Event Notification Report for September 25, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/24/2014 - 09/25/2014
Agreement State
Event Number: 50544
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: O'SULLIVAN FILMS
Region: 1
City: WINCHESTER State: VA
County:
License #: 1655
Agreement: Y
Docket:
NRC Notified By: ASFAW FENTA
HQ OPS Officer: JEFF ROTTON
Licensee: O'SULLIVAN FILMS
Region: 1
City: WINCHESTER State: VA
County:
License #: 1655
Agreement: Y
Docket:
NRC Notified By: ASFAW FENTA
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/16/2014
Notification Time: 13:47 [ET]
Event Date: 09/25/2014
Event Time: 00:00 [EDT]
Last Update Date: 10/16/2014
Notification Time: 13:47 [ET]
Event Date: 09/25/2014
Event Time: 00:00 [EDT]
Last Update Date: 10/16/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
WILLIAM COOK (R1DO)
JAMES RUBENSTONE (NMSS)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)
WILLIAM COOK (R1DO)
JAMES RUBENSTONE (NMSS)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)
AGREEMENT STATE REPORT - LOST GENERAL LICENSED MATERIAL: AM-241 STATIC ELIMINATOR BARS
The following was provided by the Commonwealth of Virginia via email:
"On September 25, 2014, the Virginia Radioactive Materials Program (RMP) received a phone call from NRC Region 1 that one static eliminator bar, NRD A2003 serial number SA772 containing Am-241, Activity 19.6 mCi as of 4/16/1973 was found in Hedgesville, West Virginia and picked by the NRC inspectors. Record from NRD LLC indicated that this static eliminator bar was sold to O'Sullivan Films, which is located in Winchester, Virginia. In addition, the record from NRD LLC indicated that two other static eliminator bars, NRD A2003, Serial numbers 1229 and 1230, each containing 21 mCi of Am-241 as of 4/18/1975, were also sold to this company. Virginia RMP contacted O'Sullivan Films to investigate this case. O'Sullivan Films investigated the case and reported to RMP by the letter dated October 15, 2014 stating that O'Sullivan Films has not possessed these static eliminator bars and found no documentation that supports O'Sullivan Films having possessed, disposed of or returned these devices.
"Currently, no information is available regarding the whereabouts of these static eliminator bars."
VA Event Report ID No.: VA-14-18
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 was provided by the Commonwealth of Virginia via email:
"On September 25, 2014, the Virginia Radioactive Materials Program (RMP) received a phone call from NRC Region 1 that one static eliminator bar, NRD A2003 serial number SA772 containing Am-241, Activity 19.6 mCi as of 4/16/1973 was found in Hedgesville, West Virginia and picked by the NRC inspectors. Record from NRD LLC indicated that this static eliminator bar was sold to O'Sullivan Films, which is located in Winchester, Virginia. In addition, the record from NRD LLC indicated that two other static eliminator bars, NRD A2003, Serial numbers 1229 and 1230, each containing 21 mCi of Am-241 as of 4/18/1975, were also sold to this company. Virginia RMP contacted O'Sullivan Films to investigate this case. O'Sullivan Films investigated the case and reported to RMP by the letter dated October 15, 2014 stating that O'Sullivan Films has not possessed these static eliminator bars and found no documentation that supports O'Sullivan Films having possessed, disposed of or returned these devices.
"Currently, no information is available regarding the whereabouts of these static eliminator bars."
VA Event Report ID No.: VA-14-18
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: 50496
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KIRK DUEA
HQ OPS Officer: DANIEL MILLS
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KIRK DUEA
HQ OPS Officer: DANIEL MILLS
Notification Date: 09/26/2014
Notification Time: 02:53 [ET]
Event Date: 09/25/2014
Event Time: 22:00 [CDT]
Last Update Date: 11/20/2014
Notification Time: 02:53 [ET]
Event Date: 09/25/2014
Event Time: 22:00 [CDT]
Last Update Date: 11/20/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
NICK VALOS (R3DO)
NICK VALOS (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 69 | Power Operation | 69 | Power Operation |
CONTAINMENT ISOLATION DECLARED INOPERABLE DUE TO RELAY AGE
"At 2200 CDT on September 25, 2014, the Duty Shift Manager was notified that Agastat relays associated with Primary Containment Isolation valves on the Hydrogen-Oxygen Analyzing System are beyond the analyzed shelf life for relays that are in the normally energized state and are considered INOPERABLE. This affected both primary containment isolation valves for a containment penetration on multiple flow paths. This issue was determined to be reportable under [10 CFR] 50.72 (b)(3)(v)(C) & (D) for an event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material and mitigate the consequences of an accident.
