ML20150F777

Matl/Byproduct License 34-00508-03 for Goodyear Tire & Rubber Co Is Amended in Its Entirety Per 770907 Application. Amend 10 Authorizes C-14 in Sealed Sources for Weight Measurement of Pliofilm.Drawings Encl

ML20150F777
Person / Time
Issue date:	03/08/1978
From:	Guinn P NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20150F395	List: ML20150F392 ML20150F777 ML20155A783 ML20155A797
References
1169, 34-00508-03, 34-508-3, NUDOCS 8006270043
Download: ML20150F777 (14)

Text

{{#Wiki_filter:-. " *" "' . S. NUCLEAR REGut.ATOR) CO ISSION ' + * ~W

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MATERIALS LICENSE e .Amsndec.t No. 10 3tc.~,.j u. n Ycar lines s Pursnant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93 438), and T.tle 10, Code of Federal Regulations. Chapter 1, Parts 30, 31, 32, 33, 34, 35, 36, 40 and 70, and in relience o: i statementa and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee t. receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use suei yy material for the purposels) and at the place (s) designated below; to deliver or transfer such material to persons authorizei

4 to receive it in accordance with the regulations of the applicable Part(s); and to import such byproduct and soure.

3. material. This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 19M

./ as amended, and is subject to all applicable rules, regulations. tad orders of the Nuclear Regulatory Commission now o g.bereafter in effect and to any conditions specified below. C'W W i- - - - - - - Licensee In accordance with application dated' T ~ ~~ ~ ~ ~ ?.i ). Goodyear Tire and Rubber Coapany ~ Septe=ber 7, 1977, "~~ ~ Gi'- ic- 'y

3. License number 34-00508-03 is amended in its entirety to read as follows :

, [ 2. 1144 East !!arket Street u iL Akron, Ohio 44316

4. Expiration date March 31, 1983 in b

.J - 'j. Docket or

5. Reference No.

f-p(. 6. Byproduct, source, and/or ,7. Chemical and/or physical

8. Maximum amount that license-W special nuclear material

? form ~ may possess at any one time s under this license l ^ [f. ,' A.' Carbon '14' .A.' Scaled' sources (Goodyear A. Not to exceed 5 J. ' Beta Source Type C mil 11 curies per T-' ri l.

• Custom Made) source N i.

9. Authorized use h{...i -

( A. For use in Goodyear Beta Gauges Dra', ring No. 343385 for weight measurement of $, 7 Q,..... P.ofilm. li ..+.. E CONDITIOUS c. g. .s~f,

p N.. f 10. Licensed material shall be used only at Goodyear Tire & Rubber Company, Plant C, l

7'*: Akron, Ohio.

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11. The licensco shall comply with the provisions of Title 10, Chapter 1, Code of fh ~

~ Federal Regulations, Part 19, "Notices, Instructious and Reports to Workers; Q'~,. Inspections" and Part 20, "Standards for Protection Against Radiation." g#. s, r ~

12. Licmsed ' material shal1 be used by,' or under the supervision of, W. C. Stacy NU '" -

or S. Z. Hansdorf. '7 i %..,' ".t i, ~ . f. 2, ' c,

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f FORh4 NKC.y,4A o U. S. NUCLEAR REGULATORY COM N Page 2 or 3 Page ,(6 75) MATERIAIS LICENSE Supplementary Sheet Ilcense Number 34-oMM-m Docket or Reference No. CONDITIONS (continued) Amendment No. 10 i .t. :

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13. ' A.(1) Each sealed source containing licensed material, other than Hydrogen 3, with a half-life greater than thirty days and in any form other than gas E

shall be tested for leahage and/or contamination at intervals not h 9.V " exceed six months. In the absence of a certificate from a transferor to K 2 < ---. - indicating that a test has been made within six months prior to the trans- ~ p fer, a sealed source received fron another person shall not be put into_._ O. ' use until tested.- - ~ ~ ~ kl.. 3 b; ~ . (2) 'Ihe periodic laak test required by this condition does not apply to m.. 7 . sealed sources that are stored and not being used. The sources excepted K~ . from this test shall be tested for leakage prior to any use or transfer N to another person unless they have been leak tested within six months I $[d!;,.,vde i h date of use or transfer. .g., ~.' Pr or to t e y_;. yn, 3 [. c yi M N. B. 'The test aban be capable of detecting the presence of 0.005 microcurie l O.', of radioactiva material on the test sample. The test sample shall be 1 i taken from the sealed source or from the surfaces of the device in which h ', \\ _ .s the sealed source is permanently mounted or stored on which one might tr '. d.. expect contamination to accumulate. Records of leak test results shall f . be kept in units of microcuries and maintained for inspection by the '[,y ]' f, (. Commission. s g + b.. ~ f: C. If the test revenis the presence of'0.005 microcurie or more of removable contaMnation, the licensee shan imediately withdraw the sealed source M. [ # . from use and shall cause it to be decontaminated and repaired or to be fyf - # - disposed of in accordance with Comission regulations.. A report shall be ter ..% : filed within 5 days of the test with the U.S. Nuclear Regulatory Ccenission, %;. ; r,;. f Region III, Office of Inspection and Enforcement, 799 Roosavait Road, Glen "0

