ML20212R666
| ML20212R666 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 12/22/1986 |
| From: | Norton B PACIFIC GAS & ELECTRIC CO. |
| To: | |
| References | |
| CON-#187-2328 OLA, NUDOCS 8702030032 | |
| Download: ML20212R666 (66) | |
Text
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232F UNITED STATES OF AMERICA
. ; ! il NUCLEAR REGULATORY COMMISSION N
BEFORE THE ATOMIC SAFETY AND LICENSING-AREc 29 P4 :51
)
DocketNos.M4275-06A' In the Matter of
)
50-323"**d 6 A
)
PACIFIC GAS AND ELECTRIC COMPANY )
(Reracking of Spent Fuel Pools)
)
(Diablo Canyon Nuclear Power
)
Plant Units 1 and 2)
)
December 22, 1986
)
LICENSEE PACIFIC GAS AND ELECTRIC COMPANY'S RESPONSE TO ASLB MEMORANDUM AND ORDER DATED DECEMBER 1. 1986 In its Memorandum and Order dated December 1, 1986, the Atomic Safety and Licensing Board (ASLB) directed the parties to this proceeding to file information on their direct case by December 23, 1986. The ASLB order required five items from each of the parties:
(1) Witnesses who will testify on their behalf; (2) Lists of exhibits they intend to introduce; (3) Documents upon which the witnesses will rely; l
(4) List of documents the parties intend to use on cross-examination (unless disclosure would compromise the cross-examination); and l
l (5) A brief description for all witnesses listed (no longer than two l
pages for each witness) of the views and position on the issues about which they will testify.
Licensee Pacific Gas and Electric Company's (PGandE's) response to this Board order is contained below.
8702030032 861226
$DR ADOCK 05000275 3So3 PDR
Item (1): Hitnesses who will testify on their behalf.
Resoonse to Item (1): Hitnesses who will testify on behalf of PGandE are identified below. A statement of professional qualifications of each of the witnesses is provided in Attachment 1.
List of Hitnesses Shankar Bhattacharya, Pacific Gas and Electric Company Edward C. Connell, III, Pacific Gas and Electric Company Leonard T. Gesinski Westinghouse Electric Corporation Bryant H. Giffin, Pacific Gas and Electric Company A. Burtron Johnson, Jr., Battelle Northwest Laboratory Gerald R. Kilp, Westinghouse Electric Corporation Burton Paul, University of Pennsylvania James D. Shiffer, Pacific Gas and Electric Company Krishna P. Singh, Holtec International Stanley E. Turner, Southern Sciences Hilliam H. White, Bechtel Western Power Corporation ItJLm_121:
Lists of exhibits they intend to introduce.
Resoonse to Item (2):
The list of exhibits which PGandE witnesses intend to
(
j introduce is given in Attachment 2.
Item (3): Documents upon which the witnesses will rely.
Reinonse to Item (3):
The documents upon which PGandE witnesses will rely are identified in Attachment 3.
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Item (4): List of documents the parties intend to use on cross-examination (unless disclosure would compromise the cross-examination).
Resoonse to Item (4): Some of the documents which PGandE intends to use on cross-examination are listed below.
PGandE may wish to use other documents not identified here. However, at this time PGandE does not intend to provide a complete list of documents which will be used on cross-examination, since disclosure of the other documents may compromise the cross-examination.
List of Cross-Examination Documents Affidavits of Richard B. Ferguson, June 16, 1986; August 4, 1986 and September 16, 1986 Affidavit of Philip H. B. Niles, September 16, 1986 Affidavit of Jake Feldman, July 14, 1986 Sierra Club's Response to First Set of Interrogatories from PGandE and the NRC, October 3, 1986 Sierra Club's Response to PGandE's Second Set of Interrogatories, November 6, 1986 Deposition of Richard B. Ferguson, December 5,1986 (Transcript)
All documents listed in Attachment 2, " List of Exhibits" Item (5): A brief description for all witnesses listed (no longer than two pages for each witness) of the views and position on the issue about which they will testify.
Resoonse to Item (5): While there will be a number of witnesses appearing on PGandE's behalf, these individuals will be presented in groups and their testimony will be presented in panel form.
Each panel will address the issues separately raised in each of the contentions and the testimony of the panel
represents the views and position of the group of witnesses comprising the 4
panel.
Thus, the response to this item is provided for each panel, rather than for each individual witness. Panel I will address the structural and criticality issues contained in Sierra Club Contentions I and II, and consists of S. Bhattacharya, L. T. Gesinski, B. Paul, K. P. Singh, S. E. Turner, and W. H. White.
Panel 2 will address the issues raised by Nothers for Peace Contention 1 relating to alternatives and consists of J. D. Shiffer, E. C.
Connell, and B. H. Giffin.
Panel 3 will address the issues raised by Consumers Organized for Defense of Environmental Safety Contention 14 on neutron embrittlement, metallurgical deterioration, and environmental stresses, and consists of S. Bhattacharya, A. B. Johnson, G. R. Kilp, and H. H. White. The views and position of each of these panels are provided in.
Respectfully submitted, ROBERT OHLBACH PHILIP A. CRANE, JR.
RICHARD F. LOCKE Pacific Gas and Electric Company P. O. Box 7442 San Francisco, California 94120 (415) 781-4211 BRUCE NORTON c/o P. A. Crane Pacific Gas and Electric Company P. O. Box 7442 San Francisco, California 94120 l
Attorneys for l
Pacific Gas and Electric Company i
j By Bruce Norton DATED:
December 22, 1986 1
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ATTACHMENT 1 f
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ATTACHMENT 1 PROFESSIONAL OUALIFICATIONS Shankar Bhattacharya Edward C. Connell III Leonard T. Gesinski Bryant W. Giffin A. Burtron Johnson, Jr.
Gerald R. Kilp Burton Paul James D. Shiffer l
Krishna P. Singh Stanley E. Turner Hilliam H. White l
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I PROFESSIONAL OUALIFICATIONS OF 2
SHANKAR BHATTACHYARYA 3
My name is Shankar Bhattacharya.
I am a Senior Civil Engineer at 4
5 Pacific Gas and Electric Company. Currently, I am the deputy group 6
supervisor of the Civil Engineering section of the Diablo Canyon Project. My responsibilities include providing assistance to the y
group supervisor in supervision, direction, and execution of all technical and administrative tasks related to the Diablo Canyon l
Power Plant.
I am a Registered Professional Civil (No. C22884) and 10 Mechanical (No. M016656) Engineer in the State of Californi,a and am
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a member of the American Society of Civil Engineers. I am also a member of Standards Committees (Committee No. 2.2, 2.10 and 2.23)
D for the American Nuclear Society.
15 My educational background includes:
B. Tech. (Hons.) Civil Engineering, Indian Institute of Technology; MS, Civil Engineering, Bucknell University, Pennsylvania; Doctoral Fellow in Civil Engineering at University of California, Berkeley; and MBA, University of California, Berkeley.
21 Prior to my involvement in the Diablo Canyon Project, I was a design supervisor at Bechtel Power Corporation's San Francisco Power Division office. My responsibilities for Bechtel included supervision and direction of engineering analysis and design related to construction of power plants, including nuclear facilities.
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Earlier I was an associate civil engineer for the East Bay Municipal 2
Utility District.in Oakland; California, where I was responsible for 3
static and dynamic analysis work associated with miscellaneous hydro 4
projects.
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9 10 11 U
13 14 15 16 17 18 19 20 l
21 22 23 24 25 26 8
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EROFESSIONAL QUALIFICATION OF EDWARD C. @_NELL III My name is Edward Connell. I am a Supervising Engineering for the Pacific Gas and Electric Company. Currently, I am the Engineering Group Supervisor of the Mechanical Systems Group for the Nuclear Engineering and Constructions Services Department.
I am responsible for the supervision of all aspects of mechanical and nuclear systems design for Diablo Canyon. Among other things, the evaluation and procurement of the high density spent fuel storage racks and the design of the supporting systems for the spent fuel pools were performed under my supervision.
l My educational background includes: Bachelor of Science - Nuclear Engineering, University of Lowell; Master of Science - Nuclear Engineering, Purdue University.
Prior to my assignment on Diablo Canyon, I was employed by the Bechtel Power Corporation as a Senior Engineer. Among other assignments at Bechtel. I was the Nuclear Group Leader and Deputy Engineering Group Supervisor for the Susquehanna Steam Electric Station.
I was responsible for the design of all nuclear related systems, including high density spent fuel storage racks and supporting systems.
Previously, I was employed by Fluor Power Services as a Senior Engineer.
There I performed analysis and various other engineering tasks for four Westinghouse PHRs.
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STATENENT OF PROFESSIONAL QUALIFICATIONS AND EXPE LEONARD T. GESINSKI Ny name is Leonard T. Gesinski and my business address is P.O. Box 3912, Pittsburgh, PA 15230.
I an employed by Westinghouse Electric Corporation (Westinghouse) as a Fellow Engineer in the Nuclear Fuel Division.
I graduated from Pennsylvania State University with a Bachelor of Science Degree in Engineering Nechanics in 1961 and a Master of Science Degree in Engineering Mechanics in 1963.
I also completed 27 credits of graduate study in Mechanical Engineering at the University of Pittsburgh.
In June 1967. I joined Westinghouse in the Pressurized Water Reactor System Division.
I was responsible for the structural dynamic analyses of reactor internals under various accident conditions. I was directly involved in the development of structural codes and in the dynamic analysis of reactor internals.
In March 1969, I was transferred to the Nuclear Fuel Division of Westinghou where I was responsible for developing analytical methods for evaluating i
nuclear fuel assemblies under seismic and loss of coolant (LOCA) accid conditions. These analyses required the use of non-linear finite element structural analysis codes and substantial amounts of tast information.
I was responsible for defining and conducting the various types of fuel assembly and component tests used in support of the fuel assembly structural analysis.
I authored numerous reports on the subject of fuel assembly accident analysis and structural testing. Thenon-lineardynamicanalysis(timehistory) esthods, which I initially developed (circa 1972) were eventually approved by the NRC and have been adopted by the various nuclear fuel' vendors as a standard for evaluating fuel assembly seismic performance.
As a part of that effort, I also developed a complex non-linear finite element structural model to represent the mechanical response of a fuel assembly.
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In November 1975, I was promoted by Westinghouse to Fellow Engineer with responsibility for specifying the fuel rod design parameters for first cores and reloads.
I also have been responsible for directing and training other engineers in the area of fuel assembly structural analysis. I have been involved in numerous mechanical analyses and tests of various fuel assembly components and designs.
I am currently responsible for performing the I
anchanical analysis of boiling water reactor (BWR) type fuel.
From 1963 to 1965, I was employed by Westinghouse at the Astro Nuclear l
Laboratory where I was responsible for conducting vibration testing of nuclear rocket reactor components.
From 1965 to 1967, I was employed by Rockwell Nfg. in Pittsburgh, PA as design engineer. My principal duties included design and development of high pressure valve products.
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PROFESSIONAL QUALIFICATIONS OF BRYANT N. GIFFIN Hy name is Bryant M. Giffin. I am a Supervising Nuclear Generation Engineer in the Nuclear Power Generation Department of Pacific Gas and Electric Company. My responsibilities include supervision and direction of nuclear i
fuel-related engineering analyses for the Diablo Canyon Nuclear Power Plant.
My educational background includes:
B.S. in Electrical Engineering, North Carolina State University Degree of Electrical Engineer, North Carolina State University.
Prior to my present position, I was the Instrumentation & Controls Maintenance Manager at Diablo Canyon. My other position with PGandE was as a Senior Nuclear Generation Engineer in Nuclear Power Generation.
