ML20207B998

Forwards List of Witnesses NRC Intends to Use in Instant Proceeding,Refs to Be Relied on & Brief Description of Position Re Issues in Case.Related Info Encl

ML20207B998
Person / Time
Site:	Diablo Canyon
Issue date:	12/19/1986
From:	Mcgurren H NRC OFFICE OF THE GENERAL COUNSEL (OGC)
To:	Bright G, Cotter B, Harbour J Atomic Safety and Licensing Board Panel
References
CON-#486-1987 OLA, NUDOCS 8612300005
Download: ML20207B998 (20)

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UNITED STATES g

8 o NUCLEAR REGULATORY COMMISSION DOCKETED

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'86 DEC 23 P3 :01 December 19, 1986 - -

B. Paul Cotter, Jr. , Chairman Glenn O. Bright, Esq.

Atomic Safety and Licensing Atomic Safety and Licensing Board Panel Board Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C. 20555 Dr. Jerry IIarbour Atomic Safety and Licensing Board Panel i U.S. Nuclear Regulatory Commission Washington, D.C. 20555 In the Matter of PACIFIC GAS AND ELECTRIC COMPANY (Diablo Canyon Nuclear Power Plant, Units 1 and 2)

Docket Nos. 50-275 OLA and 50-323 OLA (Spent Fuel Pool)

Dear Administrative Judges:

In accordance with this Board's order of December 1,1986, attached is a list of the witnesses the Staff intends to use in the instant proceeding, the ref-erences they currently plan to rely upon and a brief description of their position regarding the issues in this case. The Staff will offer two docu-ments as exhibits in this proceeding: the Environmental Assessment by the Office of Nuclear Reactor Regulation Relating to the Expansion of Spent Fuel Pools Facility Operating License Nos. DPR-80 and DPR-82 Pacific Gas and Electric Company, Diablo Canyon Nuclear Power Plant, Unit Nos. I and 2, Docket Nos. 50-275 and 50-323, and the Safety Evaluation By The Office of Nuclear Reactor Regulation Relating to the Reracking of the Spent Fuel Pools At the Diablo Canyon Nuclear Power Plant, Units 1 and 2 As Rela'9d to Amendment No. 8 to Unit 1 Facility Operating License No. DPR-80 and Amendment No. 6 to Unit 2 Facility Operating License No. DPR-82, Pacific Gas and Electric Company Docket Nos. 50-275 and 50-323. The documents that the Staff at present intends to use for purposes of cross-examination 8612300005 861219 I PDR G ADOCK 05000275 PDR

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e are affidavits of Dr. Ferguson, filed in the U.S. Court of Appeals for the Ninth Circuit and before the Commission, and his responses to interrogato-ries filed in the instant proceeding.

Sincerely, le dy L NcGurren Cou for NRC Staff Ofnce of the General Counsel Attachments: As stated ec: Service List i

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- CONSUF.1ERS ORGANIZED FOR DEFENSE OF ENVIRONMENTAL SAFETY CONTENTION 14 Staff Witness Clifford David Sellers (Statement of Professional Quali-fications attached).

Witness Views: It is my opinion that neutron embrittlement does not affect the structural integrity of the spent fuel pools and that other metalurgical deterioration will not affect the structural integrity of the spent fuel ponds under design operating conditions.

References:

A. B. Johnson, W. J. Bailey and E. R. Gilbert, S. C.

Inman " Materials Behavior in Interim Storage of Spent Fuel," Report No. PNL-SA-10553, dated November 1982 Technical Report Series NO. 218 " Storage of Water Reactor Spent Fuel in Water Pools - Survey of World Experience," IAEA; Vienna, Austria 1982

" Waste Confidence Decision", August 22, 1984 -

49 Fed. Reg. 3458, August 31, 1984 "Reracking of Spent Fuel Pools Diablo Canyon, Units 1 and 2," PG&E letter dated September 19, 1985 MOTIIERS FOR PEACE CONTENTION 1 AND SIERRA CLUB CONTENTION 1(B)7 Staff Witness Donald F. Cleary (Statement of Professional Qualifica-i tions attached).

l Witness Views: I have concluded that the proposed reracidng at Diablo Canyon has clear advantages over each of the alterna-tives for storage of spent fuel asserted in Mothers for Peace Contention 1 and Sierra Club Contention 1(B)7.

j The environmental impacts of the proposed reracking would be less than for each of the alternatives except l

l that of storage in a permanent federal repository.

