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Event Notification Report for May 28, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
5/24/2019 - 5/28/2019

** EVENT NUMBERS **


53997 54067 54070 54083 54085 54087 54089 54090 54091 54092

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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53997
Facility: MONTICELLO
Region: 3     State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: SCOTT CHRISTOS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/13/2019
Notification Time: 02:04 [ET]
Event Date: 04/12/2019
Event Time: 18:15 [CDT]
Last Update Date: 05/24/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
STEVE ORTH (R3DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 25 Power Operation 25 Power Operation

Event Text



EN Revision Imported Date : 5/28/2019

EN Revision Text: HIGH ENERGY LINE BREAK DOOR FOUND IN INCORRECT POSITION RESULTING IN LPCI AND CORE SPRAY BEING INOPERABLE

"At approximately 1815 CDT on April 12, 2019, High Energy Line Break (HELB) Door-410A in the Reactor Building was discovered in the closed position. HELB Door-410B was previously closed for maintenance. Either Door-410A or Door-410B must be open to support the current HELB analyses. With both doors closed, this is considered an unanalyzed condition resulting in the loss of a post-HELB safe shutdown path.

"With Door-410A and Door-410B closed, LPCI [Low Pressure Coolant Injection] and Core Spray injection valves in both divisions are no longer considered available.

"This condition is being reported under 10 CFR 50.72(b)(3)(ii) as an unanalyzed condition that significantly degrades plant safety and 10 CFR 50.72(b)(3)(v) as an event or condition that could have prevented the fulfillment of a safety function.

"The condition was resolved at approximately 1845 CDT on April 12, 2019 when Door-410A was blocked open. The health and safety of the public was not affected by this condition.

"The NRC Resident has been notified."

* * * RETRACTION FROM JESSE TYGUM TO HOWIE CROUCH AT 1330 EDT ON 5/24/19 * * *

"Event Notification (EN) #53997, made on 4/13/2019, is being retracted. An engineering evaluation completed subsequent to this event analyzed the discovered condition with both Door-410A and Door-410B being closed. The engineering evaluation determined that the environmental conditions present with both Door-410A and Door-410B closed would not have impacted the availability of both divisions of the LPCI (Low Pressure Coolant Injection) and Core Spray injection valves nor would it have resulted in the loss of a post-HELB safe shutdown path. Therefore, this condition did not meet the criteria for an 8-hour notification per 10 CFR 50.72(b)(3)(ii) as an unanalyzed condition that significantly degrades plant safety or per 10 CFR 50.72(b)(3)(v)(D) as an event or condition that could have prevented the fulfillment of a safety function.

"The NRC Resident Inspector has been notified."

The licensee also notified the Minnesota State Duty Officer. Notified R3DO (Cameron).

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Non-Agreement State Event Number: 54067
Rep Org: ALL WEST TESTING & ENGINEERING
Licensee: ALL WEST TESTING & ENGINEERING
Region: 4
City: HAYDEN   State: ID
County:
License #: 112763701
Agreement: N
Docket:
NRC Notified By: CHANCE WOLFORD
HQ OPS Officer: JEFF HERRERA
Notification Date: 05/16/2019
Notification Time: 10:29 [ET]
Event Date: 05/15/2019
Event Time: 10:30 [MDT]
Last Update Date: 05/16/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
DAVID PROULX (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

NUCLEAR DENSITY GAUGE DAMAGED BY VEHICLE

At 1030 MDT, on 5/15/2019, a Troxler gauge was damaged by a vehicle driving at a high rate of speed through a job site in Middleton, ID. The gauge was damaged and the source and rod disconnected from the gauge base. The on site technician contacted the radiation safety officer who arrived on-site to investigate the incident. The gauge area was quarantined, the area surveyed and the damaged equipment was placed into a container and shipped back to the office while it awaits leak testing prior to returning the gauge to the vendor. The area surveyed after the gauge was removed indicated that there was no surface contamination. The licensee filed a police report and documented the issue.

The gauge was a Troxler model 3444
Serial Number: 35061
Isotopes: Cs-137, 8 milliCuries; Am-241, 40 milliCuries

The licensee contacted the Region IV office (VonEhr).