Prior to my employment with PGandE, I served in the U.S. Navy for 21 years.
The last 13 years was as an officer in the Navy's Nuclear Power Program.
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Dr. A. Burtron Johnson, Jr.
Senicr Staff Scientist Matsrials Department Battelle-Northwest Richland, Washington 99352 Education - B.S., Fuel Technology, University of Utah,1954, with honors; Ph.D., Fuel Technology, University of Utah, 1958; distinguished graduate, Air Force ROTC 1956; elected to Phi Kappa Phi.
l Areas of Specialization l
Metallic corrosion and hydriding in high temperature aqueous environ-ments, with and without nuclear radiation.
Nuclear reactor decontamination.
Reactor behavior of Zircaloy components, including failure analysis of nuclear fuel.
l Behavior of irradiated nuclear fuel in wet and dry storage.
Durability of ancient metals.
Nuclear plant aging and life extension.
Experience Joined the General Electric Co. at Hanford in 1961 and studied corrosion of aluminum and zirconium alloys under simulated nuclear reactor conditions.
Transferred to Battelle-Northwest in 1965 and studied effects of nuclear radiation on the aqueous corrosion of several metals including Iriconel, stainless steel, titanium, but with principal emphasis on zirconium alloys.
Investigated in-reactor failure mechanisms for Zircaloy-clad fuel.
Has performed assessments and investigations of corrosion, stress corrosion, and decontamination of reactor coolant system materials.
Since 1963 has observed and participated in fuel handling operations in spent fuel pools at production, test, and connercial reactors. Since 1977, has been involved in wet and dry spent fuel storage technologies in the follgwing capacities: as program manager for spent fuel integrity studies and spent fuel exami-nations; as the U.S. representative to the BEFAST* coenittee and a delegate' to DECD/NEA and IAEA spent fuel storage specialist meetings; as a witness at several spent fuel pool modification hearings and a contributor to the NRC l
Waste Confidence Rulemaking documentation; as the lead consultant for an i
IAEA/NEA international survey of spent fuel storage experience; as a speaker l
on spent fuel storage to the NRC Commissioners.
Is project manager for investigation of nuclear plant component aging. Taught physical chemistry at the University of Dayton (1960-61); was attached to the staff at the University of Wisconsin (1973); and teaches nuclear materials courses at the Richland Joint Center for Graduate Study. He was chairman of the National Program Connittee for NACE (1982/83) and is a member of ANS and ASTM. He has l
authored approximately 320 reports and publications, including approximately i
l 40 which deal with spent fuel storage.
- Behavior of Fuel Assemblies in Extended Storage; first organized under NEA(Paris);transferredto1AEA(ViennaT
Dr. A. BURTRON JOHNSON, Jr., (continued)
Experience Thirty years of experience with performance and degradation studies e
on materials used in nuclear plants, including effects of nuclear radiation on behavior of aluminum, Inconel, stainless steels, niobium, titanium, and zirconium alloys.
Detailed knowledge of BWR and PWR coolant chemistries.
Detailed knowledge of nuclear materials behavior (emphasis on corrcsion),
Program manager for AEC radiation effects studies on reactor materials.
o Program manager for EPRI p'rogram on BWR and PWR coolant system decon-tamination.
Program manager for EPRI Trojan U-bend stress corrosion cracking study.
Program manager for DOE program on stainless steel stress corrosion e
cracking.
Task leader on Surry Steam Generator Program.
e Program manager for study of ancient metal durability (multicentury durability of archeological metals, metal meteorites and native metals).
Participated in IAEA and DECD/NEA nuclear programs.
Nuclear industry contacts in Belgium, Finland, France, FRG, India, Japan, The Netherlands Norway, Spain, Sweden. Switzerland and UK.
Twenty-two years of experience dealing with U.S. nuclear organizations,-
e including AEC/ERDA/ DOE; NRC; EPRI; nuclear steam system suppliers; and numerous utilities.
Pro.iect manager for nuclear plant aging / life extension Conducted the following surveys:
e Behavior of materials in dry cooling tower applications; published I
in BNWL-1958, Behavior of U.S. and Canadian spent fuel an'd storage pool components; published in BNWL-2256, Behavior of U.S., Canadian, European and Japanese spent fuel and storage system. components in dry stcrage; published in PNL-4189, Durability of ancient metals, published in BNWL-3198.
Lead Consultant for IAEA/0 ECD world survey of spent fuel storage experience; published in IAEA Technical Report Series No. 218.
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ah Dr. A. BURTRON JOHNSON, Jr., (continued)
Appeared as a witness at the following hearings,(see expanded list):
Trojan Reactor ASLB Hearing Trojan Reactor District Court Hearing California Energy Comission Hearing Zion Reactor ASLB Hearing Accomplishments B.S. degree with honors.
e Elected to Phi Kappa Phi (National Scholastic Society),1958, University of Utah.
Appointed Distinguished Graduate Air Force ROTC, University of Utah, e
l 1956.
l Appointed Visiting Felics at Battelle Seattia Resrarch Center for six e
weeks, 1972.
Invited to join University of Wisconsin Nuclear Engineering faculty for six months, 1973.
Appointed chaiman of PNL Fusion Comittee,1973.
Appointed to the program comnittee for Second Topical fleeting on the i
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Technology of Controlled Nuclear Fusion,1976.
Appointed chaiman of National Association of Corrosion Engineers (NACE) national comittees:
Unit Comittee T11A, Nuclear Systems 1975-47 Group Comittee Til, Thermal Power Systems 1947-79 Appointed chairman of NACE National Program Comittee for term 1981-1983.
Involves responsibility for technical program at NACE national meetings for CORROS10N/82 (Houston) and CORROSION /83 (A6aheim).
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Invited to make presentation on spent fue1 storage to NRC Comissioners, in Washington. D.C.,1978.
Appointed U.S. representative to OECU (Paris) Comittee (BEFAST ) on e
spent fuel storage.
Appointed lead consultant for joint BEFAST/IAEA World Survey of Spent Fuel Storage Experience, including interpretation and publication of survey resul ts.
- Behavior of F_uel psemblies in p_orage
1 Dr. A. BURTRON JOHNSON, Jr., (continued)
Appoir,ted to U.S. delegation for International Fuel Cycle Evaluation e
(INFCE) Working Group No. 6; attended INFCE meetings in Vienna (1978) and Madrid (1979).
Invited to participate as a member of U.S. team designing an inter-national fusion reactor (INTOR),1979.
Invited by IAEA to serve as a consultant on spent fuel storage,1980.
e Invited by IAEA (Chief of Nuclear Materials and Fuel Cycle Branch) e to write a sunnary of advances in zirconium alloy corrosion technology, 1
1980/1981.
Appointed to DOE He'adquarters team developing testimony for NRC Nuclear e
Waste Confidence Hearings,1980.
j Invited to serve as session chairman for international meetings in e
Brussels and Madrid,1982.
Appointed US Coordinator for US/FRG Spent Fuel Information Exchange e
Chairman for International Symposium / Workshop on Spent Fuel Storage.
Seattle, April 1986.
Coauthored
- 65 technical papers presented at national / international e
meetings in Canada. England, The Netherlands Spain, and The United States of America.
Published over 100 journal articles and technical reports (publication e
list available on request).
Selected for American Hen of Science and Who's Who In Technology.
e Academic A.
Teaching Experience Taught upper division / graduate classes while in graduate school, e
University of Utah, 1956-58.
By invitation, taught upper division Physical Chemistry at the University of Dayton while in the USAF, 1960/61.
Invited to join the Nuclear Engineering faculty at the University of Wisconsin for six months,1973.
Member of short course faculty. MIT,1977.
e Designed the curriculum for :nd teaches three courses at the Joint Center for Graduate Study:
Nuclear Engineering 444 - Nuclear Reactor Materials Nuclear Engineering 554 - Fusion Reactor Haterials i4aterials R501 - Corrosion and Stress Corrosion 1
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O Dr. A. BURTRON JOHNSON, Jr., (continued)
B.
Invited Seminars University of Utah,1965.
University of Washington, 1970.
AECL, Whiteshell, 1972.
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University of Wisconsin,1973.
Joint Center for Graduate Study, 1975.
Massachusetts Institute of Technology,1977.
Seattle University,1977.
Wurenlingen Institute (Switzerland),1981.
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i Seminar also Presented in 1983.
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SUIMARY OF SPENT FUEL STORAGE ACTIVITIES A. 8. Johnson, Jr.
SPENT FUEL POOL HEARING APPEARANCES AND RELATED ACTIVITIES 1977 California Energy Commiission hearing 1978 Trojan Reactor ASL8 Fuel Pool hearing 1978 Spent Fuel Storage Presentation to NRC Commiissioners 1978 Trojan Reactor District Court hearing U.S. Delegate to INFCE ") Working Group No. 6 I
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1978/1979 meetings Vienna / Madrid Assisted to Develop Spent Fuel Storage Technical Basis for the Waste Confidence Rule Making 1979/1980 OTHER SPENT FUEL STORAGE ACTIVITIES U.S. Delegate, IEA Spent Fuel Specialists meeting, 1977 Vienna U.S. Delegate, NEA Spent Fuel meetings, Madrid 1978/1982/1983 Lead consultant for IAEA/NEA World Survey of Spent 1979/1980 Fuel Storage Experience (Publication:
IAEA Special Technical Publication No.218,1982)
U.S.RepresentativetoIAEABEFAST(b) Coordinated 1980-1986 Research Program 1983 Attended meetings in Vienna 1986 Attended meetings in Leningrad U.S. coordinator, US/FRG Spent Fuel Storage Information Exchange Chairman, Third International Spent Fuel Storage Symposium / Workshop, Seattle, Washington April 8-10,1986 Author /co-author of about 40 spent fuel storage articles / reports International Fuel Cycle Evaluation.
(a) Ehavior of Fuel Assembliis in S_Torage.
(b)
o STATEMENT OF PROFESSIONAL QUALIFICATION OF GERALD R. KILP My name is Gerald R. Kilp.
My business address is Westinghouse Electric Corporation, P.O. 3912r Pittsburgh, Pennsylvania, 15230.
I am an Advisory Engineer for the Product Engineering Section of the Westinghouse Nuclear Fuel Division, Westinghouse Electric Corporation.
I have served in this function since November, 1983.
In this capacity, I am responsible for selected Materials Development programs and act as a general advisor on materials performance questions for the Westinghouse Nuclear Fuel Division.
I graduated from Missouri Valley College, Marshall, Missouri, in 1952 with a Bachelor of Science degree in l
Chemistry.
In 1957, I received a Doctorate of Physical Metallurgy from Iowa State College (since renamed to Iowa State University).
From 1952 to 1957, I was a Graduate Assistant at the Ames Laboratory for Atomic Research, an AEC supported laboratory at Iowa State College.
During this period, I worked on binary phase diagrams and evaluated methods for protection of uranium metal from water corrosion.
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From December, 1957 to May, 1962, I was a Senior Engineer and, later a Fellow Engineer, at the Westinghouse Atomic Power Department where I worked on thermoelectric and thermionic materials for application in nuclear reactors.
In May, 1962 and until September, 19_68, I acted as supervisor and later Manager of Fuel Evaluation on the NERVA Reactor Project at the Westinghouse Astronuclear Laboratory at Large, Pennsylvania.
In September, 1968 and until May, 1972, I served as the Engineering Manager of the Astronuclear Fuel Facility at Cheswick, Pennsylvania.
In this capacity, I was responsible for process development for fabrication of NERVA reactor fuel as well as reactor fuel performance evaluation.
In May, 1972, I transferred to the Westinghouse Nuclear Fuel Division of Westinghouse Nuclear Energy Systems, in Monroeville, Pennsylvania.
