ML20137T494
| ML20137T494 | |
| Person / Time | |
|---|---|
| Site: | 07000157 |
| Issue date: | 01/31/1986 |
| From: | TEXAS, UNIV. OF, AUSTIN, TX |
| To: | |
| Shared Package | |
| ML20137T473 | List: |
| References | |
| NUDOCS 8602180371 | |
| Download: ML20137T494 (31) | |
Text
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o APPLICATION FOR RENEWAL OF LICENSE SNM-180 SPECIAL NUCLEAR MATERIALS Submitted to Director, Division of Materials Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20545 by Nuclear Engineering Teaching Laboratory The University of Texas _at Austin Austin, Texas 78712 January 1986 1
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p2 REVISED SUBMITTAL FOR SPECIAL NUCLEAR MATERIAL LICENSE 70.22(a) (1)
Name of Applicant:
Nuclear Engineering Teaching Laboratory Department of Mechanical Engineering The University of Texas at Austin ETC 5.160 Austin, Texas 78712 T.L. Bauer, Laboratory Assistant Director /
Supervisor, Taylor Hall, Room 133, U.S.
Citizen D.E. Klein, Laboratory Director, Taylor Hall, Room 104, U.S.
Citizen H.G.
Rylander, Chairman, Hechanical Engin-eering, Engineering Teaching Center, Room 5.214A, U.S.
Citizen E.F. Gloyna, Dean, College of Engineering, Cockrell Hall, Room 10 310, U.S.
Cit-izen G.J.
Fonken, Provost and Executive Vice President, Main Building, Room 201, U.S.
Citizen 70.22(a) (2)
Activity and location for which Special Nuclear Material License is requested:
The Nuclear Engineering Teaching Laboratory of The University of Texas at Austin uses Special Nuclear Materials to supplement the training and instruction programs in the i
field of nuclear engineering.
The items i
described in this application are used for Junior, Senior and Graduate level labora-
,1 tory courses in the Nuclear Engineering Program of the Mechanical Engineering De-partment.
The licensed materials are to be used in experiments in the Nuclear Engineering Laboratory facilities lo-
,a
m._
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- i 1
cated in Taylor Hall of the University's Main Campus.
Laboratory facilities associated with the Nuclear Engineering Program include a re-i I
search reactor and charged particle accel-erator with appropriate Nuclear Regulatory Commission license, NRC R-92, and Texas Health Department Radioactive Materia's License Authorization TDH 6-485 No. 48.
A diagram of facility location and floor plan is included in Appendix A-1, 3
Pri-mary location for storage and operation of the assembly will be Taylor Hall Room 131.
i 70.22(a) (3)
Requested duration of license is for 5 years.
i
}
70.22(a) (4)
Description of Special Nuclear Material:
Tha Special Nuclear Material to be covered by this license is an extension of the previously granted license, SNM-180, dated February 27, 1958, and later amend-ments.
I.
U-235 Suberitical Reactor Assembly A.
Description I
1.
A hongeneous system is assembled of 2695.52 t
grams of UO2 impregnated in high density polyethylene with a total weight of 18,788.1 grams.
The UO2 is enriched to 19 7765 U-235, for a total U-235 composition of 469 74 grams.
2.
The assembly consists of a cylindrical core with 10" diameter and 14" length assemble from 8 fuel disks into one unit.
Axial and radial holes in the. assembly may be filled l
with 36 smaller fuel disks of about 1* dia-meter.
The cylindrical core unit contains 465 03 grams of U-235 with the fuel plugs totaling 4 71 grams of U-235.
(One fuel j
plug is unaccounted for.)
1 14
p4 3
The fuel assembly operation is supplemented by 3 reflector assemblies, 3" polyethylene, 6" polyethylene, and 10" graphite.
An ad-ditional graphite block provides an external thermal source.
4.
A multiplication factor of less than 7 5 has been measured for all reflector and fuel load conditions.
5.
Appendix A-4 illustrates the basic assembly components and configuration.
B.
Usage The subcritical assembly and the reflector media material are used with neutron sources to demon-
~ strate the concepts of suboritical multiplica-tion, thermal diffusion, fermi age, flux measure-ment and other basic nuclear engineering princi-ples.
Both neutron detection systems and foil activation techniques are applied in various experiments to monitor neutron flux levels and flux shape.
II.
Plutonium-Beryllium Neutron Sources A.
Description 1.
M-707 source contains 15.970 gas Pu sealed in a tantalum and stainless steel capsule with dimensions of 1.02" O.D.
x 1.46" high.
