Event Notification Report for September 27, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/26/2013 - 09/27/2013
EVENT NUMBERS
4939449389493904941249388
Power Reactor
Event Number: 49394
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: RICHARD HONEYCUTT
HQ OPS Officer: DANIEL MILLS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: RICHARD HONEYCUTT
HQ OPS Officer: DANIEL MILLS
Notification Date: 09/30/2013
Notification Time: 12:52 [ET]
Event Date: 09/27/2013
Event Time: 21:15 [EDT]
Last Update Date: 09/30/2013
Notification Time: 12:52 [ET]
Event Date: 09/27/2013
Event Time: 21:15 [EDT]
Last Update Date: 09/30/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MARVIN SYKES (R2DO)
MARVIN SYKES (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 |
TRITIATED WATER LEAK FROM TEMPORARY PIPING ON PLANT SITE
"Harris Nuclear Plant is following the guidance in NEI 07-07 and has initiated this Event Notification as a result of our voluntary communication to state agencies in accordance with the Groundwater Protection Initiative.
"On Sept. 27, 2013, at 9:15 pm EDT, plant personnel identified a leak from a temporary transfer pipe on plant property, well within the site boundary. The pipe carries secondary plant and water treatment building waste water for chemical processing. The leak is conservatively estimated to be 240 gallons of water containing a low level of tritium (3,954 picocuries per liter) leaked into the surrounding soil. The EPA drinking water standard is 20,000 picocuries per liter. The leak was stopped and the piping replaced.
"The health and safety of the public and employees on site are not affected by this event based on the leak location and low tritium level."
The NRC Resident Inspector has been notified.
"Harris Nuclear Plant is following the guidance in NEI 07-07 and has initiated this Event Notification as a result of our voluntary communication to state agencies in accordance with the Groundwater Protection Initiative.
"On Sept. 27, 2013, at 9:15 pm EDT, plant personnel identified a leak from a temporary transfer pipe on plant property, well within the site boundary. The pipe carries secondary plant and water treatment building waste water for chemical processing. The leak is conservatively estimated to be 240 gallons of water containing a low level of tritium (3,954 picocuries per liter) leaked into the surrounding soil. The EPA drinking water standard is 20,000 picocuries per liter. The leak was stopped and the piping replaced.
"The health and safety of the public and employees on site are not affected by this event based on the leak location and low tritium level."
The NRC Resident Inspector has been notified.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 49389
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN MCILNAY
HQ OPS Officer: DONG HWA PARK
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN MCILNAY
HQ OPS Officer: DONG HWA PARK
Notification Date: 09/27/2013
Notification Time: 13:35 [ET]
Event Date: 09/27/2013
Event Time: 12:45 [EDT]
Last Update Date: 10/29/2013
Notification Time: 13:35 [ET]
Event Date: 09/27/2013
Event Time: 12:45 [EDT]
Last Update Date: 10/29/2013
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):
MARVIN SYKES (R2DO)
MARVIN SYKES (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 |
CALCULATION ERROR RESULTED IN UNANALYZED CONDITION FOR APPENDIX R EVENT
"On July 18, 2012, TVA identified that a calculation error resulted in the inability to establish Essential Raw Cooling Water (ERCW) supply to the Component Cooling System (CCS) heat exchanger within the required time to ensure cooling is available to Reactor Coolant System (RCS) seal injection water during an Appendix R event. TVA promptly established fire watches as a compensatory measure to prevent initiation of fires in the areas of concern. Subsequently, abnormal operating instructions were revised to take action to ensure that adequate time is available to establish ERCW cooling to CCS, and ensure cooling to [Reactor Coolant Pump] RCP seal injection water.
"The calculation error was identified on July 18, 2012, however, it was not recognized at the time that an unanalyzed condition existed that was reportable under 10 CFR 50.72(b)(3)(ii)(B). This report documents that the condition that existed until fire watches were established is reportable under 10 CFR 50.72(b)(3)(ii)(B).
"The NRC Resident Inspector has been notified of this condition."
* * * RETRACTION FROM BRIAN MCILNAY TO DONALD NORWOOD AT 1021 EDT ON 10/29/2013 * * *
"Watts Bar Nuclear Plant Unit 1 is retracting this 8 hour non-emergency notification made on September 27, 2013, at 1335 EDT (EN #49389). The notification on September 27, 2013, reported a calculation error which resulted in the inability to establish Essential Raw Cooling Water (ERCW) to supply the Component Cooing System (CCS) heat exchanger within the required time to ensure cooling is available to Reactor Coolant System (RCS) seal injection water during an Appendix R event.
"Subsequent analysis of actual plant data concluded that TVA could have established cooling to RCS seal injection during the subject Appendix R event, and achieved and maintained fire safe shutdown. Therefore, this event was not reportable under 10 CFR 50.72(b)(3)(ii)(B).