From then to May, 1980, I served as the Manager of Materials Design.
This group had the basic responsibility for materials R&D, and approval of materials for use in Westinghouse Pressurized Water reactors.
The duties further included determination of the necessary and sufficient requirements for reactor coolant and pool storage chemistries needed to assure satisfactory performance under all warranted conditions.
All reactor and out-reactor corrosion testing evaluations were done under the cognizance
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of this group.
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O From May, 1980, and until November, 1983, I worked at the Westinghouse Advanced Energy Systems Division where I served as the Manager of Materials Interactions until November of 1983.
These activities were primarily concerned with addressing materials selection and evaluation for application in long tera storage of light water reactor fuel in underground and above ground facilities.
Since 1979 I have also been a member of the American Society for Testing and Materials (ASTM) C26
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Committee on the Nuclear Fuel Cycle.
At the present time I
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as the Chairman of Sub-committee C26.02 (Fuel and Fertile Materials Specifications) and serve on C26.03 (Neutron Absorber Materials Specifications).
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O M W METW PAEL May 1986 I.
PERS M AL IEEEEATIM Date of Birth:
June 11, 1931 Bone Address:
204 Dodds Lane Princeton, NJ 08540 Nome Telephone:
(609) 921-7464 Business:
(21,5) 898-7191 II. NW Princeton University B.S.E., 1953 (Mechanical Engineering)
Stanford University, N.S., 1954 (Engineering Mechanics)
Polytechnic Institute, Brooklyn, Ph.D., 1958 (Applied Mechanics)
III. FWWESSIMAL ACTITITIES AEB SOCIETIES l
Associate Editor, Journal of Applied Mechanics (1971-1974)
Member of Editorial Board: Computer Methods in Appl. Mech &
Engrg. (1971-
)
Registered Engineer - Pennsylvania l
Neaber American Society Engineering Education Nember U.S. Council for Theory and Mechanisms Neaber Advisory Comalttee to National Science Foundation for Nechanical Sciences and Engineering Group (1979-1981)
Nember American Academy of Nechanics Member American Society of Safety Engineers Nember American Society of Mechanical Engineers (ASME)
Nember, Comalttee on Computers. Appl. Mech. Div., ASME (1970-1973)
Nember, Committee on Transportation. Appl. Mech. Div., ASME (1971-1974)
Chairman, Committee on Transportation. Appl. Nech. Div., ASME (1974-1980)
Applied Mechanics Newsletter Editor (1965-1971)
Sponsor for Plasticity and Failure (1964-1965)
Nember Design Automation Committee Design Engineering Div., ASME (1973-
)
AND Representative to Energy and Transportation Research Needs Committee, Policy Board Research, ASME (1974-
)
l Nember Select Panel on Research Goals in Mechanical Sciences for NSF P
IV.
m A W LISTIW S Fellow of American Society of Nechanical Engineers Phi Beta Kappa Tau Beta P1, Sigma X1, Sigma Gamma Tau Listed in:
k rican Men in Science: Who's Who in Engineerig: Interne-tions1 Who's Who in Emineering: Who's Who in Technology Today: Bio-graphical Directory of Computer Graphics: International Directory of Distignished Leadership.
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O V.
EIPERIENCE (also see separate listings on Acadealc and on Consulting Activi-ties) 1969-Present Asa Whitney Professor of Dynamical Engineering. University of Pennsylvania (1982-
)
Chairman, Dept. of Mechanical Engineering & Applied Mechanics (1973-1976)
Professor of Mechanical Engineering and Applied Mechanics (1969-
)
Professor of Computer and Information Science (1983-
)
Teaching: Theory of Nachines, Kinematics, Dynaales, stress and Strength Analysis, Robotics, Vibrations, Elasticity, Finite Element Methods.
Research: In above areas and in Cable Dynaales, Vehicle Mechanics, Contact Stresses, Brittle Fracture. Rail-Nheel Interaction, Ninematics and Dynaalce of Nachinery, Plasticity, Failure Criteria.
Consultant to Industrial and Legal Firms on Mechanics and Nachinery Problems 1963-1969:
Chief of Solid Mechanics Research. Ingersoll-Rand Research Center Research and ccasulting related to a wide variety of industrial aschinery, e.g.
compressors, pumps, gas engines, steam conde:isers, rock drills, etc. Analytic, experimental, and numerical methods of stress analysis, elasticity, plasticity, vibrations, wave propagation, brittle fracture, dynamics, kinematics.
Solid Mechanics Group produced over 60 formal company reports, 13 external publications, two patents, and numerous design and consulting notes.
1961-1963:
Supervisor of Engineering Nechanics Group, Bell Telephone Laboratories Concerned with dynaales, structural, thermal, and materials problems associated with satellite design.
1960-1961:
Director of Research and Analysis, Technic. Inc.
Consulting firm working in areas of gun design, pressure vessels, shell theory, stress
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and vibrations.
1958-1960:
Assistant Professor of Engineering. Brown University Taught Theory of Structures, Nachine Design. Strength of Materials Testing Laboratory. Dynamics, Statics.
Did theoretical and experi mental research in Plasticity. Elasticity, Brittle Fracture, Eeterogeneous Materials, Kinematics of Machines.
Invited lecturer (special series on Plasticity) at N.Y.U.,
Department of Mechanical Engineering.
Special lectures on plasticity of shells at U.S. Navy Bureau of Ships, and at David Taylor Model Basin.
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Consultant to Industry on Nachine Design, Stress Analysis, Dynamics.
1956-1958:
Graduate student and Research Associate. Polytechnic Institute of Brooklyn.
Lectured in Theory of Vibrations and Engineering Nechanics.
Research in static and dynaalc loading of elastic-plastic shells, rings and plates.
I 1954-1956:
Engineer at Bulova Research and Development Laboratories _, Woodside, New York.
Research in penetratior. of thin plates by high speed projectiles.
Analytical work in stress analysis, dynamics, vibrations.
Prior to 1954:
(Part time and suaner employment) l Nright Aeronautical Corp.:
Stress and Vibration Analysis on jet engines Power Generators, Ltd., Trenton, NJ:
Stress and Dynamic Analysis of Navy Catapults Gibbs and 5111. Inc., NY: Drafting i
Princeton University:
Design of laboratory apparatus for Fluid Mechanics Laboratory VI.
PATENTS l
1.
" Reinforcing Structure for Direct Flow Steam Dome for Condensors",
Patent No. 3,382,918, issue date:
May 14, 1968, with R.J. Stoker and A.I. Soler 2.
" Steam Done" Patent No. 3,454,086, issue date:
July 8, 1969, with R. J. Stoker VII. FWEICATIM A.
Book:
Eineastics and Dynanics of Planar Machinery, Prentice-Hall 1979.
8.
Books Edited:
Surveys of Research in Transportation Technology, AND-Vol. 5, ASNE, NY, 1973.
Nechanics of Transportation Suspension Systems, AMD-Vol'.15, ASNE, NY, 1975.
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3 1
o C.
Encyclopedia Articles:
"Shsft Balancing." in Encyclopedia of Science and Technology, 5th Ed., M,cGraw-Hill
" Macroscopic Criteria for Plastic Flow and Brittle Fracture," in Eracture, An Advanced Treatise, Vol. 2, nethematical Eundamentals, Ed. by H. Liebowitz, Academic Press, NY, 1968.
" Machine Systems " in nochanical Design and Systems Bandbook, 2nd Ed., McGraw-Hill (1985).
D.
Papers:
See separate listing.
B.
Unpublished Cocoany Reports:
See separate listing.
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I 1
PUBLISEED PAPERS OF B. PAUL 1.
"The Elimination of Impact Forces at Pivots " with M. Zald, Product Egineer-
- 14. March 1955 (205-207).
Also reprinted in Product Egineering Nandbook, 1956 (F40,F41).
2.
" Graphical Solutions for Two Failure Theories " Product Egineering, March 1956 (178-181).
3.
" Armor Penetration," with M. Zaid, ordnance, January 1957_(609-611).
4.
" Approximate Yield Conditions in Dynamic Plasticity," with P. G. Hodge, Jr.,
Proceedings of 3rd Midwest Conference on Applied Mechanics, Ann Arbor, MI, April 1957 (29-47).
5.
"Nechanics of Eigh Speed Projectile Perforation " with M.
Zald, Journal of Franklin Institute. Vol. 264 No. 2, 1957 (117-126).
6.
" Normal Perforation of a Thin Plate by Truncated Frojectiles," with M. Zaid.
JrArnal of Franklin Institute, Vol. 265. No. 4, 1958 (317-335).
7.
" Carrying Capacity of Elastic-Plastic Shells under Hydrostatic Pressure," with P. G.
Eodge, Jr., Proc. Third U. S. National Congress of Applied Mechanics,
(
1958 (631-645).
8.
" Collapse Loads of Rings and Flanges under Uniform Twisting Moment and Radial Force " Journal of Applied Mechanics, Vol. 26. No. 2, 1959 (265-270).
9.
" Carrying Capacity of Elastic-Plastic Shells with Various End Conditions, under Hydrostatic Compression " Journal of Applied Mechanics, Vol. 26, No. 4, 1959 (553-560).
10.
"A Unified Criterion for the Degree of Constraint of Plane Kinematic Chains,"
Journal of Applied Aschanics, Vol. 27. No. 1, 1960 (196-200).
11.
" Oblique Perforation of a Thin Plate by a Truncated Conical Projectile " with l
N. Zaid, Journal of Franklin Institute, Vol. 268. No. 1, 1959 (24-45).
l 12.
" Prediction of Elastic Constants of Multi-Phase Materials," 1"ransactions of the Natallargical Society of MNE, Vol. 218, February 1960 (36-41).
13.
"A Simplified Geometric Proof of the Reciprocal Stress Theores," Quarterly Applied AstA., Vol. 18. No. 4, 1961 (395-396).
14.
" Modification of the Coulomb-Nohr Theory of Fracture " Journal of Applied Nechanics, Vol. 28, 1969 (259-268).
15.
" Geometric Derivation of Compatibility Equation for Finite Deformation of Rotationally Symmetric Shells," Journal of the Aerospace Sciences, August 1961 (666-667).
5
^
o l
16.
" Plastic and Viscous Deformation of Redundant Structures -- Prototypes for a i
General Theory," Journal of tAs Franklin Institute, Vol. 273, No. 6. June 1962 (482-513).
17.
" Generalization of the Schmidt Graphical Method for Transient Heat Conduc-tion " ARS Journal, July 1962 (1098).
l 18.
" Compilation of Evaporation Coefficients," ARS Journal, September 1962 (1321-1328).
19.
" Shrink Fits of Moderately Long Bands on Thin-Nalled Cylinders," Journal of i
Engineering for Industry, frans. ASME, Vol. 84 Series 3.
August 1962 l
(338-342).
20.
"An Experimental Study of Plastic Flow under Stepwise Increments of Tension and Torsion," with W. C. Dhen and L. C. Lee, Proceedlags of the 4th Nat. Cong.
of Applied Aschmajes, 1962 (1031-1038).
21.
" Planar Librations of an Extensible Dumbbell Satellite," M AA Journal, Vol. 1, j
No. 2, 1963 (411-418).
~
i 22.
"Effect of Nodal Regression on Spin-Stabilized Communication Satellites," with E. Y. Yu, M AA Journal, Vol. 1. No. 10, October 1963 (2388-2389).
23.
"On the Composition of Finite Rotations," Amer. Nath. Monthly, Vol. 70 No. 8, 1963 (859-862(,
24.
"A Passive Gravitational Attitude Control System for Satellites," with J. W.
West and E.
Y.
Yu, TAs Es11 System fechnical Journal, Vol. XLII. No. 5 September 1963, (2195-2238).