The Pu is 93 02325% enriched in (Pu-239 + Pu-241) making a total of 14.8560 gas (Pu-239 +
Pu-241).
The source has a total strength of 1.81 x 106 neutrons /second (12-3-61).
2.
M-748 source contains 31.960 gas of Pu sealed in a tantalum and stainless steel capsule with dimensions of 1.021" 0.D.
x 2.182" high.
The Pu is 93 02325% enriched in (Pu-239 +
Pu-241).
The source has a total strength of 3 83 x 106 neutrons /second (6-4-65).
3 M-700 source contains 79 940 gas Pu sealed in a tantalum and stainless steel capsule with dimensions of 1 31" 0.D.
x 2 72" high.
The Pu is 93 02325% enriched in (Pu-239 +
L
p5 Pu-241) making a total of 74 363 gas (P-239 + Pu-241).
The source has a total strength of 8.82 X 106 neutrons /second (12-3-61).
B.
Usage The plutonium-beryllium neutron sources are used for neutron detector calibration, suboritical reactor multiplication sources and neutron dose measurement experiments.
Operation of the sub-critical reactor assembly is accomplished by insertion of a neutron source into the radial or axial access hole or by positioning a source near the core assembly.
70.22(a) (6)
Technical Qualifications of Applicants I.
Administrative structure.
Staff qualifications for responsible utilization of licensed special nuclear materials in the Nuclear Engineering Teaching Laboratory include the administration of special nuclear material license, a nuclear reactor operating license and a state radioactive materials license.
The administrative structure consists of a Radiation Safety Committee, Radiation Safety Officer, Re-actor Committee, Laboratory Director and Labor-atory Assistant Director / Supervisor.
Laboratory staff includes reactor operator, research asso-ciate (radiochemist), technicians, administrative secretary and research assistants.
II.
Radiation Safety Committee The Radiation Safety Committee is established through the office of the University President and contains 3 faculty and/or staff members from Science or Engineering Departments.
A.
Duties of the Radiation Safety Officer
?
A Radiation Safety Officer acts as the dele-gate authority of the Radiation Safety Com-t sittee with responsibility to the University Safety Engineer.
Policies and practices set forth by the Radiation Safety Committee re-1
s
- Q p6 garding the safe use of radioisotopes and sources of radiation on the University campus are implemented by the Radiation Safety Officer.
Duties of the Radiation Safety Officer are numerous but consist primarily of estab-lishing, monitoring, and curtailing programs for the safe use of radioactive materials and radiation sources with respect to state or federal license requirements.
Some specific duties include periodic surveys and inspection, maintenance of radioisotope records and personnel exposures, disposal of radioactive wastes, periodic leak tests 4
of sealed radiation sources, calibration of radiation detection instruments, help in the training of staff, aide in prepar-ation of procedures, define proper radio-active material handling methods, and act as liaison for state and federal license responsibilities.
B.
Qualifications of Radiation Safety Officer Qualifications of the Radiation Safety Of-ficer require a Bachelor's degree in engin-eering, physics or related field.
Preferred qualifications require an advanced degree in health physics or radiological health or certification as a Safety Professional or Health Physicist.
Experience required is three years work in radiation safety and/or radiological health plus a thorough working knowledge of Texas Regulations for Control of Radiation and supporting regulations is-sued by the United States Nuclear Regulatory Commission.
Preferred experience includes knowledge of particle accelerators and nuclear reactors.
III.
Reactor Committee A reactor committee responsible to the Dean of l
the College of Engineering with at least three members knowledgeable in the fields of nuclear safety shall review, evaluate, and approve stan-dards associated with the operation of the lab-
p7 A
oratory facility.
Jurisdiction shall include all nuclear operations in the facility and general safety standards.
The Radiological Safety Officer is an ex officio member of the committee.
Laboratory facility operation will be under the direct control of the Laboratory Director or a licensed Senior Operator desig-nated by the Laboratory Director.
A.
Duties of the Laboratory Supervisor Daily activities of the laboratory are di-rected by an NRC licensed senior operator whose responsibility is to direct the op-eration of the nuclear reactor and other laboratory activities.
The Senior Oper-ator schedules and coordinates activities, 2
assures the maintenance of appropriate li-conse records and equipment calibrations, reviews experiments and procedures, super-vises the use of radioactive materials and sources, supervises the activities of other laboratory personnel and supports teaching research functions of the labor-atory.
B.
Qualifications of the Laboratory Supervisor Qualifications of the Reactor Supervisor re-quire a Bachelor's degree in engineering or science with three years experience in a related field.
