ML20134D182

Responds to 711005 Request for Detailed Info Re Radioactive Effluents from Reactor.Air Samples Taken Daily on Nearby Bldgs Indicate No Release of Activity Directly Attributable to Reactor Operation

ML20134D182
Person / Time
Site:	Dow Chemical Company
Issue date:	12/30/1971
From:	Hoyle H DOW CHEMICAL CO.
To:	Skovholt D US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20134D174	List: ML20134D170 ML20134D182
References
FOIA-85-256, FOIA-85-258, FOIA-85-259, FOIA-85-261 NUDOCS 8508190136
Download: ML20134D182 (4)

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THE DOW CHEMICAL COMPANY" December 30, 1971

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Dear Mr. Skovholt:

This letter is in reaponse to your letter dated October 5, 1971, requesting detailed information concerning radio-activity effluents from our reactor. The Dow TRIGA Reactor, AEC license No. R-108, Docket No. 50264, has been in operation since July 6, 1967. It is used primarily for activation analysis studies.

The radioactivity released to unrestricted areas on an annual basis results from the disposal of spent activated samples and the release of argon-41 stemming from the air contained in the " sample" rack and the pneumatic sample transfer system.

i Most of the activated samples contain only short-lived

isotopes. In 1970 and 1971, a minimum hold-up time of seventeen days was maintained between the time of activation and the time of disposal. From this procedure less than 0.0006 curies were released to unrestricted areas annually.

The production of argon-41 accounted for an additional release of less than 0.0004 curies to unrestricted areas

annually.

1 It has been the practice during this period to incinerate the radioactive waste in Dow's main incinerator. This unit is operated at approximately 1100*C with an air flow of 50,000 cubic feet per minute. The effluent temperature is approximately 200*C, and the effluent stack height is 200 feet. The incinerator is equipped with a triple spray wash system. The effluent water goes to Dow's water waste treatment facility. The amount of water effluent from this treatment facility is approximately 50 million gallons per day.

We assume that the 0.0006 curies of activated samples, when burned, were all released in the gaseous effluent from

the incinerator. For this case, the concentration at the 8508190136 850711 PDR FOIA KOHN05-256 PDR

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D. J. Skovholt Pece-laer 30, 1971 point of release to an unrestricted area (the top of the stack) would be approximately 8 x 10-13 p Ci/cc of air averaged over 1 year. Incinerations have been carried out

, only during favorable weather conditions to provide for maximum dispersion. -

If we assume, on the other hand, that all the activity were washed down and released in the water effluent from the plant, the averaged concentration would have been 9 x 10-12 C1/cc of water at the point of discharge.

The isotopes released in this manner consisted of the following:

Isotone Amount (C1)

Br - 82 <0.000010 Na - 24 <0.000001 Cr - 51 <0.000025 Fe - 59 <0.000070 Sb -124 <0.000060 P - 32 <0.000250 Sc - 46 <0.000050 Zn - 65 <0.000005 Co - 66 <0.000003 Hg -203 <0.000010 Ag -110m <0.000020 Ba -131 <0.000005 Cd -115 <0.000025 S - 35 <0.000010 Se - 75 <0.000010 Ni - 63 <0.000001 Total Mixed <0.000555 The argon-41 is released through a vent to the outside of the reactor building. The air flow through this vent is 1000 cfm. The concentration of the argon-41 at the point air.

of release is then less than 3 x 10-11 p C1/cc of The direct radiation levels to the unrestricted area from this facility is undetectable (less than 0.01 mr/hr and less than 10 milli-rem / month). The direct radiation level

'from the facility effluents is also undetectable {<1 x 10-14 -

uofC1/cc air of of air of short long lived lived isotopes, isotopes, x }J0-11 p C1/cc and < 1<x210-water for all isotopes).

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D. J. Skovholt December 30, 1971 Several monitoring systems are used to determine radiation exposures to both staff and non-staff. In the reactor room itself, are located two area monitors. One is a Nuclear Measurement Corporation continuous air monitor which pumps air into a chamber (~2 liter capacity) and through a filter paper. Approximately, 1/4 inch from the filter paper is a thin end window Geiger-Mueller tube, shielded by about 2 inches of lead. The background of this monitor, stemming from radon daughters, is 1.7 x 10-11 p Ci/cc of air. The second area m6nitor is a G-M tube located 13 feet from the top of the reactor. It is connected to a ratemeter and is sensitive to approximately 0.1 mr/hr.

Located in the water tre.atment system of the reactor is another G-M tube monitor, which continuously monitors the pool water and has a sensitivity of approximately 0.01 Ci/ml of water. All water in contact with the reactor core is cleaned up by means of demineralizers and recycled.

The decineralizer bed is periodically changed, with the old one being first monitor.ed and then incinerated. Its release of isotopes is included in the above calculations.

In addition to these area monitors, several " laboratory monitors" (mica-window G-M tubes connected to ratemeters) are continuously operated within the laboratory building housing the reactor. One of these is operated in the hood to which is connected the exhaust from the pneumatic sample transfer system of the reactor. The others are operated in adjacent laboratories. These monitors have a background

, of approximately 100 counts per minute. Many other portable, standard, health physics monitoring instruments are used in the building for routine surveys. These instruments are used for alpha, beta, gamma, and neutron radiation measurements. Several multi-channel analyzers, liquid scintillation, and pro used for evaluating gaseous, liquid, portional counters and are also solid samples.

The lower detection limit of these instruments are generally 1 x 10-7 p C1.

Film badges for beta, gamma, and neutron dose measurements -

are used to evaluate radiation exposures of individuals present in the facility. The film badges are supplied by i

R. S. Landauer, Jr. and Company and are sensitive to 10 milli-rems of X- and gamma radiation, 40 milli-rems of hard beta, 20 milli-rema fast neutron, or 10 milli-rema thermal neutron. Pocket donimeters are also used to evaluate radia-tion exposures, and are sensitive to approximately 2 mr of X- or gamma radiation.