• D ' ~. S. 4 Ellyn, Ininois 60137, describing the equipment involved, the test results, l

, ' and the corrective action taken. P 'Z l ; % : p r- <,.1 S-lE6 - ~ 5 % :? ._J-l D. Tests for leakage and/or contamination shan be performed by the licensee .': - ?.,l ;or by other persons specifically authorized by the Comaission or an Agreement . 's State to perform such services. N' *. '. . Q ~ ' O k.jg. _14. Sealed sources containing licensed material shall not be opened or remov j froct the beta gauge by the licensee. T

b. 7. J. L.. ;. .:

'.;15. Installation, relocation, maintenance, repair, and initial radiation survey of hh.h'of sealed sources containing licensed material used in device yOdevices containing licensed material and installation, replacement, and disposal. bw %.donly by Nuclear Radiation Developments or by other persons specifically ht-jpc. authorized by the Cocnis'sion or an Agreement State to perform such services. ~, W EN M 7E5it'* Q & st-w. J. s,.e m z w : w.i m.a : .z a.. ..~--~.>

nw cc.tnA a U. S. NUCLEAR REGULATORY CO N Page 3 of 3 Pag

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MATERIALS LICENSE Supplementary St.eet Ucense Number 3umnq nq Docket or Reference No. Amendnent No. 10 L COL'DITIONS

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16. L; cept as specifically provided otherwise by this license, the licensee shall j-possess and use licensed material described in Items 6, -7, and 8 of this

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A d O O 6 *. I i l l l l INFORMATION FOR QUESTION 2.C. CONCERNING THE BERTHOLD SEALED SOURCES

(.m r m) G) ^ f e v i Translation of letter of 6 Pl!YSIKALIScil-TECilNIScilE BUNDESANSTAI.T Department 6, Braunschweig h D-33 Braunschweig i Messrs. ~ ~ ~~1fuchler &~Co. avJ 71aich,'1966 E 3300 B ra un s chwei g J: [ Prankfurter Str. 294 No. 28215.65 VI it/Ra E r) Re.: Cs-137 industry sources' according t o V: 0079, V: vos, E V: 0090, V: 0091, V: 0092; Examinution in respect to s 14 of the Er: ie Strahleii-I7 schut:re tordnung, O Your ie tter Se/ sci of Oc i ohe r 2 i, ions Y As regards the question of terms for seal-testings at Cs $ p Q industry sources of the ab.ive models, the l'hys i kali sch-Tech-nische llundesanstalt (PTit) says as fo i lows : p N

1. Source Constructico Compared with former mode is the new models have the acti ve substance not as water-soluble salt hut in the form of g

compact pear 13 out of Caesium-glass (Cs-137 as addition to the glass smelt). The pearls are enclosed into welded stainless steci coatings (steci lilN 4541) wi th double w ills ; only with sourecs of type V: 0091 the internal covering is consisting of a hard soldered klonel capsule.

2. lixaminations n

O From 19.1. till 25.2.1966 cont inuous immersi on tes ts have k~ heen undertaken at two pearls o f appro. 2 inin 0 whose act i-vities had been destinated to 95 mci, in orde r to find out the Cs-137 separation capacity fiom Caesium glass (20 sepa-rate tes ts po r soure"). A wa te r-me t hanol-mi xt ure (1:1) with 100 mg Cs-lons pei 1 hate served as immersion solution. In between distilleii water was used wi th some tests. Immersion f times have been between 17 and 91 hours, temperature was 20-25 C. After a beginning decay by nearly two dimensions, a tim. fly constant activity emission i..ippened a f ter about 7 days, being l uC1/ day with one of the sources and 0,1 uCi/[ lay with the othbr. At bothsourcestheactivitywasbydnedimension j higher with disti]Ied water. . L L A BO R ATO R I U M PR O F. D R. B E RT H O D

k h ~~ / Y A ready-made source of type V: 0079 (engraving Q 325, activity about 12 mci) was set out 3 times to a blow test, each blow being 1,5 mkp. For this test the source was fastened on a

round of soft wood or lead; the blow subject was a steel lowl of 30. nun.. radius, which. fell down freely ~ from 1,5 m on the source. Although the source has been remarkably dcfstmied