Qualifications for a USNRC Senior Operator license is required.
Pre-ferred qualification is a Master's or Ph.D degree in a field of nuclear engineering or science with appropriate experience.
Exper-ience preferred is five years including two in a supervisor position.
Knowledge of nuclear facility operation, radiation de-taction systems, data acquisition and anal-ysis systems, electronic and mechanical measuring equipment and utilization of computer equipment are required skills.
IV.
Laboratory Staff
]
A.
Nuclear Technical Specialist (one or more positions)
l p8 i
4 Duties of a nuclear technical specialist j
include operation and maintenance of equip-ment, review of procedures and regulations, instruction and assistance of students or researchers, and assist in record main-tenance and report preparations.
Qualifi-cations require engineering or science de-gree or appropriate laboratory experience with radioactive materials and radiation detectors.
Pursuit of an NRC operator or senior reactor operator license.is re-quired.
Preferred experience includes ad-vance knowledge of electronica, computer j
programming or other valuable laboratory discipline.
I 1
B.
Research Associate (radiochemist) (half time i
to full time) l Duties of the radiochemist consists of plan-ning and supervising the utilization of the j
4
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nuclear reactor and other radiation sources for neutron activation. analysis, production j
of radioisotopes, and irradiation of mater-i ials.
The radiochemist instructs experimen-j ters in radiochemical procedures,.use of radiochemical equipment and facilities, and conducts research projects.
Qualifications require a Ph.D. degree or equivialent ex-j perience in fields of nuclear chemistry, L
with experience in various analysis tech-i niques that utilize radiation sources and radioactive materials.
i C.
Other Staff An administrative secretary aides in the preparation of reports and documents.
Other staff, students or researchers, are employed as projects warrant.
The minimum staff is j
considered to consist of a laboratory super-l visor, nuclear technical specialist (tech-nician) and half-time radiochemist.
Addi-l tional techneial support also is available i
from faculty members of the Mechanical En-l gineering Department employed to teach courses in the Nuclear Engineering Program.
l 4
1 l
e p9 i
a J
i l
4 D.
Appendix A-5 contains a block diagram of the j
administrative structure.
Specific data on key personnel is contained in Appendix A-6,8.
70.22(a) (7)
Facilities and Equipment for Handling Special Nuclear Material i
l j
I.
Areas of storage and use:
i A.
All the special nuclear materials described in this license are stored in Taylor Hall, Roon'131A, which contains a TRIGA nuclear r
i reactor.
Construction of the room consists of fireproof exterior walls, provisions for continuous radiation monitoring, and con-trolled access monitoring.
1 1.
Routine assembly, operation and storage of the suberitical core is in open areas of the reactor laboratory room.
Storage of the core is in a 55 gallon barrel pro-tected from exposure to combustible mater-ials.
1 1
2.
The fuel pellets are assembled in the re-l actor laboratory or in adjacent con-i trolled laboratory areas.
Storage of the pellets is in a floor safe located in the reactor laboratory.
i i
3 The plutonium-beryllium neutron sources are stored in a 10 foot deep storage well located in the reactor laboratory.
Be-l cause of the value of the plutonium-beryl-i lium neutron sources-as calibration stan-I dards the sources may be transported in i
an appropriate shipping container to 1
other laboratory facilities for temporary use.
1 i
B.
All materials are stored such that radiation i
levels at the container surfaces are less i
than 2 ar/hr.
C.
Appendix A-9 contains a diagram of the plu-tonium-beryllium neutron source shipping con-tainer.
I, si, /.
l'
p10 4
l II.
Shields, equipment and handling devices.
A.
The low specific activity of the non-oper-ating suberitical core material allows for direct handling of materials.
A polyethylene jacket protects the core assembly disk units i
against the small risk of radioacitve contam-i ination'from the fuel pellet disks.
Tweezers and small. lead shields or other shield ma-terial are available to handle radioactive foils generated by neutron exposure in the suberitical assembly.
Signs and rope are available to define radiation areas during assembly operation.
l B.
Routine handling of the plutonium-beryllius sources is accomplistid with long handle tongs and long threaded rods.
Shielding ma-terial such as paraffin, borated polyethy-lene, lead, concrete block and shield casks are available to provide improved radiation safety in various neutron source applica-l tions.
III.
Measuring and monitoring devices 4
A.
Personnel monitoring devices are required 3
of all persons working in the laboratory with radiation sources.
Film badges for laboratory personnel (that are sensitive to gamma radiation (10 ares), energetic beta (40 area), fast neutron (20 ares),
2 thermal neutron (10 ares), are provided by Landauer.
