ML20245G119

Application for Renewal of License SNM-256

ML20245G119
Person / Time
Site:	07000277
Issue date:	09/20/1977
From:	Koepel E MICHIGAN TECHNOLOGICAL UNIV., HOUGHTON, MI
To:	NRC
Shared Package
ML20245G050	List: ML20245G047 ML20245G060 ML20245G063 ML20245G073 ML20245G083 ML20245G089 ML20245G100 ML20245G106 ML20245G119
References
NUDOCS 8902140308
Download: ML20245G119 (11)

Text

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.- ~ 2. michigan t:chn: logical niversity:

houghton, michigan 49931 ES office of the vice-president of operations and finance 906/487-2642 September 20, 1977 Radioisotopes Licensing Branch Division of Fuel Cycle and Material Safety.

United State Nuclear Regulatory Commission Washington,: D.C.

20555 1

Gentlemen:

Attached is our application for renewal of our special nuclear material license number SNM-256.

Sincerely, F//

E. J. Koepel Vice President of Operations & Finance EJK/rw i

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8902140308 880210 REG 3 LIC70 SNM-0256 PNU i

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'A plica' tion for: Renewal of. Special Nuclear Materidi Li ense Number SNM-256; c'

'4.1h Specification of' Applicant 1 o

. Michigan Technological University lHoughtoni Michigan!. 49931 Incorporated in the' State.of Michigan.

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' Principal' Officials:(all USA citizens)

.Dr.;Raymond'L. Smith, President'-

1400 College Avenue I

Houghton, Michigan

,49931 y

Mr. Edward J.-Koepel, Vice President - Operations Finance

' Box 288 M-26

{,

'H6bbell, Michigan.

49934 h'

Dr. Dale. F. - Stein, Vice President - Academic. Affairs -

Rural Route 1, Box 140A Chasse11, Michigan; '49916 4.2. Specifications'of Activities to be Performed The f'ive neutron so'urces are usedlin the following ways:

One source:is. located.in wax within a cubical shaped wood. box 45 centi--

meters on a' side. A beam port approaches to within one centimeter of the ' source.

From'the beam port neutrons emerge and.they are used for demonstrations of neutron cross section measurements.

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. Another use of this source arrangement is. in conjunction with ten Argo-naut enriched uranium fuel plates. When the fuel plates are placed in-lL a-small 20x50x30 (centimeter) water tank, the neutron' source box is used l

' to; supply neutrons for neutron multiplication demonstrations. -

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The other four neutron sources are in a neutron howitzer (Nuclear Chicago model NH3) and used for foil activations and also for cross section mea-

.surements.

The enriched uranium fuel plates are used in the suberitical neutron

. multiplication demonstration.

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4.3. Specification of Special Nuclear Material

- Five Sources by Monsanto Research Corporation Mound Laboratory, Miamisburg, Ohio..Each source is a nominal 1 curie in a tantalun and stainless steel

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container of nomial outer dimensions 1 inch diameter and 1.6 inches in 6

p length. Neutron yield of each is a nominal 1.8 x 10 neutrons per second.

Composition details follow:

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Source'M401 7.86 Be, 16.00 gm Pu.-

Source'M400 7.86 grams Be, 15.99 gm Pu.

L Source M399 7.86 gm Be, 15.99 gm Pu.

Source M398 7.86 gm Be, 15.98 gm Pu.

Source M397

~7.86 gm Be, 15.99 gm Pu.

i Ten Argonaut fuel plates, U 0 in Aluminum dispersion,1 clad in aluminum, i

3s 33 w% U 0 ' 84.4 %U in U 0, 20% enriched. Table weights in graoiunito.

-l 38-38 PLATE BATCH GROSS NET SS U-235 13-6 20-2-1065 374.36 132.46 112.33 21.56 13-7 20-2-1066 373.03 130.38 110.56' 21.22 13-8 20-2-1067 371.42 129.09 109.47 21.01 14-2 20-2-1069 373.15 130.13 110.35 21.18 14-3 20-2-1070-374.26 132.35 112.23 21.54 14-4 20-2-1071 373.87 132.96 112.75 21.64 14-5.

