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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
06/23/2009 - 06/24/2009
** EVENT NUMBERS **
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| General Information or Other |
Event Number: 45139 |
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: NOT APPLICABLE
Region: 1
City: EVERETT State: MA
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: MICHAEL WHALEN
HQ OPS Officer: HOWIE CROUCH |
Notification Date: 06/18/2009
Notification Time: 09:20 [ET]
Event Date: 05/22/2009
Event Time: [EDT]
Last Update Date: 06/18/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
ART BURRITT (R1DO)
ANGELA MCINTOSH (FSME) |
Event Text
AGREEMENT STATE REPORT - RADIOACTIVE MATERIAL DISCOVERED IN SCRAP METAL
The following information was obtained from the Commonwealth of Massachusetts via facsimile:
"On 5/22/2009, a tractor trailer with scrap metal [originating from Second Street Iron & Metal Co., Inc.] set off the radiation alarm monitors at Prolerized New England Company, LLC.
"The tractor trailer was returned to [the] originator (under DOT Special Permit MA-09-001) where a gauge with Ra-226 luminescent paint was found and isolated. The contact exposure rate was 1.65 mR/hr and the estimated activity was 1 microcurie.
"On 6/15/2009, the gauge was picked up for disposal by a Radioactive Waste broker." |
| General Information or Other |
Event Number: 45140 |
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: MASSACHUSETTS INSTITUTE OF TECHNOLOGY
Region: 1
City: ROXBURY State: MA
County:
License #: 60-0094
Agreement: Y
Docket:
NRC Notified By: JOSH DOEHLER
HQ OPS Officer: JOE O'HARA |
Notification Date: 06/18/2009
Notification Time: 15:02 [ET]
Event Date: 06/18/2009
Event Time: [EDT]
Last Update Date: 06/18/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
ART BURRITT (R1DO)
ANDREW PERSINKO (FSME) |
Event Text
AGREEMENT STATE REPORT - FIVE INDUSTRIAL SMOKE DETECTORS CONTAINING RADIUM 226 DISCOVERED INSIDE DUMPSTER
The following information was received via fax:
"On June 16,2009, Allied Waste - Howard Transfer Station located at 68 Norfolk Ave. Roxbury, Massachusetts responded to a radiation alarm at its facility and notified the Commonwealth of Massachusetts, Radiation Control Program. Radiation levels of about four (4) times background, measured at 18.8 microrem per hour, were reported coming from a roll off container dumpster attached to a truck operated by Casella Waste Systems, Inc. and a DOTÀE 11406 exemption was issued to Casella for proper transport of the unknown radioactive materials to its Peabody, Massachusetts facility located at 295 Forest Street. The roll off container originated from Massachusetts Institute of Technology (M.I.T) at 400 Main Street, Cambridge, Massachusetts and M.I.T. responded to this incident and recovered the radioactive materials.
"On June 17, 2009, M.I.T reported the radioactive material was five (5) industrial smoke detectors, each containing 40 micrograms of radium-226. M.I.T. reported that the detectors are now in their possession and will be disposed of as low level radioactive waste.
"The Commonwealth of Massachusetts continues to investigate this incident. |
| General Information or Other |
Event Number: 45144 |
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: METCO
Region: 4
City: HOUSTON State: TX
County:
License #: L-03-018
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: HOWIE CROUCH |
Notification Date: 06/19/2009
Notification Time: 10:02 [ET]
Event Date: 06/10/2009
Event Time: 02:35 [CDT]
Last Update Date: 06/19/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
CHUCK CAIN (R4DO)
ANGELA MCINTOSH (FSME) |
Event Text
AGREEMENT STATE REPORT - UNABLE TO RETRACT RADIOGRAPHY SOURCE
The following information was obtained from the State of Texas via email:
"On June 10, 2009, at approximately 2:35 a.m. while performing radiographic operations at GE Oil & Gas, two radiographers found they were unable to retract the radioactive material into the shielded position.