Pocket dosimeters (ioni-l zation chambers) are avaiable for dose measurements of gamma (0-200'eres) or thermal neutron (0-120 ares).
A TLD measure-i sent system with several detectors (.1 ar/hr-100,000 R/hr) are also available for dose evaluations.
L i
B.
Portable radiaton monitors include ionisation l
chamber, two GM tube probes, two supplemental t,
t probes and one neutron detector.
The ioni-
+
4 sation chamber is a Victoreen model 440 with scale ranges of 3 to 300 ares /hr.
Two thin
]
window OM tube monitors (~1 5 mg/cm2), one a 1
p11 Victoreen Thyac III (probe 489-35) and the other a Technical Associates PU6-1AB (probe P-6A), are normally maintained.
Scale ranges for both instruments are X1, X10, X100 and X1000.
Full scale sensitivity on the X1 scale is 200 c/m and 500 c/m for the res-pective instruments with conversions of 1000 c/m and 4000 c/m for 1 mrem /hr.
Two supple-mental scintillation probes provide detection of alphas or neutrons.
One probe (model 702-
- 5) is a thin window alpha probe for the Victoreen Thyac unit and the other probe (model PNS-20) is a polyethylene moderated neutron probe for the Technical Associates unit.
Neutron detection and dose measurement are provided by an Eberline PRS-2 with DF 3 probe (model NRD-1).
The unit has a digital readout with four ranges for either measure-ment accuracy or count time, and a manual start /stop mode.
C.
Specialized detection systems are available for analytical radiation measurements that are routinely required in a neutron activa-tion analysis laboratory.
The reactor room is continuously monitored by area radiation monitors with preset alarms (5 mr/hr) and a continuous air monitor with filter for par-ticulate monitoring that also provides aud-ible alarm indication.
A gamma spectroscopy system (Ge(Li)) and 4-6 windowless propor-tfonal counter plus other miscellaneous de-tectors and equipment represent substantial capability to analyze radioactive materials.
Both BF3 proportional counters and U-235 fis-sion counters with associated electronics are available to monitor and demonstrate opera-tion of the suboritical assembly.
Other detection systems, such a gaseous, scintil-lation or solid state detectors, allow stu-dents to count neutron activated foils.
IV.
Radioactive Waste Disposal A.
Sources of radioactive waste material from the operation of the suboritical assembly are slightly contaminated from the polyethylene impregnated fuel pellets, activation products l,
i m
p12 1
l exposed in the assembly and fission products generated by operation.
B.
Provisions exist through the Radiation Safety 4
Office for the collection and disposal of low level radioactive waste materials such as i
gloves, rags, and paper created by routing i
handling, and maintenance of the assembly.
l Disposal of materials to the sanitary sewer
{
system are also monitored by the Radiation i
Safety Officer as allowed by state licenses.
l Subgriticalirradiationsareatfluxesof
~10 n/on2 seo for a few minutes to hours.
In l
/
general, foils or materials irradiated in the assembly are short half-life and reusable thus not representing a waste material, or may be stored until the radioactive hazard diminishes.
3 C.
Calculations indicate that the total fission j
product inventory of the assembly should not normally exceed several microcuries of fis-sion product activity.
Contained as an in-l tegral part of the assembly the activity is primarily a potential hasard'to handling of the assembly are not considered to waste until the assembly ~is decomissioned. (Calou-lations in Appendix A-10).
l l
70.22(a) (8)
Safety Procedures to protect health and mini-mise danger to life or property.
j i
I.
Procedures are applied to establish safe conduct of activities with radioactive materials and radi-ation sources.
The procedures in effect are to satisfy various requirements of federal USNRC
}
licenses for special nuclear satorials and state l
TDH licenses for radioactive materials.
Pro-j oedures are reviewed by staff, researchers and students.
The reactor supervisor drafts pro-i i
cedures and approves changes.
Substantive changes to procedures are reviewed by the Reactor l
Committee.
The procedures are categorised into i
four basic functional groups: monitoring, onli-bration, operation, and emergency.
A.
Monitoring Procedures
A 1
p13 t.
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?
1.
Access to laboratory areas is controlled by staff personnel.
2.
Film badges are required in the labora-n' tory for staff when radiation sources are '
in use.
i 3
Dosimeters are required for occasional
,' ' visitors and unusual source handling con-ditions.
4.
Status of special nuclear material is ver-ified by periodic inventory (6 mo. cy-cle).
5.