The overriding advantages of reracking are availabili-ty, timing and cost. A permanent federal repository will not be available until 1998 at the earliest. Storage of spent fuel at a Federal Interim Storage (FIS) facili-ty is an alternative not currently available and if and when it does become available it will be an alternative of last resort under Section 134(b) of the Nuclear Waste Policy Act of 1982 and 10 C.F.R. Part 53 and therefore will not open to Pacific Gas and Electric Company until the utility has exhausted other alternatives.

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, The shipment of spent fuel to the storage facility of another utility company is an unlikely alternative as other utilities are concerned with meeting their own ]

spent fuel storage requirements until space in a feder-

• si repository is available. Reducing spent fuel gener- i ation through operating the Diablo Canyon units at l lower power levels would result in severe economic penalties and'likely would involve exhaustion of exist-ing spent fuel storage space before a federal reposito-ry is available, thereby resulting in complete shutdown of the units. Construction of a new independent spent fuel storage installation (ISFSI) is feasible but would be economically unattractive due to the cost of con-structing additional storage facilities and the potential cost of replacement energy for the period between ex-haustion of storage space in the existing pools and completion of an ISFSI. The alternative of no action is unacceptable because exhausted storage capacity will lead to plant shutdown. The economic cost of unused generating capacity and the necessity to purchase re-placement energy and perhaps to build replacement capacity will be enormous.

Peferences: U.S. Department of Energy, Office of Civilian Radioac-tive Waste Management, " Annual Report to Congress,"

March 1986.

U.S. Department of Energy, Richland Operations Of-fice , " Spent Fuel Storage Requirements ," s DOE /RL-86-5, October 1986.

U.S. Department of Energy, Office of Civilian Radioac-tive Waste Management, " Implementation Plan for De-ployment of Federal Interim Storage Facilities for Commercial Spent Nuclear Fuel," DOE /RW-0019, Janu-ary 1985.

U.S. Department of Energy, Assistant Secretary for Nuclear Energy, " Technical Reference Book for the Energy Economic Data Base Program," DOE /NE-0059, September 1984. ,

U.S. Department of Energy, Office of Civilian Radioac-l tive Waste Management, " Mission Plan for the Civilian Radioactive Waste Management Program," DOE /RW-0005, April 1984 I U.S. Department of Energy, International Spent Fuel l Storage Program , " Spent Fuel Storage Alternatives,"

(Proceedings of and IAEA Advisory Group / Specialist Meeting, Los Vegas, Nevada, November 17-21, 1980)

D OE-SR-0009, 1980.

U.S. Nuclear Regulatory Commission, " Replacement Energy Costs for Nuclear Electricity-Ganerating Units in the United States," (Prepared by J. C. VanKuiken, W. A. Buehring, K. A. Guziel, Argonne National Lab-oratory) NUREG/CR-4012, October 1984.

U.S. Nuclear Regulatory Commission, " Final Generic Environmental Impact Statement on Handling and Stor-age of Spent Light Water Power Reactor Fuel, "

NUREG-05"5, August 1979.

"Inside Energy with Federal Lands ," February 17, 1986, published by McGraw Hill Inc.

SIERRA CLUB CONTENTIONS I(A)3, 4; I(B)2, 8; II(A)1, 2, 3, 4; AND II(B)1, 2, 3, 4 Staff Witnesses Howard Fishman and Frank Rinaldi (Statements of Pro-fessional Qualifications attached).

Witnesses Views: With regard to Sierra Club's assertions in the above contentions, it is our opinion that the Licensee has used good engineering judgment in modeling the pro-posed high density storage rack (s) and spent fuel pool wall interaction during the postulated Hosgri earth-quake. It is our opinion that no rack damage will occur as a result of this interaction and that there will be no permanent deforme.tfon to any of the Diablo Can-yon spent fuel pool racks or spent fuel pool walls.

