ML20236L672

Forwards App I Analysis,Palisades Plant, Per 10CFR50 App I & Proposed Tech Specs Re Design Objectives & Limiting Conditions for Operation ALARA for Radioactive Matl in light-water-cooled Reactor Effluents

ML20236L672
Person / Time
Site:	Palisades, 05000000
Issue date:	06/04/1976
From:	Bixel D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Purple R Office of Nuclear Reactor Regulation
Shared Package
ML18052B367	List: ML20236L668 ML20236L672 ML20236L680
References
5674, NUDOCS 8711110010
Download: ML20236L672 (1)

Text

JUN- 8 REC'O gWQ# ,

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% Consumers 1

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General OUices: 213 West Michigan Avenue, Jackson. Michigan 49201 e Area Code 517 788 0550 i

June 4, 1976 i )

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Director of Nuclear Reactor Regulation ,, 1 l Att

Mr Robert A. Purple, Chief i- [

Operating Reactor. Branch No 1 .

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US Nuclear Regulatory Commission Y j

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Washington, DC 20555 ,

DOCKET 50-255 . LICENSE DPR-20 I PALISADES PLANT, APPENDIX I SUBMITTAL 'i i

Title 10, Chapter I, Code of Federal Regulations, Part 50, Appendix I, sets q forth numerical guides for design objectives and limiting conditions for opera- l

.. tion to meet the criterion."as low as is reasonably achievable" for radioactive material in light-water-cooled nuclear power reactor effluents. For our Palisades l Plant this regulation required submittal to the Commission of the following:  ;

r' (N) 1. Such information as is necessary to evaluate the means employed for keeping j v . levels of radioactivity in effluents to unrestricted areas as lov as is rea- '

.sonably achievable, including all such information as is required by 5 50.34a  !

(b) and (c) not already conte.ined in his application and {

1

2. Plans and proposed Technical Specifications developed for the purpose or keep- '

ing releases of radioactive materials to unrestricted areas during normal re- l actor operations, including expected operational occurrences, as lov as is j reasonably achievable.  !

Enclosure 1 is a report titled " Appendix I Analysis, Palisades Plant" dated May f 1976. This report submits information as required by Item 1 above. l Enclosure 2 is a proposed Technical Specifications change which would bring the-Palisades Technical Specifications into conformance with Item 2 above.

The analysis (Enclosure 1) states that we are designing an internal recirculat- f ing air system for containment which would have a capacity of about 12,000 cfm.

Since the issuance of this analysis ve have concluded that the need for this ,

l system should be further reviewed. We vill advise you of the results of this l review should we decide to delete this item or make significant changes in its j design over that presently described.

David A. Bixel (Signed) 87 lif00 5

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) David A. Bixel Assistant Nuclear Licensing Administrator ,y 1

,, . l CC: JGKeppler, USNRC '

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