Event Notification Report for August 02, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/01/2016 - 08/02/2016
EVENT NUMBERS
5215152145521465214852149
Agreement State
Event Number: 52151
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: UKNOWKN
Region: 3
City: CLEVELAND State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: BETHANY CECERE
Licensee: UKNOWKN
Region: 3
City: CLEVELAND State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: BETHANY CECERE
Notification Date: 08/04/2016
Notification Time: 14:28 [ET]
Event Date: 08/02/2016
Event Time: 09:40 [EDT]
Last Update Date: 08/04/2016
Notification Time: 14:28 [ET]
Event Date: 08/02/2016
Event Time: 09:40 [EDT]
Last Update Date: 08/04/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
CNSC (CANADA) (EMAI)
RICHARD SKOKOWSKI (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)
CNSC (CANADA) (EMAI)
AGREEMENT STATE REPORT - FIXED GAUGE WITH SEALED RADIOACTIVE SOURCE RECOVERED AT A SCRAPYARD
The following information was received from the Ohio Department of Health (ODH) via email:
"A load of scrap metal set off the radiation detectors at a scrapyard in Cleveland, Ohio at approximately 0940 EDT on 8/2/16. A Department of Transportation exemption was issued and the scrap was returned to the supplier, Cleveland Wire, also located in Cleveland. The load was sorted by Cleveland Wire staff and a 'C-arm' fixed gauge was discovered.
"ODH investigators arrived at the Cleveland Wire site on 8/3/16 and surveyed the gauge. Highest readings were determined to be 4 mR/hour on contact at the point where the source would be located inside the device, indicating that a source was present and the shutter was closed. Smear wipes taken indicated no removable contamination present. Further investigation showed that a tag was still affixed to the device, indicating the isotope (Sr-90), activity (70 mCi) and assay date (June, 1976). The radiation readings and identifying information are in keeping with what would be expected upon review of the Sealed Source & Device (SS&D) registration for the device. The device is currently in secure storage on site at Cleveland Wire, awaiting plans for transfer or disposal.
"The ODH investigators at Cleveland Wire also learned that the device had been received from an industrial equipment reseller, HDR Industrial Surplus, located in Euclid, Ohio. Another ODH inspector was dispatched to that location on 8/3/16 to survey the facility, check for additional items that might contain radioactive materials, and to determine if the original owner/consignor could be located. No radiation levels were detected above background at the Euclid location, and no other items containing radioactive materials appeared to be present.
"Research and investigation is ongoing to attempt to determine the owner of the device.
"Source/Radioactive Material: SEALED SOURCE GAUGE
Manufacturer: AMERSHAM
Model Number: S-18
Serial Number: S-1078-7
Radionuclide: SR-90, 0.070 Ci
IAEA Category: 5
"Device/Associated Equipment:
Device Name: FIXED GAUGE
Manufacturer: SANGAMO-WESTON-SCHLUMBERGER
Model Number: M-3."
Ohio Item Number: OH160008"
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 from the Ohio Department of Health (ODH) via email:
"A load of scrap metal set off the radiation detectors at a scrapyard in Cleveland, Ohio at approximately 0940 EDT on 8/2/16. A Department of Transportation exemption was issued and the scrap was returned to the supplier, Cleveland Wire, also located in Cleveland. The load was sorted by Cleveland Wire staff and a 'C-arm' fixed gauge was discovered.
"ODH investigators arrived at the Cleveland Wire site on 8/3/16 and surveyed the gauge. Highest readings were determined to be 4 mR/hour on contact at the point where the source would be located inside the device, indicating that a source was present and the shutter was closed. Smear wipes taken indicated no removable contamination present. Further investigation showed that a tag was still affixed to the device, indicating the isotope (Sr-90), activity (70 mCi) and assay date (June, 1976). The radiation readings and identifying information are in keeping with what would be expected upon review of the Sealed Source & Device (SS&D) registration for the device. The device is currently in secure storage on site at Cleveland Wire, awaiting plans for transfer or disposal.
