05000287/LER-2004-004, Regarding Open Containment Penetration During Refueling Activities
| ML050530232 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/10/2005 |
| From: | Rosalyn Jones Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| O-04-8658 LER 04-004-00 | |
| Download: ML050530232 (9) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2872004004R00 - NRC Website | |
text
Duke RON A.
JONES laPower.
Vice President A Duke Energy Company Oconee Duke Power ONOI VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax February 10, 2005 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555
Subject:
Oconee Nuclear Station Docket Nos. 50-287 Licensee Event Report 287/2004-02, Revision 0 Problem Investigation Process No.: 0-04-8658 Gentlemen:
Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached is Licensee Event Report 287/2004-02, Revision 0, regarding operation with an open path out of containment while refueling activities were in progress.
This report is being submitted in accordance with 50.73 (a)(2)(i)(B) as operation in a condition prohibited by Technical Specifications.
This event is considered to be of no significance with respect to the health and safety of the public.
Very truly yours,
/A 4
/4 R. A. Jones Attachment www. dukepower. corn
Document Control Desk Date: February 10, 2005 Page 2 cc:
Mr. William D. Travers Administrator, Region II U.S. Nuclear Regulatory Commission 61 Forsyth Street, S. W., Suite 23T85 Atlanta, GA 30303 Mr. L. N. Olshan Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.
20555 Mr. M. C. Shannon NRC Senior Resident Inspector Oconee Nuclear Station INPO (via E-mail)
Abstract
On 12-13-04, at 1245 with Unit 3 in Mode 6 after core reload was complete, Operations personnel (OPS) discovered a deviation from Technical Specification 3.9.6 on containment closure (CC) during fuel movement. The NRC was notified at 1701 on 12/13/2004 (ENS 41256).
CC was verified prior to fuel movement.
On 12/7/04, during fuel movement, OPS ran a valve checklist which opened five steam drain valves in the turbine building.
The valves are part of the outside containment boundary for a Main Steam penetration and were required to be closed for CC.
At 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br /> on 12/12/04, a CC surveillance found the open valves and closed them.
Fuel handling was completed at 0358 on 12/13/2004.
OPS checked the actual status of the inside boundary, which was uncontrolled this outage.
OPS determined at 1245 on 12/13/04 that at least one valve on this penetration had been open inside containment during this event, making a reportable open flow path.
The event root cause was that standards and expectations for the use of the "Containment Isolation Component" tags were not clearly defined or understood.
There was no actual release due to the event.
This event is considered to have no significance with respect to the health and safety of the public.
NRC FORM 366 (7-2001)
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ADDITIONAL INFORMATION
A review for similar prior events with similar root caused occurring within the prior two years indicates this is not a recurring event or problem.
There were no releases of radioactive materials, radiation exposures or personnel injuries associated with this event.
This event is not considered reportable under the Equipment Performance and Information Exchange (EPIX) program.