Event Notification Report for February 16, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/15/2011 - 02/16/2011
Power Reactor
Event Number: 46618
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ANDREW WISNIEWSKI
HQ OPS Officer: JOHN SHOEMAKER
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ANDREW WISNIEWSKI
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 02/16/2011
Notification Time: 15:29 [ET]
Event Date: 02/16/2011
Event Time: 11:25 [EST]
Last Update Date: 02/16/2011
Notification Time: 15:29 [ET]
Event Date: 02/16/2011
Event Time: 11:25 [EST]
Last Update Date: 02/16/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MARC FERDAS (R1DO)
MARC FERDAS (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 |
STEAM LEAK ON HIGH PRESSURE COOLANT INJECTION SYSTEM
"During system startup of [High Pressure Coolant Injection] HPCI for quarterly surveillance, audible and visual indications of steam leakage were observed. The system was secured and subsequently isolated (with outboard valve de-energized for configuration control). As a result of the steam leakage, a local fire alarm was received in the Control Room. HPCI is currently isolated and will not perform its safety function.
"Operators were dispatched to the Reactor Building fire panel to verify that the fire alarm was due solely to the steam leak. As a precautionary measure, personnel were evacuated from the Reactor Building. Operators entered [Off Normal Procedure] ON 3158, Reactor Building High Area Temperature/Water Level, and verified that room temperatures were decreasing after the steam line was isolated. No EOP-4, Secondary Containment Control, entry conditions were exceeded."
The steam leak was isolated when HPCI was secured. Associated fire alarms were verified to be caused by the steam leak. There was no impact on other plant equipment or personnel safety. The source of the steam leak is suspected to be from a steam trap but this has not been confirmed.
The licensee notified the NRC Resident Inspector and the State of Vermont Department of Public Service Nuclear Engineer.
Notified R1DO (Ferdas)
"During system startup of [High Pressure Coolant Injection] HPCI for quarterly surveillance, audible and visual indications of steam leakage were observed. The system was secured and subsequently isolated (with outboard valve de-energized for configuration control). As a result of the steam leakage, a local fire alarm was received in the Control Room. HPCI is currently isolated and will not perform its safety function.
"Operators were dispatched to the Reactor Building fire panel to verify that the fire alarm was due solely to the steam leak. As a precautionary measure, personnel were evacuated from the Reactor Building. Operators entered [Off Normal Procedure] ON 3158, Reactor Building High Area Temperature/Water Level, and verified that room temperatures were decreasing after the steam line was isolated. No EOP-4, Secondary Containment Control, entry conditions were exceeded."
The steam leak was isolated when HPCI was secured. Associated fire alarms were verified to be caused by the steam leak. There was no impact on other plant equipment or personnel safety. The source of the steam leak is suspected to be from a steam trap but this has not been confirmed.
The licensee notified the NRC Resident Inspector and the State of Vermont Department of Public Service Nuclear Engineer.
Notified R1DO (Ferdas)
Agreement State
Event Number: 46622
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: RMA GROUP
Region: 4
City: RANCHO CUCAMONGA State: CA
County:
License #: 2700-36
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: VINCE KLCO
Licensee: RMA GROUP
Region: 4
City: RANCHO CUCAMONGA State: CA
County:
License #: 2700-36
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: VINCE KLCO
Notification Date: 02/17/2011
Notification Time: 20:16 [ET]
Event Date: 02/16/2011
Event Time: 00:00 [PST]
Last Update Date: 02/17/2011
Notification Time: 20:16 [ET]
Event Date: 02/16/2011
Event Time: 00:00 [PST]
Last Update Date: 02/17/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
VINCENT GADDY (R4DO)
DUNCAN WHITE (FSME)
ILTAB VIA EMAIL
MEXICO VIA FAX
VINCENT GADDY (R4DO)
DUNCAN WHITE (FSME)
ILTAB VIA EMAIL
MEXICO VIA FAX
AGREEMENT STATE REPORT - LOST MOISTURE DENSITY GAUGE SOURCE
The following information was received by email:
"On February 16, 2011, RHB [California Radiologic Health Branch] South RM [Radiologic Materials] was contacted by the [licensee] RSO [Radiation Safety Officer] of RMA Group, concerning a loss of the Cs-137 source from a Troxler model 3430 (S/N 25220) moisture density gauge (8 mCi Cs-137, SN 758021, 40 mCi Am:Be-241, SN 4721490). [The licensee RSO] stated that the Troxler gauge was in use at a construction site located at the on/off ramp of Interstate 10 at North Indian Canyon Drive, near Palm Springs in early February (sometime between Feb. 3 and Feb. 8, 2011). [The licensee RSO] stated that operator noticed that the readings taken had dropped significantly from his previous readings and thought that the computer in the gauge had malfunctioned and the gauge was returned to their facility and stored until it was taken in for service at Southwest Calibration and Training LN 7567 (SWCT) on February 14 or 15. On the afternoon of February 16, 2011, [The licensee RSO] was contacted by SWCT that the Cs-137 source pellets were missing due to the cap of the source capsule breaking off at the weld. [The licensee RSO] stated that Troxler service was consulted and that they were informed that this was an issue that had occurred twice previously in the past 6 years and that they had requested that the source rod be returned to them to allow them to determine how the break had occurred.
