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tainers as described in 5(a)(3)(1) or 5(a)(3)(ii) | tainers as described in 5(a)(3)(1) or 5(a)(3)(ii) | ||
Drawing Nos. | Drawing Nos. | ||
l (ii) Cesium-137 in the form of cesium chloride encapsulated in I sealed sources that meet the requirements of special- I form as defined in 571.4(o) of 10 CFR Part 71 or in sealed sources constructed and inspected in accordance with Picker Corporation letter dated January 4, 1980. | l (ii) Cesium-137 in the form of cesium chloride encapsulated in I sealed sources that meet the requirements of special- I form as defined in 571.4(o) of 10 CFR Part 71 or in sealed sources constructed and inspected in accordance with Picker Corporation {{letter dated|date=January 4, 1980|text=letter dated January 4, 1980}}. | ||
The sources are to be packaged in secondary inner con-l tainers as described in 5(a)(3)(ii) Drawing Nos. | The sources are to be packaged in secondary inner con-l tainers as described in 5(a)(3)(ii) Drawing Nos. | ||
(2) Maximum quantity of material per package (i) For the contents described in 5(b)(1)(i). | (2) Maximum quantity of material per package (i) For the contents described in 5(b)(1)(i). |
Latest revision as of 14:06, 22 August 2022
ML20126B893 | |
Person / Time | |
---|---|
Site: | 07109011, 07105796 |
Issue date: | 03/16/1976 |
From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
To: | |
Shared Package | |
ML20126B888 | List: |
References | |
NUDOCS 8003210210 | |
Download: ML20126B893 (21) | |
Text
{{#Wiki_filter:_ _ - _ _ _ _ _ _ NW - rjocr.'nn CE AIIFICATE Os CC '.',r LI A.'.'C E - 4
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- For Padi: active f.' ' trials Pack spes
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- WM t.fai ce<iii.ui. Nvmeee ' i.ibt ne.ision no. 1.(c) P,o ,;. see,iif.carion No. i .e d r,; e s no i .rei Tc:ai a,o. r,;e, %a w
9011 1 USA /90ll/B 1 2 P { I
- 2. PRE AMB L E N.h. h 2.la) This certifiute is issued to urisf y Seriions 173 333a, j 73.334,173.335. acd 173 r6 of ee cecarte . ens of Tra srer:a .:n s8a:
IW@ gr. dovr. Y Ma:erials Pe;utations (49 CFR 170183 and 14 CF n 103) and Se:* ion 14G t Ca and 146-19 100 of the Oe,.ar tment et " 7.,,
'frans;odahon Can;ercus Cargoes Rsp!ations (46 CF R 146-149). a s a nie nd cf.
2.lb) p.: The rackagha and contents eser ted in item 5 bele.v. meets t'e safe:v s'andards set f erih in Sutw1 C of Title 10. Core of N' F ederal PrWahoas, rart 71. Pacia;,ng o f HMicactne A'atcria's for Tr a astert and Traas;or'ation of Aad c a:ti.e A*at erial UWee D.' Certain Conditions " > j. *g l 7.(c) Th;s certifiute does not re'ie.e the c:nsl;i.or ficen semphan:o ni:5 any rMuisesment of the re;..latsr s of the U 5 Ot&teent of w Transrottatin of Mher a:ptab!s scw!atory a; enc.es, inc!vd.ng e., go.ernirent of any country threw;S cr mic who 'r e ra;kNe je) i will be 1r a ns tc rt ed. Q Q {'.3 1 . bU 3, This cer0fi:.aie is iuved on the,bam of a Wety a .atys a re; ort of the package des.gn or appl :ation- 6 3.f al h e r ed b y (?!a m e a n d a dd e n): p/G
- 3. (d) Title and identificai;on of report or a:0';u t io n-Picker Corporation ,~ .6 1020 Lcodon F.oad Picker Corporation dated Septerter 25, 1973. M Cleveland, Ohio 6110 W.
3.rci coo ,i no.' 71-9011' %g 4 CC'.DI T 6c f.5 2,.g.
,e s F*y '.
