ML17256A757

Forwards Rev 0 to Proprietary Steam Generator Evaluation, Spring 1983 Outage,Strength Testing of Sealable Sleeves Explosively Expanded Into Locked Tubes - Re Ginna Station. Rept Withheld (Ref 10CFR2.790)

ML17256A757
Person / Time
Site:	Ginna
Issue date:	06/09/1983
From:	Maier J ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
Shared Package
ML17256A758	List: ML17256A757
References
NUDOCS 8306140595
Download: ML17256A757 (4)

Text

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SUBJECT~

Forwards Rev O,to pr op> ietar y "Steam Generator Evaluation/

'Spring 1983 OutagerStrength Testing of Sealable S)eeves Explosively Expanded Into Locked Tubes RE Ginna Station."

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~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN Ci MAIER Vice Pro side nt TCLCRHONC ARcA cooc 75e 546 2700 June 9,

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:

Xn our letter dated May 24,

1983, we identified several tests which were being performed to support pretensioning of steam generator tubes for sleeving.

The attached report summarizes the tests and results.

The tests demonstrate the acceptability of the upper tube sleeve joint and of the thermally pretensioned tube.

The attached report is proprietary to Babcock and Wilcox.

Therefore, pursuant to 10 CFR 2A790(b),

we request that the attachment be withheld from public disclosure.

An affidavit is being prepared and will be forwarded in the next few days'ery truly yours, 7

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