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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/30/2007 - 05/01/2007
** EVENT NUMBERS **
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| General Information or Other |
Event Number: 43319 |
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: BAYSTATE HEALTH MEDICAL CENTER
Region: 1
City: SPRINGFIELD State: MA
County:
License #: 60-0095
Agreement: Y
Docket:
NRC Notified By: TONY CARPENITO
HQ OPS Officer: MARK ABRAMOVITZ |
Notification Date: 04/25/2007
Notification Time: 13:07 [ET]
Event Date: 04/25/2007
Event Time: [EDT]
Last Update Date: 04/25/2007 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
JAMES TRAPP (R1)
GREG MORELL (FSME) |
| This material event contains a "Less than Cat 3" level of radioactive material. |
Event Text
ONE I-125 PROSTATE SEED REPORTED MISSING
The State provided the following information via email:
"On 3/27/07, licensee reports being unable to locate a single Bard STM 1251 prostate seed containing 0.35 millicuries of Iodine-125 (60-day half-life) soon after a 130-seed (120 stranded seeds and 10 single seeds) medical procedure. This single titanium cylindrical capsule measures 0.8 mm (~0.03 inch) in diameter and 4.5 mm (~0.18 inch) in length (see Sealed Source Registry No. IL-1074-S-101-S). The last known location of the seed was in an operating room within the licensee's facility in Springfield, MA.
"The licensee conducted an extensive search of its facilities as described in its written report dated April 9, 2007. The licensee assumes the seed is lost at this point in time.
"In order to prevent recurrence, the licensee implemented updated seed counting and inventory control procedure changes and assignment responsibilities.
"Cause description: Inconsistent use of seed well container. All 10 single seeds were placed in one well instead of placing one seed in each of ten wells within container.
"Corrective action: Updated seed counting, inventory control procedure changes, and assignment responsibilities."
Massachusetts Event Docket Number: 04-6969
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. |
| Power Reactor |
Event Number: 43326 |
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BARRY COLEMAN
HQ OPS Officer: JOE O'HARA |
Notification Date: 04/30/2007
Notification Time: 09:45 [ET]
Event Date: 04/30/2007
Event Time: 09:00 [EDT]
Last Update Date: 04/30/2007 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
CHARLIE PAYNE (R2) |
| 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
LOSS OF EMERGENCY RESPONSE FACILITY - TSC VENTILATION SYSTEM UNAVAILABLE DUE TO MAINTENANCE
"Planned preventive maintenance activities are being performed today (April 30, 2007) on the Hatch Nuclear Plant's Technical Support Center (TSC). These work activities are planned to be performed and completed expeditiously within one work shift (< 12 hours). These maintenance activities include the performance of preventive maintenance on the TSC filter train, air handling unit, condensing unit and fan unit for the TSC filler train. During a portion of the time these activities are being performed, this equipment will not be available for operation. As such, the TSC HVAC will be rendered non-functional during the performance of portions of the work activity.
"If an emergency condition occurs that requires activation of the Technical Support Center, during the time these work activities are being performed, it will take no more than two hours to return the equipment back to functional status, dependent on the stage of the work activity at the time an emergency occurs. Plans are to utilize the TSC for any declared emergency during the time these work activities are being performed as long as radiological conditions allow. Procedure 73EP-EIP-063-0. Technical Support Center Activation, provides instructions to direct TSC management to the Control Room and TSC support personnel to the Simulator Building to continue TSC activities if it is necessary to relocate from the primary TSC.
"This event is reportable per I0CFR50.72 (b) (3) (xiii) as described in NUREG-1022, Rev. 1 since this work activity affects an emergency response facility for the duration of the evolution."
The licensee notified the NRC Resident Inspector. The licensee will make a courtesy notification to the State and local officials. |
| Other Nuclear Material |
Event Number: 43327 |
Rep Org: PLASTECH
Licensee: PLASTECH
Region: 3
City: FOWLERVILLE State: MI
County:
License #:
Agreement: N
Docket:
NRC Notified By: PATRICIA DIETZEN
HQ OPS Officer: JOE O'HARA |
Notification Date: 04/30/2007
Notification Time: 11:43 [ET]
Event Date: 04/24/2007
Event Time: [EDT]
Last Update Date: 04/30/2007 |
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X |
Person (Organization):
DAVE PASSEHL (R3)
GREG MORELL (FSME)
ILTAB (e-mail) () |
| This material event contains a "Less than Cat 3" level of radioactive material. |
Event Text
LOST STATIC ELIMINATOR
Plastech contacted the NRC Operations Center to inform us that they performed an inventory on 4/24/07 and identified that an Amstat Industries, Inc. static eliminator S/N A2DF555, Model - P2021-8101 was missing and presumed lost. The static eliminator has not been seen since November of 2006. The person providing the report said that the initial activity of the static eliminator was 10 milli Curies but did not know what isotope was used in the device. Typically Amstat Industries static eliminators use Polonium-210. The company recognized the loss during an inventory required to renew their lease.