24.
" Linear Bending Theory of Laminated Cylindrical Shells Under Axisymmetric Load," Journal of Applied Aschanics, Vol. 30, 1963 (98-102).
See Discussion in Vol. 31, 1964 (155-157).
26.
" Shadows Produced by Spin-Stabilized Communication Satellites," MAA Journal, Vol. 2, No. 5, 1964, (924-931).
27.
"Nazimization of Footage Drilled Before Drill Steels Fall in Fatigue," with C.
C. Fu.
Presented at 2nd Conference on Drilling and Rock Mechanics, Austin, Texas, Jan. 21, 1965.
Trans. Soc. N f n f ng Eglasers of MNE, Vol. 232, Dec.
1965 (301-307).
28.
" Evaporation Coefficients and Recoil Pressures," with L.
G.
Lyon, MAA Joarnal, Vol. 3. No. 6. June 1965 (1067-1071).
I 29.
"A Preliminary Theory for Wedge Penetration in Brittle Materials," with D. L.
Sikarskie; presented at 7th Symposium of Rock Mechanics, Penn. State Univ.,
June 14-16, 1965.
Trans. Soc. of Nialag Egineers of AINE, Vol. 232 Dec.
1965 (372-383).
6
,.c-
.,,,-.-,,_,.-,-,--,--------me,
,~...,m___---,__,7-
--.---m.,
1 o
30.
"A Nethod for Checking Force Calculations in Plane and Spatial Structures,"
Journal of Applied Nechanics, Vol. 32, 1965 (935-936).
31.
"Mohr's Circle as a Phasor Transformation." AIAA Journal, Vol. 4 No. 6. Dec.
1966 (2253).
32.
"The Semi-Infinite Beam with a Step Velocity Prescribed at the Tip," with C.
C. Fu, Journal of Applied Nechanics, Vol. 34. Trans. ASME, Vol. 89 Series E.
1967 (230-232).
Presented at 5th U.
S.
Nat. Congress Appl. Nech., Univ.
Minnesota, June 14-17, 1b66.
~
33.
" Initial and Subsequent Pgacture Curves for Blaxial Compression of Brittle Materials," with M. Gangal, in Nock Nechanics, Proc. Eighth Symposina on Nock Nechanics, Ed. by C. Fairhu
- t. A.I.M.E.,
Inc., NY, 1967 (113-141).
34.
" Generalized Pyramidal Fract e and Yield Criteria," International Journal of Solids and Structures, Vol.
1968 (175-196).
5 "MacroscopicCriteriaforPlask.icFlowandBrittleFracture,"inFracture,an 35.
l
.AdFanced Treatise, Tol.
2, Nethematical Fandamentals. Ed. by H.
Liebowitz, Academic Press, NY, 1968 (313-496).
~
" Explicit Solutions for Circular Plates with Discontinuous Axisymmetric Loads 36.
and Overhung Supports," with D. L. Sikarskie, Frans. ASNE, Tol. 90, Series 3, J. Espinserlag for Industry, 1968 (513-518).
37.
" Stability of Motion of Impact Tools," with C. C. Fu, Int. J. of Solids and Structures, Vol. 4, No. 9, 1968 (897-905).
38.
"A Three-Dimensional Stress Fracture Criterion Based on Microscopic Flaws."
Proc. Sixth Annual Meeting of Society of Engineering Science, Princeton University, Nov. 11-13, 1968.
Publ. In Recent Advances la KagineerJJg Scisace, Tol. 5 Ed. by A.
C.
Eringen, Gordon and Breach, London, 1970 (263-281).
l 39.
"Why Compressive Loads on Drill Bits Produce Tensile Splitting in Rock," with M. Gangal, Fourth Conference on Drilling and Rock Mechanics, Jan. 14-15, 1969, Univ. Texas. Soc. Petroleum Engineers.
Society of Petroleum Engineers of AINE, Dallas, Texas Paper No. SPE 2392.
40.
" Dynamic Stability of a Vibrating Hammer," with C. C. Fu, 2nd Annual Conf. on Vibrations. ASME, Phila., March 30-April 2, 1969 Trans. ASME, Tol. 923, J. of KJgineering for Industry, Nov. 1969 (1175-1179).
41.
" Periodic Notions of a Two-Body System Subjected to Repetitive Impact," with D. L. Sikarskie, 2nd Annual Conf. on Vibrations, frans. ASNE, Tol 913, J. of Esplacering for Industry, Nov. 1969 (931-938).
42.
" Energy Transfer Through Chains of Impacting Rods," with C. C.
Fu, Interna-tional Journal for Numerical Nethods in EJgineering, Vol. 2, 1970 (363-385).
7 y.,
O 43.
"3 tress Analysis of a Pressurized Bore in a Rectangular Block," with M.
D.
Gangal, ASME Paper 69-WA/PVP-3, Presented at Winter Annual Meeting, ASME, Los Angeles Nov. 1969.
44.
" Computer Analysis of Machines with Planar Motion, Part I - Kinematics," with D. Krajcinovic, Journal of Applied Mechanics, Trans. ASNE, Vol. 37 Series E, Sept. 1970 (697-702).
45.
" Computer Analysis of Nachines with Planar Motion, Part II - Dynaales,"
Jontaal of Applied Mechanics, Trans. ASNE, Vol. 37, Series E.
Sept. 1970 (703-712).
46.
" Analysis of Cable Dynaales and Optimus Towing Strategies for Tethered Submersibles," with A. I. Soler, J. of Marias Technology Society, Vol. 6, No.
- 2. March-April 1972 (34-42).
47.
"The Shifting Roles of computers. Experiments, and Analysis in Applied Mechanics," Esperimental Nechanics, Vol. 11. No. 9, 1971 (385-393).
l 48.
"Dynaalc Characteristics of a Vibrating Plate Compactor," with C.
C.
Fu, Frans. ASNE, Series B, J. of Englaseri g for Industry, May 1972 (629-636).
49.
"A Nethod for Solving Ill-Posed Integral Equation of the First Kind," with K.
P. Singh, Computer Nothods la Applied Nechanics and Englaserig, Vol. 2,1972 (339-348).
lt 50.
" Numerical Solution of Non-Hertzian Elastic Contact Problems," with K.
P.
Singh, Journal of Applied Mechanics, Vol. 41, frans. ASNE, Series E, Vol. 96, June 1974 (484-490).
51.
" Efficient Design of Axisymmetric Plates," with B. Singh, Journal of Englaser-1 4 for Industry, frans. ASNE, Vol. 96, Series B. No. 1. Feb. 1974 (210-=216).
52.
" Complex Numbers in Kinematics," Nechanical Englaserig News, Vol. 10 No. 3.
August 1973 (31-33), American Society for Engineering Education.
53.
" Dynamic Analysis of Planar Machines with Specified Force Inputs " Proc. Third Oklaboea State liniversity Applied Mechanics Conference, Stillwater OK, Nov.
1973 (14.1-14.7).
l 54.
" Stress Concentration in Crowned Rollers," with K.
P.
Singh, Joarnal of Engineering for Industry, Trans. ASNE, Series B.
Vol. 97, No.
3, 1975 (990-994).
55.
" Analytical Dynaales of Mechanisms - A Computer Oriented Overview," Nechanism l
and Nachlas Theory (Journal of Int. Federation for the Theory of Machines and Nechanisms), Vol. 10, 1975 (481-507).
The Case of Pitted 56.
" Contact Stresses for Multiply-Connected Regions Spheres " with K. P. Singh and W. S. Woodward. Proc. of the Symposina on the Mechanics of Deformable Bodies, Delft University Press, Netherlands, 1975 (264-281).
8 m
o 57.
"An Improved Fracture Criterion for 3-Dimensional Stress States," with L.
Nirandy, Journal of Engineerim Materials and Technology, Trans. ASNE, Vol.
98, Series H. 1976 (159-163).
58.
" Stresses at the Surface of a Flat Three-Dimensional Ellipsoidal Cavity," with L. Nirandy, Journal of Engineerim Materials and Technology, Trans. ASNE..Vol.
98, Series H. 1976 (164-172).
59.
" Dynamic Analysis of Nachinery Via Program DYNAC," Society of Automotive Engineers Warrendale PA, Paper No: 770049 (1-11), 1977 F -
60.
"A Review of Rail-Wheel Contact Stress Problems," Proc. of Symposium on Nailroad Track Nechanics, Pergamon Press, Oxford, 1978 (323-351).
61.
"DYNAC:
A Computer Program to Slaulate Nachinery Dynamics," 4ricultural Emineerig. Vol. 59 (Part I in No. 8, pp.15-16; Part II in No. 7, pp. 47-48),
1978.
62.
"A Reassessment of Grashof's Criterion " Journal of Aschanical Design, Trans.
~
ASNE, Vol. 101, 1979 (515-518).
63.
"An Improved Numerical Nethod and Computer Program for Counterformal Contact Stress Problems," with J. Hashemi, in Computational Technignes for Interface Problass, AND-Vol. 30. Ed. by K. C. Park et al. American Society of Mechanical Engineers, 1978 (165-180).
64.
" Contact Geometry Associated with Arbitrary Rail and Wheel Profiles." with J.
Hashemi, in TAs General Problem of Nollfag Contact, AND-Vol. 40 Ed. by A. L.
Browne and N.
T.
Tsai, American Society of Mechanical Engineers, 1980 (93-105).
t l
65.
" Contact Pressures on Closely Conforming Elastic Bodies " with J. Hasheni.
Trans. ASNE, Journal Applied Nechanics, Vol. 48, 1981, pp. 543-548.
Also'see pp. 67-78 la Solid Contact and Labrication. AND-Vol. 39 Ed. by H. S. Cheng and L. N. Keer, ASME, NY (1980).
66.
" Surface and Subsurface Stresses Associated a '.th NonHertzian Wheel-Rail Contact," in Contact Nechanics and Wear of Rail N Asel Systems. (Proceedings of the International Symposium held at the University of British Columbia, Vancouver) Edited by J.
Kalousek, et al.
University of Waterloo Press, l
Waterloo, 0.1tario, Canada, 1984, 1
67.
" Pennsylvania Articulated Mechanical Hand," (with J. D. Abramowitz and J.
W.
Goodnow, Presented at Int. Conf. on Computers in Engineering ASME, Chicago, IL, August 1983.
68.
" Elastic Deformation of End Supported Pressure Rollers," (with B.
Singh).
Trans. ASNE, J. of Vibrations, Acoustics, Stress and Reliability in Design, Vol. 106, 1984 (517-522).
9 u
o 69.
"A Cylindrical Roller Indenting an Elastic Layer," (with B.
Singh). Paper 83-WA/DE-8. ASME, 345 E. 47th St., NY 10017, 1983.
70.
" Computer Oriented Analytical Dynamics of Machinery " Proceedigs of NATO Advanced Study Institute on Computer-Aided Analysis and Optialzation of Nechanical Systems Dynamics.
Ed. by E. Haug, Springer Verlag, 1984.
71.
" Machine Systems," Chapter 12 in Mechanical Design and Systems Bandbook, 2nd Ed., Ed. by H. Rothbart, McGraw-Hill, New York 1985 (31 pages).
72.
" Kinematics Simulation of Serial Manipulators " (with J. Rosa), International Journal of Robotics Assearch, Vol. 5. No. 2, 1986 (14-31).
l e
i l
10
,,--n.--
I O
UNPUBLISEED CEEFANY REPORTS BY B. PAUL A.
At Intersoll-Rand Research Center 1.
" Load Deflection Curves for Circular Arc Channel-Valve Spring," with C. C. Fu, TN 155 (1963) l 2.
" Surge Waves in a Paving Breaker's Return Spring," with C. C. Fu, TN 156 (1963) 3.
