ML20040C965

Forwards Revised Figures 1-4 Which Define Affected Areas of Steam Generator Tube Bundle to Which Util Proposed to Limit Cycle 5 Refueling Outage Steam Generator eddy-current Exams. Revised Figures Part of Proposal to Limit Inservice Insp

ML20040C965
Person / Time
Site:	Millstone
Issue date:	01/22/1982
From:	Counsil W NORTHEAST NUCLEAR ENERGY CO.
To:	Clark R Office of Nuclear Reactor Regulation
References
B10384, TAC-47577, TAC-8320, NUDOCS 8201290416
Download: ML20040C965 (6)

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January 22, 1982 c,

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O Docket No. 50-336 B10384 4

s REf.'5!ygg 9-hlN 3 bO2th 2

Director of Nuclear Reactor Regulation s rp g-\\ Lnr @gw,9 Attn:

Mr. Robert A. Clark, Chief p

Operating Reactors Branch #3 Q(f]ITThg U. S. Nuclear Regualtory Cona.;ssion Washington, D.C. 20555

Reference:

(1)

W. G. Ccansil letter to R. A. Clark, dated January 12, 1982.

Gentlemen:

Millstone Nuclear Power Station, Unit No. 2 Steam Generator Inscrvice Inspection In Reference (1), Northeast Nuc1 car Energy Company (NNECO) proposed a license amendment to limit the Steam Generator tube inservice in-spections at Millstone Unit No. 2 during the Cycle 5 refueling outage.

The revised eddy-current inspection program would apply only to those areas of the tube bundle affected by the pitting phenomenon recently identified at the Plant. NNECO had defined the affected area of the Steam Generator tube bundle in Figures 1-4 of Reference (1).

Subsequent to the docketing of Reference (1), NNECO has obtained revised information with which to better define the sludge pile in the Steam Generators. Higher levels of sludge have since been identifed in the area of the stay cylinder and blowdown lane along the hot leg / cold leg divider plate. As such, it is NNECO's intention to perform 100% eddy-current examinations in these areas which were previously excluded from the affected area as defined in Reference (1).

Therefore, please find attached, revised Figures 1-4 which define the affccted area of the Steam Generator tube bundle to which NNECO proposes to limit the Cycle 5 refueling outage Steam Generator eddy-current exa.nina t ions.

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8201290416 820122 PDR ADOCK 05000336 O

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. i These Figures should bc substituted for those previously provided in Reference (1).

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

?$$1 W. G' Counsil Senior Vice President

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