ML19319D292

Forwards Comments on Tech Specs.Assumes LOCA Analysis Will Be Acceptable & Fuel Densification Effects Are Accounted for

ML19319D292
Person / Time
Site:	Crystal River
Issue date:	12/09/1975
From:	Brooks W Office of Nuclear Reactor Regulation
To:	Mcgough J Office of Nuclear Reactor Regulation
References
NUDOCS 8003130938
Download: ML19319D292 (3)

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Note to:

J. McCough, Section Leader, Quality' Assurance Branch, RL

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.THRU P. Check, Section Imader,- CPB, TR I have reviewed certain sections of the Technical Specification for the Cry.s_t_a_l_Ri_v_er_ Uni _t_.3 reactor. My coc:ments are enclosed.

It shouiJ be pointed out that I have asaut:ed that the LOCA analysis performd i.'r thio ;,1 uit will bc n:ceptable to tha Peactor Cyster:9 Eranch. It has also been as:ntned that faal denuification offects

- have been accounted for la the establishment of operating limits.

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- % /j Hr. A. Schwencer, Chief g h giv M Director of Nuclear Reactor Regulation Q $. k swic

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,(Sj Crystal River Unit #3 yPx ct V Dochet );o. 50-302

Dear Mr. Schrencer:

Attached are twenty (20) copies of the Gilbert Associates, Inc. report entitled, "ECCS Passive Heat Sink Data and Inferration", prepared for Florida Power Corporation in response to the KRC's Request for Additional Information contained in your letter of August 12, 1975.

If you require additional infornstion or discussion concerning our re-sponse, please do not hesitate to contact this office.

Very truly yours, Regulair.' Dx%i se

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J. T. Rodgers Asst. Vice President JIR/iv Attachaents.

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