References:

The references the witnesses will rely upon are those set forth in the Diablo Canyon Safety Evaluation de-scribed above as well as the references set forth in Appendix A to that Safety Evaluation. The witnesses will also rely upon SIMOKE, a Program for Artificial Motion Generation , distributed by NISEE/ Computer Applications.

SIERRA CLUB CONTENTIONS I(B)9; AND II(A)5, II(B)5 Staff Witness Walter L. Brooks (Statements of Professional Qualifica-tions attached).

Witness Views: With regard to the itse of boraflex for all the racks, the NBC staff requires that the k-effective value is less than or equal to 0.95. Since the Diablo Canyon Region 2 racks (without bornflex) meet this criterion when loaded with fuel meeting the burnup requirements of the proposed Technical Specifications (Figure

• 3.9-2), the Staff found the criticality design of these proposed racks to be acceptable.

The Intervenor's assertion that the postulated Hosgri earthquake will cause collisions between racks, groups of racks and the pool walls resulting in increase of k-effective above 0.95 has validity only if there is significant distortion in the proposed racks.

References:

Reracking of Spent Fuel Pools Diablo Canyon, Units 1 and 2, dated September 1985, submitted by Pacific Gas and Electric Company on September 19, 1985 Nuclear Criticality Safety Considerations in the Design of Ifigh Density Spent Fuel Storage Racks By Stanley E. Turner, Ph.D. , P.E., published in the .

Proceedings of the National Conference, ASME, June 19-24,1983 SIERRA CLUB CONTENTIONS II(A)6, 7, 8, 9; II(B)6, 7, 8, 9 Staff Witnesses Walter L. Brooks , Robert W. Fell and Amarjit Singh (Statements of Professional Qualifications attached) .

Witnesses Views: If criticality is assumed to occur, large amounts of heat and radiation may be generated resulting in po-tential radiological releases. However, since the racks are designed in accordance with the PRC general de-sign criteria and the integrity of the racks is main-tained (see, testimony above), criticality will be prevented.

The spent fuel pool cooling system is designed to re-move decay heat from the pool under normal and ab-normal conditions.

The water and c screte in the spent fuel pool would provide some shielding from radiation emitted by the fuel rods if there were a criticality accident. Howev-er, doses could occur from such an accident if noble gases were released depending on the severity of the criticality.

References:

NRC Staff Safety Evaluation, supra.

"Roracking of Spent Fuel Pools Diablo Canyon, Units 1 and 2", dated September 1985, supra.

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( , CLIFFORD DAVID SELLERS SENIOR MATERIALS ENGIhEER ENGINEERING BRANCH

.,PWR-A PROFESSIONAL QUALIFICATIONS In my present position as Senior Materials Engineer in the Materials Engineering Section of the PWR-A Engineering Branch I am involved in safety review and evaluation of materials used in the construction of nuclear power plants.

The Materials Engineering Section of the Engineering Branch is responsible for materials application, metallurgical investigative studies including

, fabrication problems, and inservice degradation processes such as stress corrosion and radiation effects. Other resposibilities of this section includes various aspects of materials integrity, fracture toughness criteria, inservice degradation processes such as corrosion one, material irradiation effects for the wide range of materials used in the construction of nuclear power plant components. In addition to the normal casework review responsi-bilities I have been involved in problems in many of the areas enumerated above. I was also previously involved in work leading to an NRC position of bolting application reouirements. Currently, much of my work involves steam generator problems.

I have a BS degree in Metallurgy (Penn State 1951) and have done graduate work at the University of Delaware and University of Idaho.

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I had been in the Materials Engineering Branch continuously since starting with the AEC late in 1973 until the dissolution of that branch in 1985 except for a brief assignment to Division of Operating Reactors, Engineering Branch.