Status of plutonium-beryllium is moni-tored by leak tests of source (6 ao. cy-cle).
\\
t B.
Operating Procedures i,t v
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+
1.
Routine operation of the suberitical pa-sembly shall consist of insertion of one e
of the plutonium-beryllium sources (in-oluding fuel pellets and non-fissile foils) into the suberitical core assembly ',
/
with any of the designed conditions for y,
reflector or moderator components.
2.
Routine operation of the suboritical as-sembly will be authorized by the reactor supervisor.
3 A survey of gamma and neutron radiation levels during operation will be made and an area radiation monitor with alars will be continuously active or a monitor avail-able at all times during operation.
\\
i,
\\ C.
Emergency Procedures 1.
Basic emergency procedures in effect for radiological emergencies in the Nuclear Engineering Teaching Laboratory are con-tained in Appendix A-12,16.
2.
Special precautions for material storage are required to minimize the poteatial for airborne radioactivity from exposure to fire hazards.
Storage when not in use will be in a tightly closed 55 gallon bar-i
?.
p14 i
1 f
rel.
The barrel is stored away from flam-mable materials.
The laboratory is con-structed of firewall construction.
Leak-age to the environment during normal oper-ation is controlled by weatherstripping i
entrances and filtered exhausts.
i
-II.
Training Program j
l The primary use of radiation sources and the sub-critical assembly in the Nuclear Engineering i
Teaching Laboratory is to support and extend the education of undergraduate and graduate students in basic concepts of nuclear engineering.
A portion of each student's education before per-4 forming experiments with radioactive materials will consist of material on radiation interac-tions, radiation hazards, dose measurements, and laboratory procedures.
Experiments are l
l performed with the supervision of laboratory i
staff. Staff personnel are trained to handle materials by a combinaton of formal classroom t
education and laboratory training by other 4
qualified staff depending on the nature of responsibility required.
III.
As Low as Reasonable Achievable The was low as reasonable achievable" goal of a radiation safety program is supported by the pro-cedures of the Radiation Safety Committee, Reac-tor Committee and Nuclear Engineering Teaching i
Laboratory.
Many of the type of experiments per-formed on a routine basis do not represent signi-ficant radiation doses.
Less routine experiments j
may be required on occasion that represent more l
significant doses.
Both occasional and periodic j
review of. radiation doses of staff, students, and visitors is carried out by Laboratory Staff and 4
the Radiation Safety Office.
In general, radia-tion doses are in the minimal or near minimal category for many routine experiments.
A re-l view of significant deviations from expected j
values will be reviewed by the appropriate com-mittee.
Typical values are presented in Appen-i dix A-17 2
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( 127 Nuclear Activatiob - h u~cle ar ~~ ~~ Analysis Laboratory Teaching Laboratory 12 5 12 9 I I .T 1 l Radiochemical 1
- Room I
- t. - - 4
__.___-_ a I31B Subcritical ( Storage Area Air Cond. Dist. Room ~ R E ACTOR LABORATORY c------- 1 31 4 s Control. -[ , Vestibule :: I Room j 131A Driveway office 133 104 i- - -. i-- 135 B 135 A a NORTH i A-3
{ O.010 " POLYETHYLEN E WALL t DETAll OF VOID FILLER s / L \\ CORE OR REFLECTOR MATERIAL DISKS FOIL FOR ACTIVATION @/ RADI AL VOID I n_________,c________, @lil-l l e i r-i L sl l llll l 9 3 l 5! / /"hb//////// // = Y l. l /El? *A h /. i v \\ L 3 = .pn l !!!!/! AXIAL 4 7/////'/////, CORE / l VOID i I i i 1 l 3" POLY. REFLECTOR _,j l 26"M r i 6" i L_"_____ POLYETHYLENE REFLECTOR ___________________J 34" = l l GRAPHITE REFLECTOR j O 10 " Iiii iI i eil SCALE Basic Configuration of Subcritical Assembly, Reflectors and Source p A-4 l l
( Office, Presiuent University of Texas at Austin I Dean College of Engineering i Radiation Chairman Safety Department of Comittee Mechanical Engineering l l l l l Director Nuclear Engineering ( k--- Teaching Laboratory N \\ / Supervisor,/ N Reactor Operations / 4 The safety of operation of the Nuclear Engineering Teaching Laboratory shall be related to the University Administration as shown in the following chart. ( A-5
