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Event Notification Report for September 19, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/16/2016 - 09/19/2016

** EVENT NUMBERS **


52233 52244 52245 52247

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Non-Agreement State Event Number: 52233
Rep Org: THRASHER ENGINEERING, INC.
Licensee: THRASHER ENGINEERING, INC.
Region: 1
City: BRIDGEPORT State: WV
County:
License #: 47-23065-01
Agreement: N
Docket: -
NRC Notified By: RANDY MEANS
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/10/2016
Notification Time: 15:45 [ET]
Event Date: 09/10/2016
Event Time: 00:00 [EDT]
Last Update Date: 09/10/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
MEL GRAY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)

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

Event Text

THEFT OF TROXLER MOISTURE-DENSITY GAUGE

Sometime between midnight and 2:30 AM on 09/10/16, a Troxler Moisture-Density Gauge Model 3440, S/N 69105, was stolen from the back of a pickup truck parked at the Sleep Inn in Beaver, WV. The Troxler Model 3440 typically contains two sources; 8 mCi Cs-137 and 40 mCi Am-241/Be. Surveillance video provided to the LLEA (Raleigh Police Department) shows an individual parking a white pickup truck next to the truck containing the gauge and subsequently transferring the gauge box to the white pickup. The licensee confirmed that the gauge was locked and properly secured prior to the theft.

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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Power Reactor Event Number: 52244
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TIMOTHY BENNETT
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 09/16/2016
Notification Time: 00:14 [ET]
Event Date: 09/15/2016
Event Time: 15:40 [CDT]
Last Update Date: 09/16/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RAY AZUA (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

POTENTIAL DEGRADATION OF ECCS PUMP PRESSURE INDICATORS

"During a review of commercial grade dedication records for a Unit 1 [Emergency Core Cooling System ECCS] Centrifugal Charging Pump discharge pressure gauge, it was identified that the process side of the diaphragm seal utilizes a Teflon (PTFE) gasket. Further review found Teflon (PTFE) to be installed in the pressure gauge seal assembly for all four of the Centrifugal Charging Pumps and both of the Positive Displacement Charging Pumps on Units 1 and 2.

"Teflon (PTFE) is a restricted material normally prohibited from use in contact with reactor coolant or in radiation environments. Teflon (PTFE) is not radiation tolerant and significantly degrades in a radiation environment. The Teflon (PTFE) used in these pressure gauges could fail during a LOCA [Loss of Coolant Accident] which could cause the [ECCS] Centrifugal Charging Pumps and both of the Positive Displacement Charging Pumps on Units 1 and 2 to be inoperable, and exceed system leakage limits. Excessive leakage from systems which would contain post-LOCA recirculation fluid would challenge onsite and offsite dose estimates and in-plant post-accident accessibility. This represents an unanalyzed condition.

"Currently, the pressure gauges for all four of the [ECCS] Centrifugal Charging Pumps and both of the Positive Displacement Charging Pumps on Units 1 and 2 have been isolated until this issue can be further evaluated. Luminant Power believes that the Teflon (PTFE) has existed in the pressure gauges since initial plant licensing. Luminant Power is currently investigating the extent of the condition and repair techniques.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 52245
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN MCHUGH
HQ OPS Officer: DANIEL MILLS
Notification Date: 09/16/2016
Notification Time: 12:17 [ET]
Event Date: 09/16/2016
Event Time: 09:13 [EDT]
Last Update Date: 09/16/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMES NOGGLE (R1DO)

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

HYDRAULIC FLUID (FISH OIL) SPILL

"At 0858 [EDT] on September 16th, 2016, approximately 3 ounces of hydraulic fluid (fish oil) was spilled in front of the Unit Two Circulating Water System (CWS) Intake trash racks at the Salem Generating Station. The spill of hydraulic fluid (fish oil) was caused by a leak from the crane used to rake debris from the Unit Two trash racks. The crane was stopped and the leak terminated at the time of discovery.

"Nuclear Environmental Affairs Department determined a 4 hr report to the NRC, under RAL 11.8.2.a, was warranted due to the 15 minute notification to the New Jersey Department of Environmental Protection at 0913 [EDT]. Nuclear Environmental Affairs Department intends to retract the report to the New Jersey Department of Environmental Protection based on the fluid remained within the Circulating Water System (CWS) Intake Structure."

The licensee has notified the New Jersey Department of Environmental Protection, the NRC Resident Inspector, and will notify the Lower Alloways Creek Township.

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Power Reactor Event Number: 52247
Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: ANDY MILLER
HQ OPS Officer: DANIEL MILLS
Notification Date: 09/16/2016
Notification Time: 23:35 [ET]
Event Date: 09/16/2016
Event Time: 16:57 [EDT]
Last Update Date: 09/16/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
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 N 0 Hot Shutdown 0 Hot Shutdown

Event Text

ESSENTIAL BUSSES NOT ALIGNED TO POWER TRANSFORMERS DURING PLANT STARTUP

"At 1657 Eastern Daylight Time (EDT) the plant entered Mode 4 (from Mode 5), and subsequently, at 1710 EDT, it was discovered that 480V AC essential busses E1 and F1 were being supplied from the shutdown operations transformers. The essential busses E1 and F1 are required to be aligned to the power operations transformers in Mode 4 for operability in accordance with TS 3.8.9.

"With both E1 and F1 essential busses aligned to the shutdown operations transformers with the plant in Mode 4, both trains of the essential electrical power distribution system were inoperable, resulting in a loss of safety function. At 1733 EDT both E1 and F1 essential busses were aligned to the power operations transformers as required by TS 3.8.9.

"This issue is being reported as a loss of safety function of the essential electrical busses.

"The NRC Resident Inspector has been notified of the event."

Page Last Reviewed/Updated Monday, September 19, 2016
Monday, September 19, 2016