MuchofmyeffortwithOperatingDe[ctorswaswithlowpressuresteamturbine disc cracking and primary comoonents sunport structures, From 1968 to 1973 I was a Senior Engineer with Westinghouse Nuclear Energy Systems-PWR Systems Division, Monroeville, Pennsylvania. In this position my duties involved design assistance and troubleshooting (both shop and field) on reactor internals, control rods, instrumentation, and reactor pressure vessels.

These duties and other field problem investigatory activities led to prepara-tion and use of field kitsto perform in-situ metallography. In this and other connections I have been involved in various activities at Beaver Valley,

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Cook, Zion, Turkey Point, San Onofre, Ginna, Yankee Rowe, Haddam Neck, Indian Point, Salem, and SENA.

During the years 1964 to 1968, I was employed as a Quality Engineer at the Naval Reactors Facility located near Idaho Falls, Idaho and served as site materials engineer. In my capacity of quality assurance engineer I prepared procedures and specification supplements, reviewed procurement documents and performed audits. My major accomplishments were the establishment of materials receiving inspection and materials verification programs.

From 1961 through 1963 I was a senior metallurgical engineer at the Bettis Atomic Power Laboratory. In this position I was a " cognizant engineer" for

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various high strength structual alloys such as 17-4 PH; 12% chromium steels; low alloy (bolting) steels; Inconel X; Haynes 75, etc., with responsibility for specification preparation and troubleshooting. Additionally, I was involved in failure analysis of components fabricated from these alloys. I also performed field and in-plant inspection of 17 a PH control rod drive mechanism components. Additionally, I was also involved in preparation of irradiation programs of high strength bolting materials ard in testing of specimens prepared for irradiated components. The later led to the presentation of a paper on irradiated stainless steel at tit 1963 '. net' a :

From graduation in 1951 I was employed in various levels of increasing responsibility at the Westinghouse Electric Corporation Aviation Gas Turbine Division until that Division's dissolution at the end of 1960. I initially was responsible for the radiographic inspection of and shop contact on aluminum and magnesium alloy castings and investment cast refractory alloys and fabrications. Subsequently I was involved in shop contact and troubleshooting of in-house casting and forging shops. Later I was responsible for development of and applications for improved light-alloy and refractory alloys, including preparation of design data and testing of engine hardware. Near the end of my service with this division I performed extensive failure analysis work on both engine and test rig failures, both in-house and in the field. During my period of employment in this division I received 13 patent disclosure awards and was also involved in training of personnel in the areas of physical metallurgy and failure analysis.

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• In my last year of college and the preceeding summer I worked at Penn State in the Metallurgy Department as an undergraduate lab technician with responsibilities for fabrication, testing, and photography of equipment and specimens and for the metallography of test specimens. The project was a joint Metallurgy / Ceramics Department project on the vitreous enameling of steel.

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(- STATEMENT OF PROFESSIONAL QUALIFICATIONS ,,

Y , DONALD P. CLEARY .- .-

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My name is Donald P. Cleary. I am Acting Chief of the Sike Analysis Branch and also Section Leader of the Regional Impact Analysis Section within that branch. The Site Analysis Branch is in the Division of Engineering, Office of Nuclear Reactor Regulation, United States Nuclear Regulatory Co:miission (NRC). I have been with th'e NRC (previous'If Atomic Energy Comission) since 1973 and was appointed Sectiori Leader in 1976. '

As a technical reviewer and supervisor I have been responsible f'or various sectionsofenvironmentalLyactstatements. T.hese include social and ,

economic impacts, need for the project, alternatives to the project, irreversible and irretrievable comitments of resources, relationships ,

k between short-term use and long-tenn productivity of man's environment,' ,

and benefit cost balance.

Prior to joining NRC, I was first an Indus'try Economist and then Staff Specialist for Program Review and Evaluation in the Office of Resource Utilization, National Marine Fisheries Service, National Oceanic and Atmospheric *' Administration, U.S. Department of Commerce.

I received a B.A. in economics from the University of Massachusetts in 1961, an,d an. M. A. in economics from the University of Florida in 1963.

I completed course work for the Ph.D in Natural Resource Economics at the University of Michigan.