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D. J. Skovholt December 30, 1971 In addition, air samples are taken on top of nearby buildings on filters which are counted by gamma spectro-

, scopy and by beta spectroscopy.

There are ten sampling locations in the reactor room, the building housing the reactor, and adjacent buildings.

The personnel film badges, changed once per month, have indicated that personnel are exposed to less than 100 milli-rem per year of X , gamma, or beta radiation at our facility, and to less than detectable amounts of neutron radiation. Area film badges have indicated less than detectable amounts of all radiation.

._ Air samples in the reactor room have indicated that airborne concentrations of radioactivity to be at the background level of the monitor (1.7 x 10-11 p Ci/cc of air) except during periods immediately following atmospheric testing of nuclear weapons. This has been confirmed by gamma spectroscopy and other routine measurements around the reactor.

j Air samples taken daily on nearby buildings indicated no

! releaseofactivitydirectlyattributab{gtotheoperation of the reactor. Some activity (1 x 10- p Ci/cc) of long j lived isotopes, mainly radium, thorium, and their decay products, with some fission products following atmospheric

! testing of nuclear devices were, however, identified in these samples.

I We hope that the above information will suffice your need.

In case additional discussion of any of the above items appears desirable, please do not hesitate to contact us again, i Very truly yours, L t,IM8/ x HsroldHoyl[e,Mairman h

Radiation Safety Committee 1701 Building HRH:dda t

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C' GOVERNMENT ACCOUNTABILITY PROJECT 1555 Connecncut Awnue. N.W Suite 202 Washington D.C. 20036 (202)232-8550 April 9, 1985 Freedom of Information Officer FRE.EDOM OF INFORMATON United States M REQUESI Nuclear Regulatory Commission Washington, D.C. 20555

Dear Freedom of Information Officer,

Under the provisions of the Freedom of Information y Act. 5 U.S.C. 552, the Government Accountability Project (CAP) is requesting copies of all licenses, permits, and any amendments to said licenses and permits, issued by the NRC and/or AEC to the Dow Chemical Company of Midla nd, Michigan. Please include all background and/or justifi-cation information which, supported the NRC and/or AEC license and/or permit.

CAP requests that any fees be waived. As you know, the Act (5 U.S.C. 552(a)(4)(a)) permits you to waive any fees when the release of the information is considered as "primarily benefiting the public." CAP believes that this request fits that category.

For any documents or portions of documents that you deny due to a specific exemption under the Act, please provide an index itemizing and describing the documents or portions of documents withheld. The index should provide a detailed justification of your grounds for claiming each exemption, explaining why each exemption is relevant to the document or portion of document with-held.

CAP would appreciate your handling this request as quickly as possible, and we look forward to hearing from you within ten (10) days, as the Act stipulates.

Sincerely, Steve Kohn Staff Attorney Richard condit Staff Associate I

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1555 Ccmecticut Awnue, N.W.. Suite 202 Washington, D.C. 20036 (202)232-8550 April 9, 1985

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Freedom of Information Officer United States sg g -

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Dear Freedom of Information Officer,

f Under the provisions of the Freedom of Informatio Act. 5 U.S.C. 552, the Government Accountability Project (GAP) is requesting copies of all reports, studies, and/or rnonitoring analyses done by and/or for the NRC and/or AEC on the incineration activities of the Dow Chemical Company of Midland, Michigan.

CAP requests that any fees be waived. As you know, the Act (5 U.S.C. 552(a)(4)(a)) permits you to waive any fees when the release of the information is considered as "primarily benefiting the public." GAP believes that this request fits that category.

For any documents or portions of documents that you deny due to a specific exemption under the Act, please provide an index itemizing and describing the documents or portions of documents withheld. The index should provide a detailed justification of your grounds for claiming each exemption, explaining why each exemption is relevant to the document or portion of document with-held.

CAP would appreciate your handling this request as quickly as possible, and we look forward to hearing from you within ten (10) days, as the Act stipulates.

Sincerely, Steve Kohn Staff Attorney Richard Condit Staff Associate

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GO'ARNMENT ACCOUNTABluTY PROJECT 1555 Comecncut Awmue, N.W., Suite 202 Washington D.C. M April 9, 1985 FREEDOM OF INFORMATX)N Freedom of Information Officer ACI RQ United States Nuclear Regulatory Commission Washington, D.C. 20555 h h*1M ~

Dear Freedom of Information Officer,

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Under the provisions of the Freedom of Information Act, 5 U.S.C. 552, the Government Accountability Project (GAP) is requesting copies of all information on record at the NRC and/or AEC which indicates, and/or has indicated, that the Dow Chemical Company of Midland, Michigan was not in compliance with any law and/or regulation and/or guideline (s) administered by the NRC/AEC and/or any other state or federal agency.

CAP requests that any fees be waived. As you know, the Act (5 U.S.C. 552(a)(4)(a)) permits you to waive any fees when the release of the information is considered as "primarily benefiting the public."

GAP believes that this request fits that category.

For any documents or portions of documents that you deny due to a specific exemption under the Act, please provide an index itemizing and describing the documents or portions of documents withheld. The index should provide a detailed justification of your grounds for claiming each exemption, explaining why each exemption is relevant to the document or portion of document with-held.

GAP would appreciate your handling this request as quickly as possible, and we look forward to hearing from you within ten (10) days, as the Act stipulates.

