ML17037B516

Letter Regarding Request for Information Concerning the Reactor Vessel, Its Materials of Construction, and Surveillance Specimens

ML17037B516
Person / Time
Site:	Nine Mile Point
Issue date:	10/28/1977
From:	Lear G Office of Nuclear Reactor Regulation
To:	Rhode G Niagara Mohawk Power Corp
References
Download: ML17037B516 (4)

Text

OCT 2 8 1977 Docket No. 50-220 Niagara tlohawk Power Corporation ATTN: fir. Gerald K. Rhode Yice President - Engineering 300 Erie Boulevard Uest

Syracuse, New York 13202 Gentlemen:

RE:

NINE 'NILE POINT NUCLEAR STATION UNIT NO.

1 Distribution v Docket ORB P3 Local PDR'RC PDR GLear CParrish SNowicki JZwetzig

Attorney, OELD OISE (3)

DEisenhut TBAbernathy JRBuchanan ACRS (16)

By letter dated tiay 20, 1977, we requested certain specific information concerning your reactor vessel, its materials of construction, and sur-veillance specimens.

Although.your letters of July 22, 1977, and August 18, 1977, submitted in response to this request, provided a useful general discussion outlining the adequacy of your surveillance

program, and the basis for your belief that the surveillance specimens are reasonably representative of the limiting materials in the reactor vessel beltline region, they do not provide all the specific items of information requested.

Thi s specific information is needed by the staff to verify that the operating limits in your Technical Specifications are in accordance with Appendices G

and H to 10CFR50, and to ass'ure that these limits are updated correctly throughout the life ot the plant.

It is recognized that new material testing requirements were imposed by Appendices G and H, and therefore some of,the material test results requested may not be available.

If this is the case for your reactor

vessel, please provide the results of the tests that were performed, and estimate the missing information in accordance with the guidance given in Section 5.3.2 of the Standard Review Plan.

As noted in our earlier letter on this subject, recent information indi-cates that some materials may be affected more by radiation than originally anticipated, leading to uncertainties in toughness properties throughout service life.

Hithout more detailed information, estimates will have to be made on a conservative "worst case" basis.

This will most likely result DPPICE~

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tliagara t'lohawk Power Corporation OCT 2 8 1977 overly conservative pressure-temperature limits, such as inconveniently high restrictions on the minimum temper atur e for core critical ity.

Accordingly, we reiterate our request that you supply each of the specific items. of information listed in the enclosure to our letter of ttay 20, 1977, and request that such submittal be made within 60 days of receipt of this letter.

Sincerely, Original signed bg George Lear, Chief Operating Reactors Branch ¹3 Division of Operating Reactors cc:

Eugene B. Thomas, Jr., Esquire

LeBoeuf, Lamb, Leiby 8 tiacRae 1757 tJ Str'eet, tI.

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Washington, D.

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20036 anthony Z. Roisman, Esquire

Sheldon, Harmon and Roisman 1025 15th Street, N. H.

5th Floor Washington, D.

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20005 Oswego City Library 46 E. Bridge Street

Oswego, ttew York 13126 OPPICR~

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