20-2-1072 372.94 131.91 111.86 21.47 14-6 20-2-1073 372.56 131.73 111.71 21.44 14-8

'20-2-1074 370.33 129.09 109.47 21.01 15-3 20-2-1078 375.21 133.38 113.11 21.71 il Total 3731.13 1313.48 1113.84 2131.78 4.4 Technical Qualifications of Personnel The primary use of the special nuclear materials is in support of the nuclear power and nuclear radiation measurement courses under the direction of D.A. Daavettila.

Dr. Bertwell K. Whitten (Chairman, Radiation Safety Committee)

WHERE DURATION OF ON THE JOB FORMAL COURSE j

TYPE OF TRAINING TRAINED TRAINING (circle answer)

(circ'e answer) 1

a. Principles and See Below practices of radi-ation protection 1952 Yes No Yes No

b. Radioactivity measurement stan-dardization and monitoring tech-niques and instruments Yes No Yes No

c. Mathematics and calculations basic to the use and measurement or radioactivity Yes No Yes No i

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. 4i4 ' Technical Qualifications of Personnel (Continued)'

d.--Biological'

'See.Below

'Present Yes No Yes

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radiation 1.'

B.K. Whitten, Prof. of Physiology, Deptof ' Biological Sciences...

~2.. Formal training,in Bionucleonics via: course work at.Purdue University.

Coverage included 8a', b, c','and-d.

Four' courses 1962-1966.

3.

Extensive research experience over. twelve years at Purdue University, Lafayette,7IN; Fitzsimmons General Hospital, Denver, C0; Natick Army.

' Laboratories, Natick, MA; and Michigan Technological University,.

IHoughton, MI.

MAX.-AMT.

WHERE EXPERIENCE DURATION OF-L

-(atfany one time)

WAS' GAINED EXPERIENCE-TYPE OF USE ISOTOPE ~

CD 2' mc FGH; NL;~MTU 9 years.

Animal & human

.metabol' studies,.

in vivo and i' vitro-H3.

2 me FGH; MTU

'7. years Animal ~& human

.'metabol studies, in vivo'and i vitro

'I125 5 me MTU 5 years m'etabolic' studies 4

& RIA. procedures.

I131 5 me MTU.

5 years 32l 5 mc PGH; NL;'MTU; 12 years animal studies in P

PU

. vivo & _i_n, vitro n

Ca + 5 2 me PU 4 years aquatic ecological' t

uptake studies Z 65 1 mc PU n

Co60

.'.1 m'c PU Sr89-500 uc PU

-Sr90-500 tic

'PU Ss137-500 uc PU g

FGH - Fitzsimmons Gen.-Hospital, Denver, C0 f.'

PU - Purdue University, Lafayette, IN NL - Natick Army Laboratories, Natick, MA MTU Michigan Technological University, Houghton, MI

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Dr. Bertwell K. Whitten (Continued) l Chairman of Radiation Safety Committee - A technical radiation safety committee has been established by the University Safety Council. This committee in conjunction with the radiation safety officer oversees the use of byproduct material by all university personnel.

Donald A. Danvettila (Radiation Safety Officer)

WHERE DURATION OF ON THE JOB FORMAL COURSE TYPE OF TRAINING TRAINED TRAINING (circle answer)

(circle answer)

a. Principles and Argonne Nat'l 1 yr.

Yes No Yes No practices of radi-Lab. (ANL) ation protection Argonne, IL

b. Radioactivity ANL 6 yrs.

Yes No Yes No measurement stan-dardization and monitoring tech-niques and instruments

c. Mathematics Michigan 6 yrs.

Yes No Yes No and calculations Technological basic to the use University and measurement.

of radioactivity.

d. Biological ANL and MTU 6 yrs.

Yes No Yes No effects of radiation MAX. AMT.

WHERE EXPERIENCE DURATION OF ISOTOPE (at any one. time)

WAS GAINED EXPERIENCE TYPE OF USE Neutron sources Reactors and 1 Argonne Nat'l 19 yrs.

Reactor curie sources Lab. & MIU operations,

& cross section meas.

Fiss Products 0.1 me at one Argonne Nat'l 6 yrs.