"On the Desirability of a Variable Frequency-Paving Breaker," with l
C. C. Fu, TN 159 (1963) 4.
" Maximization of Footage Drilled before Fatigue Failure of Drill Steels " with C. C. Fu, TN 166 (1963) 5.
" Preliminary Report on Dynamics of Reciprocating Hammer Impact Tools." with D. Sikarskie and M. Miller, TN 173 (1964) 6.
"A Preliminary Model for Wedge Penetration in Brittle Materials,"
with D. Sikarskie, TN 163 (1964) 7.
"On the Feasibility of a Two-Material Piston-Baamer for Rock Drills " TN 190 (1964) 8.
" Stress Analysis of Condenser Steam Dome and Correlation with Field Tests," with A. Soler, TN 207 (1965) 9.
"The Strength and Slip Resistance of Rings on Impacted Tapered Shafts," with C. C. Fu, TN 208 (1965) 10.
" Buckling Analysis of Condenser for AEP cardinal Plant," TN 226 (1965) 11.
"The Feasibility of Drilling and Fragmenting Rocks by Neans of Frictional Forces," TN 233 (1965) 12.
" Steady-State Response of a Vibratory Drilling System Exhibiting Intermittent Bit-Rock Contact and Rock Hysteresis," with C.
C.
Fu, TN 241 (1965) 13.
" Stress Analysis of a Piston Ring Under Impact Conditions," with C.
C. Fu, TN 240 (1965) 14.
" Elastic Design for Steam Condenser Expansion Joints," with C.
C.
Fu, TN 244 (1965) 15.
" Elastic Design for Steam Condenser Expansion Joints," with C.
C.
Fu, TN 244 (1965) 16.
" Response Curves for Non-linear Steady-State Vibratory Rock Drill-l ing," with C. C. Fu, TN 252 (1966) l 11
o 17.
"A Note on the Reduction of Hold-down Forces by Reduction of i
Rock-Bit Impact Duration," with C. C. Fu, TN 257 (1966) i 18.
" Design Approach for Unbraced Steam Domes," with A.
Soler TN 255 (1966) l 19.
" Initial and Subsequent Fracture Curves for Rocks under Blaxial Compression," with M. Gangal, TN 274 (1966) 20.
" Stress Analysis of the Cross-Bore Lip Region -ef a-6-3/4-5000 Psi Compressor Cylinder Block " with M. Gangal. TN 268 (1966) 21.
" Influence of Reinforcing Ring on Stresses in Pendelton's DynaRing Sockets," TN 284 (1966) g 22.
" Stresses in a Hollow Cylindrical Conductor due to the Passage of Electric Current," with M. Gangal, TM 6701 (1967) 23.
" Computer Solutions for Stress, Rebound Velocity, and Impact Effic-1ency of Rock Drills," with C. C. Fu, TN 305 (1967) 24.
"A Design Method for Pressurized Intersecting Bores," with M.
Gangal. TN 326 (1968)
B.
At Bell Telephone Laboratories:
1.
" Bending Stresses in Statically Determinate Circular Plates Under l
Axisymmetric Loading," MM 61-2812-8, (1961) 2.
" Planar Librations of an Extensible Dumbell Satellite,"*
1986 1 -
2812-9, (1961) 3.
"A Generalization of the Schmidt Graphical Method for Transient Heat Conduction,"* MM62-2812-1, (1962) 4.
" Compilation of Evaporation Coefficients,"* MM 62-2812-2, (1962) 5.
" Description of a Gravitationally Oriented Satellite Attitude Control System," MM 62-2812-10 (1962) 6.
"On the Composition of Finite Rotations,"* MM62-2812-8, (1962) 7.
" Scope of Analysis and Design Work for Gravity Gradient Attitude Control System," (1962) 8.
" Observations on Telemetry Requirements for Attitude Sensing," with J. H. Unger and W. J. Maybach, (1962) 9.
"Large Deflections of Cantilever Beams, Approximate Treatment of
(
Impact Problems," MM 62-2812-25, (1962) l 12
-~
--.-e-
+--__-r.,
,_y
o 10.
"Some Effects of Orbital Precession and Spin-Axis Drif t on Spin-Stabilized Satellites,"* with E. Y. Yu, MM 62-2812-28, (1962) 11.
" Structural Vibrations of some Gravitationally-Oriented Satellite Configurations," with L. S. Goldman, NM 62-2812-29 (1962) 12.
"A Passive Gravitational Attitude Control System,"* with J. W. West and E. Y. Yu, (1963) 13.
" Shadows Produced by Spin Stabilized Consunicat!'ons Satellites,"* MM 63-2812-5, (1963) 14.
" Dynamic Structural Analysis of Extension Phase for Gravitational Attitude Control Systes," with J. G. Enstros and J. W. Stafford, MM 63-2812-4, (1963) 15.
" Investigation of Effect of Torsional Stiffness of Mast of Gravita-tional Attitude Control System During Erection Phase," with J.
W.
Stafford and J. G. Engstros, NM 63-2812-6, (1963) l l
- Later published externally l
l 13 I
l
James D. Shiffer VICE PRESIDENT, NUCLEAR POWER GENERATION Education a.
B.S. Chemical Engineering, Stanford University,1960.
b.
M.S. Nuclear Engineering, Stanford University, 1961.
c.
Registered Professional Engineer, Mechanical and Nuclear, California.
Employment History - Joined PGandE in September 1961 a.
Summer 1959 and Summer 1960 - Employed by PGandE in summer engineer program. Assigned to Vallecitos Boiling Water' Reactor and Central Chemical Laboratory.
l b.
September 1961 to April 1962 - Engaged in Humboldt Bay Unit No. 3 startup preparation, c.
April 1962 to July 1969 - Various assignments in power plant nuclear engineering, chemical engineering, and other technical operations at Humboldt Bay, d.
July 1969 to July 1970 - Engaged at Humboldt Bay and at Company's General Office in Diablo Canyon startup preparation.
Includt; a seven-month assignment in Rochester, New York, during startup and initial testing of R. E. Ginna PHR Plant.
I e.
July 1970 to August 1971 - Engaged in Diablo Canyon startup preparation on Diablo Canyon Task Force.
f.
August 1971 to October 1978 - Assigned to Diablo Canyon as Power Plant Engineer.
g.
November 1978 - Assigned to Diablo Canyon as Technical Assistant to the Plant Superintendent.
h.
February 1980 - Assigned to General Office as Manager of Nuclear Plant Operations.
1.
October 1984 - Assigned as Vice President of PGandE's Nuclear Power i
Generation Department.
Nuclear Experience a.
Education - Masters degree thesis research involving operation of the Stanford Swimming Pool Reactor, irradiation of foils to determine reactor parameters, flux wire counting, and radiochemical work.
i e
-,,--,,,--,-----,,e-
-,,,,,-_,.,,,,.,,,n
,n,__ - -,_,,
n-,, -.
.-__n.-
g,,-.-._,
--,-n,.,_
o b.
Vallecitos - Assigned to Vallecitos for two summers. Participated in the startup of the AVBHR plant.
c.
Humboldt Bay - Participated in prestartup activities including preparation of training material, initial loading, and low-level testing procedures and power testing procedures. Trained operating personnel for AEC license examinations. Received an AEC Senior Operator's License.
Participated in preoperational testing of equipment and systems.
Directed initial loading and testing programs as shift nuclear engineer.
Directed the preparation of all reactor refueling procedures subsequent to initial fueling and directed the performance of this work on shift.
Responsible for the theoretical analyses of reactor core nuclear and thermal-hydraulic performance, plus evaluation of the performance of plant safeguard and other auxiliary equipment.
Provided technical advice and guidance for the chemical and radiation protection engineers and
' participated in the establishment and implementation of the chemical, radiochemical, and radiation protection programs at the plant.
d.
R. E. Ginna - Assigned to Ginna for seven months from July 1, 1969, to February 1970. Conducted training program for operators taking the AEC Operator's License examination. Participated in the preparation and review of procedures and programs for initial loading, low-level physics testing, power operation testing, and radiochemical control.
Participated in initial loading, low-level physics testing, and power operation testing programs.
e.
Diablo Canyon - Participated in the preparation and review of licensing material for Units 1 and 2, including the PSAR, FSAR, and Technical Specifications.
Supervised staff of engineers (including persons experienced in nuclear engineering, instrumentation, radiation protection, and chemical engineering) engaged in the preparation of equipment operating and testing procedures, emergency plans, administrative procedures, and equipment specifications and related material required prior to the startup of the plant.
Formal Training Courses a.
Stanford University Nuclear Engineering Curriculum as required by AEC Scholarship Program.
b.
Digital Computer Applications for Nuclear Reactor Calculations, UCLA Extension; Spring 1963.
c.
Diablo Canyon Design Lecture Series - Series of lectures given by designers of Diablo Canyon systems and equipment, Westinghouse APD; Hinter 1971.
d.
In-Place Filter Testing Workshop, Harvard School of Public Health;
(
Fall 1971.
1 l
I i m.
o e.
Refresher Training in Radiological Engineering, General Electric Vallecitos Nuclear Center; Sumer 1972.
f.
Short Course in Reactor Noise Analysis, University of Tennessee; Fall 1976.
g.
Simulator Training - Westinghouse Nuclear Training Center, Zion, Illinois. Option III (three-week course, 1974) and Option II (one week course, 1978).
h.
Metallurgy for Non-Metallurgists, cne week course given by~ Center for Professional Advancement, August 1980.
t l
l. _ - _
o NRISHNA P. SINCH Address:
416 Catewood Road, Cherry Hill, N3 08003 Telephone:
(609) 428-8408 Personal Data:
Date of Birth May 1, 1947 Marital Status Married, one daughter, one son Height and Weight 5'9" ; 155 lbs.
Health Excellent Nationality U.S.A.
Education:
Craduate School of Arts and Sciences, University of 1968 to 1972 Pennsylvania, Philadelphia, Pennsylvania Ph.D. in Mechanical Engineering and Mechanics, (1972).
l _
M.S. in Engineering Mechanics (1969).
Ph.D. Thesis " Contact Stresses in Elastic Bodies with Arbitrary Profiles".
Scholastic Average of Craduate Studies: Straight A (4.00 out of 4.00).
Support: Fellowship of University of Pennsylvania.
l l
1963 to 1967 - B.I.T. Sindri; University of Ranchi, India B.S. in Mechanical Engineering Scholastic average of undergraduate studies: First Class with Distinction t
(equivalent to straight A), ranked second in the Institute.
1961 to 1963 - St. Xavier's College, Ranchi, India.
B. Sc. I. in Science Grade average: First Class with honors.
(Ranked second in the university among nearly 4,000 students).
Work Experience:
1967 - 1968:
Lecturer in the Applied Mechanics Department, Engineering College, Allahabad.
Cave courses in " Strength of Materials" and " Theory of Machines".
t 1969 (Summer)
I Engineer at Westinghouse Electric Corporation, Lester, Pennsylvania.
Responsibility:
Investigation of the effect of stator leakage in gas l
turbines.
l l
1
__c...,..-n..-
o,
Nay 1971 - November 1974:
Principal Engineer: Joseph Oat Corporation, Camden, New 3ersey.
Responsibility: Stress analysis of pressure vessels, columns and heat exchangers.
Authored several technical reports for static and dynamic stress analysis of process equipment used in nuclear power plants.
November 1974 to 1979:
Chief Engineer:
3oseph Oat Corporation.
Supervision of design, research and development in the area of pressure vessels, heat exchangers and structures.
The group produces nearly 50 custom designs and specialized analyses per year.
November 1979 to Present:
Vice President of Engineering: Joseph Oat Corporation.
