ML20003H505
| ML20003H505 | |
| Person / Time | |
|---|---|
| Site: | 07000157 |
| Issue date: | 01/30/1981 |
| From: | TEXAS, UNIV. OF, AUSTIN, TX |
| To: | |
| Shared Package | |
| ML20003H504 | List: |
| References | |
| 18353, NUDOCS 8105060207 | |
| Download: ML20003H505 (28) | |
Text
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O REVISED 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 i
r by Nuclear Engineering Teaching Laboratory 1
University of Texas at Austin i
Austin, Texas 78712 January 1981 I
(
iS353 8105060
REVISED SUBMITTAL FOR SPECIAL NUCLEAR MATERIAL LICENSE 70.22(a) (1)
Name of Applicant:
Nuclear Engineering Teaching Laboratory Mechanical Engineering Department The University of Texas Austin, Texas 78712 T.
L. Bauer, Laboratory Supervisor Taylor Hall, Room 133, U.S. Citizen D. E. Klein, Laboratory Director Taylor Hall, Room 104 U.S. Citizen H. G. Rylander, Chairman, Mechanical Engineering Taylor Hall, Room 167, U.S.
Citizen E.
F. Gloyna, Dean, College of Engineering Cockrell Hall, Room 10.310, U.S. Citizen G. J.
Fonken, Vice President for Academic Affairs and Research, 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 uses Special Nuclear Materials to supplement the training and instruction programs in the field of nuclear engineering.
The items described in this application are used for Junior, Senior and Graduate level laboratory courses in the Nuclear Engineering Program of the Mechanical Engi-neering Department.
The licensed materials are to be used in experiments in the Nuclear Engineering Laboratory facilities located in Taylor Hall of the University's Main Campus or Building 10 of the University's Balcones Research Center.
Laboratory facilities associated with the Nuclear Engineering Program include a research reactor and charged particle accelerator with appropriate Nuclear Regulatory Commission license, NRC R-92, and Texas Health Department Radioactive Materials License Authorization TDH 6-485 No. 48.
A diagram of facility location and floor plan is included in Appendix A-1,3. Primary location for storage and operation cf the assembly will be Taylor Hall room 131A.
2 70.22(a) (3)
Requested duration of license is for 5 years.
70.22(a) (4)
Description of Special Nuclear Material:
The Special Nuclesr Material to be covered by this license is basically an extension of the previously granted license, SNM-180, dated February 27, 1958, and later amendments.
I.
U-2 35 Subcritical Reactor Assembly A.
Description 1.
A homogeneous system is assembled of 2695.52 grams of UO impregnated in high density 3
polyethylen4 with a total weight of 18,788.1 grams.
The UO2 is enriched to 19.776% 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 assembled from 8 fuel disks into one unit.
Axial and radial holes in the assembly may be filled with 36 smaller fuel disks of ebout 1" diameter.
The cylindrical core unit contains 465.03 grams of U-235 with the fuel plugs totaling 4.71 grams of U-135.
(One fuel plug is unaccounted for.)
3.
The fuel assembly operation is supplemented by 3 reflector assemblies, 3" polyethylene, 6"
polyethylene, and 10" graphite.
An additional 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 demonstrate the concepts of subcritical multiplication, thermal diffusion, fermi age, flux measurement and other basic nuclear engineering principles.
Both neutron detection systems and foil activation techniques are applied in various experiments to monitor neutron flux levels and flux shape.
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3 II.
Plutonium-Beryllium Neutron Sources A.
Description 1.
M-798 source contains 31.960 gms of Pu sealed in a tantalum and stainless steel capsule with dimensicns of 1.021" O.D. x 2.182" high.
The Pu is 93.02325% enriched in (Pu-239 + Pu-241) making a total of 29.730 gms of (Pu-239 +
Pu-241).
The source has a total strength of 6
3.83 x 10 neutrons /second (6-4-65).
2.
M-799 source contains 79.940 gms Pu sealed in a tantalum and stainless steel capsule with dimensions of 1.31" O.D. x 2.72" high.
The Pu is 93.02325% enriched in (Pu-239 + Pu-241) making a total of 74.363 gms (Pu-2 39 + Pu-241). 6 The source has a total strength of 8.82 X 10 neutrons /second (12-3-61).
3.
