ML20236T710
| ML20236T710 | |
| Person / Time | |
|---|---|
| Issue date: | 11/30/1987 |
| From: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| References | |
| NUREG-0383, NUREG-0383-V02-R10, NUREG-383, NUREG-383-V2-R10, NUDOCS 8712020034 | |
| Download: ML20236T710 (654) | |
Text
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' Revision- 10 '
Directory of Certificates of Compliance for Radioactive Materials Packages Certificates of Compliance U.S. Nuclear Regulatory Commission Office of Nuclear Material Safety and Safeguards
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,Most documents cited in N RC publications will be avallable from one of the following sourcesi s W m
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W W L 1 h The'NRC Public Document Room,1717. H Street, N.W.1 '
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C a ' J & Washington, DC 20013-7.0824, R ,i 4 c, . . , . . . . , .. 3 , . , . (s . . il b3J The National Technical Inf'ormation Service, Springfield, VA 22161: 9 i , s .: x.,m .. . . . . . .. iAlthough the listing that follows represents the' majority of documents cited in NRC publicetbnsb
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L Referenced' documents available for inspection end copying for a fee fmm the.NRC Public Docu-ment Room include NRC correspondence and internal NRC memorands; NRC Office of Inspection l and Enforcement bulletins, circulars,L information notices,.inspectionLand. investigation notices; F
. Licensee Event Reports; vendor reports and correspondence; Commission papers; and applicent and i .
licensee documents and correspondence y . q 0'
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The following documents'in the NUREG series are available for purchase;from the GPO Sales i Program: formal NRC staff and ' contractor reports,'.NRCgonsored confonmos proceedings and : NRC booklets and brochuros. Also available are Regulatory Guides, NRC regulations in the Coals of +
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focinent Reputations; and NucAner Regulatory Commission issuences. ' ,
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Documents ' available from' the' National Technical information Service include NUREG 'neries : reports and technical reports prepared by other federel' agencies and' reports propered by the Atomic ' ' Energy Commission, forerunner agency to the Nuclear Regulatory Com' mis,sion. .. . Documents available from public arid 'special ' technical librariesiinclude all open literature items? such as books, Journal and periodical articles, and transactions. Feders/ #apister notices, federal and
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state legislation, and congressional reports can usually be obtelned fro'm these libraries. l Documents such as theses, dissertations, foreign reports and translations $nd non-NRC oonferwrum proceedings'are available for purchase from the organization sponsoring the publication cited; Single copies of.NRC draft reports are av'all'a ble free, to the extent of supply,'upon' written request to the Division of Information Support Services,' DistributionLSection, U.S; Nublear, Regelatory i Commission, Washington, DC 20555.
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l j Copies of industry codes and standards used in a substantive'menner in'the NRC royaletory process _ are 'meintainsd at the NRC Library, 7920 Norfolk Avenue, Betheede,' Maryland,'and are avalleble Ethere for reference 'une by the pubuc. Codes ad standards are usually' copyrighted snd rray be purchased from the originating' organization or, if they are American National Standards, fmm'the; 4
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' American National Standards Institute,1430 Broadwy,' New York',LNY 10018.' f 4-t x .p g t
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NUREG-0383 Volume 2 Revision 10 Directory of Certificates of Compliance for Radioactive Materials Packages l Certificates of Compliance Manuscript Completed: october 1987 Date Published: November 1987 1 Division of Safeguards and Transportation Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555 p~m
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FOREWORD This directory contains a Sumary Report of the U.S. Nuclear Regulatory Commission's Approved Packages (Volume 1), all Certificates of Compliance ! (Volume 2), and Sumary Report of NRC Approved Quality Assurance Programs j (Volume 3) for Radioactive Material Packages effective October 1,1987. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the U.S. Nuclear l Regulatory Commission. To assist in identifying packaging, an index by Model l Number and corresponding Certificate of Compliance Number is included at the l back of Volumes 1 and 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory. ; i Shipments of radioactive material utilizing these packages must be in accordance with the provisions of 49 CFR 6173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with a Nuclear Regulatory ,l Commission approved quality assurance program. Copies of the current approval l may be obtained from the U.S. Nuclear Regulatory Commission Public Document l Room files (see Docket No. listed on each certificate) at 1717 H Street, . Washington, DC 20555. Note that the general license of 10 CFR 671.12 does not j authorize the receipt, possession, use or transfer of byproduct, source or i special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70. Please note that not all packages have been generally licensed in accordance i with10CFR971.21(d). If a person desires to use a package which is not 3 generally 1? censed, please contact the Transportation Branch, U.S. Nuclear ! l Regulatory Commission, concerning steps that must be taken to obtain a general l license for the package. , I Comments which would make future revisions of this Directory more useful are invited and should be directed to the Transportation Branch, U.S. Nuclear Regulatory Commission. I i Transportation Branch ! Division of Safeguards and ! Transportation, NMSS ! U.S. Nuclear Regulatory Commission Washington, DC 20555 l i 4
y----------u-----------....-________,,,,_,,____,, i E Is"aS ' "" CERTIFICATE OF COMPLIANCE
'o crR " FOR RADIOACTIVE MATERIALS PACKAGES I b REvlSION NUMBER c PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES
[ t e CERTIFICATE NUMBER USA /0361/B(U)F 4 0361 2 1 l 2 PREAMBLE l a Tnis certificate is issued to certify inai tne packsoing and contents described instem s beio.. meets tne appiec.bie safety standards set forth in Titie io. Code of y Federal Reguistions, Part 71. "Packagmg of Radioactive Matenals for Transport and Transportation of Radioactive Matenal Under Certain Conditions " g b inis certificate does not ret.e's tne consignor from comphance witn any requirement of the regulations of tne U.S. Department of Transportation or other l l W .pphcabi. r.euiaiory agencies. inciudmo the covernment of any country inroven or into wnien ine package wiii be transported l 1 I I l
* '."PEEPlA's'**E'/*.*Na%.".' *** ' ' '" ^**"i E"E ANo'iEEElfTi$$?M"OMA #f" CATION ! U.S. Nuclear Regulatory Commission NUREG-0361; Safety Analysis Report for the Plutonium l l l Washington, DC 20555 Air Transportable Package Model No. PAT-1 g l E I N I e oOcxET NuMeER 71-0361 ! l I
4 CONDITIONS l Tnis certificate es conditional upon fulfillmg tne requirements of 10 CFR Part 71, as opphcable, and tne conditions specified below l l l \ 5 (a) Packaging ) l l (1) Model No.: PAT-1 l 1 l l ' i (2) Description i d I 4 A stainless steel contaipmen hvassql (designated TB-1) surrounded by a i i l stainless steel andgewesd beeipich'[ designated AQ-1). The contents I ; are sealed with,ingstainless steel prddygt can (designated PC-1) l
}l g inside the c a.inment vessel. y y The AQ-1 ovhpack is a right circular cylindk approximately 42-1/2 l 1 inches long by(24-1/2 inches outside diameter.bJ he walls of the ;
i, overpack Ydnsist of i I encased k'i' thin o d'ub)4 Ktainlessapproximately st Vdr6ms. 8 in$ef of grain oriented redwood T%endsofthedrums I aredoublyclosed ppe'r$est udting ele t and an aluminum I l q loaddigibuterpreg as gh heyedwood. l q appyd datpIy'8-1 inches outside l 4 TheTB1~96-3)Qnghetit3 length b d Ameters contahrimerk Mbe mi(hnum wall. thickness h I N of the vessel W Pod ~ Zinch; 7he i rior cavity of the i N vessel iM riht rc r' ~4 4 inc ' diameter, with I l l hemispherthal ends tihe vesje N by 1/2-inch diameter l q pasket knife edges and an bolts and (ot@ly sealed wjth;a pp y q; elastomer O' f) . (J y l e li l
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- 5. (a) _ Packaging (continued) l I
(2) Description (continued) I i The weight of the package is approximately 500 pounds. The weight of ly the TB-1 containment vessel, when loaded with 4.4 pounds of contents is approximately 41.7 pounds. l 1 I 1 (3) Drawings and Specifications 1 I The Model No. PAT-1 packaging is fabricated in accordance with the I , I drawings and specifications in Section 9.0 of the Safety Analysis l Report, NUREG-0361. l l (b) Contents l I (1) Type and form of material I l Plutonium oxide and its daughter products, in any solid form. The l 2 plutonium oxide may be mixed with uranium oxide and its daughter y ,
- products, in any solid form. 1 )
. t: I (2) Maximum quantity of material tper pahkage and additional permissible I I l
contents N,,7 r, [, . (1) Maximum,2.0 kg total radioactive materia,1, plus: maximum 16 grams y of water and 10 grams,0f polyethylene orspolyvinylchloride bagging g material. The maximum decay heat load of ,the contents may not p exceed 25 watts. s hd I u /;y ,. p I (ii) Mbximum 200 grams totalTadicait'ive material, plus: maximum one , gram of water, maximum 200 grams of metal canning material (in l l addition to the PC-1 product %an,' Drawing No.1024), maximum 64 h grams of aluminum foil. or, honeycomb. (in addition to the top p maximum 175 grams of glass and maximum n spacer,' 35 grams' Drawing No. polyethylene o'r .j1015)j p;olyvinylchloride The maximumdecay, heat. load;ofithecontentsmafbaggingmaterial. not exceed 25 watts. g (c) Fissile Class:
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- 6. The PC-1 product can (Drawing No.1024) and the top, spacer (Drawing No.1015) h need not be used when the ' contents include 20s curies or less of plutonium, n
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- 7. Prior to first use, each packaging shall meet the acceptance tests and standards f specified in Subsection 8.1 and Section 9.0 of the Safety Analysis Report.
- 8. Prior to each shipment, the package sball meet the tests and criteria specified
- in Subsection 8.2 of the Safety Analysis Report. j
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. The package shall be prepared for shipment and operated in accordance with the l procedures specified in Section 7.0 of the Safety Analysis Report. l 1
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n------------------6.-- - ____.,..... . ,,,,,,, , u.8. NUCLEAR REGULATORY COMMISSION l l wacronum mA conomons (conunues l l l ) Page 3 - Certificate No. 0361 - Revision No. 2 - Docket No. 71-0361 I l I I I I I ' a I i 10. The systems and components of each packaging shall meet the periodic tests and l l criteria specified in Subsection 8.3 of the Safety Analysis Report. l I I l 11. Repair and maintenance of the packaging shall be in accordance with Sections 8.0 1 and 9.0 of the Safety Analysis Report. I I I i 12. The packaging shall be designed, procured, fabricated, accepted, operated, i I maintained, and repaired in accordance with a quality assurance plan approved by i
' the Nuclear Regulatory Commission for this purpose. I I I
- 13. Through special arrangement with the carrier, the shipper shall ensure observance I l of the following operational controls for each shipment of plutonium by air:
i l I I q (a) The package (s) must be stowed aboard aircraft on the main deck in the aft- i i most locatji on that is possible for cargo of its size and weight. No other l type cargo may be stowed aft of the package (s). l I f (b) The package (s) must be securely cradled and tied-down to the main deck of I i the aircraft. The tie-down system must be capable of providing package I restraint against the following inertia forces acting separately relative i i to the deck of the aircraft: Upward, 29; Forward, 99; Sideward,1.59 ; i
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l @ R E(i n (c) Cargo which bears one 'of-the following h zardous material labels may not be l I ' l 1 i transported aboard an' aircraft carrying a pachape(s): R i Explosive @* % Non-Flammableks, l l' Explosive B' ( . Flammable. Liqui? ; I Explosive'C .4 Flammable Solid A l I Spontaneously Combustible I Dangerous When Wet 14 ) D_..xipi'e'ri Flammable(3Gas l i i Organic Peroxide
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( i ; . p. Qx y y4 , > l l l This restriction does not ' apply to azar u's material;-targo labeled solely y I as: c3 y. g 3 !(; yr ,7* a 4;2 y f Radioactive I
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' Irritaqt b I I l 8 Megnetized Mateirals >lkEtiologicAgen't' W ~y g l N 14. The package authorized by this. certificate is Aereby approved for use under the p general license provisions ofl10 CFR $7,1.32. "P 1, l e m r
,l 15. The package authorized by this certificate is hereby approved for transportation I gl l of plutonium by air. l N
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- 16. Expiration date: August 31, 1988. y I
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l MMMMMMMMMMMMMMMMMM-ulu----333333333m3333333gggggggggg, , NRC FORM GleA U.S. NUCLEAR REOut.ATORY COMMISSION I l psal CONDmONS (conthed) I I I Page 4 - Certificate No. 0361 - Revision No. 2 - Docket No. 71-0361 1 I I I I REFERENCES l I Safety Analysis Report for the Plutonium Air Transportable Package Model Number PAT-1, 1 NUREG-0361, June 1978. I I Sandia Laboratories application dated February 20, 1980. l
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4 FOR THE U.S. NUCLEAR REGULATORY COMMISSION l j i : I euAOs/ Charles E. MacDonald, Chief Transportation Certification Branch l l I I y Division of Fuel Cycle and l Material Safety, NMSS I I I Date: SEP 0 61983 I I I I I I s? r 0(fj g/- i l i 1
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- am CERTIFICATE OF COMPLIANCE I q w CFR " FOR RADIOACTIVE MATERIALS PACKAGES I l D REVISION NUMBER c PAOKAGE IDENTIFICATION NUMBER d PAGE NUMBER e. TOT AL NUMBER PAGES 1 a CERTWICATE NUMBER g 4888 8 USA /4888/B( ) l' 4 W P
N d PREAMBLE g a ini. e. tificai. . ...u.o to c.rtie inat r in. packaging ano cone.nt. o..crio.o m ii.m s e.iow. m..t. ine appiicani. av.tv .tanoero. ..i tortn in Tiii io. coo. I g of F.d.ral R gulaison., Part 71," Packaging and Tran.portacion of Radioactiv. Mat. rial" l e Tni. certtiicai. co.. noi r.i ... in. con igno, ,,om comphanc. wien any r.quir.m.ni of in. r.guistion ov in. u s o.oanm nt of Tranaponation or otn., i 1 l appiscaDI. regulatory agencie.. mcludmg tne government of any country tnrougn or into wnicn tn. package will b. tran. ported N q I N1 1 ll g 3 THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETV ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION R a ISSUED To thenw smr Ad*ess/ b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION
! Teledyne Energy Systems Teledyne Energy Systems applications j g 110 West Timonium Road dated April 26, 1985 and August 19, 1986, I l Timonium, MD 21093 as supplemented. I I Wl I W
I ] (! s 71-4888 c OOCKET NUMBER ' I I fj ll N a CONomONS Thi. c rtivicat. is conditional upon fulfillmg in r.quirement. of 10 CFR Part 71, s apphcabl., and tn. condition. pecified b. low I ll I i W. i R (! s 8 Nj (a) Packaging I R; d' I y (1) Model Nos.: Sentinel-25A, LCG-25A; Sentine P 258, LCG-25B; i I . Sentinel-25C, LCG-25C; Sentinel-25C3,-250,-25E, I and-25F I ij > ll Ej I Ni (2) Description I l R ' I N q Th'e packages are th'ermoelectric generators. The major components A q; include the main housing, tungsten shield, hou' sing fla'nge, and electrical l' connectorsi The approximate dimensions'and weights for,the various I Model Nos. are as follows: R N l l ' 1 fE! Model No. . Dimensions (inches) Weight (lbs.) l n l q Sentinel-25A,'LCG-25A '25 00 x 25? 3000 i d;; Sentinel-25B, LCG-25B ;25 OD x'25
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3300 > Sentinel-25C, LCG-25C ' ' > E 24 OD x 32 i 2000 N Sentinel-25C3- 24 OD x 32 o 1300 l Sentinel-25D 25 OD x 27 ' 3300 l g Sentinel-25E 25 OD x 34 4200 h g Sentinel-25F 24 OD x 32 1400 R-l M 1 (3) Drawings g l The packagings are constructed in accordance with the following Drawing ! l Nos: y l I i I I i 4 i I l ( I I I I 5 4 1 I a l I 1 5 ' i L_ _ _ __ _____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - .E l
s u mmm mmast a mmanmumm mu n aut um sma namt ummm mmmmJuu mm amuur m mmmm mum mm m mm - - = = l w r wm osa l i coNoliloNs (continued) UE ***M'" *** i I I I a i Page 2 - Certificate No. 4888 - Revision No. 8 - Docket No. 71-4888 g I I I h 1 I I l S. (a) Packaging (continued) 1 l e i (3) Drawing Nos. g I I I Model No. Drawing Nos, I i I I l All Models Isotopes, Inc. Drawing Nos.. 001-20000, Rev. E l , i g i 001-20001, Rev. F g i 001-20002, Ref. F l i 1 001-20003, Sht. 1, Rev. B i 1 l , o p B R EGjoJP8 coo 3 l l Sentinel-25A,V-10G45A Martin (Company Drawing Nos.: l l s N0013100/R,ev. A I i N0013108, t,Rsv. D I I @M 001-40000, Rev. A i 00 D s., Isotipes Inc'. Drawing Nos. : 4, / N i f% 'dh;t$k.
