05000413/LER-2007-003, Undervoltage Condition Resulted in the Actuation of the Emergency Diesel Generator
| ML073030035 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/24/2007 |
| From: | Morris J Duke Energy Carolinas, Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 07-003-00 | |
| Download: ML073030035 (10) | |
| Event date: | |
|---|---|
| Report date: | |
| 4132007003R00 - NRC Website | |
text
PDuke DEnergy.
JAMES R MORRIS Vice President Catawba Nuclear Station 4800 Concord Road / CNO1 VP York, SC 29745-9635
- 803 831 4251 803 831 3221 fax October 24, 2007 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C.
20555
Subject:
Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke)
Catawba Nuclear Station, Units 1 and 2 Docket No.
50-413, 414 Licensee Event Report 413/2007-003 Attached is Licensee Event Report 413/2007-003 entitled, "Under voltage Condition Resulted in the Actuation of the Emergency Diesel Generators."
There are no regulatory commitments contained in this letter.
This event is considered to be of no significance with respect to the health and safety of the public.
If there are any questions on this report, please contact Marc Sawicki at (803) 831-5191.
Sincerely, James R.
Morris Attachment www.duke-energy.com
Document Control Desk Page 2 October 24, 2007 xc (with attachment):
W.D. Travers Regional Administrator, Region II U.S. Nuclear Regulatory Commission 61 Forsyth Street, S.W.,
Suite 23T85
- Atlanta, GA 30303 J.F. Stang, Jr. (addressee only)
NRC Senior Project Manager4 U.S. Nuclear Regulatory Commission Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 A.T. Sabisch NRC Senior Resident Inspector Catawba Nuclear Station INPO Records Center 700 Galleria Place
- Atlanta, GA 30339-5957
Document Control Desk Page 3 October 24, 2007 bxc (electronic copy) (with attachment):
INPO lerevents@inpo.org T.M. Hamilton R.D. Hart G.T.
Mode S.F. Hartley (EPIX)
V.A. Patterson T.P. Gillespie, Jr.
S.L. Nader B.T. Weaver K.D.
Thomas G.F. Winkel R.G. Hull B.G. Davenport J.A.
Kammer K.L. Ashe B.J.-Horsley M.J. Brown bxc (hard copy) (with attachment):
R.L. Gill L.F. Vaughn G.F. Winkel A.D. Jones-Young M.J. Sawicki K.E. Nicholson ELL Master File CN-801.01 LER File RGC Date File NCMPA-1 NCEMC PMPA SREC
Abstract
On August 25, 2007 at approximately 10:58 am, both Unit 1 and Unit 2 experienced a voltage dip of approximately 0.462 second duration when a transformer at a merchant plant connected to Duke's grid faulted.
The electrical grid disturbance caused all four Emergency Diesel Generators (EDGs) to actuate.
The EDGs ran unloaded because the condition existed for less than the 8.5 seconds required for separation from offsite power.
At 12:28, the Transmission Control Center (TCC) notified plant operations that the faulted busline was isolated, and by 12:36, all EDGs were secured and restored to standby.
The response of plant equipment to this electrical grid disturbance was as expected.
A Duke Energy team was chartered to provide further investigation to verify that the Catawba switchyard.is as secure as possible from similar.
external conditions.
The health and safety of the public were not adversely affected by this event.
NRC FORM 366 (9-2007)
(If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17) busses, cleared both busses and separated the units from the grid.
Although both EDGs on each unit were actuated, as in the current instance, the May, 2006 actuations were required due to sustained loss of voltage.
The root cause for the 2006 event determined that certain switchyard relay tap setting changes were never implemented at Catawba.
Due to the causes of these two events being unrelated, it can be concluded that this event is non-recurring in nature.
Energy Industry Identification System (EIIS) codes are identified in the text as [EIIS: XX].
There are no EPIX reportable equipment failures associated with this report.
This' event did not involve a Safety System Functional Failure.
There were no releases of radioactive materials, radiation exposures, or personnel injuries associated with this event.