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Finite Element Methodology

( Structural Mechanics and Dynamics Applied Mathematics Heat Transfer Software Development l Fluid Dynamics 4

HOWARD M;RTIN FISHMAN PROFESSIONAL EXPERIENCE

' Mr. Fishman, a Head of the Structural Engineering Section of the Engineering Department, joined Franklin Research Center in 1964. He he.s been primarily involved in the development of the digital computer programs used at FRC for the solutions of complex thermal-mechanical systems. As former head of the Computer-Aided Design Sectidh at FRC, he has developed software for interactive graphic modeling and display of mechanical systems. Mr. Fishman has performed research and provided consultation on projects requiring static, seismic, dynamic, inelastic, and thernal analysis and code evaluation for a

' variety of structural systems. These systems include nuclear containment buildings, heat exchangers and pressure vessels, piping, valves, and supports. In addition, Mr. Fishman has analyzed and developed software for cartridges and ballistic missiles; submarine hulls; centrifuges and motion simulators; mills, kilns, and other mining equipment; ball, rollar, journal, and foil bearings; chemical processing machinery; and turbine rotors, hubs, 4

( blades, and pedestals.

Prior to joining FRC, Mr. Fishman performed research in the theoretical and experimental analysis of bearing dynamics and deformation, and taught mechanics of materials. He is involved in Drexel University's Continuing Education Program, presenting seminars in finite element techniques and computerized structural and piping analyses.

. ACADEMIC BACKGROUND Engineering Mechanics Program, University of Pennsylvania All Ph.D. requirements except dissertation satisfied.

M.S., Mechanical Engineering Massachusetts Institute of Technology, 1960 B.S., Mechanical Engineering University of Pennsylvania, 1959 PROFESSIONAL AFFILIATIONS American Society of Mechanical Engineers Member, Subgroup on Design Analysis, ASME Boiler and Pressure Vessel Committee

/ Chairman, Working Group on Shalls, ASME-B&PVC American Institute of Aeronautics and Astronautics, Member of Interactive Computer Graphics Technical Committee Fishman-1

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PUBLICATIONS AND REPORTS

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1. "An Experimental Determination of the Effect of Vapor Velocity on Condensation on the Outside of Horizontal Tubes," Thesis, MIT, June 1960

2. " Kinematics of Four-Ball Apparatus with Generalized Configuration," SKP Report AL62T014, 1962. .-

3. " Influence of Lubrication on Endurance of Rolling Contacts," SKP Progress Report #4, AL62T015, September 1962.

4. "Effect of Contact Deflections in the Ze'or Spin-to-Roll Ratio Four-Taall Arrangement," SKF Report AL62T016, 1962.

5. " Development of Analytical Method for Predicting Deflections at Specified Locations for a 1/3 Scale Model of SS(N)637 Engine Room Subject to External Hydrostatic Pressure," FIE Report F-B2314,1966.

6. " Preliminary Design of Centering Pin Shock Band," FIE Report I-C2009-01, 1967.

7. " User's Manual for the CRTPLS Computer Program," FIRL Report F-C1865-05, September 9, 1970.

8. " User's Manual for the AXPLAS Computer Program," FIRL Report F-C2763-01-1, 1970.

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9. "GENSHS, Layered Static Shell Program, Program User's Guide," FIRL Report, 1970.

10. "PIPDYN, User's Manual for Three-Dimensional Piping Systems Analysis,"

. FIRL Report PD-C2689-2, 1970.

11. "LUMS, User's Manual for the Dynamic Response of Lumped Mass Systems Program," FIRL Report, 1970.

12. " Automated Cartridge Case Design and Thermal Analysis," FIRL Report F-C2695, 1971.

13. "A Three-Dimensional Finite-Element Computer Code for the Analysis of Complex Structures," NED, Vol. 20, 1, June 1972, Co-author with Z. Zudans, M. M. Reddi, and,D. Gray.

14. "Three-Dimensional Finite-Element Stress Analysis of the ATR Reflector Block," FIRL Report F-C3355-01, 1972.

15. "BOXPLT Program for Plotting BOXSHL Results, Program User's Guide," FIRL Report, 1972,

16. "HYBOS, User's Manual," FIRL Report, 1972.