This cas tdi;4'e is co w ;tional y;on tFe f lfilli^3 of the re:vire# rents Cf $wt;. art 0 of 10 CF R 71, as at:licat'e. and the cc @ti:ns sNcif:ed b Is a m s tele.v. id By
- 7. cewiat,en of raeka;:ng and Aviherited Consents, f.*odel Nur-5er. Fiside C' ass. Ctrer ConJitions, e a,w n f erenus: $
1.g. ) n. (a) Packaging M2
'11 .A It
- s. u (1) Model No.: E-MEH-00-00004 3%
(2) Description v b.R c_d. . An everpack that provides irpact and thermal protection for a teletherapy t@si head assembly. The cubical overpack consists of iaminated 2x4 hard.sood maple panels bolted together and covered with 16 Cage steel panels. $f. Peinforcing steel straps and angles are welded tocether and spaced to Q@ limit the openings between them to less than 6 inches. Skid runners are provided to facilitate fork lif t usage. Dinensions of the overpack are '@ 36"x42"x40.5" with a maximum gross weight of 4000 pounds. l ,%.n..t. (3) Drawings n[v..,.
.1 The packaging is constructed in accordance with the following Picker @
Corporation Drawings Nos.: D-MEU-00-00004, sheets 2 thru 10; with p. teletherapy head Drawings Nos. ; A-40254; A-10066; A-40063; A-40065; g.Q A-42209 ( A thru D); A-42208A; A-0067; A-42211; A-T22-86; C-3830-A; Y., A-42208 (A thru D); E-162545A, and E-18972A. kN: w- ! UI.b lt}
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I.s Page 2 - Certificate tio. 9011 - Revision tio.1 - Docket tio. 71-9011 @ jQ s.
- 5. (b) Contents $$
'f~['
- x. l (1) . Type and form of material .A 60 Cobalt sealed s'ources that meet the requirements .]{)
P f.l-of special form as defined in i 71.4(o) of 10 CFR ik Pa rt .71. The sources are to be packaged in a f3M secondary inner container (teletherapy head) as 6]y.' ' described in 5(a)(3) Drawings tios. (2) Maximum quantity of material per pacLage ' VS , ; 13,680 curies , with a radioactive decay heat load l not to exceed 200 watts. . .N, 6. U$ ! The package authorized by this Certificate of Compliance is hereby 'gh approved for use under the ger.eral license provisions of Paragraph df 71.12(b) of 10 CFR Part 71. ,
, [r,'I
- 7. Expiration date: December 31, 1980.
- r. g. '
RE F EREf1C E S f. 1.$ Picker Corporation application dated September 25, 1973. r&. Fft,-. l
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FOR THE U.S. fiUCLEAR REGULATORY COMMISS10f1 [
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Charles E. ItacDonald, Chief Wk Transportation Branch NN i Division of Fuel Cycle
. and lia terial Sa fety j'M@
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March 20, 1979 l Picker Corporation 6671 Eeta Drive . Cleveland, OH. 44143 l
SUBJECT:
L'ater Spray Test Conducted on Two (2) Cobalt Overpack Shipping Containers RE: Picker Corporation P.O. No. B67670 Herron Laboratory. Project No. L 4920 Over the period 7 February 1979 throcgh 9 February 1979, two (2) cobalt overpack shipping coatainers, asse bly nu=ber D-181361, serial nucLar 107 and assecbly nr,=ber D-181375, serial number 315, were subjected I to water spray testing in accord.ance with paragraph 711, section VII of IAEA Safety Standards, dated 1973. l
. TEST EOUIPl!ENT The weight of the two cobalt overpack shipping containers was reasured with a system consis ting of a Le Bow, codel 3124, serial nu .ber 714, load cell, with a 5000 lb. capacity and a BLR Electronic, Inc.,
rodel 120 C strain indicator. De load cell and strain indicator system were calibrated to indicate load in pounds. Calibration was perforced on a Ealdwin-Tate-Ecery electro-cechanical universal tes ting r.achine, type BTE-64, serial no. 6401264, with a 5000 lb. capacity. Read-out incorporated in r.schine is a Tate-Emery indica:cr with four ranges of 50, 200, 1000, and 5000
" lb. respectively, with N.B.S. traceable accuracy of + 0.5% of reading.