Sincerely, Steve Kohn Staff Attorney Richard Condit Staff Associate O

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l GOVEluGAENT ACCOUNTABlUTY PROJECT 1555 Comecticut Awx;e N.W Suite 202 WO5hington, D.C. 20036 April 9, 1985 Freedom of Information Officer M United States 'JREp OC O

Nuclear Regulatory Commission Washington, D.C. 20555 p g ., $ 1 (p l

Dear Freedom of Information Officer,

i L ll Under the provisions of the Freedom of Information Act, 5 U.S.C. 552, the Government Accountability Project (OAP) is requesting copies of any information compiled by and/or for the NRC/AEC regarding the Dow Chonical Com-pany of Midland, Michigan which was compiled in order to comply with, and/or to determine the need to comply with, 10 CFR Parts 19, 20, 30, 31, 32, 33, 34, 35, 40, 51.4, 51.5, cl.6, 51.7, 70, 17 0,ht a tand/or GAP requests 40 CPR any fees Darts 1500.6.

be waived. As you know, the Act (5 U.S.C. 552(a)(4)(a)) permita you to waive any fees when the release of the information as "primarily benefiting the public." is considered i

this request fits that category. GAP believes that 1

For any documents or portions of documents that you

' deny due to a specific exemption under the Act, please provide an index itemizing and describing the documents or portions of documents withheld. The index should provide a detailed justification of your grounds for claiming each exemption, explaining why each exemption is relevant to the document or portion of document with-held.

GAP would appreciate your handling this request as quickly as possible, and we look forward to hearing from you within ten (10) days, as the Act stipulates.

Sincerely.

Steve Kohn Staff Attorney Richard Condit Staff Ansociate (fT gigh,d

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. M h hbl1Id *.nuI(e fdhl i(atOd f fLe 1fbenhef d11 LO ifi o ted dbd t( n'Id f f

'3 o u. u nn m..m. , n+ r , od . n n t s ea u on p r i e,.

t o m.. e r n + - , .

9

...,d .o rrn. If the inti,ction or t m t e n N lt, m y u m tr m l 'i n d >f. t- r -

D d

n. ,5 r it_rocurie or grriter of tortn.ination, the snurre W il not l e med tr a he r',1 as a ,raled murre until it hos been r epale "d, &< nl ,lha t e d ,mi

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2r t. m 9 h4' Ikii V MJfdCf M AI1.RIAt_S LlaNSti 21-00265-06 ),L, 1 surPu MENTARY SHEET

[1 ,

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, blL _ . _ _ _ _ _ . _ _ _ .

Awfoent No. 41 _

i>

% b; If C. Each sealed source containing licensed ruterial, other than Hydrogen 3, with i'i t, a half-life gruter than thirty days and in any form other than gas shall be 13 tested for 1 rat tge and/or contamination at intervals not to etteed six nonths f(;4 f

except that och scurce designed for the purpm.e of enitting alphi particles 1.1 il

{al shall be tested at intervals not to r ueed three soths, -

d

, b; Li D. The test shall te rarable of detetting the presence of 0.005 mhrwurle of FI

't p radioactive r:aterial on the test ' . ple. The test sorple Stall !'e taken from h

it the scaled source or frem the susfates of the &vice in which the sealed source

,I]l Is penr.anently or seniper Nnently o cunted or stm od en which r no cight expect q:;

4 s Pecord of,h at test results shall be kept in P l ll- centamina units of microcuries t ion to accuraulate.ddried*

and d i f'o'r trRis / tion by the Cot oission, i p . g, - ~ (' ,. . 9 d E. If the test required by fSubsection A or C of thisiycJadition reveals the f

!] presence of 0.C05 Iii2rocurie or more of rea.ovable c'entjmination, the licensen L,1,

'l shall 1: colatelv sithdraw the scaled source from ush and shall cause it to be I btcolmiiut: d .hd r epal.t ed or to be disposed of in ac'c'ol; dance with Comission 1];

[1 t t ,;ula t kas. 4'4 ; itt < hall Le filed within.five (5) days of the test with the Fj d U.S. hocl<ir M iatory C; lission, Peginnf!!!, /99 ih esevelt ro id, Glen Ellyn, P!

q lil lra is ' 91 P , J se c it hm H e epi; r.qt in< caved, the thst results, and the .1 p

i cm m ti.c n t i n t d en.

/ r' {

s

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i g r ,th sc Ad sr ut +

e cunt.dnu g l ks wd t steri'al f: l' w d ou' side of a shielded i' il cymre 4 v h e J 41 1i or a dJrab'",1, jible, and viiible !ag ter r m ntly at tm hed 'l

'I to the *z' ace.

y j of the r ol%

'le 99 %Il t e at i et a,e (1) im b i pre, shall l ear the con-untio al radiatim t,e al prescrita in 9 'ien /0.70(: 1),10 LFR 70, and a minimm int; is tl rac tiora: Pf'L;M i LM!UM lVL l'.M LRI Af..) DO N0r HANnLE . N P;

! thall be accomplish"d by y I [q1 CIVIL per c rsAUhiRl!!LS If fMND.by.Pepgir s; ecifically 'licersed the' Cor.c or replau issicn' or. ment bn Agree of tags,d:nt State to J erform this 9

1 servico. Ql, f,' d f4 +M

,k( j' ,q

.q

g. c o mo sour ces containing ifm ed rati. rial aail rot te openca. 1' e b e o N e( 'n YI b h b=' a t f o!) b1N t iIJrl C olors (!ra gr r:t 3 or ; yi;,lo on *

'1 yelles badgreur d) as p a i d in t t h n 2 0.?n3(a)(1), Ti t le 10, f-

.a ' gal .;

,I replatitrs, Part 20, the lictv<" i s ' t ahy .m th iced to 10 el J '- .r > "11 ' . d

.]

rell t aths, ccntaining 11o r

• r d r or tal md used in p s rhr i t # , l ', '

h , oi: $

g g <erspwosly etome or sted ,.,dna n n uuuon synois u m a a m .c ,. c 1 q

% A. Cm(tor calls t u tainlng titanium tritide f oil shall only be o'ed in < u Jor c- Nj h r.f on with a p e ;erly olii ating to"perature control rar benism MIch p nti. foil .)

