Event Notification Report for November 08, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/07/2016 - 11/08/2016
Power Reactor
Event Number: 52353
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: TIMOTHY GNADT
HQ OPS Officer: DONG HWA PARK
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: TIMOTHY GNADT
HQ OPS Officer: DONG HWA PARK
Notification Date: 11/08/2016
Notification Time: 08:59 [ET]
Event Date: 11/08/2016
Event Time: 08:51 [EST]
Last Update Date: 11/08/2016
Notification Time: 08:59 [ET]
Event Date: 11/08/2016
Event Time: 08:51 [EST]
Last Update Date: 11/08/2016
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
RAY MCKINLEY (R1DO)
CHRIS MILLER (NRR)
WILLIAM GOTT (IRD)
DAVID LEW (R1DR)
MICHELE EVANS (NRR)
RAY MCKINLEY (R1DO)
CHRIS MILLER (NRR)
WILLIAM GOTT (IRD)
DAVID LEW (R1DR)
MICHELE EVANS (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNUSUAL EVENT DECLARED DUE TO EQUIPMENT FAILURE CAUSING AN EXPLOSION IN THE PROTECTED AREA
"On November 8, 2016, at approximately 0840 EST, plant personnel reported an explosion within the Protected Area resulting in a fire with potential damage to plant structures or equipment. An Unusual Event was declared at 0851 EST. The onsite Fire Brigade was mobilized. The fire was extinguished at 0848 EST. The explosion was to the 138 kV power cross connect cable between the Unit 2 and 3 Station Auxiliary Transformers. Both Units are operating normally. There was no release of radioactive material. An investigation of the event is in progress."
Offsite assistance was not required. Unit 2 was in a normal electrical line-up and Unit 3 was not affected.
The licensee has notified the NRC Resident Inspector, State, Local, and Other Government Agencies. The licensee will issue a press release.
Notified DHS SWO, FEMA OPS Center, FEMA National Watch (email only), DHS NICC, Nuclear SSA (email only).
* * * UPDATE FROM R.T. THOMAS TO BETHANY CECERE AT 0955 EST on 11/8/16 * * *
The Unusual Event was terminated at 0946 EST based on the fire being out.
The licensee has notified the NRC Resident Inspector.
Notified R1DO (McKinley), IRD (Gott), and NRR EO (Miller). Notified DHS SWO, FEMA OPS Center, FEMA National Watch (email only), DHS NICC, Nuclear SSA (email only).
"On November 8, 2016, at approximately 0840 EST, plant personnel reported an explosion within the Protected Area resulting in a fire with potential damage to plant structures or equipment. An Unusual Event was declared at 0851 EST. The onsite Fire Brigade was mobilized. The fire was extinguished at 0848 EST. The explosion was to the 138 kV power cross connect cable between the Unit 2 and 3 Station Auxiliary Transformers. Both Units are operating normally. There was no release of radioactive material. An investigation of the event is in progress."
Offsite assistance was not required. Unit 2 was in a normal electrical line-up and Unit 3 was not affected.
The licensee has notified the NRC Resident Inspector, State, Local, and Other Government Agencies. The licensee will issue a press release.
Notified DHS SWO, FEMA OPS Center, FEMA National Watch (email only), DHS NICC, Nuclear SSA (email only).
* * * UPDATE FROM R.T. THOMAS TO BETHANY CECERE AT 0955 EST on 11/8/16 * * *
The Unusual Event was terminated at 0946 EST based on the fire being out.
The licensee has notified the NRC Resident Inspector.
Notified R1DO (McKinley), IRD (Gott), and NRR EO (Miller). Notified DHS SWO, FEMA OPS Center, FEMA National Watch (email only), DHS NICC, Nuclear SSA (email only).