Reactor time Lab Atomic Power Parameter Dev. As.

Measurements.

Cs137 1 curie MTU 19 yrs.

Beam - Source Co-60 me & also with 19 yrs.

Radiation a 970 curie Cobalt l

Processing Irradiator Many small training experiment sources for counting studies with various detectors.

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' Additional' retail'.on the Nuclear. Radiation Related Training of Donald A.~Daavettila 1

1957

.One course,in Nuclear Chemistry at. Michigan Technological University in addition to a number of Physics courses that touches this area.

1957-1964 With the exception of one 9 month period absent for high school teaching the work was continuously with and around nuclear reactors and nuclear radiation at the Argonne National Laboratory.

Included is one academic year of formal course work in the Argonne International School taking courses in radiation safety and closely related subjects. Handled fuel elements (low power reactor),

many irradiated foils, worked with radiation detection instruments as a matter of daily routine.

1964 One nine month period at the Enrico Fermi reactor for

-Atomic Power Development Associates, working with and around nuclear radiation as part of the Nuclear Test Group.

1964 to present at Michigan Technological University teaching courses in Nuclear Power and Nuclear Radiation in addition to I-general physics and chemistry courses.

Serve as radiation safety officer.

' 4.5 Description of Equipment, Facilities, and Instrumentation 4.5.1 Remote handling devices are not needed for handling the fuel plates and none are used. The single neutron source is not l

handled except as part of the entire' wood containing box.

The four neutron sources are in a metal containing tube of

- 1 inch ID and 10 inches long to which a twelve inch plastic handle is attached.

4.5.2 The storage container for the fuel plates is a locked safe.

The single neutron source is in the heavy wood box, and the j

four neutron sources are in the Nuclear Chicago Howitzer Model NH that has a locked cover. All special nuclear material is 3

used and kept in a locked room. Access is limited by key.

4.5.3 The fuel plates are each contained in clear plastic covers.

One does not touch the actual plate surface by hand.

j The neutron sources are used in the same form as they are stored, that is, in the wood box and neutron howitzer. No additional shielding is needed or used.

4.5.4 The physical plant is in room 031 of_ Fisher Hall in a normally locked limited access room. No chemical or Wiy31 cal tampering j

with the special nuclear material primary containers is ever I

done. No waste is created.

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i TYPE OF INSTRUMENTS NO.

RADIATION:

SENSITIVITY USE (Include make &

AVAIL.

DETECTED RANGE (mr/hr)

(Monitor.,

model #)

Sury.,

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A.

Victoreen 440 1

x-Ray,y 3

Monitoring

& Surveying:

B.

Nucleus S-101 1

a,8,y.

500 cpm Monitoring 0.5 mrem /hr

& Surveying i

l C..,AnS alpha scintil-1 a

N/A

' Measuring lation probe,.BF3 j

detector, various

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. tubes, NE404 plas-

.i tic' phosphor for fast neutron count-ing.

D.

GM detectors (1.4 5

S,y N/A Measuring mg/cm2 windows _to 2

3.4 mg/cm ) for use with four scalers by The Nucleus, model 500 and one-l model K2.

E.

3 X 3 NaI scintil '

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~ y, N/A Measuring lation crystal for use with a TMC model 401C multichannel pulse height analyzer F.

Gas flow' counter made 2

a,8 N/A Measuring up of a NMC proportional counter converter unit model PCC12A and a scaler and HV unit model DSIA.

G.

Two precision Ge(Li) 2 y

N/A Measuring detectors with a complete Nuclear Data 4096 channel Analyzer system H.

Picker Gas Flow Counter 1 soft B N/A Cl4. Measure-model 641260, 644010 ment 3

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Packard TriCarb Liquid 1

gamma N/A primarily H scintillation spectro-

&Cl4 measure-meter model 3310 ment also P32

&1125

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- 4.5.5-; Radiation Detection Instruments (Continued)-

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Tracerlab ED-10 NaI 1

gamma N/A-I131 measure-crystal and' scaler ment.

