United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2017 > November 8

Event Notification Report for November 8, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/07/2017 - 11/08/2017

** EVENT NUMBERS **


53045 53047 53056 53057 53058 53059 53060

To top of page
Agreement State Event Number: 53045
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: KRAZAN & ASSOCIATES, INC.
Region: 4
City: MODESTO State: CA
County:
License #: 4247-10
Agreement: Y
Docket:
NRC Notified By: K. ARUNIKA HEWADIKARAM
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/30/2017
Notification Time: 19:25 [ET]
Event Date: 10/30/2017
Event Time: [PDT]
Last Update Date: 10/30/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GREG WERNER (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
ILTAB (EMAI)
CNSNS (MEXICO) (EMAI)

This material event contains a "Less than Cat 3 " level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST TROXLER MOISTURE DENSITY GAUGE

The following information was received from the State of California via email:

"On 10/30/17, California Office of Emergency Services contacted RHB [Radiologic Health Branch] to report a lost moisture density gauge. The lost gauge is a Troxler Model 3440, S/N 23171, containing 9 mCi of Cs-137 and 44 mCi of Am241/Be. According to the RSO [Radiation Safety Officer], the gauge user left the gauge on the tailgate of his truck without properly securing it, and drove off to the next job site. A passing driver alerted the gauge user of a falling object from his truck at the intersection of Floyd Street and Oakdale Street in Modesto, CA. The user immediately went back to the intersection, but was unable to locate the gauge. The RSO has notified the Modesto Police Department of this incident. He will be posting a reward for the safe return of the gauge on Craigslist. The RHB will be following up on this investigation.

"5010 Number: 103017"

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

To top of page
Agreement State Event Number: 53047
Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: EASTMAN KODAK COMPANY
Region: 1
City: ROCHESTER State: NY
County:
License #: C1347
Agreement: Y
Docket:
NRC Notified By: DANIEL SAMSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/31/2017
Notification Time: 15:36 [ET]
Event Date: 09/22/2017
Event Time: [EDT]
Last Update Date: 10/31/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY MCKINLEY (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - FAILED SEALED SOURCE LEAK TEST

The following information was received from the State of New York via fax:

"On October 10, 2017 Eastman Kodak Company reported that the results of a leak test showed 0.006 micro curies of removable contamination. The source that was surveyed is an NRD Model A2003, s/n 2977, static elimination device that contains 18.25 mCi of Am-241. The leak test was collected on September 22 and sent to an outside lab for analysis on September 25. The results of the survey were reported on October 9.

"Eastman Kodak will suspend the use of the source until the results of a retest are available. Surfaces adjacent to the device will be surveyed to determine if contamination spread.

"Event Report ID No.: NYDOH-17-10"

To top of page
Power Reactor Event Number: 53056
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: ROB KLINDWORTH
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/07/2017
Notification Time: 08:29 [ET]
Event Date: 11/07/2017
Event Time: 05:04 [EST]
Last Update Date: 11/07/2017
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):
BILL COOK (R1DO)

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

UNIT 1 AUTOMATIC REACTOR TRIP DUE TO MAIN UNIT GENERATOR OVER CURRENT

"On November 7, at 0504 [EST], BVPS [Beaver Valley Power Station] Unit 1 experienced an automatic reactor trip due to Main Unit Generator over current. The Auxiliary Feedwater system activated and remains in service. Offsite power supply is available. Normal and Emergency busses are being supplied by Offsite power. One Source Range channel failed to energize due to its corresponding Intermediate Range instrument being under compensated. It was manually energized and is not indicating as expected. The second Source Range instrument energized but is reading erratically. Both Source Range instruments have been declared inoperable and the appropriate Technical Specification has been complied with by making the Control Rods not capable of withdrawal and isolating all dilution flow paths. Plant trip response was as expected without complications, and all control rods fully inserted in the core. The plant is currently stable in Mode 3.

"This event is being reported as an actuation of the Reactor Protection system 10 CFR 50.72(b)(2)(iv)(B) and a Specified System Actuation (Auxiliary Feedwater System) 10 CFR 50.72(b)(3)(iv)(A).

"BVPS Unit 2 is unaffected by this event and remains at 100% power in Mode 1.

"The NRC Resident Inspector has been notified."

