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Current Event Notification Report for October 22, 2018
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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
10/19/2018 - 10/22/2018
** EVENT NUMBERS **
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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
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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
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
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Person (Organization):
OMAR LOPEZ (R2DO)
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| 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
EN Revision Imported Date : 10/22/2018
EN Revision 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). |
| Agreement State |
Event Number: 53659 |
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: BRASKEM AMERICA, INC.
Region: 4
City: FREEPORT State: TX
County:
License #: LL06443
Agreement: Y
Docket:
NRC Notified By: ROBERT FREE
HQ OPS Officer: KAREN COTTON
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Notification Date: 10/11/2018
Notification Time: 08:24 [ET]
Event Date: 10/10/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/11/2018
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Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
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Person (Organization):
HEATHER GEPFORD (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
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Event Text
AGREEMENT STATE REPORT- FIXED GAUGE SHUTTER BROKE
The following information was received from the State of Texas by email:
"On October 10, 2018, the Agency [Texas Department of State Health Services] was notified by the licensee that while performing a leak test of a Vega SH-F1 nuclear gauge the operating handle broke preventing manipulation of the shutter. The gauge contains a 100 milliCurie (original activity) cesium - 137 source. The gauge is located 160 ft. above ground level and does not present an exposure threat to workers. The manufacturer and a service contractor have been contacted to perform the repair of the gauge. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident: 9620 |
| Part 21 |
Event Number: 53673 |
Rep Org: ITT ENIDINE
Licensee: ITT ENIDINE
Region: 1
City: WESTMINSTER State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JEFFREY B GOTTHELF
HQ OPS Officer: OSSY FONT
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Notification Date: 10/19/2018
Notification Time: 08:40 [ET]
Event Date: 08/23/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/19/2018
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Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
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Person (Organization):
MATT YOUNG (R1DO)
GERALD MCCOY (R2DO)
DAVID HILLS (R3DO)
GREG PICK (R4DO)
PART 21 MATERIALS (EMAIL)
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Event Text
PART 21 REPORT - ENVIRONMENTAL QUALIFICATION TEST DISCREPANCY
The following report synopsis was received via fax from ITT Enidine:
On August 23, 2018, ITT Enidine discovered a discrepancy between the published specifications in sales literature, internal test acceptance procedures and the environmental qualification (EQ) test report for the ITT Conoflow model GT25 series. The current to pressure transducer EQ report 3419 lists the temperature range as -40 to 150 degrees Fahrenheit, and the linearity as 0.75 percent of span. The current temperature range specification is 0 to 150 degrees Fahrenheit, and the linearity is 1.5 percent of span. Units manufactured after October 2010 may not conform to the specifications of the EQ test report for linearity and temperature range.
Customers who procured safety related GT25 series I/P transducers and the specific part numbers since 2010 will be notified of this potential product defect by October 23, 2018.
ITT GT25 Series customer list (2010 to present):
- ALMARAZ: GT25CD1826
- ARIZONA PUBLIC SERVICE - GT25CA1826
- CALVERT CLIFFS NUCLEAR - GT25CD1826
- DUKE ENERGY (CATAWBA NUCLEAR STATION) - GT25CA1826; GT25CD1826
- CONTROL COMPONENTS INC - GT25CD1826
- ENERTECH - GT25CD1826
- ENRICO FERMI POWER - GT25CD1826
- FLOWSERVE - GT25CA1826
- TRACTABEL (VIA GEFRAN BENELUX) - GT25CA1826; GT25CD1826
- KHNP - GT25CA1826
- KOREA HYDRO - GT25CA1826
- KRSKO NUCLEAR PLANT - GT25CA1826
- NEBRASKA PUBLIC POWER - GT25CA1826
- ONTARIO POWER GENERATION - GT25CA1826
- SPX FLOW TECHNOLOGY (SPX MCKEAN) - GT25CA1826
- WEIR VALVES - GT25CA1826
- ERGYTECH - GT25CD1826
- OPPG FORT CALHOUN STATION - GT65FA1826
- BECHTEL POWER CORPORATION (TVA) - GT25CD1826; GT65CD1826 |
| Power Reactor |
Event Number: 53674 |
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: JUSTIN D. WILHELM
HQ OPS Officer: OSSY FONT
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Notification Date: 10/19/2018