TEST PP,0CEDURE . l The water spray test was conducted in accordance with paragraph 711, section VII of IAEA Safety Standards as follovs:
/
HERRON TESTING LABORATORIES, INCJ / m >cm u 40 o . cm mso. c-c% . ., m .m % ,e ccssutuios *so w .c s,sct im : j i
/ ~. - _. ,_
1 Ecrron Project No. L 4920 Page ~ March 20, 1979
- 1. Load cell was connected between overhead crane and test sample. Saeple was lif ted co=pletely off the ground with the crane such that the entire weight of the sample was supported through the load cell. The strain in the load cell was monitored on the strain indicator and the weight was read f rom the es11bration data and recorded.
2 A spray nozzle was attached to the outlet of the water line to disperse the water approximately uniformly over the entire surface of the sample. The spray nozzle was then positioned so that the vnter spray impinges upon the speciuen at an angle of apprcxi=stely 45' from the horizontal.
- 3. The water was turned on and the vater spray was collected I and ceasured. The water flev was adjusted until the amount.of water collected per unit of ground area was approxicately equivalent to a rainfall rate of 5 cm. per hour.
- 4. Subsequently, sample was positioned under the water spray and oriented such that the greatest amount of surface area was exposed to direct water spray, as illustrated in Figure 1, Appendix I.
- 5. The conditions described in procedure steps 2 through 4, above, vere maintained steady state for_ a time period of at least one hour, 6 Subsequently, water spray was turned off and the exterior of the overpack shipping container was dried with com-pressed air and paper tewels.
- 7. Ic=ediately af ter exterior drying, the shipping container was reveighed using exactly the same cethod described in procedure step 1. This final weight was compared with the original weight of the container in procedure step i to obtain the atount weight gained due to
. vater absorption.
8 Procedure steps 1 through 7, above, were repeated three additional times so that each shipping container was exposed to the test paraceters twice. The resulting increases in weight were averaged for each shipping container. N. HERRONcosw.os m, ~ . e. o . m. _ c _ m . .. ,- TESTING .so mnseLABORATORIES mu - s
'ierron Troject ?:o. L 4920 ' Pa ge ,
March 20, 1979 TEST FISULTS Each cobalt overpack shipping container exhibited an average increase in weight of less than 20 lbs. HERRON TESTING LABORATORIES , INC.
$% ~hu e Alan Reitenbaqh, ~
Engin 6Eiln Technoloc s t
)
OQ11j P. Fe tability Eng . cering Manager AR/dvu
** - .w.-.c.=.,.y llERRON 'll.S TJNG L\BOR \IORil 5, INC. fi
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i l l FIGl'RE T View of Overpack Shipping Container During L'ater Spray Test 4-HERRONa,.- Tf ~5.nTING , _ c . LABOR \lOR un scs . .. *c ao . cau. u a we w n
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/i' .-.R p m n. . Ms. . e t oM P.!,C...*:.ER.,,X_-RAY MANUFACTURING ( I d,"l . . r , . m.i._ps sw s ec.m.n.,.s3i-m, .e,, ,4, , w..~.=-.. O , 'a. 6 g.m,,,,,,,.p, ., . ,, e pp ,_ m_ ~- . - . 3 l l [ , ' Form NRC618 U.S. NUCLEAR REGULATORY COMMISSloN I U 10 C R 71 CERTIFICATE OF COMPLIANCE For Radioactive Materials Packages ) l 1.(a) Certthcate Number 1.(b) Revision No. 1.(c) Package identification No, 1,(d) Pages No. iN o. Pages 5796 2 USA /5796/B( ) 1 1.(e) Tot 5
- 3. PRE AMBLE , i 2.(a) This certificate is issued to satisfy Seulons 173.3934,173.394,173.395, and 173.396 of the Department of Transportation Hazardous Materials Regutations (40 CFR 170189 and 14 CFR 103) and Sections 14G-19-10a and 146-19-100 of the Department of .