M-797 source contains 15.970 gms Pu sealed in a tantalum and stainless steel capsule with dimen-sions of 1.02" O.D. x 1.46" high.
The Pu is 93.02325% enriched in (Pu-2 39 + Pu-241) making a total of '.4.8560 gms (Pu-239 + Pu-241)6 The source has a total strength of 1.81 x 10 neu-trons/second (12-3-61).
B.
Usage The plutonium-beryllium neutron sources are used for neutron detector calibration, subcritical reactor multiplication sources, and neutron dose measurement experiments.
Operation of the sub-critical reactor assembly is accomplished by inser-tion 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 Applicant:
I.
Administrative structure.
Staff qualifications for responsible utilization of licensed special nuclear materials in the Nuclear Engineering Teaching Laboratory include the admin 13-tration of the special nuclear material license, a nuclear reactor operating license and a state radio ~
i active materials license.
The administrative struc-ture consists of a Radiation Safety Committee, Radia-j tion Safety Officer, Reactor Committee, Laboratory Director and Laboratory Supervisor.
Laboratory staff t
l
4 includes the Supervisor, reactor operator, radiochemist, technician, 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 the Science or Engineering Departments.
A.
Duties of the Radiation Safety Officer A Radiation Safety Officer acts as the delegate authority of the Radiation Safety Committee with responsibility to the University Safety Engineer.
Policies and practices set forth by the Radiation Safety Committee regarding the safe use of radio-isotopes 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 establishing, monitoring, and curtailing programs for the safe use of radio-active materials and radiation sourcec with respect to state or federal license requirements.
Some specific duties include periodic surveys and inspec-tions, maintenance of radioisotooe records and personnel exposures, disposal of radioactive wastes, periodic leak tests of sealed radiation sources, calibration of radiation detection instruments, help in the training of staff, aide in preparation of procedures, define proper radioactive material handling methods, and act as liaison for state and federal license responsibilities.
B.
Qualifications of Radiation Safety Officer Qualifications of the Radiation Safety Officer require a Bachelor's degree in engineering, 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 l
work in radiation safety and/or radiological health plus a thorough working knowledge of Texas Regula-tions for Control of Radiation and supporting regula-tions issued by the United States Nuclear Regulatory Commission.
Preferred experience includes knowledge l
of particle accelerators and nuclear reactors.
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5 III.
Reactor Committee A reactor committee responsible to the Dean of the College of Engineering with at least three members knowledgeable in the fields of nuclear safety shall review, evaluate, and approve standards associated with the operation of the laboratory facility.
Juris-diction 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 designated by the Laboratory Director.
A.
Duties of the Laboratory Supervisor Daily activities of the laboratory are directed by an NRC licensed senior operator whose responsibility is to direct the operation of the nuclear reactor and other laboratory activities.
The Senior Operator schedules and coordinates activities, assures the maintenance of appropriate license records and equip-ment calibrations, reviews experiments and procedures, supervises the use of radioactive materials and sources, supervises the activities of other laboratory personnel and supports teaching and research functions of the laboratory.
B.
Qualifications of the Laboratory Supervisor Qualifications of the Reactor Supervisor require a Bachelor's degree in engineering or science with three years experience in a releated filed.
Quali-fications for a USNRC Senior Operator license is required.
Preferred qualification is a Master's or Ph.D. degree in a field of nuclear engineering or science with appropriate experience.
Experience preferred is five years including two in a supervisor position.
Knowledge of n clear facility operation, radiation detection system.7 data acquisition and analysis systems, electronic and mechanical measuring i
I equipment and utilization of computer equipment are required skills.
IV.
Laboratory Staff A.
Nuclear Technical Specialist (one or more positions)
Duties of a nuclear technical specialist include operation and maintenance of equipment, review of procedures and regulations, instruction and assistance I
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6 of students or researchists, and assist in record maintenance and report preparations.
Qualifications require engineering or science degree or appropriate laboratory experience with radioactive materials and radiation detectors.
Pursuit of an NRC operator or senior reactor operator license is required.
Pre-ferred experience includes advance knowledge of electronics, computer programming or other valuable laboratory discipline.
B.
Radiochemist (half time to full time)
Duties of the radiochemist consi~sts of planning and supervising the utilization of the nuclear reactor and other radiation sources for neutron activation analysis, production of radioisotopes, and irradiation of materials.
