ML20003B811
| ML20003B811 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/20/1981 |
| From: | Ketchen E NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Cole R, Lazo R, Luebke E Atomic Safety and Licensing Board Panel |
| Shared Package | |
| ML20003B807 | List: |
| References | |
| NUDOCS 8102250612 | |
| Download: ML20003B811 (20) | |
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'e UNITED STATES e's -q/'
NUCLEAR REGULATORY COMMISSION
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WASHING TON, D, C. 20555
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February 20, 1981 Robert M. Lazo, Esq., Chairman Dr. Emmeth A. Luebke Administrative Judge Administrative Judge Atomic Safety & Licensing Board Atomic Safety & Licensing Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Washington, D. C.
20555 Dr. Richard F. Cole, Administrative Judge Atonic Safety & Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C.
20555 In the Matter of DUKE POWER COMPANY (William B. McGuire Nuclear Station, Units 1 and 2)
Docket Nos. 50-369 and 50-379 Gentlemen:
On February 17, 1981, the Staff served the NRC Staff Analysis of Hydrogen Control Measures as its testimony in the re-opened proceedings in response to the contentions of Carolina Environmental Study Group (CESG).
In accordance with our statements in the cover letter transmitting the Staff Analysis, we are filing with this letter the names of the NRC Staff witnesses who will sponsor the Staff Analysis, and the professional qualifications of the Staff witnesses.
Also enclosed is a more legible copy of the Sandia National Laboratories report (including page 5 which was inadvertently omitted) dated February 9, 1981, which is attached as Appendix B to the Staff Analysis.
Sincerely, A
~W3 Edward G. Ketchen Counsel for NRC Staff Enclosures as stated cc (see page 2) 8102250 /a/A L
P cc (w/ encl.):
William Larry Porter, Esq.
Mr. Jesse L. Riley Dr. John M. Barry J. Michael McGarry, III, Esq.
Mr. David E. Smith Diane B. Cohn, Esq.
Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Appeal Panel Secretary
3-NRC STAFF WITNESSES Ralph A. Birkel, Proiect Manager Dr. Walter R. Butler, Containment Systems Charles G. Tinkler, Containment Systems Harold E. Polk, Structural Engineering Dr. F. Lowell Greinan, Ames Laboratories, Iowa State University, Anes, Iowa James F. Meyer, Reactor Systems John K. Long, Reactor Systens Vincent S. Noonan, Materials & Qualifications Engineering Krysztof I. Parczewski, Materials & Qualifications Engineering ZOLTAN R. ROSITOCZY Materials & Qualifications Engineering W
f PROFESSIONAL QUALIFICATIONS Walter R. Butler Containment Syster Branch Division of Systems Integration Office of Nuclear Reactor Regulation I have been employed by the NRC/AEC since 1967.
I am presently assigned as Chief, Containment Systems Branch, Division of Systems Integration, Office o' Nuclear Reactor Regulation.
In this position, I am responsible for managing the staff's technical reviews, analyses, and evaluations of the containment functional design, subcompartment analyses, heat removal systems, isolation systems, control of combustible gases, and leak testing.
The object of these activities is to assure that, for these areas, licensed nuclear power plants are built and operated without undue risk to the health and safety of the pub-lic.
I have been assigned to this position since July 1078.
From July 1976 to July 1978, I was assigned as Chief, Plant Systems Branch.
This Branch had responsibilities for technical reviews of all operating nuclear power plants in the areas of containment systems; electrical, instrumentation and control systems; auxiliary systems, and fire protection.
From 1972 to 1976, I was assigned as a Branch Chief for a number of different LWR projects branches.
These branches had responsibilities for managing the staff's reviews of applications for construction pemits and operating licenses.
From 1967 to 1972, I was assigned as a project leader for the staff's reviews of various appli:ations for construction permits.
From 1957 to 1967, I was employed by the Aerojet General Corporation.
I held various positions from nuclear engineer thru supervisor for reactor analysis.
I performed and supervised analyses and tests in the areas of reactor physics, shielding, heat transfer and controls.
