Event Notification Report for May 04, 2020

U.S. Nuclear Regulatory Commission Operations Center Event Reports For 5/1/2020 - 5/4/2020 ** EVENT NUMBERS **

 

54560

54679

54687

54688

54690

54691

54692

54693

Power Reactor	Event Number: 54560
Facility: PALO VERDE Region: 4     State: AZ Unit: [] [2] [] RX Type: [1] CE,[2] CE,[3] CE NRC Notified By: ANTON PESTKA HQ OPS Officer: JEFFREY WHITED	Notification Date: 03/04/2020 Notification Time: 02:07 [ET] Event Date: 03/03/2020 Event Time: 20:50 [MST] Last Update Date: 05/04/2020
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	Person (Organization): RICK DEESE (R4DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

2

A/R

Y

100

Power Operation

0

Hot Standby

Event Text

REACTOR TRIP DUE TO LOW STEAM GENERATOR LEVEL "At 2050 MST on March 3, 2020, Unit 2 reactor automatically tripped on Low Steam Generator (SG) Number 1 level signal from the Reactor Protection System. The low SG level occurred as the result of a trip of both Main Feedwater Pumps, which tripped during restoration of power to the Main Feedwater Pump Lube oil control panel. Auxiliary Feedwater (AFAS-1 and AFAS-2) actuated due to low SG levels in both SG post reactor trip as designed. This event is being reported as a reactor protection system and a specified system actuation in accordance with the reporting criteria of 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). "Following the reactor trip, all [control element assemblies] CEAs inserted fully into the core. All systems operated as expected. No emergency plan classification was required per the Emergency Plan. Safety related busses remained powered during the event from offsite power and the offsite power grid is stable. Unit 2 is stable and in Mode 3. Steam Generators are being fed via the class 1E powered motor driven auxiliary feedwater pump. "The NRC Senior Resident Inspector has been informed." Units 1 and 3 were unaffected by the trip and remain at 100 percent power. * * * UPDATE FROM ALLAN BRIEFE TO DONALD NORWOOD AT 1231 EDT ON 5/4/2020 * * * "The event reported on March 4, 2020 (EN 54560) also included actuations of the Emergency Diesel Generators in response to the AFAS-1 and AFAS-2 actuations. The Class 4.16kV buses remained energized from off-site power. "The NRC Senior Resident Inspector has been informed." Notified R4DO (Drake).

Agreement State	Event Number: 54679
Rep Org: PA BUREAU OF RADIATION PROTECTION Licensee: UNIVERSAL PRESSURE PUMPING, INC. Region: 1 City: CANTON   State: PA County: License #: PA-1446 Agreement: Y Docket: NRC Notified By: JOHN CHIPPO HQ OPS Officer: HOWIE CROUCH	Notification Date: 04/23/2020 Notification Time: 10:57 [ET] Event Date: 04/05/2020 Event Time: 00:00 [EDT] Last Update Date: 04/23/2020
Emergency Class: Non Emergency 10 CFR Section: Agreement State	Person (Organization): FRANK ARNER (R1DO) NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - STUCK SHUTTER ON BERTHOLD RADIOACTIVE GAUGE The following information was received from the Commonwealth of Pennsylvania via email: "On April 5, 2020, a technician reported to the [licensee radiation safety officer] RSO that when a shutter handle on a Berthold LB8010 with 20 mCi Cs-137 was moved to the closed position, the radiation survey indicated reduced radiation, but not the expected level. The shutter was opened and closed again, and radiation levels were lower but not at normal closed position levels. The gauge has been removed from service and is secured onsite in Canton, PA, awaiting a shipping container for return to the manufacturer. The gauge will be returned for repair or replacement. No personnel overexposure has occurred. "The Department [Pennsylvania Department of Environmental Protection] will perform a reactive inspection. More information will be provided upon receipt. Pennsylvania Report ID No.: PA200008

!!!!! 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	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
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	Person (Organization): 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

Event Text

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).

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	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
Emergency Class: Unusual Event 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)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

N

N

0

Cold Shutdown

0

Cold Shutdown

Event Text

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).

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	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
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	Person (Organization): 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

Event Text

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."

