Event Notification Report for March 13, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/12/2009 - 03/13/2009
Hospital
Event Number: 44916
Rep Org: BILLINGS CLINIC
Licensee: BILLINGS CLINIC
Region: 4
City: BILLINGS State: MT
County:
License #: 25-01051-01
Agreement: N
Docket:
NRC Notified By: CHRISTOPHER FITZ
HQ OPS Officer: JOE O'HARA
Licensee: BILLINGS CLINIC
Region: 4
City: BILLINGS State: MT
County:
License #: 25-01051-01
Agreement: N
Docket:
NRC Notified By: CHRISTOPHER FITZ
HQ OPS Officer: JOE O'HARA
Notification Date: 03/19/2009
Notification Time: 10:49 [ET]
Event Date: 03/13/2009
Event Time: 00:00 [MDT]
Last Update Date: 03/19/2009
Notification Time: 10:49 [ET]
Event Date: 03/13/2009
Event Time: 00:00 [MDT]
Last Update Date: 03/19/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
MICHAEL HAY (R4)
ANGELA MCINTOSH (FSME)
ILTAB VIA EMAIL
MICHAEL HAY (R4)
ANGELA MCINTOSH (FSME)
ILTAB VIA EMAIL
LOST THREE VIALS OF XENON - 133
The RSO for the licensee reported the hospital inadvertently disposed of 78 millicuries of Xenon-133 through the solid waste system. The hospital believes that a housekeeper may have thrown it away as solid waste. Couriers delivered the material without the knowledge of the hospital on 3/13/09. Later that same day, the licensee believes that the housekeeper picked up the boxes that the material was located inside of and mistakenly threw them away as waste. A search of the facility was conducted without success. The licensee is not taking any action to recover the material from the dump. All trash is compacted on site into a common container. The trash has already been taken to the landfill and buried. The licensee is not taking any action to recover the material from the dump. The licensee has taken corrective actions with the couriers and designated a new storage area for the material in a restricted area. Housekeeping will no longer be handling the boxes. This licensee does not consider the loss be a threat to the health and safety of the community.
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.
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
The RSO for the licensee reported the hospital inadvertently disposed of 78 millicuries of Xenon-133 through the solid waste system. The hospital believes that a housekeeper may have thrown it away as solid waste. Couriers delivered the material without the knowledge of the hospital on 3/13/09. Later that same day, the licensee believes that the housekeeper picked up the boxes that the material was located inside of and mistakenly threw them away as waste. A search of the facility was conducted without success. The licensee is not taking any action to recover the material from the dump. All trash is compacted on site into a common container. The trash has already been taken to the landfill and buried. The licensee is not taking any action to recover the material from the dump. The licensee has taken corrective actions with the couriers and designated a new storage area for the material in a restricted area. Housekeeping will no longer be handling the boxes. This licensee does not consider the loss be a threat to the health and safety of the community.
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.
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: 44905
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: TOM MORSE
HQ OPS Officer: VINCE KLCO
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: TOM MORSE
HQ OPS Officer: VINCE KLCO
Notification Date: 03/13/2009
Notification Time: 00:42 [ET]
Event Date: 03/13/2009
Event Time: 00:25 [EDT]
Last Update Date: 03/17/2009
Notification Time: 00:42 [ET]
Event Date: 03/13/2009
Event Time: 00:25 [EDT]
Last Update Date: 03/17/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JULIO LARA (R3)
JULIO LARA (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
PARTIAL LOSS OF PLANT COMPUTER FOR SCHEDULED MAINTENANCE TAKING ERDS OOS
"The Perry Nuclear Power Plant has taken a portion of the Plant Computer out of service for scheduled maintenance. This has resulted in a portion of ERDS being out of service. From 0025 hours EDT on March 13, 2009 for approximately 36 hours, personnel will be performing maintenance activities which result in a partial loss of the Plant Computer. During this planned maintenance, portions of the Safety Parameter Display System (SPDS) and the automatic mode calculation of the Computer Aided Dose Assessment Program (CADAP) will be unavailable.
"In the event of an emergency, plant parameter data will be orally transmitted to the facilities through the Status Board Ring Down circuit with back-up by the Private Branch Exchange, Off Premise Exchange, and various redundant intra-facility circuits throughout the emergency facilities. The dose assessment function will be maintained during the out of service time period by manual input of data into CADAP and, if required, by manual calculation. The ability to open and maintain an 'open line' using the Emergency Notification System will not be affected and will be the primary means of transferring plant data to the NRC as a contingency until the ERDS can be returned to service during the period of unavailability.
"This event is being reported in accordance with 10CFR50.72(b)(3)(xiii), as a condition that results in a major loss of offsite communication capability. A follow-up notification will be made when the maintenance activities are completed and the equipment is restored."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 1132 ON 3/14/2009 FROM TONY JARDINE TO MARK ABRAMOVITZ * * *
The plant has extended the expected plant computer outage time by 60 hours (ending 3/16/2009 at 2400).
Notified the R3DO (Lara).
* * * UPDATE AT 1907 EDT ON 3/16/2009 FROM TOM STEC TO BILL HUFFMAN * * *
The licensee has extended the expected outage time for the plant computer maintenance by an additional 24 hours. Repairs are now expected to be completed by 2400 EDT on 3/17/09.
