Event Notification Report for December 12, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/11/2012 - 12/12/2012
Agreement State
Event Number: 48589
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: THERMO SCIENTIFIC PORTABLE ANALYTICAL INSTRUMENTS
Region: 1
City: TEWKSBURY State: MA
County:
License #: 55-0238
Agreement: Y
Docket:
NRC Notified By: TONY CARPENITO
HQ OPS Officer: CHARLES TEAL
Licensee: THERMO SCIENTIFIC PORTABLE ANALYTICAL INSTRUMENTS
Region: 1
City: TEWKSBURY State: MA
County:
License #: 55-0238
Agreement: Y
Docket:
NRC Notified By: TONY CARPENITO
HQ OPS Officer: CHARLES TEAL
Notification Date: 12/13/2012
Notification Time: 17:05 [ET]
Event Date: 12/12/2012
Event Time: 00:00 [EST]
Last Update Date: 01/08/2013
Notification Time: 17:05 [ET]
Event Date: 12/12/2012
Event Time: 00:00 [EST]
Last Update Date: 01/08/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
DANIEL HOLODY (R1DO)
FSME EVENT RESOURCE (EMAI)
DANIEL HOLODY (R1DO)
FSME EVENT RESOURCE (EMAI)
AGREEMENT STATE - POTENTIAL CONTAMINATED SEALED SOURCE
The following was received from the Commonwealth of Massachusetts via email:
"On 12/13/12, licensee notified this Agency of the 12/12/12 determination of a potential leaking or contaminated sealed source that had been received from an out-of-state vendor. The source being returned to vendor for further analysis. There was no evidence of contamination beyond the source itself."
"The Agency considers this matter to be OPEN pending receipt of written report."
The sealed source contained 0.040 Ci of Cd-109. The manufacturer is Eckert and Zeigler, model XFB-3, with serial number TR2463.
* * * UPDATE FROM TONY CARPENITO TO CHARLES TEAL ON 1/8/13 AT 1042 EDT * * *
The following was received from the Commonwealth of Massachusetts via email:
"The Vendor/Manufacturer reported to licensee in a letter dated 1/7/13 that, per wipe and soak tests conducted in accordance with ISO 9978:1992 (Radiation protection -- Sealed radioactive sources -- Leakage test methods) the source is not leaking and removable activity initially found originated from the capsule's surface. The vendor/manufacturer also wrote that the incident was assigned to the vendor/manufacturer's internal corrective and preventive action program."
Notified R1DO (Newport) and FSME Event Resource via email.
The following was received from the Commonwealth of Massachusetts via email:
"On 12/13/12, licensee notified this Agency of the 12/12/12 determination of a potential leaking or contaminated sealed source that had been received from an out-of-state vendor. The source being returned to vendor for further analysis. There was no evidence of contamination beyond the source itself."
"The Agency considers this matter to be OPEN pending receipt of written report."
The sealed source contained 0.040 Ci of Cd-109. The manufacturer is Eckert and Zeigler, model XFB-3, with serial number TR2463.
* * * UPDATE FROM TONY CARPENITO TO CHARLES TEAL ON 1/8/13 AT 1042 EDT * * *
The following was received from the Commonwealth of Massachusetts via email:
"The Vendor/Manufacturer reported to licensee in a letter dated 1/7/13 that, per wipe and soak tests conducted in accordance with ISO 9978:1992 (Radiation protection -- Sealed radioactive sources -- Leakage test methods) the source is not leaking and removable activity initially found originated from the capsule's surface. The vendor/manufacturer also wrote that the incident was assigned to the vendor/manufacturer's internal corrective and preventive action program."
Notified R1DO (Newport) and FSME Event Resource via email.
Power Reactor
Event Number: 48583
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THOMAS GARRISON
HQ OPS Officer: JOHN KNOKE
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THOMAS GARRISON
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/12/2012
Notification Time: 19:57 [ET]
Event Date: 12/12/2012
Event Time: 15:27 [EST]
Last Update Date: 12/12/2012
Notification Time: 19:57 [ET]
Event Date: 12/12/2012
Event Time: 15:27 [EST]
Last Update Date: 12/12/2012
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):
ALAN BLAMEY (R2DO)
ALAN BLAMEY (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
TECHNICAL SUPPORT CENTER UNAVAILABLE FOR EMERGENCY ASSESSMENT
"While attempting to swap Technical Support Center (TSC) power supplies the TSC air handling unit circuit breaker tripped rendering the TSC unavailable for emergency assessment. An emergent work order has been planned to restore the TSC air handling unit to operational status."
The licensee has notified the NRC Resident Inspector. Licensee also notified state, local and other government agencies.
"While attempting to swap Technical Support Center (TSC) power supplies the TSC air handling unit circuit breaker tripped rendering the TSC unavailable for emergency assessment. An emergent work order has been planned to restore the TSC air handling unit to operational status."
The licensee has notified the NRC Resident Inspector. Licensee also notified state, local and other government agencies.
Power Reactor
Event Number: 48584
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHNNIE EDWARDS
HQ OPS Officer: JOHN KNOKE
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHNNIE EDWARDS
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/12/2012
Notification Time: 23:25 [ET]
Event Date: 12/12/2012
Event Time: 19:14 [EST]
Last Update Date: 12/12/2012
Notification Time: 23:25 [ET]
Event Date: 12/12/2012
Event Time: 19:14 [EST]
Last Update Date: 12/12/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
ALAN BLAMEY (R2DO)
ALAN BLAMEY (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 | N | 0 | Defueled | 0 | Defueled |
RISK OF POSSIBLE FLOODING TO ERCW BUILDING DURING DESIGN BASIS FLOOD
"At 1914 EST on 12/12/12, TVA determined that Sequoyah Unit 1 and 2 were at risk of flooding into the ERCW [Emergency Raw Cooling Water] Station Building during a design basis flood due to conduit penetrations not being filled with material required to make the building water tight. The lack of a barrier would allow flood waters to enter the ERCW building at a rate greater than the sump pumps can remove creating a condition that could result in the ERCW pumps being unavailable to perform their design function during a flood event above plant grade.
"This condition places both units in an unanalyzed condition that significantly degrades plant safety [10 CFR 50.72 (b)(3)(ii)(B)], and could prevent the fulfillment of the safety related function of ERCW needed to shutdown the reactor and maintain it in a safe shutdown condition [10CFR 50.72 (b)(3)(v)(A)].
"Compensatory actions are being established to be capable of removing or limiting water that could leak into the building during the event. The required safety related equipment is currently operable. There are no indications of conditions that might result in a flood in the near term."
The NRC Resident Inspector has been notified of this condition.
"At 1914 EST on 12/12/12, TVA determined that Sequoyah Unit 1 and 2 were at risk of flooding into the ERCW [Emergency Raw Cooling Water] Station Building during a design basis flood due to conduit penetrations not being filled with material required to make the building water tight. The lack of a barrier would allow flood waters to enter the ERCW building at a rate greater than the sump pumps can remove creating a condition that could result in the ERCW pumps being unavailable to perform their design function during a flood event above plant grade.
"This condition places both units in an unanalyzed condition that significantly degrades plant safety [10 CFR 50.72 (b)(3)(ii)(B)], and could prevent the fulfillment of the safety related function of ERCW needed to shutdown the reactor and maintain it in a safe shutdown condition [10CFR 50.72 (b)(3)(v)(A)].
"Compensatory actions are being established to be capable of removing or limiting water that could leak into the building during the event. The required safety related equipment is currently operable. There are no indications of conditions that might result in a flood in the near term."
The NRC Resident Inspector has been notified of this condition.