"The ODH investigators at Cleveland Wire also learned that the device had been received from an industrial equipment reseller, HDR Industrial Surplus, located in Euclid, Ohio. Another ODH inspector was dispatched to that location on 8/3/16 to survey the facility, check for additional items that might contain radioactive materials, and to determine if the original owner/consignor could be located. No radiation levels were detected above background at the Euclid location, and no other items containing radioactive materials appeared to be present.
"Research and investigation is ongoing to attempt to determine the owner of the device.
"Source/Radioactive Material: SEALED SOURCE GAUGE
Manufacturer: AMERSHAM
Model Number: S-18
Serial Number: S-1078-7
Radionuclide: SR-90, 0.070 Ci
IAEA Category: 5
"Device/Associated Equipment:
Device Name: FIXED GAUGE
Manufacturer: SANGAMO-WESTON-SCHLUMBERGER
Model Number: M-3."
Ohio Item Number: OH160008"
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
Power Reactor
Event Number: 52145
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TIM JOHNSON
HQ OPS Officer: DANIEL MILLS
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TIM JOHNSON
HQ OPS Officer: DANIEL MILLS
Notification Date: 08/02/2016
Notification Time: 14:22 [ET]
Event Date: 08/02/2016
Event Time: 06:30 [EDT]
Last Update Date: 08/02/2016
Notification Time: 14:22 [ET]
Event Date: 08/02/2016
Event Time: 06:30 [EDT]
Last Update Date: 08/02/2016
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):
LADONNA SUGGS (R2DO)
LADONNA SUGGS (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SUPPORT CENTER VENTILATION OUT-OF-SERVICE
"This is a non-emergency eight-hour notification for a loss of Emergency Assessment Capability.
"This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) as the discovered condition affects the functionality of an emergency response facility.
"A condition impacting functionality due to a loss of cooling of the TSC (Technical Support Center) Ventilation system was discovered on 8/2/16 at 0630 EDT. Repairs are complete at 1030 EDT on 08/02/16.
"If an emergency would have been declared requiring TSC activation during this period, the TSC would have been staffed and activated using existing emergency planning procedures unless the TSC had become uninhabitable. If relocation of the TSC had been necessary, the Emergency Coordinator would have relocated the TSC staff to an alternate location in accordance with applicable emergency plan implementing procedures.
"The Emergency Response Organization team was notified of the condition and the possible need to relocate during an emergency. This condition does not affect the health and safety of the public or station employees. The NRC Resident Inspector has been notified."
"This is a non-emergency eight-hour notification for a loss of Emergency Assessment Capability.
"This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) as the discovered condition affects the functionality of an emergency response facility.
"A condition impacting functionality due to a loss of cooling of the TSC (Technical Support Center) Ventilation system was discovered on 8/2/16 at 0630 EDT. Repairs are complete at 1030 EDT on 08/02/16.
"If an emergency would have been declared requiring TSC activation during this period, the TSC would have been staffed and activated using existing emergency planning procedures unless the TSC had become uninhabitable. If relocation of the TSC had been necessary, the Emergency Coordinator would have relocated the TSC staff to an alternate location in accordance with applicable emergency plan implementing procedures.
"The Emergency Response Organization team was notified of the condition and the possible need to relocate during an emergency. This condition does not affect the health and safety of the public or station employees. The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 52146
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: DEREK ETUE
HQ OPS Officer: DANIEL MILLS
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: DEREK ETUE
HQ OPS Officer: DANIEL MILLS
Notification Date: 08/02/2016
Notification Time: 14:42 [ET]
Event Date: 08/02/2016
Event Time: 10:15 [EDT]
Last Update Date: 08/02/2016
Notification Time: 14:42 [ET]
Event Date: 08/02/2016
Event Time: 10:15 [EDT]
Last Update Date: 08/02/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
RICHARD SKOKOWSKI (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
SECONDARY CONTAINMENT TECHNICAL SPECIFICATION NOT MET
"On August 2, 2016 at 1015 EDT, while restoring the east train of Reactor Building HVAC (RBHVAC) after a surveillance test on Division 2 Standby Gas Treatment System (SGTS), the Technical Specification (TS) for the secondary containment pressure boundary was not met for a duration time of approximately 1 second. The maximum secondary containment pressure observed during that time was approximately 0.120 inches of vacuum water gauge.