Power Reactor	Event Number: 54691
Facility: SUSQUEHANNA Region: 1     State: PA Unit: [1] [] [] RX Type: [1] GE-4,[2] GE-4 NRC Notified By: TOM RYDZEWSKI HQ OPS Officer: DONALD NORWOOD	Notification Date: 05/03/2020 Notification Time: 11:43 [ET] Event Date: 05/03/2020 Event Time: 08:21 [EDT] Last Update Date: 05/03/2020
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	Person (Organization): DAN SCHROEDER (R1DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

A/R

Y

76

Power Operation

0

Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM DUE TO MAIN TURBINE TRIP "At 0821 EDT on May 3, 2020, the Susquehanna Steam Electric Station Unit 1 reactor automatically scrammed due to a trip of the Main Turbine. "The Unit 1 reactor was operating at 76 percent reactor power following a ramp schedule to full power subsequent to a maintenance outage. The Control Room received indication of a Main Turbine trip with both divisions of the Reactor Protection System actuated and all control rods inserted. The Reactor Recirculation Pumps tripped on End of Cycle - Recirculation Pump Trip. Reactor water level lowered to -1 inch causing Level 3 (+13 inches) isolations. No Emergency Core Cooling System or Reactor Core Isolation Cooling actuations occurred. The operations crew subsequently maintained reactor water level at the normal operating band using Reactor Feed Water. No Steam Relief Valves opened. "The reactor is currently stable in Mode 3. Investigation into the trip of the Main Turbine is in progress. "The NRC Resident Inspector was notified. A voluntary notification to the Pennsylvania Emergency Management Agency and press release will occur. "This event requires a 4-hour Emergency Notification System (ENS) notification in accordance with 10 CFR 50.72(b)(2)(iv)(B) and an 8-hour ENS notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) and 10 CFR 50.72(b)(3)(iv)(B)."

Power Reactor	Event Number: 54692
Facility: NINE MILE POINT Region: 1     State: NY Unit: [1] [] [] RX Type: [1] GE-2,[2] GE-5 NRC Notified By: ALEX THOMAS HQ OPS Officer: DONALD NORWOOD	Notification Date: 05/03/2020 Notification Time: 22:28 [ET] Event Date: 05/03/2020 Event Time: 17:50 [EDT] Last Update Date: 05/03/2020
Emergency Class: Non Emergency 10 CFR Section: 50.72(b)(3)(v)(D) - Accident Mitigation	Person (Organization): DAN SCHROEDER (R1DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

N

Y

100

Power Operation

100

Power Operation

Event Text

MAIN CONTROL ROOM AIR TREATMENT SYSTEM INOPERABLE "On 5/3/2020 at 1100 EDT, Operations identified a step change in the Main Control Room ambient noise. The cause of the noise was a rise in vibrations on the Number 11 fan motor of the Main Control Room Ventilation Circulating Fan. Another step change in noise occurred and Operations swapped from the Number 11 fan motor to its redundant Number 12 fan motor, but the noise and vibrations did not improve. The two independent motors are connected to the blower shaft with belts on either end of the shaft. This entire fan and motor assembly is contained within the Main Control Room ventilation ducting and is not visible. At 1118 EDT, Operations shut off the Main Control Room Ventilation Circulating Fan due to Number 11 fan motor vibrations, declared the Main Control Room Air Treatment System inoperable, and entered the Technical Specification 3.4.5.e, 7-day action statement. "At 1750 EDT, Maintenance entered the ductwork and informed Operations that the Number 11 fan bearing had catastrophically failed and because of the extent of damage and close physical proximity to the Number 12 fan motor, jeopardized its continued operation. As a result, Operations also declared the Number 12 fan motor inoperable and determined the event was reportable as a loss of safety function per 10 CFR 50.72(b)(3)(v)(D)." The licensee notified the NRC Resident Inspector.

!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor	Event Number: 54693
Facility: LASALLE Region: 3     State: IL Unit: [] [2] [] RX Type: [1] GE-5,[2] GE-5 NRC Notified By: JOE MESSINA HQ OPS Officer: DONALD NORWOOD	Notification Date: 05/04/2020 Notification Time: 23:40 [ET] Event Date: 05/04/2020 Event Time: 16:40 [CDT] Last Update Date: 05/08/2020
Emergency Class: Non Emergency 10 CFR Section: 50.72(b)(3)(v)(D) - Accident Mitigation	Person (Organization): 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

100

Power Operation

Event Text

DIESEL GENERATOR COOLING WATER SYSTEM DECLARED INOPERABLE "This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to mitigate the Consequences of an Accident. A through wall leak was found on piping connected to the Division 3 Diesel Generator (DG) Cooling Water Strainer. This condition has been evaluated and the Division 3 DG Cooling Water System has been declared inoperable. The Division 3 DG Cooling Water System is a support system for the Division 3 Emergency DG and the High Pressure Core Spray System (HPCS). "The NRC Resident Inspector has been notified." * * * RETRACTION ON MAY 8, 2020 AT 1709 EDT FROM JOE MESSINA TO BRIAN LIN * * * "This update retracts Event Notification #54693, which reported a condition that could have potentially prevented fulfillment of a safety function needed to mitigate the consequences of an accident. "An evaluation of the flaw on the piping connected to the Unit 2 Division 3 Diesel Generator (DG) Cooling Water strainer concluded that the system would have remained operable. The High Pressure Core Spray system, supported by the operable DG Cooling Water system, remained operable and capable of performing its safety function. "The NRC Resident Inspector has been notified." Notified R3DO (Stone).