My academic training is as follows:
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1956: BS in electrical engineering, University of Cal.'(Berkeley);
2.
1957: MS in engineering science, University of Cal. (Rerkeley);
3.
1967: MBA in production management, Cal. State Ifniversity (Sacramento); and 4.
1971: PhD in nuclear engineering, University of Md. (College Park).
I am a registered professional engineer in the State of California and a member of the American Nuclear Society.
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PROFESSIONAL QUALIFICATIONS Charles G. Tinkler, Jr.
I am a Containment Systems Engineer in the Containment Systems Branch of the Office of Nuclear Reactor Regulation, U. S. Nuclear Regulatory Commission.
In this position, which I have held since May 1976, I am responsible for the review and technical evaluation of containment related aspects for PWR applications for both construction permits and operating licenses. Among the plants for which I have or have had this responsibility are Yellow Creek Nuclear Plant; San Onofre Nucle'r Generating Station, Units 2 and 3; Sundesert Nuclear Plant; and Bellefonte Nuclear Plant.
From June 1979 to March 1980 I was assigned to the Systematic Evaluation Program Branch where I was responsible for the review of reactor and containment systems related a.pects for the Yankee Rowe, R. E. Ginna, and Pali-sades nuclear plant:;. My most recent assignment is the analysis of hydrogen c',n-trol in LWR plants.
From September 1973 to May 1976, I was employed as an engineer in the Nuclear Energy Systems Division of the Westinghouse Electric Corporation, Pittsburgh, Pennsylvania.
My responsibilities included performing safety related analysis pertinent to the licensing of PWR plants, preparing responses to NRC questions and writing appropriate sections of safety analysis reports.
I was principally involved in work related to the licensing of ice condenser containment plants where I also participated in the ice condenser tett program.
From July to September 1973 I was employed by Westinghouse in the Heat Transfer Division where I was responsible for design analysis of waste heat recovery systems.
l I. received a Bachelor of Science in Mechanical Engineering from Virginia Polytechnic
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J HAROLD E. POLK PROFESSIONAL QUALIFICATIONS STRUCTURAL ENGINEERING BRANCH DIVISION OF ENGINEERING 0FFICE OF NUCLEAR REACTOR REGULATION I am a Senior Structural Engineer ti, the Structural Engineering Branch, Division of Engineering, Office of Nuclear Reactor Regulation, U. S.
Nuclear Regulatory Commission, Washington, D. C..
I am responsible for reviewing safety analysis reports with regard to structures and seismic analysis for nuclear power plants assigned to me.
I joined the Division of Engineering in November 1974.
I have served as structural Reviewer for the safety reviews of many plants including Hartsville Nuclear Power Station, Black Fox Station, Arkansas Nuclear One Unit 2, Yellow Creuk Nuclear Plant and New England Power 1 and 2 project.
I hold a Bachelor of Civil Engineering (1958) from North Carolina State College, and did graduate study at North Carolina State College in Structural Engineering.
My 23 years er,erience includes 8 years of dirCraft stress analysis and flight performance with the Boeing Company on the Minuteman Missile Program and the Appolo Project which landed the first men on the moon.
I joined the NRC staff after completing over 4 years of seismic dynamic analysis of nuclear power plants with the Bechtel Power Corporation of which the last 2 years was a Supervisor of a Seismic Analysis Group.
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I am currently a member of the American Nuclear Society, ANS2.2/2.10 Working Group on Seismic Instrumentation and a member of American Institute of Steel Construction, AISC Nuclear Specification Task Committee III.
I am a registered Professional Engineer in the states of Maryland (PE 3075) and Florida (18643).
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Dr. Lowell F. Greimann Professional Qualifications I am an Associate Professor of Civil Engineering at Iowa State University in Ames, Iowa.
I hold a Bachelor of Science degree in Civil Engineering (1964) from Iowa State University and a Masters of Science and Ph.D. in Structural Engineering from the University of Colorado, (1966 and 1968).
My 13 years of experience includes structural research on dynamics of offshore oil platforms and guard rail impact for Southwest Reasearch Institute (1968 -
1973), and at Iowa State University (1973 to present) I teach undergraduate and graduate courses in structural analysis, structural dynamics and finite element analysis.
