ML20206H774

Application for Amend to License SNM-1562,authorizing Use of 500 Mci Cs-137 & 2.9 G Pu-238.Fee Paid

ML20206H774
Person / Time
Site:	07002008
Issue date:	07/23/1980
From:	Reynolds J RESERVE MINING CO.
To:	NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20206H245	List: ML20206H239 ML20206H722 ML20206H729 ML20206H763 ML20206H774
References
16913, NUDOCS 8811230321
Download: ML20206H774 (26)

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, ggj RESERVE MINING COM PANY p

g:J :13 QikU FR S ILVEIt B AY, M INNE SOTA 55614 July 23, 1980 4

3 Division of Fuel Cycle & Material Safety Office of Material Safety and Safeguards r

U. S. Nuclear Regulatory Conriss.is 7

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Washington D. C.

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Dear Sir,

g The enclosed information' Tidven weie5 - 2"NM'%_* to support ot/P request f'r the renewal of our existing Special Nuclear Materi'l License Number SNM-1562.

The special nuclear material source is a componer;t part of our.f.lyr neutron activation analysis systems.

Its function and cor iinment is described in the body of this renewal application.

We ha',

included a check for $113.00 for the Special Nuclear Materia'. License Renewal fee.

The Cet'n iJ7 source which is also a component part of the N0LA

'[ (Neutron On-line analyzer) systems is covered under our existing By-product Material License No. 22-13759-01.

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JUL231980 The five existing systems are lastalled at:

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d Reserve Mining Company Silver Bay, Minnesota Reserve Mining Ccmpany is a Minnesota Corporation with principal ".

offices located at Silver Bay, Minnesota.

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The principal officers are.

M. G. Woodle President M. R. Banovetz Executive Vice President R. A. Lee Vice President Finance p

Reserve is jointly owned by Republic Steel Corporation', Cleveland.o, Ohio, and Armco Steel Corporation, Middletown, 0 hic,.

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ihe person primarily responsible for control of material and records is Michael H. Holmquist, Safety inspector /Ra ' tioCProtectipn Of ficer or in Mr. Holmquist's absence, we would request that Kenneth J. Fisher, St.nior Research Engineer of our Research and Development Division be allowed to substitute.

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l Education, Training and Experience Michael H. Holmquist-Mr. Holmquist graduated from Southwest State University in Marshall, Minnesota with a 4-year B.A. degree in Biology and Chemistry.

Mr. Holmquist also completed a one-day Radiation Safety Training course conducted by Troxler Electronics at Reserve Mining Company on August 9, 1978.

Certificate of traininn is attached.

In addition, Mr. Holmquist has completed a Radiation Safety training course conducted by the Texas Nuclear Division of Ramsey Engineering Company in Austin, Texas. His record of performance, certification of l

training, and letter of certification are attached.

1 Mr. Holmquist has worked closely with Mr. Ken Fisher, our forner l

Radiation Safety Officer, on radiation safety matters at Reserve Mining Company, and has performed wipe tests on radiation sources many times l

during the past two years. Mr. P91mquist has been our Radiation Safety I

Officer since June of 1979.

The on-the-job training Mr. Holmquist received under the supervision of Mr. Fisher encompassed leak tests, record keeping, and safety meetings l-dealing with sealed sources.

Kenneth Fjsher-Mr. Fisher graduated from the University of Wisconsin with a B.S. degree l

in Physics. Major studies included two semesters of coursa work in atomic and nuclear physics.

In addition, Mr. Fisher completed a basic radiological health course conducted by the U.S. Department of Health, Education and Welfare at the University of Minnesota, Minneapolis, in July of 1970. Attached certificate.

Mr. Fisher also completed a 2-day Radiation Safety trainbg course con-ducted by Troxler ElectN>nics at Reserve Mining Company on September 12 and 13, 1977. Attached certificate.

Mr. Fisher held the position of Radiation Protection Officer for Reserve Mining Company at Silver Bay, Minr.esota from 1969 to June of 1979.

Mr. Fisher supervised the installation of and made periodic radia'. ion safety checks on the sealed sources used at Reserve Mining Company.

If any additional infonnation is needed, please do not hesitate to cor us.

