ML20070B564

Forwards Resume of a Stephens.Stephens Has Been Appointed to Position of Reactor Administrator for Univ,Replacing H Charyulu

ML20070B564
Person / Time
Site:	Idaho State University
Issue date:	06/22/1994
From:	Clovis R IDAHO STATE UNIV., POCATELLO, ID
To:	Mendonca M NRC
References
NUDOCS 9406300248
Download: ML20070B564 (6)

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June 22,1994 United States Nuclear Regulatory Commission [#' N Washington, D.C. 20555-0001 Attn: Mr. Marvin Mendonca sri,Arl,h, UNIVERSITY

Dear Mr. Mendonca:

Enclosed is a copy of the resume cf Dr. Al Stephens. Dr. Stephens has been appointed to the position of Reactor Administrator for the Idaho State University Reactor Facility replacing Dr. Hary Charyulu who passed away last week.

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["g18,, yo Dr. Stephens qualifications for the position of Reactor Administrator meets Ibcatello, Idaho and exceeds our technical specification regt.rements which reference 8NWo ANSI /ANS standard 15.4.

If you have any questions regarding Dr. Stephens appointment to the position of Reactor Administrator, please feel free to contact me (208) 236-3637.

Sincerely,

1. ((m R. David Clovis Reactor Supervisor Cc: Unihd States Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Attn: Mr. Blaine Murray w/ attachments Phone: * -2 g fr$ 9406300248 940622 PDR ADOCK 0500o284 g\

ge) 23 3338 ISU ls An Equal Opportunity Employer

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RESUME A. G. Stephens EDUCATION Ph.D. Nuclear Engineering, Pennsylvania State University, 1975 M.S. Nuclear Engineering, Rensselaer Polytechnic Institute 1962 U.S. Chemical Engineering, Lafayette College, 19b7 Ph.D. Thesis: Determination of Two Phase Flow regimen by Photon Attenuation 1

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, Joint appointement at University of Idaho and Idaho State University 2/90 to present - Director, Joint Nuclear Enginecring Ph.D.

1 Program Idaho State University (1985-2/1990) 8/86 to 2/90 - Associate Professor, College of Engineering.

Teaching, research, consulting in thermal / hydraulics, reactor nafety. Associato Dean, College of Engineering l 1/85 to 8/86 - Industry Shared Profensor, College of Engineering /EG&G Id,sho. One of four EG&G personnel to cach half time in Idaho State University College of Engineering. Proposed and working toward establishment of a Muasuremento and Control graduate program and Fluid Measurements Laboratory for ISU.

PRINCIPAL TECHNTCAL ACCOMPLTSHMENTS AT INEL

• Conceptual design and proof of principle of LOFT densitometer Conceptual design, development of low energy den-sitometern (used on Semiscale; 2D/23 in Germany, Japan; FIST) and, with J.L. Anderson, development of tha comiucale two-phase flow measurement system

• Advanced development of scanning (reference) densitometer for flow regime dotornination Development and incorporation of optical probe nystemn into Semiscale Development of auxiliary two-phase mass flow measurement techniques including the condenser / catch tank and reflux ineter concepts at Semiccale

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, EXPERIENCE AT INEL (197S-1985) 8/84 to 1/85 - Instrumentation and Control Branch, Enginonring Division. Earlier assigned project leader of EG&G Idaho team assisting DOE Morgantown Energy Technology Center personnel in development, tonting of two-colorlaser transmissomotor end alkalino monitors for coal ganification studios at General Electric Research Center.

8/83 to 8/U4 - Manager Water Reactor Research Test Programu Test Facilities Branch - 25 people including three section supervisors, $2 million annual budget - responsible for conducting Semiscale toot program on schedule and within budget; headed team providing four advanced doncitometern to FIST program.

5/82 to 7/83 - NRC Site Technical Representative at General Electric FIST (Reactor Safety) Test Program. Performed data (Juali f i cation, set up INEL data reduction software for FIST, generated FIST Facility Description report, worked on improved FIST men.aurements.

1/81 to S/82 - Supervicor Semiscalo Program Experiment Planning and Analysis Section - cix people, $500K annual budget -

responnible for specification, analysis and reporting of Somioca3e tents.