Responsible for all project engineering, and applied research and development activities of the company.
1 -
Scholastic and Extracurriculars:
Award for "Overall Best Scholarship:
at St. Xavier's College, Ranchi (1963)
Certificate of Herit from Bihar Secondary School Examination Board for finishing second in nearly 100,000 students (1961).
Elected Chairman, Debating Society, 8.I.T. Sindri (1966-67)
Ranked seventh in India in the Indian Engineering Services competitive examination taken by several thousand engineers (1967)
Funded Research:
Four contracts (totalling over $800,000) from Electric Power Research Institute, (EPRI), Palo Alto, California to conduct research in various problems in power plant operation and maintenance.
Work performed on these contracts has not been published for contractual reasons.
Continuing Education Courses Givent o
Five day course given at I. I.T., Bombay, India on " Heat Exchanger Nechanical Design". (1979) o Three courses in " Heat Exchanger Technology" given at Duke Power Company. (1982-83)
Three day course given at National Italian Reactor Authority, Genoa, o
Italy on " Nuclear Plant Equipment Design". (1984) l
o Professional Activities, Associations, etc.
Registered Professional Engineer, Pennsylvania (1974) a.
b.
Member, A.S.M.E. (1973)
Member, Pressure Vessel and Piping Subcommittee of A.S.M.E. Nuclear c.
Engineering Division (1976) d.
Member, TEMA Technical committee (1976-)
Reviewer, A.S.M.E. transaction Journals e.
f.
Member, Technical Committee on Nuclear Heat Exchangers of Heat Exchange Institute (1977-)
g.
Member, American Nuclear Society (1979-)
h.
Listed in: "Who's Who in Technology" (1979-)
1.
Member, American Association for Advancement of Science (1980-)
Patents, etc.
" Heat Exchanger for Withstanding Cyclic Changes in Temperature" (with a.
M. Holtz and A. Soler), Patent No. 4,207,944 (1980) b.
" Radioactive Fuel Cell Storage Rack" (with M. Holtz), U.S. Patent No.
4,382,060 (May, 1983)
Books (authored or edited)
Mechanical Design of Heat Exchangers and Pressure Vessel Components, a.
with A.I. Soler, Arcturus Publishers, Cherry Hill, NJ, 1100 pages, hardbound (1984).
b.
"Feedwater Heater Workshop Proceedings", with Thos,as Libs EPRI 78-123 (1979)
"Feedwater Heater Procurement Guidelines", EPRI-CS-4155 (1985).
c.-
Publications l
1.
"A Method for Solving Ill-Posed Integral Equations of the First Kind",
(with B. Paul), Computer Methods in Applied Mechanics and Engineering 2 (1973) 339-348.
2.
Numerical Solutions of Non-Hertzian Elastic Contact Problems, (with B. Paul), Journal of Applied Mechanics, Vol. 41, No. 2, 484-490, June, l
1974.
3.
"On the Inadequacy of Hertzian Solution of Two Dimensional Line Contact Problems", Journal of the Franklin Institute, Vol. 298, No. 2, 139-141 (1974).
4.
"How to Locate Impingment Plates in Tubular Heat Exchangers",
Hydrocarbon Processing, Vol. 10, 147-149 (1974).
5.
" Stress Concentration in Crowned Rollers", (with B. Paul), 3ournal of Engineering for Industry, Trans. ASE, Vol. 97, Series 8, No.
3, 990-994 (1975).
~. -. _ - - - -. -
-~
C 6.
" Application of Spiral Wound Caskets for Leak Tight Joints", 3ournal of Pressure Vessel Technology, Trans. ASE, Vol. 97, Series 3, No.1, 91-83, (1975).
7.
" Contact Stresses for Multiply-Connected Regions - The Case of Pitted Spheres", with B. Paul and W.S. Woodward, Proceedings of the IUTAM Symposium on Contact Stresses, August 1974, Holland, Delft University Press, 264-281, (1976).
i 8.
" Design of Skirt-Mounted Supports", Hydrocarbon Processing, Vol. 4, 199-203, April 1976.
9.
" Predicting Flow Induced Vibration in U-Bend Regions of Heat An Engineering Solution", 3ournal of the Franklin Exchangers Institute, Vol. 302, No. 2, 195-205, Aug. 1976.
1 10.
"A Method to Design Shell-side Pressure Drop Constrained Tubular Heat Exchangers", with H. Holtz, 3ournal of Engineering for Power, Trans.
of the ASE, Vol. 99, No. 3 July 1977, pp 441-448.
11.
"An Efficient Design Method for Obround Pressure Vessels and Their End Closures", International Journal of Pressure Vessel and Piping, Vol.
5, 1977, pp 309-320.
- 12. " Analysis of Vertically Mounted Through-Tube Heat Exchangers", 3ournal of Engineering for Power, Trans. ASE, Vol.100 No. 2, April 1978, pp 380-390.
13.
" Study of Bolted 3oint Integrity and Inter-Tube-Pass Leakage in U-tube i
Heat Exchar,gers: Part I - Analysis", Journal of Engineering for Power, Trans. ASE, Vol.101, No.1, pp 9-15 (1979) 14.
" Study of Bolted 3oint Integrity and Inter-Tube-Pass Leakage in U-Tube Heat Exchangers, Part II - Applications", Journal of Engineering for Power, Trans. ASE, Vol.101,1, pp 16-22 (1979).
- 15. "On Thermal Expansion Induced Stresses in U-Bends of Shell-and-Tube Heat Exchangers",
(with Maurice Holtz); Trans. ASE, Journal of Engineering for Power, Vol. 101, No. 4, October, 1979, pp. 634, 639.
- 16. " Heat Transfer Characteristics of a Generalized Divided Flow Heat Exchange:",
Proceedings of the Conference on Industrial Energy Conservation Technology, Houston, Texas, pp 88-97 (1979) 17.
"An Approximate Analysis of Foundation Stresses in Horizontal Pressure Vessels", (with Vincent Luk), Paper No. 79-NE-1, Trans. ASE, 3ournal of Engineering for Power, Vol. No. 2, No. 3, pp555-557, July,1980.
18.
" Generalization of the Split Flow Heat Exchanger Geometry for Enhanced Heat Transfer", (with Michael Holtz), AIChE. Symposium series 189, Vol. 75, pp 219-226 (1979)
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y_,,--.
_m.
o 19. " Analysis of Temperature Induced Stresses in the Body Bolts of Single Pass Heat Exchangers",
(with Maurice Holtz), ASE Winter Annual Meeting, Paper No. 79 WA/E-7.
j 20.
" Optimization of Two-Stage Evaporators for Minimizing Rad-Waste Entrainment",
(with Maurice Holtz) Journal of Mechanical Design, Trans. of the ASE, Vol.102, No. 4, pp 804-806 (1980)
"A Comparison of Thermal Performance of Two and Four Tube j' ass Designs 21.
for Split Flow Shells", (with M.3. Holtz), 3ournal of Heat Transfer, Trans. of the ASE, Vol.103, No.1, pp 169-172, February, 1981 22.
"A Method for Maximizing Support Leg Stress in a Pressure Vessel Mounted on Four Legs Subject to Moment and Lateral Loadings",
International 3ournal of Pressure Vessels and Piping, Vol. 9, No. 1, pp 11-25 (1981)
- 23. " Design, Stress Analysis and Operating Experience in Feedwater Heaters", (with Tom Libs), Proceedings of the Conference on Industrial Energy Conservation Technology, Houston, pp 113-118 (1980) 24.
"On the Necessary Criteria for Stream Symmetric Tubular Heat Exchanger Ceometries", Heat Transfer Engineering, Vol. 3, No.1 (1981) i
- 25. "Some Fundamental Relationships for Tubular Heat Exchanger Thermal Performance", Trans. ASE, Journal of Heat Transfer, Vol. 103, pp l
573-578 (1981) i 26.
" Transient Swelling of Liquid Level During Pool Boiling in an Emergency Condenser", with 3.P.
Cupta, Letters in Heat and Mass Transfer, Vol. 8, No. 1, pp 25-33, Jan/Feb., 1981.
i 27.
"An Approximate Method for Evaluating the Temperature Field in j
Tubesheet Ligaments Under Steady State Conditions", with H. Holtz, l
3ournal of Engineering for Power, Trans. ASE, Vol.104, pp 895-900 (1982).
28.
" Feasibility Study of a Multi-Purpose Computer Program to Optimize Power Cycles for Operative Plants", with Y. Menuchin and N. Hirota, Proceedings of the Conference on Industrial Energy Conservation Tecnnology, Houston, (1961).
29.
" Design Parameters Affecting Bolt Load in Ring Type Casketed 3oints",
with A.I. Soler, Trans. ASE, Journal of Pressure Vessel Technology, i
Vol. 105, pp 11-13 (1983).
30.
"A Design Concept for Minimizing Tubesheet Stress and Tubejoint Load in Fixed Tubesheet Heat Exchangers", with A.I. Soler, Trans. ASE (c.
1982).
O.
31.
" Dynamic Coupling in a Closely Spaced Two-Body System Vibrating in Liquid Medium:
The Case of Fuel Racks", with A.I. Soler, Proceedings of the Third International Conference on " Vibration in Nuclear Plant",
Keswick, England, May, 1982, pp. 815-834.
32.
"Effect of Nonuniform Inlet Air Flow on Air Cooled Heat Exchanger Performance", with A.I. Soler and Lee Ng, Proceedings of the 30 int ASE-3SE Heat Transfer Conference,1983, pp. 537-542_
33.
" Seismic Response of Free Standing Fuel Rack Cons.tructions to 3-D Motions", with A.I. Soler, Nuclear Engineering and Design Vol. 80 (1984), pp. 315-329.
34.
"A Method for Computing Maximum Water Temperature in a Fuel Pool Containing Spent Nuclear Fuel", Nuclear Technology, American Nuclear Society (c. 1984).
35.
"On Minimization of Radwaste Carry-Over in an N-stage Evaporator",
with Maurice Holtz and Vincent Luk, Heat Transfer Engineering, pp.
68-73, Vnl. 5, No.1-1 (1984).
Some New Performance
- 36. Feedwater Heater Procurement Guidelines Criteria, Symposium on state-of-the-art Feedwater Heater Technology, EPRI (c. 1984).
37.
" Method for Quantifying Heat Duty Derating due to Inter-Pass Leakage in Bolted Flat Cover Heat Exchangers", Heat Transfer Engineering, (pp. 19-23, Vol. 4, No. 3-4 (1983).
38.
"On Some Performance Parameters for Closed Feedwater Heaters, Proc. of PvP Conference, ASE (c.1985).
39.
"A Design Procedure for Evaluating the Tube Axial Load due to Thermal Effects in Multi-Pass Fixed Tubesheet Heat Exchangers", (with A.I.
Soler), 30urnal of Pressure Vessel Technology, Trans. ASE (c.1986).
40.
"An Elastic-Plastic Analysis of the Integral Tubesheet in U-tube Heat Exchangers - Towards an ASE Code Oriented Approach", Proc. of PVP Conference, ASE (c.1985).
41.
invited paper, Proc. of the Joint NSF-ASI Conference, Poona, India (c. 1986).
42.
" Surface Condensers",
invited paper, Proc. of the Joint NSF-ASI Conference, Poona, India (c. 1986).
43.
" Flow Induced Vibration", invited paper, Proc. of the Joint HSF-ASI Conference, Poona, India (c. 1986).
44.
" Mechanical Design of Heat Exchangers", invited paper, Proc. of the l
Joint HSF-ASI Conference, Poona, India (c. 1986).