Sincerely, RESERVE MINING COMPANY j

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/. A. Reynolds Ass't. Manager of Operations Silver Bay Division A

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Technical Data his systen is toed for elanental detenninations in iron ore and uns supplied to Reserve 111ning Cmpany by Texas Nuclear Corporation 9101 Highuny 183, Austin, Texas 78758. The systcm is shown on a drawing labeled "Schanatic Representation of IOLA I".

W e slurry is cycled continuously through the irradiate cell and the detector for analysis.

ne general layout of the NOLA Syston is shown on the drawing labeled "?OIA I Silica Analyzer", he analyzers are installed in 12' X 14' rocms which are used only to house the neutron activation analysis systen. his rom has solid floors and un11s and can easily be secured against unauthorized entry, here are no extrcmes of tanperature, humidity, etc. at the installation site.

De principal hazards of concern in this systen are:

a.

Exposure to radiation outside the shield under nonm1 operating conditions; b.

Failure of the source capsule inside the shield; c.

B:posure to radiation under cmergency conditions; d.

Disposal of the activated materials.

Density Channel The density channel is shown in the drawing titled "Nola I Density Gauge".

l Re 5176 source head acts as a ccmplete t.tvrage container for the 500 mci Cs-137 sealed uaurce, Texas Nuclear mdel 570-57157C, both prior and subse-quent to installation of the system. We radiation levels one foot frcm any accessible surface ar? less than 0.5 mR/hr.

In the event work must be done inside the detector box, the shutter will be closed and locked before such work begins. h is source will be leak tested at least once even thiee years, in accordance with Texas Nuclear procedure QT/1X (see >rpendix).

?b unst dispasal is involved.

If the use of the gauge is discontinued, the source will be returned to Texas Nuclear for disposal.

Silicon mannel i

Re construction of the shield is detailed on the drawing titled "Neutmn Source Shield" (see appendix) and scha mtically shown in the figure titled "Nola I Irradiator".

The source is th.eaded onto a stud at the bottcm of the inne.r cell, h e irradiate cell slips over the source and can be in-stalled and ramved without rroving or unshielding the source. h is con-struction is shown on the drawing labeled "Inner Source Shield Asscmbly" (see appendix).

We Plutoniun 23S-Bery111um neutmn source contains aoproximately 2.9 grams of Plutonium 238 as an oxide mixed with 15.2pams of Bery111un, he neutmn anission rate of the source is 1.1 x loo n/xec, and the source uns fabricated to the specifications shoun on the drawing labeled "PuSBe-Source Capsule" by 2nsanto Research Corporation, Dayton, Ohio.

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An cnclysis of prcssure build-up due to alpha particlo d3 cry of the contained Pu-238 was nade.

This analysis was based upon a maximum loading of 4.24 gra=s of Pu0, 80% c: iched in Pu-238 at an initial pressure of 2

one atmosphere.

It was assumed thag the :lelium obeyed the Ideal Gas Law and that a:51ent temperature was 70 C.

It was clso assumed that 30% of the internal volume was void due to the approximate 70% compaction of theoretical density that one gets af ter pressing the PuC ~

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In the activation analysis system one can estimate the useful life of the source to be 80 years, based on tne required sensirivity of the measure-ment.

This would mean a pressure builw up of approximatelv 400 psia.

One can calculate the bursting pressure of the inner capsule, ur.ing the tensile strength of 304 SS as 85,000 psi, to be greater than 6,400 psia.

Prototypes of thir capsule have been tested under American National Standards Institute procedures and classified E55535.

s Radiation exposure rates outside the neutron source shield are shown at typical survey points on the decwing labeled "Neutron Cource Shield".

The source itself is shielded as shown, with lead and water on cll sides except the top, which is covered by 33 inches of oil.

This filling insures access to install or remove the teflon irradiation cell without undue radiation cxposure (reference Cell Check and Removal Procedure).

The cever plate has a ecble and lock to insure that only authori:ed personnel have access to the cell.

As usual, the shield is mascive and the exposure rates are very low due mainly to the high sensitivity of the system detectors rather then personnel exposure consideration.

The son-sitivity of these detectors also provides an additional margin of safety, since they will inilcate a change in performance if some abnormality occurs.

Clearly, exposure to radiation outside the shield is minimal.

