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Event Notification Report for October 05, 2018

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/4/2018 - 10/5/2018

** EVENT NUMBERS **


53624 53637 53643 53644 53646 53647 53648

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Fuel Cycle Facility Event Number: 53624
Facility: NUCLEAR FUEL SERVICES INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
Region: 2
City: ERWIN   State: TN
County: UNICOI
License #: SNM-124
Docket: 07000143
NRC Notified By: KENNETH GREER
HQ OPS Officer: OSSY FONT
Notification Date: 09/26/2018
Notification Time: 16:29 [ET]
Event Date: 09/26/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/26/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
NICOLE COOVERT (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
FFD GROUP (EMAIL)
FUELS OUO (EMAIL)

Event Text

FITNESS FOR DUTY - DISCOVERY OF KOMBUCHA TEA INSIDE THE PROTECTED AREA

"An unopened (sealed) container of Herbal Tea (Kombucha) was found in a refrigerator located within a common office break area inside the protected area. Kombucha Tea is a fermented tea, which contains at least 0.5 percent alcohol by volume. Alcohol is a prohibited item per the requirements of 10 CFR Part 26.719(1).

"The incident was entered into the NFS corrective action program and an investigation is in progress

"The licensee notified the NRC Resident Inspector."

NFS Event (PIRCS) Number: 67184.

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Fuel Cycle Facility Event Number: 53637
Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
LEU FABRICATION
LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON   State: NC
County: NEW HANOVER
License #: SNM-1097
Docket: 07001113
NRC Notified By: SCOTT MURRAY
HQ OPS Officer: BETHANY CECERE
Notification Date: 10/02/2018
Notification Time: 14:38 [ET]
Event Date: 10/01/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/04/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (c) - OFFSITE NOTIFICATION/NEWS REL
Person (Organization):
OMAR LOPEZ (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

CONCURRENT NOTIFICATION

"At approximately 1525 [EDT] on October 1st, 2018, Fire Riser 318 which serves both non-contaminated and contaminated areas in [Fuel Manufacturing Operations] (FMO), was taken out of service due to a pin hole leak in the pipe. Water was contained and surveys were completed to ensure no contamination was released into non-contaminated areas. The New Hanover County Deputy Fire Marshall was notified at 1655 [EDT] on October 1st, 2018, per State code requirements. An hourly fire watch was implemented for surveillance of the affected areas. Because the New Hanover County Deputy Fire Marshall was notified, a concurrent notification to the NRC Operations Center is being made per 10 CFR 70, Appendix A(c)."

The licensee will notify NRC Region 2 and the State of North Carolina Radiation Protection Section.

* * * UPDATE ON 10/4/18 AT 1335 EDT FROM PHILLIP TO OLLIS * * *

"The leaking sprinkler pipe fitting was replaced this morning and the system was restored to service at approximately 11 AM, 10/4/18. The NHC [New Hanover County] Deputy Fire Marshal was notified via telephone of the return to service at 11:50 AM, 10/4/18."

Notified the R2DO (Lopez), NMSS Events Notification via email.

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Power Reactor Event Number: 53643
Facility: VOGTLE
Region: 2     State: GA
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KEVIN LOWE
HQ OPS Officer: VINCE KLCO
Notification Date: 10/04/2018
Notification Time: 07:57 [ET]
Event Date: 10/04/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/19/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
OMAR LOPEZ (R2DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 0 Startup 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DURING LOW POWER PHYSICS TESTING

"At 0544 EDT on October 4, 2018, with Unit 1 in Mode 2 with reactor power in the intermediate range performing low power physics testing, the reactor was manually tripped due to a rod control urgent failure alarm. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam system.

"Unit 2 was not affected.

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

"The NRC Resident Inspectors have been notified.

"All control rods inserted as expected. The cause of the rod control urgent failure is being investigated."