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Agreement State Event Number: 54070
Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: KENTUCKY TRANSPORTATION CABINET
Region: 1
City: FRANKFORT   State: KY
County:
License #: 201-086-51
Agreement: Y
Docket:
NRC Notified By: ANJAN BHATTACHARYYA
HQ OPS Officer: JOANNA BRIDGE
Notification Date: 05/17/2019
Notification Time: 08:06 [ET]
Event Date: 05/14/2019
Event Time: 16:20 [EDT]
Last Update Date: 05/17/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
DON JACKSON (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE - UNATTENDED GAUGE DAMAGED BY BULLDOZER

The following was received via e-mail:

"On May 14, 2019, at approximately 1620 [EDT] Kentucky Transportation Cabinet, (KY RML# 201-086-51) reported that a Humboldt 5001 EZ, serial number 3133 moisture density gauge had been severely damaged and partially buried by a bulldozer, at a road construction project in Madison County located near Richmond KY. The gauge contained 0.37 GigaBq (10 milliCi) Cesium-137 (serial number 8273GQ) and 1.48 GigaBq (40 milliCi) Americium-24:Beryllium (serial number NJ03357). The technician had been taking some readings, while waiting for more rock to be put in place and put the device in safety mode and set it on top of pile of Dense Graded Aggregate. He then walked over about 80 feet to talk to an operator when it was run over by a bulldozer. KY Radiation Health Branch personnel were on the scene at approximately 1800 [EDT] and determined that the top of the source rod had been broken off and the outer case of the gauge was cracked. There was no leakage detected and the survey of the broken case showed readings = 10mR/hr on contact indicating that the shielding had not been compromised. The area was taped off in a 30 foot circle surrounding the damaged device till it was recovered by the Fayette County HAZMAT Team and placed into a 55 gallon drum, sealed and removed to a storage facility. The Radiation Safety Office indicated that a final decision on the disposition of the gauge will be forthcoming, and that retraining of the employee would be a priority, to include emphasis on surveillance and situational awareness at jobsites."

KY Event No.: KY190005

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Power Reactor Event Number: 54083
Facility: LIMERICK
Region: 1     State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RICHARD WAGNER
HQ OPS Officer: JEFFREY WHITED
Notification Date: 05/24/2019
Notification Time: 09:51 [ET]
Event Date: 04/18/2019
Event Time: 02:49 [EDT]
Last Update Date: 05/24/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
FRANK ARNER (R1DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling

Event Text

INVALID ACTUATION OF A UNIT 2 CONTAINMENT ISOLATION LOGIC DUE TO A BLOWN FUSE

"This 60-Day telephone notification is being made per the reporting requirements specified in 10 CFR 50.73(a)(2)(iv)(A) to describe an invalid actuation of Limerick Generating Station Unit 2 containment isolation logic.

"On April 18, 2019, while performing a relay replacement on the Division 2/4 Main Steam Line logic, a partial containment isolation occurred due to a blown fuse.

"The following systems had components that actuated due to the partial isolation:
Reactor Water Clean-Up System
Primary Containment Instrument Gas System
Drywell Chilled Water System
Reactor Enclosure Cooling Water System
Core Spray System

"The Residual Heat Removal System received an isolation signal; however, the system remained in service because the isolation was defeated in accordance with plant procedures.

"This event resulted in partial Group 2A, 3, 7A, 8A, and 8B isolations. The systems successfully functioned per the plant design and plant configuration."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 54085
Facility: PERRY
Region: 3     State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAVID DUESING
HQ OPS Officer: CATY NOLAN
Notification Date: 05/24/2019
Notification Time: 13:09 [ET]
Event Date: 05/24/2019
Event Time: 07:30 [EDT]
Last Update Date: 05/24/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JAMNES CAMERON (R3DO)
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

LOW PRESSURE CORE SPRAY INOPERABLE

"At 0730 [EDT] on May 24, 2019, it was discovered that the Low-Pressure Core Spray System was inoperable. At Perry, the Low-Pressure Core Spray system is considered a single train system in Modes 1, 2, and 3; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v). Inoperability of the Low-Pressure Core Spray system was caused by Emergency Service Water Pump A inoperability.

"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 54087
Facility: WOLF CREEK
Region: 4     State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: CATY NOLAN
Notification Date: 05/24/2019
Notification Time: 17:12 [ET]
Event Date: 05/24/2019
Event Time: 13:10 [CDT]
Last Update Date: 05/24/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
HEATHER GEPFORD (R4DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 97 Power Operation

Event Text

LOSS OF OFFSITE POWER DUE TO FIRE ON STARTUP TRANSFORMER

"At 1310 CDT on 5/24/2019, Wolf Creek experienced a loss of offsite power to the safety-related NB02 bus, due to an external fire on a bushing on the startup transformer. The NB02 bus was reenergized when the 'B' Emergency Diesel Generator started and the output breaker automatically closed. The shutdown sequencer automatically started equipment as expected.