( 17. "FELAP, Finite Element Computer Program, Input Description and User's Guide," FIRL Report, 1972.

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18. " Review a'nd Analysis of an S5G Bundle Type Pressuriser," FIRL Report

.( 31G-C2962-09, 1972.

19. " Theory and Users Manual for EPACA - General Purpose Elastic-Plastic-Creep Finite Element Analysis Program for Three-Dimensional Thick Shell Structures," Final Report F-C3038, June 30, 1972.

20. " Elastic-Plastic-Creep-Analysis of High Temperature Nuclear Reactor Components," Co-author with Z. Zudans. M. M. Reddi, T. Y. Chow, and H. C.

Tsai. Presented at 2nd International Conference en Structural Mechanics in Reactor Technology, 1973, Berlin. ,

21. "BOXSHL, Layered Static Box Shell Program, Program User's Guide," FIRL Report, 1973.

22. "PIPDYN II, A Computer Progrant* for the Complete Analysis and Evaluation of Piping Systems and Three-Dimensional Frame Structures," Three Volumes, FIRL, 1973.

23. " Comprehensive Design Review of the Page Engineering Co. Model 757-374 Walking Dragline," Report F-C4000, May 1975.

24. " Elastic-Plastic, Finite Element Analysis of Elbows," Report F-C2570. .

25. " Preliminary Stress Analysis of a Pipe Joint," FIRL Report F-C4318, November 1975.

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26. " Structural Analysis of PDX Vacuum Vessel," Final Report F-C4385, May 1977. 1

27. " Thermal and Structural Analysis of 2-1/2 inch 'Y' Globe Valves for Fuel Rod Test Facility," FIRL Final Report F-C4533, April 1977.

28. " Seismic Withstand Capability of Allis-Chalmers AC Induction Motor," FIRL Report C4845, March 1978.

29. " Seismic Qualification Analysis of Yarway Valves," FIRL Report F-C4878, May 1978.

30. " Analysis of Nordberg Grinding Mills," FIRL Report F-C4904.

31. " Dynamic Stress .3nalysis of A Reactor Vessel Closure Subjected to j Pressure Transient," FRC Report 02I-C5135-01, August 1979.

i 32. " Structural Analysis of the San. arco Mill," FIRL, Inc. Report F-A5208,

! September 1979.

33. " Analysis of Line 13 & 32 Propellers," FIRL, Inc. Report F-A5208, September 1979. -

34. " Evaluation of Aerofall and Koppers Designs of Wet Semi-autogenous

( Grinding Mills with Gearless Drive and Associated Equipment," FRC Report l

021-A5226-01.

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35. " Turbine Shafting Failure Analysis at Webbers Falls," FRC Report

] ( F-C5376-01 to Corps of Engineers, February 1981.

f 36. " Structural Experience with Operating Reactors, A Designer-Analysts' i View," Sixth International Conference on Structural Mechanics in Reactor Technology (SMIRT-6), Paris, France, August 17-21, 1981. Presented at special session, " Operating Reactor Structural Experience." Co-authored with Z. Zudans and G. P. Wachte11.

37. " Computer Simulation of Dynamic Response in Railroad Impact Test,"

Proceedings of 13th Annual Pittsburgh Modeling and Simulation Conference, l April 1982. Co-authored with B. J. Sullivan, j 38. " Response Spectra and Response Spectrum Envelopes for the Salem Nuclear Generating Station," FIRL Inc. Technical Report 402-2530-002-9, September

7, 1982. -

39 "RSCENV - Response Spectra Curve Envelop Computer Program," User's Guide, FRC Technical Report 402-2530-001-10.

40. " Resonant Freguency Analysis for Extended Structures," Proceedings of j

First International Modal Analysis Conference, November 1982.

41. " Perceived Margins of Safety in Nuclear Power Plant Structures under Evolving Design Codes and Loading Criteria," Eighth International i[ Conference on Structural Mechanics in Reactor Technology (SMIRT),

i \ Brussels, Belgium, August 20, 1985. Co-authored with T. C. Stilwell, M.

i Darwish, and D. Persinko.

