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Event Notification Report for April 7, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/06/2017 - 04/07/2017

** EVENT NUMBERS **


52657 52666 52668 52669

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Part 21 Event Number: 52657
Rep Org: AMETEK
Licensee: VISHAY/INTERNATIONAL
Region: 3
City: COLUMBUS State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ETHAN SALSBURY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/03/2017
Notification Time: 09:28 [ET]
Event Date: 06/01/2016
Event Time: [EDT]
Last Update Date: 04/06/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
MICHAEL KUNOWSKI (R3DO)
CHRISTOPHER CAHILL (R1DO)
PART 21/50.55 REACT (EMAI)
EUGENE GUTHRIE (R2DO)
MICHAEL VASQUEZ (R4DO)

Event Text

PART 21 NOTIFICATION - FAILURE OF VISHAY DIODES

The following information is the summary letter was received from Ametek via email:

"Product: Vishay/ International Rectifier Clamp, Diodes 600 V, 250A, forward and reverse bias. Ametek part numbers 07-600254-00 and 07-600255-00.

"Ametek Solidstate Controls is submitting the following Report of a Potential Defect in accordance with the requirements of 10CFR21. This notification is applicable to equipment model number 85-VC0250-29 provided to Dominion Nuclear at Millstone Power Station. Serial numbers affected by this potential defect are:

C901880111
C901880211
C901880221
C901880231
C901880244

"AMETEK SOLIDSTATE CONTROLS CORRECTIVE ACTION: If you wish to replace the diodes, Ametek Solidstate Controls will work with you to arrange replacements. Please contact Mr. Mark Shreve of our Client Services group at 1-800-222-9079 or 1-614-846-7500 ext. 6332. mark.shreve@ametek.com"

"Please contact us at telephone: 614-846-7500; 1-800-635-7300 or e-mail: ethan.salsbury@ametek.com, if there are any questions.

* * * UPDATE ON 4/6/17 AT 0839 EDT FROM ETHAN SALSBURY TO BETHANY CECERE * * *

"The original notification for this report contained a typo on the last serial number of the equipment affected."

Instead of serial number C901880244, the correct serial number is C901880241.

Notified R1DO (Cahill), R2DO (Nease), R3DO (Skokowski), R4DO (Vasquez), and Part 21 Reactors group by email.

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Power Reactor Event Number: 52666
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: DAVID GHOLSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/05/2017
Notification Time: 16:32 [ET]
Event Date: 04/05/2017
Event Time: 14:00 [CDT]
Last Update Date: 04/06/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MICHAEL VASQUEZ (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

Event Text

UNANALYZED CONDITION FOR BOTH EDG TRANSFER LINE CONNECTIONS

"Both Emergency Diesel Generators [EDGs] have truck connections connected to transfer lines that are potentially not compliant with general design criteria. A potentially unanalyzed condition exists due to threat of tornado generated missiles.

"While in Mode 1 at 100% power, the Control Room was notified that the outdoor portion of the line upstream of JEV0001, EMERG FUEL OIL STORAGE TK A TRUCK CONN ISO, and the outdoor portion of the line upstream of JEV0002, EMERG FUEL OIL STORAGE TK B TRUCK CONN ISO, potentially have not been reviewed to meet general design criteria.

"No major equipment was out of service. No systems were required to respond to this event. The unit remains in Mode 1 at 100% power.

"The NRC Senior Resident Inspector has been notified.

"Compensatory measures have been established IAW [in accordance with] EGM 15-002."

The Unit entered Tech Spec 3.8.1 Condition B and D for approximately 45 minutes until compensatory measures were put into effect. The licensee identified this condition during a design review and is currently identifying long-term corrective actions.

* * * UPDATE ON 4/6/17 AT 0938 EDT FROM DAVID GHOLSON TO DONG PARK * * *

The Unit entered Tech Spec 3.8.1 Condition B and F, not Tech Spec 3.8.1 Condition B and D mentioned earlier.

Notified R4DO (Vasquez).

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Power Reactor Event Number: 52668
Facility: SUMMER
Region: 2 State: SC
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: GREGORT TRAVERS
HQ OPS Officer: JEFF ROTTON
Notification Date: 04/06/2017
Notification Time: 15:58 [ET]
Event Date: 04/06/2017
Event Time: 09:48 [EDT]
Last Update Date: 04/06/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
REBECCA NEASE (R2DO)
FFD GROUP (EMAI)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Under Construction 0 Under Construction
3 N N 0 Under Construction 0 Under Construction

Event Text

FITNESS FOR DUTY VIOLATION

A contractor manager had a confirmed positive for alcohol during a pre-access test. The employee's access to the construction site has been revoked.

The licensee notified the NRC Unit 2 & 3 Resident Inspector.

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Power Reactor Event Number: 52669
Facility: WATTS BAR
Region: 2 State: TN
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHARLES BROESCHE
HQ OPS Officer: JEFF ROTTON
Notification Date: 04/06/2017
Notification Time: 22:40 [ET]
Event Date: 04/06/2017
Event Time: 16:20 [EDT]
Last Update Date: 04/06/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
REBECCA NEASE (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Hot Shutdown 0 Hot Shutdown

Event Text

TEMPORARY LOSS OF CONTROL ROOM ENVELOPE BOUNDARY

"At 1620 EDT on April 6, 2017, a Main Control Room (MCR) door was found ajar. At that time, both control room ventilation filtrations trains (CREVS) were declared inoperable in accordance with Technical Specification 3.7.10, condition B, due to the inoperability of the Control Room Envelope (CRE). At 1623 EDT, the door was closed, CREVS was declared operable and LCO 3.7.10, Condition B was exited.

"The safety function of the CRE boundary is to ensure the in-leakage of unfiltered air into the CRE will not exceed the in-leakage assumed in the licensing basis analysis of Design Basis Accident (DBA) consequences to CRE occupants. Additionally, it ensures that the occupants are protected from hazardous chemicals and smoke.

"This event is being reported pursuant to 10 CFR 50.72(b)(3)(v)(D).

"NRC Resident Inspector has been notified."

Page Last Reviewed/Updated Friday, April 07, 2017
Friday, April 07, 2017