ML20204H570
| ML20204H570 | |
| Person / Time | |
|---|---|
| Issue date: | 03/08/1978 |
| From: | Guinn P NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20204D654 | List: |
| References | |
| FOIA-98-341 1169, 34-00508-03-01, 34-508-3-1, NUDOCS 9903290103 | |
| Download: ML20204H570 (14) | |
Text
{{#Wiki_filter:-_ .-. .- --- . . - - - - - _ - - .- - . - - - _- -
. U. S. NUCLE AH acGut.ATO' CO' il5SION '""' - - %
*"~~ I /~
MATERIALS LICENSE
.Amendme.t No. 10 4 t .
318L * ~ri 14 .- YC.;r Files l l Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 9 438), and Title 10. Code of Federal Regulations. Chapter 1. Parts 30. 31. 32. 33, 34, 35, 36, 40 and 70, and in reliance < l .s statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee ' i receive acquire, possess, and transfer byproduct. source, and special nuclear material designated below; to use suc s y material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material to persons authoria I
;.L to receive it in acca,rdance with the regulations of the applicable Partis); and to import such byproduct and souri
- 9. material. This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 195 i
.7 as amended, and is subject to all applicable rules. regulations and orders of the Nuclear Regulatory Commission now .
g.hereafter in effect and to any conditions specified below. , W-~ ,-
- -- - - Licensee -'
In accordance with application dated D -
~
Septe:nber 7,1977,
~~ ~ " ~ ' ' ~ ~
71 1. Goodyear Tire and Rubber Company ; 7 .
. e~ 3. License number 34-00508-03 is amended i, - -
in its entirety to read as follows :
.: . 2. 1144 East !!arket Street U Akron, Ohio 44316 .
- 4. Expiration date
;.g ,
14 arch 31,1983_ k<- '. .; - Docket or i'- {. .
- 5. Reference No.
h(. 6. Byproduct, source, and/or - - , 7. Chemical and/or physical 8. Maximum amount that license p , special nuclear material :- form . may pos:.ess at any one time
~
- ' under this license 4 .- .
3 A.' Carbon 14' ~ A.' Scaled ' sources (Goodyear A. Not to exceed 5 y'j, ,'. , Beta Source Type C '
, nillicuries per pC *.' . - O+. ' '
Custom Made) . source i P..l . j"fi . 9. Authori::ed use . . .
- 4. - ,
~
h),.A.ForuseinGoodyearBetaGaugesDrawingNo. 343385 for weight measurement of ,, pliofilm, u - g@t ,- ; :. 3
-r . . . .
.u. , . ..
t,.-
-s CONDITIONS
~
@k.,.: . Akron, 50. 'Licensediaterial shall be' .used .. 4 only at Goodyear Tire & R
.,,,'.s..
. f.~
. Ohio. .,.
- r. , , , ,
. .- .1. u. _ . ,, .
M '< ll'. The licensee shall comply with the provisions of Title 10, Chapter 1, Code of k. b': "* * .- - Federal Regulations, Part 19 " Notices, Instructions and Reports to Workers; -
- g. Inspections" .and Part 20, " Standards for Protection Against Radiation."
- p. .. r, .
.w .. _, . . ..- .
~
w'F,. 212. Licensed ' material shall'be.used +* by,'
.. or under the supervision of, W. C. Stacy- -
r.f, Y
. or S. Z. Mansdorf.- .- . .
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%'.' maar# " - -' N 1-5.4%.l sh.J/as / h fe.$,stewie &C,v.a.1 JJ.% Ewald MA "H ^ *' N M8e E rekw A4 *.! d P'* I *-e * - 4 I4 : #
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9903290103 990322 PDR FOIA P,OST98-341 PDR l
1 l l l row eccaya o e U. S. NUCLEAR REGULATORY COh #N Page 2 of_ 3 Page l (645)
- l L
MATERIAIS LICENSE - l Supplementary Sheet Ucetue Number L1mM-m l
. l Docket or Reference No.
