Event Notification Report for May 05, 2020

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
5/4/2020 - 5/5/2020

** EVENT NUMBERS **

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

A/R

100

Power Operation

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: 54682
Rep Org: VIRGINIA RAD MATERIALS PROGRAM Licensee: DUPONT SPECIALTY PRODUCTS USA, LLC Region: 1 City: RICHMOND State: VA County: License #: 041-313-1 Agreement: Y Docket: NRC Notified By: ASFAW FENTA HQ OPS Officer: JEFFREY WHITED	Notification Date: 04/27/2020 Notification Time: 09:50 [ET] Event Date: 04/24/2020 Event Time: 00:00 [EDT] Last Update Date: 04/27/2020
Emergency Class: Non Emergency 10 CFR Section: Agreement State	Person (Organization): DAN SCHROEDER (R1DO) NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - FIXED GAUGE SHUTTER TEST FAILURE

The following was received from the Commonwealth of Virginia via email:

"On April 24, 2020, a licensee reported that the shutter of a fixed gauge used to measure the level of material inside a process vessel was stuck in the open position. This incident was identified on April 24, 2020, during the biennial leak testing of the source. The gauge is a Ronan Engineering Company, device (Model SA-1, serial number SO-VA-7063), and Source (Model SA1-F37, serial number M7451), containing 40 mCi of Cs-137. The report indicated that the impacted site personnel were notified immediately and barriers were erected to prevent access to the gauge area. Based on the report, there was no public exposure or environmental release from this event. The licensee has contacted the manufacturer (Ronan Engineering Company) for further investigation and to fix the problem.

"The Virginia Office of Radiological Health will review the licensee's written report and determine if additional actions are needed to be taken."

!!!!! 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

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).

Page Last Reviewed/Updated Thursday, March 25, 2021