I am involved in research work in structural vibrations and concrete beam to column connections.
I also perform consulting service in the areas of best estimate and uncertainty analysis of the ultimate strength of nuclear power plants.
I also consult in the areas of structural failure analysis for ordinary civil structures.
I have published 11 articles in the areas of structural dynamics, structural failure mechanisms and analytical procedures.
I have completed 32 research reports on the same subjects.
I am a registered Professional Engineer in the States of Iowa and Colorado and a member of American Society of Civil Engineers, American Railway Engineers Association and the Earthquake Engineering Research Institute.
I have been awarded membership in the following honorary societies, c
Sigma XI, Tau Beta Pi, Chi Epsilon and Phi Kappa Phi.
PROFESJIO!!AL QUAllFICATIONS JAt1ES F. MEYER REACTOR SYSTEMS BRANCH DIVISI0fl 0F SYSTEMS IflTEGRATION My name is James F. Meyer.
I am employed by the U.S. Nuclear Regulatory Com-mission, Washington, D. C.
20555.
I am a Senior Task Manager and, as such-am responsible for analyzing and evaluating tcchnical input for licensing actions in the general areas of severe (core degradation, melt or disruption) accidents in nuclear power plants.
I attended Valparaiso Univeristy, Valparaiso, Indiana from 1958 to 1963, where I received Bachelor degrees in Electrical Engineering and Physics. Upon com-pletion of my undergraduate studies in 1963, I enrolled in the Nuclear Engi-neering Department at the Pennsylvania State University.
In 1965, I received my M.S. degree and in 1968 my PhD, both in the subject area of nuclear engi-neering.
Following graduate studies, I worked for Argonne National Laboratory for about six years. During the first five years, I worked in the Applied Physics Division at ANL on development, planning, execution, analysis, and reporting of experiments on Zero Power (Plutonium) Reactors. My experience was in reactor analysis, fast reactor experiments, and general engineering (designanddevelopment).
In addition to completing the above tasks, my responsibilities included being a reactor supervisor on tuo plutonium test reactors.
From October 1973 to November 1974 I was on loan from ANL to the Atomic Energy Commission (now NRC) working in the Liquid Metal Fast Breeder Reactor Branch.
For about 4 years (including the one year I was on loan from ANL), my duties included analysis, assessment, and evaluation of safety / licensing issues associated with the Clinch River Breedtr Reactor with specific responsibility in the areas of fuels, reactor physics, accident analysis, and core disruption analysis. Accomplishments during this period included publishing reports, establishing licensing criteria and preparation for licensing hearings. IVom l
about August 1977 to August 1978, I had similar responsibilities for the Fast l
Flux Test Facility (FFTF) culminating in contributions to the Safety Analysis Report for FFTF.
The NRC, especially during the period from August 1978 to August 1979, parti-l cipated in the Carter Administration's Non-Proliferation Alternative Systems Assessment Program and the International Nuclear Fuel Cycle Evaluation Program.
I had lead responsibility, representing the Office of Nuclear Reactor Regula-tion, in conducting an independent comparative evaluation of the safety, environmental, safeguards, and licensing issues for the advanced reactors under consideration. Our preliminary assessment has been sent to the Department of Energy and a Report to Congress was prepared.
Because of my experience in the area of severe (core melt) accidents for advanced reactors, I was given similar parallel responsibilities, during
_2_
e the summar of 1979, in the area of Pi!R and BWR severe accidents and severe accident mitigation features. These responsibilities incl 0de analysis and evaluation of Filtered Vented Containment Systems, Hydrogen Control Systems, and Core Retention Devices. Particular licensing applications include the Zion / Indian Point Task Force consideration of mitigating features for these power plants and the scheduled Rulemaking on consideration of degraded or melted cores in safety reviews.
Expanding on the above activities, I am presently a Senice Task Manager responsible for guidance and coordination of MRR licensing activities related to degraded core / molten core accidents.
