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Event Notification Report for August 18, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/17/2017 - 08/18/2017

** EVENT NUMBERS **


52893 52895 52911 52912 52913

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Agreement State Event Number: 52893
Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: HILLIS-CARNES
Region: 1
City: ANNAPOLIS JUNCTION State: MD
County:
License #: MD-03-054-01
Agreement: Y
Docket:
NRC Notified By: CHARLES COX
HQ OPS Officer: DONG HWA PARK
Notification Date: 08/09/2017
Notification Time: 15:27 [ET]
Event Date: 08/08/2017
Event Time: [EDT]
Last Update Date: 08/09/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BRICE BICKETT (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)

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

Event Text

AGREEMENT STATE REPORT - STOLEN AND RECOVERED MOISTURE DENSITY GAUGE

The following was received from the Maryland Department of the Environment via email:

"On August 8, 2017, Hillis-Carnes, Maryland Licensee MD-03-054-01, notified the Maryland Radiological Health Program (RHP) that a field technician had his van carjacked at the Key's Point temporary job site. His Troxler moisture density gauge model 3430 (serial number 31733) was still in the van and locked. The licensee notified Baltimore police.

"On August 9, 2017, the Maryland Department of the Environment Emergency Response Division was notified by the Baltimore police that the van and the Troxler gauge were recovered at O'Donnell Heights the evening of August 8. An RHP inspector went to the site and took possession of the gauge and is notifying the licensee so they can retrieve it.

"Troxler 3430 has a Cesium 137 sealed source less that 9 milliCuries and a 44 milliCurie AmBe source. No indication of any damage."

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

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Agreement State Event Number: 52895
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: PASADENA REFINING SYSTEM INC
Region: 4
City: PASADENA State: TX
County:
License #: 0134
Agreement: Y
Docket:
NRC Notified By: IRENE CASARES
HQ OPS Officer: JEFF HERRERA
Notification Date: 08/10/2017
Notification Time: 14:48 [ET]
Event Date: 08/09/2017
Event Time: [CDT]
Last Update Date: 08/10/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HEATHER GEPFORD (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - SHUTTER FAILURE DUE TO WATER INTRUSION

The following report was received from the Texas Department of State Health Services via email:

"On August 10, 2017, the licensee's radiation safety officer notified the Agency [Texas Department of State Health Services] that a fixed gauge (Ohmart Vega, SHLG-2, SN 8551CM, 3000 milliCuries, Cs-137) had a stuck shutter. A repair company was called and the technician completed repairs on the gauge within one day. Shutter failure was from water intrusion in the slide channel causing the shutter to rust and reduce movement. The gauge was cleaned and lubricated. A monthly maintenance procedure will be placed in effect to reduce or eliminate this issue."

Texas Incident: I-9503

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Power Reactor Event Number: 52911
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DREW RICHARDS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/17/2017
Notification Time: 16:48 [ET]
Event Date: 08/17/2017
Event Time: 14:42 [CDT]
Last Update Date: 08/17/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
WILLIAM GOTT (IRD)
CHRIS MILLER (NRR)

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

NON WORK RELATED ONSITE FATALITY

"At 1315 Central Daylight Time (CDT) on 8/17/2017, the South Texas Project Unit 1 Control Room was notified that a contract employee had experienced a non-work-related medical emergency within the Protected Area. The individual was transported to Matagorda Regional Medical Center in Bay City, TX. At 1442 CDT, the Unit 1 Control Room was notified that the patient was declared deceased.

"The Occupational Safety and Health Administration (OSHA) will be notified. This notification is being made under 10CFR50.72(b)(2)(xi) as an event for which another government agency is being notified. The deceased individual was not radioactively contaminated.

"The NRC Senior Resident Inspector has been notified."

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Power Reactor Event Number: 52912
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN McILNAY
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/17/2017
Notification Time: 17:24 [ET]
Event Date: 08/17/2017
Event Time: 12:05 [EDT]
Last Update Date: 08/17/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MARVIN SYKES (R2DO)

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

ACTUATION OF TURBINE DRIVEN AUXILIARY FEEDWATER PUMP DUE TO LOSS OF 6.9KV SHUTDOWN BOARD

"On August 17, 2017, at 1205 Eastern Daylight Time (EDT), the Watts Bar Nuclear Plant (WBN) lost power to the 1B-B 6.9kV Shutdown Board. The loss of power to this safety related bus resulted in an automatic start of the Unit 1 Turbine Driven Auxiliary Feedwater Pump (TDAFWP). The motor driven AFW pumps did not start and were not expected to start for this event. No other system actuations occurred as a result of loss of power to the 1B-B 6.9kV Shutdown Board. Power to the 1B-B Shutdown Board was restored at 1505 EDT on August 17, 2017.

"During the loss of power to the 1B-B Shutdown Board, a reduction in containment and control rod drive mechanism cooling occurred. At 1233 EDT, lower containment average temperature exceeded the procedural limitations specified, and Technical Specification 3.6.5 Condition A was entered for containment average air temperature not within limits. Lower containment average temperature was restored to within limits at 1525 EDT on August 17, 2017. This is reportable as a potential loss of safety function.

"Other than several common Unit Technical Specifications having not been met, Unit 2 was not operationally impacted by the loss of power to the 1B-B Shutdown Board and remains in Mode 1 at 100% power.

"The NRC Resident Inspector has been notified."

The loss of power occurred during restoration from Emergency Diesel Generator maintenance.

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Power Reactor Event Number: 52913
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: DON GREGOIRE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/17/2017
Notification Time: 17:55 [ET]
Event Date: 08/12/2017
Event Time: [PDT]
Last Update Date: 08/17/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
PART 21/50.55 REACTO (EMAI)

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

PART 21 REPORT - RELAY MOUNTING PLATE MOUNTED UPSIDE DOWN

"Pursuant to 10 CFR 21, this is a non-emergency notification by Energy Northwest concerning a defect in General Electric (GE) Nuclear HMA124A2 relays received at Columbia Generation Station.

"On August 12, 2017, Energy Northwest completed a 10 CFR 21 evaluation of a condition associated with GE Nuclear HMA124A2 relays supplied by GE Hitachi Nuclear Energy Americas, LLC, and intended for use at Columbia Generating Station. The evaluation was performed to determine the applications where the relays were approved for installation, and where they were installed in the plant, and to determine if the failure of the relays could result in a Substantial Safety Hazard as defined In 10 CFR 21.3.

"Two of the HMA124A2 relays received had back plates that were mounted upside down, causing the terminals to not match the standard configuration. Although the internal wiring to the physical stud locations was correct, the numbering scheme embossed on the back plate did not match the correct configuration. With the incorrectly mounted back plate, the internal coil of the energizing circuit could be wired to the incorrect portion of the control circuitry, which would not energize when required and could result in the failure of a safety function. This deviation presents a Substantial Safety Hazard as defined In 10 CFR 21.3, as these relays were approved for use in safety related applications; however, there was no actual risk to plant safety since this deviation was recognized and resolved by station craft prior to installation of the relays. This condition is reportable under 10 CFR 21.21(d)(1) as a defect as defined in 10 CFR 21.3.

"The defective HMA124A2 relays were installed in the plant in the correct configuration with post-maintenance testing performed to ensure operability of the relays. The remaining HMA124A2 relays were examined and no additional defects were identified. GE Hitachi has been notified of the condition."

The licensee will notify the NRC Resident Inspector.

Page Last Reviewed/Updated Friday, August 18, 2017
Friday, August 18, 2017