Power Reactor
Event Number: 52355
Facility: DRESDEN
Region: 3 State: IL
Unit: [] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: RICHARD GALLAGHER
HQ OPS Officer: JEFF HERRERA
Region: 3 State: IL
Unit: [] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: RICHARD GALLAGHER
HQ OPS Officer: JEFF HERRERA
Notification Date: 11/08/2016
Notification Time: 12:50 [ET]
Event Date: 11/08/2016
Event Time: 05:10 [CST]
Last Update Date: 11/08/2016
Notification Time: 12:50 [ET]
Event Date: 11/08/2016
Event Time: 05:10 [CST]
Last Update Date: 11/08/2016
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):
MARK JEFFERS (R3DO)
MARK JEFFERS (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 3 | N | N | 0 | Refueling | 0 | Refueling |
REACTOR BUILDING TO ATMOSPHERE DIFFERENTIAL PRESSURE OUT OF SPECIFICATIONS
"On 11/8/16, Operators were performing Division I Undervoltage Testing Surveillance on Unit 3, when a 2 [psi] drywell signal was inserted, Reactor Building Ventilation tripped and SBGT initiated as expected. At 0510 [CST], reactor building to atmosphere differential pressure dropped below the [negative] 0.25 inches water. This condition represents a failure to meet Surveillance Requirement 3.6.4.1.1. As a result, entry into Technical Specification 3.6.4.1 condition A was made due to Secondary Containment becoming inoperable. This event is being reported in accordance with 10CFR 50.72(b)(3)(v)(C) as a condition that could have prevented the fulfillment of a safety function. At 0532, the 2/3 Reactor Building material interlock inner door was closed and Reactor Building [differential pressure] was restored to greater than [negative].25 inches of water column. An issue report has been initiated. An investigation will be conducted and a 60 day Licensee Event report will be submitted in accordance with 10 CFR 50.73(a)(2)(v)(C).
"The NRC Resident Inspector has been notified."
"On 11/8/16, Operators were performing Division I Undervoltage Testing Surveillance on Unit 3, when a 2 [psi] drywell signal was inserted, Reactor Building Ventilation tripped and SBGT initiated as expected. At 0510 [CST], reactor building to atmosphere differential pressure dropped below the [negative] 0.25 inches water. This condition represents a failure to meet Surveillance Requirement 3.6.4.1.1. As a result, entry into Technical Specification 3.6.4.1 condition A was made due to Secondary Containment becoming inoperable. This event is being reported in accordance with 10CFR 50.72(b)(3)(v)(C) as a condition that could have prevented the fulfillment of a safety function. At 0532, the 2/3 Reactor Building material interlock inner door was closed and Reactor Building [differential pressure] was restored to greater than [negative].25 inches of water column. An issue report has been initiated. An investigation will be conducted and a 60 day Licensee Event report will be submitted in accordance with 10 CFR 50.73(a)(2)(v)(C).
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 52356
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BLAKE MITCHELL
HQ OPS Officer: VINCE KLCO
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BLAKE MITCHELL
HQ OPS Officer: VINCE KLCO
Notification Date: 11/08/2016
Notification Time: 17:36 [ET]
Event Date: 11/08/2016
Event Time: 00:00 [CST]
Last Update Date: 11/08/2016
Notification Time: 17:36 [ET]
Event Date: 11/08/2016
Event Time: 00:00 [CST]
Last Update Date: 11/08/2016
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):
STEVE ROSE (R2DO)
STEVE ROSE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 32 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO STEAM GENERATOR REDUCED FEEDFLOW
"At 1331 [CST] on November 8, 2016, Farley Nuclear Plant Unit 1 manually tripped from 32% reactor power. The plant was ramping down to remove the main generator from service due to an unrelated issue. 1A SGFP did not respond to control Steam Generator (SG) level as expected when the miniflow was opened per procedure. SG levels lowered due to lower feed flow and the reactor was manually tripped in accordance with plant procedures. All control rods fully inserted and Auxiliary feedwater (AFW) auto started as expected. The Main Steam Isolation Valves were closed to minimize the cool-down. Decay heat is being removed through the Atmospheric Relief Valves.
"All other systems responded as expected. The plant is currently stable in Mode 3 (Hot Standby). The failure of the 1A SGFP control is under investigation.
"Unit 2 was not affected.
"The NRC Resident Inspector has been notified."
There is no primary to secondary leakage.
"At 1331 [CST] on November 8, 2016, Farley Nuclear Plant Unit 1 manually tripped from 32% reactor power. The plant was ramping down to remove the main generator from service due to an unrelated issue. 1A SGFP did not respond to control Steam Generator (SG) level as expected when the miniflow was opened per procedure. SG levels lowered due to lower feed flow and the reactor was manually tripped in accordance with plant procedures. All control rods fully inserted and Auxiliary feedwater (AFW) auto started as expected. The Main Steam Isolation Valves were closed to minimize the cool-down. Decay heat is being removed through the Atmospheric Relief Valves.
"All other systems responded as expected. The plant is currently stable in Mode 3 (Hot Standby). The failure of the 1A SGFP control is under investigation.
"Unit 2 was not affected.
"The NRC Resident Inspector has been notified."
There is no primary to secondary leakage.