While working in all of the above areas, I have been responsible for managing a large ($1 million) technical assistance program at various laboratories and universities. Also, I have made numerous presentations before the Advisory Committee on Reactor Safeguards.
During this time period in the evenings I have taught reactor physics courses at the University of Maryland. As a " Visiting Lecturer" I taught three 3-credit graduate level courses in the Fall of 1976 and 1977 and the Spring of 1978.
My honors include Sigma XI, a number of Scholarships and Fellowship awards, and a "High Quality Certificate" presented in July 1978.
I am the author or co-author of several papers involving reactor physics and reactor safety.
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PROFESSIONAL QUALIFICATIONS OF JOHN K. LONG Reactor Physicist, USNRC My name is John K. Long.
I am a reactor physicist in tne Reactor Systems Branch of the Nuclear Regulatory Comnission, business address Washington, DC 20555.
I graduated from Columbia University with a bachelor's degree in Chemical Engineering, 1942.
I was employed by the Hercules Powder Company, 1942-1945, in the manufacture of explosives.
I worked at Wright-Patterson Air Force Base, Dayton, Ohio, 1945-1949, in the development of aircraft materials.
I redeived a Ph. O. in Nuclear Physics from Ohio State University in 1953, and was employed by Argonne National Laboratory from 1955 to 1974. At Argonne I participated in and directed research on reactor critical facilities, analysis of reactor operating phenomena at EBR-2, and development of procedures for criticality control.
I have been employed by the Nuclear Regulatory Commission since 1974 have reviewed many problems related to the licensing of sodium cooled fast breeder reactors, including problems related to the accidental generation of hydrogen and its release in containment.
Since the TMI-2 accident I have participated in accident analyses involving hydrogen problems for the TMI-1, Zion, Indian Point, Sequoyah and McGuire reactors.
A list of recent publications is attached.
List of Publications A. !!. Broonficid, A. L. Mess, P.1. Anundson, Q. L.
Baird, E. F. Bennett, L'. G. Davey, J. !!. Gasidlo, W. P. Keeney, J. K. f.ong and P. L. !!cVean, ZPit-III AssembJics 48, 48A, and 4EB:
The Study of a Dilute Plut enf un-fueled Assembly and its Ytriants, A:~L-7759 (Dec. 1970).
J. K. 1.ong - The Effect of a Metallurgical Thase Change on the Power Coefficient of EER-II.
- ucl. Appl. 10 17 (ac mary,1971).
J. K. Long and E. M. Dean, EER-II Codes for Pescessing Reactivity Data at Fell and Reduced Coolant Flcus.
ASL/ EBP.-020 (May, 19 70).
J. E. Long and D. Meneghetti, Anisotropic Scattering Calculations for a Stainicss Stcel Reficctor.
Trans. /.55 1_5,, 2, - 796 (::ovenber, 19 72 ).
J. K. Long - Shortcenings of the Albedo Approxination in KE: 0 Calculaticns.
Trans. A' S J 7_,
269 (::oved er, 1973)
Safety Evaluation Report, Fast Flux Test Facility, NUREG-0358, August 1978, (J. K. Long responsible for accident consequence analysis)
Final Environmental statement. Clinch River Breeder Reactor Plant, NUREG-0139, February 1977 (J. K. Long responsible for chapters 8, 9, and parts of 11)
Site Suitability Report, Clinch River Breeder Reactor Plant, March 1977, (J. Long responsible for section on containment design)
J. K. Long, A. R. Marchese, T. P. Speis, r. D. Gasser, W. T. Pratt, Radiological and Containment Analysis for a Postulated Fast Reactor Melt Through Accident With Containment Venting, Proceedings of the meeting of the European Nuclear Society on Fast Reactor Safety Technology, Seattle, Washington, Aug. 19-23, 1979 l
_p.