"Due to the undervoltage condition on the NB02 bus, an AFAS-T [Auxiliary Feedwater Actuation Signal] signal was generated which started the turbine driven auxiliary feedwater pump. Turbine load was reduced to maintain reactor power less than 100% in response to the start of turbine driven and 'B' motor driven auxiliary feedwater pumps.

"The fire was extinguished using a fire extinguisher at 1320 CDT.

"The unit is stable at 97% power."

The NB02 bus remains on the 'B' Emergency Diesel Generator (EDG). The other EDG is operable in standby.

The NRC Resident Inspector was notified.

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Power Reactor Event Number: 54089
Facility: NINE MILE POINT
Region: 1     State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: KENNETH NOEL
HQ OPS Officer: DAN LIVERMORE
Notification Date: 05/25/2019
Notification Time: 00:30 [ET]
Event Date: 05/24/2019
Event Time: 20:19 [EDT]
Last Update Date: 05/25/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
FRANK ARNER (R1DO)
FFD GROUP (EMAIL)
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

LICENSED EMPLOYEE FAILED A RANDOM FITNESS -FOR-DUTY TEST

"A licensed employee was determined to be under the influence of alcohol during a random [fitness-for-duty] test. The employee's access to the plant has been canceled."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 54090
Facility: BRAIDWOOD
Region: 3     State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MARK TUBERGEN
HQ OPS Officer: ANDREW WAUGH
Notification Date: 05/26/2019
Notification Time: 01:58 [ET]
Event Date: 05/25/2019
Event Time: 19:30 [CDT]
Last Update Date: 05/26/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMNES CAMERON (R3DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF MAIN CONTROL ROOM AREA RADIATION MONITORS

"At 1930 [CDT] on 5/25/2019, communications were lost with the main control room area radiation monitors. These detectors are used to determine if an emergency action level (EAL) has been reached for initiating condition RA3 (Radiation levels that impede access to equipment necessary for normal plant operations, cooldown, or shutdown).

"This unplanned loss of the ability to evaluate an EAL for initiating condition RA3 is considered a loss of emergency classification capability and is reportable as a Major Loss of Emergency Preparedness Capabilities per 10 CFR 50.72(b)(3)(xiii). This is an 8-hour reportable notification.

"Portable area radiation monitors have been established as a compensatory measure per station procedures.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 54091
Facility: ARKANSAS NUCLEAR
Region: 4     State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: MICHAEL STROBEL
HQ OPS Officer: DAN LIVERMORE
Notification Date: 05/26/2019
Notification Time: 09:25 [ET]
Event Date: 05/26/2019
Event Time: 05:12 [CDT]
Last Update Date: 05/26/2019
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):
HEATHER GEPFORD (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

AUTOMATIC REACTOR TRIP DUE TO A REACTOR COOLANT PUMP TRIP ON GROUND FAULT

"This is a 4-hour Non-Emergency 10 CFR 50.72(b)(2)(iv)(B) notification due to a Plant Protection System (PPS) actuation. Arkansas Nuclear One, Unit 2, automatically tripped from 100 percent power at 0512 CDT. The reactor automatically tripped due to 2P-32B Reactor Coolant Pump tripping as a result of grounding.

"No additional equipment issues were noted. All control rods fully inserted. Emergency Feedwater (EFW) actuated and was utilized to maintain Steam Generator (SG) levels. The EFW actuation meets the 8-hour Non-Emergency Immediate Notification Criteria of 10 CFR 50.72(b)(3)(iv)(A). No Primary safety valves lifted. Main Steam Safety Valves (MSSVs) did lift initially after the trip.

"The NRC Resident Inspector has been notified.

"Decay heat is being removed via the steam dump valves to the main condenser. Unit 2 is in a normal shutdown electrical lineup. Unit 1 was not affected by the transient on Unit 2. The licensee notified the State of Arkansas."

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Power Reactor Event Number: 54092
Facility: FERMI
Region: 3     State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: KELLEY BELENKY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/27/2019
Notification Time: 11:53 [ET]
Event Date: 05/27/2019
Event Time: 09:40 [EDT]
Last Update Date: 05/27/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMNES CAMERON (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

ONSITE SPILL OF CHEMICAL TOILET

"On May 27, 2019 at 0940 EDT, a portable chemical toilet was found tipped over. Approximately one gallon of contents spilled to the gravel only and did not reach any waterways or storm drains. Cleanup efforts are in progress. A notification to the Michigan Department of Environmental Quality and local health department is required, as well as a press release.

"This event is being reported pursuant to 10 CFR 50.72(b)(2)(xi)."

The licensee has notified the NRC Resident Inspector.


Page Last Reviewed/Updated Tuesday, May 28, 2019
Tuesday, May 28, 2019