1 to ,eratures fi,o c u n ding FPS degrees Contigrade, 1

,i -l .,,;

, . . Of cells (0PtalnlW Mand luld tTltlde foil shall nnly lJ Used ln Id'hjblC- ~!

n tu atna m, iyorraungice.ae,em,a,a umni.o nn - -, u 3 jp t" -i a t ues f rc , c. < eding #5 dtgr ees Cent igrade, i I!4

gl d

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,. t usg

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ge r o. m . u cutuony cm .'

"Ltux_ f I .u

.t ,5 w 5 c. m d;

I II M.\ ll:llI ALS 1.lRNSE 21-COTb5-06 1

• ' "^""'

[l

• SoPPLLMLNTARY TEET !a el

!. i i .t fl! Amendment No. 41 d . Exrerirental anir:als administered licensed ruterials or their products shall not Le used for hum n censumption.

l ff Lt il

[k

i

!!Szo(. Installation, relocation, raintenance, repair, and initial radiation survey of dev h.cs L1 centaining licased r.aterial and installation, irplace. .nt, and dispr<al of soled i d l

' Q sources containir o licensed c.aterial uf ed in devices shall f.e K fon ed only by by the licu;sen or by other persons sp tifically mthorized by the Ce7iission j

ky or an f grct; ent State to pcrforn such st:i vict s. .lo 9 ,6., d '

• f.

'j ,,*re ' j l QM , s*"sd q

l [t  % A. rarsuant to %ctions 20.106(b) and 20.302, 10 C F R ? Olicenu , t O e[y,is authorticd 51

i

to C h yse of licensed v.a t erialt. jut hor it.ad ,in Subit eu fM by bc f ra t a tion

(

F r os iNd the gaseous ef(10ayt' fium iritiidrati/q does not exceed the lir.its ;j" l'

k sgcified for air in A diy esed of as ord,ihar/rendix B, Table 11,10 DAfD. waste provided app Ash res H as nay Le j h a

!1 f r.ction 20.?01 are 'rdde to deternine that concent rat, ions of licenstd raterial ..

i

[i m;pearing in the a;h residues do not exceed the conceitraticns (in terms of d' LI 1 i nicrocuries ter,r gran) specified N N,, for water in Appendiv ,y ,,

B ,4. Table !!, 10 CIR P0.

. a

4

. s < . . -

-t

t. , B. This 11rtnse /f a, s not aut hori<c a: . rcialf incineration, or the  :.

G incinerat kn of waled .ou: O sp cial)nocleor, or source rif eriais, 'j D /

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d< 6 id o\r deil:.1 r l i, nu d ct<'ial ta l

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it 3.

4 It e l i c c r u e . iy ,t e rm, .t 1 1 < . o a carrier for tr, Wort ,in xcord w e with tl'c riavision's at Title 10, f Me of j

j Federal Regulatice.s; Part 71, "Iad Miw o f C Micac t i'.c !N e rial f or S.x , ort j and Trrrsportation of Radiective f' terial 4 ' > r Coi t ain Ccodi tions."

yN -l' 1

( 'i c c ',  ; l i  ; '

44 w.and

t r,r.ept as ccificniy. provva n.m.a by wis ume, tw wsw u,n pm-use licensed roterial di t scribed ,in item 6, /, cod 8 of this lit ense in atua ds 1 .i l  ;'l with statrents, representations,and prnredores contained in applit atica dited  ;.1 li 0 ;^ Mr 11, lW.; letter datied optm ier ?8,19M. The , Nuclear Repla t ory F,I

]

^

(- Askn's reculations' thall gwern the licmee's itato "nts in pplications or N le't.,c, ,rinss the statt: ,nts are , are r est rir tive t han the repla t i..ns. j '

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- d29$> w- DOW CHEMICAL U.S.A.

MICHIGAN DIVISION **^N* "*"CAN N3 f March 11, 1985 .

! r. George M. !'cCann

• U.S.N.R.C.

Recton III 799 Faccevelt Road ,

Glen Ellyn, IL 60137 Ocar Sirs:

This is notification as to our intent to purchase a 252-Californiun neutron snurce reca A:-ernh m Car; oration, Arlindton liclchts, Illinois. The source

is !.*C ar,.reve

1, #CV!!.-CYS, and 'is coverca untice our license 21 40?65 06 This re utron r.,orce is 50 nicrograns, 27 nillicuries. This m'.rce will be t .ed for r e c irch pur; o res.

J

.~I t fil t_ r 017,

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, #{ V 3+ 3.. . .*y.; [-

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• ad* r 'l I. , JifCt k) '

r f, * . ! '3 t i l t T ,c' sr "u;a r y !:sor

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! hw Tr ica Fe. : <* circh Pnactor ne 1

R -: c C \ ') 6 0 t ,.m. . , 1 3 1'f5 v'.C'03 N i

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Wn,Ay[L ' ' '

1

k- o:, Y ir' i u r.M A f un y (W A ' # l 'F b r f. .

fL LL't.D COPY .

M.\ l l:RITI.S 1.lCl.NSE I"' W ant fio. 41 4 Ph y Pu @rmnt to the Atomic Energy Act of 1951, a amended, the I ns tgy y 1

y Code of Fe detal Regahstions, rt apter 1. Parts 30. 31. 32. 31. 31,35,40 and 70. and in actiance on itatt ments nd s;m em,.3.' i

]; heretafore nade by the tuensee, a lisense is hereby issued authorizing the licensee to receise. .uquire, possess, and transfe 3 t ponn, f

,4; source, and special nudcar material designated below; to use it.ch material for the purpose (s) and at the p!.ne(s) desgn3 tea % ,,, l,,

4; de!iser o. t ansfer su h material to persons authurized to receive it in xcerd.mce with the regulations of the apptiegte gnig p4 q

[f L cw sh d' be dqn,ed to sontain the conditions spesified in Section 183 of the Atomie l'nergy Act of 1954, as an,emh a, y ubject to it: apphab!c rutes, rep!aiions and orders of the Nodcar Rerutatory commiWe n...s or hooff er in c f rea ;md t , ny i,,1:, s , . h: ions 5; caneJ bh>w.