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. |
| Other Nuclear Material |
Event Number: 43328 |
Rep Org: ACUREN - USA
Licensee: ACUREN - USA
Region: 4
City: LAPORTE State: TX
County:
License #: 42-32443-01
Agreement: Y
Docket:
NRC Notified By: LLOYD GRAY
HQ OPS Officer: BILL HUFFMAN |
Notification Date: 04/30/2007
Notification Time: 15:49 [ET]
Event Date: 04/30/2007
Event Time: 14:00 [CDT]
Last Update Date: 04/30/2007 |
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X |
Person (Organization):
NEIL O'KEEFE (R4)
GREG MORELL (FSME)
BENJAMIN SANDLER (TAS)
JEFFREY CRUZ (IRD)
HASELTON (DHS)
MORRONY (DOE)
SNODEN (EPA)
GILES (USDA)
WILLIAMS (HHS)
FULLER (FEMA) |
| This material event contains a "Category 2" level of radioactive material. |
Event Text
RADIOGRAPHY CAMERA MISSING IN TRANSIT
The licensee's RSO reports that a Sentinel Model 880 delta radiography camera containing a 31 curie Iridium-192 source is missing in transit. The camera was shipped with two other radiography cameras from Anchorage Alaska on April 24, 2007. The cameras were being sent to QSA Global in Baton Rouge, Louisiana for source replacement. Two of the cameras arrived at QSA Global as scheduled on April 26, 2007. However, the third camera has not yet arrived as of the time of this report. The shipper is Federal Express. Each camera was assigned a separate FedEx tracking number but all three cameras were shipped at the same time. The RSO is attempting to track the package but has not yet received priority attention. The FedEx tracking system still shows the package in transit at Oakland CA. The RSO was not notified of the missing shipment by QSA Global until approximately 1400 CDT on 4/30/07.
* * * UPDATE FROM GRAY TO HUFFMAN AT 1814 EDT ON 4/30/07 * * *
The licensee reports that after a high priority trace by FedEx, the package was confirmed to still be in Oakland CA. FedEx stated that the camera will be sent onto Baton Rouge tonight. The licensee no longer considers the shipment missing. R4DO (O'Keefe), FSME (Morell), IRD(Cruz), and ILTAB (Sandler) notified. Applicable Federal Agencies have also been made.
THIS MATERIAL EVENT CONTAINS A "CATEGORY 2" LEVEL OF RADIOACTIVE MATERIAL
Category 2 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. These sources are typically used in practices such as industrial gamma radiography, high dose rate brachytherapy and medium dose rate brachytherapy. |
| Power Reactor |
Event Number: 43329 |
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD DESANCTIS
HQ OPS Officer: PETE SNYDER |
Notification Date: 04/30/2007
Notification Time: 16:49 [ET]
Event Date: 04/30/2007
Event Time: 15:02 [EDT]
Last Update Date: 04/30/2007 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL |
Person (Organization):
DANIEL HOLODY (R1) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
Y |
80 |
Power Operation |
0 |
Hot Standby |
Event Text
REACTOR TRIP DUE TO GRASS INTRUSION INTO CIRCULATING WATER INTAKE STRUCTURE
"A manual trip of Salem Unit 1 was initiated due to a loss of the circulators from heavy grassing at the circulating water intake structure. All rods fully inserted on the trip and all systems responded as designed, with decay heat being removed via the atmospheric relief valves and subsequently the steam dump system. All Auxiliary Feedwater pumps auto started as expected on low steam generator levels from the trip. Salem Unit 1 had entered the abnormal operating procedure for circulating water due to two (2) circulators being out of service; one circulator previously emergency tripped due to excessive traveling water screen [differential pressure] and a second circulator emergency tripped soon thereafter. The procedure provides guidance to trip the plant if less than three (3) circulators are in service and power is above ten (10) percent. Two (2) of the remaining four (4) in-service circulators emergency tripped due to excessive traveling water screen differential pressure. At this point the manual reactor trip was initiated. The crew entered emergency operating procedures and stabilized the plant at no load conditions.
"No personnel injuries have occurred as a result of the trip. Salem Unit 2 was not affected and is operating at 100% power.
"Salem Unit 1 is currently in Mode 3. Reactor Coolant System temperature is 547° F with pressure at 2235 psig.
"All ECCS and ESF Systems are available. Actions are being taken to return circulators to service."
The licensee notified the NRC Resident Inspector. |
| Power Reactor |
Event Number: 43331 |
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BRIAN HUPKE
HQ OPS Officer: JOE O'HARA |
Notification Date: 05/01/2007
Notification Time: 00:39 [ET]
Event Date: 04/30/2007
Event Time: 20:17 [CDT]
Last Update Date: 05/01/2007 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION |
Person (Organization):
CHRISTINE LIPA (R3) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
Y |
98 |
Power Operation |
98 |
Power Operation |
Event Text
HPCI DECLARED INOPERABLE DUE TO PRIMARY CONTAINMENT NITROGEN LEAK
"At 1007 on the morning of 04/30/2007, operations personnel identified an adverse trend in Primary Containment Nitrogen makeup frequency. The subsequent investigation determined that Primary Containment Nitrogen was leaking backwards thru V22-0017 HPCI Turbine Exhaust Line Stop-Check Valve and V22-0016 HPCI Exhaust Check Valve, via the HPCI exhaust vacuum breakers and the environment of the HPCI room via the turbine seals.
"The degradation of V22-0016 and V22-0017 constitute a condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident. (50.72(b)(3)(v)(D)).
"At 2017 on the evening of 04/30/2007, V22-0017 HPCI Turbine Exhaust Line Stop-Check Valve and V22-0016 HPCI Exhaust Check Valve were declared inoperable due to Primary Containment Nitrogen leakage as described above.
"At 2032 on the evening of 04/30/2007, V22-0017 HPCI Turbine Steam Exhaust Line Isolation was shut to isolate Primary Containment Nitrogen leakage.
"With V22-0017 shut, HPCI is INOPERABLE and Unavailable."
The licensee is in a 14 day LCO under section 3.6.1.3 for Primary Containment Isolation Valves (PCIV). However, they are in a 72 hour LCO for having "A" core spray and HPCI inoperable, concurrently. The licensee expects to have "A" core spray restored during dayshift on 5/1/07. Additionally, the licensee is in a 7 day LCO for EDG OOS.
The licensee notified the NRC Resident Inspector. |
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