ML20244D471

Forwards AEC W/List of Comments Re Addl Info Required About Seismic Design,Transient Analysis & Accident Design Considerations

ML20244D471
Person / Time
Site:	Nine Mile Point
Issue date:	06/20/1968
From:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
To:	Zabel C Advisory Committee on Reactor Safeguards
Shared Package
ML17055E652	List: IA-89-101, Informs of Completion of Review of Application by Niagara Mohawk Power Corp for Conversion of Util Provisional OL to full-term OL During ACRS 740905-07 Meeting.Concurs in Subj License Conversion IA-89-114, Confirms 740624 Meeting Re Author Review of Util SER & Concurrence Subj to Revs Discussed ML17055E651 ML17055E653 ML20244C683 ML20244C712 ML20244C715 ML20244C728 ML20244C740 ML20244C761 ML20244C768 ML20244C776 ML20244C791 ML20244C807 ML20244C810 ML20244C813 ML20244C816 ML20244C818 ML20244C821 ML20244C825 ML20244C827 ML20244D471 ML20244D475 ML20244D485 ML20244D499 ML20244D512 ML20244D553 ML20244D969 ML20244D979 ML20244D984 ML20244D995 ML20244E011 ML20244E026 ML20244E032 ML20244E123 ML20244E128 ML20244E141 ML20244E163 ML20244E184 ML20244E223 ML20244E231 ML20244E248 ML20244E270 ML20244E353 NUREG-1125, Final Response to FOIA Request for Documents.Forwards App a Documents.App a Documents Also Available in Pdr.Acrs Rept Subj to Request Published in NUREG-1125,Vol 2, Compilation of ACRS Repts
References
FOIA-89-101, FOIA-89-114 NUDOCS 8904210361
Download: ML20244D471 (1)

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UNITED STATES r

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ATOMIC ENERGY COMMISSION

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RECEIVED

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June 20, 1968 1968JUN 21 PM 3 02 Docket No. 50-220 U.S. ATWC DEP.GY C0 91.

/MG@rf COMMITTEEI 5 Rd.CIM SAFHUARDl Dr. Carroll 'J. Zabel

.j Chairman, Advisory Committee

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on Reactor Safeguards i

U. S. Atomic Energy Commission Washington, D. C.

Dear Dr. Zabel:

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I:ichteen copies of the following are transmitted 4

for the review of the Committee:

NIAGARA MOHAWK P0JSR CORPORATION (Nine Mile Point Nuclear Station)

ACRS Committee Members SHB_d__

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AEC letter dated June 6, 1968, with list of HE_.d__

Jet __(__sp.s comments concernin6 additional information WLF_ d__

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required relating to seismic design, transient FAG _/__

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analysis and accident design considerations.

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Sincerely yours, i

Peter A. Morris, Director Division of Reactor Licensing

Enclosures:

As stated above Q

8904210361 890413 PDR J O L,

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