,q ti. t r.e e

-. H N in accordance with application dated .N 8 September 11, 19E4 '!

hI-y ra Che nical h mpeny 3 I i""e nuba 21 00n,$.06 is ar tnded in its i ntir ety to read as follows:

, ;4

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, g 2. 111 dl ar.d , !!! 43640 , ,

~

ij

j 4 Ii.;+.ine hte s .. tio m her 30, 1989

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~/ 5 Dodet or s 's 1

4 g Referent e No. '/- SMt-1451/07001487 3

j

[4

6 Ilypodut t. o m e, and/or -

7. Chemitat and/or phpical ( R himu:n a nount th3t h,ensee '

ge<ial nu.!ar no'oial N

('. .s form ,. , ' ?may peess at any one time ,i P (A N N .-/ '

ilnder this ticense d'

'i /,7 > '

• q

.d_A. l.ny byprcduct raterial

! A. Any / A. fiot to excred 1 j i

h  ! t..e( n Atcuic flurNrs  ; curle per radio- 1' I 4 1 and 83 inclusive '

/

t nuclide and 75 3 l4 ,

curies total, 3

!i -

esccpt as listed >i l belcw. 1

4 1 f, r u n i m !

q(

Carbon 14 htalt 60 2 cvt - .

K - '

Cesium 13/ 2 curb:s ,:

14

~

q Hydrogen 3 /5 curb < '

.;4 1

, Krypton 8510 cue b s Q s

!) 8. Any t;jproduct raterial B. f11 red fission products 4. 2 curies I n .:

'4 C. At eririum-241 C. f.kC apricved viled sources C. !;ot to n eed 10 J it c t. : !cs pir scurre '

150 turies total 2 I

4

[4 4

0, rai i fi i ii -?,2 f. '.M .w ni d < oaled sat as D. f ot to enced 0.2  !,!,

y cur les per soun e, ,,;

4 2 curies total r;

'4 i 1 E. Curtur444 E, fGC approved sealed sources E. f;ot to n c a d 0.5 j,

[1 1 turies Ier riveio

• I 3 curies total -'

.4 f4  :

'a F. Any typ t att ratorial F. f.PC approved scaled sources f. fiot to en t ed 5 -

l4 t o t v r en Atonic f;unbers ct. ries per st urce 1

',11; 3 at d E4 400 curles total i 4

G-3 -

0 g p f (ill W ,,

9

7: .:- :.x.a w w

. . c :2. ~ ;c w . . c, , ,, ,,

' U.S Y q[I f1 '"c ro,m Na P* 3744 E AH RFCUL Af 0RY co. *.1Ms0f4 um nune

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{j SIA rERIALS LICENSE n7,,g,, y;,,),g,3,f[ S$_h1____

j SUPPLEMENTARY SHEET

{l

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_ _ _ _ . _ _ _ _ _ _ gj -

L I

C..ORREC__TE_D COPY kl i i t _ -

_ ._ Amendm_ent N_o_.__.41 _ _ . _ . . _ . _ _ __

V'

! tt 6. Byproduct, source, 7. Chemical and/or 8. Maximum amount that M l kI and/or special nuclear physical form material licenseemaypc,sess%

at any one time i [!

l 7, j under this license

.i :

i l

'p%

[i G. Plu enium-238 G. Scaled Sources (Amersham Model PPC-X)

G. 5 sources not to exceed 30 milli-h!

N!

curies per source r i1 e f ,,

I fiI H. Flutonium-238 H. Scaled Sources H. I source not to y:'

{ f! ercced 120 $

! l gl(M 'Amei' shag '

V (f l% del fP,C-X) millicuries F .

I. Cesium-137 1. Scaled Sources \ 1. 144 curies F @ Ox y:

~ ~

I l F~~AJUiorliid Vse: e N

-" /' fl l; l) , pGl A- :b !

j L; A. through E. For resear,/h and devol6rment as defined,in 56ction 30.4(q) Title 10, Ccde of frederal Pegulatidns, Part:30,' including antr;al studies, is; -

h sg l Carbon-la, uay alsc be.11 vied ir[ fiejd ind ).h' uran studies.) j. l; tg -, . .

! [d C. through F. To to Acd in NOC apprcAe'd(isottrial prrductions gautes/scurce ll l

ri holders for physic lal rm.urc.er ts and ar,alyses of r.aterials cr in Dow

)(

l l4 custcm-Lade devices in accor&t.ce with" protocol' contained in 1' applicatien,dat'edterteder11,19(4., e' j .

yI ,

4

.s ,

.q  :;

i V G. For use in Telesec l'odel X-200 Xiray flucencence adalyzers for testing of pi j rna terials. Y, " 4 (J H!

Q, 1/. Mj wp' ;d !

!  !(j:

4 H. for use in Texas f.uclear (ustom-designed thickness for gau5e(V testing of .i':

h r,atcrials. / o

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y,

.* _ $ ,, g:

i y4 !. .-

To te used in Eberline Model 1006 instrurent, calibrator for instrurant a>

4 calibration. ;r 4

3 I4 i i ;4 -

g g . __ --. . .g g~

~ . ~ . _ . - - . . _ . - . - . _ _- 1, i4 9 -

!  ! 10. 1.icecsed r.aterial shall be used in facilities approved by the licensee's Radiation pl

! j<a Safety Comittee at the following locations: tjl l ;i N, i d. A. Ocw facilities located at and associated with the 1803 Building, Midland, la i I

II Michigan, d

4 q

,4 t, 1

ja D. Ocw facilititis loca*ed at and in conjunction with the 9001 Building,  !'

l g Agriculture Fe',circh Center, liidland, litchigan, q, g- .

3.