J. K. Long Analysis of the Static Icrer Ct efficient of BP-]I with heduced Coolnnt Flow, ::u.cl.1.ppl. 6.,116 '1909)
J. K. Long, R. W. Hy'.dnan Prc=pt Feedback heactivity in 82-3I, Tranc. A? 3.-
} 2, 2, 6?) (Decenber 1959)
,J. K. Long, The Contributien of Fuel Dpancien to the E3P-II Twer Coeffi-cient, Tranc. A!!S, 12 (Supplement) p. Y:. 'Sen Juan, Tuerte T.ico, October 1959)
W. G. Dwey, A. Broomfield, P.
I. Ac*.uniren, Q. L. Ptird, J. M. G3sidic, W. P. Keeney, J. K. L:ng, E. G. In t).'ch, R. L. 'M e.n, L. A. '.'au ntfo rd,
R. J. P Or.er, h. O
.'erbur,-h.
A hench nrk 2 erie-of Plutanit=-h:eled Fast Critical A.cremblies.
Trtnc. A':S. M,1, 239 (June,1908)
J. K. 1.ong, F. S. Kirn, Fffect of Erduced F1w C:n iltionr. on the Fever Coefficient of K3R-II.
Tr tr.r. A:i3, H, 1, E SO ; Jun e, 1%3)
P. J. Persi :.ni, J. Kellfeln, F. S. Kirn, J. K. T.:ng, R. Smith, Eh-II Pcwer C efficient Vsriati:ns 2: ring Cpcrational Eun 26.
Trant. /J:S, ~31, 1, 281 June, 1% 8)
R. R. Smit)., R. A. Cu rha.n, E. '. L'ynd". :, F. F. Ki r n, J. K. Long, W. B.
Lee.<enctein, J. T. Itdell, 2. E. Bu.p, n~1 P. J. Terzi* ni, Eccent Operatin; Experience with E3E-:~.
Eri;. :;uel. :-nerry Foc. Conf. on the Thysics of
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..oe2 c., n a m u.- m cn
.oma i PP i R. R. rai th, T. E. Ih: p,
R'. A. Cu s h:'.sn, E.
.!. Myn d.an, F. S. hi rn,
'1.
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L cueneteIn, J. K. Len.;, J. T. '3 5 ell, P. J. Terr i.ni, '.. R.. sili n,
Tne Pffe:tr af an Over-Cooled Stainler: Steel Eeflector en the E35-II Power Cuefficient. A!;L-75M.,,';9-33)
P. J. Perciani, T. R. Eury,1. A. Cuslmn, J. K. Lent, D. Kutcra, Analysis of the Variaticn in "he 'ER-II To ter Ccefficient Tn:e tr.10 anket Chance, Trans. AI:3., 11_, 1, 252, ' June, 1963)
F. S. Kirn, ii. K. Long, K. R. Enith, 2frect of the Stainierr-Steel Reflecter on the Power Coefficient of 13E-I, Trans. AI:3 10, 2, 6'48, (I!:vember,1967)
J. K. Long, A. L. Hecs, R. L. McVecn, P. J. Persiani, A. J. Ulrich, Q. L. Siird, R. A. 7.ennett, S. L. Engoiren, FPIF Critical Bperimente -- C:ntrol Fad Siuiien cn ZPE-3 Trann. A?:s., lo,1, 269 (June,1967).
A. M. Rree:.f cld, P. I. A.indmn, W. '). Davey, J. M. Casidle, A. L. Hess, W. P. Keeney and J. K. Lcng "ZTE-3 Ascently Lb: Studies of a Dilute Plute-nium Fteled Anrenbly" Internstienal C:nference on Fast Critical Experiments und 'Iheir Analyris, /C;L-73EC p. 2C5-214.29fd) g
P. J. Ttr:1 ni, T. *.
r.p, R. I..
Cu: 1.m n,.T. L n c, n r.0 '.
.a.,
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5 c f the Vari : tion in the : R-II Fazer Co 'T!c 5 '.nt. Lae to :o.. 2t Ci.n7c,
.n "Isactor ILycic Livicien Annual !<_part; Jul;. 3,1%7 to J ne 30, 1 % S,"
- p. 203, A!!L-7h10.
P. J. Persiani, J. b)) Telz, F. Kirn, J. K l ong, and R. T.i'h, EEE-II P:s.er Coefficient Bariaitions During Operation sl ten 26, in ".Heacter Thycic: Divitien Annual report; July 1,1%7 to June 30,1%8," p. 201, /J L-7410.