, 42. " Critical Design Review of the Model WL-50 Bucket Wheel Reducing," FRC i Technical Report F6085, October 1985, Co-authored with J. E. Sague l 43. "A Structurai Model Demonstrating Incineration Hearths Remain in Place l After Many Thermal Cycles," FRC Technical Report 6059-033, January 14, 1986, Co-authored with T. C. Stilwell

44. " Failure Analysis of the HAB Launcher Telescopic Hydraulic Cylinders, FRC l Technical Report," F-6144-1, April 4, 1986, Co-authored with A. A. Okaily j and E. Mucha l

45. "The Ar.alysis and Design of High Performance Motion Dampers," to be presented at the ASME 1986 Winter Annual Meeting ASME Journal of Dynamic Systems, Measurement and Control, Co-authored with D. J. Barrett, E.

Mucha, R. C. Chow, and B. J. Sullivan PATENTS U.S. Patent No. 4,446,716 issued May 8, 1984, "Self Co/pensating Centrifuge Arm"

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PROFESSIONAL QUALIFICATION OF FRANK RINALDI

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I am a Structural Engineer in the Engineering Branch of the Division of PWR Licensing-A, office of Nuclear Reactor Regulation,11.S. Nuclear Regulatory Comission. I am responsible for the Veview and evaluation of adeouacy of criteria used in the structural design and analysis of Seismic Category i  ;

structures, systems and components of nuclear power plants assigned to the Enaineering Branch.

I received a Bachelor's Degree in Civil Enoineering from the City Colleae of New York in 1966 and a Master's Degree of Science in Civil Engineering from the University of Maryland in 1974 I am a registered Professional Engineer in the State of Virginia and a member of Working Group on Concrete Containments and of the Main Committee of the ASME/ACI 359 (Code for Concrete Reactor Vessels and Containments).

( My professional experience includes:

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Present Structural Enaineer, Engineerino Branch, Division of PWD Licensino-A, Office of Nuclear Reactor Reaulation, U.S. Nuclear Regulatory Commission 1974 -

1985 Structural Engineer, Structural Engineering Branch, Division of Systems Safety Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission 1971 - 1974 Structural Engineer Fuel Fabrication and Transportation Branch, Division of Materials Licensing, U.S. Atomic Enerav Commission 1470 - 1971 General Engineer, Division of Research, n evelopment, Testing and Evaluation, Naval Facilities Engineerina Command, U.S.

Navy Department 1968 - 1970 Structur:1 Enaineer, Electronics Support Rranch, Naval Facilitias Engineering Command, U.S. Navy Department 1966 - 1968 Civil Engineer, Chesapeake Division, Naval Facilities Enaineering Command, U.S. Navy Department

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i WALTER l.. BROOKS .

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0FFICE OF NUCLEAR REACTOR REGULATION PROFESSIONAL QUALIFICATIONS l

My name is Walter L. Brooks. I am employed as a Nuclear Engineer in the Reactor Systems Branch, Division of PWR Licensing-A, Office of Nuclear Reactor

, Regulation (NRR). In my position I have primary review responsibility for the core physics aspects of applications for construction permits and operating licenses. In addition I review the criticality aspects of fuel storage racks at the request of the branch having primary review responsibility. In the area of operating reactor licensing actions I have primary responsibility for the review of core phy' sics and spent fuel pool criticality aspects. I have field this position for six months. I held a similar position for six years in the previous NRR organization.

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I hold a bachelors degree in mathematics from Lincoln Memorial University and masters degree and doctorate from New York University. Prior to joining NRC (then the Atomic Energy Commission) in 1974 I had a total of 21 years of experience beyond graduate school - almost entirely in the nuclear field. All ,

of my employment was with the Gulf Un!ted Corporation, Nuclear Development -

Corporation of America, and Nuclear Development Associates. Among my duties during my employment from 1953 to 1974 were performance and evaluation of

critical experiments for light water moderated, heavy water moderated, and 1

fast (liquid metal moderated) reactors, development of calculation methods for heavy water roderated reactors and verifiction and modi.fication of a nodal

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calculation technique for light, water moderated reactors.

