05000413/LER-2009-001, Both Trains of Chemical Volume Control, Auxiliary Feedwater and Containment Spray Systems Were Inoperable Due to a Component Failure
| ML090960308 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/01/2009 |
| From: | Morris J Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 09-001-00 | |
| Download: ML090960308 (12) | |
| Event date: | |
|---|---|
| Report date: | |
| 4132009001R00 - NRC Website | |
text
Duke Energy Carolinas JAMES R. MORRIS, VICE PRESIDENT Duke Energy Carolinas, LLC Catawba Nuclear Station 4800 Concord Road / CN01 VP York, SC 29745 803-701-4251 803-701-3221 fax April 1, 2009 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C.
20555
Subject:
Duke Energy Carolinas, LLC (Duke)
Catawba Nuclear Station, Unit 1 Docket Nos.
50-413 Licensee Event Report 413/2009-001 Revision 0 Attached is Licensee Event Report 413/2009-001 Revision 0 entitled, "Both Trains of Chemical and Volume Control, Auxiliary Feedwater and Containment Spray Systems were Inoperable due to a Component Failure."
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 A. Jones-Young at (803) 701-3051.
Sincerely, James R. Morris Attachment www. duke-energy. corn
t Document Control Desk Page 2 April 1, 2009 xc (with attachment):
L.A. Reyes Regional Administrator, Region II U.S. Nuclear Regulatory Commission 61 Forsyth Street, S.W.,
Suite 23T85
- Atlanta, GA 30303 J.H. Thompson (addressee only)
NRC Senior Project Manager 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 April 1, 2009 bxc (electronic copy) (with attachment):
INPO lerevents@inpo.org T.M. Hamilton R.D. Hart G.Y. Helton S.F. Hatley (EPIX)
M.K. Green D.R. Brenton S.L. Nader A.M. Peterman K.D. Thomas R.G. Hull R.J.. Freudenberger R.C. Meixell H.D.
Brewer R.E. Abbott B.J. Horsley M.J. Brown bxc (hard copy) (with attachment):
R.L. Gill L.F. Vaughn G.F. Winkel A.D. Jones-Young ELL Master File CN-801.01 LER File RGC Date File NCMPA-1 NCEMC PMPA
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010
Abstract
On January 30, 2009, with Unit 1 operating in Mode 1-at 100% power, 1RN-291 (Component Cooling System (KC)
Heat Exchanger lA Nuclear Service Water System (RN)
Control Valve) failed to control flow to 1A KC Heat Exchanger.
The valve was indicating open on the Operator Aid Computer (OAC); however, the expected increase in flow through theheat exchanger was not obtained when the operational mode of the valve was changed.
Train 1A of KC was declared inoperable.
A review of OAC data revealed that valve 1RN-291 had failed on January 28, 2009.
During this timeframe, Train 1A of KC was unable to provide a heat sink for various systems that are essential to the mitigation of design basis events.
Additionally, between January 28 and January 30, Train lB of Chemical and Volume Control, Containment Spray, and Auxiliary Feedwater Systems were taken out of service to perform maintenance activities; therefore, both trains of these systems were inoperable at some point during this time period.
The event is attributed to the failure of the Rod End Bearing Assembly of valve 1RN-291.
The valve was repaired and Train 1A KC was declared operable.
This event did not adversely affect the health and safety of the public.
This report involves a safety system functional failure.
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 NRC. (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)
ADDITIONAL INFORMATION
Within the last three years, there were no LERs that involved both trains of a safety related system being inoperable and the cause attributed to component failure.
Therefore, this event was determined to be non-recurring.
Energy Industry Identification System (EIIS) codes are identified in the text as [EIIS: XX].
This event is reportable to the Equipment Performance and Information Exchange (EPIX) program.
This event is considered to be a Safety System Functi6nal Failure.
There were no releases of radioactive materials, radiation exposures, or personnel injuries associated with this event.