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Event Notification Report for March 1, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/28/2017 - 03/01/2017

** EVENT NUMBERS **


52458 52569 52581 52582 52583

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Part 21 Event Number: 52458
Rep Org: ITT ENIDINE INC.
Licensee: ITT ENIDINE INC.
Region: 1
City: WESTMINSTER State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: RAY SMITH
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/22/2016
Notification Time: 17:35 [ET]
Event Date: 11/02/2016
Event Time: [EST]
Last Update Date: 02/28/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
JAMES NOGGLE (R1DO)
GERALD MCCOY (R2DO)
STEVE ORTH (R3DO)
MICHAEL HAY (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
PART 21 MATERIALS ()
PART 21/50.55 REACTO ()

Event Text

PART 21 - POTENTIAL TRANSDUCER COMPONENT DEFECT

The following information was received via fax:

"The ITT Conoflow models GT25CA1826 and GT25CD1826 current to pressure (l/P) transducers produce a calibrated 3.0 to 15.0 psi output pressure from a 4.0 to 20.0 mA DC (input) signal. On November 2, 2016, a discovery was made of unqualified electrical component substitutions on the internal circuit board. Supplier and internal record reviews indicate these unqualified components were used as early as May 10, 2013, as the previously qualified PCB components are no longer available. Environmental qualification of the suspect circuit boards is planned for early 2017. If any component falls to meet requirements, nuclear facilities which use this product will be advised to examine their product for unqualified printed circuit boards via notification and visual references. Qualified replacement components will be provided to all affected customers.

"Customer Name / Item Number / No.: Units
Calvert Cliffs Nuclear / GT25CD1826 / 30
Control Components Inc. / GT2SCD 1826 / 3
Duke Energy Carolinas LLC / GT25CA1826 / 8
Duke Energy Carolinas LLC / GTI:SCD1826 / 4
Enertech Curtiss-Wright / GT25CA1816 / 19
Enertech Curtiss-Wright / GT25CD1826 / 4
Ergytech Inc. / GT25CA1826 / 3
Ergytech Inc. / GT25CD1826 / 3
Gefran Benelux NV / GT25CD1826 / 2
Ontario Power Generation / GT25CD1826 / 31
SPX Flow Technology / GT25CA1826 / 2
Weir Valves & Controls UK / GT25CA1826 / 78"

* * * UPDATE ON 2/28/17 AT 0918 EST FROM RAY SMITH TO DONG PARK VIA FAX* * *

"On November 2, 2016 a discovery was made of unqualified electrical component substitutions on the internal circuit board. Supplier and internal record reviews indicate these unqualified components were used as early as May 10, 2013, as the previously qualified PCB components are no longer available. Environmental qualification of test samples containing the suspect circuit boards has been completed. The subject parts continued to operate and perform their intended safety function throughout all EQ [Equipment Qualification] tests."

Notified R1DO (DeFrancisco), R2DO (Bartley), R3DO (Jeffers), R4DO(Deese), NMSS Events Resource, and Part 21 Group via email.

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Agreement State Event Number: 52569
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: DESERT NDT, LLC
Region: 4
City: ABILENE State: TX
County:
License #: NM IR362-3
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/21/2017
Notification Time: 16:44 [ET]
Event Date: 02/20/2017
Event Time: [CST]
Last Update Date: 02/21/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GREG PICK (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - LOST THEN RECOVERED RADIOGRAPHY CAMERA

The following information was received via E-mail:

"On February 20, 2017, the licensee's radiation safety officer (RSO) notified the Agency [Texas Department of State Health Services] that one of its New Mexico radiography crews was performing radiographic operations on a pipeline that was being built in Reeves County, Texas. The crew finished work at one section and put the Spec 150 radiography device on the tailgate of their truck while they drove down the pipeline right-of-way to their next location. Unbeknownst to the radiographers, the device fell off the tailgate. The licensee and crew learned of the loss after a contractor found the device, picked it up, put it in the back of his pickup, and took it to another of the licensee's radiography crews who was also working on the pipeline. That crew called their site RSO who then called the crew who lost the camera.

"The camera was surveyed and readings were as expected. The source was in the fully shielded position and the safety plug was in the front of the camera. Based on calculations by the RSO on February 21, 2017, the contractor's exposure does not appear to have exceeded any regulatory limit.