/~], 001;70024, Rev't t i
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,# \',001-10000,RevrB 001-70025, Sht{l,Rev.D l i
l ?1.:}A[ , _1ha.1'f 001-70033, Shts el & 2, Rev. A I I H (s g001-70036/ b I I g W1 p 9 , N '"I% p g" g,001-80005f ;;3 l
, t e y u ,, u 43 4 .- . j, ,a g i Sentinel-25B 7,LCG-250 % r >
Vy@%NI[ g i if3 d).; Martin Company-D'rawing Nos.: N0013200,Rev,0C 1 i 37 ;w . . g ,, s, . 001..40012 Ca I i
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'/h QW Isotopes,O"Ec. Orawing Nos.: l l
y t /) e 001-70024, Rev. C 001-70025, Sht 1, Rev. D g y l l @, w,.
,A, ./. 001-70033, Shts. 1 & 2, Rev. A I I ^ /v P 001-70036 I
{ i 001-80005 I I I l Sentinel-25C, LCG-25C Martin Company Drawing Nos.: i 001-40004, Rev. A {p l 001-70010 I i 001-70012, Rev. B I i 001-80004 I i I l Isotopes, Inc. Drawing Nos.: l i i 001010000, Sht 1, Rev. D & Sht. 3 p g 001-70009, Rev. D I I I
! Sentinel-25C3 Isotopes, Inc. Drawing Nos.: I l 001C10000 Shts. 1 & 2, Rev. D 001-70009, Rev. D l l g, i 001-70057, Rev. D s' i 001-70060, Rev. C I l l 001-40019, Rev. B 11 q
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u s wcaan nmAm cosmmsson ""." * *'** conomons (continued) Page 3 - Certificate No. 4888 - Revision No. 8 - Docket No.- 71-4888 l l l l Sentinel-25D Martin Company Drawing No. l 001-80004 i i Isotopes, Inc. Drawing Nos.: l 001010000 Shts. 1 & 2, Rev. C I 1 001-70036 001-70033 Shts. 1 & 2, Rev. A l 001-70025 Sht. 1, Rev. D i 001-70024, Rev. C i 001-40015, Rev. C 1 001-40006, Rev. B I [sd" Apes,Inc.DrawingNos.: I g- b$ Sentinel-2SE 0011?10000,* Shts. 1 & 2, Rev. E, & Sht. 3 l v 001-70039, Rev. C l 001-70025 ht. 1, Rev. D & Sht. 2 g h 001-70024, .C I g' eg . 001-40017, (h s. 1 & 2, Rev. D I b) g 00 06, Re'. B I 4/ 5 l Sentjnal-25F 1 '. f:NE I opes,Inc. awing Nos.: )
% 001F10000, Sht & 2, Rev. H* I N7 t '. /%L 001-70070, Rev.-y I I
H ,t%%- A01570060/ Revs g G ij hh - ]r{'Jp 1 TQ01 70009$ Rev.*0 l tfy4,,M i ; /l'001-40025,Rev$A i i
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j 1 (b) Contents Y $ g-, M*syg Q' l 3 (1) Type and form ,of material y, 4 , g (i) Strontium 90 an'a 'dbUbi fenc psulated in a Haste 11oy or i Uniloy fuel capsule which meet the requirements of special form I I radioactive material; or (ii) Model No. Sentinel-25F may have, strontium fluoride doubly encapsulated in a Haste 11oy or Uniloy fuel capsule, with a Haste 11oy l C-276 liner which meets the requirements of special form radioactive I material. I l (2) The maximum quantity of material per package l ; I 125,000 curies i I I I I I I l 7 l
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I Uh* ***U'^*"" i conoirsons ccontonveo) lE \ a I I Page 4 - Certificate No. 4888 - Revision No. 8 - Docket No. 71-4888 lyl I I I I I I l 6. A barrier (permitting the free circulation of air) must be provided with sufficient I i separation distance to ensure that the requirement of 671.43(g) will be met. l l t I 7. Eye-bolt shall be removed or covered during transportation to prevent their use i I as tie-down devices of packages. I I I l 8. The packages authorized by this certificate are hereby approved for use under l the general license provisions of 10 CFR 571.12. l I l I I 9. Expiration date: November 30, 1991. l l l t i R I qyREFERENEI$5 Q- 1 (j p I l l 26,1985i and August 19, 1986. l l Teledyne Energy Systems app [itchtib71s dated April Supplement dated: s I I Novembler3,1986. q) ' /'Q# R I I l N - FOR THE U.S. NUCLEAR REGULAf0'3RY +~ COMMISSION I D). - -< l hy,/ p Qi N'h l Tg ,'{t q-I I s (4 w a, . 8 vr i O I l i I , Charles:E..MacDonald, Chief .x i Wi'r;iTransportati6n- Ce' ratification Branch I I t-- 5 I c ,n~~ "DivisionW: Fuel,0ycle and
. y . ~ MateE alj$afety, NMSS)
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'h e 1 ll, ., ,.. . . . . . . . _ _ _ _ _ . . . . . . . . u . _ . _ ,. m m . . . . . . . . . . . . 3 I vsHC FCRM sts i a io CFR t' CERTIFICATE OF COMPLIANCE (Aat NUCLEAR REGULATORY '
FOR RADIOACTIVE MATERIALS PACKAGES , , , UMBER b RE ION NUMBER cPAC T F CA I NUMllLR ePAGE UMBER e TOTAL UM8Erk FAGE% # t 3 CdRTIF 2 PREAMBLE l a This certificate is issued to certify that the packaging and Contents described in item 6 below, meets the apphcsbie f atety standards set forth in Title 10, Code of Federal Regulations, Part 71,"PaChagmg and Transportation of AarHoective Material" , Il b T9tl CertifsCato does not reheve the Cons #gnor from Comphance w0th OPy r4quirement of the reguldflons of the U S. be.sartment of Transportation or otent l SpphC8ble regulatory agencies encluding the government of any Country through of into which the package WM be tran999fted ; I : f I y 3 TNtB CERTIFICATE 15 ISSUED ON THE BAS 16 OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DEBIGN OR APPLICAftON - a t$5uf D To mieme amt Aspess# b T4TLE AND l IDENTIFICATION OF REPORT OR APPLICAllON- : I s I i i General Electric Company j Ceneral Electric Company application dated . i l P.O. Box 780 November 19 4 1982, as supplemented. L I Wilmington, NC 28401 f 4 , r . L[ , e oOex TNui,iBeR ^ 71' . 4909 l d j 4 CONDITIONS . .s b' / W Tnis Conif Cai. is Cond.iionai upon fuifsinng ine,,eauiternents of 10 CFR Part 71, as apphCable, and the conditions specified tielow
\
R g s _N- f' i l g hj o] {s l y (a) Packaging (3 j h {,s g (1) Model Nos.: 'GE-21PF-1 and W-21PF-1 ~a , . A [I l g /,; f . M. X \ f - [: , l I (2) Description -
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Packaging as described )and constructedlin' accordance w'ith DOT' l: l l Specification 21PF-1'exceptiasishown in c J General, Electric; Company 1-i l i Drawing No. 769E237t(GE-21PF-1) - Sheet [Nos. I and 2. Rev. 3; or 1 l l Westinghouse Electri c'Corporati ont Drawing No.) 36&lEEQ01 ~ l' l l Il l 1 the 8"<x 2.5"? tie-down support [ch}annel may beEfrom 43'to 55 s ' b inche l and vent holes-irt 'the.exterjorishpilimay bessealed with' plastic plugs. 4 Maximum gross cnight; of"thb;patkag6 E gt gi
,.qw- 1s-8,600 ,;.i- pounds M,, ;
Wl I (b) Contents g
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Iy t p g 1 l ll (1) Typeandforhlofmaterial [* i f' Uranium hexafluoridei j , , .h,' p-8 ((f y p l yg - ; y,_ ,,,y. .- (l (2) Maximum quantity of mate"r'ial Mr paEkage and fissile class ll 11 In accordance with DOT Specification 21PF-1 (li 3
- 6. Prior to each shipment, the overpack gaskets must b inspected. These 1 gaskets must be replaced if inspection shows any def'ects or every 12 ll
] months, whichever occurs first.
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q ige 2 - C6 t'ficate s No. 4909 - Revision No. 7 - Docket No. 71-4909 Il
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/. I I 7. The fol'dwing conditions apply to the Model No GE-21PF-1 packaging:
I 1 (1) For'packagingswhichare'notstolwelid,thejointsbetweentheinnerand 1 l l' i outer shells (ends) and the side (end) panel moldings must be silicone l sealed. The inner and outer overpack mskets must cover side (end) panel l - y i molding joints (unless seal welded). 4xcept for joints covered by a glued ; I I down gasket, visually impct all silscone sealed joints and maintain in I I good repair prior to eac!. s' t!pment or outside storage (loaded or empty). 1 ; si (ii) Prior to June 30, 1985, all body seams' and joints for the inner and outer l i shells (ends) and the s,ide end) pavel poldings must be continuous welds. [ g! I Welding must be by a fusior((l preces'st i n tecordance with the American i Welding l 1 Society Code or Amer.jcergWeiety of Mechanical gineers' Code. ll l
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{ g The packages ruthorized)is%s of 10 CFR 671.12.y; Qis certificate are hereby'app thegenerallice,nse(p;v l l ! 9. Expiration date: M enber T . 1987. - y
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; .3 PREFERENCES
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l 4eneral Electric Compt (y aprPcation ida'ted November;191 1982. g; {? y n, 1N y " -"y,ji!. y. C[>
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; A Supplements dated: SeptemberJ3,1983;,~and [ebruary?15'and May 2271984. 3:
i U1 ffy b. ;) } ( ) f ( b X .O l gf. Westinghouse Electric Co(/gyporationl supplement dated: July ~20and;$ovember 21, 1983; f 1987.;[. 4 g hy'4},Q i lll ( g-l$ and March 30 and April (3 ( & < a- ll J, 2 g, gNuclearContainers, Incorporated'supplementdated: August 22,/1986. y: W' @ u '/ o %g; k FOR THE U.S. NUCLEAR REGULATORY COMMISSION k! l l f 'h/ ) ,.- y gj p
! l Charles E. MacDonald, Chief C j ! Transportation Branch .il l, Division of Safeguards and I:
Transportation, NMSS
! aate: APR 22 IGN l / c[
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! 4.sm hac ronu sis U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE l i 10 CFR 71 FOR RADIOACTIVE MATERIALS PACKAGES Ill 1 a CERTIFICATE NUMBER D REVISION f. UMBER i C PACKAGE IDENTIFICAflON NUMBER O PAGE NUMBER e TOTAL NUMBER PAGES g ,'
5'
; i 4949 USA /4949/AF 1 2 g PREAMBLE M; a Tn, certincate is issued to cenity ina! ine packaging and contents described m nem s beiow. meets ineappiicabie satee r standards set fortn in Titie io code I
( of Federal Regulations, Part 71," Packaging of Radioactive FJh i als for Transport and Transportation of Radioactwe Material Under Certam Conditions " g I i Hl b inis ceniticaie does noi reneve ine consignor from compnance wan any requirement or ine reguianons or ine u.s o partment of Transporision or otner U apphcable regulatory agencies, meluding the government of any country througn or into which vne package will be transported. I l El I .
