Event Notification Report for September 15, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/14/2014 - 09/15/2014
Power Reactor
Event Number: 50457
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: JOHN SHOEMAKER
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: PAGE KEMP
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 09/15/2014
Notification Time: 14:54 [ET]
Event Date: 09/15/2014
Event Time: 09:00 [EDT]
Last Update Date: 09/30/2014
Notification Time: 14:54 [ET]
Event Date: 09/15/2014
Event Time: 09:00 [EDT]
Last Update Date: 09/30/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION 74.11(a) - LOST/STOLEN SNM 20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION 74.11(a) - LOST/STOLEN SNM 20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
SCOTT SHAEFFER (R2DO)
SCOTT SHAEFFER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
FAILED FUEL ASSEMBLY IDENTIFIED DURING CORE OFF-LOAD
"With North Anna Unit 2 in Mode 6 during a scheduled refueling outage, discharged assembly 4Z9 was identified as a failed fuel assembly by In-Mast Sipping. The fuel assembly was located in core location B11. Initial inspection of the fuel assembly identified two (2) visibly split fuel pins of eight (8) to ten (10) inches long with visible damage to the top of the pins. The internals of the affected pins are visible and the springs from the top of each pellet stack are touching the top nozzle. The fuel assembly has been placed into its designated location in the Spent Fuel Pool. No abnormal increase was noted on any radiation monitor either after or during fuel assembly movement. This fuel assembly had been used during three (3) previous operating cycles and is not scheduled for reuse.
"On September 15, 2014, at 0900 [EDT], subsequent video inspection of the fuel assembly identified that the top springs of the two (2) fuel pins were dislodged. Video inspection of the reactor vessel identified debris that has the potential to be fragments of fuel pellets resting on the core plate. Additional investigations are in progress.
"Due to the fact that the failure exceeded expected conditions, this event is being reported per 10 CFR 50.72(b)(3)(ii)(A), as any event or condition that results in the condition of the nuclear plant, including its principle safety barriers, being seriously degraded."
The licensee has notified the NRC Resident Inspector and will notify local county authorities.
* * * UPDATE FROM PAGE KEMP TO HOWIE CROUCH AT 1227 EDT ON 9/30/14 * * *
"Event Notification #50457 was provided on September 15, 2014, at 1454 hours, pursuant to 10 CFR 50.72(b)(3)(ii)(A), to provide notification that North Anna Unit 2 discharged assembly 4Z9 had two visibly split fuel pins and debris on the core plate that had the potential to be fuel pellet fragments.
"Detailed video inspections estimated that fifteen (15) fuel pellets were dislodged from fuel assembly 4Z9. For reference, the reactor core contains approximately 15 million fuel pellets. Efforts to identify and recover the fuel pellets were performed. Debris fragments, estimated to represent five (5) fuel pellets, were located within the damaged fuel assembly that is currently in the spent fuel pool. In addition, an estimated three (3) pellets worth of material was retrieved by the foreign object search and retrieval (FOSAR) efforts in the reactor vessel. The remaining seven (7) fuel pellets have already or are expected to granulate into fine particles that will remain in low flow areas of the primary plant systems or be removed by normal purification processes. However, since the specific location of the seven (7) fuel pellets is undesignated, a report is being made pursuant to 10 CFR 74.11(a) for the loss of special nuclear material.
"The seven (7) fuel pellets contain licensed material in a quantity greater than 10 times the quantity specified in Appendix C of 10 CFR 20; therefore a report is also being made pursuant to 10 CFR 20.2201(a)(ii).
"The cause of the fuel clad degradation is understood and is being addressed. It has been evaluated that the dispersion of fuel pellet material will pose no threat to the integrity or operation of the reactor fuel and primary system components. Reactor Coolant System activity will remain below Technical Specification limits during power operation. In addition, there are no adverse radiological consequences to the public as a result of this issue."
The licensee will be notifying the state of Virginia, local authorities in Louisa County and has notified the NRC Resident Inspector.
Notified R2DO (Vias) and IRD (Stapleton).
