Event Notification Report for April 04, 2017
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/03/2017 - 04/04/2017
Power Reactor
Event Number: 52663
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAVID BURRUS
HQ OPS Officer: JEFF HERRERA
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAVID BURRUS
HQ OPS Officer: JEFF HERRERA
Notification Date: 04/04/2017
Notification Time: 06:57 [ET]
Event Date: 04/04/2017
Event Time: 00:10 [CDT]
Last Update Date: 04/04/2017
Notification Time: 06:57 [ET]
Event Date: 04/04/2017
Event Time: 00:10 [CDT]
Last Update Date: 04/04/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MICHAEL VASQUEZ (R4DO)
MICHAEL VASQUEZ (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 75 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM DUE TO CONDENSATE LEAK
"At 0010 [CDT], 04/04/2017, the reactor was manually scrammed from approximately 75 [percent] core thermal power due Condensate Storage tank level lowering to 24 feet. All control rods fully inserted and all systems actuated and operated as designed. No safety relief valves actuated. Reactor level and pressure are currently being controlled within normal bands. RCIC [reactor core isolation cooling] was manually initiated for level control.
"This event is reportable under 10CFR50.72(b)(2)(iv)(B) for the reactor trip and 50.72(b)(3)(iv)(A) for the manual start of the reactor core isolation cooling system."
The cause of lowering level was a condensate pipe leak. Decay heat is being removed via steam dumps to the condenser. The electrical grid is stable and supplying plant loads.
The licensee has notified the NRC Resident Inspector.
"At 0010 [CDT], 04/04/2017, the reactor was manually scrammed from approximately 75 [percent] core thermal power due Condensate Storage tank level lowering to 24 feet. All control rods fully inserted and all systems actuated and operated as designed. No safety relief valves actuated. Reactor level and pressure are currently being controlled within normal bands. RCIC [reactor core isolation cooling] was manually initiated for level control.
"This event is reportable under 10CFR50.72(b)(2)(iv)(B) for the reactor trip and 50.72(b)(3)(iv)(A) for the manual start of the reactor core isolation cooling system."
The cause of lowering level was a condensate pipe leak. Decay heat is being removed via steam dumps to the condenser. The electrical grid is stable and supplying plant loads.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 52664
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: HENDRIK VERWEY
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: HENDRIK VERWEY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/04/2017
Notification Time: 11:32 [ET]
Event Date: 04/04/2017
Event Time: 07:35 [EDT]
Last Update Date: 04/04/2017
Notification Time: 11:32 [ET]
Event Date: 04/04/2017
Event Time: 07:35 [EDT]
Last Update Date: 04/04/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
CHRISTOPHER CAHILL (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 |
HIGH PRESSURE COOLANT INJECTION INADVERTENTLY ISOLATED DURING CONDUCT OF MAINTENANCE SURVEILLANCE
"On April 4, 2017, at 0735 [EDT], the HPCI System was inadvertently isolated during the performance of l&C [Instrument and Control] testing.
"Technicians were in the process of performing instrument surveillance tests for the HPCI [high pressure coolant injection] System (using Allowed Out of Service Times) when a trip signal was applied to the incorrect instrument. This caused a HPCI System isolation signal on High Area Temperature, resulting in the closure of the HPCI steam isolation valves and rendering the system inoperable and unavailable. RCIC was immediately verified to be operable.
"The surveillance testing was aborted and system restoration is in progress.
"This condition is being reported as a condition that could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident per 10CFR50.72(b)(3)(v)(D)."
This placed the plant in a 14-day LCO action statement under Technical Specification 3.5.1.
The licensee has notified the NRC Resident Inspector.
"On April 4, 2017, at 0735 [EDT], the HPCI System was inadvertently isolated during the performance of l&C [Instrument and Control] testing.
"Technicians were in the process of performing instrument surveillance tests for the HPCI [high pressure coolant injection] System (using Allowed Out of Service Times) when a trip signal was applied to the incorrect instrument. This caused a HPCI System isolation signal on High Area Temperature, resulting in the closure of the HPCI steam isolation valves and rendering the system inoperable and unavailable. RCIC was immediately verified to be operable.
"The surveillance testing was aborted and system restoration is in progress.
"This condition is being reported as a condition that could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident per 10CFR50.72(b)(3)(v)(D)."
This placed the plant in a 14-day LCO action statement under Technical Specification 3.5.1.
The licensee has notified the NRC Resident Inspector.