"Additionally, the required actions involved isolating six flow paths via manual isolation valves. This action rendered the Hydrogen-Oxygen Analyzers non-functional for both trains and constitutes a loss of Emergency Preparedness and Accident Assessment Capability. This is reportable under [10 CFR] 50. 72(b)(3)(xiii).
"The Primary Containment Isolation Valves have been, and remain, in their closed position to satisfy their Primary Containment Function and protect the health and safety of the public.
"The NRC Senior Resident Inspector has been notified."
The licensee will notify the State of Minnesota.
The relays of concern were manufactured 19 years ago and have been in operation for 11 years, versus a manufacturer assumption of a 10 year operational lifespan.
* * * UPDATE FROM SCOTT CHRISTOS TO DONALD NORWOOD AT 1430 EST ON 11/20/2014 * * *
"Partial retraction for EN 50496. This is an update of Emergency Notification System (ENS) report 50496 that was submitted at 0253 EDT on Friday, September 26, 2014.
"ENS notification was made due to four relays associated with the sampling valves on the Hydrogen-Oxygen Analyzing (HOA) system that perform Primary Containment Isolation Valve (PCIV) functions. These relays were discovered installed beyond their manufacturer qualified service life, which called operability into question.
"The portions 10 CFR 50.72 (b)(3)(v)(C) & (D) are being retracted after subsequent bench testing and investigation of system operability. Based on the past operability evaluation, all four relays associated with PCIV functions on the HOA system would have performed their specific safety function of primary containment isolation, as required by the facility's technical specifications. Therefore, this event does not meet the threshold of an event or condition that would prevent fulfilment of a safety function.
"The loss of emergency preparedness and accident assessment capability previously reported under 10 CFR 50.72 (b)(3)(xiii) remains unchanged.
"The NRC Resident Inspector has been notified."
Notified R3DO (Peterson).
"At 2200 CDT on September 25, 2014, the Duty Shift Manager was notified that Agastat relays associated with Primary Containment Isolation valves on the Hydrogen-Oxygen Analyzing System are beyond the analyzed shelf life for relays that are in the normally energized state and are considered INOPERABLE. This affected both primary containment isolation valves for a containment penetration on multiple flow paths. This issue was determined to be reportable under [10 CFR] 50.72 (b)(3)(v)(C) & (D) for an event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material and mitigate the consequences of an accident.
"Additionally, the required actions involved isolating six flow paths via manual isolation valves. This action rendered the Hydrogen-Oxygen Analyzers non-functional for both trains and constitutes a loss of Emergency Preparedness and Accident Assessment Capability. This is reportable under [10 CFR] 50. 72(b)(3)(xiii).
"The Primary Containment Isolation Valves have been, and remain, in their closed position to satisfy their Primary Containment Function and protect the health and safety of the public.
"The NRC Senior Resident Inspector has been notified."
The licensee will notify the State of Minnesota.
The relays of concern were manufactured 19 years ago and have been in operation for 11 years, versus a manufacturer assumption of a 10 year operational lifespan.
* * * UPDATE FROM SCOTT CHRISTOS TO DONALD NORWOOD AT 1430 EST ON 11/20/2014 * * *
"Partial retraction for EN 50496. This is an update of Emergency Notification System (ENS) report 50496 that was submitted at 0253 EDT on Friday, September 26, 2014.
"ENS notification was made due to four relays associated with the sampling valves on the Hydrogen-Oxygen Analyzing (HOA) system that perform Primary Containment Isolation Valve (PCIV) functions. These relays were discovered installed beyond their manufacturer qualified service life, which called operability into question.
"The portions 10 CFR 50.72 (b)(3)(v)(C) & (D) are being retracted after subsequent bench testing and investigation of system operability. Based on the past operability evaluation, all four relays associated with PCIV functions on the HOA system would have performed their specific safety function of primary containment isolation, as required by the facility's technical specifications. Therefore, this event does not meet the threshold of an event or condition that would prevent fulfilment of a safety function.
"The loss of emergency preparedness and accident assessment capability previously reported under 10 CFR 50.72 (b)(3)(xiii) remains unchanged.
"The NRC Resident Inspector has been notified."
Notified R3DO (Peterson).