ML20053E131

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Proposed Tech Specs to Application for Amend to License R-83,re Administrative Controls/Organization
ML20053E131
Person / Time
Site: 05000128
Issue date: 05/27/1982
From:
TEXAS A&M UNIV., COLLEGE STATION, TX
To:
Shared Package
ML20053E127 List:
References
NUDOCS 8206070635
Download: ML20053E131 (3)


Text

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6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION

a. The facility shall be under the direct control of the Director-(NSC) or a licensed senior operator designated by him to be in direct control. The Director (NSC) shall be responsible to the Director of the- Texas Engineering Experiment Station (TEES) for safe operation and maintenance of the reactor and its associated equipment. The Director (NSC) shall report to the Director of TEES through the Head of Nuclear Engineering Research. The Director (NSC) or his appointee -shall review and approve all experiments and experimental procedures prior to their use in.the reactor. He shall enforce rules for the protection of personnel against radiation.
b. The safety of operation of the Nuclear Science Center Reactor shall- be related to the University Administration as shown in the following chart.

Director ,

Radiological Texas Engineering' Reactor Safety - - - -

Experiment Station -----

Safety Office (TEES) Board 1

I Head i Nuclear Engineering Research I (TEES) I I

I Senior Director Health l Nuclear Science Center-Physicist (NSC)

Reactor Operations i

6.2 REVIEW AND AUDIT

a. A Reactor Safety Board (RSB) or at least three (3) members knowledgeable in fields which relate to Nuclear Safety shall review, evaluate, and approve safety standards associated with

. the operation and-use of'the facility. The University Radiological Safety Officer shall be an ex-officio member of l the Reactor Safety Board. The jurisdiction of the RSB shall include all nuclear operations in the facility and general

! safety standards.

8206070635 820527 PDR ADOCK 05000 2 P

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BIOGRAPHICAL DATA FELTZ, Donald E. May 1982 Associate Director, Nuclear Science Center Birthdate: 1933 Citizenship: U.S. S.S. No.: 461-46-2956 Birthplace: Sherman, Texas Marital Status: Married i

l Securi ty Clearance. None '

Nund;er of Children: Two P ro f . Interes ts : Reactor Component Design - Mech.

Radiation Air Monitor Design Systems Engineering Maintenance Engineering Nuclear Experiment Design Reactor Operations EDUCATION:

M.S., Nuclear Engineering, Texas A&M University, 1963 B.S., Mechanical Engineering, Texas A&M University, 1959 EXPERIENCE:

Educational Associate Director, Nuclear Science Center, Texas ASM University, 1978 - Present Assistant Director, Nuclear Science Center, Texas A&M University, 1965 - 1978 Chief of Facility Operations, Nuclear Science Center, Texas A&M University, 1963 - 1965

Reactor Supervisor, Nuclear Science Center, Texas A6M University, 1961 - 1963 l Graduate Assistant, Nuclear Science Center, Texas A6M University, 1959 - 1961 In_dustrial Engineer in Training, Texas Power and Light, 1956 - 1957 Military U.S. Army Artillery, 1953 - 1955; Communications Chief

m FELTZo Donald E PROFESSIONAL LICENSES:

Licensed Senior Reactor Operator (Nuclear Regulatory Commission)

SOCIETY MEMBERSHIPS:

American Association for Advancement of Science American Nuclear Society Sigma Xi HONORS, AWARDS, LISTINGS AND PATENTS:

American Men of Science Co-Chairman, Test , Research, Training Reactor (TRTR) Managers, 1982 - 1983 Co-Chairman , TRIGA Owners Group , 1982 - 1983 PUBLICATIONS:

Technical Journal Papers and Contributions to Books

" Programs for Recovery from Obsolescence at the Texas A&M University Nuclear Science Center Reactor", J.D. Randall, Trans. Amer gul Nuclear Society, Suppl. No. 1 to Vol. 32, August b-8, 197'

" Compatibility of an Established ALARA Program with Reactor Operations at a Research and Training Reactor", E. F. Bates, J. D. Randall, Trans. American Nuclear Society, Suppl. No. I to Vol. 32, Augus t 5- 8, 1979 "An Attempt to Reduce fuel Cost and Improve Operating Characteristics Using Poisoned TRIGA Fuel", J. D. Randall, T. A. Godsey, and R. F. Schumacher, Trans. American Nuclear Society , August 1974

" Performance Testing ot a Mixed Core Using TRIGA-Standard and TRIGA-FLIP Fuel", Trans. American Nuclear Society, Myrtle Beach, South Carolina, Suppl. No. 1 to Vol . 17, J . D. Randall, T. A. Godsey, M. Hardt, August 1973