P. J. Tersiani, J. K. Long, A. J. Ulrich, and D. A. Kucera, Development of the Critical.b:rerinent Procrn:r. fcr the Fast Puelt Tect Faci 31ty in "Eeactor Thysics Divicion Annus1 R< ;;rt; July 1,1966 to June 30, 1967," p. 232,
/J L-7210.
R. Avery, C. Dickerran, W. Y. Kato, J. K. l ong, A. B. Caith, in " Fact Freeder Reactor 6" P. V. Evv:, c 1., p. 403-h20. Oxford, Tcr.;;c:n Pres:,.1967 rra.
British !!uclear Enerc;; Society C nfernece on Fast Erceder Eeacterc, L:nden.
J. M. Gas!dlo, J. K. Long, R. L. McVean, Critical 5tuiles of a Di3utc Fast Ecactor Core (ZPE-III), Ascc.bly 31) AI.1-633S (Oct:ber,1%1)
A. L. Hecs, W. Gt-. ell, '. K. Leng, R. L. McVran, Critiesl Si dies rf a h O.
liter Uraniua Cxide Fast Ecactcr Core (ZIE-III), Arremb2y 29) A::L-63?6, e.
. lor. 0.
v J. M. Gnsidlo, J. K. Lcng, R. L. McVenn, Critical Studies f n Fast Ecsetrr Core Conta'ning.e nnd Sadiun as Dilucnt (ZP3-III, Acccmb1;. 36,'
Al'L-64@ (.'anuary.pleted Uraniu :
1 CW -
P. I. Ic.undsen, W. Ce. nell, J. K. Long, R. L. McVenn, Critical Studies.f Ur.niu._-Freel ani Uranit=-Fteel-S:diun Fast.:cacter C:re. [Z7R-1I1, Arsc:.-
blics 32 and 33) /J L-6690 (Fcbruary,1963).
J. M. Gacidlo, J.
~. Long, W. P. Ecency, D.'ppler Effect Measurenente, E:dite Void Coefficients, and Critical Studies of a 5000-liter Fast ?:ver Ereeder' Ecactcr by the ?.ro-Zone Method.
ZPR-III, A:senbly L3. /c;L-6838,M:y,196h).
J. K. Leng, R. L. McVean, A. 3. Reynolds, S. L. Stewart, A. Weit: berg, A Ler! don, Critical M2ss of SEFOR Moch-Up in EFR-III. I;ucl. Sci. Eng. 25, hh2-4, 1966).
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F. W. Tnalcott, J. K. Leng, '. G. Davey, W. Y. Ente, S. G. Carpenter, H. A. Merewitz, G. H. Bes ;, Fast Critical Pxperi ent: an:1 Tneir An tlysi:,
A/COI;F. ; 8/F/263,3rd Int. Cenf. Cn reaccrul Uses of Atcraic Enerry,1964).
R. O. Brittan, B. Cerutti, H. V. Lichtenberger, J. K. Long, R. L. McVean, F. 'W. Tr.alcott, M. :s?vich, E. Rice, Hatard Evaluaticn Ecp:rt en the Fast Reactor Zero Tower Experinent (ZPR-III) /CiL-6h08 [Octcher,1961).
J. K. 'L:ng, A. R. Ecer, W. Gc = ell, W. P. E ceney, R. L. McVenn, F. W.
Thalcott in " Physics of.-'ast and Internediate Reactors, Vol.1" p. 061-85 Vienna Internatienu Ate:.ic Enercy /gcncy (1962).
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PROF A IONAL QUALIFICATIONS VINCENT S. N00 NAN U. S. NUCLEAR REGULATORY COMMISSION DIVISION OF ENGINEERING MATERIALS & QUALIFICATIONS ENGINEERING I am currently the Assistant Director for Materials and Qualifications Engineering, Division of Engineering, Office of Nuclear Reactor Regulation.