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( United Nuclear Corporation United Nuclear Corporation application dated I l Nlj Recovery Operations October 4,1979, as supplemented. 1 Wood River Junction, RI [ 02894 l
. cfoocktNUR E m-1949 I l! a Tnsa coNomoNs sv *i certificate is conditional upon fulfilkna tne reot,arepeetts of 10 CF A Part 11, as apphcable, and Ihe d@ons speciteed beiow ll l (a) Packaging O l I
nl K.* ./,, j) i I dj (1) Model go.: 'UNC-1484 . f- I s g, gl g! (2) Description f^ fr. gfD
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g gl i gl N ",%( Nj f e ,) f/- g 1 (j Containment vess61? consists ^o'f & 5 ,1/4f iD x 36-1/61ong and 3/8" I l N: thick" steel pipe"with welde'd_ bottom'p' late and bolted top flange closure. I i Cont'ainment vessel;is'cehtered and supported'withinla 65 gallon minimum I l [ gl 16-gage ste'el drum with-00T Spec,1ficatioq-17H : closure by plywood spacers, benelex,' tubular ste pokes, and, insulation material. l gl j l t n 'yy q $g 4 ,- % y j g; (3) Drawings (,h I j q dj ir z 4%A K' ,
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e ," I Wi Container is constructed'in,accordance'.with UnitEif Nuclear Corporation II l Drawing No 0-5005-8017, Rev; ') .' g l l l f (b) Contents Y l d , - ~ l i d,i (1) Type and form of material; 7' l Uranium oxide and compounds which will withstand a temperature of 750' l ! l g' i without pressure generatir.g decomposition. Density may not exceed l l 1 g 5.3 g U/cc. The theoretical-density-moderator relationship for "U g ! E compounds" shown in Figure 309 XXIV, dated February 6,1970, Docket No. I ! W 70-36, or in Figure 1.D.17 of the UK Handbook may not be exceeded, I 8 Uranium may be enriched to any degree in the U-235 isotope. The I ; lj maximum H/X atomic ratio considering all sources of hydrogenous material interspersed with the fissile material shall not exceed 0.5. [ l g g l 4 i i dj l I dl-H l i r l i if II E! 11 e n 11 1 W N I N __ ll _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ w
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*i Page 2 - Certificate No.'4949 - Revision No,' 5 - Docket No. 71-4949 I
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h Wi, N ki i M n ( 5. (b) Contents l:i p-Ni E! . Ni (2) Maximum quantity of material per package bj l d Ej J Total contents not to exceed 65 pounds with the U-235 content not to 'I fli g Hi exceed 25.4 kg. [j g j l Hj (c) Fissile Class 11 and III p: lR:. 8: F d (1) Minimum transport inaex to 2.0 i l 8 i lfq be shown on label, 4 for. JA Class L i * 'II C (m f J g/ ,
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8; (2) Maximum number.ot packages per ( g'f 50 A !g! ] shipment ,for,) Class III lN
$ ,, feg .
hi a g f 6. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 971.12. > (gj i 3 y(' 'y;'
- 7. Expiration date: Novembet 30, 1989- '/ ' .
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REFERENCES Ej ! y, s' 1 t / ga ) f United Nuclear Corporation application dated October .4, .1979. ~ I af Supplement dated: November 14, 1979. fl
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FOR!THE-U.S. NUCLEAR REGULATORY COMMISSION
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i WObwk 0 Charles E. MacDonald, Chief
'i lii h: i d Transportation Certification Branch gl; i Division of Fuel Cycle and Material Safety, INSS jl, l54 fDate:
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- CERTIFICATE OF COMPLIANCE llI '
l io can 7' FOR RADIOACTIVE MATERIALS PACKAGES I c PACKAGE identification NuMO&R a PAGE NUMBER e TOTAL NUMBER PAGES o nevision muueen l' i a canviricATs 4986 muusen 19 USA /4986/AF 1 4 h, N 2 PREAMBLE l
- a. This certificate is issued to certify that the packagmg and contents described m stem 5 below, meets the apphcable safety standards set forth m Title 10.j l of Federal Regulahons. Part 71,"Packagmg and Transportation et Radioactive Matenal?
l l l I I l p. Tnis cutificate does not reheve the consignor from comphance with any requirement of tne reguistions of me u s. Department of Transportation or other l apphcable regulatory agencies. meludmg the government of any country through or mte which the package wGi De transported i I I l
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l * '."si'5'e','Ji','"fl ., "'"' ' * **" ^*^'"."'E"s'E'li!cIfr*!$8='MrEAT oA'E*cATio= l l I i, General Electric Company General Electric Company application dated ! l March 1, 1982, as supplemented. l g P.O. Box 780 Wilmington, NC 28402 m ~. j l 1 - i e ooe=Er uuMeEa " 71L4986 c to is conditional upon fuihihng tne requirements of 10 CFR Part 71. as apphcable. and the conditions specified below 8 (5 N. - . (a) Packaging g' l y g (1) Mode 17 Nos.: RA-2 and RA-3 e# g y g . . A g ,
' I I (2) Description y '
I I Afdelassembly.an'd fuel rod shipping c'ontainer. Pack' agings are right l rectangular boxes consisting' of an outer. container of wooden construction p l and a metal inner container. separated byfcushioning material. l y u g
' , / - (l l The metal inner container isill-1/2. inches by 18 ;incheOy 179 inches sl l'
1 long and is-positioned within a Model' No. RA-3 wooden outer container approximately 30; inches by 31iinches, by 207 inches long. Cushioning is l f gi provided between the inner;andiouter containers by phenolic impregnated y honeycomb and ethafoam;'or equivalent. - Closure is accomplished by bolts, ll
/yl latches, or equivalent. A pressure relief (breather) valve is provided 0 l
E on the inner container, and is, set.for 0.5 psi differential. The total Rl weight of the packaging and contents is 2,800. pounds, {! (3) Drawings f ' Ilg, (1) The packagings areIonstrutied sin accordance with the following ! GE Drawing Nos.: l 1l t j 8 I 769E229, Revision 1. Model RA-3 Wooden Outer Container l l l 769E231, Revision 3, Model RA-3 Inner Container 769E232, Revision 3. Model RA-2 Inner Container [l l p 1 1 The RA-3 inner container may be constructed in accordance with Exxon I I Nuclear Company Inc. Drawing No. XN-NF-304.416, Rev. 2; or Westing- i l house Electric Corporation Drawing No.1685E66 Rev.1. l I ! (4) Product Container I Five-inch, Schedule 40, stainless steel, pipe fitted with screw type or I I flange closure. Container shall be vented in the event it contains l materials which decompose at less than 1475"F. l g
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CONDmONS (contmuod) UU** * * % #"'%*W' l l l Page 2 - Certificate No. 4986 - Revision No. 19 - Docket No. 71-4986 1 l I 1 I I 5. (b) Contents 1 I I l (1) Type and form of material j
! (1) U0 fuel assemblies with a maximum average U-235 enrichment of l 3.3%byweight. Assembly rods are clad with a minimum 0.029-inch l g
I thickness of Zircaloy and a maximum fuel pellet outside diameter l I of 0.416 inch. : Each assembly, made up of a maximum 8 x 8 square l l array of fuel rods, must have a maximum fuel length of 174 inches I i with a maximum fuel cross-sectional area of 25 square inches. I l I I I n 4 I (ii) UO fuel assemb11.es;witfCy Jr.arimum average U-235 enrichment of i i Assehbly rodsarg#plad with a mininum 0.032- l l 2.f% by weight inch thickness @?of Zircaloy and a maximum, fuel pellet o 3 i diameterg6f)0'.490 inch.. Each assemblyi pade up of a maximum 7 x l 7 square array of fuel rods, must have a maximum fuel length of l y i 174 itihes with a maximum cross-sectional'a'rea of 25 square l l fl" rA l inches 7 i I y) %- 5 l (iii) U0 / fuel rodsM: .th a maximum U-235 enrichment .of, 5.0% by weight. I i RodsarecladItith'Zircaloy IpcatoyT Inconel, lor stainless steel I i such that the ratio'of. clad toaf6el- cross sect 16 pal area be at l 1 east 0.26, and alliaximum f el" pellet outside diameter of 0.508 l e I I inch. Each.rodlaiust'hhis Tmaximumilength of 174 inches. The i N i I clad6ribedlin1 des rods'must'be 5 (a)(4))(( bundled {W (]~Tv' contained),in C the pFoduct contain I l l p '%f .d s p (iv) 00,yfuel rodsfiefthia. max M' b f.7 D U-235fenrichmenticf 6.5% by weight. l i Ro8s)are clad'with ZircaloyMciloy, Inconelfbr stainless steel a i I such that the ratio of clad to fuelicross sectional area be at i least 'Of26, and a maximum lfu'el pellet outside diameter of 0.508 I l inch. Ea'chrodmusthave'amaximumlength~of174 inches. The i i i clad rods must be bundled (contained) 'in the product container described in 5(a}(4) 444,p. [ y I n H t' b i (v) U0,, fuel assemblies with a maximum average U-235 enrichment of I p
~
3.3% by weight for assembly rods clad with a' nominal.0.030-inch I
- l. thickness of Zircaloy and a nominal fuel pellet outside diameter I i of 0.3565 inch. Each assembly to be made up of a 9 x 9 square i array of fuel rods with a maximum fuel length of 174 i' %s and a l g
I maximum fuel cross-sectional area of 25 square inches. 1 I = 1 I (vi) U0 fuel assemblies with a maximum average U-235 enrichment of I l 3.$% by weight for assembly rods clad with a nominal 0.030 inch I i thickness of Zircaloy and nominal fuel pellet diameter.of 0.3565 g inch. Each assembly to be made up of a 9 x 9 square array of l g fuel rods with a maximum fuel length of 174 inches and a maximum g p
.{
I I cross-sectional area of 25 square inches. Each assembly will l contain a minimum of six rods containing U0 -Gd 03 pellets with a I l minimum of two percentp3Gd 0 byweightloca$ed$ntheinteriorof , i the assembly (non-perimeter position). ll J i g .j l l J I I ) 14 I
' I
______________m________________________md
rureurmerurum: - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ US ""^n MUL M %""H I l I "R "~ " conomous toontinuw) l Page 3 - Certificate No. 4986 - Revision No.19 - Docket No. 71-4986 I I I I l I 5. (b) Contents (continued) I I I l (vii) UO fu crbsselassembliesinan8x8squarearraywithamaximumfuelsection l l 174 inches, and a maximum enrichment of 5% U235. Pellet and , . I cladding dimensions and nuclear poison specifications are to be l l 1 I l in accordance with the limits established in Section 1.0 of I I Attachment 2 to the General Electric application dated April 29, 1986. j , l
! (2) Maximum quantity of material per package !
I I escritied Th i ) I (1) For the contents (b){1)'(v f)g(b) 1)(1), 5(b)(1)(ii), 5(b)(1)(v), 5(b)(1)(vi); . ({ l ] l l Two(2) i assemblies.* l
! (ii) Forthcontentsdescribedin5(b)(1)(iii 5(b)(1)(iv): !
T C(I) hue'$' bundles.* I I (A. bundle%W. h n isidet nbd asTinTarra[nges'ent of rods which are either I , l i l
~
contained within jbroduct t i l ?
*Two short fuel, assemblies
% " 2 or bund
,may be substit7ted for a full [es/ b( I Ae i
length' f bundleh)uel assesnb1f "are shipped ehdjMig a'nd ov bundlerprovided-the(individ0h1 the tota);1ength"does not exceed assembi I I 174 inches. ! t4 C ' V 'O V! b<.t[$ky l 3b;fDJ#y (c) FissileClassM VQ3 n. . mpA N (9 Q3 g q
/,
n., - u 0q p <,p& g , , Each fuel assembly must be unsheathed or mus't be enclose'd[In an unsealed, I
)_
l 6. 3l l 1 polyethylene sheath which',may not extend' beyond the en'ds"of the fuel assembly. 4 The ends of the sheath ma'y<not be folded or taped in any manner that would ll l prevent the flow of liquids into oqout,of the sheiathed fuel assembly, g m n n 3 j Polyethylene shipping shims may be inserted between rods within the fuel assemblies i
, up to a maximum of 0.20 g H2 O equivalent per cubic centimeter averaged over the
" assembly. l
- 7. In lieu of the product container specified in 5(a)(4), except for UO !
?j with U-235 enrichment greater than 3.2% and for rods described (1)(v), in 5($) I fuel the clad rods must be bundled (bound with steel strappings at two or more I I
locations) with a maximum cruss sectional area of 20.0 square inches. The total breaking strength of the strapping must be 30 times the weight of the bound [ g rods. i I I l li I l ll l I [ 15 I f_______ _ ______________ _ ____________________________i
R I
" " ' ' ^ ' " ' " I I
coNomoNs (continued) ' '" ^ " " t % ^
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3 71-4986 I l)Page4-CertificateNo.4986-RevisionNo.19-DocketNo. l' I I g I 8. The maximum spacing between adjacent rods within the bundle must be 0.012 inch. l l The spacing must be maintained by the product container wall, metal strappings I i or peripheral metallic dunnage with a melting point greater than 1475*F within I i the bundle. l l 9. The package authorized by this certificate is hereby authorized for use under l l l the general license provisions of 10 CFR 971.12. I I I l 10. Expiration date: January 31, 1992. l j l I l I I i I REFERENCES y General Electric Company applica g at M c Supplements dated: March 15,k982;andApril 29, 1986. h($98{. i 1 A) Exxon Nuclear Company supplements dated: June 24, 1981; January)M
)(s l y
i l l February 9,1982; and October 3..and November 19, 1984. yJ J1 and y I f l 39 ' . . , . ,x b y ^ l i WestinghouseElectricCorporation;Agupplements dated;'; February 4,(1983 I I i March 27, 1984. L. 'p' J WO / fgf, ' I ,, "(\d% C (
-4 l
7 . FOR_h_ _HE3 A.U.. .Sg' 'NUC(. EAR REGULAT,O.R
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+?,' E Ch rles.E^.lMacDonald, Chief h/,'
l 'd , s Transpo'rtation~ Certification Branch y I e t Division of Fuel CycleJan'd
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' Materia'l Safety, NMSS' I I
, ' u- g l Date:
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I ' I l I I I I I I I I I 5 I I I I I I I i l l I I I I I I I I I I I I I I I 16 1 I I
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I NRC FORM ets U.S. NUCLEAR REGULATORY COMMISSION I i$m CERTIFICATE OF COMPUANCE I io CFR n FOR RADIOACTIVE MATERIALS PACKAGES I to REVISION NUMBER c PACKAGE IDENTIFICATION NUMBER a PAGE NUMBER e. TOTAL NUMsER PAGES 1 a CERTWICATE NUMBER g 5059 10 USA /5059/AF 1 2 i i >REAMsLE l n This ceri,# cate is issued to certsey inat ene packaging eno contents oescribed in item s below. meets theappiscabie safety stanoards settorin mTitle1o, coos i of Federal Regulations Part 71. " Packaging and Transportation of Radioactive Matenal." I b This certificais oo s not relieve ene consignor from compiiance with any requirement of the reguistions of ine u s. Department of Transportation or other I appi.cabie reguiaiory agencies. inciuomo ine government of any country inrougn or into wnien ene package wiii de transported i I 3 THiS CERTIFICATE iS ISSUED ON THE BASl$ OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DES,0N OR APPLICATION
! a ISSUED To (Aieme east Aditeses t TITLE AND IDENTIFICATION OF REPORT OR APPLICATION.