Transportation Dangerous Cargoes Regulations (46 CFR 146-149), as amended, t 2.(b) The packaging and contents described in item 6 below, meets the safety standards set forth in Subpart C of Title 10, Code of 1 Federal Regulations, Part 71, " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under 1 Certain Conditions." l 2.(c) This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported. I
- 3. . This certificate is issued on the basis of a safety analysis report of the package design or application-3.(a) Prepared by (Name and address): 3.lb) Title and identification of report or application.
Picker Corporation Picker Corporation application dated l , 1020 London Road December 19, 1974, as supplemented ! Cleveland, OH 44110 - 3.tc) Docket No. 4 CONDITIONS This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71, as applicable, and the conditions specified in stem 6 ostow.
- 6. Description of Packaging and Authorized Contents, Model Nurnber, Fissile Class, Other Conditions. and References.
! (a) Packaging (1) Model Nos.: 181375 and 181361 (2) Description 1 Overpacks that provide impact and thermal protection for teletherapy head assemblies or source exchange assemblies. .The cubical overpacks consist of laminated 2x4 hardwood maple panels bolted together and covered with 16 gage steel panels. Reinforcing steel straps and angles are welded together and spaced to limit the openings between them to less than 6 inches. Skid runners are provided to facilitate fork lift usage. Dimensions of the Model No. 181375 are 37"x40"x41" . with a maximum gross weight of 3,325 pounds. Dimensions of the Model No.181361 are 39"x39.5"x 48" with a maximum gross weight of 4,000 pounds, i 1 (3) Drawings . i The packagings are constructed in accordance with the following Picker Corporation Drawing Nos.: (1) Model No. 181375: 0-18375, Rev. G; C-181368, Rev. B; D-181369, .Rev B; and C-55156, Rev. B, with teletherapy heads Drawings Nos.; D-63790; C-46879, Rev. C; D-184713; B-184704; D-16424-E, Rev. D; l D-16423B, Rev. F; and B-T60A-547. < t t - ( b Page,2 - Certificate No. 5796 - Revision No. 2 - Docket No. 71-5796
- 5. (a) Packaging (continued)
(3) Drawings (continued) I (ii) Model No. 181361: 0-181361, Rev. D; C-181357, Rev. D; C-181356, Rev. 0; B-181390, Rev. A, with source i exchange assembly Drawing Nos. ; D-T60-478; B-13708-A; i B-37092-A, Rev. C; C-13707-A, Rev. C: B-14241A; D-T60-558; . and C-13709A or C-137098. ! i (b) Contents i f i (1) Type and form of material ' (i) Cobalt-60 sealed sources that meet the requirements of i special form as defined in 571.4(o) of 10 CFR Part 71. l The sources are to be packaged in secondary inner con- ! tainers as described in 5(a)(3)(1) or 5(a)(3)(ii) Drawing Nos. l (ii) Cesium-137 in the form of cesium chloride encapsulated in I sealed sources that meet the requirements of special- I form as defined in 571.4(o) of 10 CFR Part 71 or in sealed sources constructed and inspected in accordance with Picker Corporation letter dated January 4, 1980. The sources are to be packaged in secondary inner con-l tainers as described in 5(a)(3)(ii) Drawing Nos. (2) Maximum quantity of material per package (i) For the contents described in 5(b)(1)(i). 13,680 curies, with a radioactive decay heat load not j to exceed 200 watts. (ii) For the contents described in 5(b)(1)(ii). l 2,200 curies, with a radioactive decay heat load not to exceed 17 watts.
- 6. The packages authorized by this certificate are hereby approved for use under the general license provisions of 10 CFR 571.12(b).
l: 7. Expiration date: December-31, 1980. I a I . i i . j . Page,3 - Certificate No. 5796 - Revision No. 2 - Docket No. 71-5796 I i j i l REFERENCES l Picker Corporation application dated December 19, 1974. 1 i Supplement dated: October 17,1975; May 29 and August 15, 1979; and January 4, 1980. FOR THE U.S. NUCLEAR REGULATORY COMMISSION l b .[ b Charles E. MacDonald, Chief i Transportation Certification Branch i ! Division of Fuel Cycle and 1 Material Safety ! JAN 171980 I Date: 1 1 1 i l I I l l l 1 ..I l 10313 - i:}}