Event Notification Report for May 01, 2020
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/30/2020 - 05/01/2020
EVENT NUMBERS
54688546905468754758
Power Reactor
Event Number: 54688
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: GEORGE SHEALY
HQ OPS Officer: DONALD NORWOOD
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: GEORGE SHEALY
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/01/2020
Notification Time: 13:16 [ET]
Event Date: 05/01/2020
Event Time: 12:53 [EDT]
Last Update Date: 05/01/2020
Notification Time: 13:16 [ET]
Event Date: 05/01/2020
Event Time: 12:53 [EDT]
Last Update Date: 05/01/2020
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):
MARK MILLER (R2DO)
LAURA DUDES (R2RA)
HO NIEH (NRR)
JEFFERY GRANT (IRD)
CHRIS MILLER (NRR EO)
MARK MILLER (R2DO)
LAURA DUDES (R2RA)
HO NIEH (NRR)
JEFFERY GRANT (IRD)
CHRIS MILLER (NRR EO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
NOTIFICATION OF UNUSUAL EVENT DUE TO FIRE IN NON-SAFETY RELATED ELECTRICAL SWITCHGEAR
At approximately 1238 EDT on May 1, 2020, an alarm indicated smoke on a non-safety related electrical switchgear bus in the turbine building. Plant personnel were dispatched to investigate. Smoke and heat were found coming from the bus. At 1253 EDT, a Notification of Unusual Event was declared. At 1308 EDT the fire was declared out and fire watches posted.
Offsite assistance was requested during the event and the Jenkinsville, SC fire department responded to the site. There were no plant personnel injuries or impact to the health and safety of the public.
The cause of this event is unknown at the present time. The electrical bus has been de-energized. The unit is currently in a planned refueling outage.
The licensee notified the NRC Resident Inspector.
Notified DHS SWO, FEMA Operations Center, CISA IOCC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
* * * UPDATE FROM GEORGE SHEALY TO DONALD NORWOOD AT 1754 EDT * * *
The Notification of Unusual Event was terminated at 1737 EDT on May 1, 2020. The cause of the event is currently being investigated.
The licensee will notify the NRC Resident Inspector.
Notified R2DO (Miller). NRR EO (Miller), IRD MOC (Grant). Additionally, notified DHS SWO, FEMA Operations Center, CISA IOCC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
At approximately 1238 EDT on May 1, 2020, an alarm indicated smoke on a non-safety related electrical switchgear bus in the turbine building. Plant personnel were dispatched to investigate. Smoke and heat were found coming from the bus. At 1253 EDT, a Notification of Unusual Event was declared. At 1308 EDT the fire was declared out and fire watches posted.
Offsite assistance was requested during the event and the Jenkinsville, SC fire department responded to the site. There were no plant personnel injuries or impact to the health and safety of the public.
The cause of this event is unknown at the present time. The electrical bus has been de-energized. The unit is currently in a planned refueling outage.
The licensee notified the NRC Resident Inspector.
Notified DHS SWO, FEMA Operations Center, CISA IOCC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
* * * UPDATE FROM GEORGE SHEALY TO DONALD NORWOOD AT 1754 EDT * * *
The Notification of Unusual Event was terminated at 1737 EDT on May 1, 2020. The cause of the event is currently being investigated.
The licensee will notify the NRC Resident Inspector.
Notified R2DO (Miller). NRR EO (Miller), IRD MOC (Grant). Additionally, notified DHS SWO, FEMA Operations Center, CISA IOCC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
Power Reactor
Event Number: 54690
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: RANDY KOUBA
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: RANDY KOUBA
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/01/2020
Notification Time: 15:34 [ET]
Event Date: 05/01/2020
Event Time: 08:31 [CDT]
Last Update Date: 05/01/2020
Notification Time: 15:34 [ET]
Event Date: 05/01/2020
Event Time: 08:31 [CDT]
Last Update Date: 05/01/2020
Emergency Class: Non Emergency
10 CFR Section:
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)(C) - Pot Uncntrl Rad Rel 50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
JAMES DRAKE (R4DO)
JAMES DRAKE (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
BOTH SECONDARY CONTAINMENT ACCESS DOORS OPEN SIMULTANEOUSLY
"At 0831 CDT, the Main Control Room received a 'Reactor Building 903 ft. Access Both Doors Open' alarm. Investigation found the interlock between the inner and outer doors did not prevent the opening of both doors while personnel were accessing the Reactor Building. The doors were immediately closed. Based on alarm times, both doors were open for less than one second. With both doors open, SR 3.6.4.1.3 was not met and Secondary Containment was declared inoperable. This unplanned Secondary Containment inoperability constitutes a condition reportable under 10 CFR 50.72(b)(3)(v)(c) and (d), 'An event or condition that at the time of discovery could have prevented the fulfillment of the safety function of SSCs that are needed to control the release of radioactive material and mitigate the consequences of an accident.'