"[The licensee RSO] stated that he had been given a survey meter to be used to attempt to find the source. [The licensee RSO] stated that a survey of the storage area of their Rancho Cucamonga facility (all of the other gauges were out being used at the time) and the vehicle used to transport the gauge when the incident was likely to have occurred and did not find the source. [The licensee RSO] stated that he would attempt to find the sources at the construction site in the morning when he had determined the area that the gauge was in use when the incident occurred. [The licensee RSO] stated that the source may have already been buried under 10 inches of fill (soil) and 8-10 inches of asphalt, but he was not absolutely sure. [The licensee RSO] was informed that a 30 day report was required to be submitted to [the RHB] office.
"On February 17, 2011, [RHB] confirmed that the damaged gauge had never had any incidents or trauma that potentially could have resulted in damage to the source capsule and that the construction site was on N. Indian Canyon Drive at one of the on/off ramps to Interstate 10. The results of the search for the missing source and a confirmation of the exact location of the incident will be forwarded to NMED when the RSO has confirmed the information. An investigation into the cause of the damage of the source capsule and possible location of the source capsule is ongoing."
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
The following information was received by email:
"On February 16, 2011, RHB [California Radiologic Health Branch] South RM [Radiologic Materials] was contacted by the [licensee] RSO [Radiation Safety Officer] of RMA Group, concerning a loss of the Cs-137 source from a Troxler model 3430 (S/N 25220) moisture density gauge (8 mCi Cs-137, SN 758021, 40 mCi Am:Be-241, SN 4721490). [The licensee RSO] stated that the Troxler gauge was in use at a construction site located at the on/off ramp of Interstate 10 at North Indian Canyon Drive, near Palm Springs in early February (sometime between Feb. 3 and Feb. 8, 2011). [The licensee RSO] stated that operator noticed that the readings taken had dropped significantly from his previous readings and thought that the computer in the gauge had malfunctioned and the gauge was returned to their facility and stored until it was taken in for service at Southwest Calibration and Training LN 7567 (SWCT) on February 14 or 15. On the afternoon of February 16, 2011, [The licensee RSO] was contacted by SWCT that the Cs-137 source pellets were missing due to the cap of the source capsule breaking off at the weld. [The licensee RSO] stated that Troxler service was consulted and that they were informed that this was an issue that had occurred twice previously in the past 6 years and that they had requested that the source rod be returned to them to allow them to determine how the break had occurred.
"[The licensee RSO] stated that he had been given a survey meter to be used to attempt to find the source. [The licensee RSO] stated that a survey of the storage area of their Rancho Cucamonga facility (all of the other gauges were out being used at the time) and the vehicle used to transport the gauge when the incident was likely to have occurred and did not find the source. [The licensee RSO] stated that he would attempt to find the sources at the construction site in the morning when he had determined the area that the gauge was in use when the incident occurred. [The licensee RSO] stated that the source may have already been buried under 10 inches of fill (soil) and 8-10 inches of asphalt, but he was not absolutely sure. [The licensee RSO] was informed that a 30 day report was required to be submitted to [the RHB] office.
"On February 17, 2011, [RHB] confirmed that the damaged gauge had never had any incidents or trauma that potentially could have resulted in damage to the source capsule and that the construction site was on N. Indian Canyon Drive at one of the on/off ramps to Interstate 10. The results of the search for the missing source and a confirmation of the exact location of the incident will be forwarded to NMED when the RSO has confirmed the information. An investigation into the cause of the damage of the source capsule and possible location of the source capsule is ongoing."
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
Agreement State
Event Number: 46855
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: LOWELL GENERAL HOSPITAL
Region: 1
City: LOWELL State: MA
County:
License #: 44-0060
Agreement: Y
Docket:
NRC Notified By: KENATH O. TRAEGDE
HQ OPS Officer: PETE SNYDER
Licensee: LOWELL GENERAL HOSPITAL
Region: 1
City: LOWELL State: MA
County:
License #: 44-0060
Agreement: Y
Docket:
NRC Notified By: KENATH O. TRAEGDE
HQ OPS Officer: PETE SNYDER
Notification Date: 05/17/2011
Notification Time: 14:14 [ET]
Event Date: 02/16/2011
Event Time: 00:00 [EDT]
Last Update Date: 05/17/2011
Notification Time: 14:14 [ET]
Event Date: 02/16/2011
Event Time: 00:00 [EDT]
Last Update Date: 05/17/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MEL GRAY (R1DO)
CHRISTIAN EINBERG (FSME)
MEL GRAY (R1DO)
CHRISTIAN EINBERG (FSME)
AGREEMENT STATE REPORT - DOSE TO FETUS DURING THYROID SCAN
The following report was received from the state via fax:
"A patient having a thyroid scan was administered 4 mCi of I-131 while in a pregnant condition. The circumstances under which the dose was administered are under investigation. The dose to the developing fetus is also under investigation. The whole body dose to the fetus is estimated to be 1 rad at this time.
"The discovery date [of 4/15/11] is an estimate. The real dose of discovery will be reported during the investigation. Also, the licensee was allowed 15 working days to issue a report to [the Massachusetts Radiation Control Program]. [The Massachusetts Radiation Control Program] received that report on May 12, 2011."
The following report was received from the state via fax:
"A patient having a thyroid scan was administered 4 mCi of I-131 while in a pregnant condition. The circumstances under which the dose was administered are under investigation. The dose to the developing fetus is also under investigation. The whole body dose to the fetus is estimated to be 1 rad at this time.
"The discovery date [of 4/15/11] is an estimate. The real dose of discovery will be reported during the investigation. Also, the licensee was allowed 15 working days to issue a report to [the Massachusetts Radiation Control Program]. [The Massachusetts Radiation Control Program] received that report on May 12, 2011."