~ the following wipe and immersion test did not indicate any coming out radioactive substance (indication limit 0,2 nCi). i j

3. Final Decisions 1

by bringing the radioactive sub: tance into the glass smelt y the radioactive substance flowing off small leaks is noti-ceabic reduced and the danger of loosing larger quantities at a rough damage is reduced. Terms for repeated tes ts accor-ll ding to S 44 of the 1. SVO pan therefore be set to 3 ye ars, and - with an especially secure fi rm moun t in g into measuring + e uipments - to 5 years, if the following conditions are ful .1 led : a) The glass pearls mu"t be thoroughly cleaned before coming into the coating. b) Within 6 months before handling them to the applicant the 7 covering of the sources must be examinated on leakage and contamination. The activity of the substance may not e x'- ceed 0,01,uci. The applicant must receive a certificate containink the engraving of the source, examination method as well as date and result of the test. c) The sources may only be app 11cated with environmental con-ditions, granting the covering to 1e free of leakage. O d) A seal-test must be effected without delay when there is II suspicion on leakage. This statement is only for sources which correspond to the construction drawings at the Bundesanstalt in its essential features (physical and chemical condition of the radioactive substance, material-and wall thickness of the covering, kind of sealing and activity). The handed in test subjects can be picked up. s By order (Di Uciss) Enclosure . bill of cost 8

o ( Translation of letter of PHYSIKALISCH-TECHNISCHE BUNDESANSTALT Department 6, Braunschweig Messrs. D-33 Braunschweig, Laborato'rium Prof. ' Dr. B6rthold ~ - - ~ ~~~ " 15th~ January, 1974 7547 Wi 1dbad Postfach 160 No. 6.3 - 38491/73 60 Re.: Co-sources for level measuring equipments; reference in respect to 2(2) and S 44 of the "Erste Strahlenschut2Verordnung" of the Federal Republic of Germany Ref.: Your letter: Lohr/J of 18/12/73 with construction drawing no. F 2602-100 The source capsules manufactured by Laboratorium Prof. Dr. Bertholdfrtheutilizationat level gaging equipments 6 contain Co in a massive metallic form, according to the statement of the manufacturer, and that as a piece of wire made out of a Cobalt-Nickel-alloying (~-50 % Co,-v49 % N1). j For each of the sources an activity with max. 200 mC1 is stated. 1 According to the construction drawing no. P 2602-100, the I radioactive material is encapsuled into a stainless steel (V2A) container with a min. wall thickness of 1.5 mm. The container is screwed by means of a worm plug and additio-nally welded by way of the Argon-Arc-method. Each source capsulo must be examinated en seal and suffi-l cient decontamination of its coat before dispatch to the applicant. If the activity of the wipe sample is less than 10 nC1 the source is to be considered as encapsuled radio-active material according to @ 2(2) of the "Erste Strahlen-schutzverordnung" of the Federal Republic of Germany (first decree of radiation protection). In the opinion of the Physikalisch-Technische Bundesanstalt, seal tests according to 6 44 of the "Erste Strahlenschutz-verordnung" are unnecegsary if the sources are applied up to temperatures of 400 C. This statement is a replacement for the certificate of the Physikalisch-Technische Bundes-anstalt of the 29th September, 1961, no. 24320 VI B/Ra. Enclosure By order bill of costs (Prof. Dr. H. M. WeiB) ~, ~

Technical data sheet for applying for a periaission for h a n d li n g,ra,d i o a c t i ve m a,t_e r i,a l,,( Co,,,60 p oi n t sources) Applicant : Goodyear 1. Description of the radioactive material: 1.1 Radioactive raaterial i rl :t-Name of-isotope---- - - - 1.1.2 Chemical conclition : Co 1.1.3 Physical condition: solid aggregate condition (Co-60 wire) 1.2 Capsuled or uncapsuled form: capsuled 1.3 Quantity and individual activity: 4 piece (s)

