ML20052A700

Submits Correction to Last Page of 820419 Response to NRC Request for Addl Info Re Inservice Insp

ML20052A700
Person / Time
Site:	Clinch River
Issue date:	04/26/1982
From:	Longenecker J ENERGY, DEPT. OF
To:	Check P Office of Nuclear Reactor Regulation
References
HQ:S:82:023, HQ:S:82:23, NUDOCS 8204290047
Download: ML20052A700 (2)

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a Mr. Paul S. Check, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Check:

RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION - INSERVICE INSPECTION

Reference:

Letter, J. R. Longenecker to P. S. Check, " Responses to Request for Additional Information - Inservice Inspection," Letter Number HQ:S:82:021, dated April 19, 1982 This letter provides a correction to the last page of our response contained in the reference letter.

With regard to the remaining question (CS 250.1), a response will be provided under separate cover by May 14, 1982, rather than April 23, 1982, as stated in the reference letter.

Sincerely,

~ o John R. Longenecker, Manage Licensing & Environmental Coordination Office of Nuclear Er.ergy Enclosure l cc: Service List l

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2. Voli - tric s'vamination of Dimmimilar Metal Welds The dissimilar metal welds on the IIrrs are all located in the Steam Generator Building. The Project will perform a voltanetric examination of 33% of the welds once every ten years, choosing a different sample each interval in order to cover essentially 100% of the welds by the end of the third interval. This examination is performed in addition to periodic visual examinations and continuous monitoring for leak detection.

The specific volumetric examination to be performed on these 2-1/4 Cr-1 Mo material dissimilar metal welds will be dependent upon the results of on-going contributing base development progr as. These developnent programs address transition weld development, life tests and methods for fabrication examinations as well as inservice examinations. Should final stress analysis determine that these are i limited life caponents, more frequent volumetric examinations than presently defined may be required and will be factored into the inservice examination requirements.

3. Vol' = tric 5'v=mination of Staam Generator e le Tubina Refer to PSAR Appendix G which states that 3% of the heat transfer surface tubes in each steam generator module (9 total) will have an inservice volumetric examination daring the first 10 year inspection intervals. During each of the two successive ten year inspection intervals, 1-1/2% of the heat transfer surface tubes in each of the three steam generator modules in one loop will receive a volumetric examination. All tubes to be examined are selected from previously examined tubes, including any tubes which exhibit a wall thinning rate greater than the design allowable.

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