I Nuclear Fuel Services, Inc. application
; Nuclear Fuel Services, Inc.
i P.O. Box 218 dated March 27, 1981, as supplemented. E Erwi n , TN 37650 l 71-5059 o r*y r .
, 2. DOCM(T NUh48ER: f fn / ,
4 CONDITIONS ^
. 5~ s
- V/
This certificate es conosinonal upon fulfillmg the requhnemen'ts of 10 CFR Part 71. as appiscable, ano the, conditions spec 6fied below
, 3- , y, sg g 3 g (a) Packaging Q[) 4.e,)
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l (1) Model Nogya WS; Uranyl Nitrate Tank Trailer - f '/s~ j l u.aw . A..f, ..n \ s y s I (2) Desc ri p'ti on C Q, N /J' .q
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l k. , ;O\ l< Bulk liquid insulated? cargo tank trailer.(The;3,800 gallon" tank trailer is of all welded construction of type 304L stainless steel . b'
, . j 4 4. 1 ~r (3) , " OM.4 k , ; - - ' a.hfS ,/' 75 Drawi rig [~ .51 V MVT TtTidW .!? ?: -, =
The tank trailerfs, constructed n Accordance kith)0T SphMfication MC-312. W~ d r ~ .$l f[j% .f 7 . ,7
~
l (b) Contents .
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(1) Type and form of material.
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Uranyl nitratejin dilute acid soluti6n. The maximundU-235 enrichment in f the uranium must not exceed 20% by weight. Thew '235 content of the solution y must not exceed 10 grams per liter. \ I g
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CONDmoNS tconhnued) l Page 2 - Certificate No. 5059 Revision No. 10 - Docket No. 71-5059 l I h I I I I I
- 5. (b) Contents (continued) l I
I
! il) Type and form of material (continued) l l 1 1 The total uranium content must not exceed 357 grams per liter (1.5M). ;
I The~ l The HNO90c$nce$t (N0 )ha-6H 0 content ti$n will must not be normally 0.4M.exceed The50freezing weight temperature percent. of I l any3 of the solutions must be less than 72*F. i l l l l (2) Maximum quantity of material per package i I I I Not more than 45,600 pounds, net yeight of uranyl nitrate acid solution. 1 (c) Fissile Class 1
/ 111 i
Maximum number of,(pa,ckages per shipment Onef'
/<<!s l N. ' %
l g I I 6. O t i The solution must befat a temperature of 68'F or above.atythe time of packaging.
- 7. Priortodelivery'koa ahi.er for transport, for^ U-235 enrichments greater than I l
l l 4% by weight the4 shipper must ensure that at no, point along the proposed shipping t l l l route that the ' ambient temperature will 'be less than 32*F.11n, the event freezing h I weather is encountered the: administrative procedures and controls as specified p
! in Nuclear Fuel' Services, Inc. (application. dated March 27, 1961, must be complied i
% I I
with for all U 235 i enrichments.NJ fi' . d i O T me", l 'e f 1:p ,
+
# N q
The package must)be tested' and maintain'ediin 'a,ccor' dance with[Section 8.0 of the
^
i 8. l l I Application. () v 3, l g gj}{j a {m ? 2;. ; 7 . , j, A p p ,
\
I 9. The package authoYized by this. certificate sis hereby approved for use under the I ! I general license provisions of 10 CFR 571.12i *- V' S' I l f <;/ ;# , .s_ (",
- l e
l g i 10. Expiration date: Augustgl ,1991. ~ I s 4 - hl i 2 REFERENCES ; p i 4 p i Nuclear Fuel Services, Inc. application dated March 27, 1981. I I N
! Supplement dated: August 6, 1986. l l
l b l l FOR THE U.S. NUCLEAR REGULATORY COMMISSION g i I I i li Ac/A Charles E. MacDonald, Chief y l R Transportation Certification Branch I E Division of Fuel Cycle and I 1 I Material Safety, INSS lljiI
' I '
{Date: l W I la p
---.... ............. _ ..,_ _ ,,,,,,,,, - .- l1 l
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$"s$f""
to CFR n CERTIFICATE OF COMPUANCE FOR RADIOACTIVE MATERIALS PACKAGES } { 1 a CERTIFICATE NUMBER b REVISION NUMBER c PACKAGE IDENTIFICAllON NUMDER d PAGE NUMBER e TOTAL NUMBER PAGES j
<i 5086 5 USA /5086/B( )F 1 2
*l l b-l' PREAMBLE l l
- a. This certificate is lasued to certify that the packaging and contents described in item 5 below, meets the applicable safaty standarda set iortn in Title 10. Code j g of Federal Regulations. Part 71," Packaging of Radioactive Matenals for Transport and Transportation of Radioactive Material Under Certain Conditions."
l tt thss certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S Department of Transportation or other j ll R appiscabie reguistory agencies. inciuding the so ornment of any couniry inrouan or into which ine package wiii be transported. j i i q !B ' 1 IN g 3 THis CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSl$ REPORT OF THE PACKAGE DESIGN OR APPLICATION !g a PREPARED BV (Name and Addresar b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION 1 United Nuclear Corporation United Nuclear Corporation application dated N: 67 Sandy Desert Rd. April 22, 1980, as supplemented. l Uncasv111e, CT 06382 - V ' E o D (:
. c 'oOCat NUuBeR c b71-5086 N il e CONDITIONS % %: 'ff This certificate is conditional upon fulfillmg the requirements of 10 CFR Part 71, as applicable, and the conddions specified below !
,o ss <m i
( (a) Packaging U U I R:l & l ll 8 (1) Model p<o,: .UNC-2,600 ,.g-
/
'/~
ll g s ., (2) Desc ion \ j Q q The inner container is an 11-gauge tsteel box 96" Idig with a 25 square s h ! Ni inch maximum, cross 's'ection. The_ inner container is supported in a B, I 22-1/2" ID by 102". long .14-gauge ' steel drum by an insertable cage N J J formed by n'ine, 21-1/2" diameter by 3/8" thick steel, plates spaced i l i approximately 12" apart, with) a , channel fonned through the center of ll g! g! g the plates by angle iron.1iThetouter container closure is made with a I n R 14-gauge or heavier drum lid with 12-gauge bolt locking ring with drop I I Ell forged lugs, one of-which is threaded, having a. 5/8" diameter bolt. A. I I I{ , (3) Drawing [l ll E al g! The packaging is constructed in accordance with United Nuclear Corporation lip Drawing No. D-20354-6, Sheet 7. Revision No. 4. I j - I l 3 i (b) Contents R 11 i f (1) Type and fom of material [ 1 b l (1) Dry uranium-zirconium, uranium-aluminum alloys and compounds with I dll N densities not exceeding 1 kg U-235 per liter in the fonn of plates or sheets. Uranium may be enriched to any degree in the I 1 U-235 isotope. l l h (ii) Dry uranium oxide pellets encapsulated in stainless steel, aluminum ! I or zircaloy rods. Uranium may be enriched to a maximum 5.0 w/o i I in the U-235 isotope. I I I I- (iii) Moderated uranium-zirconium compounds with densities not exceeding I h g 1 kg U-235 per liter in the form of plates and sheets. Uranium may be enriched to any degree in the U-235 isotope. y p l-I I g 19 ; U _. 1
---- - - - -- -- - -- # - - - - - - - - - - - - - - ssir#w- - -- # - ,.n v.i, - - w
- j
- ka mmm l '" "
7 L' "***M'""" * !' conoirnous ccontinues> ' l? 1 ll Page 2 - Certificate No. 5086'- Revision No. 5 - Docket No. 71-5086 l 1 I j l h ! l ( 5. (b) (2) Maximum quantity of material per' package 4 R Ten kilograms U-235 and the net weight of the contents not to exceed-308 pounds. li (c) Fissile Class II and III !
! I q!
W (1)' For the contents described in 5(b)(1)(1) ! I E and'5(b)(1)(11) i
$l ! }
ll Minimum transport index to be shown 10.0 .l on label for Class I . ['{ l Maximumnumbepdofvp~aEkages per shipment k <j 1,0 l N for Class III e
#- l II Fortheco& ' (~) I f (2) ntents described in 5(b)(1)(iii)'
~
., 'M i
i gl g Maximum'pumbstif; packages per shipmentg. 5 4 l 1 for Class III ' N' N l
/, 'u , -
s < ! d:; g MN 'l l 4 N! 6 . The cross-secti6riof the inne'r contain~er 'shall beilimited to a maximum 19.6 l I square inches for, the contents specified,in 5(b)(1)(i) and 5(b)(1)(iii) where f the ratio of the weight of U-235,,to-the~ weight of-U-235.plus zirconium exceeds I
)
)
0.074 or the ratio of thef weight 'of.U-235 to' the~ weight .of U-235 plus aluminum ] l hl exceeds 0.22. - ~ij!i i Ci' - I g; j l ) Optional banding'of wooden Lblocks to' hu'tkide 0f container is not authorized. 7. gl 8. The package authorized by this ' certificate is hereby approved for use under the ! ] q general license provisions of 10 CFR 971.12. j i ll i Ni 9. Expiration date: May 31, '1990. l N f REFERENCES United Nuclear Corporation application dated April 22, 1980. I; i dl Supplements dated: May 8,1980; and November 6,1984. ; N. l FOR THE U.S. NUCLEAR REGULATORY COMMISSION jl k Ni CEAb Charles E. MacDonald, Chief l!
;l N- Transportation Certification Branch i l Division of Fuel Cycle and !
g, Material Safety, NHSS I l
- Date: May 22 1985 I!
l 20 I'
;I
-_--M_---__-------- -------m ------m------ q ;---m ----
I Mac FOMM eis U.S. NUCLEAR REGULATORY COMMISSION I ** CERTIFICATE OF COMPLIANCE I to CFR 71 FOR RADIOACTIVE MATERIALS PACKAGES D REVISION NUMBER c PACKAGE IDENTIFICATION NUMBER 6 PAGE NUMBER e TOTAL NUMBER PAGk i a CERTwiCATE NUMBER g 5088 4 USA /5088/B( )F 1 4 I l .d PREAMBLE d a. Thia certificai. 6. ..u.o to ceriity inat in paennoing ano contenti o crio.o in item s beiow. m..is inoappieceoie ssi.iy atanoaroe s.i fortn in Titie to, coo. q oi r.o.ral Reguistions. Part 11,Packagmg and Transportation of Radioactiv. Mat.nat" I ti Tni. c.riivicat. oo.. noi ,.n. in. con.lanor from compiianc. .,in any r.auir.m.ni or in. r.auistion oe in. u s o.parim ni or Tr.n.portation or otn.< W appocani. r.guiaiory ea.nc . mciuoina in. so..rn .ni or any couniry inrouan or mio -nien in. paca.o. . ii b. iransport.o. I 1 g 3 THis CERTIFICATE 18 ISSUED ON THE BA$iS OF A SAFETY ANALYSl$ REPORT OF THE PACKAGE DESIGN OR APPLICATION D TfTLE ANO IDENTIFICATION OF REPORT OR APPLICATION l R a ISSVED 70Imame sad Armessi N ' Babcock & Wilcox Company Rockwell International application dated l P.O. Box 785 September 8, 1980, as supplemented. Lynchburg, VA 24505 1 E m ;
)
4
<.1 i ,eoOCxET NUMBER : , _ 71.5088 I a CONomonS 'a l )
Tni. c.rtshcat. is conostionai upon fulfithng tn. r. Quit.m.t ,nts of 10 CFR Part 71, as apphcanie. and in. condition. sp.cified b. low. R l s > d f (a) Packaging h A l (1) Model, Nos . : -D34710-1 and D34710-2 , 9# , 1 ,% 4L _/ 4 l (2) Description 3J { c ,s s s ,, , .
, ],
., s i
Containment vessel tis 'a 12:250-inchi IDLSch'edule 20 sfeel pipe, 40 to l 410 inches long:for the Model No'. D34710-1 and 50 to Sleinches long for l g q the"Model No. D34710-2. with 5/16-irich; thick welded end. plate, and ! I bolted flange closure with leak tight gasket. ' Inner , container is l l centered andisupported in a!22;5; inch diameter steel drum with minimum i thicknessiofcl8-gage. iVoid(spacesWtween inner andtouter container I are filled with vermiculite, ) Gdoss weights of, the pa'ckage is 420 lbs 480ilbs y for, the ) Model No','D34710J12
-s
. . . ~ r g. and[q eg; forithe g Model"No. D34710-2.
lgl l (3) Drawings i C3 m om? ' th 1 g r
., i t
9 -
, s-1 Ei The Model No. 034710-1 packagin,g is constructed'in
accordance with the following National Lead Company Drawing Nos.: l D34710 Sheet 1 of)2. Issue 6, , ql! l D34710 Sheet 2 of' 2, Issue 2.1< i - g E I,
'l5 1
21 : E
----- EMdm m mmMm m m m MM mm WM MNMMMMMmMMMMM MmmM mmm mmMMM Mmm af
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- l conotrions tcontinued) '
11 I!
! Page 2 - Certificate No. 5088 - Revision No. 4 - Docket No. 71-5088 ! ;
l' ! ! f ll ^ l -(3)-Drawings (continued) ; , q C34711, Issue 3 C34712, Issue 4
~
E 8 C34713, Issue 1 i Hi > a si The Model No. D34710-2 packaging is constructed in accordance with the ll following National I.ead Company Drawing Nos.: gl I; l li Nl 8 C34799, Issue 1 034710 Sheet < [J,, D 1of2, f* CIssue a 6ngf3{f[ t ; C34712, Issue
- ly q L: '
g C34713. Issue (.4('% 1; ' . D35846T-1.Jssue 2, as amended by letter dated . February 8,1978.
