| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/06/2017 - 04/07/2017 ** EVENT NUMBERS ** |
 | 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. |
| 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). |
| 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. |
| 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." | |