Event Notification Report for October 19, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/18/2010 - 10/19/2010
EVENT NUMBERS
4640647702463454634646347
General Information or Other
Event Number: 46406
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: LIMA REFINING COMPANY
Region: 3
City: LIMA State: OH
County:
License #: 31201020001
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: JOHN KNOKE
Licensee: LIMA REFINING COMPANY
Region: 3
City: LIMA State: OH
County:
License #: 31201020001
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: JOHN KNOKE
Notification Date: 11/09/2010
Notification Time: 12:12 [ET]
Event Date: 10/19/2010
Event Time: 00:00 [EST]
Last Update Date: 11/09/2010
Notification Time: 12:12 [ET]
Event Date: 10/19/2010
Event Time: 00:00 [EST]
Last Update Date: 11/09/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
ANN MARIE STONE (R3DO)
GLENDA VILLAMAR (FSME)
ANN MARIE STONE (R3DO)
GLENDA VILLAMAR (FSME)
AGREEMENT STATE REPORT - FIXED GAUGE SHUTTER NOT OPERATING PROPERLY
The following information was reported via email by the State of Ohio:
"A licensed service provider (AHP) visited the licensee's site on 10/19/10 and completed an inspection of six fixed level gauges with the following results:
a) Four device shutters functioned as designed and were secured closed for maintenance activities.
b) One shutter device was inoperable due to the fact that the shutter positioning pin was rusted and could not be removed. Through lubricating and gentle mechanical persuasion the pin was removed and the shutter cycled properly.
c) The last device had a shutter operating handle that turned freely but did not rotate the shield block into the beam path. This device obviously did not function as designed and meets the reporting criteria. Through the use of more aggressive measures that did not include disassembly the shutter was eventually closed.
"These activities were closely monitored by the service provider's representative and at no time were licensee personnel exposed to the direct beam. The shutter on this device is now seized in the closed position. Upon identification of the shutter hanging up the service provider contacted the Bureau by telephone and e-mail.
"All six devices remain bolted in their fixed positions. The licensee intends to have the service provider unbolt and transfer all six devices to a secure storage location on licensee property where they will be properly packaged for transfer for disposal."
The 2 sealed sources are both 50 milliCuries of Cs-137. The manufacturer of the fixed gauge is General Nucleonics, Model # 13250, serial # 114 & 116.
Ohio Item Number: OH100027
The following information was reported via email by the State of Ohio:
"A licensed service provider (AHP) visited the licensee's site on 10/19/10 and completed an inspection of six fixed level gauges with the following results:
a) Four device shutters functioned as designed and were secured closed for maintenance activities.
b) One shutter device was inoperable due to the fact that the shutter positioning pin was rusted and could not be removed. Through lubricating and gentle mechanical persuasion the pin was removed and the shutter cycled properly.
c) The last device had a shutter operating handle that turned freely but did not rotate the shield block into the beam path. This device obviously did not function as designed and meets the reporting criteria. Through the use of more aggressive measures that did not include disassembly the shutter was eventually closed.
"These activities were closely monitored by the service provider's representative and at no time were licensee personnel exposed to the direct beam. The shutter on this device is now seized in the closed position. Upon identification of the shutter hanging up the service provider contacted the Bureau by telephone and e-mail.
"All six devices remain bolted in their fixed positions. The licensee intends to have the service provider unbolt and transfer all six devices to a secure storage location on licensee property where they will be properly packaged for transfer for disposal."
The 2 sealed sources are both 50 milliCuries of Cs-137. The manufacturer of the fixed gauge is General Nucleonics, Model # 13250, serial # 114 & 116.
Ohio Item Number: OH100027
Agreement State
Event Number: 47702
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: EASTMAN CHEMICAL COMPANY
Region: 1
City: KINGSPORT State: TN
County:
License #: R-82007-H15
Agreement: Y
Docket:
NRC Notified By: DEBRA SHULTS
HQ OPS Officer: CHARLES TEAL
Licensee: EASTMAN CHEMICAL COMPANY
Region: 1
City: KINGSPORT State: TN
County:
License #: R-82007-H15
Agreement: Y
Docket:
NRC Notified By: DEBRA SHULTS
HQ OPS Officer: CHARLES TEAL
Notification Date: 02/28/2012
Notification Time: 13:09 [ET]
Event Date: 10/19/2010
Event Time: 16:30 [EST]
Last Update Date: 02/28/2012
Notification Time: 13:09 [ET]
Event Date: 10/19/2010
Event Time: 16:30 [EST]
Last Update Date: 02/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MARC FERDAS (R1DO)
ANGELA MCINTOSH (FSME)
MARC FERDAS (R1DO)
ANGELA MCINTOSH (FSME)
AGREEMENT STATE REPORT - SOURCE CARRIER ON OHMART GAUGE FAILED TO RETRACT
The following was received from the State of Tennessee via facsimile:
"On 10/19/10, it was discovered that the source carrier on Ohmart gauge, Model SHLM-C, could not retract from the well pipe back into the source holder. An Ohmart technician attempted to repair the gauge without success. A visual inspection confirmed that the process materials had leaked into the well pipe around the source carrier preventing retraction of the source. A remediation team was called to retrieve the source carrier. The gauge contained Cesium-137, two sealed sources of 63 milliCuries each."
