Event Notification Report for July 12, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/11/2007 - 07/12/2007
EVENT NUMBERS
43484434854348743488
Hospital
Event Number: 43484
Rep Org: ST LUKES REGIONAL MEDICAL CENTER
Licensee: ST LUKES REGIONAL MEDICAL CENTER
Region: 4
City: TWIN FALLS State: ID
County:
License #: 11-27312-01
Agreement: N
Docket:
NRC Notified By: JEFFERSON FAIRBANKS
HQ OPS Officer: MARK ABRAMOVITZ
Licensee: ST LUKES REGIONAL MEDICAL CENTER
Region: 4
City: TWIN FALLS State: ID
County:
License #: 11-27312-01
Agreement: N
Docket:
NRC Notified By: JEFFERSON FAIRBANKS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/12/2007
Notification Time: 14:40 [ET]
Event Date: 07/12/2007
Event Time: 00:00 [MDT]
Last Update Date: 07/12/2007
Notification Time: 14:40 [ET]
Event Date: 07/12/2007
Event Time: 00:00 [MDT]
Last Update Date: 07/12/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
VINCENT GADDY (R4)
RICH LEONARDI (R4)
JOSEPH HOLONICH (FSME)
VINCENT GADDY (R4)
RICH LEONARDI (R4)
JOSEPH HOLONICH (FSME)
MISSING Ir-192 SOURCE
A 6 Curie source was being shipped by Federal Express from the Twin Falls branch of St Luke's Regional Medical Center to Alpha-Omega in Louisiana. A cardboard box arrived in Louisiana containing what appeared to be aircraft parts.
See also Event Notification #43480
* * * UPDATE ON 7/12/07 AT 1525 FROM JEFFERSON FAIRBANKS TO MARK ABRAMOVITZ * * *
The source was found at Alpha-Omega in Louisiana. It had been at their location and misreported as lost.
Notified the R4DO (Gaddy).
A 6 Curie source was being shipped by Federal Express from the Twin Falls branch of St Luke's Regional Medical Center to Alpha-Omega in Louisiana. A cardboard box arrived in Louisiana containing what appeared to be aircraft parts.
See also Event Notification #43480
* * * UPDATE ON 7/12/07 AT 1525 FROM JEFFERSON FAIRBANKS TO MARK ABRAMOVITZ * * *
The source was found at Alpha-Omega in Louisiana. It had been at their location and misreported as lost.
Notified the R4DO (Gaddy).
General Information or Other
Event Number: 43485
Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: FULLER, MOSSBARGER, SCOTT AND MAY ENGINEERS, INC.
Region: 1
City: LEXINGTON State: KY
County:
License #: 201-142-51
Agreement: Y
Docket:
NRC Notified By: BRIAN PARSLEY
HQ OPS Officer: PETE SNYDER
Licensee: FULLER, MOSSBARGER, SCOTT AND MAY ENGINEERS, INC.
Region: 1
City: LEXINGTON State: KY
County:
License #: 201-142-51
Agreement: Y
Docket:
NRC Notified By: BRIAN PARSLEY
HQ OPS Officer: PETE SNYDER
Notification Date: 07/12/2007
Notification Time: 15:25 [ET]
Event Date: 07/12/2007
Event Time: 00:00 [CDT]
Last Update Date: 07/12/2007
Notification Time: 15:25 [ET]
Event Date: 07/12/2007
Event Time: 00:00 [CDT]
Last Update Date: 07/12/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RAYMOND LORSON (R1)
MICHELE BURGESS (FSME)
ILTAB (E-MAIL)
RAYMOND LORSON (R1)
MICHELE BURGESS (FSME)
ILTAB (E-MAIL)
STOLEN MOISTURE DENSITY GAUGE
At 9am on 7/12/07 the licensee noticed that their Troxler, Model 3440, S/N 20970, moisture density gauge was stolen. The gauge had been secured in a truck with a lock and chain inside a locked case at 3pm on 7/11/07. The licensee noticed that the lock on the case had been cut and the gauge was gone.
The licensee reported the incident to the Lexington Police Department as case identification number 07131235.
The gauge has a 0.04 curie Americium-241 source and a 0.008 curie Cesium-137 source. The sources were last leak checked in April of 2007.
The state is following up on this issue.
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.
At 9am on 7/12/07 the licensee noticed that their Troxler, Model 3440, S/N 20970, moisture density gauge was stolen. The gauge had been secured in a truck with a lock and chain inside a locked case at 3pm on 7/11/07. The licensee noticed that the lock on the case had been cut and the gauge was gone.
The licensee reported the incident to the Lexington Police Department as case identification number 07131235.
The gauge has a 0.04 curie Americium-241 source and a 0.008 curie Cesium-137 source. The sources were last leak checked in April of 2007.
The state is following up on this issue.