Notification Time: 10:00 [ET]
Event Date: 10/19/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/19/2018
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
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Person (Organization):
DAVID HILLS (R3DO)
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| Unit |
SCRAM Code |
RX Crit |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
N |
N |
0 |
Cold Shutdown |
0 |
Cold Shutdown |
Event Text
LOW PRESSURE CORE INJECTION PUMPS INCAPABLE OF AUTOMATIC STARTUP
"On 10/19/2018, at approximately 0400 EDT, during an investigation into a failed surveillance test for a Loss of Offsite Power (LOP) coincident with a Loss of Coolant Accident (LOCA), it was identified that the Engineered Safety System Bus degraded voltage relay scheme contained a time delay setting that could inhibit all Low Pressure Core Injection (LPCI) pumps from automatically starting and operating during a LOP/LOCA, thus making LPCI incapable of meeting its functional requirement of automatic startup and operation regardless of the availability of offsite power supply (UFSAR Section 6.3.1.4 and Tech. Spec. Surveillance Requirement 3.8.1.17).
"The condition was identified during the first-time performance of a revised surveillance procedure for a LOP coincident with a LOCA signal. Fermi is currently in Mode 4 (Cold Shutdown) and LPCI auto start on a LOP/LOCA signal is not required. However, the initial investigation identified the condition likely existed in the past during modes of operation where LPCI auto start on LOP/LOCA was required. Investigation into the cause and corrective actions is ongoing.
"Since LPCI auto start is not required at the time of discovery (Mode 4), this event is being reported pursuant to 50.72(b)(3)(ii)(b).
"The NRC Resident Inspector has been notified." |
| Power Reactor |
Event Number: 53675 |
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: EDWARD CONDO
HQ OPS Officer: ANDREW WAUGH
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Notification Date: 10/19/2018
Notification Time: 12:04 [ET]
Event Date: 10/19/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/19/2018
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
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Person (Organization):
DAVID HILLS (R3DO)
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| 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
POSTULATED HOT-SHORT FIRE EVENT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT
"During extent of condition review of a previously identified fire induced hot-short (Ref. EN#53644) an unfused circuit associated with the 0M23C0002A, Miscellaneous Switchgear Recirculation Fan was discovered. This condition is not bounded by existing design and licensing documents.
"This results in an 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 the Appendix R Evaluation, Safe Shutdown Capabilities Report, due to an unfused circuit.
"Without overcurrent protection for this circuit, the potential exists that an initial fire event affecting this circuit could cause a short circuit 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 multiple fire zones in the control complex.
"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 Resident Inspector."
* * * UPDATE ON 10/19/2018 AT 1454 EDT FROM EDWARD CONDO TO ANDREW WAUGH * * *
"Further extent of condition reviews have discovered another unfused circuit. The circuitry is related to 0M24C001A, Battery Room Exhaust Fan. This condition is not bounded by existing design and licensing documents.
"This results in an 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 the Appendix R Evaluation, Safe Shutdown Capabilities Report, due to an unfused circuit.
"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."
Notified R3DO (Hills). |
| Power Reactor |
Event Number: 53676 |
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: TERRY BRANDT
HQ OPS Officer: ANDREW WAUGH
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Notification Date: 10/19/2018
Notification Time: 21:44 [ET]
Event Date: 10/19/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/19/2018
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
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Person (Organization):
DAVID HILLS (R3DO)
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| 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 TRIP DUE TO FEEDWATER REGULATING VALVE FAILING CLOSED
"At 1725 CDT, a Feedwater Regulating valve failed closed, resulting in a reactor level transient, which initiated a reactor trip, Primary Containment Isolation System signals to valves in Groups 2, 3, and 4 and initiation of High Pressure Coolant Injection and Reactor Core Isolation Cooling. All control rods inserted and level has been restored to normal. The cause of the feedwater valve failure is under investigation. All other systems responded as expected.