"Secondary Containment was declared operable at 0836 CDT after independently verifying at least one Secondary Containment access door was closed.
"The NRC Senior Resident Inspector has been informed."
"At 0831 CDT, the Main Control Room received a 'Reactor Building 903 ft. Access Both Doors Open' alarm. Investigation found the interlock between the inner and outer doors did not prevent the opening of both doors while personnel were accessing the Reactor Building. The doors were immediately closed. Based on alarm times, both doors were open for less than one second. With both doors open, SR 3.6.4.1.3 was not met and Secondary Containment was declared inoperable. This unplanned Secondary Containment inoperability constitutes a condition reportable under 10 CFR 50.72(b)(3)(v)(c) and (d), 'An event or condition that at the time of discovery could have prevented the fulfillment of the safety function of SSCs that are needed to control the release of radioactive material and mitigate the consequences of an accident.'
"Secondary Containment was declared operable at 0836 CDT after independently verifying at least one Secondary Containment access door was closed.
"The NRC Senior Resident Inspector has been informed."
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 54687
Facility: COOK
Region: 3 State: MI
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RODNEY PICKARD
HQ OPS Officer: DONALD NORWOOD
Region: 3 State: MI
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RODNEY PICKARD
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/01/2020
Notification Time: 11:53 [ET]
Event Date: 05/01/2020
Event Time: 03:54 [EDT]
Last Update Date: 05/15/2020
Notification Time: 11:53 [ET]
Event Date: 05/01/2020
Event Time: 03:54 [EDT]
Last Update Date: 05/15/2020
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):
ANN MARIE STONE (R3DO)
ANN MARIE STONE (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 0 | Hot Standby |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAKAGE
"At 1000 EDT on May 1 2020, Operations commenced a shutdown of DC Cook Unit 2 to comply with LCO 3.4.13, Condition B Reactor Coolant System (RCS) pressure boundary leakage.
"At 0354 EDT on May 1, 2020, Operations detected an estimated 8 gpm Reactor Coolant System leak. The source of the leak could not be identified and Tech Spec 3.4.13, Condition A was entered for unidentified RCS leakage in excess of the 0.8 gpm limit.
"At 0745 EDT on May 1, 2020, Unit 2 entered LCO 3.4.13, Condition B when the 4-hour limit to complete the required actions of Condition A could not be met.
"At 0945 EDT on May 1, 2020, Unit 2 entered LCO 3.4.13, Condition B when the 4-hour limit to complete the required actions of Condition A could not be met.
"At 0945 EDT on May 1, 2020, inspections inside containment identified the leak as pressure boundary leakage from a pressurizer spray line which also requires entry into LCO 3.4.13, Condition B.
"At 1059 EDT on May 1, Unit 2 was tripped from 15 percent power. All systems functioned normally.
"This event is reportable under 10 CFR 50.72(b)(2)(i), the initiation of any nuclear plant shutdown required by the plant's Technical Specifications as a 4-hour report and under 10 CFR 50.72 (b)(3)(ii)(A), degraded condition, as an 8-hour report. The NRC Resident Inspector has been notified."
* * * PARTIAL RETRACTION ON 5/15/2020 AT 1442 EDT FROM BUD HINCKLEY TO THOMAS HERRITY * * *
"The condition identified in EN #54687, pursuant to 10 CFR 50.72 (b)(3)(ii)(a) has been evaluated, and has been determined not to be RCS pressure boundary leakage. As such, the 8-hour report is being retracted, as it is not an event or condition that results in, 'the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.'
"The leakage was subsequently determined to be from the tell-tale nipple of a pressurizer spray valve, not from the pressurizer spray line piping as previously reported. The Reactor Coolant Pressure Boundary (RCPB) is formed by the valve body, plug, seat, body to bonnet extension, and bonnet of the pressurizer spray valve. Therefore, the leakage is not RCPB leakage.
"There is no change to the 4-hour report made under 10 CFR 50.72(b)(2)(i), the initiation of any nuclear plant shutdown required by the plant's Technical Specifications.
"The NRC Resident Inspector was notified of this retraction."
Notified R3DO (Stone).
"At 1000 EDT on May 1 2020, Operations commenced a shutdown of DC Cook Unit 2 to comply with LCO 3.4.13, Condition B Reactor Coolant System (RCS) pressure boundary leakage.
"At 0354 EDT on May 1, 2020, Operations detected an estimated 8 gpm Reactor Coolant System leak. The source of the leak could not be identified and Tech Spec 3.4.13, Condition A was entered for unidentified RCS leakage in excess of the 0.8 gpm limit.