(continued) /cendnent No.10
+
e. g '13. A.(1) Each scaled source containing licensed material, other than Hydro;;en 3, j ls . with a half-life greater than thirty days and in any form other than gas ! 3 _ shall be tested for Icahage and/or contamination at intervals not to W'* p exceed six couths. In the absence of a certificate from a transferor indicating that a test has been made within six months prior to the trans-p fer, a sealed source received from another person shall not be put into y use until tested.~ - W - C - (2) The periodic leak test required by this condition does not apply to Q- . sealed sources that are stored and not being used. The sources excepted 3 - frcr2 this test shall be tested for leakage prior to any use or transfer { to another person unless they have been leak tested within six months (y; y;.- . prior to the date of use or transfer. y " B. The test shall be capable of detecting the presence of 0.005 microcurie 4 Y ' ,' of radioactive material on the test sample. The test sample shall be taken from the sealed source or from the surf aces of the device in which k; the scaled source is permanently mounteo or stored on which one might W expect contamination to accumulate. Records of leak test results shall W. ~
. be kept in units of microcuries and maintained for inspection by the Creni ssion.
."( -
s - f~ g.:
' C. If the test reveals the presence of'O.005 microcurie or more of removable contanination, the licenaec shall immediately withdraw the scaled source K, ', from use and shall cause it to be decontaminated and repaired or to be
$.f -
disposed of in accordance with Co= mission regulations. A report shall be
- 15. M -
filed within 5 days of the test with the U.S. Nuclear Regulatory Cocmission, y,; , Region III, Office of Inspection and Enforcement, 799 Roosevelt Road, Glen
. 2. Ellyn, Illinois 60137, descr.5bing the equipment involved, the test results, y', and the corrective action taken.
f.' - u- - CT s D. Tests for leakage and/or contamination shall be performed by the licensee i-
?- : or by other persons specifically authoriced by the Commission or an Agreement
.I- -
State to perform such services. p- , ~ ~,, k .
- 14'. Scaled sources containing licensed material shall not be opened or removed
; from the beta gauge by the licensee.
k_hfil5.' E Installation, relocation, maintenance, repai
.C I
, -!:g?.c13 vy ' devices containing licensed material and installation, replacement, and dispos
}'E SM ofonly sealed by Nuclearsources containing Radiation licensed material Developments or by other used pe aonsin devices shall be perfora specifically
'A 4.,F. .g ; .. ...
authorized by the Comission or an Agreement State to perform such services.
- C.b : ~ *. :. L i wwu-ex ,;e c.s,.au .a : s.a,a.-m:-- .- . W ~ - -
l l l
row ucana a U. S. NUCl. EAR REGULATORY CC .SiON Page 3 of 3 Pa; nm* MA11? RIALS LICENSE a l Supplementuy Sheet Ucense Number 3 u nsn hn- [
. Docket or l l Reference No. l l
Amendment No. 10 I e ! + CONDITIONS t. s .
.' (continued) .
I f 16. Except as specifically provided otherwise by this license, the licensee shall l j- - possess and use licensed material described in Items 6, 7. and 8 of this j license in accordance with statements, representations, and procedures l
~ ~ ' ~ ~ contained ~1n applications ~ dated Septemb'er 7; 1977T 0ctober 28, 1977 and
' - ~~
; December 21,.1977. ' l
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For th . Nuclear Regul Commissi i h- MAR 0 81978 ), [ 4.9 gl.e.@'. . [ .