* * * UPDATE FROM KEVIN LOWE TO DONALD NORWOOD AT 1408 EDT ON 10/19/2018 * * *

"This Event Notification is being updated to clarify that the reactor was not critical when this event occurred. Therefore, the reporting requirement is changed from 10 CFR 50.72(b)(2)(iv)(B) to 10 CFR 50.72 (b)(3)(iv)(A).

"During Dynamic Rod Worth Measurement testing, Control Bank Charlie was inserted approximately 153 steps when the urgent failure occurred (CBC positioned at 75 steps out). Following the scram, additional analysis concluded that the reactor was subcritical when the Reactor Protection System was actuated."

The licensee notified the NRC Resident Inspector.

Notified the R2DO (McCoy).

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Power Reactor Event Number: 53644
Facility: PERRY
Region: 3     State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ALEX HALLMARK
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/04/2018
Notification Time: 12:29 [ET]
Event Date: 10/04/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/04/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
STEVE ORTH (R3DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 96 Power Operation 96 Power Operation

Event Text

POSTULATED HOT SHORT FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT

"Degraded or unanalyzed condition due to the possibility for a postulated fire induced hot short to cause a secondary fire in a different fire area, which would be outside the boundaries analyzed for safe shutdown in calculation SSC-001 due to an unfused circuit associated with the 1M43C0001A, Diesel Generator Building Ventilation Fan. This condition is not bounded by existing design and licensing documents.

"Without overcurrent protection for this circuit, the potential exists that an initial fire event affecting this circuit could cause a short circuit without protection that would cause excessive current through the circuit beyond the capacity rating of the conductors. This could lead to a secondary fire in another plant area where this circuit is routed challenging the ability to achieve and maintain safe shutdown.

"The postulated event would affect the following fire zones: 1CC-3c (Unit 1, Division 1 4160V and 480V Switchgear Room, 620 feet 6 inch elevation), 1CC-3e (Unit 1 West Corridor North of Elevator, 620 feet 6 inch elevation), DG-1d (Hallway Diesel Generator Building 620 feet 6 inch elevation), and 1DG-1c (Unit 1, Division 1 Diesel Generator Building 620 feet 6 inch elevation).

"This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B). Interim compensatory measures (i.e., fire watches) have been implemented for affected areas of the plant.

"The licensee has notified the NRC Senior Resident Inspector."

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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53646
Facility: COOPER
Region: 4     State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: TERRELL HIGGINS
HQ OPS Officer: VINCE KLCO
Notification Date: 10/05/2018
Notification Time: 09:52 [ET]
Event Date: 10/05/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/24/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling

Event Text

MAIN STEAM ISOLATION VALVES EXCEEDED PRIMARY CONTAINMENT LOCAL LEAK RATE ACCEPTANCE CRITERIA

"At 0520 (CDT), on October 05, 2018, it was discovered that a Primary Containment local leak rate test performed on Main Steam Isolation Valves (MSIV) exceeded its acceptance criteria.

"During Mode 1, 2, and 3, Surveillance Requirement 3.6.1.3.10 requires MSIV leakage for a single MSIV line to be less than or equal to 106 standard cubic feet per hour (scfh) when tested at 29 psig and Surveillance Requirement 3.6.1.3.12 requires the combined leakage rate for all MSIV leakage paths to be less than or equal to 212 scfh when tested at 29 psig.

"As-found for the 'C' MSIV line leakage results were unquantifiable and gave a [minimum] path value greeter than 160 scfh. This leakage rate lead to Surveillance Requirement 3.6.1.3.10 and 3.6.1.3.12 limits to be exceeded. This event is being reported as a condition of the nuclear power plant, including its principal safety barriers, being seriously degraded per 10 CFR 50.72(b)(3)(ii)(A) since the Primary Containment Isolation Valves leakage limits for MSIVs were exceeded.

"The NRC Resident Inspector has been notified."