1.4 Producer

Labor Prof. Dr. Berthold 15 mci

1.5 Supplier

Labor Prof. Dr. Berthold 2. Description of the capsule and shielding,;, dose,, rate : l 2.1 Description of the capsule : The radioactive material is in a stainless steel capsule of 10 mm diam, and 13 rra length. The capsule is firmly closed by scre'.:s and welding. All de tails regarding the construction of the capsule can be seen from drawing no. P 2601-100. The caosule of the radioactive material is tested"by the Physikalisch-Technische Bundes-anstalt (see enclosed certificate of the l . _.. ----- Physikalisch-Technische Bundesanutnit Braun-schweig of 16.01.1974). l 2.2 Description of the shielding: The capsule containing the radioactive material G is housed in a lead shielding with a lockable channel for radiation emission. The technical data of the shielding are the fo11pl ng : i Outer diam.: 22 (cm) Height 24 (cm) Weight 31 (kgs) e f fe c t, shielding thickness: 9,7 (cm) s

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/ \\ {J Qj 2.3 Dcuails regarding the construction of the lead (10 9 ding can be seen from the drawing no. PB 2197'100 2.4 Dose rate in nRem/h 2.4.1 In 1 m distance from the not shielded radioactive material: 20.3 .g. ..di'sdnce f rom tlie shiel; ~ ~ ~ ' ~ ~ ~ ' ~ ~~ ~ ~ ~ ~ ded radioactive material: less than 0.1

2. 4. 3 At the surf ace of the sitielding:

less than 8 Desc,r1 t,ipp of.t,h,e,,1n,t,e,nde,d_use 3. 9 The sources are parts of continuous level gaging equip-ments at a Werner and Pfleiderer reactor. t ( d. Protective equipic.en t, radiation protection measures and j tr.eni,uring instrurents : 1 The radiation channel of the shielding container is l lockable. l l 5. Indicete where radioactive material no longer required [. o_r_ dying,out remains: l y-Return to the collecting points for radioactive waste mate-rial of the individual government of the respective state. _., y l g l p: f[.,k p^"m ~ 5 ~ "" "] fi f: Date : 25.11.1976 1 ~ @rI Lob.r 'r

r. O ri '"

- hold -; td) .u 7517 7 y%,. . fi.f. Calmt.u.2r P.r' 2 Jgg'j 160 au pai ( - Tei. ton i r.6.a on4cis \\ yc'Nglg pnc,1osur,es, f drawing no. P l l 1 x piece o 2602-100 $l'p;.) ij 1 x piece of drawing.no. D 1 x piece of the certificate of the PTB L..<.'.,.v. e N.^ I I %; j ,i I fb w I

O O ~ WERNER & PFLEIDERER CORPORATION I Cables: WERNPFLEID WaldwickNewJersey 163 HOPPER AVENUE - Telephone: 201-652-8600 WALDWICK, N. J. 07463 .._..._ -. WV - Telex: 134 303 November 30, 1976 SPECIAL DELIVERY Mr. G. L. Hess Radiation Protection Officer Corporate Industrial Hygiene The Goodyear Tire & Rubber Co. 130 Johns Avenue Akron, Ohio 44316

Reference:

Your P.O. #82502 Nuclear level gauging systems for ZDS-R800 reactors.

Dear Mr. Hess:

During a telephone conversation on Monday November 29, 1976 between your Messrs. J. House and H. Bennison and myself, Goodyear agreed to substitute the presently installed 10 mci Cs137 sources with 15 mci 00-60 sources. The new sources will also be made by Berthold. Prondsed shipping date of the sources will be middle of the second week of December 1976 ex Germany. Customs clearance will be done by WPC. The transfer of the sources will be made by our Mr. Walter Walz. A letter from Berthold, stating that Mr. Wulz was properly trained will follow beginning, of next week. In respect to selection and sizing of the source Mr. Jack Kennedy from Ohmart Corporation in Cincinnati arrived at the same results. Enclosed is one copy of the following information: I a) Technical data sheet for applying for a permission for handling radioactive material (C.>60 point sources). b) Letter from Physikalisch-Technische Bundesanstalt dated 1/16/74 plus translation. c) Drawing #P-2602-LOO Source enclosure, d) Radiation intensity at ZDS-R800. Olit E EC, 31975 INDUSTRIAL HYGlEi E 1

1

~'

s ~ y !WERNER & PFLElDERER dORPORATION i ..i' 'to Mr. G. L. Hess The Goodyear Tire & Rubber Co. Jiovernber 30n19) $ f 4 e) Output voltage of LB3121 by using of CD-60. point source. f) Transportation shielding and changing of sources. ~We h'pe,'that the' enclosed information is sufficient for your license ~' o extension. Vety truly yours, 1 l WLdNER & PFLEIDERER CORFORATION i I OA. W T i-Rainer C. Herter Manager Design and Systems Engineering RCH ga cci Mr. L. E. Shelley Mr.'J. House Nr. H. Bennison l i S l' l l 1 / l L -}}