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< / k- icensing Bra:
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. ' by Radioisotopes Division of Meterials and Fuel Cycle (n, .Date Facility Licensing
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. 't Wadiington. D. C. 20555
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4 .E-'-a*&m e 44-.--- R 4AC -*-A 4-= J s 44 m,_A. e4 m4laA,.3 4,e&a.A u-4 --*- En 4 qg, A - .e. m adakma a %* = ew. _,.J--- I I l 1 i INFORMATION FOR QUESTION 2.C. CONCERNING l THE BERTHOLD SEALED SOURCES l I i l f
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i ' Translation of letter of 6 1 i a PilYSIKALISCil-TECllNISC11E BUNDESANSTAl l' y Department 6, Braunschweig
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r D-33 B ra un scince i e '
% Messrs. 3 cd Thii ch , 1966
[E ~ ~ "If uch l e r ' & ~Co . 3300 B raun sclaei g i Trankfurter St r. 294 No. 18215.65 VI n/Ra 7 k r h Re.: Cs-137 industry sources'accordiny t o V: 0079, V: iM, M V: 0090, V: 0091, Y: 0091; y Examination in respect to % 44 of the Er ie Strahlen-schut:ve rordnung , 3 Your 1c tter Se/ sci or Oe mber zi, r9os g O
- 7 As regards the quest ion of terms for seal-test ings at Cs-137 f
h- industry sources o f the al...ve mottel s , t he Physikalisch-Tech-g nische flundesanstalt (PTit) says as follows :
- 1. Source Constructioq Compared with forme r mode is the new models have the acti ve h substance not as water-soluble salt but in the form of compact pearls out of Caesium-glass (Cs-137 as addition to l the glass smelt). The pearls are enclosed into welded stainless steel coatings (st eel lilN 4541) wi t h double w.il l s ;
l c only with sourecs of type V: 0091 the internal covering is h consisting of a hard soldered blonel capsule. k 2. I!xaminations g From 19.1. till 25.2.1966 continuous immersion tests have
' been undertaken at two pearls of appro 2 ime 0 whose act i-vities had been destinated to 95 mci, in orde r to find sepa- out the Cs-137 separation capacity fiom Cacsium glass (20 rate tests per sourco). A wa te r-me t hanol-mi x t ure (1:1) with 100 mg Cs-ions pei 1 hase served as immersion solution. Immersion In r between distilicil wate r was useil wi th some tests.
times have been between 17 and 91 hours, temperature was i 1 20-2S C. After a beginning deca) by nearly two dimensions , a timely constant activity emi.ssion I.appened after al out 7 days, l = sources and C,1 uCi[ day with being l uCi/ the othbr. j Atday bothwith one ofthe sources the activitywasbydnedimension higher with distilled water. 2 NE A 00f GO CD@ fD @. D R. _ B E RTH O LD
)
v e A ready-made source of type V: 0079 (engraving Q 325, activity ' about 12 mci) was set out 3 times to a blow :est, 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
.___._.> owl of 30.mm.. radius, which. fell.down freely _from 1.,5.m ,on_ .
l the source. Although the source has been remarkably deformed ' the following wipe and immersion test did not indicate any coming out radioactive substance (indication limit 0,2 nCi).
- 3. Final Decisions by bringing the radioactive sub: tance into the glass smelt 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 tests accor-() ding to 5 44 of the 1. SVO can therefore be set to 3 years, and - with an especially secure firm mounting into measuring e uipments - to 5 years, if the following conditions are ful . l 1 led :
a) The glass pearls mu t be thoroughly cleaned before coming into the coating. b) Within 6 months before hand 11r.g them to the applicant the covering of the sources must be examinated on leakage and contamination. The activity of the substance may not ex-ceed 0,01,uCi. The applicant must receive a certificate containing 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. d) A seal-test must be effected without delay when there is l llI suspicion on leakage. 1 1 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). j The handed in test subjects can be picked up.
's By order l
(D Weiss) i Enclosure bill of costs
. t (
, Translation of letter of l
PHYSIKALISCH-TECHNISCHE BUNDESANSTALT Department 6, Braunschweig Messrs. D-33 Braunschweig,
~ ~~~ ~~ ~ ~ ~~ ~ ~ Laboratorium Pro f . Dr . Berthold
- '-~~~
~~ 16th 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 44 of the "Erste Strahlenschutzverordnung" 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 6 level gaging equipments 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 (~s50 % Co,-v49 % N1). For each of the sources an activity with max. 200 mci is stated. According to the construction drawing no. P 2602-100, the radioactive material is e.ncapsuled into a stainless steel (V2A) container with a min, wall thickness of 1.5 mm. The container is screwed by meens of a worm plug and additio-nally welded by way of the Argon-Arc-method. Each source capsulo must be examinated on seal and suffi-cient decontamination of its coat before dispatch to the applicant. If the activity of the wipe sample is less than 10 nCi 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 5 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)
~
. J J Technical da':a sheet for applyint for a permission for
, handling ra,dioactive ma,t_crial ,(Co, 60 polpt sources)
Apulicant : Goodyear
- 1. Description of the radioactive material:
1.1 Radioactive material 1.1 :t-Na:ne of- isotope - - - - - -- - 1.1.2 Chemical condi tion : 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 15 mci Producer: Labor Prof. Dr. Berthold 1.5 Supplier : Labor Prof. Dr. Berthold 4 2. Description of the capsule and shielding;_ dose,, rate: , 2.1 Description of the capsule : The radioactive material is in a stainless steel capsule of 10 mm diara. and 13 rm length. The capsule is firmly closed by scre.:s and welding. All de tails regarding the construction of the capsule can be seen frora drawing no. P 2601-100.