The radiochemist instructs experimenters in radiochemical procedures, use of radiochemical equip-ment and facilities and, conducts research projects.
Qualifications require a Ph.D. degree or equivalent experience in fields of nuclear chemisty, with experi'-
ence in various analysis techniques that utili=e radiation sources and radioactive materials.
J C.
Other Staff A secretary aides in the preparation of reports and documents.
Other staff, students or researchists, are employed as projects warrant.
The minimum staff is considered to consist of a laboratory supervisor, nuclear technical specialist (technician) and half time radiochemist.
Additional technical support also is available from faculty members of the Mechanical Engineering Department employed to teach courses in the Nuclear Engineering Program.
D.
Appendix A-5 contains a block diagram of the 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.
Areas of storage and use:
A.
All the special nuclear materials described in this license are stored in Taylor Hall room 131A, which contains a TRIGA nuclear reactor.
Construction of the room consists of fireproof exterior walls, pro-visions for continuous radiation monitoring, and contro11ed' access monitoring.
7 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 protected from exposure to combustible materials.
2.
The fuel pellets are assembled in the reactor laboratory or in adjacent controlled laboratory areas.
Storage of the pellets is in a floor safe located in the reactor laboratory.
3.
The plutonium-beryllium neutron sources are stored in a 10 foot deep storage well located in the reactor laboratory.
Because of the value of the plutonium-beryllium neutron sources as calibration standards the sources are occasionally transported to Building 10 at the Balcones Research Center in an appropriate shipping container.
B.
All materials are stored such that radiation levels at the container surfaces are less than 2 mr/hr.
C.
Appendix A-9 contains a diagram of the plutonium-beryllium neutron source shipping container.
II.
Shields, equipment, and handling devices.
A.
The low specific activity of the non-operating suberitical core material allows for direct handling of materials.
A polyethylene jacket protects the core assembly disk units against transfer of radio-active materials from the disks.
Gloves are used to protect against the small risk of radio-active contamination from the fuel pellet disks.
Tweezers and small lead shields or other shield material are available to handle radioactive fails generated by neutron exposure in the suberitical assembly.
Signs and rope are available to define radiation areas during assembly operation.
~
B.
Routine handling of the plutonium-beryllium sources is accomplished with long handle tongs and long l
threaded rods.
Shielding material such as paraffin, l
borated polyethylene, lead, concrete block and shield casks are available to provide improved radiation
. safety in various neutron source applications.
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8 III.
Measuring and monitoring devices A.
Personnel monitoring devices are required of all persons working in the laboratory with radiation sources.
Film badges for laboratory personnel (that are sensitive to gamma radiation (10 mrem),
energetic beta (40 mrem)), fast neutron (20 mrem),
thermal neutron (10 mrem), are provided by Landauer.
Pocket dosimeters (ionization chambers) are available for dose measurements of gamma (0--200 mrem) or thermal neutron (0-120 mrem).
B.
Portable radiation detectors include a Victoreen Thyac III model 490 with thin window GM probe (1.4 mg/cm2) and Nuclear Chicago model 2671 with shielded BF3 probe.
The respective full scale ranges for gamma detection are 2, 2, 20, and 200 mr/hr and for neutron detection are 25, 250, 2.5%, and 25k n/cm2/sec.
The respective sensitivi-ties are 800 counts / min per 2mR/hr (radium source) and 1 cps (shielded probe) per 10 n/cm2/sec (radium beryllium neutron source), or 3 cps (unshielded probe) 2 per 10 n/cm /sec (thermal neutron source).
Other detectors available include Technical Associates model PUG-LAB with both e-S-y GM probe and shielded neutron scintillation probe, Tnd a Victoreen model No. lA ionization chamber with ranges up to 500 r/hr.
C.
Specialized detection systems are available for analytical radiation measurements that are routinely required in a neutron activation analysis laboratory.
The reactor room is continuously monitored by area radiation monitors with preset alarms (5 mr/hr) and a continuous dir monitor with filter for particulate monitoring that also provides audible alarm indication.
A gamma spectroscopy system (Ge (Li) ) and a-S windowless proportional counter plus other miscellaneous detectors and equipment represent substantial capability to analyze radioactive materials.
Both BF3 proportional counters and U-235 fission counters with associated electronics are available to monitor and demonstrate operation of the suberitical assembly.