"The NRC Resident Inspector has been notified."
R2DO (Bartley) notified.
"On July 18, 2012, TVA identified that a calculation error resulted in the inability to establish Essential Raw Cooling Water (ERCW) supply to the Component Cooling System (CCS) heat exchanger within the required time to ensure cooling is available to Reactor Coolant System (RCS) seal injection water during an Appendix R event. TVA promptly established fire watches as a compensatory measure to prevent initiation of fires in the areas of concern. Subsequently, abnormal operating instructions were revised to take action to ensure that adequate time is available to establish ERCW cooling to CCS, and ensure cooling to [Reactor Coolant Pump] RCP seal injection water.
"The calculation error was identified on July 18, 2012, however, it was not recognized at the time that an unanalyzed condition existed that was reportable under 10 CFR 50.72(b)(3)(ii)(B). This report documents that the condition that existed until fire watches were established is reportable under 10 CFR 50.72(b)(3)(ii)(B).
"The NRC Resident Inspector has been notified of this condition."
* * * RETRACTION FROM BRIAN MCILNAY TO DONALD NORWOOD AT 1021 EDT ON 10/29/2013 * * *
"Watts Bar Nuclear Plant Unit 1 is retracting this 8 hour non-emergency notification made on September 27, 2013, at 1335 EDT (EN #49389). The notification on September 27, 2013, reported a calculation error which resulted in the inability to establish Essential Raw Cooling Water (ERCW) to supply the Component Cooing System (CCS) heat exchanger within the required time to ensure cooling is available to Reactor Coolant System (RCS) seal injection water during an Appendix R event.
"Subsequent analysis of actual plant data concluded that TVA could have established cooling to RCS seal injection during the subject Appendix R event, and achieved and maintained fire safe shutdown. Therefore, this event was not reportable under 10 CFR 50.72(b)(3)(ii)(B).
"The NRC Resident Inspector has been notified."
R2DO (Bartley) notified.
Power Reactor
Event Number: 49390
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JON LAUDENBACH
HQ OPS Officer: VINCE KLCO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JON LAUDENBACH
HQ OPS Officer: VINCE KLCO
Notification Date: 09/27/2013
Notification Time: 17:42 [ET]
Event Date: 09/27/2013
Event Time: 13:30 [CDT]
Last Update Date: 09/27/2013
Notification Time: 17:42 [ET]
Event Date: 09/27/2013
Event Time: 13:30 [CDT]
Last Update Date: 09/27/2013
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):
BILLY DICKSON (R3DO)
BILLY DICKSON (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 |
LOSS OF EMERGENCY ASSESSMENT CAPABILITY DUE TO RADIATION MONITORS OUT OF SERVICE
"On 9/27/13, Monticello Nuclear Generating Plant personnel identified that when the Service Water Radiation Monitor or the Discharge Canal Radiation Monitors are removed from service for planned maintenance activities, a loss of emergency assessment capability may occur. The adequacy of compensatory measures for when these radiation monitors are removed from service is under evaluation.
"The Service Water Radiation Monitor is taken out of service weekly for flushing. This last occurred at 0221 [CDT] on 9/26/13. The Discharge Canal Radiation Monitors are taken out of service approximately once a year for cleaning. The last time these monitors were removed from service was at 1250 [CDT] on 9/18/13.
"In accordance with 10CFR50.72(b)(3)(3)(xiii) these past occurrences are being reported as a loss of emergency assessment capability.
"The NRC Resident Inspector has been notified."
"On 9/27/13, Monticello Nuclear Generating Plant personnel identified that when the Service Water Radiation Monitor or the Discharge Canal Radiation Monitors are removed from service for planned maintenance activities, a loss of emergency assessment capability may occur. The adequacy of compensatory measures for when these radiation monitors are removed from service is under evaluation.
"The Service Water Radiation Monitor is taken out of service weekly for flushing. This last occurred at 0221 [CDT] on 9/26/13. The Discharge Canal Radiation Monitors are taken out of service approximately once a year for cleaning. The last time these monitors were removed from service was at 1250 [CDT] on 9/18/13.
"In accordance with 10CFR50.72(b)(3)(3)(xiii) these past occurrences are being reported as a loss of emergency assessment capability.
"The NRC Resident Inspector has been notified."
