Event Notification Report for July 30, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/29/2016 - 07/30/2016
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 52136
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: PAUL REIMERS
HQ OPS Officer: JEFF HERRERA
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: PAUL REIMERS
HQ OPS Officer: JEFF HERRERA
Notification Date: 07/30/2016
Notification Time: 03:52 [ET]
Event Date: 07/30/2016
Event Time: 03:33 [EDT]
Last Update Date: 07/30/2016
Notification Time: 03:52 [ET]
Event Date: 07/30/2016
Event Time: 03:33 [EDT]
Last Update Date: 07/30/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
STEVE ROSE (R2DO)
STEVE ROSE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | M/R | Y | 54 | Power Operation | 0 | Hot Standby |
TURKEY POINT UNIT 3 SHUTDOWN DUE TO WATER HAMMER
"Power had been reduced for planned maintenance on the 3B feedwater heater. During isolation of the feedwater heaters, a repeated water hammer was experienced.
"A normal shutdown of Unit 3 was performed."
Unit 4 was not affected by the water hammer. The decay heat is being removed via the condenser and all offsite and onsite electrical power is available. The investigation of the cause is underway.
The licensee will notify the NRC Resident Inspector.
* * * UPDATE AT 2141 EDT ON 07/30/16 FROM ERIC JUERGENS TO S. SANDIN * * *
The licensee is retracting this report based on the following:
"At 0352 EDT on July 30, 2016, EN #52136 provided notification of a Reactor Protection System (RPS) actuation during a normal shutdown of Unit 3 in response to a secondary system equipment issue. Upon further investigation, the unit shutdown and manual RPS actuation were in accordance with general plant operating procedures. The manual RPS actuation was in accordance with the general operating procedure and not required to mitigate the consequences of the secondary system equipment issue. As such, the notification made by EN #52136 for a valid actuation of a specified system is hereby retracted.
"The NRC Resident lnspector will be notified."
Notified R2DO (Rose).
"Power had been reduced for planned maintenance on the 3B feedwater heater. During isolation of the feedwater heaters, a repeated water hammer was experienced.
"A normal shutdown of Unit 3 was performed."
Unit 4 was not affected by the water hammer. The decay heat is being removed via the condenser and all offsite and onsite electrical power is available. The investigation of the cause is underway.
The licensee will notify the NRC Resident Inspector.
* * * UPDATE AT 2141 EDT ON 07/30/16 FROM ERIC JUERGENS TO S. SANDIN * * *
The licensee is retracting this report based on the following:
"At 0352 EDT on July 30, 2016, EN #52136 provided notification of a Reactor Protection System (RPS) actuation during a normal shutdown of Unit 3 in response to a secondary system equipment issue. Upon further investigation, the unit shutdown and manual RPS actuation were in accordance with general plant operating procedures. The manual RPS actuation was in accordance with the general operating procedure and not required to mitigate the consequences of the secondary system equipment issue. As such, the notification made by EN #52136 for a valid actuation of a specified system is hereby retracted.
"The NRC Resident lnspector will be notified."
Notified R2DO (Rose).
Power Reactor
Event Number: 52137
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: DON TAYLOR
HQ OPS Officer: HOWIE CROUCH
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: DON TAYLOR
HQ OPS Officer: HOWIE CROUCH
Notification Date: 07/30/2016
Notification Time: 15:17 [ET]
Event Date: 07/30/2016
Event Time: 11:52 [EDT]
Last Update Date: 07/30/2016
Notification Time: 15:17 [ET]
Event Date: 07/30/2016
Event Time: 11:52 [EDT]
Last Update Date: 07/30/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
STEVE ROSE (R2DO)
STEVE ROSE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 35 | Power Operation |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO UNISOLABLE REACTOR COOLANT SYSTEM BOUNDARY LEAKAGE
"On July 30, 2016 at 1152 hours [EDT] following a containment walkdown to investigate an increase in RCS unidentified leakage to 0.15 gpm, a leak was identified on the seal return line from 2-RC-P-1C, 'C' Reactor Coolant Pump. The source of the leakage cannot be isolated and is considered RCS pressure boundary leakage. [Technical Specification] LCO 3.4.13, RCS Operational Leakage, Condition B for the existence of pressure boundary leakage was entered. Technical Requirement TR 3.4.6, ASME Code Class 1, 2, and 3 Components is also applicable. Unit 2 is projected to be taken to Mode 5 for repair.
"This event is reportable in accordance with 10 CFR 50.72(b)(2) for 'the initiation of any nuclear plant shutdown required by the plant's Technical Specifications' and 10 CFR 50.72(b)(3)(ii)(A) for 'any event or condition that results in the condition of the nuclear plant including its principal safety barriers, being seriously degraded.'"
The licensee will be notifying the Louisa County Administrator and has notified the NRC Resident Inspector.
"On July 30, 2016 at 1152 hours [EDT] following a containment walkdown to investigate an increase in RCS unidentified leakage to 0.15 gpm, a leak was identified on the seal return line from 2-RC-P-1C, 'C' Reactor Coolant Pump. The source of the leakage cannot be isolated and is considered RCS pressure boundary leakage. [Technical Specification] LCO 3.4.13, RCS Operational Leakage, Condition B for the existence of pressure boundary leakage was entered. Technical Requirement TR 3.4.6, ASME Code Class 1, 2, and 3 Components is also applicable. Unit 2 is projected to be taken to Mode 5 for repair.
"This event is reportable in accordance with 10 CFR 50.72(b)(2) for 'the initiation of any nuclear plant shutdown required by the plant's Technical Specifications' and 10 CFR 50.72(b)(3)(ii)(A) for 'any event or condition that results in the condition of the nuclear plant including its principal safety barriers, being seriously degraded.'"
The licensee will be notifying the Louisa County Administrator and has notified the NRC Resident Inspector.