'K'. ' Nuclear Assoc. model 1

Hard Beta N/A P32~ measure-GM' tube and Nuclear gamma ment Chicago model 8775 scaler METHOD,. FREQUENCY, AND STANDARDS USED IN CALIBRATING INSTRUMENTS LISTED ABOVE. The two monitoring (see A, B' Section 10) instru-ments are calibrated by small check sources daily when in use by the RSO.

Complete calibration and servicing by the manufacturer-is done each year for the primary survey instrument. VICTOREEN

1. 440 (VICT0REEN, 5806 Hough Avenue, Cleveland, OH). This service -

includes accurate calibration with several radiation sources and certification of calibration on return. 'All other instruments are check tested and calibrated by the user, using small appro-priate calibration sources. Neutron detection --BF -- is'cali-3 brated by showing that neutrons are being detected and the results in agreement with prior checks. Counts are taken with and with-out'the. neutron source being present. Primary neutron dose cali-bration is through use of film badges read by Searle Services.

4.6 Proposed Procedures to Protect Health and Minimize Danger 4.6.l' Specification of Radiation Safety Responsibilities and Duties.

In order-to establish and maintain standards'for the utilization of sources of ionizing radiation on the campus of Michigan Tech-

- nological University, a Radiatica Safety Committee has been established by the MTU safety Council. The Committee is respon-

.sible for tha radiation safety of all machine sources, and the safe procurement, use and disposal of radioisotopes both licensed and unlicensed.

The MTU Safety Council has appointed a Radiation Safety Officer (RS0) who is a member of and works closely with this committee and is directly responsible for administering the University standards with regard to the use of radiation and radiation-producing devices.

The Committee and the RSO oversee the use of radiation and radioisotopes by all University per-sonnel who wish to use hyproduct material for teaching and research.

Byproduct material. The ratiation safety officer is responsible for determining competence and evaluating training of users, overseeing procurement, use, routine maintenance and waste dis-posal. He reports to the General Manager of University Operations.

4.6.2 Film badge changed monthly and processed by Searle Analytic Inc.

of Des Plains, IL.

Some dosimeters available for demonstration.

Bio-Assay Service, if needed, by Radiation Management Corp. of Philadelphia, PA.

Use of Badges. It is the responsibility of each project leader or major professor in charge of investigations which involve the use of isotopes or of other radiation sources to submit the names of all individuals involved in these investi-gations to the radiation safety officer (RS0).

It is the res-possibility of the persons in charge of projects involving

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4.6 Proposed Procedures to Protect Health;and Minimize Danger (Continued) i radiation to see that each of.the individuals working'on~the project has and uses a film badge as; provided by the RSO. The Safety, Committee upon the recommendation of the RSO, may order a medical examination at any time it is deemed necessary. In

. addition the radiation: safe *.y officer has the authority to shut down any project:where film badges should be used but are either-not being used or are being used improperly.. Film badge reports will be issued through the RSO to the individuals responsible g

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for the project.

Bio-Assay. The need for and order of bio-assays will be deter-mined by'the Radiation Safety Committee'or the RS0' depending on the time, circumstances end the availability of the individuals.

Ordinarily the decision for bio-assay would be made at a regular meeting of the committee when they consider the requested project and notice to the individual concerned would be via the radiation safety officer. We do not anticipate'at this time a'need for bio-assays.

4.6.3 Radiation Survey Program. The present storage and use configu-rations of both the fuel and neutron sources have been shown by film badge measurements to be safe--near zero doses for practical times. -Four day--24 hour continuous exposures are less'than 30 mrem total-(.3 mrem /hr) gamma and zero fast neutron for the multiplication study geometry. Contact surface of the howitzer does rate is less than 3 mrem per hour neturon and gamma.. No experiment r c uires such close contact, hence, all experiments have much less exposure than this. Occasional checks continue.

4.6.4 Waste Disposal. No waste is generate /.

1 4.'6. 5 Record Management. Records are maintained by the Radiation Safety Officer (RS0) herein described.

Records are kept of surveys, inventories, personnel exposure, and receipt and disposal of materiale. Personnel exposure records are simply the Searle film badge reports. All other records are hand

l written or typed reports kept in appropriate labeled notebooks.