"An investigation into this event is ongoing and further information will be provided as it is obtained in accordance with SA-300.

"The device was a Spec model 150, serial No.: 1778 containing a 60 Curie (current activity) Iridium-192 source, serial No.: YA0302."

Texas Incident No.: I-9466

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Power Reactor Event Number: 52581
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN OSBORNE
HQ OPS Officer: JEFF ROTTON
Notification Date: 02/28/2017
Notification Time: 16:24 [ET]
Event Date: 02/28/2017
Event Time: 10:00 [EST]
Last Update Date: 02/28/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
ANNE DeFRANCISCO (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 28 Power Operation 0 Hot Standby

Event Text

TECHNICAL SPECIFICATION SHUTDOWN DUE TO REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAKAGE

"On February 28, 2017 at 0930 [EST], a containment visual inspection was performed to identify the source of elevated RCS [Reactor Coolant System] leakage. A leak was identified between 13RC6 and 13SS661, 13 RCS hot leg sample isolation valves at 1000 [EST]. These valves are manual isolation valves in the reactor coolant hot leg sample line. Leak isolation could not be initially verified and is considered RCS pressure boundary leakage. Salem Unit 1 entered Technical Specification 3.4.6.2a, RCS operational leakage, for the existence of pressure boundary leakage.

"This event is being reported under the requirements of 10CFR50.72(b)(2)(i) for 'The initiation of a plant shutdown required by Technical Specifications' and 10CFR50.72(b)(3)(ii)(A) or 'Any event of condition that results in the condition of the nuclear power plant, including its principal safety barriers being seriously degraded.'

"The unit was placed in mode 3 at 1554 [EST] on 02/28/2017.

"This condition has no impact on public health and safety."

Per Technical Specifications, the unit is proceeding to mode 5. The leak rate at the time of shutdown was 0.33 gpm. This event has no effect on Unit 2.

The licensee has notified the NRC Resident Inspector. The licensee will be notifying the Lower Alloways Creek Township, the State of New Jersey and the State of Delaware.

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Power Reactor Event Number: 52582
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: TRICIA LOULA
HQ OPS Officer: JEFF ROTTON
Notification Date: 02/28/2017
Notification Time: 21:34 [ET]
Event Date: 02/28/2017
Event Time: 18:25 [CST]
Last Update Date: 02/28/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
MARK JEFFERS (R3DO)

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

Event Text

SHORT DURATION LOSS OF SECONDARY CONTAINMENT DUE TO SEVERE WEATHER

"At 1825 [CST] on 02/28/2017, Dresden Station received unexpected alarm 923-5 C-1, RX BLDG DP LO [Reactor Building Differential Pressure Low]. Reactor Building differential pressure was observed to briefly lose vacuum and return to a normal reading of 0.6 inches vacuum water gauge. At the time of the transient, Grundy County was under a Severe Weather Warning and gusts of wind were being monitored from the Main Control Room up to approximately 57 mph. The Reactor Building differential pressure returned to [greater than or equal to] 0.25 inches vacuum water gauge at 18:25 after 18 seconds with no operator action. Operators observed differential pressure reading to lose vacuum, below 0 inches vacuum water gauge, for approximately 3 seconds.

"This condition represents a failure to meet Surveillance Requirement 3.6.4.1.1. As a result, entry into Technical Specifications 3.6.4.1 condition A was made due to Secondary Containment being inoperable. This event is being reported in accordance with 10CFR50.72(b)(3)(v)(C) as a condition that could have prevented the fulfillment of a safety function.

"An issue report has been initiated and a 60-day Licensee Event Report will be submitted in accordance with 10CFR50.73(a)(2)(v)(C).

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 52583
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRAD HARDT
HQ OPS Officer: BETHANY CECERE
Notification Date: 02/28/2017
Notification Time: 21:48 [ET]
Event Date: 02/28/2017
Event Time: 10:30 [CST]
Last Update Date: 02/28/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
RICK DEESE (R4DO)
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 - PROHIBITED ITEM FOUND INSIDE PROTECTED AREA

"Event Report per 10 CFR 26.719(b)(1).

"On February 28, 2017, a violation of the site Fitness For Duty policy was committed. A prohibited item was found inside the Protected Area.

"The licensee notified the NRC Resident Inspector."

Page Last Reviewed/Updated Wednesday, March 01, 2017
Wednesday, March 01, 2017