"At 0745 EDT on May 1, 2020, Unit 2 entered LCO 3.4.13, Condition B when the 4-hour limit to complete the required actions of Condition A could not be met.
"At 0945 EDT on May 1, 2020, Unit 2 entered LCO 3.4.13, Condition B when the 4-hour limit to complete the required actions of Condition A could not be met.
"At 0945 EDT on May 1, 2020, inspections inside containment identified the leak as pressure boundary leakage from a pressurizer spray line which also requires entry into LCO 3.4.13, Condition B.
"At 1059 EDT on May 1, Unit 2 was tripped from 15 percent power. All systems functioned normally.
"This event is reportable under 10 CFR 50.72(b)(2)(i), the initiation of any nuclear plant shutdown required by the plant's Technical Specifications as a 4-hour report and under 10 CFR 50.72 (b)(3)(ii)(A), degraded condition, as an 8-hour report. The NRC Resident Inspector has been notified."
* * * PARTIAL RETRACTION ON 5/15/2020 AT 1442 EDT FROM BUD HINCKLEY TO THOMAS HERRITY * * *
"The condition identified in EN #54687, pursuant to 10 CFR 50.72 (b)(3)(ii)(a) has been evaluated, and has been determined not to be RCS pressure boundary leakage. As such, the 8-hour report is being retracted, as it is not an event or condition that results in, 'the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.'
"The leakage was subsequently determined to be from the tell-tale nipple of a pressurizer spray valve, not from the pressurizer spray line piping as previously reported. The Reactor Coolant Pressure Boundary (RCPB) is formed by the valve body, plug, seat, body to bonnet extension, and bonnet of the pressurizer spray valve. Therefore, the leakage is not RCPB leakage.
"There is no change to the 4-hour report made under 10 CFR 50.72(b)(2)(i), the initiation of any nuclear plant shutdown required by the plant's Technical Specifications.
"The NRC Resident Inspector was notified of this retraction."
Notified R3DO (Stone).
Part 21
Event Number: 54758
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: Thomas Herrity
Licensee: United Controls International
Region: 1
City: Norcross State: GA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Rob Hale
HQ OPS Officer: Thomas Herrity
Notification Date: 06/29/2020
Notification Time: 12:04 [ET]
Event Date: 05/01/2020
Event Time: 00:00 [EDT]
Last Update Date: 06/29/2020
Notification Time: 12:04 [ET]
Event Date: 05/01/2020
Event Time: 00:00 [EDT]
Last Update Date: 06/29/2020
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):
DAVE WERKHEISER (R1DO)
- PART 21/50.55 REACTORS (EMAIL)
DAVE WERKHEISER (R1DO)
- PART 21/50.55 REACTORS (EMAIL)
PART 21 - ABB/THOMAS & BETTS/CYBEREX PRINTED CIRCUIT BOARD SHORTS TO GROUND WHEN INSTALLED IN HOST BATTERY CHARGER
The following is a summary of information received from United Controls International:
On May 1, 2020, Peach Bottom Atomic Power Station notified United Controls International (UCI) that a printed circuit board (PCB) in a station battery charger was shorting to ground. UCI has determined that an energized trace was too close to the mounting screw/washer causing the short. The trace was too close because the mounting holes were modified at the time of installation prior to commercial grade dedication. The modification was not documented. However, this modification was made to subsequent Time Delay Oscillator PCBs.
UCI has determined that in this application the energized trace is not used and can be removed from the board without affecting the function. The subject boards should be returned to UCI for this additional modification. UCI will remove the trace and inspect to ensure sufficient clearance exists.
The component is used in ABB/Thomas & Betts/Cyberex P/N: 93-41-119385. The subject board was supplied to Peach Bottom Generating Station in May, 2009.
CONTACT:
Wesley Hickle
Engineering Manager
whickle@unitedcontrols.com
770-496-1406 x 165
The following is a summary of information received from United Controls International:
On May 1, 2020, Peach Bottom Atomic Power Station notified United Controls International (UCI) that a printed circuit board (PCB) in a station battery charger was shorting to ground. UCI has determined that an energized trace was too close to the mounting screw/washer causing the short. The trace was too close because the mounting holes were modified at the time of installation prior to commercial grade dedication. The modification was not documented. However, this modification was made to subsequent Time Delay Oscillator PCBs.
UCI has determined that in this application the energized trace is not used and can be removed from the board without affecting the function. The subject boards should be returned to UCI for this additional modification. UCI will remove the trace and inspect to ensure sufficient clearance exists.
The component is used in ABB/Thomas & Betts/Cyberex P/N: 93-41-119385. The subject board was supplied to Peach Bottom Generating Station in May, 2009.
CONTACT:
Wesley Hickle
Engineering Manager
whickle@unitedcontrols.com
770-496-1406 x 165