Event Notification Report for January 11, 2017
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/10/2017 - 01/11/2017
Power Reactor
Event Number: 52484
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HUNTER SCHILL
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HUNTER SCHILL
HQ OPS Officer: DONALD NORWOOD
Notification Date: 01/11/2017
Notification Time: 16:56 [ET]
Event Date: 01/11/2017
Event Time: 15:00 [CST]
Last Update Date: 01/11/2017
Notification Time: 16:56 [ET]
Event Date: 01/11/2017
Event Time: 15:00 [CST]
Last Update Date: 01/11/2017
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):
NICK TAYLOR (R4DO)
NICK TAYLOR (R4DO)
| 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 |
TEFLON FOUND IN CONTAINMENT SPRAY PUMP COMPONENTS
"On September 16, 2016, Comanche Peak reported an unanalyzed condition and potential loss of safety function per 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v) related to Teflon (PTFE) installed in the pressure gauge diaphragm seal assemblies for all four of the Centrifugal Charging Pumps and both of the Positive Displacement Charging Pumps on Units 1 and 2 (EN#52244). On November 14, 2016, this event was subsequently retracted.
"On December 12, 2016, during the ongoing extent of condition review, Teflon was also found to be installed in the suction and discharge pressure gauge diaphragm seal assemblies for the Unit 1 and 2 Containment Spray Pumps. On January 11, 2017 at approximately 1500 CDT, the reportability evaluation determined that reasonable assurance did not exist that the Containment Spray system would have been able to fulfill its design function of removing heat from the containment environment without impacting the applicable dose limits.
"Teflon (PTFE) is a restricted material normally prohibited from use in contact with reactor coolant or in radiation environments. Teflon (PTFE) is not radiation tolerant and degrades in a radiation environment. The Teflon (PTFE) used in these diaphragm seal assemblies could fail during a postulated Loss of Coolant Accident (LOCA) which could cause the Containment Spray Pumps on Units 1 and 2 to be inoperable, and exceed system leakage limits. This could challenge dose limits and in plant post-accident accessibility. This represents an unanalyzed condition. The pressure gauges and diaphragm seals for all of the Unit 1 and 2 Containment Spray Pumps have been isolated and the Unit 1 and 2 Containment Spray Pumps are operable. The Teflon (PTFE) has likely existed in these diaphragm seals since initial plant licensing. Luminant Power is continuing to investigate the extent of this condition and potential repair techniques.
"The NRC Resident Inspector has been notified."
"On September 16, 2016, Comanche Peak reported an unanalyzed condition and potential loss of safety function per 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v) related to Teflon (PTFE) installed in the pressure gauge diaphragm seal assemblies for all four of the Centrifugal Charging Pumps and both of the Positive Displacement Charging Pumps on Units 1 and 2 (EN#52244). On November 14, 2016, this event was subsequently retracted.
"On December 12, 2016, during the ongoing extent of condition review, Teflon was also found to be installed in the suction and discharge pressure gauge diaphragm seal assemblies for the Unit 1 and 2 Containment Spray Pumps. On January 11, 2017 at approximately 1500 CDT, the reportability evaluation determined that reasonable assurance did not exist that the Containment Spray system would have been able to fulfill its design function of removing heat from the containment environment without impacting the applicable dose limits.
"Teflon (PTFE) is a restricted material normally prohibited from use in contact with reactor coolant or in radiation environments. Teflon (PTFE) is not radiation tolerant and degrades in a radiation environment. The Teflon (PTFE) used in these diaphragm seal assemblies could fail during a postulated Loss of Coolant Accident (LOCA) which could cause the Containment Spray Pumps on Units 1 and 2 to be inoperable, and exceed system leakage limits. This could challenge dose limits and in plant post-accident accessibility. This represents an unanalyzed condition. The pressure gauges and diaphragm seals for all of the Unit 1 and 2 Containment Spray Pumps have been isolated and the Unit 1 and 2 Containment Spray Pumps are operable. The Teflon (PTFE) has likely existed in these diaphragm seals since initial plant licensing. Luminant Power is continuing to investigate the extent of this condition and potential repair techniques.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 52482
Facility: VOGTLE
Region: 2 State: GA
Unit: [3] [4] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: AMANDA PUGH
HQ OPS Officer: STEVE SANDIN
Region: 2 State: GA
Unit: [3] [4] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: AMANDA PUGH
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/11/2017
Notification Time: 13:52 [ET]
Event Date: 01/11/2017
Event Time: 10:58 [EST]
Last Update Date: 01/11/2017
Notification Time: 13:52 [ET]
Event Date: 01/11/2017
Event Time: 10:58 [EST]
Last Update Date: 01/11/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
SCOTT SHAEFFER (R2DO)
FFD GROUP (EMAI)
SHANE SANDAL (R2)
SCOTT SHAEFFER (R2DO)
FFD GROUP (EMAI)
SHANE SANDAL (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Under Construction | 0 | Under Construction |
| 4 | N | N | 0 | Under Construction | 0 | Under Construction |
FITNESS-FOR-DUTY TEST POSITIVE FOR NON-LICENSED SUPERVISOR
A non-licensed supervisor tested positive for alcohol during a for-cause test. The individual's access to the site has been terminated pending the results of an investigation.
The licensee notified RII (Patterson) and the NRC Resident Inspector.
A non-licensed supervisor tested positive for alcohol during a for-cause test. The individual's access to the site has been terminated pending the results of an investigation.
The licensee notified RII (Patterson) and the NRC Resident Inspector.