PERSONNEL QUALIFICATIONS ( I. H. W. Bryant, Radiation Safety Of ficer A. Experience U.S. Air Force, 1950-54 One year electronics and radar school; Three years. radar technician General Dynamics, Fort Worth, Health Physics Group, 1954-1973 Aircraft decontamination programs; Instrumentation (maintenance, calibration, procure-ment) ; Area Monitoring (3 reactors, neutron generators, x-ray equipment; multicurie sources, radioactive waste); Environmental monitoring; Personnel monitoring; . Air pollution control; .The University of Texas, 1973-present Radiation Safety Officer B. Education Texas Christian University, 89 semester hours ( U.S. Public Health and NIOSH Schools: Basic Radiological Safety - 1956 Occupational Radiation Safety - 1957 Gamma Spectroscopy - 1967 Reactor Safety and Hazard Evaluation - 1969 Nonionizing Radiation - 1974 Occupational Health Hazards - 1976 The University of Texas Division of Extension Certified Safety Professionalists Safety Study Program (taught radiation safety, physics, and math sections of course) - 1975 The A&M University Extension Service Safety in the Chemical Industry - 1976 Austin Community College Instructor in safety courses C. Organization Membership Charter Member of Health Physics Society South Texas Chapter of HPS II. D. E. Klein, Director Nuclear Engineering Teaching Laboratory A. Experience Design Engineer, IBM, Summer 1969 ( Design Engineer, Proctor & Gamble, Summer 1970, 1971-1972
Summer Engineering Practice School ~, Argonne National Laboratory, 1973 (' Teaching Assistant, Univeristy of Missouri-Columbia, 1973-1977 Engineer, General Atomic,.1974 -Assistant Professor Mechanical Engineering (Nuclear Program) University of Texas,-1977-present Associate Director Nuclear Engineering Teaching Laboratory University of Texas, 1977-1978 Director, Nuclear Engineering Teaching Laboratory, 1978-present B. Education University of Missouri B.S., Mechanical Engineering', 1970 M.S., Mechanical Engineering,-1971 Ph.D., Nuclear Engineering, 1977 C. Organizations American Nuclear. Society. American Society of Mechanical Engineers Registered Professional Engineer, State of Texas, 1979 k III. T. L'. Bauer, UT Nuclear Engineering Laboratory Supervisor A. Experience The-University of Texas Center for Nuclear Studies, Laboratory Assistant, 1970-71; Nuclear Reactor. Laboratory, Research Assistant / Teaching Assistant, 1971-77; Mechanical Engineering Department (Nuclear Program), Assistant Professor, 1978-1980; Research' Scientist / Nuclear Engineering Teaching Laboratory Supervisor, 1980-present USNRC operator license, UT TRIGA, 1979-1981 USNRC senio'r operator license, UT TRIGA, 1980-present B. Education The University of Texas Bachelor of Science in Physics, 1971 Master of Science in Engineering, 1974 Ph.D.,_ Nuclear Engineering, 1978 C. Organizations American Nuclear Society A-7 C.- u.
IV. M.G. Krauta, Nuclear T:chnic:1 Specialist A. Experience Resident Associate, Argonne National Laboratory, Idaho, 1979 Graduate Research Assistant, The University of Texas at Austin, Department of Mechanical Engineering, 1979-80, 1982, 1983 Teaching Assistant, The University of Texas at Austin, Department of Mechanical Engineering, 1980, 1982, 1984 Nuclear Technical Specialist, The University of Texas at Austin, Nuclear Engineering Teaching Laboratory, 1980-present B. Education The University of Texas at Austin B.S., Mechanical Engineering, 1978 M.S., Mechanical Engineering, 1984 Work on Ph.D. in Mechanical Engineering in progress C. Organizations American Nuclear Society Pi Tau Sigma - National Mechanical Engineering Honor Society Tau Beta Pi - National Engineering Honor Society V. R.H. Clements, Nuclear Laboratory Research Assistant III A. Experience U.S. Navy Nuclear Power School / Training Unit, 1973 Engineering Watch Supervisor /USS James Madison SSBN 627, ~ 3" -78 Commercial Senior Reactor Operator /St. Lucie Nuclear Generating Station, Florida Power & Light Company, 1980-83 Operations Consultant /MEC Inc., Washington, D.C., 1983-84 Research Senior Reactor Operator / Texas A&M University TRIGA, 1984-85 B. Education Texas A&M University, Mechanical Engineering (61 hours) 1 The University of Texas at Austin, Mechanical Engineering (13 hours) VI. D.H. Eppes, Nuclear / Electronics Technical Specialist III A. Experience Westinghouse Electric Corporation, Naval Reactors Facility, Idaho National Engineering Laboratory, 1980-84 The University of Texas at Austin, Nuclear Engineering Teaching Laboratory, June 1984-present B. Education Texas A&M University, B.S. in Nuclear Engineering The University of Texas at Austin, 30 hours towards M.S. in Electrical Engineering A-8 /> Ojh r