Event Report ID No.: TN-10-143
The following was received from the State of Tennessee via facsimile:
"On 10/19/10, it was discovered that the source carrier on Ohmart gauge, Model SHLM-C, could not retract from the well pipe back into the source holder. An Ohmart technician attempted to repair the gauge without success. A visual inspection confirmed that the process materials had leaked into the well pipe around the source carrier preventing retraction of the source. A remediation team was called to retrieve the source carrier. The gauge contained Cesium-137, two sealed sources of 63 milliCuries each."
Event Report ID No.: TN-10-143
Power Reactor
Event Number: 46345
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: GEORGE ROBERTSON
HQ OPS Officer: JOHN SHOEMAKER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: GEORGE ROBERTSON
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/19/2010
Notification Time: 17:45 [ET]
Event Date: 10/19/2010
Event Time: 08:42 [EDT]
Last Update Date: 10/19/2010
Notification Time: 17:45 [ET]
Event Date: 10/19/2010
Event Time: 08:42 [EDT]
Last Update Date: 10/19/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
RANDY MUSSER (R2DO)
RANDY MUSSER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY - POSITIVE TEST FOR ALCOHOL OF CONTRACT SUPERVISOR.
"A non-licensed contract employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details."
The NRC Resident Inspector has been notified.
"A non-licensed contract employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details."
The NRC Resident Inspector has been notified.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 46346
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [] [] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: MIKE WONG
HQ OPS Officer: JOE O'HARA
Region: 4 State: CA
Unit: [] [] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: MIKE WONG
HQ OPS Officer: JOE O'HARA
Notification Date: 10/19/2010
Notification Time: 20:09 [ET]
Event Date: 10/19/2010
Event Time: 15:15 [PDT]
Last Update Date: 10/21/2010
Notification Time: 20:09 [ET]
Event Date: 10/19/2010
Event Time: 15:15 [PDT]
Last Update Date: 10/21/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
VIVIAN CAMPBELL (R4DO)
VIVIAN CAMPBELL (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
VALID SPECIFIED SYSTEM ACTUATION
"On October 19, 2010, at about 1515 PDT, SONGS Unit 3 RPS channels 'B' and 'D' were tested for maintenance. During this testing, both channels were powered off, which brought in LPD/DNBR [local power density/departure from nucleate boiling] trips on both channels. There are no applicable Technical Specifications required for these RPS channels in Mode 5.
"Southern California Edison(SCE) is reporting this occurrence as a valid actuation of RPS in accordance with 10 CFR 50.72(b)(3)(iv)(a).
"SCE has taken actions to restore both channels 'B' and 'D' of RPS and cleared the RPS trip signal. At the time of this occurrence, Unit 2 was at approximately 100% power and Unit 3 was in a Steam Generator Replacement Outage, Mode 5, shutdown and cooldown with the RCS open, proceeding to Mode 6."
The NRC Resident Inspector has been notified.
* * * RETRACTION FROM DENNIS MORRIS TO PETE SNYDER AT 0045 EDT ON 10/21/10 * * *
"On October 19, 2010, SCE reported (Event No. 46346) a valid actuation of the Reactor Protection System (RPS) in accordance with 10 CFR 50.72(b)(3)(iv)(A). Upon further review, SCE determined the actuation was invalid and is retracting the notification.
"Maintenance and surveillance testing was being conducted by Computer Technicians on the Core Protection Calculator [CPC] Channels 'A' and 'D', respectively, following station procedures. De-energizing the CPC channels was expected to bring in an RPS trip signal. The process to disable the control room RPS alarms had not as yet, been completed by the Instrument and Controls group when the CPCs were de-energized by procedure, actuating the RPS logic and causing the control room alarms.
"The actuation is considered invalid, as the equipment that would have been actuated by the trip safety function was previously de-energized and removed from service for the refueling outage. The Unit 3 reactor was in Mode 5, with the reactor trip breakers open, and control rods inserted. Unit 2 reactor remains at 100% power."
The licensee notified the NRC Resident Inspector. Notified R4DO (V.Campbell).
"On October 19, 2010, at about 1515 PDT, SONGS Unit 3 RPS channels 'B' and 'D' were tested for maintenance. During this testing, both channels were powered off, which brought in LPD/DNBR [local power density/departure from nucleate boiling] trips on both channels. There are no applicable Technical Specifications required for these RPS channels in Mode 5.
