ML17256A661

Submits Addl Info Re Proposed Tubesheet Sleeve Design,Per Request.Info Addresses Inspectability,Pullout & Corrosion Potential.Fifty Tubesheet Sleeves Will Be Installed During Present Refueling Outage,Per

ML17256A661
Person / Time
Site:	Ginna
Issue date:	04/26/1983
From:	Maier J ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
NUDOCS 8305030352
Download: ML17256A661 (8)

Text

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ROCHESTER GAS AND ELECTRIC CORPORATION

~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAILER Vice President TELEPHONE AREA coDE 7lo 546.2700 April 26, 1983 Director of Nuclear Reactor Regulation Attention:

Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.

5 U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Steam Generator Sleeving R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Crutchfield:

On April 20, 1983 we submitted information to you regarding a proposed tubesheet sleeve design.

In subsequent telephone conversations, you have requested some additional information regarding the tubesheet sleeves.

The following is in response to those requests:

1 existing steam generator tube resulting from the upper tubesheet sleeve explosive weld can be inspected using our standard eddy current equipment and techniques.

By using lower frequencies we can detect flaws in this transition comparable in size to what we can currently detect'n the existing tube roll transition.

Exact, sizing of these indications will be somewhat more difficult due to the lower frequencies required.

However, if flaws are detected in this area, additional inspections will be performed using more sensitive techniques such as the rotating, radial differential probe method developed for inspection of the braze/

expansion area of brazed sleeves.

This equipment is described in our March 25, 1983 letter.

The attached drawing shows details of the area to be inspected.

The geometry is very similar to that in the braze/expansion area.

2.

Pullout - The upper expansion transition in the existing steam generator tube resulting from the tubesheet sleeve explosive weld is a minimum of 1 inch below O

the top of the tubesheet.

In Section 6.2.3.3 of our April 26, 1982 Steam Generator Evaluation Report there is an analysis of pullout.

That, analysis shows a

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ROCHESTER GAS AND ELECTRIC ORP.

April 26, 1983 Mr. Dennis M. Crutchfield SHEET NO.

3.

maximum stretch of 0.14 inches under worst case pressure loading.

Although that analysis was performed specifically for pullout from a tube support plate, the conclusions are equally valid for the tubesheet.

Corrosion Potential To date, no detectable tubesheet intergranular attack (IGA) has been found within 4 inches of the top of the tubesheet at Ginna.

As a result of the crevice flushing process, the detectable indications, in general, are being found farther below the top of the tubesheet with time.

These results, together with the all volatile secondary water treatment (AVT) currently utilized at Ginna, reduces the probability of corrosion above the proposed'ubesheet sleeves.

As indicated in our April 20 letter, we are planning to install approximately 50 tubesheet sleeves during our present.

refueling outage.

Materials are currently in place at Ginna for installation of tubesheet sleeves.

Preparation and review of the tubesheet sleeve installation procedure will be completed in the very near future.

I Very truly yours,

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