'N w sh %~ (/
N' (b) Contents Y / '
'O I' >
M e ,, ^,' For the ModellNo. D34710-1 packaging: w
, p,
- i ;
lyl q
" .Q N (1) Type And form of l material
'f ) [4 -[8 g
(d . eq b H d 1 / i 2 y .., 6... .e .; 4 P; Uranium metal or' llo{y plats.typ'e udirradiated fuel elements with a a 7 s : L minimum active fuel' length of 23 inchesa Vranium may,be enriched to p: t Nl b: 93.5 w/o in the'U-235;v gjisotoige.TTTV" 7 *-a ' ' ' . N - av. t.&b6 q-i E - - , aw ,
+.2 peir! package . s/
g,i (2) Maximum quaniitNc mof{ mater 31 % > R1 % ~ f6&dwif. LRM;N'f Co ( ;' d! 2.025 kilograms' $235. Wh" s 5 e" [;;: di y n (c '" 3 For the Model NoiD34710-2 pac kaging':h,3('Ag['f dd j!b l llg' 'V m f dy^'[ h; g! (1) Type and form 'of' material " k: 6 g s./ H 4 4 < p; MTR-type fuel elements. 77 p y % I : f (2) Maximum quantity of material f { l 860 grams U-235. a W a I: a s ( p: l l! s a R ;
?
ll a ' ll $ nj I 22 5 i L___...___ ___________________ .. .v_________. um._____ i
.----------------------------------Ah----------------+
'Op t < w w U ' #'#'" ## # ~
oONDmoNs (continued) f l L 1 C 1 'Page '3 - Certificate No. 5088 -LRevision No. 4 - Docket No. 5088 ' Ip . 1 [ I 1 (c) Fissile Class. ( J; L L 1l .For the Model No. D34710-1 packaging: C l [ i l l Fissile Class II h i kl 1 1 Minimum transport'index to be shown on label Max kilograms U-235 per container Transport Index [ L 1; ; 1; ' 2.025 1.2 : 3
.1.0 4
F
. I t'.'400d//q7 0.9 li 1l d )\ h A gI p 1 ?700-A 1.100 0.800 ,A .
-0.8 0.7 [
,,%.) 0.500 (* ) ' O.5 r
%)
4 e -5 For the Model No. D3,4710-2 packaging: ~ ~
=
y C4 ~ m. e : ! 3 d Fissile Class' L
'M((. o.t g N %.
II ' .!q[) e <j ; m
, L
[ li Minimum transport indext % '} Maxgrams('U-235- Transport -
$ to be shown,on label .per container- 'Index h ' O.7 :
[]j3,4,1,$,860";.# J, t1 1 as Pc ,
.50.0 0.5
=
1 .a (~^ . I 6. For the Model NoCD34710-1[packagingi ? f ': c
) }y 31 The H/X atomic ratio considering all hydrogenous materials between, fuel elements within the inner container and the weight of the uranium;shall not exceed:
f i T C ! 1! ' Max kilograms U-235 [ j 1l per container Maximum H/X r ; li : i f y! 2.025 1.700 2.2 2.6 I 1l 1.400 3.2 f l 1 1.100 4.1 : l i 0.800 5.6 ji 0.500 ' 8. 9 0.350 10.4 g{ 0.290 13.0 g - 1, . : q\I 1 w . T 1! 5 ( : l 1 F m ! 1 1
----------------------------------y------------.ir------.
tummummmmmmummmmmmmmmmummmmmmumumaummmmm
* ' " " " U"****' ""~ * ' " ' '*
conolilous (contrnued) g Page 4 - Certificate No. 5088 - Revision No. 4 - Docket No. 71-5088
)
- 6. (Continued) r; 5:
For the Model No. D34710-2 packaging: E! F. The H/X atomic ratio considering all hydrogenous material between fuel elements l' within the inner container and the weight of the uranium.shall not exceed: p Max grams U-235 per container Maximum H/X lE. E 860 T 6.1
'800 pA [~{ { (J [ft6.5 (f ft
<+700 7.5 !;,
8.7 s C
*h(.600 500 10."4(5 lLi
[p 400 13.0 (.
- 7. The packages authorizeE b'y~this certificate is hereby.approhed for use under the g!
general license provision 30f110fFR671.12.
~
'i
, 7 f~ '
lt; g Expiration dateE' October 31,Ii99'O. fg s 7
- 8. - -
tp
- k. ~, < ' ltj
;ri
. .. . .: :\ l' ,Ci REFERENCES . pc '
h
, ; } . J .. --
I Rockwell International application dated.Se, dtember'8,1980. $! q c t.
' University of Missouri letter (Gooden to-Ladd) dated July 30, 1968; Idaho Nuclear fl Corporation letter (Fox to Tingey) dated April-.30,1968; and Oak Ridge National !gi Laboratory, Neutron, Physics Annual Progress Report period ending September 1,1958, lp; pp 34-36. ;Wi lh!
FOR THE V.S. NUCLEAR REGULATORY COMMISSION jl
, Di Charles E. ac onal Chief lkj j
Transportation Certification Branch fl Division of Fuel Cycle and h '; Material Safety, NHSS lp. a f j 6: Date: OCT17 W s l l 5 Pl lu; t n. 24
-- --- --- - - ----- - --- m m- ------m ----- - . . wgwes# ####gggg.
r
. ---- ,- - - -- - - aa-- - Easa aa - - - --- --- -- - - -- - -- - ---- - - -- -, $ NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION I re-am CERTIFICATE OF COMPLIANCE Il l so CFat T' FOR RADIOACTIVE MATERIALS PACKAGES h b REVISION NUMBER c PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER f i . CERTIFICATE NUMBER e TOTAL NUMBER PAGES f / 5149 5 USA /5149/B( )F 1 2 g PREAMBLE I bl l . This ceriivicare es issueo to certif y that the pack.ging and contenis described m item 5 below, meets the applicable safety standards set forth in Title 10. code I q or reder.i Regui.tions. part n. -e.ck.ging or Radioactive u iensis for Transpori .nd Transportation of R dio.cieve uaionai under certain condaiion. - l Il b ini. ceriivicaie does not reiievi, tne consignor from compi..nce in any requirement ov ine reguistions et ine u.s o.p rimoni or Transportation or einer I applicable regulatory .gencies including the govemment of any country through or ento which the package will be transported. 4 I N I ED ON THE BASIS OF A SAFETV ANALYSIS REPOf17 OF THE PACKAGE DESIGN OR APPLICATION g g 3 THIS CERTIFICATE a PREPARED BY INeme IS ISSUnd AdcessJ b TITLE AND lOENTIFICATION OF REPORT OR APPLICATION gl Babcock & Wilcox Company Babcock & Wilcox Company application i E. P.O. Box 785 dated September 20s 1979. I N Lynchburge VA 24505 i El- N
- ToOchtNuR E G f , P5"9 l 4 CONDITIONS \ \#' A This certificate is conditional upon fulfilling the req 6,erepeats of 10 CFR Part 71, as applicable, and he t. dgns specified below f'
d (a) Packaging T O l W %j (1) Model No.,: W 814A #g 7. d 1 I dj d (2) Descri3t' ion
%4 14 U '
d I [i b $Dh G SteeLeontainer asISescribedin Babcock &lWilcox Co$ny's application
.1' l
i (! s dated'5eptember 20st 1979._b.. ~ A? l P b~ I,,) g~f f // b I (b) Contents g Qi{3,y IV %.. '$.] gypp ,y
-4., r
,L
.s 4 3 l pV g I (1) Typeand, form %fghaterial. 5 j h g g 1
P .P Unirradiated fuel' cliister,Aq,LA MJ
#- d . qAdd l l
h; (2) Maximum qua f u f&.h fifh h l ll ty of materialjperipackage O' l One fuel cluste7 containing U-235 with ins ed poison fixture as l ll q specified in Babcockqk Wi,1cox Company s; application dated September 20s 1979. 'T yr ,k y u H! (c) Fissile Class III I N1 i f g Maximum number of packages per shipment or per railroad car Five (5) ! y d I 6 6. The package authorized by this certificate is hereby approved for use under the 1 general license provisions of 10 CFR 671.12. l l g 7. Expiration date: October 31e 1989. l E I i I Ni I Ni I
' l
. l l l g I
@ii 1 pj 25 1 1 dl d
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i i
% M___
Nl , N
@ CONOl TION 5 (continued) > ,
u Hi ! H ql 4 r Page 2 - Certificate No. 5149.- Revision No. 5 - Docket No. 71-5149 h i
=W i L N i El i Al hl W'
N! REFERENCE I d W'I g .! Babcock & Wilcox application dated September 20, 1979. j 4 1l l 1 H; FOR THE U.S. NUCLEAR. REGULATORY COMMISSION dl ll .- d; . g!
,b t
Charles:E. MacDona d, Chief y! g m.' Transportation Certification Branch lp B 1 - Division of Fuel Cycle and - gl 2v Material Safety NMSS Date: OCT 2 51984" l< e 1'm
'< ; ., i W -
'. 1
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l $\ <~ ' > l a!
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p l E; g. 7 ,c g Q p? - l gl 3 ;, .
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..... ____ _.......sw. ___mnmen-mmmmnmmmen- __ t U.S. NUCLEAR REGULATORY COMMISSION is-as CERTIFICATE OF COMPLIANCE %ll io CFR NRC 7' FORM 618 FOR RADIOACTIVE MATERIALS PACKAGES 1
b REYiSiON NUMBER c PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOT AL NUMBER PAGES 5341 kI a CERTIFICATE NVMBER 6 USA /5341/B( )F 1 2 l l N d a PREAMBLE er Tnis certificate is issueo io certify inai ine pecuag,no ano conienis oescriDeo en siem s beiow. meets ine apphcabie saiet y sianoaras sei forth in Teile io. coo. p
; of reograi neguiaisons. part 7i. -pacmaging of nao.oaci~e uateriais to, Transport ano Transportation of naaioacime Materiar unoer certain conoti ons.-
j b This certificate does not relieve the consignor from comphance with any requirement of the regulations of tne U.s Department of Transportation or einer 4. lE q
; apphcable regulatory agencies. enciuoing the government of any Country through or into whtCh ine package will be transported j 1 i )
i i j d 3 THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION f l a PREPARED BY (Name and Address). b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION l l 1 Babcock & Wilcox Company Babcock & Wilcox application dated June 23, . 1 P. O. Box 785 1967, as supplemented. ! Lynchburg, VA 24505 l
- c. o D NUMBER p, ( 'yn[/
@ 71-5341 1 iDOCI(ET j 4 CONDITIONS \ v Q p j This certificate is conditional upon fulfilling the requireynents of 10 CFR Part 71. as apphcable. and the conoWons specified below a s g < ._
! I 1 (a) Packaging f3 Q, '
l 1 u Au # l (1) Model No.: 'NFP-55
/j 7
' ? /g f ;
f jj >(2) Descr'iption
,y I
?t '
f // (~'; W t , A 4 . ( g; ,.3 Packaging as described;and constructed in accordance:with D0T Specifi-ll 4~ 1 ^ E cation 6M except: '(1) the' containment vessel is limited to a 5-inch t p Schedule 4Q steel ~ pipe with threaded / cap closure and welded bottom i p plated (ii and,'(iii))sthe i I ;f the outside sides anddrum ' ends;hUst-have of .the containment at'ledt 55-gallon vessel must capacity; have at ! d leastr71nches 'of, insulation WitO the radial clearance between the 1 l
)j insulation y and the, M
- r. outer the.1 E7-not ixc,eeding 3,
5/,8. Cinch. ! Q .s \ tr i 4 (b) Contents tg 7; 3 J M, v.j ,y( (1) Type and fokof material Uranyl nitrate or uranium oxides, ofiny enrichment in the U-235 l
%}j isotope, provided the H/U-235" ratio does not exceed 20, considering all sources of moderation within the inner container, i i !
4 (2) Maximum quantity of material per package t . Not more than 3.6 kilograms U-235 in a volume not to exceed 3.6 liters. !, t( 9 l 1 t"l t i l l $. i l y 4 4 W
# 27 l
1
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conosisons ccontinued) N 1. d 10
! l-Page 2 - Certificate No. 5341 Revision No. 6 - Docket No. 71-5341 [
(! E Mi K-E- t, Nl t! a
- 5. (c) . Fissile Class II and III l l
NI (1) Minimum number transport index to be shown on label for Class II 1.3' [ h g
$ I 8
d; (2) Maximum number of packages per 1: 40 packages I; i shipment for Class III
- 6. Pipe cap closure on the Schedu d.p e h 1(b6 ealed with teflon. tape.
- 7. The package authorize kf h s certificate is hereb afproved for use under the ! i M- I general license provisions of 10 CFR 671.12. El d: s c,s t
g y j - 8. Expiration date: October 31, 1989. >.
