ML20236L672
| 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: |
| References | |
| 5674, NUDOCS 8711110010 | |
| Download: ML20236L672 (1) | |
Text
JUN-8 REC'O gWQ#
m Consumers 1
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General OUices: 213 West Michigan Avenue, Jackson. Michigan 49201 e Area Code 517 788 0550 June 4, 1976
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a Director of Nuclear Reactor Regulation 1
l Att: Mr Robert A. Purple, Chief i-
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Operating Reactor. Branch No 1
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US Nuclear Regulatory Commission Y
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Washington, DC 20555 DOCKET 50-255. LICENSE DPR-20 I
PALISADES PLANT, APPENDIX I SUBMITTAL
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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:
(N) 1.
Such information as is necessary to evaluate the means employed for keeping j
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. levels of radioactivity in effluents to unrestricted areas as lov as is rea-v
.sonably achievable, including all such information as is required by 5 50.34a (b) and (c) not already conte.ined in his application and
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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.
! is a report titled " Appendix I Analysis, Palisades Plant" dated May f
1976. This report submits information as required by Item 1 above.
l 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.
87 David A. Bixel (Signed) lif00 5
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David A. Bixel 1
Assistant Nuclear Licensing Administrator l
,y CC: JGKeppler, USNRC
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