The large water shield also has a low water varning system consisting of a Cutler-Han=er Level Probe, located approxicately one-half inai below the tank top, and connected to a Cutler-Ha=mer standard duty f ail safe relay.

The alarm circuit will indicate when the water level is approxieutely one inch below the tank top.

At that time, one would not observe any appre-ciable increase in the dose rates as presented.

Lights on the control panel indicate the status of the water level.

A contact closure is also provided for remote alarms if desirable.

The water shield has a chemical additive to inhibit corrosion and organic growth identified as NALCO 39-L, and supplied by Nalco Che:ical Co:pany

• 5757 Bellaire Blvd.

Houston, Texas Water replenishment, if ever necessary, would be a manual operation as there is no provisions for automatic filling.

The physical location of the sample room, the building construction and general housekeeping conditions make it unlikely that conditions could exist which would endanger the shiciding properties of the primary container.

Although ue cannot envision the accident, if such occurred, we would attc=pt to evacuate personnel f rom the area cf the source, notify the Rediation Safety Officer and Texas Nuclear Hecith Physier, and avai t instructions and/or the arrival of trained personnel to evaluate the situ-ation.

However, the dose rates are not so high as to preclude maintenance

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.e on the ta!A. On] can estimate the unattenuated dose rato at a meter to be slightly nore than 100 mrcm/hr by using:

8 a,

neutron unission = 10 n/sec, b.

averagefirstcolligiondoseintissue=

4.0 x 10-9 rad /n/cm,

c.

mean quality factor = 8.5 for pus-Be neutrons, d.

adding the garmn contribution frcm both the 4.43 MeV capture in Hydrogen.

Additionally, note that the source is not unshielded if all the water is out of the tank, here is a 5-inch oil bath plus the irradiation cell and the 20 inch O.D. lead half-annulus to cor. sider.

In fact, except for near the floor level, and the tank end awny frcrn the large crystal detector, the total dosa rates would not exceed 15 mrun/hr at the nearest point of the shield tank with no water.

Failure of the source inside the shield is ramte at best. his type of capsule constmetion has been used for scrne time with few failures.

Also, a failure of the source would change the optimizc4 gctmetry and this would innediately affect the operation of the systen, h erefore, w propose to leak test this source using the pmcedor 3 entitled "Leak Test of Activation Analysis Sources", (see Appendix) at least once every six tronths under normal canditions, and at any other times the operational data lead t.s to suspect that sone source or cell abrrtmality has occurred.

In the event the leak test is p3sitive, m will dit:entinue use of the systan, secure the mcrn and annit further instructions frcm Texas Nuclear and the Reserve Mining &mpany Safety Officer. W believe that even a ruptured source could be safely contained for scrne time in the shield with little probability that contamination would be a hazard outside the container.

We following are additional itens that are an integral part of our program:

a.

Le systcms ar e ima11ed by trained personnel of Texas Nuc'. ear Corporation, b.

Personnel receive training in the operation and hazards of the activation analysis systan by Texas Nuclear personnel, c.

Radiation surveys are made at the tine of installation by Texas Nuclear and copies will be retained for inspection, d.

Personnel working amund the activation analysis systan udll not use personnel nnnitors.

It is unlikely that any individual can approach a whole tody dose of 0.125 ran per quarter.

c.

Personnel will not ranxe the source frce the primary shield.

In the event that circumtances lead us to believe that the shield is no longer an integral unit, personnel will be ramved frun the area and Texas Nuclear will be notified.

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f.

The ptrnping systen will not be turned off with mterial in the irradiate cell during nonnal operation.

Prior to snutdown, we will flush the syst s with water. To insure that no nnterial ranains in the irradiate cell, we will continue to flush and drain until the ganma spectrmeter count rate appmaches back-

gmund, g.

In the event the use of the systen is discontinued, the re-noval and disposal of the radioactive material will be handled by Texas Nuclear.

These points and included procedures are incorporated in the operations m nual provided by Texas Nuc1 car.

There is only very low-level radioactive waste generated in this syst s.

In operation (reference "Schamtic Representation of Nola I") a srm11 sample of iron ore slurry is recirculated through the activate cell and count cell for five minutes.

