Event Notification Report for December 27, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/26/2019 - 12/27/2019
Power Reactor
Event Number: 54457
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JASON PARIS
HQ OPS Officer: OSSY FONT
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JASON PARIS
HQ OPS Officer: OSSY FONT
Notification Date: 12/27/2019
Notification Time: 07:53 [ET]
Event Date: 12/27/2019
Event Time: 07:04 [EST]
Last Update Date: 12/27/2019
Notification Time: 07:53 [ET]
Event Date: 12/27/2019
Event Time: 07:04 [EST]
Last Update Date: 12/27/2019
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):
JOHN CHERUBINI (R1DO)
JOHN CHERUBINI (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL TRIP DUE TO FEEDWATER PUMP TRIP
This is a synopsis of initial information received via phone:
On December 27, 2019, at 0705 EST, while Unit 2 was at 100 percent (Mode 1), the 'A' Main Feedwater Pump tripped due to an unknown cause. The reactor was manually tripped and is currently at zero (0) percent power (Mode 3). Decay heat is being removed via Auxiliary Feedwater. The 'B' Feedwater pump is operable.
There was no impact on Unit 3.
The licensee notified the NRC Resident Inspector. Additionally, Connecticut Department of Environmental Protection, Waterford Dispatch, and East Lyme Emergency Management Division will be notified.
* * * UPDATE ON 12/27/2019 AT 1330 EST FROM JASON PARIS TO CATY NOLAN * * *
"This is an update to NRC Event Number 54457.
"At 0704 EST, on 12/27/2019, with Millstone Unit 2 operating at 100 percent power, operators inserted a manual reactor trip. The trip was initiated due to a trip of the 'A' Main Feedwater Pump.
"The Auxiliary Feedwater System (AFW) automatically actuated as required.
"All control and shutdown rods fully inserted. All safety systems responded as designed. No primary or secondary safety valves actuated during or after the transient. Unit 2 is currently stable at normal operating pressure and temperature in Mode 3, Hot Standby. Reactor Coolant System (RCS) temperature is being maintained by the steam dump system with all Reactor Coolant Pumps (RCPs) in service. Main Feedwater has been secured, and Auxiliary Feedwater is in service. The electrical system is in normal alignment.
"There was no impact on Unit 3. There was no impact to the health and safety of the public or plant personnel.
"Due to Reactor Protection System (RPS) actuation while critical, this event was reported as a four hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B); and an eight hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of the AFW system."
The licensee will notify the NRC Resident Inspector of the update.
Notified R1DO (Cherubini).
This is a synopsis of initial information received via phone:
On December 27, 2019, at 0705 EST, while Unit 2 was at 100 percent (Mode 1), the 'A' Main Feedwater Pump tripped due to an unknown cause. The reactor was manually tripped and is currently at zero (0) percent power (Mode 3). Decay heat is being removed via Auxiliary Feedwater. The 'B' Feedwater pump is operable.
There was no impact on Unit 3.
The licensee notified the NRC Resident Inspector. Additionally, Connecticut Department of Environmental Protection, Waterford Dispatch, and East Lyme Emergency Management Division will be notified.
* * * UPDATE ON 12/27/2019 AT 1330 EST FROM JASON PARIS TO CATY NOLAN * * *
"This is an update to NRC Event Number 54457.
"At 0704 EST, on 12/27/2019, with Millstone Unit 2 operating at 100 percent power, operators inserted a manual reactor trip. The trip was initiated due to a trip of the 'A' Main Feedwater Pump.
"The Auxiliary Feedwater System (AFW) automatically actuated as required.
"All control and shutdown rods fully inserted. All safety systems responded as designed. No primary or secondary safety valves actuated during or after the transient. Unit 2 is currently stable at normal operating pressure and temperature in Mode 3, Hot Standby. Reactor Coolant System (RCS) temperature is being maintained by the steam dump system with all Reactor Coolant Pumps (RCPs) in service. Main Feedwater has been secured, and Auxiliary Feedwater is in service. The electrical system is in normal alignment.
"There was no impact on Unit 3. There was no impact to the health and safety of the public or plant personnel.
"Due to Reactor Protection System (RPS) actuation while critical, this event was reported as a four hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B); and an eight hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of the AFW system."
The licensee will notify the NRC Resident Inspector of the update.
Notified R1DO (Cherubini).
Part 21
Event Number: 54476
Rep Org: UNITED CONTROLS INTERNATIONAL
Licensee: UNITED CONTROLS INTERNATIONAL
Region: 1
City: NORCROSS State: GA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROB HALE
HQ OPS Officer: ANDREW WAUGH
Licensee: UNITED CONTROLS INTERNATIONAL
Region: 1
City: NORCROSS State: GA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROB HALE
HQ OPS Officer: ANDREW WAUGH
Notification Date: 01/14/2020
Notification Time: 10:37 [ET]
Event Date: 12/27/2019
Event Time: 00:00 [EST]
Last Update Date: 01/14/2020
Notification Time: 10:37 [ET]
Event Date: 12/27/2019
Event Time: 00:00 [EST]
Last Update Date: 01/14/2020
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
JAMIE HEISSERER (R2DO)
- PART 21/50.55 REACTORS (EMAIL)
JAMIE HEISSERER (R2DO)
- PART 21/50.55 REACTORS (EMAIL)
PART 21 - INCORRECT TIP MATERIAL USED ON GAUGES
On December 27, 2019, United Controls International received a Product Advisory Letter from Ashcroft Inc. dated December 2, 2019 informing of a potential error in the tip material used on Ashcroft 2 « inch and 3 « inch model 1009, 63 mm model 2008, 63 mm and 100 mm model 1008 industrial gauges along with Weksler 3 « inch regal gauges. Due to a supplier issue, 304SS tip material may have been supplied on the subject gauges instead of the specified 316SS material. In certain applications the 304SS tip material may be subject to accelerated oxidation or degradation, resulting in potential release of process media. However, no detrimental effects are expected in non-corrosive applications.
Hatch and Farley have been identified as the affected plants and have been notified of this issue.
Please contact Wesley Hickle, Engineering Manager, at (770) 496-1406 ext. 165 or whickle@unitedcontrols.com for any questions.
On December 27, 2019, United Controls International received a Product Advisory Letter from Ashcroft Inc. dated December 2, 2019 informing of a potential error in the tip material used on Ashcroft 2 « inch and 3 « inch model 1009, 63 mm model 2008, 63 mm and 100 mm model 1008 industrial gauges along with Weksler 3 « inch regal gauges. Due to a supplier issue, 304SS tip material may have been supplied on the subject gauges instead of the specified 316SS material. In certain applications the 304SS tip material may be subject to accelerated oxidation or degradation, resulting in potential release of process media. However, no detrimental effects are expected in non-corrosive applications.
Hatch and Farley have been identified as the affected plants and have been notified of this issue.
Please contact Wesley Hickle, Engineering Manager, at (770) 496-1406 ext. 165 or whickle@unitedcontrols.com for any questions.