ML19316A562
| ML19316A562 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/17/1977 |
| From: | Parker W DUKE POWER CO. |
| To: | |
| References | |
| NUDOCS 8001100778 | |
| Download: ML19316A562 (2) | |
Text
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U.S. NUCLEAR REGULATORY COMMIT
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NRC DISTRlBUTION FOR PART 50 DOCKET MATERIAL
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OATE OF DOCUMENT Duke Power Company 6/17/77
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Mr. Edson G. Case Charlotte, North Carolina OATE RECEIVED Mr. William O. Parker, Jr.
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ENCLOSU RE j OESCRIPTION l Informing NRC of a recent steam generator
- tube leak which occurred in the Unit 3 "B"
steam generator......
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PLANT NAME:
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June 17, 1977
'/+Cr PRESiCENT TC'.EP=C N g:Asta7C4 3 'tano P#0DvCT'ON 3 73-4C 9 3 Mr. Edson G. Case, Acting Director Of fice of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission
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Washington, D. C.
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Re: Oconee Unit 3 1
Docket No. 50-287
Dear Mr. Case:
The purpose of this letter is to appraise you of a recent Oconee Nuclear Station steam generator tube leak which occurred in the Unit 3 "B"
steam generator. This leak first appeated on May 27, 197'7 and was determined to be approximately 0.1 gpm.
Continued operation of the unit with this small leakage rate is considered to be acceptable and within the technical specifications limits.
Shortly after the conduct of a main steam stop valve test on June 9, 1977, this leakage rate increased to approximately 0.2 gpm and the unit was shutdown for repair of this leak. Specific details will be forwarded by Reportable Occurrence Report R0-287/77-8 on June 24, 1977.
Subsequent to this shutdown, a leak test was performed and tube 1 in row 78 was determined to be the leaking tube.
Eddy current testing was per-formed on this tube and approximately 120 other steam generator tubes.
Only tube 1 in row 78 revealed a deleterious indication.
Examinations using a fiber optics visual technique of the inside diameter of this tube indicated a 900 circumferential crack.
This tube has been removed from service by the installation of a stabiliz-ing rod in a manner similar to that of other tubes of Oconee.
It is expected that the unit will return to power in the near future.
We will provide you information concerning the performance of the unit after power operation is resumed, and will discuss the augmentation of investigative programs with you should this be necessary.
Very truly yours,
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William O. Parker, Jr.
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