N \\ / / '\\ \\ o = _ _ qJ l %__/ STAND ARD PIPE CAP NEUTRON O.9 m REM / HR II PIPE GAMMA READING 4 2mr/hr N 6 fj d l" l-n 1 _v DRUM R ((; )) SIZE GAMMA 15 G A L. 15_l" READING 2 m r/hr e \\@ = N ,i ro s NEUTRON (( )) x MOUND LABORATORY O.9 MREM / N STANDARD NEUTRON HR N SOURCE SHIPPING [r CONTAINER - FROM DWG. 3-174 6 7-5-57 e o 2R = c Plutonium Beryllium and Shipping Container A-9
q-( Fission Product Buildup in Subcritical Assembly Experimental measurements with a neutron source of 6 1.6 x 10 n/sec generate a neutron density approximately but conservatively represented by n (x) = a(sin bx)/x in both' axial and radial dimensions. The constants are -3 2 -1 determined to be a = 50 x 10 n/cm, and b =.18 cm The total fission rate in the assembly is then determined by n(r) V dE where V is the thermal neutron velocity f 2.2 x 10 cm/sec. The total fissions /sec are calculated 4 to be 9.65 x 10 With an energy release of 185 MeV/ fission 4 the power of the assembly will be (9.65 x 10 fission /sec) x -13 -6 ( (185 MeV/ fission) x (1. 60 - x 10 wa tts/MeV) equals 2.86-x 10 6 watts. A source strength of 8.82 x 10 n/sec would generate -6 15.8 x 10 watts. The smaller source represents about 90 watts-sec of power / year of continuous operation. A more realistic estimate is 100 hours / year or about 5.71 watts-secs with the-larger source. From 1960 till 1985 100 hr/yr operation with the larger neutron source results in (25 yr) x (3.15 x 10 sec/yr) x (1.15 x 10-5) 4 x (9.65 x 10 fissions /sec) x 6 6 12 (8.82 x 10 n/sec) / (1.6 x 10 n/sec) is 4.80 x 10 fissions. Assuming that after 100 days the fission products beta decay -8 12 at a rate of 10 decays per fission then (4.8 x 10 fissions) -8 4 x (10 decays / fission) x (3.7.x 10 decays /p curie) is less than 1.5 p curies of activity. I-A_10 ,i >- / - - a
LICENSE CONDITION FOR LEAK TESTING ( SEALED PLUTONIUM SOURCES A. Each plutonium source shall be tested for leakage at inter-vals not to exceed six (6) months. In the absence of a certificate from a transferor indicating that a test has been made within.six (6) months prior to the transfer, the sealed source shall not be put into use until tested. B. The test shall be capable of detecting the presence of 0.005 microcuries of alpha contamination on'the test sample. The test-sample shall be taken from the source or from appropriate accessible surfaces of the device in which the sealed source is: permanently or~semipermanently mounted or stored. Records of leak test results shall be kept in units of microcuries and maintained for inspection by the Commission. C. If the test' reveals the presence of 0.005 microcurie or more of removable alpha comtamination, the licensee shall immediately withdraw the sealed source from use and shall cause it to be decontaminated and repaired by a person appropriately licensed to make such repairs or to be disposed of in accordnace with the Commission regulations. Within five (5) days after determining that any source has leaked, the licensee shall file a report with the Division of Fuel Cycle and Material Safety, U.S. Nuclear ( Regulatory Commission, Washington, D.C. 20555, describing the source, the test results, the extent of contamination, the apparent or suspected cause of source failure, and the corrective action taken. A copy of the report shall be sent to the Director of the nearest NRC Inspection and Enforcement Office listed in Appendix D of Title 10, Code of Federal Regulations, Part 20. D. The periodic leak test required by this condition does not apply to sealed sources that are stored and not being used. The_ sources excepted from this test shall be tested for leakage prior to any use or transfer to another person unless they have been -leak tested within six (6) months prior to the date of use or transfer. A-ll
( University of Texas Nuclear Engineering Teaching Laboratory Emergency Procedures The basic philosophy in case of emergency is, first, to remove all persons to safe locations and, secondly, for quali-fied~ individuals to return cautiously for evaluation of the situation. Possible hazards are: (1) Isotope spill (2) Radiolytic gas release Remote hazards are: (1) Uncontrolled power excursion (2) Chemical reactions The amount of emergency action taken shall be based upon .the most pessimistic view of the potential hazard. The Super-( visor or his designated agent shall be in complete command of all persons in the Laboratory and all actions taken in the Laboratory during an emergency. During the emergency he shall follow. orders from the Laboratory Director or from the Chairman of the Radiation Safety Committee only if in his opinion such orders lead to a more conservative or more cautious approach to the correction of the overall situation. 1. Radiological Hazard. There shall be three grades (or classifications) of emergency situations ranging from the most minor to the maximum credible. The required action in each grade shall include all pertinent provisions of all lower grades. A-12 fu W-