"Secondary containment pressure was returned to within the TS operability limit by RBHVAC and SGTS already in operation. There were no radiological releases associated with this event.
"The cause of the event is under investigation.
"The TS requirement is to maintain secondary containment vacuum greater than or equal to 0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1) for secondary containment operability. Declaring secondary containment inoperable is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material.
"The licensee has notified the NRC Resident lnspector."
"On August 2, 2016 at 1015 EDT, while restoring the east train of Reactor Building HVAC (RBHVAC) after a surveillance test on Division 2 Standby Gas Treatment System (SGTS), the Technical Specification (TS) for the secondary containment pressure boundary was not met for a duration time of approximately 1 second. The maximum secondary containment pressure observed during that time was approximately 0.120 inches of vacuum water gauge.
"Secondary containment pressure was returned to within the TS operability limit by RBHVAC and SGTS already in operation. There were no radiological releases associated with this event.
"The cause of the event is under investigation.
"The TS requirement is to maintain secondary containment vacuum greater than or equal to 0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1) for secondary containment operability. Declaring secondary containment inoperable is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material.
"The licensee has notified the NRC Resident lnspector."
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 52148
Facility: BYRON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PAT COMERFORD
HQ OPS Officer: DANIEL MILLS
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PAT COMERFORD
HQ OPS Officer: DANIEL MILLS
Notification Date: 08/02/2016
Notification Time: 17:55 [ET]
Event Date: 08/02/2016
Event Time: 09:34 [CDT]
Last Update Date: 08/29/2016
Notification Time: 17:55 [ET]
Event Date: 08/02/2016
Event Time: 09:34 [CDT]
Last Update Date: 08/29/2016
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):
RICHARD SKOKOWSKI (R3DO)
RICHARD SKOKOWSKI (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 |
WATERTIGHT DOOR DISCOVERED OPEN AND UNATTENDED
"On August 2, 2016 at 0934 CDT, Byron Operators entered and exited 1BOL 8.1 Conditions B and F for the 1A and 1B Diesel Generators due to 0DSSD192 (1B DOST Watertight Door) being discovered open and unattended. 0DSSD192 was closed within 5 minutes of discovery.
"0DSSD192 protects the DOST [diesel oil storage tank] transfer pumps from the effects of a postulated failure of a Circulating Water expansion joint at the condenser waterboxes in the Turbine Building. An open watertight door associated with one DOST has the potential of making both Diesel Generators inoperable.
"This event is reportable per 10 CFR 50.72(b)(3)(v)(D) for any event or condition that could have prevented fulfillment of a safety function of structures or systems that are needed to mitigate the consequences of an accident.
"The licensee has notified the NRC Resident Inspector."
* * * RETRACTION FROM SHANE HARVEY TO DONALD NORWOOD AT 1627 EDT ON 8/29/2016 * * *
"The purpose of this report is to retract a previous report made on August 2, 2016 at 1755 EDT (EN 52148). Notification of the event to the NRC was initially made for a condition where the station determined that an open watertight door associated with one DOST [Diesel Oil Storage Tank] had the potential to make both Diesel Generators inoperable, and the condition was reported under 10 CFR 50.72(b)(3)(v)(D) for any event or condition that could have prevented fulfillment of a safety function of structures or systems that are needed to mitigate the consequences of an accident.
"Upon further investigation, Byron Station has concluded that the 1A Diesel Generator was never inoperable, and therefore, no loss of safety function occurred. Based on this, the prior ENS notification is being retracted.
