05000269/LER-2002-001, From Oconee Nuclear Station Unit Three Regarding Moisture Separator Reheater Level Results in Reactor Trip
| ML030220465 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/13/2003 |
| From: | Rosalyn Jones Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 02-001-00 | |
| Download: ML030220465 (9) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 2692002001R00 - NRC Website | |
text
Duke
- - I14twrPower,D A Duke Energy Company R. A JONES Vice President Duke Power 29672 / Oconee Nuclear Site 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax January 13, 2003 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555
Subject:
Oconee Nuclear Station Docket Nos. 50-269,-270, -287 Licensee Event Report 287/2002-01, Problem Investigation Process No.:
Revision 0 0-02-06562 Gentlemen:
Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached is Licensee Event Report 287/2002-01, Revision 0, concerning the Unit 3 Reactor trip due to Moisture Separator Reheater level.
This report is being submitted in accordance with 10 CFR 50.73(a)(2)(iv)(A).
This event is considered to be of no significance with respect to the health and safety of the public.
Very )fjuy yours, Attachment www duke-energy corn
Document Control Desk January 13, 2003 Page 2 cc:
Mr. Luis A. Reyes 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 November 14, 2002, Oconee Unit 3 was operating in Mode 1 at 100%
power.
At approximately 0419 hours0.00485 days <br />0.116 hours <br />6.92791e-4 weeks <br />1.594295e-4 months <br />, Unit 3 experienced a high level in a Moisture Separator Reheater (MSRH).
The turbine tripped as a protective feature to prevent water from backing up into the turbine.
This caused an anticipatory reactor trip.
The high level was caused by three separate equipment failures which resulted in discharge flow paths from the 3A Moisture Separator Drain Tank (MSDT) becoming isolated and water backing up into the MSDT and MSRH.
In this event, the plant systems and operators responded as expected.
Automatic system responses and operator actions in accordance with procedures were adequate to safely control the reactor following this trip.
The corrective action was to repair the three Unit 3 A MSDT level control equipment problems.
The health and safety of the public was not compromised by this event.
NRC FORM 366 (7-2001)
(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)
Replace DVC for 1,2,3HD-27 and 1,2,3HD-28 at the next refueling outage.
Evaluate adequacy of 3R PM frequency for 1,2,3HD-27 and 1,2,3HD-28. Assign to MCE.
There are no NRC Commitment items contained in this LER.
SAFETY ANALYSIS
This event did not include a Safety System Functional Failure.
The MSRH emergency high level trip is a turbine protective trip for economic reasons: high MSRH level does not affect nuclear safety.
Post-reactor trip response, as discussed in the Event Description section of this report was within acceptable limits as defined by the Babcock and Wilcox Owners Group Transient Assessment Program.
There were no Emergency Feedwater actuations required as a result of this event.
ADDITIONAL INFORMATION
A review of reportable events indicated that no reactor trip events have occurred within the past two years due to the root cause identified in this event.
The trip of the Reactor constitutes a Maintenance Rule functional failure and is considered reportable under the Equipment Performance and Information Exchange (EPIX) program.
The NRC cause code is B.
There were no releases of radioactive materials, radiation exposures or personnel injuries associated with this event.
Therefore, there was no actual impact on the health and safety of the public due to this event.(1-2001)
LICENSEE EVENT REPORT (LER)
FAILURE CONTINUATION PA~rll ITV MAMF (1' IlOCIIFT I9I NA [A)
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COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
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