05000413/LER-2004-003, Regarding Unanalyzed Condition Due to Inadequate Evaluation of Fire Interactions
| ML042150402 | |
| Person / Time | |
|---|---|
| Site: | Catawba  (NPF-035, NPF-052) |
| Issue date: | 07/21/2004 |
| From: | Jamil D Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 04-003-00 | |
| Download: ML042150402 (10) | |
| Event date: | |
|---|---|
| Report date: | |
| 4132004003R00 - NRC Website | |
text
P Duke drPowere A Duke Energy Company D.M. JAMIL Vice President Duke Power Catawba Nuclear Station 4800 Concord Rd. / CNOI VP York, SC 29745-9635 803 831 4251 803 831 3221 fax July 21, 2004 U. S. Nuclear Regulatory Commission ATTENTION:
Document Control Desk Washington, DC 20555-0001
SUBJECT:
Duke Energy Corporation Catawba Nuclear Station Unit 1 and 2 Docket Nos. 50-413 and 50-414 Licensee Event Report 413/2004-003 Revision 0 Attached please find Licensee Event Report 413/2004-003 Revision 0, entitled "Unanalyzed Condition Due To Inadequate Evaluation of Fire Interactions".
This report does not contain any NRC commitments.
Questions regarding this Licensee Event Report should be directed to G. K. Strickland at 803-831-3585.
Sincerely, D. M. Jamil Attachment www.duke-energy.com rn12L
U.S. Nuclear Regulatory Commission July 21, 2004 Page 2 xc:
W. D. Travers U. S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 S. E. Peters (addressee only)
NRC Project Manager (CNS)
U. S. Nuclear Regulatory Commission Mail Stop 0-8 G9 Washington, DC 20555-0001 E. F. Guthrie Senior Resident Inspector (CNS)
U. S. Nuclear Regulatory Commission Catawba Nuclear Site INPO Records Center 700 Galleria Place Atlanta, GA 30339-5957
Abstract
approximately 15 single-spaced typewritten lines)
On June 23, 2004 Catawba identified an unanalyzed condition related to fire protection cable separation requirements.
A fire in the Unit 2 A-train 4160V switchgear room (2ETA)
[EIIS:EB] was postulated to cause a hot short to spuriously close centrifugal charging pump suction valve 2NV188A and damage the running pump (EIIS:CB].
Because the running pump and the 4160V switchgear room may be opposite train components, the postulated fire may result in both charging pumps being unavailable for post-fire plant recovery.
A fire in 2ETA may also affect the standby makeup pump.
This postulated loss of both trains of charging pumps was not analyzed in the Safe Shutdown Analysis.
On June 24, 2004 Unit 1 was determined to have a similar vulnerably for a fire in the B-train 4160V switchgear room (1ETB).
The apparent cause is inadequate original Safe Shutdown Analysis of certain spurious hot short valve operations.
Corrective actions included fire watches for the switchgear rooms until operating procedures were implemented to protect the correct train charging pump for post-fire plant recovery.
The conditions addressed by this report are related to postulated accidents and potential failures and had no direct effect on the health and safety of the public.
NRC FORM 366(7-2001)
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ADDITIONAL INFORMATION
Within the last three years, no other LERs occurred at Catawba involving fire events or the safe shutdown analysis.
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 did not meet the criteria for a Safety System Functional Failure.
There were no releases of radioactive materials, radiation exposures or personnel injuries associated with this event.