ML20090F814

Resume of RW Keaten

ML20090F814
Person / Time
Site:	Three Mile Island
Issue date:	01/04/1982
From:	Keaten R GENERAL PUBLIC UTILITIES CORP.
To:
References
TASK-10, TASK-GB B&W-0336, B&W-336, NUDOCS 8307070312
Download: ML20090F814 (4)

Text

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Ex. 38 For ID

/ '/-#c;2. J.R. Danyo ROBERT W. KEATEN l

l Business Address: GPU Service Corporation

( . 100 Interpace , Parkway Parsippany, New Jersey 07054 Education: B.S., Physics, Yale University,1957.

Post-Graduate and Professional Courses in Mathematics, Engineering and Business, UCLA, 1960-1972.

Experience: Manager, Systems Engineering Depart-ment, GPU Service Corporation, April 1978 to present. Responsible for the development and application of specialized analytical skills in such areas as nuclear core reloads and fuel management; plant dynamic and safety analysis; system generating plant process computers; control and safety systems analysis, and analysis of plant operating performance for 1

, , , nuclear and fossil plants. Served as

, Deputy Director of Technical Support at Three Mile Island during the post-accident period.

Program Manager, Light Metal Fast Breeder Reactor Technology, Atomics

. International Division of Rockwell International,1974 to 1978. Managed research and development programs -

performed for U.S. Department of Energy, including programs in reactor physics, safety and component development.  ;

Manager of Systems Engineering, Light Metal Fast Breeder Reactor Program, Atomics International Division of '

Rockwell International,1968 to 1974.

Responsible for performance of safety analyses, development of safety 8307070312 820104 criteria and development of instru-PDR ADOCK 05000289 mentation, control and safety systems P

HOL design.

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American Representative to the CECD

'N Halden Reacter Project in Norway, 1965-1968. Participated in research on nuclear fuel performance, appli- ,

cation of digital computers to nuclear .'

, reactors, and on development and application of in-core instru- l mentation.

Supervisor of Engineering, Sodium Reactor Experiment, Atomics International, Divirion of Rockwell

. International, 1962-1965. '

Responsibilities included analysis and measurement of the nuclear heat transfer and hydraulic parameters of the- reactor core and process systems; specification and installation of nuclear and process instrumentation; design and installation of new control systems.

Senior Physicist, Sodium Reactor Experiment, Atomics International, Division of Rockwell International, 1959-1962. Performed measurements and

.- analyses of the nuclear ,acd thermal

,, , parameters of the reactor.

Experimental Physics Group, DuPont Savannah River Plant, 1957-1959.

. Performed measurements and calcula-tions of the nuclear parameters of the reactor lattices.

Honors and Pro f e ssional Affiliations: Member of the Nuclear Power Plant

, St'andards Steering Committee of the American Nuclear Society.

Member and past Chairman of the LMFSR Design Criteria ( ANS-54) Standardz I

, Committee of the American Nuclear Society. i Registered Professional Engineer (Nuclear Engineering) , California. l A e*

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Publications: " Analysis of TMI-2 Sequence of Events

! Operator Response," presented to a special session of the American Nuclear Society Conference, San Francisco, November 1979; and to Edison Electric Institute Conference,

. Cleveland , October 1979.

"The Role of Instrumentation in the TMI-2 Accident," presented at the American Nuclear Society Conference, June 1980.

Safety and Environmental Aspects of Liquid Metal Fast Breeder Reactors" 35th Annual American Power Conference, Chicago, Ill., May 1973.

" Safety Aspects of the Design of Heat Transfer Systems in LMFER's" International Conference on Engineering of Fast Reactors for Safe and Reliable Cperation, Karlsruhe, Germany, Cetober 1972.

" Safety Criteria and Design for an FBR Demonstration Plant," ASME Nuclear Engineering CocJerence at Palo Alto, Calif., March 1971.

" Evaluation of Thermocouples for Detecting Fuel Assembly Blockage in LMTBR's," American Nuclear Society Annual haeting, Los Angeles, California, June 1970.

"A Mathematical Model Describing the Static and Dynamic Instability of the SRE Core II," Reactor Kinetics and Control, AEC Symposium Series 2.

( Also published as NAA-SR-8431. )

" Reactivity Calculations and Measurements at the SRE," ANS Topical Meeting : Nuclear Performance of Power-Reactor Ceres, September 1963.

" Measurement of Dynamic Temperature Coefficients by Forced Cscillations in Coolant Flow," Trans-American Nuclear Socie tv 5, No . 1, June 196 2.

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, ' Analysis of Power Ramp Measurements with an Analog Computer,' Trans-American Nuclear-56,ciety 5, No. 1, June 1962.

" Reflected Reactor Kinetics,"

NAA-SR-7263.

Many other reports covering analytical and experimental work.

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