"This report is being made under 10 CFR 50.72 (b)(2)(iv)(B), (b)(3)(iv)(A) and (b)(2)(iv)(A).
"The Senior Resident Inspector has been informed."
Decay heat is being removed via the main condenser and reactor vessel water level is being maintained by the condensate and feedwater systems. |
| Power Reactor |
Event Number: 53677 |
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: DERICK DURHAM
HQ OPS Officer: JEFF HERRERA
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Notification Date: 10/20/2018
Notification Time: 01:13 [ET]
Event Date: 10/19/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/20/2018
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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
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Person (Organization):
GERALD MCCOY (R2DO)
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| Unit |
SCRAM Code |
RX Crit |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
M/R |
Y |
19 |
Power Operation |
0 |
Hot Standby |
Event Text
TURBINE STEAM SEAL HEADER PRESSURE MALFUNCTION
"On 10/19/18 at 2202 EDT, at 19 [percent] Reactor power, a malfunction of [the] Turbine Steam Seal Header pressure control caused a loss of Condenser vacuum, resulting in an automatic trip of the Main Turbine and a manual reactor trip (RPS Actuation). Just prior to the reactor trip, Emergency Feedwater was manually initiated to mitigate the potential loss of Main Feedwater. Condenser vacuum was recovered after the reactor trip and Main Feedwater remained in operation. Due to the RPS actuation while critical, this event is being reported as a 4-hour non-emergency per 10CFR50.72(b)(2). Also, due to the manual initiation of Emergency Feedwater, this event is also being reported as an 8-hour non-emergency per 10CFR50.72(b)(3).
"Following the reactor trip, all systems responded as expected with no complications. Emergency feedwater was secured at 2300. Unit 1 is in Mode 3 and stable, continuing to cooldown for a refueling outage."
The NRC Resident Inspector has been notified. |
| Power Reactor |
Event Number: 53678 |
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [] [] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TODD CHRISTENSEN
HQ OPS Officer: JEFF HERRERA
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Notification Date: 10/21/2018
Notification Time: 06:19 [ET]
Event Date: 10/21/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/21/2018
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
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Person (Organization):
GERALD MCCOY (R2DO)
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| Unit |
SCRAM Code |
RX Crit |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 3 |
N |
Y |
67 |
Power Operation |
67 |
Power Operation |
Event Text
TECHNICAL SPECIFICATION SHUT DOWN DUE TO CHEMISTRY LIMIT EXCEEDED
"At 0200 Central Daylight Time on 10/21/2018, Browns Ferry Nuclear Plant Unit 3 commenced a reactor shutdown as required by the Technical Requirements Manual Limiting Condition for Operation 3.4.1 Coolant Chemistry Condition D due to conductivity greater than 10 micro mho/cm at 25 degrees Celsius. The required action for this condition is to immediately initiate an orderly shutdown and be in Mode 4 as rapidly as cooldown rate permits. This event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i).
"There was no impact on the health and safety of the public or plant personnel. The NRC Senior Resident Inspector has been notified." |
| Power Reactor |
Event Number: 53680 |
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN ALEXANDER
HQ OPS Officer: ANDREW WAUGH
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Notification Date: 10/21/2018
Notification Time: 19:58 [ET]
Event Date: 10/21/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/21/2018
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
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Person (Organization):
GERALD MCCOY (R2DO)
BO PHAM (IRD)
CHRIS MILLER (NRR EO)
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| 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 |
80 |
Power Operation |
80 |
Power Operation |
Event Text
OFFSITE NOTIFICATION DUE TO DEATH OF EMPLOYEE ON SITE
"This notification is being made due to the death of an employee on-site. A Security Officer was found unresponsive on the Turbine Building Moisture Separator Re-heater deck on the Unit 1 side. Upon arrival of Fire Operations and on-site medical the individual had suffered an apparent heart attack. Hamilton County Emergency Medical Services will be transferring the individual to the medical examiner's office. The on-site NRC Senior Resident Inspector has been notified."
The licensee believes this event may receive media attention and a press release could be issued. |
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