ML19257A890

Responds to NRC 791209 & 27 Requests for Review of Info Re New NRC Fuel Cladding Strain & Fuel Assembly Flow Blockage Models.Nrc Test Data Consistent W/Data Used by GE in Formulating Approved ECCS Model

ML19257A890
Person / Time
Site:	Peach Bottom
Issue date:	01/04/1980
From:	Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
NUDOCS 8001090354
Download: ML19257A890 (3)

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PHILADELPH!A ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 SHIELDS L. D ALTROFF s:,acterc Pa o om January 4, 1980 Re: D ocket Nos. 50-277 50-278 Mr. Darrell G. Eisenhut, Acting Director Division of Operating Reactors Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Eisenhut:

Your letters of November 9, 1979 and November 27, 1979 requested that we review the information on the new NP.C fuel cladding strain and fuel assembly flow blockage nodels. In addition, your letters requested that we confirm that the cladding strain and assembly blockage models used f or the Peach Bottom Atomic Power Station Unit 2 and Unit 3 Emergency Core Cooling System (ECCS) calculations are as conservative as the staff's new models.

Since the ECCS calculations for Peach Bottom Unit 2 and Unit 3 were performed by General Electric Company as part of their nuclear fuel supply services, the f ollowing discussion pertains to the General Electric Company approved models.

In accordance with your request, we have reviewed the information contained in your letters of November 9 and November 27, 1979. In addition, we are aware of the review effort conducted by General Electric on this issue. We have reviewed the results of General Electric's studies pertaining to this issue contained in their letters of N ove mb e r 2, 1979, N ove mb e r 16, 1979 and December 7, 1979 to the NRC. Based on the information contained in these letters, it is our understanding that the new NRC test data is consistent with and in fact c omp lime n t s , over the BWR range of interest, the data used by General Electric in formulating their approved ECCS model. Based u

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Mr. J. G. Eisenhut Page 2 upon the foregoing and additional supportive correspondence received from General Electric Company, we hereby confirm that, over the operating range pertinent to Peach Bottom Atomic Power Station Unit 2 and Unit 3, the models used by General Electric in thethe as ECCS calculations staff's for Unit 2 and Unit 3 are as conservative new models. Accordingly, the Technical Specifications presently in effect f or Peach Bottom Units 2 and 3 should remain unchanged since they assure peak cladding temperatures below 2200 degrees F.

If you require any additional inf ormation or have any questions, please contact us.

Very truly yours,

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COMMONWEALTH OF PENNSYLVANIA  :

ss.

COUNTY OF PHILADELPHIA  :

S. L. DALTROFF, being first duly sworn, deposes ano states that he is Vice President of Philadelphia Electric Company, Licensee under Facility Operating Licenses DPR-44 and DPR-56 for Peach Bottom Atomic Power Station Units 2 and 3; that he has read the foregoing letter to Mr. Darrell G. Eisenhut, Acting Director of the Division of Operating Reactors, and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.

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Subscribed and sworn to before me this y day of 01

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[ otary{d]ble ELI - SETH H. BOYER 4 Nota blic. Phita.. Phda. Co.

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