"With North Anna Unit 2 in Mode 6 during a scheduled refueling outage, discharged assembly 4Z9 was identified as a failed fuel assembly by In-Mast Sipping. The fuel assembly was located in core location B11. Initial inspection of the fuel assembly identified two (2) visibly split fuel pins of eight (8) to ten (10) inches long with visible damage to the top of the pins. The internals of the affected pins are visible and the springs from the top of each pellet stack are touching the top nozzle. The fuel assembly has been placed into its designated location in the Spent Fuel Pool. No abnormal increase was noted on any radiation monitor either after or during fuel assembly movement. This fuel assembly had been used during three (3) previous operating cycles and is not scheduled for reuse.
"On September 15, 2014, at 0900 [EDT], subsequent video inspection of the fuel assembly identified that the top springs of the two (2) fuel pins were dislodged. Video inspection of the reactor vessel identified debris that has the potential to be fragments of fuel pellets resting on the core plate. Additional investigations are in progress.
"Due to the fact that the failure exceeded expected conditions, this event is being reported per 10 CFR 50.72(b)(3)(ii)(A), as any event or condition that results in the condition of the nuclear plant, including its principle safety barriers, being seriously degraded."
The licensee has notified the NRC Resident Inspector and will notify local county authorities.
* * * UPDATE FROM PAGE KEMP TO HOWIE CROUCH AT 1227 EDT ON 9/30/14 * * *
"Event Notification #50457 was provided on September 15, 2014, at 1454 hours, pursuant to 10 CFR 50.72(b)(3)(ii)(A), to provide notification that North Anna Unit 2 discharged assembly 4Z9 had two visibly split fuel pins and debris on the core plate that had the potential to be fuel pellet fragments.
"Detailed video inspections estimated that fifteen (15) fuel pellets were dislodged from fuel assembly 4Z9. For reference, the reactor core contains approximately 15 million fuel pellets. Efforts to identify and recover the fuel pellets were performed. Debris fragments, estimated to represent five (5) fuel pellets, were located within the damaged fuel assembly that is currently in the spent fuel pool. In addition, an estimated three (3) pellets worth of material was retrieved by the foreign object search and retrieval (FOSAR) efforts in the reactor vessel. The remaining seven (7) fuel pellets have already or are expected to granulate into fine particles that will remain in low flow areas of the primary plant systems or be removed by normal purification processes. However, since the specific location of the seven (7) fuel pellets is undesignated, a report is being made pursuant to 10 CFR 74.11(a) for the loss of special nuclear material.
"The seven (7) fuel pellets contain licensed material in a quantity greater than 10 times the quantity specified in Appendix C of 10 CFR 20; therefore a report is also being made pursuant to 10 CFR 20.2201(a)(ii).
"The cause of the fuel clad degradation is understood and is being addressed. It has been evaluated that the dispersion of fuel pellet material will pose no threat to the integrity or operation of the reactor fuel and primary system components. Reactor Coolant System activity will remain below Technical Specification limits during power operation. In addition, there are no adverse radiological consequences to the public as a result of this issue."
The licensee will be notifying the state of Virginia, local authorities in Louisa County and has notified the NRC Resident Inspector.
Notified R2DO (Vias) and IRD (Stapleton).
Power Reactor
Event Number: 50459
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN MILLER
HQ OPS Officer: JEFF ROTTON
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN MILLER
HQ OPS Officer: JEFF ROTTON
Notification Date: 09/15/2014
Notification Time: 17:57 [ET]
Event Date: 09/15/2014
Event Time: 13:09 [EDT]
Last Update Date: 09/15/2014
Notification Time: 17:57 [ET]
Event Date: 09/15/2014
Event Time: 13:09 [EDT]
Last Update Date: 09/15/2014
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):
SCOTT SHAEFFER (R2DO)
SCOTT SHAEFFER (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 |
LOSS OF EMERGENCY SIREN ACTIVATION CAPABILITY
"At 1309 Eastern Daylight Time (EDT) on September 15, 2014, it was determined that the ability to activate the thirty-eight (38) emergency sirens within the 10 mile emergency planning zone (EPZ) radius of the plant was lost. Subsequently, activation capability was restored when a loose modem cable was discovered and remedied. By approximately 1450 EDT, the ability to activate the emergency sirens had been satisfactorily tested. Activation capability of the emergency sirens was restored in approximately 1 hour and 41 minutes. This event is being reported in accordance with 10 CFR 50.72(b)(3)(xiii) as a major loss of communications capability.
