ML20069K665

Forwards UCLA Witness List for 830718 Hearing on Inherent Safety Issue.Witness Testimony Will Explain Engineering Principles Underlying NRC Generic Analyses & Respond to Committee to Bridge the Gap Witnesses

ML20069K665
Person / Time
Site:	05000142
Issue date:	04/20/1983
From:	Cormier W CALIFORNIA, UNIV. OF, LOS ANGELES, CA
To:	Frye J, Luebke E, Paris O Atomic Safety and Licensing Board Panel
References
NUDOCS 8304260435
Download: ML20069K665 (3)

Text

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'O cn John H. Frye, III, Chairman Dr. Emmeth A. Luebke Administrative Judge Administrative Judge Atomic Safety and Licensing Board Atomic Safety and U.S. Nuclear Regulatory Commission Licensing Board Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Dr. Oscar H. Paris Washington, D.C. 20555 Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 In the Matter of The Regents of the University of California (UCLA Research Reactor)

Docket No. 50-142 (Proposed Renewal of Facility License)

Dear Administrative Judges:

Enclosed is University's witness list for the hearing on the " inherent safety" issue, which the Board has scheduled to begin July 18, 1983.

Except for its UCLA staff, University has only recently confirmed the participation of these witnesses in the upcoming proceeding. As a result, the precise scope of the testimony of each is not known at this time. However, the scope of the testimony to be presented by University remains unchanged.

University's presentation will be based on the pertinent generic analyses published by the NRC Staff as extended in the analysis conducted by the UCLA staff. University's witnesses will provide testimony both to explain the basic engineering principles which underlie these analyses and to respond to specific matters raised by CBG's witnesses. University's witnesses will not be producing new analyses or studies. Several of University's witnesses will be testifying briefly on a single point only. The topics to be addressed by University's wi~nesses c include some overlap to insure that all areas are covered in the event that a scheduling conflict unknown at the present time may make it

' impossible for a particular witness to participate at the actual time of the hearing.

8304260435 830420 PDR ADDCK 05000142 G PDR

.- Jchn H. Frys, III, Cheirm n Pega 2 Dr. Emmeth A. Luebke .

Dr. Oscar H. Paris April 20, 1983 University understands the scope of the July hearing to be that which the Board described in its Prehearing Conference Memorandum and Order of March 23, 1983 (pp. 4-12),

Accordingly, University does not plan to include in its testimony a consideration of the possible dose consequences of accidents, sabotage scenarios, nor the safety implications of the use of low-enrichment fuel. Moreover, the University does intend to rely on the relevant NRC generic analyses in the manner in which such analyses'are commonly used in NRC proceedings.

University notes these matters only because CBG has recently made requests to alter the scope of the hearing and these requests are still pending before the Board. In the event the scope of the upcoming hearing is changed University will have to reconsider its witness list.

Respectfully submitted, LJ'~7 William H. Cormier Representing UCLA Enclosure cc: Service List (w/ enclosure)

UNIVERSITY'S EXPERT WITNESS LIST July 18, 1983 Hearing bur. Neill Ostrander, UCLA - overall review of Argonaut reactor safety analyses extended to the specific case of the UCLA research reactor.

Prof. Ivan Catton, Ph.D., UCLA - review of thermal-hydraulics principles as applicable to the core-melt potential of the UCLA reactor. ,

Dr. Stanley Kaplan, Pielard. Lowe and Garrick Consulting Engineers - basic reactor kinetics and "re-criticality".

Dr. Jay Boudreau, Los Alamoa National Laboratory - basic reactor kinetics and "re-criticality".

Dr. Walter Lipinski,-Argonne National Laboratory -

applicability of-SPERT and Borax reactor experiments.

Mr. Stanley O. Johnson, Intermour.tain Technologies (Idaho Falls, Idaho)^- power excursion experience gained from the SPERT series of reactor tests.

Mr. Clyde R. Toole and/or Mr. Jimmy G. Crocker, EG&G (Idaho Falls, Idaho) - large reactivity insertion experience with SPERT series of reactor tests.

Prof. Milton S. Plesset, Ph.D., Caltech - subcooled nucleate boiling as phenomenon responsible for inherent, self-limiting characteristics of plate-type, water-cooled reactors.

Dr. Harry Pearlman, Energy Consultant - combustion and Wigner energy effects and diffusion of radioisotopes in matrices.

Dr. Dana Powers, Sandia Laboratories (Albequeque, N.M.) -

water-aluminum and other chemical reactions.

4 Dr. Craig B. Smith, Applied Nucleonics Co., Inc. (Los Angeles, Calif,) - experimental vibration testing of the reactor and seismic effects on reactor performance.

Dr. Donald Olander, Ph.D., UCB - diffusional release of fission products.

Prof. Harold W. Lewis, Ph.D., UCSB - overview of small research reactor accident potential.

Dr. Walter F. Wegst, Ph.D., UCLA - overview of small research reactor accident potential.

April 20, 1983 l - .

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