"l Idj p' i 4b(,h) g%
h C ij ll REFERENCE #[2 i
- s. _. ( 4 -
W! J ni cf r. (, y 3 -(f . l' I 8 u Babcock & rWilcox ' y; Comkany q%3 applic'atIo!'/'n p< ps ',
~~J h dated'8unei23, I h Supplements dated:
gj; ;( ,s 7dnf
,$1980.'<!N .>
l L 4 (DanuarE5i .197'0;3 l 7lM
, y, st 1 p O) ' M/dd . M o q FN E)6S".kUCLE REGULATORY COMMISSION f
, e4-
; s. , . ' 8 y' e h. i i
(,A[M > $m' f >(,'q, M f' hie 4: SQ Charles E. MacDona , ifh di s Transportation Certification Branch
;f kV ';
sh. Division of Fuel Cycle and Material Safety,19455 l q y 4 l ill Date: OCT 2 51984 n u ! Wl d pl i it- I ( I a! d; r I e' - I s i i i 4- 1 ( i l dl H 28 I
%j I l
4!..,..................__,...-______________________..!I
+
w_____--_________-___-___-_______
7--------------------------------------L----_---g-9eRC FORee Sie U.S. NUCLEAR REGULATORY COMMISSION 1 *= CERTIFICATE OF COMPLIANCE I
~ 10 CFR FOR RADIOACTIVE MATERIALS PACKAGES D REVISION NUMBER c PACxAGE IDENTIFICATION NUMBER d PAGE NUMBER 's. TrJTAL NUMBER PAGES 4 J
- 1. Cr "IEE NUMBER 3 USA /5362/B() 1 2 l
l' f 1 , ,Rausa
. this certific.t. i. ..u.o to c.riiiv in.i ine s.ckaging .no coat.ni. ne.cr'b.o m it.m s b. tow, m..t. in. .ppuc.bi...' iv .i.no.ro...i'orta m Tiii. io. coa. 1 1
1 or r.o.r.i Reguietson. Part 7i. -P.ck ging ano Tr n port. tion of Radio.ctiv. Materiai' l ;; li ! 1 o ini. c.ri,ric.i. oo.. noi ,.n.v. in. con.ignor vrom comon.nc. .iin any r auir.m.ni ov in. regui.ison or in. u s o parim.ni of Tr n.portation or einer J .ppuc.bi. r.gui.iory .g.nce . mesuomo in. governm.ni of .ny country inrouan or mio -nien in. pack a. wrii b. ir nspori.o Nl N 1 1 i l
) s ig,gi,,;C,4,rysgugoN inE ersas o, a sarErv 4Natysis,REpoa,1,o,.,1,s,Egna,c,E o,Esgogne, tic,4,rgN ,
i 1 U.S. Department of Agriculture U.S. Department of Agriculture application I dated October 17, 1980. I 1 Radiological Safety Staff fBeltsville,MD 20705 l 1 e ooCxErNuweER 71 5362 I o CoNDIT10NS I 1 int cen nc.i. i. cono i.one upon voit,inna in. ,.auer. ni o, io err pari ri. .. ppuc.bi.. no in. conoiiion. no.: vi.o b.iow 1 L Ts I i! I f
- (
(a) Packaging l l i # - I l I i 1 (1) Model No.: Natick Irradiator I I Ef N (2) Description l l , g The package is a cylindrical, steel-encased, lead filled weldment 29- 1 N 3/4" OD by 58" high enclosed in a double-walled impact and fire shield I I (overpack) 57" by 45" by 90" high mounted on a pallet 57" by 45". The j# stepped cavity is 9.56" ID by 8-1/4",12" ID by 27-1/2" and 20" ID by f l 11-5/8". The source holder (drawer assembly) is 9.48" OD by 46.625" y $ g with 9-1/2" shielding on bottom and 12-1/8" on top. A lead shielded 4 gj cask insert assembly 20" OD by 9.52" ID by 12.12" is installed at the lr L top of the cask and the entire assembly is held in place with a 1" lt li thick steel lid secured with twelve,1" bolts. A cask drain line is $' f sealed with a pipe plug. A 39" 0D laminated plywood plug fills the space between the top of the cask and the overpack. Plywood will be f j g: g positioned around the circumference of the irradiator for support. $ The cask weighs 16,000 lbs. I l , g([t 1 (3) Drawings l! t fp The packaging is constructed in accordance with Lockheed Nuclear l Products Drawing Nos. 442-20a?, Rev. 0; 442-2094, Rev. 0; 442-2096, I gj Rev 0; 442-2098, Rev. 0; 442-3002, Rev. 0; and U.S. Army Natick Research i I and Development Laboratories Drawing No. FE-81-16, Rev. O. I I I I E I ( l l I l n 1 I I 29 l 1
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4
' " ' " " ' " "'D' conomons tcontonued)
' ' ' in ' "> a 1 l J ge 2 - Certificate No. 5362 - Revision No. 3 - Docket No. 71-5362 l i i
- 5. (b) Contents l (1) Type and form of material Cesium 137 sources meeting requirements for special form radioactive material.
(2) Maximum quantity of material per package l 250,000 ci 1 6. rsA RFri The package authorized by thfecertificate is here,by approved for use under the i I general license provisions,.of'10 CFR 671.12. l
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- 7. Expiration date: Novem$r 30, 1991. Q l
- ?
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q:;p._ REFERENCE g': hl
. .. ; . ~_ . - ,/ <f.. O q U.S. Department of Agriculture application' dated October:17,1960.% i
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<l e s ... _ c ona a C ief l 1 Transportation Certification Branch I
'i , Division"of Fuel. Cycle and 1
- I
-, Material Safetf 3 NMSS I
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Date: NOV 2 51986 , V c( %,* l ..( l I ll il p i l l l l\
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-----------------------------------------------3 NAC FORM 818 U.S. NUCLEAR REGULATORY COMMIS$10N I
1 ce CERTIFICATE OF COMPLIANCE I to crR H FOR RADIOACTIVE MATERIALS PACKAGES D REvtSION NUMBER c PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER .. TOTAL NUMBER PAGES 1 s CERTIFICATE NUMBER g 5450 24 USA /5450/AF 1 5 g I q r PREAusts
- a. Tnia ceriiticate issued to certify inai ine packaging and contents described in tiem s beio.. meets tne apphcabie safety standards set forin m Titie io. code W
i of redersi neguistions. Port 71. " Packaging and Transportation of Radioactive Matenal? l b This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other I appiscable reguistory agencies,includmg the government of any cour try through or into which the package will be transported. I I I ( I
" I I * '",C',Mo*,^18 s . ,8fJ' .,," '"' *** ' ' '" ^*^"."R"E ANo',"o'E5",81/J,'U" ."OMN,0 c" A1,0N i Westinghouse Electric Corporation Westinghouse Electric Corporation application 8
l I P.O. Box 355 dated December 20, 1985, as supplemented. l l Pittsburgh, PA 15230 I 1 l l . eOded,,ddE!C71-5450 ! d CONOlflONS 5 .. Ed , i This certificate is conditional upon fulfilling tne requirements of 10 CFR Part 71, as apphcable. and the coeditions specified below { l g 5 (a) Packaging %)
.. . ?.
h(- l p l (1) Model'Nos.: m l r i
~
l f I RCC,'yRCC-1,~ RCCi2, 'RCC-3. and RCC-4. , %' " I I a, y 8 3 , 4 f.e ./ s n I y V .1 l i (2) D'scription 9 , ; [\%i Qm 's. 4 g I .e .N l , : :q l Steel fuel element cradle .a,ssembly consisting of a strongback and
~
l l l adjustable /fue17 element clamping assembly) shock mounted to a 14-gauge I I steel outer container by shear mounts. : Neutron 'absortier plates are required fof the contents as specified. Gross seight-for the RCC and l l RCC-2 is 6,300 lbs. , RCC ,1? anld,RCC-3 is 7,200 lbs. , an'd RCC-4 is 8,400 y i g lbs. ,~ , 1! ^ ;K t p 9 / - i
; q.- f g ;y . _. ,s s .
ss , ef- , e a I (3) Drawings iJ'- ^ '
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.i .g The palkagings are constructed 11ri ac' c ordance with the following l
l Westinghouse Electric Corporation Drawing Nos.': l g I , l For the RCC and RCC-2 packagings: 1596E24, Sheets 1 through 3, lh I I Sub 1; 1596E25, Sheets,1 & 2, Sub 1; 1553E31, Sub 1;. SKD-86008, I I Sheets 1 through 3, Rev. 2.~ l I I h; For the RCC-1 and RCC-3 packagings: 1596E24, Sheets 1 through 3, ! I Sub 1; 1596E25, Sheets 1 & 2, Sub 1; 1553E30, Sub 1; SKD-86008, g I Sheets 1 through 3, Rev. 2. I I I I For the RCC-4 packaging: SKE-85002, Sub 3; SKE-85003, Sub 3; SKE- 1 85004, Sheet 1, Sub 3, and Sheet 2, Sub 2; SKE-86004, Sub 3; SKD- l l 86009, Sub 2.
; y I I I (4 ) Fuel rod container reinforced 13-gauge steel box constructed in I I accordance with Westinghouse Electric Corporation Drawing No. C5650D55, a I Rev. 7. I I I I I 31 i i l--------------------------------y---------------J 1
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a---mk--mmmmmmmmmmmmmmmm.mmmmmmmmm---mmmmmmmmmmmmm mmmm, .
', d U ~""**"#*"* i CONDITIONS (continued)
\g l Page 2 - Certificate No. 5450 - Revision No. 24 - Docket No. 71-5450 g i ,
I ! 1
- 5. (b) Contents l I f (1) Type and form of material i 1 1 j (1) Uranium dioxide as Zircaloy or stainless steel clad unirradiated I i fuel elements. Two neutron absorber plates consisting of 0.19" I thick, full length stainless steel containing 1.3% minimum boron l or 0.19" thick 0FHC copper are required between fuel elements of g the following specifications: l l l I
8 14x14 15x15 14x14 15x15 17x17 16x16 14x14 Zr STg Zr- Zr Zr l Type rZrih(. 3ST Clads YClad Clad d (_@C lad:, Clad 7 Clad Clad ;
- g 'g ,
Pellet diameter .0.54k- 0.308- 1 (nom), in y.0 367. 0.367 0.384 0.384 0.322 0.322 0.3805 I 3 Rod diameter C 0.400- 0.3603 (nom), in , 0.422., 0.422 0.422 0.422 10:374 ),0.374 0.44 l Maximum fuel length, in 144
~ ;c.
+144, .120 ...
'/??
.12.0;f L 168 (7144 144 g
g Maximum rods / cR) -
'! ! /.$ ' b i I
element 180 ~204/ '180 '204 264 -235 s 176 Maximum cross 'C, '2 - a .- D Tm I section, ' -- M e I (nom), in sq' 7.82 8.4 U17817f8.4'.'8.4
, i *
%7.8 5
'7.98 l q Maximum U-235/ ,
g I element, kg 17.7 18.3 18.5?iE18.7 E" '
' 16.95 216.6 19.0 g o (144"L ) ? I 19.8< l lq (168"L) l Maximum U-235 g, enrichment, w/o 4.0 3.65 4.0 3.65 ^ 3.65 4.0 3.85 (ii) Uranium dioxide' as Zircaloy clad unirradiated fuel elements l 1 l contained within the Model No. RCC-4 packaging. Two neutron
;I l absorber plates consisting of 0.19" thick carbon steel are required ll
( between fuel elements of the following specifications: p ( h W 17 x 17 h i Type ZR Clad I d i l Pellet diameter, in 0.308 - 0.322 l g Rod diameter, in 0.360 - 0.374 N Maximum fuel length, in 168 %y N Maximum rods / element 264 ;> i N Maximum cross section, il 8 (nom), in sq 8.4 ll Maximum U-235/ element, kg 19.3 lg Maximum U-235 enrichment, w/o 3.55 gj g; 11 4 W 0 l 32 I N I.e-- ------- - - -- - -- - r- -- -r-rw-w-- w ssw -- - s+ ##w- -- , -- s- - . . s#o lII
t._, ______ ,___________________________ ... . _,
" "" 0 8 ^ U NU An ATORY COMMI5 MON coNDmONS (continued)
Page 3 - Certificate No. 5450 - Revision No. 24 . Docket No. 71-5450 (iii) Uranium dioxide as Zircaloy clad unirradiated fuel elements. Two ; neutron absorber plates consisting of carbon steel, 0.g35 inches in thickness, with 4 mils of Gdp3 0 (0.02 gm - Gdp30 /cm ) affixed to each side of the plate are rBquired between fDeT elements of the following specifications I 14x14 15x15 14x14 15x15 17x17 16x16 16x16 Zr Zr SST SST Zr .Zr Zr . ; Clad ! Clad Clad Clad Clad Clad - M Clad Pellet diameter 0.344- 0.308-(nom),in 0.367 0.367 LJE4 0.384 0.322 0.322 0.325 Rod diameter 0.400 0.360-(nom),in C. 02 KF 0.427 GOurzf,{s.0.374 0.374 0.382 Maximum fuel length, in 14 144 120 120 Y 144 150 Maximum rods / 8 . 236 element T 80 204 180 204
.f/pA 26 235 Maximum cross Q section,
' (nom), in sq 7.8 D. g N 1.8 8 .4 d.8 7.98 Maximum U-235//~
element, kg 22.1 M{. 21 - fy'i l23. $. i19.9 67 21.1 h AwM ,/ y (144"L) . l b ( . 23'.3 . I
% ,h1~66"L) j- F Maximum U-235 (f) 5 -
i s< f ,
- 4. T .3 4.2 '
enrichment, w/jo 4. h 3 4.3 4 hlMk i CQ (iv) UNnjum di t asIfk&1 oho !nless$teelcladunirradiated fust ds of t gSp fjcati sf' Qo Type SSTetJad Zr Clad Zr Clad Zr Clad ZrCladh2rClad. Pellet diameter (nom), h 4,.0:G44P0.308- ,.,Jf M in 0.384 0.322 0.3805 0.325 0.367 0.322 Rod diameter (nom), in 0.422 0.400- 0.360- 0.374 0.44 0.382 0.422 0.374 Fuel length (max), in 120 144 168 144 144 150 U-235 enrichment (max), w/o Note (1) 4.0 4.0 3.65 4.0 3.85 --- Note (2) 4.2 4.2 4.3 - 4. 3 --- 4.2 j j Note (3) --- --- 3.55 --- --- --- ( 33 [ 7EMEMMMMMMMMMMMMMW'HMMWWwwhwwwwmwgwgg nggggggggggggggg L_-__________.__.__ .. _ _ _ . _ _ . _ . .
na AA----dkA------------------------____-------------,q D CONDmONS (continued) U S NUCMG REGUuTO,w covwwoN l Page 4 - Certificate No. 5450 - Revision No. 24 - Docket No. 71-5450 l I I I Notes: l (1) Two neutron absorber plates consisting of 0.19-inch thick, full length stainless l steel containing 1.3% (minimum) Boron or 0.19-inch thick 0FHC copper are required g between the rod boxes. l (2) Two neutron absorber plates consisting of carbon steel, 0.035 inch in thickness, I with 4 mils of Gd 0 (minimum 0.02 gm 2Gd 0 /sq. cm) affixed to each side of the I plate are require $ btween the rod boxes. 3 l (3) Two neutron absorber plates consisting of 0.19-inch thick carbon steel are g required between the rod boxes. l I I ge I (2) Maximum quantity pf @t f aMr@ (i) For the 9h tents described in 5(bHif(/'i), 5(b)(1)(ii), and l 5(b) T) lii): l Twdhel elements. ,) (ii) th described in 5 ): 6 0 kilograms U-235. [Twoinnerlo (in rs colit31n n not.more tha p l
- 5. (c) Fissile Cfass xN [ wi - ,I 6.