Agreement State
Event Number: 49412
Rep Org: OK DEQ RAD MANAGEMENT
Licensee: UNIVERSITY OF OKLAHOMA HEALTH SCIENCE CENTER
Region: 4
City: OKLAHOMA CITY State: OK
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: BILL HUFFMAN
Licensee: UNIVERSITY OF OKLAHOMA HEALTH SCIENCE CENTER
Region: 4
City: OKLAHOMA CITY State: OK
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 10/04/2013
Notification Time: 17:19 [ET]
Event Date: 09/27/2013
Event Time: 00:00 [CDT]
Last Update Date: 10/04/2013
Notification Time: 17:19 [ET]
Event Date: 09/27/2013
Event Time: 00:00 [CDT]
Last Update Date: 10/04/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
HEATHER GEPFORD (R4DO)
FSME EVENTS RESOURCE (E-MA)
HEATHER GEPFORD (R4DO)
FSME EVENTS RESOURCE (E-MA)
AGREEMENT STATE REPORT - LEAKING ELECTRON CAPTURE DETECTOR SOURCE
The following information was received from the Oklahoma Department of Environmental Quality via e-mail:
"On Sept. 27, [2013] the [Oklahoma Department of Environmental Quality] was notified by the University of Oklahoma Health Science Center that they had found an Electron Capture Detector with approximately 1 microCi of removable contamination. The unit in question is a Varian 3000 Series (P/N 02-001972-00) S/N A8075 (SSDR #CA-8253-D-80 1-B). Activity was 8 mCi [Ni-63] in Aug. 1990. The unit has been removed from service and is being stored prior to disposal."
The following information was received from the Oklahoma Department of Environmental Quality via e-mail:
"On Sept. 27, [2013] the [Oklahoma Department of Environmental Quality] was notified by the University of Oklahoma Health Science Center that they had found an Electron Capture Detector with approximately 1 microCi of removable contamination. The unit in question is a Varian 3000 Series (P/N 02-001972-00) S/N A8075 (SSDR #CA-8253-D-80 1-B). Activity was 8 mCi [Ni-63] in Aug. 1990. The unit has been removed from service and is being stored prior to disposal."
Power Reactor
Event Number: 49388
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MARK HOESCHEN
HQ OPS Officer: CHARLES TEAL
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MARK HOESCHEN
HQ OPS Officer: CHARLES TEAL
Notification Date: 09/27/2013
Notification Time: 09:33 [ET]
Event Date: 09/27/2013
Event Time: 08:20 [CDT]
Last Update Date: 09/27/2013
Notification Time: 09:33 [ET]
Event Date: 09/27/2013
Event Time: 08:20 [CDT]
Last Update Date: 09/27/2013
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):
BILLY DICKSON (R3DO)
BILLY DICKSON (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 |
TECHNICAL SUPPORT CENTER PLANNED MAINTENANCE
"On 9/27/13, Monticello Nuclear Generating Plant's Technical Support Center power supply will be isolated to perform a planned maintenance activity. The maintenance activity may require implementation of compensatory measures to maintain TSC functionality during the activity. The compensatory measures include having the Emergency Director report to the Control Room and co-locating the remaining TSC staff at the EOF should an event be declared requiring ERO activation. The ERO has previously successfully demonstrated the ability to implement these compensatory measures. The maintenance activity is scheduled to be completed with the TSC returned to full functionality by the end of the dayshift on 9/27/13. The Site Emergency Response Organization has been notified of the maintenance activity.
"The licensee has notified the NRC Resident Inspector."
* * * UPDATE ON 9/27/13 AT 1916 EDT FROM MARK IHLENFELDT TO DONG PARK * * *
"On 9/27/13, Monticello Nuclear Generating Plant's Technical Support Center power supply was isolated to perform a planned maintenance activity. The maintenance activity required implementation of compensatory measures to maintain TSC functional during the activity. Maintenance activity is completed and TSC is fully functional and returned to service. Site Emergency Response Organization has been notified. The licensee has notified the NRC Resident Inspector."
Notified R3DO (Dickson).
"On 9/27/13, Monticello Nuclear Generating Plant's Technical Support Center power supply will be isolated to perform a planned maintenance activity. The maintenance activity may require implementation of compensatory measures to maintain TSC functionality during the activity. The compensatory measures include having the Emergency Director report to the Control Room and co-locating the remaining TSC staff at the EOF should an event be declared requiring ERO activation. The ERO has previously successfully demonstrated the ability to implement these compensatory measures. The maintenance activity is scheduled to be completed with the TSC returned to full functionality by the end of the dayshift on 9/27/13. The Site Emergency Response Organization has been notified of the maintenance activity.
"The licensee has notified the NRC Resident Inspector."
* * * UPDATE ON 9/27/13 AT 1916 EDT FROM MARK IHLENFELDT TO DONG PARK * * *
"On 9/27/13, Monticello Nuclear Generating Plant's Technical Support Center power supply was isolated to perform a planned maintenance activity. The maintenance activity required implementation of compensatory measures to maintain TSC functional during the activity. Maintenance activity is completed and TSC is fully functional and returned to service. Site Emergency Response Organization has been notified. The licensee has notified the NRC Resident Inspector."
Notified R3DO (Dickson).