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Event Notification Report for June 06, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
6/5/2019 - 6/6/2019

** EVENT NUMBERS **


54069 54093 54102

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Power Reactor Event Number: 54069
Facility: CALLAWAY
Region: 4     State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JEFF GULICK
HQ OPS Officer: JOANNA BRIDGE
Notification Date: 05/17/2019
Notification Time: 03:35 [ET]
Event Date: 05/16/2019
Event Time: 23:03 [CDT]
Last Update Date: 06/05/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DAVID PROULX (R4DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R N 0 Startup 0 Hot Standby

Event Text



EN Revision Imported Date : 6/6/2019

EN Revision Text: REACTOR TRIP DUE TO SOURCE RANGE HI FLUX SIGNAL

"This is an 8-hour, non-emergency notification for a valid reactor trip signal with the reactor not critical, and a valid auxiliary feedwater system actuation in accordance with 10 CFR 50.72(b)(3)(iv)(A) - Valid System Actuation.

"At 2303 [CDT] on May 16, 2019, the plant was administratively in mode 2 due to withdrawing control rods for startup following refuel. The reactor had not been declared critical. The P-6 permissive at 10E-10 Amps was met for one of two Intermediate Range detectors allowing for block of the Source Range high flux trip (1E5CPS). Prior to performing the block, the Source Range high flux trip setpoint was exceeded and a reactor trip received. All systems responded as expected. A feedwater isolation signal was received due to the reactor trip with feedwater temperature less than 564 degrees Fahrenheit. Auxiliary feedwater was started to maintain steam generator levels. The plant is being maintained stable in mode 3 with no complications. The NRC Resident Inspector was present during the startup and was notified of the reactor trip."

* * * UPDATE FROM JONATHAN LAUF TO HOWIE CROUCH AT 1454 EDT ON 6/5/19 * * *

"A correction is being made for the sixth sentence in the second paragraph above, which states, 'A Feedwater Isolation signal was received due to the reactor trip with feedwater temperature less than 564 degrees Fahrenheit.' Within this sentence, 'feedwater temperature' is to be replaced with 'reactor coolant system temperature.'"

The licensee has notified the NRC Senior Resident Inspector.

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Agreement State Event Number: 54093
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: DESERT NDT LLC
Region: 4
City: ABILENE   State: TX
County:
License #: L06462
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JEFF HERRERA
Notification Date: 05/29/2019
Notification Time: 16:22 [ET]
Event Date: 05/29/2019
Event Time: 00:00 [CDT]
Last Update Date: 05/29/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JASON KOZAL (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - SOURCE DRIVE CABLE DISCONNECTED

The following report was received from the Texas Department of State Health Services via email:

"On May 29, 2019, the agency [Texas Department of State Health Services] was notified by the licensee's radiation safety officer (RSO) that one of their crews had suffered a source disconnect at a field site location. The exposure device being used was a QSA 880D device containing a 58.8 Curie Iridium - 192 source. The RSO stated two individuals approved for source retrieval, retrieved the source, and that no over exposures occurred due to the event. The RSO stated that during the retrieval it was found that the drive cable broke near the connector. The crank out device has been taken out of service and will be sent to the manufacturer for inspection. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident #: 9683

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Part 21 Event Number: 54102
Rep Org: ENGINE SYSTEMS, INC
Licensee: DRESSER-RAND
Region: 1
City: ROCKY MOUNT   State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAN ROBERTS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 06/05/2019
Notification Time: 16:39 [ET]
Event Date: 06/05/2019
Event Time: 00:00 [EDT]
Last Update Date: 06/05/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
RAY KELLAR (R4DO)
- PART 21/50.55 REACTORS (EMAIL)

Event Text

PART 21 INTERIM NOTIFICATION - FAILURE OF A SIGNAL CONVERTER SUPPLIED TO COOPER NUCLEAR PLANT

The following is a summary of the information received from Engine Systems, Inc. via facsimile:

ESI was notified on April 6, 2019 that a signal converter (also called a signal conditioner) that sends the Reactor Core Isolation Cooling turbine speed to the turbine controller had failed. The converter is at the manufacturer's facility undergoing testing at this time and they have been unable to complete their evaluation within 60-days. The evaluation is expected to be completed by July 31, 2019.

The converter was only supplied to Cooper Nuclear Plant.


Page Last Reviewed/Updated Thursday, June 06, 2019
Thursday, June 06, 2019