ML19210A904

Forwards Hall & Newmark Final Rept on PSAR & Amends

ML19210A904
Person / Time
Site:	Three Mile Island
Issue date:	07/27/1971
From:	Newmark N NATHAN M. NEWMARK CONSULTING ENGINEERING SERVICES
To:	Case E US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7911010613
Download: ML19210A904 (3)

Text

DATE OF DOCUMENT: DATE RECENED NOJ athan M. Neumark .,- -t e J

... 7-27-71 7 '7-71 rhema, Illinois 618C - wa. = Eu o; aEroar; OrwEa:

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50-289 { Consultant File)

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N;(Must Be Unclassaf ted) REFERRED TO DATE RECENED av OATE review of Fg&R including Andts D Lange 7 71 0 of Three Mila Island Unit 1 ishing Final Report om design Wh2cvsforACTIN ysis.....

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_NATHAN M. NEW. .RK CONSULTING ENGINEERING SERVICES 1114 CIVIL ENGINEERING BUILDING URBANA. ILLINOIS 618ot 27 July 1971 v

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. y Mr. Edson G. Case, Director 'd ,w Division of Reactor Standards

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U.S. Atomic Energy Ccmmission Washington, D.C. 20545 N/h'

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Re: Contract No. AT(49-5)-2667 Three Mile Island Nuclear Station -- Unit 1 Metropolitan-Edison Company and Jersey Central Power and Light Company AEC Docket No. 50-289

Dear Mr. Case:

Upon the conclusion of our review of the Preliminary Safety Analysis Report and Amendments for the Three Mile Is land Nuclea r Station -- Unit 1, Dr. W. J. Hall and I have prepared our final report, which is transmitted to you herewith.

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NATHAN M. NEWMARK CONSULTING ENGINEERING SERVICES 1114 CIVIL ENGINEERING BUILDING URBANA, ILLINOIS 61801 I

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FINAL SAFETY ANALYSIS REPORT FOR THREE MILE ISLAND NUCLEAR STATICN -- UNIT 1 METROPOLITAN-EDISON COMPANY AND JERSEY CENTRAL POWER AND LIGHT COMPANY AEC Docket No. 50-289

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by N. M. Newma rk a nd W. J. Ha l l After our review of the FSAR, including Amendments through No. 20, we believe that the design of the Three Mlle Island Nuclear Station, Unit 1, can be considered adequate in terms of provision for safe shutdown for a Design Basis Earthquake of 0.12g maximum horizontal ground acceleration, and capable otherwise of withstanding the effects of an Operating Basis Earthquake of half this intensity.

Our review was based on consideration, among other things, of the design criteria and results of analyses presented by the applicant for Reactor Internals, Reactor Buildings, Buried Piping, Other Nuclear Piping and Equipment, and Critical Items of Control and Instrumentation.

The Aircraf t Impact Design described by the applicant was also taken into account in our review.

We believe the procedures used and the designs developed are in accord with the state of the art. We conclude that the design incorporates an acceptable range of margins of safety for the hazards considered. ,

1589 180

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