Other detection systems allow students to count neutron activated foils.
IV.
Radioactive Waste Disposal A.
Sources of radioactive waste material from the operation of the suberitical assembly are slightly contamination from the polyethylene impregnated fuel pellets, activa-tion products exposed in the assembly and fission pro-ducts generated by cperation.
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9 B.
Provisions exist through the Radiation Safety Office for the collection and disposal of low level radio-active waste materials such as gloves, rags, and paper created by routing handling, and maintenance of the assembly.
Disposal of materials to the sanitary sewer system are also monitored by the Radiation Safety Officer as allowed by state licenseg.
Sub-critical irradiations are at fluxes of -10 n/cm2/sec for a few minutes to hours.
In 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.
C.
Calculations indicate that the total fission product-inventory of the assembly should not normally exceed several microcuries of fission product activity.
Contained as an integral part of the assembly the activi'y is primarily a potential hazard to handling c
of the assembly and not considered to be waste until the assembly is decomissioned. (calculations in Appendix A-10) 70.22 (a) (8)
Safety Procedures to protect health and minimize danger to life or property.
I.
Procedures are applied to establish safe conduct of activities with radioactive materials and radiation sources.
The procedures in eff ct are to satisfy various require-ments of federal USNRC licenses for special nuclear materials and state TDH licenses for radioactive materials.
Procedures are reviewed by staff, researchists and students.
The reactor supervisor drafts procedures and approves changes.
Substantive changes to procedures are reviewed by the Reactor Committee.
The procedures are categorized into four basic functional groups; monitoring, calibration, operation, and emergency.
A.
Monitoring Procedures 1.
Access to laboratory areas is controlled by staff personnel.
2.
Film badges are required in the laboratory for staff when radiation sources are in use.
3.
Dosimeters are required for occasional visitors and unusual source handling conditions.
4.
Status of special nuclear material is verified by periodic inventory (6 mo. cycle).
5.
Status of plutonium-beryllium is monitored by leak tests of source (6 mo. cycle).
10 C.
Operating Procedures 1.
Routine operation of the subcritical assembly shall consist of insertion of one of the plutonium-beryllium sources (including fuel pellets and non-fissile foils) into the sub-critical core assembly with any of the designed conditions for reflector or moderator components.
2.
Routine operation of the subcritical assembly will be authorized by the reactor supervisor.
3.
A survey of gamma and neutron radiation levels during operation will be cade and an area radiation monitor with alarm will be contin-uously active or a monitor available at all times during operation.
D.
Emergency Procedures 1.
Basic emergency procedures in effect for radio-logical emergencies in the Nuclear Engineering Teaching Laboratory are contained in Appendix A-12,16.
2.
Special precautions for material storage are required to minimize the potential for airborne radioactivity from exposure to fire hazards.
Storage when not in use will be in a tightly closed 55 gallon barrel.
The barrel is stored away from flammable materials.
The laboratory is constructed of firewall construction.
Leakage to the environment during normal operation is controlled by weatherstripping entrances and filtered exhausts.
II.
Training Program The primary use of radiation sources and the suberitical assembly in the Nuclear Engineering Teaching Laboratory is to support and extend the education of undergraduate l
and graduate students in basic concepts of nuclear engi-neering.
A portion of each student's education before l
performing experiments with radioactive materials will consist of material on radiation interactions, radiation hazards, dose measurements, and laboratory procedures.
l Experiments are performed with the supervision of labora-tory staff.
Staff personnel are trained to handle materials by a combination of formal classroom education and laboratory training by other qualified staff depending
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on the nature of responsibility required.
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11 III.
As Low as Reasonably Achievable The "as low as reasonably achievable" goal of a-radiation safety program is supported by the procedures of the Radiation Safety Committee, huactor Committee and Nuclear Engineering Teaching Laboratory.
Many of the type of experiments performed on a routine basis do not represent significant radiation doses.
Less routine experiments may be required on occasion that represent more significant doses.
Both occasional and periodic review of radiation doses of staff, students, and visitors is carried out by Laboratory Staff and the Radiation Safety Office.
In general radiation doses are in the minimal or near minimal category for many routine experiments.
A review of signi-ficant deviations from expected values will be reviewed by the appropriate committee.