It can then be dtriped either into a suste line or back into the produce line. None of the activated material is ever released to any area that directly connects to any life support chain.

The imn ore slurry has as its principal constituents Fe2 3 (60-7CTA) and O

SiOn (3-20%). Table I lists scme data on the nere prominent activation reactions possible. Consider that in operation we put 100 grams of iron a

ore for five minute irradiation every cycle. For neutron irradiations of this type, the fonrula NU 3 f

where A = Activity in curies A=

(3.7 x 1010) n = Neutmn flux f

S = Saturation factor - (1-e I)

N = Ntrnber of target atcms available o = Activation cross section will estinnte the aanunt of activity produced per irradiation within an order of magnitude.

'bwever, exprimentally it has been detemined, in a five minute count period that the Si28 (n,p) AIUS reaction pmduces about 1.5 x 10-2 uCi of A138 in the systen.

55 All the other reactions, except Fe (n,y) Fe have ccrparable cmss sections, but wjl1 not produce as much radioactive material as the above reaction because their half-lives are long ocnpared to the irradiation time. Therefore, the naturation factor for these reactions is much arn11er.

In stnnary, we propose that no significant hazard exists either to mployees or the general public, in the routine release of the annunts of radioactive mterial produced in this systan.

W, therefore, will not make routine noni-toring or sar:pling rart of our safety progran.

. TABLE I Type of Ecaction Activation' Half-Life Gama-Ray Energies Isotope Activated and Cross Sect'on Threshold ~

Product of (MeV) and Reintive Abundances Element _

nnd Abundance at 14 MeV (eb)

(McV)

Nuclide Activity _

6 0

0 (99.8%)

(n p), 40 10.0 N

7.14 sec 6.1, 7.1 Si Si (92.2%)

(n,p), 160 3.8 Al 2.3 min 1.77 Si 2.62 hrs 1.26 (0.1)

Si Si (3.09%)

(n,y), 110*

Fe 2.7 yrs

.0.006 Fe Fe (5.82%)

(n,y), 2500*

(n,p),

375 2.0 Mn 290 days Cr X-rays 56 (91.7%)

(n.p), EO 3.9 H

2.58 hrs 0.845 (100)

Fe Fe 1.81 (30) 2.13 (20)

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TABIE OF 00tfIDfrS Iten No.

Its 1

Surary of Radiation Safety Precautions f

t 2

Isak Test Procedure QT/1X (Ps-137) i 3

Cell Oteck and Removal Proced tre l

I 4

Imak Test of Activation Analysis Sources 5

Drawing - Pu238-Be Source Capsule 6

Drawing - Neutron Source Shield l

7 Drawing - Inner Source Shield Assmbly t

8 Certificate of Training, Truxler - Michael H. Holnquist l

9 Certificate of Training, Texas Nuclear - Michael Holnquist 10 Intter of Certification, Texas Nuclear - Michael Holnquist 11 Record of Perfortnance, Texas Nuclear - Michael Holnquist 12 Certificate of Training, Dept. HEW - Kenneth Fisher t

13 Certificate of Training, Truxler - Kenneth Fisher l

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APPENDIX 1 SUS 1ARY OF RADI ATION SATETY PRECAUTIONS A.

NOLA Density System 1.

Cs-137; 500 mci in a lead-filled source head.

2.

Radiation survey provided at installation and need not be repeated.

3.

Leak test once every three years. (QT/lK-Appendix 2) 4.

Insure that the. source shutter is closed during all maintenance on the electronics and '.eak testing.

B.

NOLA Activation Analysis System 8

1.

Pu-238-Be emitting 1.1 x 10 n/sec.

2.

Radiation survey provided at installation and need not be repeated.

3.

Leak Test once every six months.

(Leak Testing of Activation Analysis Sources - Appendix 4) 4.

Radiation fields under normal conditions of use are very low.

5.

The source is affixed to a plate at the bottom of the oil bath.

6.

Loss of the entire water shield does not preclude repcir with the cource in place.

The maximum radiation levels without the water shield would be approximately 15 millirem per hour at the tank.

, 7.

Reserve Mining Co=pany personnel will not remove the source.

8.

The slurry loop is always to be flushed with water prior to any shutdown.

9.

Removal of the irradiate cell requires the handling of slightly radioactive materials.