"This event did not result in any adverse impact to the health and safety of the public. The Brunswick Nuclear Plant and State of North Carolina Emergency Response Plans include back-up processes to provide warning to affected areas, if required, in the event of the loss of sirens.
"The cause of the loose modem cable will be investigated.
"The NRC Senior Resident [Inspector] has been notified."
"At 1309 Eastern Daylight Time (EDT) on September 15, 2014, it was determined that the ability to activate the thirty-eight (38) emergency sirens within the 10 mile emergency planning zone (EPZ) radius of the plant was lost. Subsequently, activation capability was restored when a loose modem cable was discovered and remedied. By approximately 1450 EDT, the ability to activate the emergency sirens had been satisfactorily tested. Activation capability of the emergency sirens was restored in approximately 1 hour and 41 minutes. This event is being reported in accordance with 10 CFR 50.72(b)(3)(xiii) as a major loss of communications capability.
"This event did not result in any adverse impact to the health and safety of the public. The Brunswick Nuclear Plant and State of North Carolina Emergency Response Plans include back-up processes to provide warning to affected areas, if required, in the event of the loss of sirens.
"The cause of the loose modem cable will be investigated.
"The NRC Senior Resident [Inspector] has been notified."
Agreement State
Event Number: 50460
Rep Org: SC DIV OF HEALTH & ENV CONTROL
Licensee: SHERTECH PHARMACY
Region: 1
City: SPARTANBURG State: SC
County:
License #: 531
Agreement: Y
Docket:
NRC Notified By: JIM PETERSON
HQ OPS Officer: JEFF ROTTON
Licensee: SHERTECH PHARMACY
Region: 1
City: SPARTANBURG State: SC
County:
License #: 531
Agreement: Y
Docket:
NRC Notified By: JIM PETERSON
HQ OPS Officer: JEFF ROTTON
Notification Date: 09/15/2014
Notification Time: 17:55 [ET]
Event Date: 09/15/2014
Event Time: 00:00 [EDT]
Last Update Date: 09/15/2014
Notification Time: 17:55 [ET]
Event Date: 09/15/2014
Event Time: 00:00 [EDT]
Last Update Date: 09/15/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JOHNATHAN LILLIENDAH (R1DO)
FSME EVENTS RESOURCE (EMAI)
JOHNATHAN LILLIENDAH (R1DO)
FSME EVENTS RESOURCE (EMAI)
AGREEMENT STATE REPORT - IODINE 131 SPILL IN PHARMACY
The following information was provided by the State of South Carolina via email:
"Shertech Pharmacy (SC Radioactive Material License No. 531) in Spartanburg, SC, reported a spill of 100mCi of I-131. A pharmacist dropped the iodine vial on the pharmacy floor. Most of the contamination was on the floor and the shoes of the pharmacist. The Radiation Safety Officer and pharmacist began clean-up procedures. Clothes and shoes were placed in zip lock bags. The floor was cleaned with Radiac wash and the cleaning items were placed in zip lock bags. Activated charcoal was placed on the floor. The four individuals present did take Lugol's solution. Zip lock bags containing the contaminated items were placed in the fume hood. No contamination was found on the skin of any of the individuals involved. Readings of 0.6 mR/hr are measured outside of the closed room. The licensee will perform bioassays at 24, 48, and 72 hours on the four individuals present during the spill and clean up. The primary contamination appeared to be on the shoes themselves."
The following information was provided by the State of South Carolina via email:
"Shertech Pharmacy (SC Radioactive Material License No. 531) in Spartanburg, SC, reported a spill of 100mCi of I-131. A pharmacist dropped the iodine vial on the pharmacy floor. Most of the contamination was on the floor and the shoes of the pharmacist. The Radiation Safety Officer and pharmacist began clean-up procedures. Clothes and shoes were placed in zip lock bags. The floor was cleaned with Radiac wash and the cleaning items were placed in zip lock bags. Activated charcoal was placed on the floor. The four individuals present did take Lugol's solution. Zip lock bags containing the contaminated items were placed in the fume hood. No contamination was found on the skin of any of the individuals involved. Readings of 0.6 mR/hr are measured outside of the closed room. The licensee will perform bioassays at 24, 48, and 72 hours on the four individuals present during the spill and clean up. The primary contamination appeared to be on the shoes themselves."