4.6.6 Material Control Provisions. It is not planned that any special i

nuclear material shipments will be received. The general uni-versity policy follows.

Transfers of radioactive material shall not be made from one user to another at Michigan Technological University except through the RSO who will accept such material from one user, check it and reassign it to the new user.

All incoming packages of radioisotopes will be inspected at the central receiving building for leakage, contamination, or damage as soon as possible by Dr. Whitten or Prof. Daavettila. The radiation level.will ce monitored by either of the two instru-ments mentioned in-this application and marked. No packages will be opened there. A damaged package would be sealed in plastic and placed into radioactive waste storage. Packages are trans-port ed from central receiving to biology or physics by either Whi ten or Daavettila.- Upon receipt at the appropriate depar t

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'the,pa'ckage would bc taken to the nuclear detection ~ laboratory and opened using plastic gloves and t'o'ngs by Daavettila or Whitten..The received' source would then be checked for leak-age by. wipe testing. In any case'the primary container (one

. hich isotope 1s received-in) wouldLbe placed in secondary con-w tainer or ' plastic whether or not -surf ace contamination was detected.

4 The secondary container is then labeled and placed into a locked, safe under the control of Daavettila and/or Whitten and cannot be removed without their permission.

4.6.7 Sealed Source Leak-Testing Provisions.

LICENSE CONDITION FOR LEAK' TESTING

. SEALED PLUTONIUM SOURCES A.

Each plutonium source shall be tested'for leakage at intervals not to exceed six (6) months. In the absence of a certificate i

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.

4 B.

The test shall be capable of detecting the presence of 0.005 microcurie of alpha contamination on the test sample. The test sample shall be taken from the source or from appropriate access-ible surfaces of the device in which the cealed source is per-manently 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 contamination, the lincensee 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 accordance with the Commission regulations. Within five (5) days after determining that any source has leaked, the licensee shall file a report with the Materials Branch, Directorate of Licensing, Nuclear Regulatory Commission, Washington, D.C.

20545, describing the source, the test results, the extent of contamination, the apparent or suspected cause of source failure, and the corrective action i

taken. A copy of the report shall be sent to the Director of the nearest NRC Regional Compliance Office listed in Appendix D of Title 10, Code of Federal Regulations, Part 20.

i D.

The periodic leak test required by this condition does not apply l

to sealed sources that are stored and not being used. The source 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.

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4.6.8. Emergency. and Decontamination Procedures EMERGENCY PROCEDURES FOR THE NUCLEAR COUNTING ~ LABORATORY.

In. case of fire in this room everyone should vacate the room, close the door, and call the campus security emergency number 123..

In' case of a radioactive' material spill take appropriate' local procedures;to avoid spreading the contamination, vacate the room, close and lock the' door.. post the No-entry' signs on both room access' doors. Then,;(1) call D.A. Daavettila at 487-2084 or 482-5787, (2) Dr. G.P. Agin at 487-2084 or 482-4105, or Campus security at 487-2216.

4.6.9 Procedures for Training Personnel.

Each person, whether staff or student,'who works with radioactive materials must have taken or be taking the equivalent of one of the three university radi-ation courses.

.Briefly they are PH417, Nuclear Radiations Measurements, which is primarily a laboratory course obtaining and. interpreting -

data from all the kinds of radiation instruments we have on campus.-LBL419, Radioisotope Techniques in Biological Sciences, which'is a course designed to enable the students to use the unique properties of radioactive tracers in studies of biology.

A necessary.part of each of these two courses is a thorough understanding of working with and around radioactive materials..

The third course-taught by Public Service is'mainly designed to give staff ~and students correct procedures with and around radio-activity., The course has 5 lectures and a tour with demonstra-tions.in the physics and biology nuclear laboratories. This seminar course is under the direction of Dr. Tom Ellis. The lectures are:

1.

Nuclear Radiation, its origin, nature, properties, and hazards.

2.

Nuclear Radiation, its interaction with material and shielding.

3.

Radiological health, radiation effects on living things, flux, dose.

4.

Radiation measurements and dosimetry techniques.

5.

Laboratory rules and Federal and State Regulations and the individual's rights.

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