United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2019 > August 07

Event Notification Report for August 07, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
8/6/2019 - 8/7/2019

** EVENT NUMBERS **


53999 54186 54197 54203

To top of page
Power Reactor Event Number: 53999
Facility: SEQUOYAH
Region: 2     State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CAL ATCHLEY
HQ OPS Officer: BETHANY CECERE
Notification Date: 04/14/2019
Notification Time: 06:44 [ET]
Event Date: 04/14/2019
Event Time: 03:20 [EDT]
Last Update Date: 08/06/2019
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
Person (Organization):
NICOLE COOVERT (R2DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby

Event Text



EN Revision Imported Date : 8/7/2019

EN Revision Text: AUTOMATIC REACTOR TRIP DUE TO MAIN FEEDWATER PUMP TRIP

"At 0320 EDT, April 14, 2019, Sequoyah Unit 1 experienced an automatic reactor trip. The event was initiated by the trip of the 1A main feedwater pump. During the automatic unit runback, an automatic reactor trip was initiated due to low-low level in Steam Generator number 3.

"The Auxiliary Feedwater System (AFWS) automatically actuated as required when the expected post-trip feedwater isolation actuated. Reactor Coolant System temperature is being maintained by the AFWS and the steam dump system. During this operational cycle, one control Rod Position Indicator (RPI) for core position E-5 in shutdown bank 'A' has been inoperable, and the appropriate Condition and Required Actions of [Technical Specification Limiting Condition of Operation] 3.1.7 were complied with. Due to this inoperable RPI, the associated shutdown rod is conservatively assumed to be full out and untrippable. Consequently, boration was required to establish adequate shutdown margin. All other Control and Shutdown rods fully inserted. All safety systems responded as designed. No primary or secondary safety valves actuated during or after the reactor trip. The unit is currently stable in Mode 3. Unit 1 is in a normal shutdown electrical alignment.

"There was no impact on Unit 2.

"Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B) and in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the AFW system.

"There was no impact on the health and safety of the public or plant personnel.

"The NRC Senior Resident Inspector has been notified."

* * * UPDATE ON 8/6/19 AT 12:20 EDT FROM KEVIN MICHAEL TO KERBY SCALES * * *

The licensee provided an update to paragraph 2.

"The Auxiliary Feedwater System (AFWS) automatically actuated as required when the expected post-trip feedwater isolation actuated. Reactor Coolant System temperature is being maintained by the AFWS and the steam dump system. All Control and Shutdown rods fully inserted, except E-5 which was previously identified and conservatively assumed to be in a full out position. Applicable TS actions were performed to maintain shutdown margin. All safety systems responded as designed. No primary or secondary safety valves actuated during or after the reactor trip. The unit is currently stable in Mode 3. Unit 1 is in a normal shutdown electrical alignment."

Notified the R2DO (Gerald McCoy)

To top of page
Agreement State Event Number: 54186
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: BRANSCOME, INC DBA BRANSCOME RICHMOND
Region: 1
City: RICHMOND   State: VA
County:
License #: 760-352-1
Agreement: Y
Docket:
NRC Notified By: MICHAEL FULLER
HQ OPS Officer: ANDREW WAUGH
Notification Date: 07/30/2019
Notification Time: 13:24 [ET]
Event Date: 07/29/2019
Event Time: 21:25 [EDT]
Last Update Date: 07/30/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - DAMAGED GAUGE

The following is a synopsis of information received from the Commonwealth of Virginia via email:

On July 29, 2019, at approximately 2315 EDT, the Virginia Department of Health, Office of Radiological Health (Rad Health) was notified of a traffic accident involving a Troxler Gauge - model 4640B, Serial Number 2739, containing an 8 mCi Cs-137 source, source serial number 77-6508. At approximately 2125 EDT, a motorist entered a closed traffic lane and struck the gauge. Surveys by the Radiation Safety Officer (RSO) indicated that the source was likely not breached. The Rad Health Duty Officer advised the RSO that the gauge was safe to transport to the licensee's secured storage location.

On July 30, 2019, Rad Health's Radioactive Materials (Rad Materials) staff visited the licensee's facility and performed contamination surveys of the gauge and the Type A package. No contamination was detected on any of the swipe samples collected. The licensee and the Rad Materials staff contacted the Troxler service department to discuss next steps. The Troxler service representative explained that they could use the swipe samples to perform a leak test. The RSO was advised that once the source is confirmed not to be leaking by Troxler, the licensee may transport the damaged gauge for repair or replacement. The RSO was advised by Rad Material staff that the Type A package label will need to be changed to correct the transport index (TI) value from 0.2 to 0.5, and the shipping papers would also need to be changed to show the new TI.

