ML19210A921

Repts on 701007 Trip to Facility.Requests Addl Info Re Properties of Packing Matl Between Edges of Control Room Floor & Walls & Expected Behavior Seismic Response in Terms of Shielding Floor from high-intensity Seismic Motion

ML19210A921
Person / Time
Site:	Three Mile Island
Issue date:	10/14/1970
From:	Newmark N NATHAN M. NEWMARK CONSULTING ENGINEERING SERVICES
To:	Case E US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7911010632
Download: ML19210A921 (3)

Text

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Trip Reoort:

Site: 3-Mile Island Nuclear Station Unit I p@I Metropolitan-Edison Company g Harrisburg, Pennsylvania Ogergg Date of Visit: 7 October 1970 t Attendees: AEC OCT] 91970.To6 T{4 / Q p,k D. F. Ross -- DRL f ocCKE[ ctg [3 s D. M. Hunnicutt -- Compiiance 7/

R. Brown -- Compilance 43g p AEC Consultants N . M. Newma r k -- Newma rk & As soc i a te s W. J. Hall -- Newmark & Associates Gilbert Associates, Inc.

H. Lorenz D. Croneberger ,

C. Chen L. Patterson Metropolitan-Edison Comoany R. M. Kiingaman J. L. C. Bachofer, Jr.

D. H. Reppert The morning was devoted to an inspection tour of the facility. Those principal items examined included the containment structure, auxiliary and tur-bine building, and the pump house. Also examined were such items as piping, equipment mounting, tendon gallery, cable trays, etc.

In the af ternoon a technical meeting was held in which the following items were discussed:

(a) Clarification was provided to Gilbert Associates personnel re-garding several statements made in a report to AEC Regulatory Staff, " Adequacy of the Structural Criteria for Three Mile Island Nuclear Station Unit 1" by N. M. Newmark and W. J. Hall, dated December 1967.

(b) Most of the time was spent in reviewing in detail the questions of seismic concern contained in the list of questions dated 16 September 1970, as transmi tted f rom Dr. Peter A. Morris, Director of Division of Reactor Licens-Q. 0_6 /

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Ing, U. S. Atomic Energy Commission, to the Metropolitan-Edison Company, Attention: Mr. J. G. Miller. As a result of this review of the questions and status of the analyses and design, it was believed that the final answers to these questions will be simplified, yet at the same time contain consid-erably more information of engineering significance than would otherwise have been the case.

Drs. Newmark and Hall will undertake review of the Gilb,rt Associates, Inc. topical report on pip!ng in conjunction with the procedures of Biggs and Roesset, as applicable, by the time the answers to the questions are submitted in order to provide a basis for evaluation of the piping design. We shall also review requests BAW-10000 Part I and Part 2 dealing with Reactor Internals and Fuel Assembly Analyses. Comments on these reviews will be transmitted to DRS/DRL AEC in the near future if it appears necessary.

In studying the "aircraf t hardening" that has gone into the design, and as a result of the inspection of the facility, it would be helpful if the project s taf f could obtain additional information about the properties of the packing materials placed between the edges of the Control Room floor and the walls, and its expected behavior under seismic response in terms of shielding the floor from high-intensity seismic motions.

The air coolers were noted to be items of significance from a seismic design standpoint and it is assumed that additional information on this aspect of the design will be transmitted to us in the near future by DRS.

, & G M 0AJ N. M. Newmark cic cc: W. J. Hall lbb)

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