" Modification of a BSR-MTR Type Grid Plate to Accept Fueled Followers",

Trans. American Nuclear Society, J. D. Randall, August 1971

" Experience in Sample Encapsulation for Pool-Type Research Reactors",

Trans. American Nuclear Society, San Juan, Puerto Rico, Suppl.

to Vol. 12, J. D. Randall, P. M. Mason and D. G. Anderson, October 1969 "Sys tem Gamma Irradiation Using a Nuclear Reactor", Trans. American Nuclear Society, San Juan, Puerto Rico, Suppl. to Vol.12, D. G. Anderson, J. D. Randall, D. W. Mueller and P. S. Sandel, October 1969

" Design and Performance of a Iow Cost Fission Product Monitor System",

Trans. American Nuclear Society, Annual Meeting, J. D. Randall, E. F. Bates and P. S. Sandel, June 1968

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FELTZ, Donald E.

Significant Reports

" Core Modification of the Texas A&M Nuclear Science Center Reactor for j Improved Commercial Utilisation", Seventh U.S. TRIGA Owner's Conference, San Deigo, California, Parch 1980, with J. D. Randall, K. L. Walker and J. P. Taft

" Management of Effluent Releases and Occupational Exposures to Radiation at a University Research Reactor", Proc. , 24th Annual Meeting, Health Physics Society, Philadelphia, PA., July 1979, with E. F. Bates, R. D. Neff and J. D. Randall "A System for Documentation and Accountability of Reactor Serices",

Sixth TRIGA Owner's Conference , Oregon State University ,

Corvallis, Oregon, March 1978, with B. J. Browning, R. F. l Schumacher, J. D. Randall and E. F. Bates

" Fuel Surveillance and Accountability at the Texas A&M NSCR", Sixth TRIGA Owner's Conference, Oregon State University, Corvallis, Oregon, March 1978, with R. F. Schumacher and E. F. Bates

" Procedures for Receiving Irradiated FLIP Fuel at the Texas A&M NSCR", Sixth TRIGA Owner's Conference, Oregon State University, Corvallis, Oregon, March 1978, with E. P. Bates, J. D. Randall j and R. E. doelfel

" Report on Damaged FLIP TRIGA Fuel", Filth American TRIGA Owner's Conference, Tucson, Arizona, March 1977, with J. D. Randall and R. F. Schumacher "Effect of the Measured Power Distribution in a FLIP Fuel Element Upon the Safety Analysis Report of the NSCR", TRIGA Reactor l Owner's Conference IV, Salt Lake City, Utah, March 1976, with I J. D. Randall

" Post-Pulse Power Oscillations in a 35-FLIP Element , Mixed TRIGA t Core", TRIGA Reactor Owner's Conference IV, Salt Lake City, Utah, March 1976, with J. D. Randall and T. A. Godsey "The Improvement in Operating Characteristics Resulting from the Addition of FLIP Fuel to a Standard TRIGA Core", J. D. Randall, T. A. Godsey and R. F. Schumacher, Third European Conference of TRIGA Users, Neuherberg near Munich, Germany, October 29-31, 1974

" Loading Procedures for Shipment of Irradiated fuel", P. S. Sandel, E. F. Bates , B. Schoenbucher, February 1974, TRIGA Owner's Conference III, Albuquerque, New Mexico

" Performance Testing of a Mixed TRIGA Core", R. F. Schumacher, T. A. Godsey, J. D. Randall, February 1974, TRIGA Owner's Conference III, Albuquerque, New Mexico

" Assessment of the Technical Specification for a Mixed FLIP-Standard TRIGA Core", J. D. Randall, February 1974, TRIGA Owner's CorJerence III, Albuquerque, New Mexico

" Health Physics Procedures Shipment of Irradiated Fuel from Texas A&M University Nuclear Science Canter Reactor", R. D. Nef f, E. F.

Bates and B. Schoenbucher, July 1974, Health Physics Society 19th Annual Meeting, Houston, Texas

" Design and Installation of Fueled Followers in the Texas A6M Conversion Reactor", P. M. Mason, J. D. Randall, February 1972, TRIGA Owner's Conference II, Texas A6M L5iversity, College Station, Texas

" Feasibility Studies of a Mixed Core Using Standard TRIGA and FLIF Fuel", J. D. Randall, Mike Hardt , February 1972, TRIGA Owner's Conference II, Texas A6M University, College Station, Texas

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