8/79 to 1/81 - Supervisor Semiscale Measurement Systems Engineering Section - six people, $500K labor, $500K capital equipment budget - renponsible for design, implementation and operation of measurement systems in Semiscale and development of new measurement techniques. Initial design, construction, operation of Steam-Air-Water test facility.

6/77 to 8/79 - Semincale Advanced Instrumentation Section, Instrumentation Diviolon - Conceptual design and development of low onergy densitometers, and with J.L. Anderson, Development of Semiscale two phace mass flow measurement system. Development of acanning (re f eronco) denoitomet er. Incorporation of advanced densitomoter systems in Semiscale. Development and incorporation of optical proben in Semiscale. Development of auxiliary two- i phanc maan 110w measurement techniques including condenser / catch i tank and reflux meter for Semiscalc.

10/75 to 6/77 - LOFT Advanced instrumentation Section,  ;

Inctrumentation Division. Initiated development work on LOFT embcdded fuel cladding thermucouple. Generated conceptual l

<leuign, initiated development and performed proof of princip:o I testing of LOFT advanced densitometern.

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EXPERIENCE PRIOR TO INEL (1957 - 1975) 1970 - 1975 - Westinghouse Nuclear Energy Systems Design Connultant (8 months), Senior Engineer: Developed at:d applied advanced two-phase flow instrumentation, on-line computerized data acquisition and validation system, and unique two-phase density data reduction computer program in leading effort on ECCS steam / water mixing exporimental program. Provided initial design of experimental loop, reactor main coolant pump

two-phase tent, likewise reactor hot wall and steam / water mixing.

Earlier, as consultant, developed ningle heated tube void fraction measurement program.

1965 - 1966 - Pennsylvania State University Reactor Staff Roccarch Assista.c: Helped install 1-MW TRIGA reactor, obtained AEC reactor operator license and operated I reactor. Investigated experimental criticality results. l l

1962 - 1965 - Westinghouse Astronuclear Laboratory l l

Engineer, Senior Engin**r: Devoloped loops for and performed radiation er:tects tests in NASA Plum Brook Reactor. Produced l initial process and mechanical design, and directed procuromont, ,

installation and operation of water cooled inpile loop. I I

Coordinated design of subcoquent 50 degree R, 20 KW cryogenic helium refrigerator /inpile loop. Prepared significant portions of loop design, hazards, and operation manuals; made design changen; administered operator training.

1961 -

1962 -

Rensselaer Polytechnic Institute Linear Electron Accelerator Laboratory Grtduate Assistant:

Analyzed neutron capture gamma data on iron and tungston, Developed and published improved analytical method of determining half-liven of short-lived isotopes.

Summor of 1961 - New York Stato Electric and Gas Corporation Engineer: OcVeloped technique and calculation to minimize spent fuel reprocessing cost, prepared company report on analysis techniques.

1957 -1960 - Westinghounc Atomic Power Department Junior, Asuistant, Associate Engineer: Dasigned radioactive auxiliary fluid nyntemn in !!R-3, CVTR small commercial nuclear power plants. Prepared system flow diagrams, equipment layout drawings, vperating and test manuals, coct estimatos and equipmont npecitications. Designed heavy water decontamination and rocovery system for CVTR.

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hint. of_Enhligat.i_ous aad_1M.t es l

1. Cr oljnan - Vircipiis Tubo _ Reactor Penort, Wentinghouse l Electric Corp., Atomic Power Department, CVNA-30, June 1959,  !

Contributor 1

2. Stephens, A.G., Optimi.re.sLSpent ruel neprocensing coqt j Study, New York State Electric and Gas Corp., August, 1961. j i

3. Article, "The Integral Plot Method for Measuring Short llalf l Periods", in A__ Manual _of Exper_inents_in Reactor._P3lynics , pp j 157-167 P.A. Valento, Editor, Macinillan Co. , 1963.

4. EXper_iRQBt Design Manua_lmd_Harards Analysis - PJyy__Rrpoh Ref.LQ10LfAc.il11y, Westinghouse Electric Corp. Astronuclear  !