4 si

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UsN C U M CULA MM Y cW . MON

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?F" t $1 ,

.%fATliRIALS LIGNSE 21-00265-06 l h! nyg g,7ug,c, ,,,ig,, , '[)I -

(; $UPPLEMENT ARY SHEE T

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, !j COR_R_ECT _ED C _OPY Amendment No. 41 i ti _

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!  !! C. Dow facilities located at and in conjunction with 4868 Wilder Road, iy ,

! Bay City, Michigan.

(

i

[f i

t D. Ocw facilities located at and in conjunction with Larkin Laboratories, j

[ri l: Midland Michigan.

' [}t Ll pi j '

The licensee shall certply with the provisions of Title 10, Chapter 1 Ccde of rederal d'I

$,h11. Regulations, Part 19. " Notices, Instructions and Reports to Workers; Inspections" and N:

t!

'I Part 20, " Standards for Protection Against Radiat. ion." . j' '

g 4

12. Licensed materials nay be used by7orgundeg th9 supervision of individuals g j r designated '{ ;

W. Rampy, by The Dow Chemicpigg-pan]'s* Ra,diatio41/(Safety Comittee,*

j L. Chairperson.

g q ,

if 13. The use of licensed mathal in or on humans beings, sha e by, or under the A .

! supervisicn of a physic,f an as defir.ed in 10 CFR 35.3(b). y, i ;1 -

h /7s 4 l 14 The Radiation Protect}cn Of fi'cer for the acthities:buthorized by this license is f(

{ ;f

G. W. Ergdahl and ,T.' 'W. Parsons (ucording to duties"cutlined in application 1 t l d' dated Septu a r 11,1904),

] a } c ,; }  ; ()' ]!

T(4 l( 15. A.

' / /'

(1) rechsea'edscutteccatainirglicbnsid .a terial, othcr) than bA LSr-3,

_. . < 1 g

l

!( with a latf-life great;r tbn thirty das'and.in any fern other tt an g,

i gas shall'be tested for.letacc and/or cuntsination~at intervah not 4

] fl to excr5d six rentts; eicept these scaled hources asispecified by the i ranufacturer and sfccifically icthorf ed ty th'e Combslon or an

%g!

i Agttteent State uay be Icak Msted 'at intervals not <to exceed three

~

l I T4 years. In the absence Q;

! 4 that a test,has bcen ra,of de bithin a certificate i,ii sonths fromprio a transferor indicatinga to the transfer, Li I [d sealed source' received frct'a'nother pers6n shall,(hot to put into use il J

;(4 until tested. Ur) - &

g-9, pl !

, ;q ,, s .

j (2) %twithsti.ncirg the per(Wic icak test required by this condition, any i

h

'y licensed 9 aled scurce is exer.pt frem such Ital tests dcn the source jfl!

.; cateins 100 microcuries or loss of Leta ard/or gat

a unitting 7terial N(

1 or 10 ricrowries or less of al Aa niittir y raterial, dl q .

, Q;l (3) Empt for al;ha sources defined in 15.C. belew, the periodic leak test bl j required by this ccndition dces not apply to sealed sources that are j ;

lq q stored and not being used. The sources excepted from this test shall it !

4 be tested for leakege prior to any use or transfer to another person M!

unless they have been leak tested within six months prior to the -

date of use or transfer. },i j

%{of

,y B. Tach sealtd scurce fabricated by the licenstc shall be inspected and tested for j l

! h construction defuts, kakage, and contenination prior to use or transfer as a ji <

j 4 sealtd source. If the inspection or test reveals any construction defects or <

0.005 nicrocurie or greater of contamination, the source shall not be used or 3 k:

i l transferred as a tealed source until it has teen repaired, detontaninated and Nj i ;t retr tel. . .

l  ;'  ;

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( ~'~ ' ,,- - ~ ~4 ~cm ,,3 '

L ".' i tens m nder 5 -

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I MAIERIALS 1.lGNSE ..

2 WM5:01_ l'

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I j SUPPLLMENTAnY SHE ET N'

j L; _ _ --___ _ ___.

y i [ CDRM CTED COPY Amendment tio. 41 . f' f C. Each spled source containing licensed rnaterial, other than Ilydrogen 3, with t! a half-life greater than thirty days and in any form other than Sas shall be a

[4t! tested for leakage and/or contamination at intervals not to exceed six months except that each source designed for the purpose of emitting alpha particles M'

1l II d shall be tested at intervals not to exceed three months. 'il i j  !%

pj

I! D. The test shall be capable of detecting the presence of 0.005 nicrocurie of ij h' radicactive material on the test sanple. The test smple shall be taken from 3 i the scaled source or from the surfaces of the device in which the sealed source 1 i

'l 1s perrarently or scalpermanently rounted or stored on which one riight expect fi d

I ,j i

contamination units of microcuries to accumulate.kalr?ed' and rdi lor'fnip'ection by the Cow.ission. Records ij j VI E. If the test rec,uired (~

by'VSubsection A "Q or C of thisicjndition reveals the H

!! . k{

f. presence of 0.005$i2rocurie or more of renovable cont 9mination, the licensce shall imediately(withdraw the scaled source from use'and shall cause it to be h.h Il' tj i i deccnta.ainated,and repa(red or to be disposed off in;ac'c'ofdance with Connission p

! [i regulaticns. , repos shall be filed within,five-(5) day's of the test with the 9j

j U.S. Nuclear r{efulator) C&51gston,ili,t799 Pegionf Poosevelt Road, Glen Ellyn, j invoNd, the testi j;re

4 ig Illir.ois ac corrective 60137, t,ien t d en.

describing f

f (the[ \/ ' equip  :,.'~ cnt()

< d i d Each staled sourc,e containing .