"The NRC Senior Resident Inspector has been notified."
Notified R3DO (Dickson).
"On August 2, 2016 at 0934 CDT, Byron Operators entered and exited 1BOL 8.1 Conditions B and F for the 1A and 1B Diesel Generators due to 0DSSD192 (1B DOST Watertight Door) being discovered open and unattended. 0DSSD192 was closed within 5 minutes of discovery.
"0DSSD192 protects the DOST [diesel oil storage tank] transfer pumps from the effects of a postulated failure of a Circulating Water expansion joint at the condenser waterboxes in the Turbine Building. An open watertight door associated with one DOST has the potential of making both Diesel Generators inoperable.
"This event is reportable per 10 CFR 50.72(b)(3)(v)(D) for any event or condition that could have prevented fulfillment of a safety function of structures or systems that are needed to mitigate the consequences of an accident.
"The licensee has notified the NRC Resident Inspector."
* * * RETRACTION FROM SHANE HARVEY TO DONALD NORWOOD AT 1627 EDT ON 8/29/2016 * * *
"The purpose of this report is to retract a previous report made on August 2, 2016 at 1755 EDT (EN 52148). Notification of the event to the NRC was initially made for a condition where the station determined that an open watertight door associated with one DOST [Diesel Oil Storage Tank] had the potential to make both Diesel Generators inoperable, and the condition was reported under 10 CFR 50.72(b)(3)(v)(D) for any event or condition that could have prevented fulfillment of a safety function of structures or systems that are needed to mitigate the consequences of an accident.
"Upon further investigation, Byron Station has concluded that the 1A Diesel Generator was never inoperable, and therefore, no loss of safety function occurred. Based on this, the prior ENS notification is being retracted.
"The NRC Senior Resident Inspector has been notified."
Notified R3DO (Dickson).
Power Reactor
Event Number: 52149
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: GREG MILLER
HQ OPS Officer: DANIEL MILLS
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: GREG MILLER
HQ OPS Officer: DANIEL MILLS
Notification Date: 08/02/2016
Notification Time: 20:33 [ET]
Event Date: 08/02/2016
Event Time: 17:10 [EDT]
Last Update Date: 08/02/2016
Notification Time: 20:33 [ET]
Event Date: 08/02/2016
Event Time: 17:10 [EDT]
Last Update Date: 08/02/2016
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):
RICHARD SKOKOWSKI (R3DO)
RICHARD SKOKOWSKI (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO ONSITE SEWAGE SPILL
"At 1612 EDT on 08/02/16, Fermi 2 discovered a sanitary sewer system leak from underground lines beneath the parking lot near Warehouse B. Some of the sewage has entered the storm drain system. The sewage leak was stopped at approximately 1730 EDT. The duration and quantity of the spill is unknown. A local sanitary contractor is currently responding to the site to clean the affected areas.
"Reports to the Michigan Department of Environmental Quality (MDEQ), the local health department [Monroe County], and the local news media are in progress. Since these reports are in the process of being made, this is considered a News Release or Notification to Other Government Agencies, therefore this event is reportable under 10 CFR 50.72(b)(2)(xi).
"The NRC Resident Inspector has been notified."
"At 1612 EDT on 08/02/16, Fermi 2 discovered a sanitary sewer system leak from underground lines beneath the parking lot near Warehouse B. Some of the sewage has entered the storm drain system. The sewage leak was stopped at approximately 1730 EDT. The duration and quantity of the spill is unknown. A local sanitary contractor is currently responding to the site to clean the affected areas.
"Reports to the Michigan Department of Environmental Quality (MDEQ), the local health department [Monroe County], and the local news media are in progress. Since these reports are in the process of being made, this is considered a News Release or Notification to Other Government Agencies, therefore this event is reportable under 10 CFR 50.72(b)(2)(xi).
"The NRC Resident Inspector has been notified."