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I 1
STATEMENT OF PROFESSIONAL QUALIFICATIONS OF DR. STANLEY E. TURNER Education:
University of South Carolina, B.S. Chemistry, 1945 University of Texas, Ph.D., Nuclear Chemistry, 1951 Professional Experience:
Southern Science Office of Black & Veatch, Engineers-Architects Proiect Manaaer/ Consultant fl977-Present)
Dr. Turner is responsible for a wide range of
~
scientific projects, including radiological monitoring systems, assessment of alternate nuclear fuel cycles, combustible gas generation and control, reactor physics analyses, and safety evaluations.
Over the past few years, Dr. Turnet has been involved in the design, evaluatior, and licensing of high density spent fuel storage racks, including l
both criticality analyses and assessment of radiological consequences.
Additionally, he has evaluated the core physics performance and isotope
' production rates of research, test, training, production, and power reactors.
As Project Manager for several U.S. Arms Control and Disarmament Agency programs, Dr. Turner has investigated possible modifications to reactors for improved fuel utilization and has evaluated advanced PWR reactor concepts, involving extended fuel burnup, increased core regionalization and alternate methods of reactivity control.
NUS Corporation - Senior Consultant (1973-19771 Dr. Turner was Project Manager on numerous assignments.
Among them were the assessment of post-LOCA hydrogen generation, and methods of control and development of specialized radiological monitoring systems; a survey of European nuclear fuel cycle plans and capabilities; generic review of public issues in the nation's nuclear power program; investigation of Halon-1301 for fire control and inhibition of hydrogen burning; a study of radiolytic decomposition of Halon; and a survey of U.S. nuclear plant practice for foreign clients.
His other work dealt with such activities as
l i
analytical physics support, evaluation of catalyst performance, and fission gas release and inventory calculations.
Southern Nuclear Encineerina. Inc. - Vice President, Physics (1964-731 During his association with this company, Dr. Turner managed and participated in a number of projects which involved assessing trYti~um production and control methods; performing calculations of heavy isotope production; reviewing licensing documents; preparing operating procedures; performing safety assessment of large, special purpose reactors; evaluating consequences of industrial sabotage in nuclear power plants; assessing reactors for maritime application; and evaluating fuel cycle economics.
General Nuclear Enaineerina - Senior Reactor Physicist (1957-1964)
Dr. Turner performed or directed most of the fuel cycle cost evaluations, heavy isotope analysis, and fuel management work performed by this company. He planned and coordinated various experiments and testing programs, and managed research and development activities related to advanced nuclear fuel elements.
In addition, he participated in plant licensing actions and safety reviews, and served as a member of the Safety Committee for an operating nuclear power plant.
Socony-Mobil Research Laboratory - Physicist (1952-1957) i Dr. Turner performed research in radiological methods for oil exploration, including radiation measurements and field tests.
U.S. Navy Radioloaical Defense Laboratory Physicist (1951-1952)
Dr. Turner performed research in the consequences l
and methods of defending against nuclear bomb detonations, including field tests and radiological measurements.
Honorary Societies:
Sigma Pi Sigma, Phi Lambda Epsilon, Blue Key, Sigma Xi l
Professional l
Affiliations:
Dr. Turner is a member of the ANS Standards Committee 8.17 on Nuclear Criticality Safety, and l
Chairman of ANS 5.3 and 5.4 Working Groups on I
o Fission Product Release.
He was formerly a member of the ANS 5 Committee on Decay Heat and contributed to the formulation of the standard on fission product decay heat.
Registered Professional Nuclear Engineer:
Florida, No. 22862.
A r
O y-
Y O
PROFESSIONAL QUALIFICATIONS OF WILLIAM H. WHITE My name is Hilliam H. White.
IwasanAssikantProject Engineer in the Diablo Canyon integrated organizatio'n consisting of Pacific Gas and Electric Company and Bechtel Power Corporation employees. My responsibilities included supervision and direction of seismic-related engineering analyses for the Diablo Canyon Unit 1 Project Engineering Organization. Currently I am the Chief Civil / Structural engineer for the San Francisco office of Bechtel Nestern Power Corporation.
I am a Registered Professional Civil Engineer in Oregon and member of the American Society of Civil Engineers.
My educational background includes: BS, Civil Engineering, University of Idaho; MS, Civil Engineering, University of Colorado; PhD, Civil Engineering, University of Colorado.
l Prior to my involvement in Diablo Canyon, I was an l
l engineering specialist with Bechtel's San Francisco Power Division working with the Chief Civil Engineer's staff in the area of seismic analysis for several Bechtel projects.
Earlier, I was a Structural Engineer with the Tennessee Valley Authority, where I was responsible for seismic analysis of l
i
- _ ~ - _ _.,
all Category I structures for a twin-unit nuclear power plant, including seismic input for the design of the nuclear steam supply system.
I was an Assistant Professor at Oregon Stati University, where I taught undergraduate and graduate courses in structural mechanics and analysis and computer applications.
I performed a special study for Bechtel on soil-structure interaction for the proposed Mendocino nuclear power plant while teaching at Oregon State University.
While employed at the Bettis Atomic Power Laboratory, I was a Senior Engineer working on shock analysis of nuclear reactors aboard submarines and was involved in programs to assess the shock resistance of reactor internals subjected to long-term irradiation damage.
l i
e ATTACHMENT 2 e
I f
I 1775M/2
4 i
o ATTACHMENT 2 List of Exhibits 1.
Pacific Gas and Electric Company, Reracking of Spent Fuel Pools, j
Diablo Canyon Units 1 and 2, Letter No. DCL-85-306, September 19, 1985 2.
Pacific Gas and Electric Company, License AmendmenLRequest 85-13, Roracking of Spent Fuel Pools, Letter No. DCL-85-333, October 30, 1985 3.
Pacific Gas and Electric Company, Spent Fuel Pool Reracking -
Additional Information, Letter No. DCL-86-019, January 28, 1986 4.
Pacific Gas and Electric Company, Response to Questions on Spent Fuel Racks, Letter No. DCL-86-067, March 11,1986 i
5.
Pacific Gas and Electric Company, Supplemental Information on Spent j
Fuel Racks, Letter No. DCL-86-126, May 9, 1986 6.
Pacific Gas and Electric Company, Spent Fuel Pool Reracking -
Additional Information, Letter No. DCL-86-149, May 28,1986 Pacific Gas and Electric Company reserves the right to mark as an 7.
Exhibit any and all documents set forth in the attached " List of Documents to be Relled Upon."
8.
Pacific Gas and Electric Company reserves the right to mark as an Exhibit any and all documents listed as " Exhibits" or " Documents j
Relied Upon" by any other party.
l; i
f.
O ATTACHMENT 3 1775H/3
O ATTACHMENT 3 List of Documents to be Relied Uoon 1.
United States Nuclear Regulatory Commission, Environmental Assessment and Finding of No Significant Impact - Spent Fuel Pool Expansion, Diab',o Canyon Nuclear Power Plant, Units 1 and 2 May 21, 1986
~
2.
UnitedStatesNuclearRegulatoryCommissionSafetyEva1iationof Reracking of Spent Fuel Pools as Diablo Canyon Units 1, and 2, May 30, 1986 3.
Nuclear Regulatory Commission Staff Response to Request for a Stay by Sierra Club and Mothers for Peace, June 25, 1986 4.
United States Nuclear Regulatory Commission Memorandum and Order (CLI-86-12), July 22, 1986 S.
Seismic Analysis of Hiah Density Fuel Racks, by A. I. Soler, Oat Report No. TM-779, Rev. 3, 1986 6.
Dynamic Coupling in a Closely Spaced Two-Body System Vibrating in Liquid Medium: The Case of Fuel Racks, K. P. Singh, and A. T. Soler, Proceedinas of the Third International Conference on Vihratjon in Nuclear Plants, Keswick. Enaland. May 1982, pp. 815-834 7.
Seismic Response of Free Standing Fuel Rack Constructions to 3-D Motions, K. P. Singh, and A. I. Soler, Nuclear Engineering and Design Vol. 80, 1984, pp. 315-329 8.
" Mechanical Test and Evaluation of the 17x17 Fuel Assembly," HCAP-8286, June 1974, Westinghouse Proprietary Class 2 9.
Pacific Northwest Laboratories (PNL), " Alternatives and Issues for Extended Storage of Spent Nuclear Fuel from Humboldt Bay Power Plant Unit No. 3," July 1985. Attached to PGandE letter to NRC, No.: HBL-86-035
- 10. SECY-84-433, " Final Rule 10 CFR Part 53, Criteria and Procedures for Determining the Adequacy of Available Spent Nuclear Fuel Storage Capacity," Dircks to Commissioners, November 7, 1984 l
- 11. NUREG-0575, " Final Generic Environmental Impact Statement on Handling and Storage of Spent Light Water Power Reactor Fuel." August, 1979
- 12. NUREG/CR-2704, "'J.S. Reactor Spent-Fuel Storage Capabilities." June, 1982 I
- 13. PGandE Memorandum on Vendor Presentation on Spent Fuel Storage and Transport, August 4, 1981 (Produced as Document No. 1 in PGandE's Response to Mothers for Peace Interrogatories, October 3, 1986) l t
h w
-e--
~
O ATTACHMENT 3 (CONT'D)
List of Documents to be Relied Uoon 14.
International Atomic Energy Agency.
1982. Storage of Hater Reactor Spent Fuel in Hater Pools - Survey of World Experience., Technical Report Series No. 218, (STI/ DOC /10/28, ISBN 92-0-155182-7)
- 15. Merrill, E. T., and J. F. Fletcher.
1983.
Economics 2 At-Reactor Soent Fuel Storaae Alternatives. PNL-4517, Pacific Northwest Laboratory, Richland, Washington
- 16. Douglas, D.
L., "The Metallurgy of Zirconium," Published by the International Atomic Energy Agency, Vienna, 1971 Supplement, page 363
- 17. Dalgaard, S. B., "Long Term Corrosion and Hydriding of Zircaloy 4 in Commercial Presaurized Reactors with Forced Convective Heat Transfer."
presented at the Electrochemical Society, Inc., May 2-7, 1976, Page 1.
- 18. Garzarolli, F., Jorde, D., Manzel, R., Parry, P. H. and Smerd, P.G.,
" Review of PHR Fuel Rod Haterside Corrosion Behavior," EPRI NP-1472, l
August 1980, Section 2.0.
- 19. Heeks, J. R., " Corrosion of Materials in Spent Fuel Storage Pools,"
BNL-NUREG-23021, July 1977.
- 20. Johnson, A.
B., " Behavior of Spent Fuel in Water Storage," BNHL 2256, September, 1977.
- 21. Cohen, Paul. " Hater Coolant Technology of Power Reactors," Monograph of ANS, 1980
- 22. Hoebel, J. C. (Westinghouse Electric Corporation), 16 February 1984.
Letter to J. V. Rocca (Pacific Gas and Electric Company), PGE-5812
- 23. Hunt, C.E.L., et al. 1981.
" Seventeen Years of Experience Hith Storage of Irradiated CANDU Fuel Under Water," NACE Conference, Toronto, Canada 24.
Irvin, J. E., et al. 1964.
"The Combined Effect of Temperature and Irradiation on the Mechanical Properties of Austenitic Stainless Steels,"
Flow and Fracture of Metals and A11ovs in Nuclear Aeolications, ASTM STP 380, American Society for Testing and Materials, Philadelphia, Pennsylvania
- 25. Johnson, A. B. Jr., et al.1982.
" Materials Behavior in Interim Storage of Spent Fuel," Trans. Am. Nucl. Soc., 43, p314-315
- 26. Kustas, F. M., et al. 1981.