I am responsible for planning, directing, and supervising the programs and activities of the Materials Engineering, Chemical Engineering, Equipment Qualifications and Quality Assurance Branches in the Division of Engineering. These programs and activities include analyses and evaluations which are to establish, maintain and improve the safety of operating nuclear power plants, and plants under construction or licensing review.
I was the Chief of the Engineering Branch, Division of Operating Reactors, respon-sible for directing and supervising the engineering safety review, analyses and evaluations of materials and structural and mechanical components for reactor facilities licensed for operation, for the evaluation of applications and issuante of construction permits and operating licenses for non-power reactors and for the evaluation of operational and design modifications of ERDA and D0D-owned operating facilities exempt from licensing as requested.
Previous to this-time I was a Section Leader in the Engineering Branch, Division of Operating Reactors, and a technical reviewer of the Mechanical Engineering Branch, responsible for the review and evaluation of design criteria for mechanical components, the dynamic analyses and testing of safety related systems and com-ponents and the criteria for protection against the dynamic effects associated with postulated failures of fluid systems for nuclear facilities.
I was also one of three members of the Mechanical Engineering Seismic Qualification Test Review Team responsible for the review of test methods for the seismic qualification of electrical and mechanical equipment.
I also had the responsibility as the Mechanical Engineering Branch's principle reviewer on the issue of.asynnetric loading on reactor vessel supports resulting from transient differential pressures around the exterior of the vessel and from forces induced in the internal structures within the reactor vessel, a.x
. A summary of my experience includes (1) duties as manager and technical reviewer in all areas of engineering for operating reactors and new plants in the operat-ing license and construction permit stages. These areas include mechanical engineering (structural analysis for seismic, dynamic and static loads for reactor vessel, piping, piping and equipment supports) and all other general mechanical engineering areas including fatigue; (2) civil engineering, including both static and dynamic structural analysis for structures and foundations and other civil engineering related areas for both concrete and metal structures; (3) materials engineering, including analyses for fractural mechanics, stress corrosion cracking for both piping and supports, turbine cracking, nuclear fuel material problems and all other general areas of metallurgical engineering; (4) chemical engineering, including primary and secondary water chemistry and corrosion; (5) fire protection, including the writing and editing of Appendix R to 10 CFR 50; (6) equipment qualification, including both environmental and seismic qualification for both electrical and mechanical equipment; and (7) pump and valve operability. Have good working knowledge of ASME codes.
Prior to joining the U. S. Nuclear Regulatory Commission I was employed with McDonnell Dou;1as Corporation as a group engineer in structural dynamics respon-sible for environmental qualification testing of electrical and mechanical equipment for aerospace applications and for structural dynamics analyses and advanced technology.
Responsible for finite math modeling and complex structures, eigen vector and eigen value (model) analyses, vibration and shock analyses, random vibration and sonic fatigue analyses. Responsible for sub-contractor /
engineering consultant relationships on vibration, shock and acoustic problems.
Closely involved with structural dynamics and computer programs. Conducted seismic response analyses on structures located in underground silos.
Performed math modeling for high (+1000 F) and low (cryogenic) temperature transient analyses for aircraft and silo piping.
Performed near miss shock analyses for missiles and hydrofoils. Responsible for design and vibration, shock and acoustic environ-ments.
In addition, I have had experience as a computer programmer involved in mechanical and statistical programming for Air Force missile charts.
I served as an officer in the United States Air Force as triple rated navigator aboard B-36 type aircraft.
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. 1 My educational experience includes a B.S. in Aeronautical Engineering, St. Louis University, Parks College, Cahokia, Illinois, July 1959; M.S. in Engineering Mechanics, St. Louis University, St. Louis, Missouri (36 credit hours completed, thesis incomplete); M.S. in Engineering Mechanics, University of Missouri, Rolla, Missouri, May 1973 (completed additional 33 credit hours); St. Louis University Law School, St. Louis, Missouri (completed 1 year, June 1970); Air Force Cadet School,1953.