"They had made approximately 13 radiographic exposures prior to the malfunction. One of the radiographers contacted an approved Source Retrieval Supervisor, who was at the jobsite grading film. The Source Retrieval Supervisor immediately went to the area where the radiographic operation was located, assessed the situation and ensured the barricaded area was at less than 2 mR/hour. He determined the source was located within the collimator, but would not retract by normal means. The source tube was positioned with a fairly sharp bend which he felt may have put the drive cable in a bind, so he ran to the exposure device and repositioned it to reduce the source tube's bend. This action had no effect.
"The Source Retrieval Supervisor contacted the Site Radiation Safety Officer (RSO) by phone and reported the situation. They agreed that the Source Retrieval Supervisor should attempt to return the source to the exposure device by hand pulling the drive cable. After obtaining tools, the Source Retrieval Supervisor and one of the radiographers approached the crankout assembly, disassembled the crankout, and pulled the drive cable to return the source to the shielded position. After ensuring the source was in the exposure device, the crankout was further disassembled so that it could be disconnected from the source pigtail, the exposure device was locked and the source tube removed. The Source Retrieval Supervisor then called the RSO at approximately 3:00 a.m. to report the successful source retrieval. There were no members of the public in the immediate area.
"Pocket dosimeter reading for Source Retrieval Supervisor: 10 mR at start of retrieval operation, 15 mR at finish.
"Pocket dosimeter reading for Radiographer Aiding in Source Retrieval: 15 mR at start of retrieval operation, 15 mR at finish.
"Pocket dosimeter reading for Other Radiographer: 0
"Equipment involved:
Exposure device: Spec-150, s/n 0181
Source: QSA Global, 969, s/n 52911B, 35.8 curies
Source tube: NDT Repair & Supply, 7', serial number B13-2
Crankout: SPEC, 35', s/n 0603"
Texas Incident No. I-8641 |
| Power Reactor |
Event Number: 45148 |
Facility: HATCH
Region: 2 State: GA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: STEVE BURTON
HQ OPS Officer: HOWIE CROUCH |
Notification Date: 06/23/2009
Notification Time: 05:08 [ET]
Event Date: 06/23/2009
Event Time: 03:51 [EDT]
Last Update Date: 06/23/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION |
Person (Organization):
JONATHAN BARTLEY (R2DO) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
A/R |
Y |
61 |
Power Operation |
0 |
Hot Shutdown |
Event Text
AUTOMATIC REACTOR SCRAM DUE TO HIGH REACTOR WATER LEVEL
"[The reactor automatically scrammed] on a Main Turbine Trip >27.6% rated thermal power. The main turbine trip was due to reactor high level. Post scram, reactor level decreased to approximately -26 inches. Reactor water level was restored with the condensate system.
"Both reactor recirc pumps tripped as required on EOC RPT Logic when the main turbine tripped. Both pumps have been restarted.
"A Group 2 isolation was received at +3 inches reactor water level with all valves closing as required.
"Investigation as to the cause of the transient is underway."
All rods inserted during the scram. No relief valves actuated during the transient. Decay heat is being removed via turbine bypass valves to the main condenser. The plant is within normal shutdown temperature and pressure limits. The electrical grid is stable and the plant is in a normal shutdown electrical lineup. The Group 2 has been reset. There was no effect on Unit 1.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor |
Event Number: 45151 |
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JOHN KEENAN
HQ OPS Officer: VINCE KLCO |
Notification Date: 06/23/2009
Notification Time: 15:16 [ET]
Event Date: 06/23/2009
Event Time: 12:49 [CDT]
Last Update Date: 06/23/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION |
Person (Organization):
ANN MARIE STONE (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
OFFSITE NOTIFICATION DUE TO FISH KILL
"At 1249 CDT on 06/23/09, it was discovered that a fish kill took place in LaSalle County Nuclear Station's cooling lake, due to increased temperature. As summer air temperatures increased, the cooling lake temperature increased above 93?F, the threshold at which species susceptible to increased temperature begin to perish. It was communicated to the Illinois Department of Natural Resources (IDNR), that a fish kill has occurred. Efforts are under way to contact the IDNR district fish biologist to quantify the mortality.