"Southern California Edison(SCE) is reporting this occurrence as a valid actuation of RPS in accordance with 10 CFR 50.72(b)(3)(iv)(a).
"SCE has taken actions to restore both channels 'B' and 'D' of RPS and cleared the RPS trip signal. At the time of this occurrence, Unit 2 was at approximately 100% power and Unit 3 was in a Steam Generator Replacement Outage, Mode 5, shutdown and cooldown with the RCS open, proceeding to Mode 6."
The NRC Resident Inspector has been notified.
* * * RETRACTION FROM DENNIS MORRIS TO PETE SNYDER AT 0045 EDT ON 10/21/10 * * *
"On October 19, 2010, SCE reported (Event No. 46346) a valid actuation of the Reactor Protection System (RPS) in accordance with 10 CFR 50.72(b)(3)(iv)(A). Upon further review, SCE determined the actuation was invalid and is retracting the notification.
"Maintenance and surveillance testing was being conducted by Computer Technicians on the Core Protection Calculator [CPC] Channels 'A' and 'D', respectively, following station procedures. De-energizing the CPC channels was expected to bring in an RPS trip signal. The process to disable the control room RPS alarms had not as yet, been completed by the Instrument and Controls group when the CPCs were de-energized by procedure, actuating the RPS logic and causing the control room alarms.
"The actuation is considered invalid, as the equipment that would have been actuated by the trip safety function was previously de-energized and removed from service for the refueling outage. The Unit 3 reactor was in Mode 5, with the reactor trip breakers open, and control rods inserted. Unit 2 reactor remains at 100% power."
The licensee notified the NRC Resident Inspector. Notified R4DO (V.Campbell).
Power Reactor
Event Number: 46347
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: RYAN HAMILTON
HQ OPS Officer: JOE O'HARA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: RYAN HAMILTON
HQ OPS Officer: JOE O'HARA
Notification Date: 10/19/2010
Notification Time: 21:14 [ET]
Event Date: 10/19/2010
Event Time: 21:08 [EDT]
Last Update Date: 10/20/2010
Notification Time: 21:14 [ET]
Event Date: 10/19/2010
Event Time: 21:08 [EDT]
Last Update Date: 10/20/2010
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):
MARIE MILLER (R1DO)
MARIE MILLER (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 |
FAILURE OF PLANT PROCESS COMPUTER DISPLAYS AND SPDS TO UPDATE
"This 8-hour non-emergency report is being made based upon requirements of 10 CFR 50.72(b)(3)(xiii) which states that the licensee shall notify the NRC as soon as practical and in all cases within eight hours of the occurrence of: 'Any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system).'
"At 1308 EDT on Tuesday, October 19, 2010, the Nine Mile Point Unit 1 Control Room received the annunciator for Process Computer Trouble. At the same time, all Process Computer displays stopped updating, including the Safety Parameter Display System (SPDS).
"All Control Room panel indicators and annunciators continue to respond properly providing operators with non-computer based emergency assessment capability. An additional Plant Operator has reported to shift in accordance with Technical Specification 6.2.2.a for minimum shift complement with the process computer out of service.
"An update to this notification will be made after repairs are completed and the SPDS is returned to service."
The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 0802 EDT ON 10/20/10 FROM JOHN DRISCOLL TO DONG PARK * * *
"On Wednesday, October 20, 2010, repairs were completed and at 0439 EDT, the Plant Process Computer (PPC) was successfully restarted. Upon restart, SPDS was verified operable."
The licensee informed the NRC Resident Inspector. Notified R1DO (Miller).
"This 8-hour non-emergency report is being made based upon requirements of 10 CFR 50.72(b)(3)(xiii) which states that the licensee shall notify the NRC as soon as practical and in all cases within eight hours of the occurrence of: 'Any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system).'
"At 1308 EDT on Tuesday, October 19, 2010, the Nine Mile Point Unit 1 Control Room received the annunciator for Process Computer Trouble. At the same time, all Process Computer displays stopped updating, including the Safety Parameter Display System (SPDS).
"All Control Room panel indicators and annunciators continue to respond properly providing operators with non-computer based emergency assessment capability. An additional Plant Operator has reported to shift in accordance with Technical Specification 6.2.2.a for minimum shift complement with the process computer out of service.
"An update to this notification will be made after repairs are completed and the SPDS is returned to service."
The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 0802 EDT ON 10/20/10 FROM JOHN DRISCOLL TO DONG PARK * * *
"On Wednesday, October 20, 2010, repairs were completed and at 0439 EDT, the Plant Process Computer (PPC) was successfully restarted. Upon restart, SPDS was verified operable."
The licensee informed the NRC Resident Inspector. Notified R1DO (Miller).