The activation products built-up will not create radiation fields that are high in terms of significant dose.

One should be cware of them and, if appropriate instrunentation is available, monitor these fields during handling of the irradiate

cell, Gloves should be worn during handling and the hands washed upon co:pletion.

All cceponents should be cleaned and stored away from occupied areas until reasse=bly.

Familiari:ation with the "Cell Check and Removal Procedure" is advised.

APPENDIX 2 1EAK TEST PROCEDURE - QT/lK The gauge should not be diamantled or disassembled in order to leak test.

Testing of the external senes, flanges, and end plate is adequate.

Each kit is designed and supplied to test one gauge.

1.

If the gat ge has a movable shutter, position the shutter actuator to the closed position.

In the event that the shutter actuator is f rozen, or appears d saged, notify immediately:

Texas d: e. lear Corporation Health Physics Section (512) 836-0801, Ext. 256.

2.

Remove the two cotton-tipped applicators and the bottle containing the wash solution.

3.

Hoisten the applicators in the solution and wipe the source holder surf aces, around sea:s and bolts, where contamination is most likely to appear.

The radioactive material itself cay be in a small, pcuder-like form and if the steel encapsulation f ails, the material can appear on the exterior of the source holder at places where unwelded seams occur, around sha"? bushings, or around bolt penetrations.

A drawing, if enclosed, or comments under "Additional Instructions", if any, will assist one in defining the areas to wipe.

4.

Af ter wiping, place the applicators in the bottle (cotton down) and hreak the wooden stems off against the bottle edge so that the top can be resealed.

Care should be taken not to touch the cotton end of the applicators with the fingers following the wiping operation.

5'.

Place the bottle containing the cotton tips back in the mai.ing tube, af ter securely sealing the bottle.

Identify the device tested, either on the enclosed drawing, or on a separate page.

6.

Place the information sheets back in the mailing tube and rescal.

7.

Use the self-addressed label to return to Texas Nuclear.

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RECORO OF PERFORMNCE Michael H. Holmquist i

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( >M TRAINING COURSE FOR THE USE OF NUCIIAR TESTING EQUIPMENT.

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Q; SUBJECTS INCLUDED IN THIS COURSE WERE AS FOLIDWS:

i' 2,5ik h Radiological Safety i

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Principles and pmotices of mdiation 5.

Radioactiviiy measurement standardization b

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and monitoring techniques and ip-

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Leak testing pwcedures.

instrwnents.

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Mathematics and calcula,tions basic to 6.

Accident and incident procedurce.

i C4 i the une and measurement of 7.

Procedures for nuclear gauge stomge t

O M i m dioactivity.

and transportation.

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Biological effects of mdiation.

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General safety precautions.

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APPDiDIX 2 - Continued NOTES Upon rcceipt, the applicators will be counted on appropriate laboratory instrumentation that has a demonstrated sensitivity and ' accuracy f or the particular isotope being tested.

If the applicators are found to be free of contardnation, a notice will be sent via mail in the form of a Jeak test certificate.

If the applicators are f ound to contain significanc amounts of radioactive material, an energency notification will be sent, via telephone or telegram, advising that the unt.t must be taken out of

. service and what additional actions should be taken.

The sensitivity of the measurement will be stated on the leak test certificate.

The Post Of fice Department regulations prohibit the shipment of radio-active material through the cails when the level of gamma radiation at the outer surf ace of the calling tube exceed 0.5 milliroentgens per hour.

i Therefore, the mailing tube should be surveyed with an appropriate radiation detector, when such is availtble, prior to nailing.

If the levels exceed O.5 ni111 roentgens per hour, notify Texas Nuclear f or further instructions.

If.af ter reading the instractions contained there is still some question as r

to procedure, please contact Texas Nucicar Health Physics before proceeding.

Additional instructions:

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d APPENDIX 3 CELL CHECK AND PR! OVAL PROCEDUE This procedure is utilized only af ter the counting data leads one to believe that some Jbnormality has occurred to the source or irradiate cell.

The operator should shut of f the input of alurry, actuate ths main valve, 1.

and open the water flush valve to cican the system.

Leak test the source according to the Leak Test Procedure, and do not 2.

proceed on cell removal until the results of the test are received.