W Fuel rods must@ closely kQ %
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s rod container pm no more than an l y j equivalent metal-to-mqt)squarei' pack artiallyiloadekfuel rod containers g must be fitted with a mi}nimum ofa rep $}1y spac$d blocks, of which the .g noncombustible pdtt d they are secured I must assure \that th, ion of th'e;tildc (&e rodshie'p'aintained(theime$ on no'm0Fe tharCan equivalent metal-to- i hod b V I 7. metal square lattice,j4within the fuel [orod 40'ntsiner. .o Each fuel assembly mustf be unsheathed or must be enclosed in an unsealed, l y polyethylene sheath which' will not extend beyond thd ends of the fuel assembly. p The ends of the sheath nust Mt be',fo]ded3r taped in any manner that would I prevent the flow of liquids into 'or out ofFthe sheathed fuel assembly. I I Alternatively, the fuel assembly may be enclosed in an elongated plastic bag or l sheath along its full length. At the bottom end of the fuel assembly, the bag y will be cut off or folded back to assure that the entire cross section of the lower end of the assembly is unobstructed. When folding is used, the portion of llp the sheath that is folded back will be cinched with tape near its end to hold it I in place, and the length will be such that when the assembly is loaded in the l ' q packaging, the folded sheath will be clamped in place in at least two grid locations. The top end of the bag may be gathered together and taped closed. [p l l However, the top end then will be slit on all four sides. The slits will run g
)
perpendicular to the axis of the assembly and will extend the inner distance .I J between the top nozzle pads and spring clamps (approximately 60% of the length ll of each side). The slits will be made in a plane near that formed by the top of I the pads and clamps. [ll ]
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I l 1 34
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$5 " "^ CONDITIONS (continued)
US NUCLE ~Ali REGUL ATORY COMMISMON l l l Page 5 - Certificate No. 5450 - Revision No. 24 - Docket No. 71-5450 1 I I I I I I l l 8. The package authorized by this certificate is hereby approved for use under the i < l general license provisions of 10 CFR $71.12. I I I l 9. Expiration date: July 31, 1991. l I I I REFERENCES l I I I Westinghouse Electric Corporation application dated December 20, 1985. I j l I i l Supplements dated: April 28, July 1, and July 21, 1986. l j l l l I Department of Energy supplement t Mjt{ l h FOR THE U.S. N E)RREGULATORYCOMMISSION I h l l l co b . 44f M-4 Charles E 4% chald, Cryigf l I forticertificatfon Branch I l g hy g Jrpnspor Tuel C I 1 i DWisfon fafNy,yclea@ 1 I h s f#ateri NMSS l l l Date: i r er 55 l l I U, t-ww[shr %m
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l ! ll 1 , I , 1 I I i a i i l ' l i l ' I I l i' I I I l l l I I g . l' l I 35 I I I I__-----__--_____________,e_w_-ww--_--____-__.____________,I . l
--__----------------------------------------s--y W mRe ponu sta U.S. NUCLEAR REGULATORY COMMISSloN I am CERTIFICATE OF COMPLIANCE I to crR n I
I 1 a CERTIFICATE NUMBER FOR RADIOACTIVE MATERIALS PACKAGES b REVISION NUMBER c PACKAGE IDENTIFICATION NUMBER 6 PAGE NUMDER a TOTAL NUMBER PAGES 5461 2 USA /5461/B( ) i I REauaLE e This certificate is tasued to certify that the packaging and con j 1 ents described m item 5 below meets the apphcable satoty standards set forth in Title 10. Code 3 P Of Federal Regulations, Part 71. "Packagmg and Transportatsort of Radioactive Material? lll l 0 This certificate does not reheve the consignor from comphance with any requirement of the reguistions of the u S Department of Transportanon or other E l apphcable regulatory agencies, including the government of any country through or ento which the package wHi be transported I , l' 3 TMs N flF CAT S BSUE ON THE BA$18 OF A 6AFETY ANALYSl8 RE RT OF THE PAC AGE 8 OR APPL CATI g I I g Oak Ridge National Laboratory Safety Analysis Report for Packaging (SARP) of I i P.O. Box X the Oak Ridge National Laboratory TRU Curium l i 5 Oak Ridge, TN 37830 Shipping Container, Report No. ORNL-5147/RI, 8 August 7, 1981 Revision. l h . A o$c./ETNde{Rf ' /7 , 71-5461 y I a cONomONs ., n> ' in,s cert f.cate . condit.onai upon fuivining the r.nuirements of io crn pari n. as appi.cabie. and the conoit ons .pecif.ed beiow l l ,
! (a) Packaging , I g
I es i (1) Model 'No:_ ORNL TRU Curium Shipping' Container. I i Gq CN " j' l (2) De,scfiptionigQy - l 7 y i ,~ mss -
, ra ,; i l Packaging forl solid radioactive materials. The container is a right p I circular cylindeh 29, inches' inl diameter and 30-7/8 iriches high with a I I
304L stainless steellouter. shell whichLis 3/8-inch thick for the 1 l bottom and sidis and.1/42 inch ~ thick < for the top. Thel shell for inner l p cavj ty is 4-1/4 inches"in, diameter x'19-1/4 inches deep, is fabricated l l fran 1/4-inch thick 3044 stainlpss steel plate, and 1s recessed 1-3/8 t I inches frontthe . top. ;The inner, cavity for the radioactive naterials l l 1s'6 inches in diameter M8 inchesLhigh an'd fabricated from 1/4-inch i I thick 304L stainless steel.' ? Seven-eights-inch thick lead fills the I
,E space 'between the sides a'nd bottom of the cavity shell and the inner
,! cavity. . The annulus between the outer.shell and inner shell is filled l i i with limonite concrete. 'The in'ner cavity is closed with a concrete- l,'
ll and-lead plug which is enclosed in 1/4-inch thick 304L stainless steel I plate. A 1/16-inch thick Neoprene gasket serves as a seal between the h I top flange of the plug and the cask body. Eight,1/2 "-13 UNC-2 nuts I i on studs hold the plug flange. to'the ' cask body. A 3/8-inch diameter b l 304L stainless steel bail isiused' to lift the plug. A 1/4-inch thick ll l 304L stainless steel plate, which covers the top 13UNC-2 nuts on g I s tuds . The cask is equipped with four,1/2-inch thick lifting and 1 I tie-down ears with two,1-inch diameter holes per ear. The cask is 1 I mounted on a skid. The gross weight of the cask and skid is 2,800 I pounds. l l l l l 1 . I I I I I I I I I I I I I I I I I 36 l l l Is_ _ - -
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l l 1h *
- CONDITIOH8 (cd..druedl .
9
' 1-3 I Page 2 - Certificot? No. 5461 - Revision No. 2 - Ddeket No. 71-5461 >#
I f ,, i , [._, - 6 l l . I 1 !/ l 5. (a) (3) Drawin; [ .(< l - [ I The packaging for the TRU Curium Shipping Container is constructed in i f= I accordance with Dak Ridge National Laboratory Drawing No. M-12175-CP-078-E-3 (Report No. ORNL-5147/AI, August 7,1981' Revision). f l I r. l (b)' Contents 6 I , [: 1 (1) Type and fonn of material ! L-ikotopes of curium, berkelium, . !' g (1) -Transuranic, californium, an incIudinka f@ni form of metal, oxide, chloride. [: a or other Afned in c s that meet the requirements of [; s pecial _ dioactivematerie%.(y l : U (ii)Tra nics, including any iso, opes o #fhtoniumM 'Itile 10m of g. me 4 oxide, chloride, or other salt doDtf, enc 3psulated in ' t gl cpps les4 hat each meet the requirementyo ' cial form radioactive : ! g m Q rial nli UJ % *
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( (2) Maxi p quantityp. terja]-pey c g, .! g The(ximumintern1 at t pe 0 atts; k (i) rthet$t i t p4 ri .i j [ of 10 9 'or any ! bin n a&2 (p)fato
-247 r Cf-249. l f ,
(ii) $t thehna Iq i bbl _a
) 1 of 3 g of Cf-251. j (iii) F Jhemateriahdqse' bdpg k)(ii) tc,tal of 'aNy cmbinatiorl fl u
a Of h)r,s ,9 and Pu-24I ahel' ed t g. I i
,f
- 6. Special form radioact @pterial capsules may be hh within DOT Specification 2R containers.
( y f, hereby approved for use under
!! 7. The package authorized by this ce f te j general provisions of 10 CFR 971.12.
- 8. Expiration date: May 31,1991. IF
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! "",C ' " 8^ cowomONS (continuer 0 S. NUCMAR hlGULATORY CC66 TON l
I 1 I ' I l , Page 3 - Certificate No. 5461 - Revisirp fio. 2 - Docket No. 71-5461 j i I I 1, I I ! I REFERENCE I I I: I Safety Analysis Report for Packaging (SARP) of the Oak Ridge'?latioEal Laboratory TRO I l Curium Shipping Container, August 7,1981 itevision to P. port >!o. ORNL-5147/RI. l l FORTHEU.S.Opd'fARREGULATORYCOMMISSION l l , c r
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g , I l i d . 8R - Macoonaid. chier'- tion Certification Branch I i g- b ' ,.
'3 I Division Pugl Cycle and I I v Material 5 iffty, INSS 1
d g Q i Date: 3AY O 5 5 I l l A, e l x w@ , 4 s yl c:~ + O Ig l . P l - ij: Q n l 6 (- J%>. v l l b
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*m Fons eis CERTIFICATE OF COMPLIANCE I io crn n FOR RADIOACTIVE MATERIALS PACKAGES I o nEvisioN NUMBEn c PACKAGE IDENTIFICATION NUMBER e PAGE NUMBEn a TOTAL NUM.ER PAGES i . CEntiNUNUuuEn 3 USA /5468/B( )F 2 )
l 1 l d , PnEu.etE f g .. Thi. c.riivic.i. i. ...u.o ro certity m.i th. p.ca.ams .no cont.nt. o..crio.o m ii.m s o.iow. m..t. th..pphc.oi. e.tr et.no ro...t tortn m Teii. io. coo. I oi F o.r.: n. oui.tione. p.rt ri. -e.ca.gina no Tr.n portation o, nacio.ctiv u.t ries.- i b The. C.rtificpt. do.. not r.h.v. th. Consignor from comphenc. with any r quirement of the r gul.Ilon. Of th U S D.pertm nt of Transportation os oth.r I apphcabi. r.0ul. tory ag.nce . mcludmg the go6ernment of any country through or into which th. pack.D. will b. tren. port.o I I i # I E I 3 THiS CEnTiFnCATE iS IS$UEr i THE BASI $ of A GAf ETY ANAtY$l$ nEPoRT OF THE PACKAGF DEBiGN OR APPLICATION
. issuto To w,, a., o TiftE ANo identification or nEPonT on APPticAfioN I i 1 1 I i N Nuclear Fuel Ser ias. Inc. Nuclear Fuel Services, Inc., application I 8 dated May 1.1967, as supplemented. I lP.O.
4 Box 218 Erwin. TN 37650
- c. oocErT NuveEn < ,71;5468 l
I s, I 4 coNoitioNs d Tn . ceri,vic.t. i conoaion i upon tumning m. r.quiremoni. of to crn Pari ri, .. .pphc oi . ano th. conoition so cit .o b.io. I ri I h5 (a) Packaging /l s ; l (1) Model No.: NFS-IX-A '?, l l E .. - l q (2) Description I R '
', )o , / I I
Dak wood container 48" x 62." x 13-1/2" outside dimensions with an l internal cavity 36", x 50" x 1;1/2" lined with 0.020" thick cadmium. l l s .o . g (3) Drawing 2. jU > - g ,
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l l l l TheNFS-IX-Apackacjeisconstructed.in'accordancewithNuclearFuel l Services, Inc.,LDrawing No'. RMP-481, Rev. B. , l,
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( d (b) Contents -
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(I ; I (1) Type and form of material l lt l glj 11 si k i 1 N{ Pu0 -UO ceramic fuel pellets enclosed in alumiriumi stainless steel, or I l zirbnibmtubeswhichhavebeenweldedclosed.andtestedtoshow h , h leaktightness. y y 8 4 I i . I I I I l< l l l 1 1 1 , I l - l ll l l l l l l l l l 1 l l 1 1 , I I l l l l l l 39 I I I I
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nvcouw won l l i l h I* age 2 - Certificate No. 5468 - Revision No. 3 - Docket No. 71-5468 li I I I (2) Maximum quantity of material per package l-I Total contents not to exceed 350 pounds and for the following w/o I Pu0 /UO , the slab thickness must not exceed: 2 2 l w/o Pu0,* Slab Thickness, .nches l 3 I
'l 100 0.60 g 90 0.67 I-80 0.75 1
!8 50 gb 9pB REG 9 8:n
.05 l
g 40 71/2 1 30hv 1. II
*For U0 g
r 9ontain3 d as Pu) 3 kU-235 or more, h5k
-f35mustJp th l
I consi lrmip{ng,/o u y () I , (c) FissileCla( ; ,I O l N. Internal cavity k the hyp , t r p qqs T ' - led (with er or other ! L packing material (19 mai tai !1 es p> %ie slah';thickgass. Not more than p 1/2-inch of elastic materl at ' ,'must-} is M if 1 iaintainipg the41ab thickness for I fuel rods 1-inch 7. eter2 The type and form oY terla'l ts esc bed i 5( [)'isdefeyminedtobeexempt j l from the requirement p 10 CFR l 1.B } 'y ' p
- 8. Thepackageauthorizedbh,4fjiscertificateisherebyapprovedforuseunderthe r}
e ; general licente provisions of 1pCFR 671.12. J 9. 9 Expiration date: November 30,191 k l l ) j REFERENCES l l I Nuclear Fuel Services, Inc., application dated May 1, 1967. l Supplement dated: May 26, 1967. l l FOR THE U.S. NUCLEAR REGULATORY COMMISSION l li ' l l 3 Charles E. MacDonald, Chief i Transportation Certification Branch l Division of Fuel Cycle and i Material Safety, NMSS I d Date: NOY14 m i 40 g ; l [ .__ .______ __ ______-_______ __ __-
u ... . ii l I IaS[" o c'a " CERTIFICATE OF COMPLIANCE I I I FOR RADIOACTIVE 1AATERIALS PACKAGES o ntvl8 ION NUMBER c PACKAGE IDENDHCATiON NUMBER d PAGE NUMBER e 70TAL NUMBER PA0tS~
-s e ctnfiricArrNuMeta 5492 4 USA /5492/AF 1 3 i r
I : ensAMete l I a in. cortificeie is issued to certify thet the peckaging end contents describod inltern 6 beiow meets the epplicable safety stendards set torth in Title 10. Code of l l rederei Reguistions. Part 71,"Peckaging of Radioactive Meternels for Tronoport and Trenoportation of Radioactive Meienal Under Certain Conditionr.." l l tt Th certificate does not rehove the consegnor frorn compilence witft any requirement of the regulations of the U.S. Department of Transported'en or other l I apphcebio reguistory agences. 6ncluding the Govemment of any country through or into which the package will be transported. l l I I I l "=,w==~~~=======,,- l l Nuclear Fuel Services, Inc. Nuclear Fuel Services, Inc. application dated l l P.O. Box 218 August 25, 1982, as supplemented. i l Erwin, TN 37650 l l l l ! l 71-5492 I I c. oocarT NuMern l I c cete is conditional upon fuffilling the requirements of 10 CFR Port 71. es applicable, and the conditions specified below. I I . I l (a) Packaging' l
! (1) Model No.: RMG-181-1 l l l l l (2) Description I I I i The containment vessel hipp hedule 40 steel pipe with ASA 'l ll y standard threaded p chtsbr th ends with the bottom cap I
( welded to the p contains seal ethlene bottles and/or l l sealed metal . The containment vesse 5 supported in a DOT a 1 Specificat H steel drum as shown in g No. Dr)aRMG-181-I. l 1 Vermiculit used to fill the entire void en the containment i 3 vessel an uttuontainer; 1/8" asbestosqliee placed between both I j l ends of con i qt vessel and o , ntai ; three inches of I ' vermicu are ofcon@nmentvessel. l b ingg L $2 O I (3) Drawing ( The pac j ing E cons H' - - /$ n th ear Fuel Services. j 1 l
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_ _ _ _ _ _u.s._NUCLEAM _ _ _REOULATORY _ _ _ COMMISSION _______ I i I l I l Page 2 - Certificate No. 5492 - Revision No. 4 - Docket No. 71-5492 I I I I I I I I I 5. (b) Contents i l l l (1) Type and form of material i I 4 l (1) Uranium or any uranium compound or solution, any U-235 enrichment. l l l (ii) U-235 as metal or oxide, or as compounds or alloys having a I maximum H/U-235 ratio of 3 considering all sources of hydrogen I within tiie inner container.