Typical values are presented in Appendix A-17.
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iO" I it i iIii il SCALE Basic Configuration of Subcritical Assembly, Reflectors and Source A-4 l
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Office, President
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Radiation Chairman Safety Department of Comittee Mechanical Engineering l
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Director Nuclear Engineering k---
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l The safety of operation of the Nuclear Engineering Teaching l
Laboratory shall be related to the University Administration as shown in the following chart.
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PERSONNEL QUALIFICATIONS I.
H. W. Bryant, Radiation Safety Officer A.
Experience U.S. Air Force, 1950-54 One year electronics and radar school; Three years radar technician General Dynamics, Fort Worth, Health Pitysics Group, 1954-1973 Aircraft decontamination programs; Instrumentation'(maintenance, calibration, procure-ment) ;
Area Monitoring (3 reactors, neutron generators, x-ray equipment; muluicurie 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 A-6
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Summer Engineering Practice School, Argonne National Laboratory, 197 3 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 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; l
Research Scientist / Nuclear Engineering Teaching Laboratory Supervisor, 1980-present USNRC operator license, UT TRIGA, 1979-1981 USNRC senior 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.
Crganizations American Nuclear Society A-7
i IV.
Nicholas Povio, Nuclear Technical Specialist A.
Experience U.S. Navy Basic Electricity and Electronics School - 1971 Electronics Technician "A" School - 1972 Nuclear Power School / Training Unit - 1973 Naval Diver Training - 1975 Personnel Counselling School - 1975 USS Theodore Roosevelt SSBN600 - 1973 - 1977 Watchstanding Instructor / Maintenance Technician /
Classroom Instructor, Naval Nuclear Power Training Unit, 1977-present B.
Education New York State University, 59 semester hours A-8
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SIZE GAMMA 15 G A L.
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mr/hr e
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STANDARD NEUTRON O.9 MREM /
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SOURCE SHIPPING z
CONTAINER.- FROM DWG. 3 - 174 6 7-5-57 v
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Plutonium Beryllium and Shipping Container A-9 l
i O
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 dr where V is the thermal neutron velocity 5
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 watts /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-see of power / year of continuous operation.
A more realistic estimate is 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> / 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 7
4 (3.15 x 10 sec/yr) x (1.15 x 10-5) 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 12 at a rate of 10-decays per fission then (4.8 x 10 fissions) 4 x (10' decays / fission) x (3.7 x 10 decays /u curie) is less than 1.5 u curies of activity.
A-10
LICENSE CONDITION FOR LEAK TESTING SEALED PLUTONIUM SOURCES A.
Each plL onium 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 scaled 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-11 i
l l
L
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-fled 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.
l le Radiological Hazard.
There shall be three grades (or classifications) of emergency situations ranging from the most minor to the masimum
- credible, Tha required action in each grade shall include all i
pertinent provisions of all lower grades.
A-12
~
a.
Grade A:
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 ope ator 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 A-13
~
survey equipment and closing the doors on their way out.
If there
.s 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 l
equipment, in the driveway south of the Laboratory.
If radiation 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 ha=ards not directly associated with radiation, the general procedure will be to scram the a
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 $
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
At least two carbon dioxide fire extinguishers shall be maintained in readiness in the Laboratory area.
In the event of fire all ventilation erguipment will be shut down.
3.
The folicwing persons shall be :aotified:
(1)
Laboratory Supervisor:
Thomas L.
Bauer CTX 5136 (345-5044)
(2)
Laboratory Director Dale E.
Klein CTX 5136 (459-0075)
(3)
Radiation Safety Office:::
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:
Nicholas A. Poirio CTX 5136 (445-0324)
If necessary, the Chief Traffic and Security Officer may request assistance fron the City of Austin Police 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
.I I
I POSITION RADIATION SOURCE I
2 3
4 METER TYPE l
BARE 3 " POLY 6" POLY GRAPHITE M-797 0
0 0
0 S U-14 TW
\\
v l
S+y limr/ hr 6 mr/ hr 3 m r/hr limr/ h r S U-14 T W l
2 2
2 n(Thermal) 220/cm sec UNDET.
120/cm sec 45/cm sec FOILS NONE 0
0 0
0 SU -14 TW S+y 1.2 m r / h r O
O O
S U-14TW l
1 i
)d ba U
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