ML17209B053

Requests Addl Info Re Application for Ol.Info on Hydrologic Engineering in Environ Rept Should Be Submitted by 810608

ML17209B053
Person / Time
Site:	Saint Lucie
Issue date:	05/05/1981
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
References
NUDOCS 8105140019
Download: ML17209B053 (5)

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1981 Docket No.

50-389 Florida Power tI Light Company ATTN:

Dr. Robert E. Uhrig, Vice President Advanced Systems 8 Technology P. 0.

Box 529100 Miami, Florida 33152 DISTRIBUTION:

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g DEisenhut RMiraglia VNerses JLee RTedesco Shanauer RVollmer TMurley DRoss RHartfield, MPA OELD OIE (3)

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SUBJECT:

ST.

LUCIE PLANT, UNIT 2 ER - REQUEST FOR ADDITIONAL INFORMATION From the review of your application for an operating license by the Hydrologic Engineering Section of the Hydrologic and Geotechnical Engineering

Branch, we find that we need additional information regarding the St. Lucie Plant. Unit 2 ER.

The specific information required is listed in the Enclosure, which was given to Mr. Dotson'n April 24, 1981. It is suggested that meetings with the staff of the Hydrologic Engineering Section be arranged so that we may share with you the body of information necessary to perform this analysis.

Responses to the enclosed reque'st should be submitted by June 8, 1981. If you cannot meet this date, please inform us within seven days after receipt of this letter of the date you plan to submit your responses.

Please contact Mr. Nerses (301-492-7468), St. Lucie 2 Project Manager, if you desire any discussion or clarification of the enclosed report.

Sincerely, gffj(h QpJggnl slglted es Tetiasoo

~1'8 198)e Robert L. Tedesco, Assistant Director for Licensing Division of Licensing

Enclosure:

As stated

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~ 4 Hydrologic Engineering Environmental Reviewer St.

Luci e.Pl ant, Unit 2 Docket No. 50-389 4

t Calculate the radiological consequences of a liquid pathi;'ay release from a postulated core melt accident.

The analysis should assume, unless

, othenvise justified, that there has been a penetration of the reactor hasemat by the molten core mass, and that a substantial portion of radioactively contaminated sump era ter iIas released to the ground.

Doses should be compared to those calculated for the Liquid Pathiray Generic Study (llUREG-0440, 1978) land-based coastal site.

Provide a

summary of your analysis proceCures and the values of parameters used (such as permeabilities,

, gradients, popul ations affected, i;a ter use)

Dr. Robert E. Uhrig, Vice President Advanced Systems and Technology Florida Power 8 Light Company P. 0.

Box 529100 Miami, Florida 33152 ccs:

Harold F. Reis, Esq.

Lowenstein, Newman, Reis, Axelrad 8 Toll 1025 Connecticut Avenue, N. li.

washington, D. C.

20036 doorman A. Coll, Esq.

t icCarthy, Steel, Hec tory 8 Davis 1-;th Floor, First National Bank Building

!',iami, Florida 33131 hr. flartin H. Hodder, 1131 N.

E. 86th Street hiami, Florida 33138 Resident Inspector St. Lucie Nuclear Power Station c/o U. S. Nuclear Regulatory Commission P. 0.

Box 400 Jensen Beach, Florida 33457 i ~

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