Event Notification Report for April 11, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/10/2015 - 04/11/2015
Power Reactor
Event Number: 50974
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RON FRY
HQ OPS Officer: JEFF ROTTON
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RON FRY
HQ OPS Officer: JEFF ROTTON
Notification Date: 04/11/2015
Notification Time: 05:22 [ET]
Event Date: 04/11/2015
Event Time: 00:51 [EDT]
Last Update Date: 04/11/2015
Notification Time: 05:22 [ET]
Event Date: 04/11/2015
Event Time: 00:51 [EDT]
Last Update Date: 04/11/2015
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):
MARC FERDAS (R1DO)
MARC FERDAS (R1DO)
| 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 | Hot Shutdown | 0 | Hot Shutdown |
SECONDARY CONTAINMENT INOPERABLE DUE TO FAILURE OF RUNNING FANS
"On April 11, 2015 at 0051 EDT, Secondary Containment became inoperable requiring a Technical Specification 3.6.4.1 entry for failure to meet SR [Surveillance Requirement] 3.6.4.1.1 on Unit 1 and Unit 2, loss of required differential pressure.
"The inoperability was caused by a loss of normal Zone 2 differential pressure due to loss of running fans and failure to start of standby fans. The cause is being investigated.
"Engineering and maintenance personnel implemented a Temporary Engineering Change, which allowed restoration of one set of fans and dampers. Normal secondary containment differential pressure was restored. Technical Specification 3.6.4.1 was exited at 0320 EDT.
"This event is being reported under 10 CFR 50.72(b)(3)(v)(c) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment system.
"The NRC Resident Inspector was notified."
Temporary Engineering Change consisted of removing air to a previously running fan discharge damper so it would close and allow standby fans to start.
"On April 11, 2015 at 0051 EDT, Secondary Containment became inoperable requiring a Technical Specification 3.6.4.1 entry for failure to meet SR [Surveillance Requirement] 3.6.4.1.1 on Unit 1 and Unit 2, loss of required differential pressure.
"The inoperability was caused by a loss of normal Zone 2 differential pressure due to loss of running fans and failure to start of standby fans. The cause is being investigated.
"Engineering and maintenance personnel implemented a Temporary Engineering Change, which allowed restoration of one set of fans and dampers. Normal secondary containment differential pressure was restored. Technical Specification 3.6.4.1 was exited at 0320 EDT.
"This event is being reported under 10 CFR 50.72(b)(3)(v)(c) and per the guidance of NUREG 1022 Rev 3 section 3.2.7 as a loss of a Safety Function. There is no redundant Susquehanna Secondary Containment system.
"The NRC Resident Inspector was notified."
Temporary Engineering Change consisted of removing air to a previously running fan discharge damper so it would close and allow standby fans to start.
Power Reactor
Event Number: 50976
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: LONNIE CRAWFORD
HQ OPS Officer: DONALD NORWOOD
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: LONNIE CRAWFORD
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/11/2015
Notification Time: 11:23 [ET]
Event Date: 04/11/2015
Event Time: 09:58 [EDT]
Last Update Date: 04/11/2015
Notification Time: 11:23 [ET]
Event Date: 04/11/2015
Event Time: 09:58 [EDT]
Last Update Date: 04/11/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
MARC FERDAS (R1DO)
MARC FERDAS (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
DRYWELL LEAKAGE POINT IDENTIFIED
"On 4/11/15, Unit 2 drywell entry was performed during a planned Unit 2 refueling inspection outage. At 0958 EDT, the licensee identified leakage from a weld on the 3/4 inch seal vent piping connected to the 2A reactor recirculation pump seal area. The location is within the reactor recirculation loop isolation valves, therefore it is isolable from the reactor vessel. The piping is ASME Class 2 and is a reactor coolant pressure boundary. The reactor was in mode 3 at the time of discovery.
"This event is being reported as a degraded condition pursuant to 10CFR50.72(b)(3)(ii)(A)."
The licensee notified the NRC Resident Inspector.
"On 4/11/15, Unit 2 drywell entry was performed during a planned Unit 2 refueling inspection outage. At 0958 EDT, the licensee identified leakage from a weld on the 3/4 inch seal vent piping connected to the 2A reactor recirculation pump seal area. The location is within the reactor recirculation loop isolation valves, therefore it is isolable from the reactor vessel. The piping is ASME Class 2 and is a reactor coolant pressure boundary. The reactor was in mode 3 at the time of discovery.
"This event is being reported as a degraded condition pursuant to 10CFR50.72(b)(3)(ii)(A)."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 50977
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: CHARLES PIKE
HQ OPS Officer: HOWIE CROUCH
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: CHARLES PIKE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/11/2015
Notification Time: 22:15 [ET]
Event Date: 04/11/2015
Event Time: 21:00 [EDT]
Last Update Date: 04/11/2015
Notification Time: 22:15 [ET]
Event Date: 04/11/2015
Event Time: 21:00 [EDT]
Last Update Date: 04/11/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
JAMIE HEISSERER (R2DO)
JAMIE HEISSERER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 80 | Power Operation |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO SAFETY INJECTION TANK OUTLET PIPING LEAK
"During investigation of a small leak on the 2B2 Safety Injection Tank inside Saint Lucie Unit 2 containment, a through wall flaw was identified on Class 2 piping associated with the 2B2 Safety Injection Tank. The 2B2 Safety Injection Tank was declared inoperable on April 11, 2015 at 1204 EDT and Unit 2 entered a 24-hour shutdown action statement for Technical Specification 3.5.1.b. On April 11, 2015 at 2100 EDT, Unit 2 initiated a plant shutdown in compliance with Technical Specifications.
"This condition is being reported pursuant to 10 CFR 50.72(b)(2)(i)"
The electrical grid is stable and no safety-related equipment that would affect a safe shutdown was out of service at the time of the report.
The licensee has notified the NRC Resident Inspector.
"During investigation of a small leak on the 2B2 Safety Injection Tank inside Saint Lucie Unit 2 containment, a through wall flaw was identified on Class 2 piping associated with the 2B2 Safety Injection Tank. The 2B2 Safety Injection Tank was declared inoperable on April 11, 2015 at 1204 EDT and Unit 2 entered a 24-hour shutdown action statement for Technical Specification 3.5.1.b. On April 11, 2015 at 2100 EDT, Unit 2 initiated a plant shutdown in compliance with Technical Specifications.
"This condition is being reported pursuant to 10 CFR 50.72(b)(2)(i)"
The electrical grid is stable and no safety-related equipment that would affect a safe shutdown was out of service at the time of the report.
The licensee has notified the NRC Resident Inspector.