05000366/LER-2005-002, Unit 2 Re Secondary Containment Bypass Leakage Requirements Exceeded
| ML051990353 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/13/2005 |
| From: | Sumner H Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-05-1255 LER 05-002-00 | |
| Download: ML051990353 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii) |
| 3662005002R00 - NRC Website | |
text
H. L Sumner, Jr.
Southern Nuclear Vice President Operating Company, Inc.
Hatch Project Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7279 SOUTHERN COMPANY July 13, 2005 Energy to Serve Your World9S Docket No.:
50-366 NL-05-1255 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin 1. Hatch Nuclear Plant - Unit 2 Licensee Event Report Secondary Containment Bypass Leakage Exceeded - Revision I Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50.73(a)(2)(ii), Southern Nuclear is submitting the enclosed revision to Licensee Event Report (LER) concerning a failed Local Leak Rate Test wvhich resulted in secondary containment bypass leakage being exceeded. A reference to the Unit I Technical Requirements Manual is being removed from the Corrective Action section.
This letter contains no NRC commitments. If you have any questions, please advise.
Sincerely, H. L. Sumner, Jr.
HLS/OCV/daj Enclosure: LER 2-2005-002-01 cc:
Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. G. R. Frederick, General Manager - Plant Hatch RTYPE: CHAO2.004 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Mr. C. Gratton, NRR Project Manager - Hatch Mr. D. S. Simpkins, Senior Resident Inspector-Hatch
Abstract
On 3/02/2005 at 1500 ET, Unit 2 was in the Refuel mode with fuel in the vessel and the reactor cavity flooded for refueling operations. At that time, plant engineers and technicians were performing Local Leak Rate Testing (LLRT) on Primary Containment Isolation Valves (PCIVs) when it was discovered that two Reactor Core Isolation Cooling (RCIC) valves had failed their associated LLRT. Both of these valves are located in the same penetration and are associated with Secondary Containment bypass leakage. The leakage acceptance criteria for Secondary Containment bypass are contained in the plant's Technical Specifications.
The primary cause of the failures for the inboard (2E5 1-F007) RCIC valve, and the outboard (2E5 1-F008)
RCIC valve appears to be degradation over a period of time. Corrective actions for this event included repairing the valves by installing new wedges and performing another LLRT with successful results.
NRC FORM 366 (6-2004)
(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)
CORRECTIVE ACTIONS
Valves 2E5 1 -F007 and 2E5 I -F008 were repaired by installing new wedges.
The information necessary to identify penetration ten as a potential bypass leakage path will be added to the Unit 2 Technical Requirements Manual. This will be done by August 15, 2005.
ADDITIONAL INFORMATION
No systems other than those already mentioned in this report were affected by this event.
Failed Component Information
MasterPartsListNumber: 2E51 -F007&F008 EIIS System Code: BN Manufacturer: Powell Reportable to EPIX: Yes Model Number: 73600 Root Cause Code: X Type: Valve, Shutoff EIIS Component Code: SHV Manufacturer Code: P305
Previous Similar Events
No events have been reported in the past two years in which the plant exceeded the Technical Specification limits for Secondary Containment bypasses leakage.
Commitment Information: This report does not create any permanent licensing commitments.
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