 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DAVID HURT
HQ OPS Officer: HOWIE CROUCH | Notification Date: 03/05/2010
Notification Time: 16:32 [ET]
Event Date: 03/05/2010
Event Time: 13:25 [CST]
Last Update Date: 03/05/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
CHUCK CAIN (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 UNANALYZED CONDITION - STEAM SUPPLY VALVE CREDITED AS CLOSED IN FSAR ANALYSIS IS NORMALLY OPEN DURING OPERATIONS
"Valve FBV0147, Boric Acid Batch Tank Auxiliary Steam Supply Isolation Valve, is credited with being closed in the Callaway FSAR. This eliminated the need to analyze lines FB-081-HBD and FB-082-HBD for high energy line breaks (HELB). However, FBV0147 was found to be kept normally open to allow steam service for the boric acid batching tank. This is contrary to the normal position assumed in the FSAR and HELB analyses.
"With valve FBV0147 open, the lines must considered high energy lines. The lines are in the auxiliary building and they traverse rooms containing several components including the flow transmitters for Residual Heat Removal (RHR) to train `A' accumulator injection supply header, RHR train `A' and 'B' SIS hot leg recirculation supply header, and several safety related auxiliary feedwater components. These instruments are used to provide indications during post-accident conditions. This configuration is therefore outside of current HELB analysis and potentially represents a condition that significantly degrades plant safety.
"The condition was identified to Operations at 0740. Valve FBV0147 was closed at 0810. At 1325 CST, the issue was determined to be reportable.
The NRC resident inspector has been notified." |
| Power Reactor | Event Number: 45748 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: ALFRED ERDELJI
HQ OPS Officer: HOWIE CROUCH | Notification Date: 03/07/2010
Notification Time: 14:23 [ET]
Event Date: 03/07/2010
Event Time: 11:24 [MST]
Last Update Date: 03/07/2010 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
CHUCK CAIN (R4DO)
BRIAN HOLIAN (NRR)
WILLIAM GOTT (IRD)
ELMO COLLINS (R4)
ERIC LEEDS (NRR)
RYAN LANTZ (R4)
BILL ROPER (DHS)
MIKE LAFORTE (FEMA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text NOTIFICATION OF UNUSUAL EVENT DUE TO ELECTRICAL FAULT CAUSING DAMAGE TO EQUIPMENT
"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"On March 7, 2010, at approximately 1124 MST Palo Verde Unit 1 declared a Notification of Unusual Event (NOUE) due to an electrical fault (explosion) experienced on the 13.8 KV Non-Class busses being supplied from the Unit Auxiliary Transformer. The fault resulted in a minor explosion and damage to the bus work leading from NAN S03 to NAN S01. The fault resulted in the loss of the NAN S01, which caused a reactor trip due to the loss of 2 of 4 reactor coolant pumps. There was no fire detected after the initial event. The reactor trip (RPS actuation at 1117 MST) was from 100% rated thermal power due to low departure from nucleate boiling (DNBR) trips on all four channels of the core protection calculators (CPCs). The unit was at normal temperature and pressure prior to the trip.
"All of the control rods fully inserted into the core. Four of eight steam bypass control valves quick opened, per design, directing steam flow to the condenser. No main steam or primary relief valves lifted and none were required. There was no loss of heat removal capability or loss of safety functions associated with the event. ESF Electrical buses remain energized from off-site power.
"The Shift Manager determined this event was an uncomplicated reactor trip. No significant LCOs have been entered as a result of this event. No major equipment was inoperable prior to the event nor contributed to the event.
"Unit 1 is stable at normal operating temperature and pressure in Mode 3. No ESF actuations [other than RPS] occurred and none were required. The event did not result in any challenges to the fission product barrier or result in any releases of radioactive materials. There were no adverse safety consequences or implications as a result of this event. The event did not adversely affect the safe operation of the plant or health and safety of the public."
Decay heat is being removed via the steam bypass valves to the condenser. The plant is in its normal shutdown electrical lineup with the exception of powering the NAN S01 bus. Unit 2 and Unit 3 were not affected by the transient on Unit 1.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM ALFRED ERDELJI TO HOWIE CROUCH @ 1723 EST ON 3/7/10 * * *
Palo Verde Unit 1 has terminated the NOUE at 1516 MST. The termination criteria was that the plant is stable, the area around the fault has been inspected and no other conditions exist that would prevent termination of the event.
Decay heat path has been changed from steam dumps to condenser to atmospheric dumps due to difficulty in maintaining temperature. There is no known primary to secondary leakage.
The licensee has notified the NRC Resident Inspector. Notified R4DO (Cain), NRR EO (Holian), IRD (Gott), DHS (Roper) and FEMA (LaForte). | |