1ic\raterial ensed w - to be used outside of a shielded ti

{ d egosure device sba)1 bear i durable, Icgible, and sisible tati Icmar.cotly attached ij t

to tte sturce. The tag shall be at I m t cne (1) inch square, shall bear the con- N

, (d antienni radiation sMol prescritt:d in $<:cticn 20.F03(a),10 CFR 20, ar.d a mininum '

l

' 4 4

of the folic.<ing instructions: ~

L LMER - PMICALMVC F.MERI CIVIL AUTNRITIES IF FOUND.+ Repgir or replacemnt of tags shall t,e accornplished by

~

4+

k persons specifically'llcensed by tho'Cojnission or ~an ' Agree,nent State to perform this M

[4 service. Qf i gh ' .i ,

d s'/3 &() '

j 16. Scaled sources ccntaining licensed raterial shall notTe opened. -'

t1 . .- s  ! r.- ,

4 17. In lieu of using the conventicnal rediation caution colors (magenta or purple on 4' '

! [4 yellcw backgrcund) as provided in Section 70.203(a)(1), Title 10, Code of red:ral i Mulaticns, fort 20, the lictntee is heri.bj authorited to label detector cells ed A 3;'l cell beths, contair>ing licensed nterial end used in gas chroratography dev bs, u p.

• l j ccnspicuously etched or starred radiation caution syrbols withcut a color r equire".+t.  ;

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D.2 4 1330 Docket No. 50-264 h*

Dow Chemical U.S.A.

ATTN: Dr. Larry W. Rampy Radiation Safety Committee Building 1803 Midland, MI 48640 Gentlemen:

This refers to the routine inspection conducted by Mr. P. C. Lovendale of this office on September 10-12, 1980, of activities at TRIGA Reactor Facility authorized by NRC Operating License No. R-108 and to the dis-cussion of our findings with Dr. Anders and others at the conclusion of the inspection.

The inspection was an examination of activities conducted under your license as they relate to radiation safety and to compliance with the Commission's rules and regulations and with the conditions of your license. The inspection consisted of a selective examination of pro-cedures and representative records, observations, independent measure-ments, and interviews with personnel.

No items of noncompliance with NRC requirements were identified during the course of this inspection.

In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room, except as follows. If this report contains information that you or your contractors believe to be proprietary, you must apply in writing

' to this of fice, within twenty days of your receipt of this letter, to withhold such information from public disclosure. The application must include a full statement of the reasons for which the information is considered proprietary, and should be prepared so that proprietary in-formation identified in the application is contained in an enclosure to the application.

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Dow Chemical U.S.A. %EP.> 3 We will gladly discuss any questions you have concerning this inspection.

Sincerely, A. B. Davis, Chief

. Fuel Facility and Platerials Safety Branch

Enclosure:

IE Inspection Report No. 50-264/80-02 cc w/ encl:

Central Files Reproduction Unit NRC 20b PDR NSIC TIC e

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M I.ovFndale/jp Rill (

Fisher Davis Ridgway 9/22/80 ,

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j U.S. NUCLEAR REGULATORY COMMISSION  !

OFFICE OF INSPECTION AND ENFORCEMENT 1

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• Report No. 50-264/80-02 Docket No. 50-264 License No. R-108 i

l Licensee: Dow Chemical U.S.A.

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1803 Building I

Midland, MI 48640 Facility Name: TRIGA Reactor

] Inspection At: TRIGA Reactor Site, Midland, MI Inspection Conducted: September 10-12, 1980 Inspector: P. C. L vendgle 9/24/gp_

< 1 l Approved By: W. L. Fis er, Chief 9[o2.She Fuel Facility Projects and j Radiation Support Section

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l Inspection Summary j

Inspection on September 10-12, 1980 (Report No. 50-264/80-02) j Areas Inspected: Routine, unannounced inspection of radiation protection f

i and radwaste management program, including: qualifications; audits; training;

! radiation protection procedures; instruments and equipment; exposure control; posting, labeling, and control; surveys; notifications an,d reports; records j of effluents; radioactive waste; IE Bulletin No. 79-19; IE Circular No. 80-14;

a previous item of noncompliance; and transportation activities. The inspec-l tion involved 13 inspector-hours onsite by*one NRC inspector.

, Results: No items of noncompliance or deviations were identified.

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DETAILS ,, ,

1. Persons Contacted s',

• Dr. O. U. Anders, Reactor Supervisor ken,r*Mr.. K'.- J.. Kelly, Assistant Reactor Supervisor

• Mr. J. M. Macki, Senior Research Manager

• Mr. E. E. Bickel, Health Physicist i

• Dr. C. W. Kocher, Radiochemist Mr. T. W. Parsons, Health Physicist

• Denoter, those present at the exit interview.

2. General This inspection, which began with visual observation of facilities and equipment, posting, labeling, and access controls at 10:30 a.m. on September 10, 1980, was conducted to examine the routine operational radiation protection and radwaste management program. During this and subsequent tours, the inspector used a licensee survey instrument to  ;

monitor the reactor area. The highest radiation level, about 7 mR/hr, was found at waist level above the reactor pool. No problems were noted.

3. Previous Item of Noncompliance  !

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(Closed) Noncompliance (50-264/79-02): Failure of the Reactor Operations Committee to meet during second quarter of 1979. A " reminder board" is i now in use to prevent recurrence (Paragraph 5). [

4. Organization f The following changes in the reactor staff have been made since the last radiation protection inspection (October 1979): Mr. K. J. Kelly has been appointed Assistant Reactor Supervisor; Mr. J. M. Macki has replaced Mr. H. Gill as Research Manager in building 1602; )

Mr. E. E. Bickel has replaced Mr. T. W. Parsons as Reactor Health Physicist. No problems were identified.

5. Licensee Audits Minutes of the Reactor Operations Committee (ROC) and Radiation Safety Committee (RSC) meetings held since October 1979 were reviewed. Member-ship and meeting frequencies for both committees were as required in .

Technical Specifications I.2 and I.S.

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A As a result of a previous inspection,1/ the licensee instituted a i ,

" reminder board," which lists required due dates for ROC and RSC meet-ings so that they will not be missed.

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No items of noncompliance were identified.