Virginia Event Report ID: VA 19-005

To top of page
Power Reactor Event Number: 54197
Facility: CLINTON
Region: 3     State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAVID LIVINGSTON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/03/2019
Notification Time: 06:47 [ET]
Event Date: 08/03/2019
Event Time: 02:26 [CDT]
Last Update Date: 08/06/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
PATRICIA PELKE (R3DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 98 Power Operation 0 Hot Shutdown

Event Text



EN Revision Imported Date : 8/7/2019

EN Revision Text: AUTOMATIC REACTOR SCRAM ON LOW REACTOR WATER LEVEL

"At 0226 [CDT], an automatic scram on low reactor water level occurred due to a trip of the 'B' Reactor Feed pump. All control rods fully inserted. Reactor water level 2 was reached and the High Pressure Core Spray system, Reactor Core Isolation Cooling system, Division 3 diesel generator, Standby Gas Treatment Systems 'A' and 'B' and all shutdown safety related service water pumps started as expected. Reactor Core Isolation Cooling and High Pressure Core Spray injected as expected. All level 2 containment isolation signals occurred as expected and all level 2 containment valves closed as expected. Reactor water level is currently being controlled in band by condensate. Reactor pressure is being maintained by main turbine Bypass Valves.

"This event is being reported under 10 CFR 50.72(b)(2)(iv)(A), for ECCS discharge to RCS; 10 CFR 50.72(b)(2)(iv)(B), for RPS actuation, and 10 CFR 50.72(b)(3)(iv)(A), for specified system actuation.

"The NRC Senior Resident Inspector has been notified."

No safety relief valves lifted during the transient. The plant is in a normal shutdown electrical lineup with all safety equipment available. The licensee notified the Illinois Emergency Management Agency per their communications protocol.

* * * UPDATE FROM DAVID LIVINGSTON TO HOWIE CROUCH AT 0321 EDT ON 8/4/19 * * *

"Following automatic initiation of the High Pressure Core Spray (HPCS) System as described above, the HPCS System was manually secured following station procedures after verification that additional RPV [reactor pressure vessel] injection was no longer required. Securing HPCS injection in this manner prevents automatic restart of the system in the event of a subsequent low RPV level condition, rendering it inoperable. As the HPCS system is considered a single train safety system, this meets the reportability requirements of 10 CFR 50.72(b)(3)(v)(D). This reportable condition was identified following review of post-scram actions. The HPCS system has been restored to a Standby lineup."

The licensee will be notifying the NRC Resident Inspector.

Notified R3DO (Pelke).

* * * UPDATE FROM JAMES FORMAN TO KERBY SCALES AT 1545 EDT ON 8/6/19 * * *

"Following the scram, the Primary Containment to Secondary Containment and the Drywell to Primary Containment differential pressure limits were exceeded. Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.4, Primary Containment Pressure, and 3.6.5.4, Drywell Pressure, Actions A.1, B.1, and B.2 were entered. Primary Containment to Secondary Containment differential pressure and Drywell to Primary Containment differential pressure were restored to within the LCO limits at 1505 on 8/3/19 and the associated TS Actions were exited. This event is reportable under 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition that could have prevented the fulfillment of the primary containment function due to being outside the initial conditions to ensure that drywell and containment pressures remain within design values during a loss of coolant accident. This event is also reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of the drywell and primary containment functions to control the release of radioactive material for the same reason."

The licensee notified the NRC Resident Inspector.

Notified R3DO (Pelke).

To top of page
Power Reactor Event Number: 54203
Facility: PERRY
Region: 3     State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ED CONDO
HQ OPS Officer: ANDREW WAUGH
Notification Date: 08/06/2019
Notification Time: 17:29 [ET]
Event Date: 08/06/2019
Event Time: 13:35 [EDT]
Last Update Date: 08/06/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
PATRICIA PELKE (R3DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 65 Power Operation 65 Power Operation

Event Text

INOPERABLE INSTRUMENTATION AFFECTS SAFE SHUTDOWN CAPABILITY

"At 1335 EDT on 08/06/2019, it was discovered that reactor protection system (RPS) instrumentation functions for turbine stop valve closure and turbine control valve fast closure, end of cycle recirculation pump trip (EOC-RPT) instrumentation, and control rod block instrumentation were simultaneously inoperable due to a loss of feedwater heating; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v).

"RPS instrumentation, EOC-RPT instrumentation, and control rod block instrumentation functions were restored at 1422 EDT on 08/06/2019.

"There was no impact on the health and safety of the public or plant personnel.

"The NRC Senior Resident Inspector has been notified."


Page Last Reviewed/Updated Wednesday, August 07, 2019
Wednesday, August 07, 2019