- The capsule of the radioactive material is tested by the Physikalisch-Technische Bundes-anstalt (see enclosed certificate of the j
.. _ .- Physikalisch-Te r.hnische Bunde s anstalt Braun-schweig of 16.01.1974).
] 2.2 Description of 1 m the shielding: The capsule containing the radioactive material W - is housed in a lead shielding with a lockable channel for radiation eraission. The technical i data of the shiciding are the following : Outer diam.: 22 (cm) lleight : 24 (cm) h'eigh t : 81 (kgs) e f fe c t . shielding thickness: 9,7 (cm) s 2-
.nn-w e-. .. g..,.7.,. .- . n m .e- ...n.-+ . . ~ . --
' * ~
_: - JL/VyaFLn52fAfD 0 00 00 GD CD R G . n n o e- n=r u n e_n
l 2.3 Dedalls regarding the construction of the lead { 16 3 ding can be seen from the drawing no. PB 2197-~100 l 2.4 Dose rate in nRem/h 2.4.1 In 1 m distance from the nou shielded radioactive material: 20.3 - ~ - ' ' ~ ~ ~ ~ ~
~~~~ 7.4.2'In l'~m'di' stance frcm the shiel-ded radioactive material: less than 0.1 2.4.3 At the surface of the shielding: less than 8
- 3. Dpscriotiop of the, ,in,te,nd.ed_use :
The sources are parts of continuous level gaging equip-ments at a Werner and Pfleiderer reactor. , t
- 4. Protective equipn.ent, radiation protection neasures and measurinc instrur.ents:
The radiation channel of the shielding container is lockable.
- 5. Indicate where radioactive material no longer required
'. or dyino out remains:
.I y; Return to the collecting points for radioactive waste mate-
_.: rial of the individual government of the respective state.
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'd.i Date : 25.11.1976
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h.{ Lob,r h r. O ~'n * - Sold 5 na 7547 Y Jh )L,. s, Id) M,'r} Calmb,c mr 3;r' 2 160 l4{.i,'; j Telefon t .ul)3981 - ra6es 0724019 F En 1 sur,,es 1 x piece of drawing no. P 2602-100
>c AN.+q y 1 x piece of drawing,no.
(l.% 1 x piece of the certificate of the PTB w
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- WERNER S PFLEIDERER CORPORATION l Cables: WERNPFLEID WaldwickNewJersey 160 HOPPER AVENUE Telephone: 201-652-8600 WALOWICK, N. J. 07463
_..- _ WU - 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 Csl37 sources with 15 mci CD-60 sources. The new sources will also be made by Berthold. Promised 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 Wulz. 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: a) Technical data sheet for applying for a permission for handling radioactive material (CO-60 point sources). b) Letter from Physikalisch-Technische Bundesanstalt dated 1/16/74 plus translation. l c) Drawing #P-2602-LOO Source enclosure, d) Radiation intensity at ZDS-R800. Glif r{g ,3 jg76 I INDUSTRIAL HYGlEI'E
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- 2) i
, WERNER & PFLEIDERER CORPORATION
.. yo Mr . G . L . He s s The Goodyear Tire & Rubber Co. November 30, 1976
(, !v 5 e) Outpu+ voltage of LB3121 by using of 00-60 point source. f) Transportation shielding and changing of sources. l [
~We hope, thai the enclosed information is sufficient for your license extension.
~. l Very truly yours, ; WERNER & PFLEIDERER CORFORATION I
; d, / e Rainer C. Herter Manager Design and Systems Engineering RCH:ga cc: Mr. L. E. Shelley
'. Mr. J. House = Mr. H. Bennison N ew w +u I 4}}