If leak test results are negative, proceed with cell removal as outlined 3.

below and in the section titled "Removal of Activate Cell (reference Inner Source Shield Assembly Drawing).

4.

Cover the working area at the top of the tank with absorbent material.

-5.

Position a plastic pan nearby so that the enc sulation coli can be lif ted up through the oil and placed in the pan with no spillage, llandle the cell with rubber gloves which can be easily washed.

6.

Measure the radiation exposure rates f rom the encapsulation cell to insure that the levels are low enough to proceed.

Por exceple, exposure rates at the surface of the cell up to 25 nR/hr should be considered acceptable.

The components of the encapsulation cell assenbly should be monitored 7.

as disassembly proceeds, and all parts should be cleaned thoroughly as 7

soon as practicable.

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APPDIDIX 4 LEAK TEST OF ACTIVATION ANALYSIS SOURCES the system should not be dismantled to leak test the source.

1.

With the source and cell in position, dip out two to four ounces of shield fluid f rom down near the top of the cell, and pour it into the sample bottle supplied with the test kit.

Close and lock the top cover plate.

2.

Cap the bottle and tapa the top closed to provide a positive seal.

3.

Till in the provided card with full information, including model number, serial number and date.

4.

Place the bottle in the mailing tube and send as f ollows:

Texas Nuclear Corporation P. O. Box 9267 Austin, Texas 78766 Attnt Health Physics Upon receipt of the oil sa.f e, the fluid will be diluted to H NO3 (1-normal) 2 and then filtered.

It will then be evaporated to dr ncsc and counted for j

alpha contamination.

If found free of contamination, a notice will be sent via mail, in the form of a leak test certificate, that the source is leak

. free.

If the oil is found to contain detectable amounts of alphe contamin-ation, notification will be sent, via telephone or telegram, advising that the oil bath cover should not be opened and that an additional leak test sample is to be taken and sent by air to Texas Nuclear f or analysis.. if the second sample contains alpha contamination, notification util be sent advising that Texas Nuclear personnel will be sent to remove the source f or return to the manuf acturer. Under no circumstances is the shield to be opened during this period of time.

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i1 IIAS SUCCESSr*JLLY COMPLETED TIE TROXLER EIICTRONIC IABORATORIES, ING, b}

TRAINING COURSE TOR TIE USE OF NUCIIAR TESTING EQUIPMENT.

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SUBJECTS INCLUDED IN TilIS COURSE WERE AS FOLLOWS:

c}f4(y Radiological Safety

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1.

Principles and pmotices of radiation S.

Radioactivity measurement. standaniination

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and monitoring techniques and

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Leak 'esting procedures.

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Nato atics and calculations basic to 6.

Accident and incident.procedums.

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Procedures for nuclear gange storage i:

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and transportation.

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Biological effects of radiation.

8.

Ceneral safety precautions.

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Instrienent theory 4.

Field application g.

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Operiting pwpedurca 5.

Cauge calibration y < r-

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AUGUST 9.1973 M.'LLIAM F. TROILER I

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C, Appendix 10 l

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} 21 536 4 601 LETTER OF CERTIFICATION This is to certify that Michael H. Holmquist l

Reserve itining Company l

t has attended and cuccessfully completed a course of instruction, conducted t

under the auspices of Texas Nuclear Division and described in the attached i

Course Agenda.

The course covers fundamentals of radiation, units of dose i

and qual' ty of radiation fields, hazards of radiation exposure, detection I

devices, regulatory controls, industrial devices and specific training on

[

i installation and leak testing of Texas Nuclear density, level and weigh gauges, j

I The said course of instruction, together with ' prior experience, is struc'uted f

to qualify persons who complete it te understand and safely perform various f

I operations involving nuclear devices including the instaliation, relocation I

and leak testing of such equipment.

The operations are to be done in f

accordance with the rules and regulations of the United States Nuclear

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Regulatory Comminion and/or "Agreement States", and are in all respects i

subject to such rules and regulations.

This letter cannot be used in lieu of a specific license from or other sanction by an appropriate regulatory agency, TEXAS NUCLEAR DIV!SION Ramsey Engineering Company yj/pg.pwn,'

j tr. G. Hendrick Health Pnysicisc L