To top of page
Power Reactor Event Number: 53057
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [ ] [ ]
RX Type: [3] CE
NRC Notified By: MATTHEW NAYLOR
HQ OPS Officer: HOWIE CROUCH
Notification Date: 11/07/2017
Notification Time: 10:49 [ET]
Event Date: 11/07/2017
Event Time: 03:37 [CST]
Last Update Date: 11/07/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JEREMY GROOM (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF INBOUND COMMERCIAL LINES AND FTS LINES TO FACILITY

"On November 7, 2017, at approximately 0337 (CST) hours, Waterford 3 [WF3] Control Room received a phone call from Entergy's Load Dispatcher to inform us that the NRC was unable to call Waterford 3 by ENS [emergency notification system] phone or by PABX [private automatic branch exchange] phone. The NRC was called by the Waterford 3 Control Room using the PABX at 0339 (CST) hours. However, the ENS phone could not call the NRC. Also, outside lines were not able to call in to Waterford 3.

"Offsite prompt Public Warning Sirens were available at all times. State and Local notification capability was available via PABX. WF3 Emergency Response Organization notification capability was available at all times. WF3 site Emergency Response Facility intercommunications were available at all times.

"This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) due to a loss of offsite communications capability.

"ENS communication and full PABX functionality was reestablished at 0452 (CST) on November 7, 2017.

"The licensee notified the NRC Resident Inspector."

To top of page
Power Reactor Event Number: 53058
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: ROB KLINDWORTH
HQ OPS Officer: JEFF HERRERA
Notification Date: 11/07/2017
Notification Time: 14:19 [ET]
Event Date: 11/06/2017
Event Time: 14:45 [EST]
Last Update Date: 11/07/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
BILL COOK (R1DO)
FFD GROUP (EMAI)

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

FITNESS FOR DUTY PROGRAM VULNERABILITY

"It was determined that a licensed employee was not placed in an additional Fitness-For-Duty (FFD) testing program as directed by the MRO (Medical Review Officer). Upon discovery, the individual was subsequently tested . . . and determined Fit-For-Duty per 10 CFR 26 requirements.

"This event is being reported pursuant to 10 CFR 26.719(b)(4).

"The NRC Resident Inspector has been notified."

To top of page
Power Reactor Event Number: 53059
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: ANDREW MITCHELL
HQ OPS Officer: VINCE KLCO
Notification Date: 11/07/2017
Notification Time: 22:09 [ET]
Event Date: 11/07/2017
Event Time: 18:10 [CST]
Last Update Date: 11/07/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
HIRONORI PETERSON (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

UNIT 1 HIGH PRESSURE COOLANT INJECTION INOPERABLE

"On November 7, 2017 at 1810 [CST], Unit 1 High Pressure Coolant Injection (HPCI), was manually isolated following failure of the remote turbine trip pushbutton to function. Unit 1 HPCI Operability Testing was in progress to the point of securing the HPCI turbine with the remote manual pushbutton. The pushbutton failed to trip the turbine resulting in operator action to lower the flow controller setpoint and isolating the HPCI steam line. HPCI remains isolated and is Inoperable pending resolution of the Turbine Trip circuitry.

"This event is being reported as a condition that could have prevented fulfillment of a safety function in accordance with 10CFR50.72(b)(3)(v)(D). The HPCI system is a single train system and the loss of HPCI could impact the plant ability to mitigate the consequences of an accident. The Reactor Core Isolation Cooling (RCIC) system was confirmed operable.

"The NRC Senior Resident Inspector has been notified."

To top of page
Power Reactor Event Number: 53060
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: MICHAEL S. MOORE
HQ OPS Officer: JEFF HERRERA
Notification Date: 11/07/2017
Notification Time: 22:32 [ET]
Event Date: 11/07/2017
Event Time: 19:57 [EST]
Last Update Date: 11/07/2017
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):
RANDY MUSSER (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

AUTOMATIC REACTOR TRIP ON TURBINE TRIP

"On 11/7/2017 at 1957 [EST], VC Summer Nuclear Station automatically tripped due to a turbine trip. The cause of the turbine trip is under investigation at this time.

"All systems responded as expected. All Control Rods fully inserted and all Emergency Feedwater pumps started as required. The plant is stable in Mode 3.

"This event is reportable per 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A).

"The unit is currently stable in Mode 3 with decay heat removal via the Main Steam to the Main Condenser.

"The NRC Resident Inspector has been notified."

The licensee will notify the South Carolina State Emergency Management Division, the Fairfield, Richland, Lexington and Newberry Counties.

Page Last Reviewed/Updated Wednesday, November 08, 2017
Wednesday, November 08, 2017