I have published the following papers:
Regulatory Requirements and Research Nseds to Improve Safe Operation of PWR Steam Generator, Inelastic Dynamic Analysis for Reactor Vessel and Primary Coolant Piping Asymmetric LOCA Loads; Shock &
Vibration, Bulletin 44, December 1973; Harpoon Missile Flight Environmental Measurement Program; Shock & Vibration, Dulletin 35, Part 6, April 1966, Structural Response to Impulsive Loading (Pyro-Technic Devices); Sonic Fatigue Structural Analysis,1972; Shock & Vibration, Bulletin 35, Part 2, January 1966, The Vibration Design Approval and Acceptance Test Program for the Gemini Spacecraft-Component, Module and Whole Vehicle Testing; Structural Evaluation -
0AMS and RCS Titanium to Stainless Steel Brazed Tube Joints; plus additional related papers.
I hold professional membership status in ASME Committee, Appendix F, Faulted Loading Conditions; and Alpha Delta Law Fraternity.
I can converse passably in Polish and can read articles, technical materials, etc.
for own use in Scientific Russian easily.
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b PROFESSIONAL QUALIFICATIONS KRZYSZT0F I. PARCZEWSKI
- 9. S. NUCLEAR REGULATORY COMMISSION DIVISION'0F ENGINEERING CHEMICAL ENGINEERING BRANCH I am employed by the U. S. Nuclear Regulatory Commission as a Senior Chemical Engineer in the Chemical Engineering Branch, Division of Engineering, Office of Nuclear Reactor Regulation.
I am responsible for reviewing chemical engineering aspects of nuclear power plants.
Specifically, I am engaged in monitoring the work related to hydrogen generation and control in these plants.
I attended the National University of Ireland and received a Bachelor of Science degree in Chemistry and Physics in 1951. Subsequently I attended London University and received a Dipoloma in Chemical Engineering.
In 1956 I was awarded a degree of Doctor of Philosophy in Engineering by the University of Nottingham.
I am a Registered Professional Engineer in Nuclear Engineering in the State of California.
In 1958 I commenced work at the Central Research Laboratory, Celanese Corporation of America, Summit, N. J. -I worked there until 1961 on various projects related to manufacture of man made fibers. From 1961 to 1966 I was employed by the Research Division of American Standard Co.
in Piscataway, N. J.
I was working on various heat transfer and thermo-dynamical research and development projects.
In 1966 I joined the
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Knolls Atomic Power Laboratory, General Electric Co., Schenectady, J. Y.
I worked on various naval submarine and surface ship projects. I was responsible for analytical and experimental developmental work of primary coolant systems.
I joined the Nuclear Regulatory Comission in 1974 as a reactor engineer in the Office of Nuclear Reactor Regulation and in 1980 I was transferred to my present position.
i PROFESSIONAL QUALIFICATIONS OF ZOLTAN R. ROSITOCZY My name is Zoltan R. Roszteczy.
I am currently employed'by the U.S. Nuclear Regulatory Commission as Branch Chief of the Equipment Qualification Branch, Divisicn cf Engineering, Office of Nuclear Reactor Regulation (NRR).
Prior to the formation of the Equipment Qualification Branch I served as Branch Chief of the Analysis Branch, NRR.
My duties and responsibilities include the supervision of the revies and evaluation of the capabilities of safety related systems and components to perferm their design functions under all normal, abncrmal and accider. cal environcer. cal conditions and in the ever.: of seismic occurer.ces.
I participate in the development of criteria, guides and regulations pertaining to equipment qua l i fi,ca ti en.
I am a graduate of the University of Tecnnical Sciences Hungary.
I have also received a Master of Science degree in Mechanical Engineering frcm the University of California and a Ph.D. in Nuclear Engineering from the University of Ari:ena.
Prior to my appointment with the NRC I was employed by Combustion Engineering Inc.,
Windsor, Connecticut (1964-1973) and by the Institute of Engineering Research, University of California (1959-1952).
During the last six years of my em:loyment witn Cc=bustion Engineering (CE) I served as Manager, Safety Analysis.
In this c pacity I was responsible for directing the safety evaluation of CE su;p'.ied nuclear power systems.
I also coordinated CE's participation in the rule making hearing on Esergency Core Cooling Effectiveness.
- am a member of the American Nuclear Society and of Sigma-Xi.
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