* * * RETRACTION AT 2320 EDT ON 10/24/2018 FROM THOMAS FORLAND TO MARK ABRAMOVITZ * * *

"CNS [Cooper Nuclear Station] is retracting the 8-hour non-emergency notification made on October 5, 2018 at 0520 CDT (EN# 53646). Subsequent evaluation concluded that overall as-found 'C' MSIV leakage rate was not at a level that exceeded the surveillance requirement 3.6.1.3.10 and 3.6.1.3.12 limits and thus the Primary Containment Isolation Valve leakage rate limits for the MSIVs were not exceeded.

"The NRC Senior Resident Inspector has been notified."

Notified the R4DO (Drake).

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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53647
Facility: WOLF CREEK
Region: 4     State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: MARCY BLOW
HQ OPS Officer: ANDREW WAUGH
Notification Date: 10/05/2018
Notification Time: 09:59 [ET]
Event Date: 10/05/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/18/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
THOMAS FARNHOLTZ (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

UNPLANNED LOSS OF THE ASSESSMENT CAPABILITY DUE TO TECHNICAL SUPPORT DIESEL

"At 05:52 CDT on 10/5/2018, the [Wolf Creek Nuclear Operating Corporation] (WCNOC) Technical Support Center (TSC) Diesel fuel oil transfer pump would not run. There was ongoing modification to the facility Halon system at the time. The modification process had included a jumper to the fuel oil transfer pump to allow it to continue to be available. This issue was discovered during testing as the modification was progressing. The pump was verified to function on 10/4/2018 by normal operations rounds.

"If an emergency is declared requiring the TSC activation during the time the TSC diesel is non-functional, the TSC will be staffed and activated using existing emergency planning procedure. If offsite power is lost, the TSC will relocate to the Alternate TSC using existing emergency planning procedures.

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

"The NRC Resident Inspector has been notified."

* * * RETRACTION ON 10/18/2018 AT 1306 EDT FROM MARCY BLOW TO ANDREW WAUGH * * *

"Event Notification (EN) 53647, made on October 8, 2018, is being retracted because during the time that the TSC Diesel fuel oil transfer pump was not available, normal power was continuously available. The Alternative TSC was also available.

"Consequently, the condition did not meet the criteria for a 8-hour notification per 10 CFR 50.72(b)(3)(xiii) for any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system).

"The NRC Resident Inspector has been notified of the Event Notification retraction."

Notified R4DO (Pick).

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Power Reactor Event Number: 53648
Facility: PILGRIM
Region: 1     State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: KENNETH KNELL
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/05/2018
Notification Time: 15:39 [ET]
Event Date: 10/05/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/05/2018
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):
JON LILLIENDAHL (R1DO)
WILLIAM GOTT (IRD)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM DUE TO LOW REACTOR WATER LEVEL

"On Friday, October 5, 2018 at 1209 hours, with the reactor at 100 percent core thermal power, Pilgrim Nuclear Power Station (PNPS) automatically tripped due to reactor water level perturbation and receipt of a low reactor water level Reactor Protection System (RPS) signal. The cause of the low reactor water level is under investigation. The plant is in hot shutdown.

"All other plant systems responded as designed. Pressure is being controlled using the Mechanical Hydraulic Control System and Main Condenser. Reactor water level is being maintained with the feedwater and condensate system.

"During the automatic reactor scram the plant experienced the following isolation signals as designed:
Group 2 Isolation: Miscellaneous containment isolation valves
Group 6 Isolation: Reactor Water Clean-up
Reactor Building Isolation System Actuation

"Due to the RPS actuation while critical, this event is being reported as a four-hour, non-emergency notification in accordance with 10 CFR 50.72(b)(2)(iv)(B), 'any event that results in actuation of the reactor protection system (RPS) when the reactor is critical.' This notification is also being made in accordance with 10 CFR 50.72(b)(3)(iv)(A), 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of this section ... ' (B)(2) 'General containment isolation signals affecting containment isolation valves in more than one system.'

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

The licensee will notify the Massachusetts Emergency Management Agency.


Page Last Reviewed/Updated Friday, May 03, 2019
Friday, May 03, 2019