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• PROFESSIONAL QUALIFICATIONS OF ROBERT W. FELL

=4 w EDUCATION University of Maryland, Ph.D. Program (All Completed Except Dissertation)

(Mechanical Engineering- Energy Conversion)

University of Michigan, M.S.E., Electrical Engineering,1967 University of Michigan B.S.E., Electrical Engineering and Engineering Mathematics, 1966 Bettis (Westinghouse) Atomic Powe'r Laboratory Engineering School, Nuclear Engineering Certificate,1969 (U.S. Nuclear Navy)

REGISTRATION Professional Engineer - Electrical and Mechanical Engineering EXPERIENCE United States Nuclear Regulatory Commission,1981 to Present NUS Corporation,1971 to 1981

/ Division of Naval Reactors (U.S. Navy),1967 to 1971 i University of Michigan,1966 to 1967 International Business Machines 1963 to1967 U.S. Nuclear Regulatory Commission (USNRC) - As a Nuclear Engineer, .

responsible for design, review and evaluation of all PWR balance of Pl ant systems; review of plant technical specifications; safety evaluation of plant systems; review and evaluation of liquid, gasious and solid radioactive waste management systems; Developed guidelines for solid waste process control programs (PCPs); Responsible for radioactive effluent technical specifications, and associated effluent limits and monitoring programs. Managed subcontractors and developed programs for testing laboratories.

As a project manager, coordinated all activities required to evaluate the acceptability of older nuclear power plants compared to present NRC licensing criteria; evaluated desirability of backfit modifications to bring old nuclear plants in compliance with present criteria.

NUS - Responsible for the detail design and project managment of high radiation reactor coolant end containment sampling systems for the Zion Nuclear Power Plant. Developed the conceptual design for the TREAT air cooled test reactor cooling system.

Analyzed the technical feasibility to find lost isotope heat sources using f infrared, gamma and neutron detection schemes for ERDA. Set up NUFUEL

\ computer code for demand, supply and cost studies for varicus nuclear fuel cycles. Projected nuclear power growth and associated demands for uranium recycle. Responsible for the mechanical design and I

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PROFESSIONAL QUALIFICATIONS AMARJIT SINGH PLANT SYSTEMS BRANCH DIVISION OF PWR LICENSING - A I am employed as a Mechanical Engineer (Auxiliary Systems) in the Plant Systems Branch, Division of PWR Licensing - A, Office of Nuclear Reactor Regulation, United States Nuclear Regulatory Comission, Washington, D.C.

My duties consist of reviewing and evaluating the associated safety

( considerations on nuclear power and fuel handling systems and associated engineering fields on power reactors. I am responsible for providing technical input to various documents including Safety Evaluation Reports.

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I received a Bachelor of Science Degree in Nuclear Engineering from Catholic University of America, Washington, D.C. in 1976. Since 1976. I have taken courses on PWR and BWR Technology. I have completed 15 credits in Master of Science in Engineering degree program at Catholic University of America. I have been a registered Professional Engineer in the State of Wisconsin (No. 19779) since 1980.

My experience includes 10 years with the Department of Energy, Naval Facilities Engineering Comand, Chesapeake Division and Department of Environmental Services as Environmental Engineer engaged in diversified engineering work including: fossil power plants, facility surveys, engineering studies, contract administration, project engineering, water and waste water treatment plants.

I From August 1981 to the present, I have been employed by the United

. States Nuclear Regulatory Commission. I have been in the Auxiliary Systems Branch of the Division of Systems Integration until November 24, 1985 when NRR was reorganfied and I have been assigned to the Plant Systems Branch, Division of PWR Licensing - A. I have been the Task Manager for the resolution of two Generic Issues. My duties include safety reviews and evaluations of system design and operation at nuclear power plant facilities. As required. I prepare safety evaluations and make presentations to the Advisory Committee on Reactor Safeguards. I am presently reviewing applications for operating licenses, proposed Technical Specifications, and spent fuel expansions. To date I have reviewed the design of the spent fuel storage facilities for 7 reactor sites.

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