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6. Trainingl D h ' i m nt Iz ici 9~ .-

o ,  ;., :. ; , iy u , ~, p y-Except for the reactor staff, no other individuals frequent the reactor 3 area. The reactor staff receives radiation protection training during annual requalification, which meets the requirements of 10 CFR 19.12.

Also, female employees receive additional training as outlined in Regulatory Guide 8.13.

I j No items of noncompliance were identified.

i 7. Radiation Protection Procedures l The inspector reviewed the procedures contained in the "TRIGA Operations j Manual," including calibration procedures for the area radiation monitor, continuous air monitor, and water radiation monitor.

• 4 No items of noncompliance were identified.

8. Instruments and Equipment

a. Portable Survey Instruments '

i j Operable and calibrated instruments capable of detecting beta, gamma, and neutron radiations are available at the reactor. Additional i

instruments are available from the Industrial Hygiene Office as needed. Records indicated that instruments are calibrated either j quarterly (ionization type and neutron meters) or annually (Geiger-

Mueller type meters). No problems were noted.

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b. Area Radiation Monitors Records reviewed indicate that the monitor was calibrated in March and August 1980. (Technical Specification G.3 requires an annual frequency.) The inspector observed a calibration check of this instrument and verified that the monitor's audible alarm was func-tional and that the alarm setpoint was correct. No problems were l noted.

! c. Continuous Air Monitor (CAM) i i

i The. inspector reviewed records of calibration and alarm setpoint checks performed since October 1979 and noted that the frequency l

1/ IE Inspection Report No. 50-264/79-02.

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ba was as required by Technical Specification G.3. The inspector observed a calibration check of this instrument an'd' verified that the monitor's audible alarm and visual alarms were functional and

that the alarm setpoint was correct. No problems were noted.

i No items of noncompliance were identified.

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9. Exposure Control

a. External Exposure

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i t *I The vendor's film badge reports were reviewed for the period October 1979 to date. The greatest whole body and extremity doses received 1 in CY1979 were 210 mrems and 180 mrems, respectively. No measurable j whole body dose has been received in CY1980 to date; the highest extremity dose was 40 mrems. No problems were noted.

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b. Internal Exposure i

The licensee has no routine bioassay program for the reactor staff

and relies on the CAM, contamination surveys, and pool activity i measurements to define any problem areas. The inspector reviewed l recordsofpheseindicators;noproblemswerenoted. A previous

inspection 2 noted that pool water was last analyzed for tritium in 1971. The licensee has recently analyzed the pool wateg for

tritium and found it to be less than approximately 1 x 10 pCi/ml, i their lower detection limit. No problems were noted.

t The inspector reviewed action taken by the licensee relating to i IE Circular No. 80-14 " Radioactive Contamination of Plant Deminer-l alized Water System and Resultant Internal Contamination of l Personnel." The only possible means of contaminating the deminer-a alized water storage tank is through a hose used to add makeup j water to the reactor pool. The hose is short enough so that it i

can not be physically submersed into the pool. It is unlikely i that contamination of the demineralized water tank could occur 1

via this route. No problems were noted.

. No items of noncompliance were identified.

i 10. Posting and Labeling The' licensee's compliance with posting and labeling requirements specified in 10 CFR 19.11 and 10 CFR 20.203 were reviewed.

No items of noncompliance were identified.

2/ IE Inspection Report No. 50-264/79-02.

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11. Transportation Ac_tivities c , .

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The licensee stated that~no radioactive ma'erial t has been received under'the TRIGA license since the last radiation protection inspection l (October 1979). The inspector reviewed records of radioactive ship-ments made since October 1979. - No problems were noted.

The licensee has not submitted a quality assurance program satisfying the requirements of 10 CFR 71, Appendix E and has no plans to do so.

No shipments of greater than Type A quantities have been made.

The inspector reviewed the licensee's response to IE Bulletin No. 79-19.

No problems were noted.

No items of noncompliance were identified.

12. Surveys The reactor staff performs contamination and radiation surveys monthly.

The Industrial Hygiene Office performs quarterly contamination surveys of the facility. Results of these surveys were reviewed. Only occa-sional low-level contamination is found in known contamination areas.

No items of noncompliance were identified. '-

13. Notifications and Reports - ' > ' -

A review of records and discussions with licensee representatives indicated compliance with 10 CFR 19 and 10 CFR 20 requirements.

No items of noncompliance were identified.

14. Radioactive Waste

a. Liquid Radioactive Waste The licensee stated that they do not release liquid radioactive waste from the facility. Any ifquids requiring disposal are l

solidified and shipped to a licensed burial site.

b. The facility has no gaseous effluent monitor, since calculations in the SAR determined that 10 CFR 20 limits will not be exceeded with continuous rabbit operation. The rabbit system is used only a few hours per week.

Particulate effluents would be detected by the CAM. No significant particulate activity has been noted.

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c. Solid Radwaste l l

Solid radioactive waste generated at the reactor facility is collected by the Industrial Hygiene Office and transferred (under l u NRC Byproduct' License No. 21-00265-06) to atlicensed~ disposal  !

. vendor. About one 55 gallon drum of waste is ' generated annually.

'The inspector noted that 'the licensee has been incinerating by-product material' (approximately 11 millicuries of carbon-14 and hydrogen-3 in CY 1979). The licensee stated that this practice has been conducted under Byproduct License No. 21-00265-06 for approximately seven years. The licensee further stated that the <

license did not specifically allow them to incinerate byproduct l material, but that they had interpreted the regulations to mean I that they could incinerate as long as the limits of 10 CFR 20 Appendix "B" Table II were not exceeded. This matter will be reviewed during a future inspection of Byproduct License No. 21-00265-06.

No items of noncompliance were identified.

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15. Exit Interview The inspector met with licensee representatives (denoted in Paragraph

1) at the conclusion of the inspection on September 12, 1980. The inspector summarized the scope and findings of the inspection.

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