Laboratory, WANL-TNR-119, May,1964 Principal Contributor )

5. Stephens, A.G., Two !!hnpe Simgl.tCoop_QD8vnt Maximum._Elow, i unpublished literature surycy and thenin proposal July, l 1968. l l

6. Stephens, A.G., Lilly, G.P., and Hochreiter, L.E., 1.L114 _

fiq.a_le_DipatLWa t er M i xina Fup_ ort , Westinghouno Electric Corp.

Nuclear Energy Systems Division, WCAP-8307, Septamber, 1974

7. Lilly, G.P. and flochreiter, L.E., 1L3-Scale Steam Watar M1Xing._iloport, Westinghousa Electric Corp. Nuclear Energy Systemu Division, WCAp-8423, April, 1975. Contributor

8. Stephenn, A.G., pe_typi nation of__ILlow 13ecime Chara_qt.cris1{.g.g by PhotionEtenuition, r Ph. D. Thenis, The Penncylvania State University, August, 1975.

9. Stephens, A.G., Low 3n_grgy Densitometet__pevelopment, NRC Annual Instrumentation Review Meeting, Troy, N.Y., March, 1978.

10. Stephenn, A.G., " Application of a Scanning Densitometer for Indicating Flow Rogimes dt. ring Two Phane Flow", articlO in Nucl ear TrchDQlO4Y_Ollaftorly Progress _Rgpott, pp 2-3 0, EGI,G Idaho, Inc., NUREG/CR-0412, TREE 1294, October, 1978.

. 11. Stephenn, A.G., E.gpiscale Program _AdNIlged Instr 11ESAtittipn, NRC 6th Annual Water Reactor Safety Hencarch Meeting, Gaithersburg, MD, Nov., 1978.

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12. Stephens, A.G., Emery, M.A., Hochreiter, L.E., " Local Density Measuromonts in a Steam Water Mixing Zone u; sing the Photon Attenuation Technique", paper in Topien in_Two._Phas.e ll2At__T_ra n t; f g r__ and Flow, pp. 183-191, ASME Winter Meeting, San Francisco, December, 1978.

13. Lasnahn, G.D., Stephenn, A.G., Taylor, D.J., Wood, C.B., X-Ray _and Capgan Day Trannmission Densitomotry,i International col]oquium on Two Phase Flow Instrumentation, Idaho Falls, ID, June, 1979.

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14. Stephens, A.G., Exner _imental Data for pg. termination of J

1]ncertainty of Two Phage _ Mass Flow nato in a Sem_iAcaJe Mod-3 flyntem Spool _Ei iq3_At laLlgruhe Kernf_o_rschtH192entrum, EG&G Idaho, Inc., SEMI-S722, January, 1982.

15. Stephens, A.G., Semis.calo Mod-2A Unner Head Injection _ Tent fierjf%.Resul_tp , Ninth Annual Water Reactor Safety Roccarch Mooting, Gaithersburg, MD, November, 1981.

16. Stephens, A.G., fy;periment Onorat_ing Snecification for l Semiocale Mod-2A Experiments _SOTB-1 a.ind S-IB-2, EG&G 1daho, Inc., EGG-SEMI-5722, January, 1982.

17. Stephens, A.G., Quipl Loo};__ Report for SemiAq_ ale _ Int..erymdiAtt Dreak Tent S -I D_- 1, EG&G Idaho, Inc., EGG-SEMI-5859, April, 1982.

18. Stephens, A.G., Kullberg, C.M., Bourchor, T.J., Qnipk I.co};

Honort for Semin_gM o Intprnediate Break Test S _IB-2, EG&G Idaho, Inc., EGG-SEMI-602.1, August, 1982.

19. Stephens, A.G., Full _ Integral Simulation Test Fa_c.i]ity 11Dsqri nt_ign_ RoDort, General Electric Co., NUREG/CR-2576, EPRI NP-2314, GEAP-22054, October, 1982.

20. A.G. Stephens, FIST Dennitometer Uncertainty Analynis, NUREG/CR-TBD, March 1987.

23. Constitutivo Equations and Property Revisions for TRAC-PF-1/ MOD 1 Manual SCIL-00S-87, January, 1987 - Co-author.