ML17326A262

Requests Extension to 800901 to Complete Phase C of Analytical Evaluation of Effects of Certain Postulated Break Loads on RCS & Internals

ML17326A262
Person / Time
Site:	Cook
Issue date:	09/26/1979
From:	Maloney G INDIANA MICHIGAN POWER CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:00137, AEP:NRC:137, NUDOCS 7910010334
Download: ML17326A262 (3)

Text

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INDIANA II MICHIGAN POWER COMPANY P. O. BOII 18 BOWLING GREEN STAT ION NEW YORK, N. Y. 10004 September 26, 1979 AEP:NRC:00137 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

REFERENCES:

(.1) Letter from Mr. Victor Stello, Jr. of NRC to Indiana 5 Michigan Electric Company, dated January 25, 1978 (2) Letter from Mr. J. A. Tillinghast to Mr. E. G. Case, NRC, dated March 8, 1978 (3) Letter from Hr. J. A. Tillinghast to Hr. E. G. Case, NRC, dated Hay 15, 1978

Dear Mr. Denton:

This letter is in reference to condition C.3(a) to the operating license for Unit 2 of the Donald C. Cook Nuclear Plant, No. DPR-74.

The license condition requires that an analytical evaluation of the

'.effects of certain postulated break loads on the reactor 'coolant system and internals be made by September 30, 1979. The latter date modified to January 25, 1980 by Mr. V. Stello's letter, Reference

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was 1). We responded to Mr. Stello's letter on March 8, 1978 (Reference

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2)) and on Hay 15, 1978 (Reference (3)).

As detailed in References 2 and 3, we are a member of the Westinghouse Owners'tility Group formed to perform this analytical evaluation work. The analytical evaluation was broken into three phases. Westinghouse has completed the two initial phases and has started the third phase, i.e., phase "C" evaluation. The analysis to be performed during this phase involves the effects of a LOCA break at any of the reactor vessel nozzles inside the reactor cavity. The details of the phase "C" evaluation were presented to the NRC on f:,

July 18, 1979 and the scope was revised to include the Commission's coments. It is anticipated that phase "C" evaluation will be completed by August 1, 1980, at which time we will report to you the results of the reactor vessel supports and internals evaluation. 0~@

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Hr. H. R. Denton September 26, 1979 In agreement with the commitment we made in Reference (3), we hereby request an extension to the due date to respond to license condition C.3(a} of Donald C. Cook Nuclear Plant Unit 2 up to September 1, 1980.

We want to point out that phase "C" analysis is being done assuming the presence of some type of rupture restraints for the primary coolant piping, located inside the primary shield wall penetration. After the completion of the analysis, details of the potential plant modifications will be submitted to your Staff for review and approval.

AEP interprets 10 CFR 170 Subsection 22 as requiring that no submittal fee accompany this request.

Very truly yours, GPM:em MYice Preside t I

cc: G. Charnoff R. C. Callen D. V. Shaller-Bridgman R. S. Hunter R. W. Jurgensen