a. Grade A: I This includes the most situations, such as a small spill of a non-volatile low-level radioactive liquid. Whoever first notices the situation is responsible for alerting all others in the Laboratory. The reactor operator shall modify his plans for operation as he may deem necessary and shall be prepared to scram the reactor until the situation is remedied. The Supervisor is re-sponsible for the evaluation and correction of the situa-tion and for supervising all necessary monitoring, remote handling, use of protective clothing, and other health and safety measures. b. Grade B: Up to 100 mr/hr Up to 5000 cpm on CAM Known cause. '( This limiting level has been established as being near the upper limits permitted by the Nuclear Regulatory Commission and Texas Radiation Council for restricted areas if a person were to remain in the area for a period of about twelve hours per calendar quarter. This grade ~has been established for cautionary purposes. Occupancy of the Laboratory is restricted to employees with film badges. c. Grade C: Over 100 mr/hr, or Over 5000 cpm on CAM Unknown cause. All persons shall immediately evacuate the Laboratory into TAY 125, picking up all readily available portable l A-13 l
survey equipment and closing the doors on their way 'I out. If there is any damage to the walls or roof of the Laboratory, the air-conditioning blower in room 131B shall be turned off (switch on right upon entering 131B). If the situation warrants, the Supervisor or his designated agent shall evacuate all adjacent rooms (104, 125, 129, 131B, 133, 135, 204). One person shall warn others not to enter the hall near the Laboratory from the north. Another will similarly guard at the corridor intersection adjacent to room 135. The Super. visor or his agent will station himself, with monitoring equipment, in the driveway south of the Laboratory. If gadiation levels in the corridors adjacent to the Labora-tory approach the legal maxima for unrestricted areas, ( the evacuation of all persons shall be continued as far as necessary to ensure compliance with these regula-tions. 2. Fire and Other Hazards In case of fire or other hazards not directly associated with radiation, the general procedure will be to scram the reactor, secure radioactive materials and notify the Fire Marshal (CTX 3511) or the Chief, University Police (CTX 4441). The Supervisor or his designated agent shall have the same authority and responsibility as.he has in the case of a radiation hazard. He shall decide the type and extent of action to be taken based upon the location and characteristics of the hazard. A-14 h/W
At least two carbon dioxide fire extinguishers shall I be maintained in readiness in the Laboratory area. In the event of fire all ve.ntilation equipment will be shut down.- 3. The following persons shall be notified: (1) Laboratory Supervisor: Thomas L. Bauer CTX 5136 (345-5044) (2) Lab' oratory Director Dale E. Klein CTX 5136 (459-0075) (3) Radiation Safety Officer: Bill Bryant CTX 4601 and 3511 (452-6689) (4) Chief, Traffic & Security Officer (Chief, University Police) CTX 4441 PAX 1031 (5) Radiation Control Division of State Health Department: (512)458-7460 ( (6) Laboratory Technician: If necessary, the Chief Traffic and Security Officer may request assistance from the City of Austin Polica and Fire Departments. If Laboratory personnel are unable to obtain sufficient survey equipment and/or protective clothing during the evacuation, such items shall be requested from the Radiation Safety Officer or the Radiation Control Division. At least once each calendar quarter the emergency procedures as out-lined above shall be reviewed by the employees involved. A-15 .i
POSITlON RADIATION SOURCE I 2 3 4 METER TYPE BARE 3 " POLY 6" POLY GRAPHITE l M-797 S l l 'O j O. lO! O S U-14 TW h S+y I II,fmr/ hr! I 6lmr/ hr 3 rnr/hk limr/ h r S U-14 T W ) 2 2 a n(Thermal) 22d/dm shcl UNDET. 120/cm dec 45/cm sec FOILS { NONE ? 'O ; O iO! O SU -14 T W i ]l S*y ,1.2 mr / h r O 10( > 0 S U -14T W ~ i, = i I i i 1 . 9 S
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