Event Notification Report for September 10, 2017
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/09/2017 - 09/10/2017
Power Reactor
Event Number: 52959
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: ANTHONY ALSUP
HQ OPS Officer: STEVE SANDIN
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: ANTHONY ALSUP
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/10/2017
Notification Time: 20:45 [ET]
Event Date: 09/10/2017
Event Time: 11:51 [CDT]
Last Update Date: 09/10/2017
Notification Time: 20:45 [ET]
Event Date: 09/10/2017
Event Time: 11:51 [CDT]
Last Update Date: 09/10/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD 50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD 50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
ERIC MICHEL (R2DO)
ERIC MICHEL (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 | Y | 100 | Power Operation | 100 | Power Operation |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
TWO CONTROL BAY CHILLERS DECLARED INOPERABLE
"At 1151 [CDT] on September 10, 2017 Browns Ferry Units 1 and 2 declared 'B' Control Bay chiller inoperable. 'A' Control Bay chiller was previously declared inoperable. This resulted in inoperability of the equipment in the U1 and U2 4kV Shutdown Board Rooms. The declarations of the equipment in the Shutdown Board Rooms is a loss of safely function for electrical components (4kv Shutdown Boards and 480V Shutdown Boards) required for shut down of the U1 and U2 reactors and maintaining them in a safe shutdown condition, as well as RHR capability and Accident Mitigation.
"lnoperability of these boards also requires declaring two trains of Standby Gas Treatment inoperable resulting in a loss of safety function for Units 1, 2 and 3 for systems needed to control the release of radioactive material. This event requires an 8 hour report IAW 50.72(b)(3)(v), 'Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to (A) Shut down the reactor and maintain it in a safe shutdown condition; (B) Remove residual heat; (C) Control the release of radioactive material; or (D) Mitigate the consequences of an accident."
The NRC Resident Inspector has been notified.
CR 1336821 was initiated in the Browns Ferry Corrective Action Program.
"At 1151 [CDT] on September 10, 2017 Browns Ferry Units 1 and 2 declared 'B' Control Bay chiller inoperable. 'A' Control Bay chiller was previously declared inoperable. This resulted in inoperability of the equipment in the U1 and U2 4kV Shutdown Board Rooms. The declarations of the equipment in the Shutdown Board Rooms is a loss of safely function for electrical components (4kv Shutdown Boards and 480V Shutdown Boards) required for shut down of the U1 and U2 reactors and maintaining them in a safe shutdown condition, as well as RHR capability and Accident Mitigation.
"lnoperability of these boards also requires declaring two trains of Standby Gas Treatment inoperable resulting in a loss of safety function for Units 1, 2 and 3 for systems needed to control the release of radioactive material. This event requires an 8 hour report IAW 50.72(b)(3)(v), 'Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to (A) Shut down the reactor and maintain it in a safe shutdown condition; (B) Remove residual heat; (C) Control the release of radioactive material; or (D) Mitigate the consequences of an accident."
The NRC Resident Inspector has been notified.
CR 1336821 was initiated in the Browns Ferry Corrective Action Program.
Power Reactor
Event Number: 52960
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: TIM JONES
HQ OPS Officer: STEVE SANDIN
Region: 2 State: FL
Unit: [] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: TIM JONES
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/10/2017
Notification Time: 22:20 [ET]
Event Date: 09/10/2017
Event Time: 18:55 [EDT]
Last Update Date: 09/10/2017
Notification Time: 22:20 [ET]
Event Date: 09/10/2017
Event Time: 18:55 [EDT]
Last Update Date: 09/10/2017
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):
ERIC MICHEL (R2DO)
GERALD McCOY (R2 I)
ERIC MICHEL (R2DO)
GERALD McCOY (R2 I)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 4 | M/R | Y | 88 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP ON LOWERING STEAM GENERATOR WATER LEVEL
"On 09/10/17 at 1855 [EDT], [Turkey Point] Unit 4 reactor was manually tripped from 88% RTP [Rated Thermal Power] due to a failure of 4C Steam Generator main feed regulating valve causing lowering S/G [Steam Generator] level. All other systems operated normally. Auxiliary Feed Water initiated as designed to provide S/G water level control. EOP's [Emergency Operating Procedures] have been exited and General Operating procedures (GOP'S) were entered. Unit 4 is stable in Mode 3 at NOT/NOP [Normal Operating Temperature/Normal Operating Pressure]."
The licensee is investigating the failure of the feed regulating valve. Offsite power is available. Decay heat is being removed via main feedwater with steam discharged to atmosphere using the ADVs [Atmospheric Dump Valves]. There is no known primary-secondary steam generator tube leakage.
The licensee informed the NRC Resident Inspector.
"On 09/10/17 at 1855 [EDT], [Turkey Point] Unit 4 reactor was manually tripped from 88% RTP [Rated Thermal Power] due to a failure of 4C Steam Generator main feed regulating valve causing lowering S/G [Steam Generator] level. All other systems operated normally. Auxiliary Feed Water initiated as designed to provide S/G water level control. EOP's [Emergency Operating Procedures] have been exited and General Operating procedures (GOP'S) were entered. Unit 4 is stable in Mode 3 at NOT/NOP [Normal Operating Temperature/Normal Operating Pressure]."
The licensee is investigating the failure of the feed regulating valve. Offsite power is available. Decay heat is being removed via main feedwater with steam discharged to atmosphere using the ADVs [Atmospheric Dump Valves]. There is no known primary-secondary steam generator tube leakage.
The licensee informed the NRC Resident Inspector.