The licensee will notify the NRC Resident Inspector. R3DO(Ring) notified.
* * * UPDATE AT 1723 EDT ON 3/17/2009 FROM ANTHONY JARDINE TO BILL HUFFMAN * * *
The licensee states that that the plant computer and all associated functions (SPDS, CADAP, and ERDS) were returned to service at 1313 EDT on 3/17/09. The licensee has notified the NRC Resident Inspector.
R3DO(Ring) notified.
"The Perry Nuclear Power Plant has taken a portion of the Plant Computer out of service for scheduled maintenance. This has resulted in a portion of ERDS being out of service. From 0025 hours EDT on March 13, 2009 for approximately 36 hours, personnel will be performing maintenance activities which result in a partial loss of the Plant Computer. During this planned maintenance, portions of the Safety Parameter Display System (SPDS) and the automatic mode calculation of the Computer Aided Dose Assessment Program (CADAP) will be unavailable.
"In the event of an emergency, plant parameter data will be orally transmitted to the facilities through the Status Board Ring Down circuit with back-up by the Private Branch Exchange, Off Premise Exchange, and various redundant intra-facility circuits throughout the emergency facilities. The dose assessment function will be maintained during the out of service time period by manual input of data into CADAP and, if required, by manual calculation. The ability to open and maintain an 'open line' using the Emergency Notification System will not be affected and will be the primary means of transferring plant data to the NRC as a contingency until the ERDS can be returned to service during the period of unavailability.
"This event is being reported in accordance with 10CFR50.72(b)(3)(xiii), as a condition that results in a major loss of offsite communication capability. A follow-up notification will be made when the maintenance activities are completed and the equipment is restored."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 1132 ON 3/14/2009 FROM TONY JARDINE TO MARK ABRAMOVITZ * * *
The plant has extended the expected plant computer outage time by 60 hours (ending 3/16/2009 at 2400).
Notified the R3DO (Lara).
* * * UPDATE AT 1907 EDT ON 3/16/2009 FROM TOM STEC TO BILL HUFFMAN * * *
The licensee has extended the expected outage time for the plant computer maintenance by an additional 24 hours. Repairs are now expected to be completed by 2400 EDT on 3/17/09.
The licensee will notify the NRC Resident Inspector. R3DO(Ring) notified.
* * * UPDATE AT 1723 EDT ON 3/17/2009 FROM ANTHONY JARDINE TO BILL HUFFMAN * * *
The licensee states that that the plant computer and all associated functions (SPDS, CADAP, and ERDS) were returned to service at 1313 EDT on 3/17/09. The licensee has notified the NRC Resident Inspector.
R3DO(Ring) notified.
Power Reactor
Event Number: 44906
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: REX KNIGHT
HQ OPS Officer: MARK ABRAMOVITZ
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: REX KNIGHT
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/14/2009
Notification Time: 02:03 [ET]
Event Date: 03/13/2009
Event Time: 21:51 [CDT]
Last Update Date: 03/14/2009
Notification Time: 02:03 [ET]
Event Date: 03/13/2009
Event Time: 21:51 [CDT]
Last Update Date: 03/14/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
THOMAS FARNHOLTZ (R4)
THOMAS FARNHOLTZ (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 84 | Power Operation | 0 | Hot Standby |
FEEDWATER REGULATING VALVE FAILURE LEADS TO MANUAL REACTOR TRIP
"At 2151 CDT on 3/13/2009 with plant power at 84% following securing of the 2P-1A Main Feedwater Pump at 1934 due to bearing degradation, Unit 2 experienced a failure of the 'B' Main Feedwater Regulating Valve 2CV-0740 which caused 2E-24B Steam Generator level to lower. At 2151, with 2E-24B Steam Generator level at approximately 25% control room staff manually tripped the reactor anticipating an automatic trip at 22% steam generator level. Emergency Feedwater Actuation System automatically actuated at 22% steam generator level and responded to restore level to the normal post-trip levels. All Control Element Assemblies (rods) Inserted on the reactor trip."
No safeties or relief valves opened after the trip. The plant is in its normal shutdown electrical line-up. Steam generator level is being maintained with emergency feedwater and decay heat is being dumped to the main condenser.
The licensee notified the State of Arkansas and the NRC Resident Inspector.
"At 2151 CDT on 3/13/2009 with plant power at 84% following securing of the 2P-1A Main Feedwater Pump at 1934 due to bearing degradation, Unit 2 experienced a failure of the 'B' Main Feedwater Regulating Valve 2CV-0740 which caused 2E-24B Steam Generator level to lower. At 2151, with 2E-24B Steam Generator level at approximately 25% control room staff manually tripped the reactor anticipating an automatic trip at 22% steam generator level. Emergency Feedwater Actuation System automatically actuated at 22% steam generator level and responded to restore level to the normal post-trip levels. All Control Element Assemblies (rods) Inserted on the reactor trip."
No safeties or relief valves opened after the trip. The plant is in its normal shutdown electrical line-up. Steam generator level is being maintained with emergency feedwater and decay heat is being dumped to the main condenser.
The licensee notified the State of Arkansas and the NRC Resident Inspector.