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: 43487
Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DEAN RAASCH
HQ OPS Officer: MARK ABRAMOVITZ
Region: 3 State: WI
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DEAN RAASCH
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/12/2007
Notification Time: 18:35 [ET]
Event Date: 07/12/2007
Event Time: 10:15 [CDT]
Last Update Date: 07/12/2007
Notification Time: 18:35 [ET]
Event Date: 07/12/2007
Event Time: 10:15 [CDT]
Last Update Date: 07/12/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
DAVID HILLS (R3)
DAVID HILLS (R3)
| 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 |
FIRE INSPECTION ANALYSIS OF PRESSURIZER PORVS AND BLOCK VALVES
"During a review of abnormal operating procedure (AOP) 10A, Safe Shutdown-Local Control, by the NRC triennial fire inspection team, it was identified that fire damage to the reactor coolant system (RCS) power-operated relief valve (PORV) and block valve circuits as a result of a fire in the cable spreading room could also result in simultaneous damage to a block valve circuit and spurious actuation of a PORV. While the actions included in abnormal operating procedure (AOP)-10A provide reasonable assurance that positive control of RCS Inventory is maintained, these steps do not ensure that simultaneous failure of the block valve circuit and spurious operation of a PORV will not result in RCS depressurization. Therefore, a postulated fire may potentially remove the ability to fully implement the Safe Shutdown Strategy. Compensatory measures in the form of twice-per-shift fire rounds in the cable spreading room have been implemented."
The licensee notified the NRC Resident Inspector.
"During a review of abnormal operating procedure (AOP) 10A, Safe Shutdown-Local Control, by the NRC triennial fire inspection team, it was identified that fire damage to the reactor coolant system (RCS) power-operated relief valve (PORV) and block valve circuits as a result of a fire in the cable spreading room could also result in simultaneous damage to a block valve circuit and spurious actuation of a PORV. While the actions included in abnormal operating procedure (AOP)-10A provide reasonable assurance that positive control of RCS Inventory is maintained, these steps do not ensure that simultaneous failure of the block valve circuit and spurious operation of a PORV will not result in RCS depressurization. Therefore, a postulated fire may potentially remove the ability to fully implement the Safe Shutdown Strategy. Compensatory measures in the form of twice-per-shift fire rounds in the cable spreading room have been implemented."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 43488
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MARK KRUSE
HQ OPS Officer: PETE SNYDER
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MARK KRUSE
HQ OPS Officer: PETE SNYDER
Notification Date: 07/12/2007
Notification Time: 19:14 [ET]
Event Date: 07/12/2007
Event Time: 16:30 [CDT]
Last Update Date: 07/12/2007
Notification Time: 19:14 [ET]
Event Date: 07/12/2007
Event Time: 16:30 [CDT]
Last Update Date: 07/12/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
DAVID HILLS (R3)
DAVID HILLS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNALLOWABLE MANUAL ACTIONS CREDITED FOR FIRE SAFE SHUTDOWN
"During performance of NFPA-805, Transition Project Task SUP-1, 'Manual Action Compliance,' it was determined manual operator actions are being credited in IX/12-A Lower 4KV Room and XII/14-A Upper 4KV Room to achieve and maintain hot safe shutdown. The manual actions are to provide temporary ventilation capability to the 4KV rooms to assume continued operability of vital switchgear. The switchgear provides power to equipment needed to achieve and maintain hot shutdown. These manual actions were specified in an Appendix R Section III.G.1/G.2 fire area; however, they do not meet the criteria for allowable manual actions specified in RIS 2006-10, 'Regulatory Expectations with Appendix R paragraph III.G.2 Operator Manual Actions.' No system actuations occurred as part of this event.
"The discovery of these manual actions is being reported as an unanalyzed condition as defined by 10 CFR 50.72(b)(3)(ii)(B) and has been entered into the site's corrective action program The alternate compensatory measure for these areas is to perform the specified manual actions. An extent of condition review will be initiated that will encompass the remainder of the safe shutdown areas. The results of the extent of condition will be documented in the site's corrective action program with compensatory measures being established as appropriate.
"The 60 day licensee event report, submitted to the Commission in accordance with 10 CFR 50.73(a)(2)(ii), will provide the results of the manual action compliance review and follow-up corrective actions. This is based on preliminary data and further investigation is ongoing."
The licensee will notify the NRC Resident Inspector.
"During performance of NFPA-805, Transition Project Task SUP-1, 'Manual Action Compliance,' it was determined manual operator actions are being credited in IX/12-A Lower 4KV Room and XII/14-A Upper 4KV Room to achieve and maintain hot safe shutdown. The manual actions are to provide temporary ventilation capability to the 4KV rooms to assume continued operability of vital switchgear. The switchgear provides power to equipment needed to achieve and maintain hot shutdown. These manual actions were specified in an Appendix R Section III.G.1/G.2 fire area; however, they do not meet the criteria for allowable manual actions specified in RIS 2006-10, 'Regulatory Expectations with Appendix R paragraph III.G.2 Operator Manual Actions.' No system actuations occurred as part of this event.
"The discovery of these manual actions is being reported as an unanalyzed condition as defined by 10 CFR 50.72(b)(3)(ii)(B) and has been entered into the site's corrective action program The alternate compensatory measure for these areas is to perform the specified manual actions. An extent of condition review will be initiated that will encompass the remainder of the safe shutdown areas. The results of the extent of condition will be documented in the site's corrective action program with compensatory measures being established as appropriate.
"The 60 day licensee event report, submitted to the Commission in accordance with 10 CFR 50.73(a)(2)(ii), will provide the results of the manual action compliance review and follow-up corrective actions. This is based on preliminary data and further investigation is ongoing."
The licensee will notify the NRC Resident Inspector.