"This notification is made in accordance with Exelon Reportability manual SAF 1.9, ENV 3.26, LaSalle County Station Facility Operating License Appendix B Section 4.1 'Unusual or Important Environmental Events', and 10CFR50.72(b)(2)(xi)."
The licensee notified the NRC Resident Inspector. |
| Power Reactor |
Event Number: 45152 |
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: TIM BUCHAL
HQ OPS Officer: VINCE KLCO |
Notification Date: 06/23/2009
Notification Time: 20:35 [ET]
Event Date: 06/23/2009
Event Time: 18:23 [EDT]
Last Update Date: 06/23/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD |
Person (Organization):
PAMELA HENDERSON (R1DO) |
| 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
POTENTIALLY DEGRADED INVENTORY CONTROL DURING SHUTDOWN
"[At 1823 EDT, the] 23 charging pump, the in-service pump, exhibited degraded capacity resulting in slowly lowering pressurizer level. The 21 charging pump was placed in service and the 23 charging pump was secured. The 23 charging pump is required for fulfillment of the [Reactor Coolant System] RCS inventory control safety function needed to shut down the reactor and maintain it in a safe shutdown condition. Troubleshooting is in progress to determine cause of degraded capacity."
In accordance with Technical Specification 3.3.4, the out of service 23 charging pump places the Indian Point Unit 2 into a 30 day shutdown action statement.
The licensee notified the NRC Resident Inspector and the New York Public Service Commission (PSC) of the event. |
| Power Reactor |
Event Number: 45153 |
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BRANDON SHULTZ
HQ OPS Officer: VINCE KLCO |
Notification Date: 06/23/2009
Notification Time: 22:40 [ET]
Event Date: 06/23/2009
Event Time: 20:30 [EDT]
Last Update Date: 06/23/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
PAMELA HENDERSON (R1DO) |
| 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
PARTIAL LOSS OF THE EMERGENCY RESPONSE DATA SYSTEM (ERDS)
"A partial loss of the ability to send ERDS data to the NRC for greater than 60 minutes occurred. The loss affects transmission of Standby Liquid Control Tank levels, Main Condenser Vacuum levels, and data for North and South Ventilation Stacks and Drywall Post LOCA radiation monitors.
"The [Safety Parameter Display System] SPDS, [Health Physics Network] HPN and [Emergency Notification System] ENS systems are not affected.
"Troubleshooting to identify and correct the data loss to ERDS is in progress."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 0029 EDT ON 6/24/09 FROM SHULTZ TO HUFFMAN * * *
"Data for North and South Ventilation Stacks and Drywell Post LOCA monitors was restored to ERDS at 2345 hours on 6/23/09"
The licensee will notify the NRC Resident Inspector. |
| Power Reactor |
Event Number: 45154 |
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ELLIS VANN
HQ OPS Officer: BILL HUFFMAN |
Notification Date: 06/23/2009
Notification Time: 23:37 [ET]
Event Date: 06/23/2009
Event Time: 17:04 [CDT]
Last Update Date: 06/24/2009 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION |
Person (Organization):
ANN MARIE STONE (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 |
Event Text
AUTO START OF EMERGENCY DIESEL GENERATORS DUE TO OFFSITE VOLTAGE TRANSIENT
"This report is being made under 10CFR50.72(b)(3)(iv)(A), 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(A) of this section' due to the auto start of the 'A' and 'B' Standby Diesel Generators.
"The auto start of the 'A' and 'B' Standby Diesel Generators occurred on a valid bus undervoltage condition caused by a transient on the 161 kV Fairfax line while there were severe thunderstorms in the DAEC area. The Standby Diesel Generator supply breakers did not close onto their respective essential buses. The essential buses were not required to load onto either diesel as they remained powered from their normal power supply, 1X003 Start-up Transformer, during and after the event. Offsite power remained fully operable during and following the event. The Standby Diesel Generators have been returned to the standby/readiness condition.
"As designed, both Emergency Service Water systems auto started when the SBDGs started. The Emergency Service Water systems have been returned to the standby/readiness condition.
"All ECCS systems were available before the event and have remained available following the event.
"The NRC Resident Inspector has been informed of the automatic SBDG start." |
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