Investigation of the Condition of Spent Fuel Pool Components. PNL-3513, Pacific Northwest Laboratory, Richland, Washington
O ATTACHMENT 3 (CONT'D)
List of Documents to be Relied Uoon
- 27. Nuclear Haste Policy Act of 1982
- 28. Federal Register, Volume 49, No. 171, August 31, 1984; pp. 34658 through 34696; "10 CFR Parts 50 and 51, Haste Confidenca_ Decision and Requirements for License Actions Regarding the Disposition of Spent Fuel Upon Expiration of Reactor Operating Licenses; Final Rule."
- 29. "In the Matter of Proposed Rulemaking on the Storage and Disposal of Nuclear Haste (Waste Confidence Rulemaking)," Statement of Position of the United States Department of Energy; DOE /NE-0007, 1980; and Supplement 1.
30.
" Safety Analysis of the 17 x 17 Fuel Assembly for Combined Seismic and Loss of Coolant Accident," HCAP-8236, December 1973, Westinghouse Proprietary Class 2.
- 31. " Safety Analysis of the 8-Grid 17 x 17 Fuel Assembly for Combined Seismic and Loss of Coolant Accident," HCAP-8236, Addendum No. 1 March 1974 Hestinghouse Proprietary Class 2.
32.
" Benchmark Problem Solutions Employed for Verification of the HECAN Computer Program," HCAP-8929, April 1977, Westinghouse Class 3.
- 33. PGantfE memorandum on Dry Cask Storage, J. D. Shiffer to J. O. Schuyler, May C, 1983 (Produced as Document No. 2 in PGandE's Response to Mothers for Peace Interrogatories, October 3, 1986).
- 34. PGandE Job Estimate Submitted to the Board of Directors, February 15, 1984 (Produced as Document No. 10 in PGandE's Response to Mothers For Peace Interrogatories, October 3,1986).
- 35. Peehs, M. and Fleisch, J. 1985, "LHR Spent Fuel Storage Behavior,"
Journal of Nuclear Materials, 137 (1985) p. 190-202.
- 36. Johnson, A. B. Jr., et al.1980, " Significance of Shippingport and Connecticut Yankee Fuel Examinations to Extended Hater Storage of LHR Fuel," Soent Fuel Storace Alternatives, DOE-SR-009, U. S. Department of Energy.
- 37. Distribution of Job Estimate, PGandE NPG-041, February 14, 1984 (Produced as Document No. 1 in PGandE's Response to Mothers for Peace Interrogatories, October 3, 1986)
- 38. Diablo Canyon Final Safety Analysis Report Update, Rev. 2, September, 1986 l
1 L --
ATTACHMENT 3 (CONT'D)
List of Documents to be Relied Uoon 39.
U. S. NRC Safety Evaluation Report of Diablo Canyon Nuclear Power Station, Units 1 and 2, NUREG-0675, October 1974, and Supplements 1 through 33 40.
Licensing Report for High Density Spent Fuel Storage RNks for Rancho Seco Nuclear Generating Station - Sacramento Municipal, Utilities District, Docket No. 50-312, June 1982
- 41. Spent Fuel Pool Modification For Increased Storage Capacity; Quad Cities Nuclear Unit 1, Docket No. 50-254; Quad Cities Nuclear Unit 2, Docket No. 50-265, June 1981
- 42. Safety Evaluation by the Office of Nuclear Reactor Regulation relating to the modification of the spent fuel storage pool, Facility Operating License No. DPR-70, Public Service Electric & Gas Company, Salem Nuclear Generating Station, Unit No. 1 Docket No. 50-272 43.
Philadelphia Electric Company, Peach Bottom Atomic Power Station Units 2 and 3, Spent Fuel Storage Capacity Modification Safety Analysis Report, Docket Nos. 50-277 and 50-278, Rev. 1, July 1985 44.
Licensing Report for Calvert Cliffs Unit 1 Nuclear Plant High Density spent Fuel Storage Racks, prepared by Nuclear Energy Services Inc.,
Docket Nos. 50-317 and 50-318 45.
Licensing Report for the Indian Point Unit No. 2 Spent Fuel Storage Racks, prepared by Nuclear Energy Services Inc., Docket No. 50-247
- 46. Nonlinear Time-history Seismic Sliding Analysis Report for the Indian Point Unit No. 2 Spent Fuel Storage Racks, prepared by Nuclear Energy Services Inc., Docket No. 50-247
- 47. Nonlinear Time-history Seismic Analysis for the Crystal River Unit 3 High Density Spent Fuel Storage Racks, prepared by Nuclear Energy Services Inc., Docket No. 50-302 1
48.
Licensing Report for Oconee Nuclear Station Unit 3 High Density Spent Fuel Storage Racks, Docket No. 50-287 1
- 49. Trojan Nuclear Plant Spent Fuel Storage Rack Replacement Report, Portland General Electric Company, July 1983, Decket No. 50-344
. i
i ATTACHMENT 3 (CONT'D)
List of Documents to be Relied Upon
- 50. Safety Evaluation by the Office of Nuclear Regulation relating to the second modification of the spent fuel pool, Facility Operating License No. NPF-1, Portland General Electric Company, Trojan Nuclear Plant, Docket No. 50-344
- 51. Technical Evaluation Report For High Density Spent Fuel Racks, Browns Ferry Units 1, 2, and 3, Tennessee Valley Authority, Dbcket Nos. 50-259, 50-260, and 50-296
- 52. Technical Evaluation Report for High Density Spent Fuel Racks, Cooper Nuclear Station, Nebraska Public Power District, Docket No. 50-298 I
- 53. Manual of Steel Construction, Eighth Edition, American Institute of Steel Construction Inc., Chicago, Illinois, 1980
- 55. ACI 349, Code Requirements for Nuclear Safety-Related Concrete Structures and Commentary
- 56. ASME Boiler and Pressure Vessel Code,Section III, American Society of Mechanical Engineers
- 57. NUREG/CR-1161, " Recommended Revisions to Nuclear Regulatory Commission Seismic Design Criteria," Prepared for US NRC by Lawrence Livermore Laboratory, May 1980
- 58. ASCE Draft Report " Uncertainty and Conservatisms in the Seismic Analysis and Design of Nuclear Facilities," 1984 l
l
O ATTACHMENT 4
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wo O
~
1775H/4 l
l l
C ATTACHMENT 4 Views and Position of Hitness Panels A.
Panel 1:
Sierra Club Contentions I ard II This panel will respond to the Sierra Club Contentions I and II. The panel will discuss the models developed and analyses performed to evaluate the adequacy of the fuel racks, and how these models appropriately represent the response of the fuel racks to the postulated Hosgri event.
In addition, it is the position of the panel that all appropriate parameters have been considered, or are bounded by those used in the analyses, and that the results obtained confirm that no significant damage to the fuel assemblies, racks, or pool is expected.
Thus, no adverse release of heat or radioactivity is anticipated, and the public health and safety is assured.
Further, the panel believes that the models developed by Dr. Ferguson are technically inadequate, and more appropriate rack responses would have been obtained if the inadequacies t
were corrected.
B.
Panel 2: Mothers for Peace Contention 1 l
This panel will respond to the Mothers for Peace Contention I.
The panel will discuss various alternatives considered by PGandE during the decision-making process that resulted in the selection of reracking the existing spent fuel pools, including consideration of the economic factors and other available licensed concepts.
It is the position of the panel that the requirements of the Nuclear Haste Policy Act, for
ATTACHMENT 4 (CONT'D)
Views and Position of Hitness Panels appropriate consideration of alternatives, have been met by both PGandE and the NRC.
Particularly, it is the view of this panel that PGandE has adequately considered the viable alternatives associated with the storage of Diablo Canyon spent fuel to arrive at the conclusion that reracking the existing spent fuel pools is the best alternative.
C.
Panel 3: Consumers Oraanized for Defense of Environmental Safety Contention 14 This panel will respond to the Consumers Organized for Defense of Environmental Safety Contention 14. The panel will discuss the structural integrity of the spent fuel pools during long term storage of spent fuel, and the capability of these materials to withstand the effects of the minor increases in radiation and heat due to increased spent fuel storage capacity.
It is the position of the panel that the structural integrity of the pools would not be significantly degraded due to any potential environmental stresses, and there would not be any significant neutron embrittlement or other metallurgical deterioration.
In conclusion, it is the panel's view that the structural integrity of the pools would not be adversely affected by the proposed increase in the spent fuel storage capacity.
l l
D UNITED STATES OF AMERICA c, s :,
NUCLEAR REGULATORY COMMISSION
' ' Jiii BEFORE THE ATOMIC SAFETY AND LICENSIhG BOARD m Ltc 49 P4 :51 Docket # d i50-275
-I a
)
In the Matter of
)
50323-
)
PACIFIC GAS AND ELECTRIC COMPANY )
(Reracking of Spent Fuel Pools)
)
(Diablo Canyon Nuclear Power
)
Plant Units 1 and 2)
)
)
CERTIFICATE OF SERVICE I hereby certify that on December 22, 1986, copies of the following
~
documents in the above-captioned proceeding have been served on the following by deposit in the United States mail, first class, or as indicated by an asterisk through delivery by courier:
LICENSEE PACIFIC GAS AND ELECTRIC COMPANY'S RESPONSE TO ASLB MEMORANDUM AND ORDER DATED DECEMBER 1, 1986.
B. Paul Cotter, Jr., Chairman
- Docketing and Service Branch Administrative Judge Office of the Secretary Atomic Safety and Licensing U.S. Nuclear Regulatory Commission Board Panel Washington DC 20555 U.S. Nuclear Regulatory Commission 4350 East West Highway 4th Floor Bethesda HD 20814 Glenn 0. Bright
- Lawrence Chandler, Esq.*
Administrative Judge Henry J. McGurren, Esq.
Atomic Safety and Licensing Office of Executive Legal Director Board Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Conmission Maryland National Bank Building 4350 East West Highway 4th Floor Room 9604 Bethesda MD 20814 7735 Old Georgetown Road Bethesda MD 20814 Dr. Jerry Harbour
- Lewis Shollenberger Administrative Judge Regional Counsel Atomic Safety and Licensing U.S. Nuclear Regulatory Commission Board Panel Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 4350 East Hest Highway 4th Floor Halnut Creek CA 94596 Bethesda MD 20814
O Diablo Canyon Reracking Service List Atomic Safety and Licensing Dian M. Grueneich*
Board Panel Grueneich & Lowry U.S. Nuclear Regulatory Commission 345 Franklin Street Washington DC 20555 San Francisco CA 94102 Atomic Safety and Licensing Jacquelyn Wheeler Appeal Board Panel 2455 Leona Street U.S. Nuclear Regulatory Commission San Luis Obispo CA 93401 Hashington DC 20555 j--
Laurie McDermott, Coordinator
- Mr. Lee M. Gustafson C.0.D.E.S.
Pacific Gas and Electric Company 731 Pacific Street Suite #42 1726 M Street NH Suite 1100 San Luis Obispo CA 93401 Washington DC 20036-4502 Managing Editor Janice E. Kerr, Esq.
San Luis Obisoo County Public Utilities Commission Telearam-Tribune 5246 State Building 1321 Johnson Avenue 350 McAllister Street San Luis Obispo CA 93406 San Francisco CA 94102 Richard E. Blankenburg Nancy Culver, Co-publisher 192 Luneta Street Wayne A. Soroyan, News Reporter San Luis Obispo CA 93401 South County Publishing Company P. O. Box 460 Arroyo Grande CA 93420 Dr. Richard Ferguson*
Vice-Chairman Sierra Club i
Rocky Canyon. Star Route Creston CA 93432 7
lab
/ h/k Richard F. Locke Pacific Gas and Electric Company l
77 Beale Street, 31st Floor San Francisco, CA 94106 Dated at San Francisco, California, this 22nd day of December,1986.
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