~
I l I l (2) Maximum quantity of material per package I
! (1) Forthecontentsdescribedin5(b)(1)(1): l I
I I Ten kilograms U-235 contained in a maximum of 100 pounds of I 4 I I material. I I g I
! (ii) For the contents described in 5(b)(1)(ii): l l I
i Fourteen kilograms U-235 contained in a maximum of 100 pounds of I l
; 4 I material . l S. (c) Fissile Class ,
gRREG 11 and rii l l l (1) Minimumtransphtindex to be showrL%n label hO l l 1: forClass(P, ,4 g T~ _. . /) J~ f I Fo e contpqts described in ,; l i I a 1 3 a l (2) Maximup_ uQ of1 % number packagep pertshipment y ; r"e"i W,' P 4 g
- 1
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;p ' E-l Fobbeconk,'ents,Sescrbed D Y d L i in 5(b) 1)(1) 'a'nflimitedt. ~F W l' I in 5(b) 2)(1): ' L; II) Eigh(eln (18) f I 6. A minimum 1-inch thick 4-3/4-ine d ameter. woodA ck must be inserted at I I
l each end of the containment vepsel so that thq, contents are between the wood L- l blocks. The specified thickness of. verJniculite required at each end of the I .!
! containment vessel may be reduced'by n anidunt equal to the thickness of each E wood block.
I I l L I I r I I y' I I I I I I I h I , 42 y I kl , W..m.mmmm.....mm.m. l -
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m . . - . . - - - . . A .L. . . A . . . . . . . . . . . . . . . . . . . . . . . . . . .,, ) U.S. NUCLEAR REOULATORY COMMISSION I l Nnc rona sisA f, is<n coNomoNS (continued l, j i I i l l Page 3 - Certificate No. 5492 - Revision No. 4 - Docket No. 71-5492 g j l i I I I I I l 7. The package authorized by this certificate is hereby approved for use under the , i general license provisions of 10 CFR 571.12. ; I i I 8. Expiration date: January 31, 1988. i l I I I REFERENCES l l 1 I I I L Nuclear Fuel Services, Inc application dated August 25, 1982. g i I I Supplement dated: December 10, 1982. l l FOR THE U.S. NUCLEAR REGULATORY COMMISSION l i i Charles E. MacDonald, Chief I I l Transportation Certification Branch ! I i I q Division of Fuel Cycle and p g t.eri4 Q Je MSS o,te. sEP 0 61983 - i l
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_ answennar====nn. _ _ _ _ __ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ -uq u U___NRC FORM $1s U.S. NUCLEAR REoULATORY COMMISSION 1 wem
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CERTIFICATE OF COMPLIANCE hl, N FOR RADIOACTIVE MATERIALS PACKAGES E I wl s g;! 1 a CERTIFICATE NUMBER D REVISION NUMBER c PAGF AGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER FAGES g! 5517 I,, REAM <. 4 USA /5517/AF 1 2 I r a Tni. e. rise,cai. i. ..u.a io c.rner inai rn. packaging sno conioni. o..crio.o in nem s daio . moei in.appocadi. t.iy itanoare...ivorin in Tiii io. Coo. t-oe r.oeral Regulabons, Part Ti," Packaging of Radioactiv. Mai. rials for Transport ano Transporianon of Ra'hoacbv. Material Unoer Certain Conathons " [. 4 Ei o Tni. c.,oficat. oo.. not r.a. in. con.ignor trom compaance wiin any requiremoni of ine reguiation. of in u s o.parimoni ce Transportanon o, einer I di .ppacaei. r guiaiory agenc . incivoing in. gov,rnm.ni of any country inrouan or inio -nicn in. packag. wiii e. iran. pori.a- r' dj k it I N i l 3 THIS a eReeAREoCERTIFICATE ev rN.,,s. l$ .n ISSUE,D A ON.THE BASIS OF A SAFETYn ANALYS15 n REPORT OF OF mtE ANo ioENTwiCAfiON THE PACKAGE REeORr DESiON OR APPLICATION OR AretiCAviON j ! d; Nuclear Fuel Services, Inc. Westinghouse Electric Corporation application fl l d! P.O. Box 218 dated December 15, 1967, as supplemented. Ni Enitin, TN 37650 81 71-5517
- c- n NUunen D
dj r, G3 ;nocat -[' t w ,, f k e CONDITIONS ( V kp f This certificate is conoihonal upon fulhlhng the reqt.u,rernorris of 10 CFR Part 71. as apphtable, and the cono$ons specife.d below (a) Packaging: N~sa 4<i d T 'Op N (1) Model No,; BB 250-1 . f 1." Q 2, ^,' ll g (2)
Description:
f"~ g% ' 7 J'ffu , () q; , x 'T \ w. l s. m W A uranium dioxide powder shipping co,ntainer, consisting of a steel f cylinder held in the center of an outer container (two steel drums l welded end-to-end)'hy fire-resista'nt' foam. j h p;tn ,'s J , Inner container is ll;5-inch (ID;'16-gauge" steel cylthder, 63.5 inches g! long, with bolted and gasketed top, flange closure and seal welded j q bottom plate. Inner container is centered and supported in a 22.5-8 inch ID by minimum 74-inch long,16-gauge steel drum by fire resistant 8 6 phenolic foam of AEC Material and Equipment Specification SP-9. - g r ! q (3) Drawing: 6l (! The packaging is constructed in accordance with Westinghouse Electric
$ Corporation Drawing No. C882D962 Sub. 5.
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!. " C "" * "# CONDITIONS (continued)
I i l Page 2 - Certificate No. 5517 - Revision No. 4 - Docket No. 71-5517 l I N l t. l!
- 5. (b) Contents:
l (1) Type and fom of material: {h I i I I Bulk uranium oxide (UO 2 r U,0 8) powder with a maximum density of 2 g I i U/cc and enriched to a maximum 4 w/o in the U-235 isotope. The maximum l I H/U atomic ratio, considering all sources of hydrogenous material i ll within the inner container must not exceed 1.13. [ (2) Maximum quantity of material per package: Total contents no c[eedb5hg with the U-235 content not to j exceed four ( rams. l (c) FissileClass.y I l h O I
<' s Prior to each shipSt, the lid gasket must be inspected. W .
d 6. I i replaced if inspgion' hows any defectsTQmonths,whichever or every pwelvE (4e g occurs first. s l
' byapprove or use under the l i
t
- 7. The package aut' h orized by f certifEE[Ni l
l general licens , rovisions{o }0pFR . 2. ; V g 4! 8. Expiration dat k FebruA 2Q Ih50. k I W g 5 t h D If D F M b'f !
- o Q 1 M[E ais iye ~ !
T Westinghouse Electric te ora $iphfpfliaNd c er 15 67.
- l. Supplement dated: ,1968. k,v I Januar[8,h FOR THE U.S. CLEAR REGULATORY COMMISSION l
)f ya 4 & l l1l A A /A~ M Charles E. MacDonald, Chief !,
4 ql q Transportation Certification Branch y 4 Division of Fuel Cycle and I Material Safety, NMSS f l l Date: Feb 6 1985 l
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..________ _ __________..______ _____ _ _ _ ____ _ m I
Y "' io cvR " CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATEHIALS PACKAGES 1 a CERTIFICATE NUMBER D REVISION NUMBER . PACKAGE iDENtlFICA TON NUMBI H
' 0 PAGE NUMBER . YOTAL NUMBER PAGES~
5552 0 USA /5552/B( ) 2 l 2 PREAMBLE 1 l I a ini. c.riivicai. i. i u.o to c.rtify inat in. packaging eno cont.nts o crie.o initem s b.io.. m.ets en. ppiicani. .afety stanoaro. ..i torin en riti. io. Coo.o e i i F.o. ret R.gulatione, Part 7t, " Packaging of Radioactiv. Mat.riais for Transport and Transportation of Radioactive Mat.nsi Under C.rtain Concetions " , I g I e Tnis certificai. oo not reisev. in. consignor from comprianc. witn any r.au6r. ment of in. reguistions of en u s. o.partm.nt of Transportation or otn.e I 1 appucani e.guistory ag.nci e. inciuomo in. govemm.nt of any country inrougn or into wnien in. packag wiis b transport.o l l l l I l l l * '"f,',"#,'s^'Y
., ,l'ssu o,oN,,,, Tse,sasis or a sarrn amsis,RegR,T,o,r T,Nr,ggio,c,gagN o,Rc gc,474)N,,,o, oo o l l U.S Department of Energy Safety Analysis Report for Packaging: The ORNL I i Oak Ridge Operations Gas-Cylinder Fire and Impact Shield. Report l P.O. Box E No. ORNL/ENG/TM-5/R1, April 1983. l I Oak Ridge, TN 37830 g I l 5
. oocktTwuMetR 71-5552 1 4 CONDITIONS l This certificat. 4s conditional upon fulfilling the r.quer.m.nt. of 10 CFR Part 71, sa applicabi.. and in. conditions sp.cife.d b. low.
l l ) I I (a) Packaging I l (1) Model No.: Gas Cylinder Fire Impact Shield 1 l I (2) Description 1 I l ; I l 1 The overpack is a nominal I l A protective 80-gallon, 16-ga overpack I ruhNitta fordgapaqrl)q(ders. yelded steel closure flange. I l i Positive closu l 3/8-inch diam steele bolts. foam-filledA 16-gagegas,kppd qkeel lidliner is provided with a bolted by 8, l y I i and gasketet osure provides a cavity 11-7/Ainches in diameter by g 30-5/8 inc Q high. The steel liner is cent 6M d within the outer l I d rum. Ti spa esbetween the steel liner-and odfar drum is filled with fire re nt l l ' yc foam meeting, -)pecifTtationSP-9. Wood I bracing used i l 5, and bliter c, gort,th,es inn f- per. Gasrgylinders, nominal 2,
), prpyhe inment. l i positio(d within . eeyiner gl. padded i}nserts to preventh9 gas y cylind I moveme The kage is-l eral;( nthes in d Qmeter 41-1/8 inches I high a pas xiimiAg fcssm ar c i ?7 p', pound ?"
l I I w T p , g I (3) Drawingsh 9 i E I' h d [o < rawings in Figures A.1 i l The packaMg is 1, ,
.4 b I i h,t,ructdd l through A.Vyl ORNLRdpotFNp$'n'accgrdancewi ORNLjEltG/TM- April 1983. l
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l ! I I I L r , I Il 46 I ! 4 u L..........................__._...--2
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! w<*ne ronu neA CONDmONS (continued i
M l 3 P l Page 2 - Certificate No. 5552 - Revision No. 0 - Docket No. 71-5552 0, l I I I I I I I 5. (b) Contents 0 ' y I (1) Type and form of material I l >
! Tritium gas (uncompressed) l
{l p l (2) Maximum quantity of material per package W 3 I I Maximum decay heat load not to exceed 5 watts; maximum activity not to I exceed 30,000 curier,; internal pressure of containment vessel when b l loaded not to exceed 11.8 psia at 70'F. i l
! 6. The package must be leak tested in accordance with procedure 16A dated l l October 11, 1978. y I I The package authorized by this certificate is hereby approved for use under the I j l 7. l i
general license provisions of 10 CFR 671.12, i I 8. Expiration date: July 31, 1988. l. I I I I I l l cptREFERENCES 4 > + " (c .///, I N' i Dak Ridge National Laboratory, Report No. ORNL/ENG/TM-5/ill, April 1983. I Supplement dated: July 6,Iq83. ' 't ), l I u , , , I h FORTHEU.S.NUCLEAPrREGULATORYCOMMI.SS10N g i
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[ j?p R .,_Rgf y :; ll l I c7 ' ;j / Charles Q MacDonal , Chief ! l p, . .g 1% -Transportation Certification Branch y l >
% 1 Divisionlof Fue]'.C.vcle and I @ ($, 1 ;?
a 3.6l,MaterialSafety,
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! Date: JUL 131983 ;?. fl . #' .
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.------------------------Aaa---ea---------w------------9 NRC FORM 818 e U.S. NUCLEAR REGULATORY COMMISSION l <'*eC'" " CERTIFICATE OF COMPLIANCE I FOR RADIOACTIVE MATERIALS PACKAGES i . CERTIFICATE NUMBER b REVISION NUMBER h
C PACKAGE lOENiiFICAflON NUMBER d PAGE NUMBER . TOf AL NUMBER PAGES 5563 5 USA /5563/B( )F 1 2 g PREAMBL E l I
. Thi. certific.t. i. i..ueo to certif y inat the pack.ging .no conteni. o.. crib.o in item 5 below, m..ts the pplic bi. f t yit.no.ro. ..t torth in Title io, cooe 1 l o, r.o.r.i n.gui.iion. pari ri. -e.ck.ging av n.oio.ci. u.i.ri.i. ior Tran pori no Tr n.porini on oe n.oio.ciiv. u.i ri i uno., c.rimin conoiilon. - y i e Tni a or ein.,
app. c.riivic.i. oo.. not r.ii... in. consignor erom compii.nc. wiin .ny r.quirem ni of in. reouistions or in. u s. onperimeni of Tr.n. pori iion oc oi. reouistory .g.nc ... inciuoing in go ,nment of .ny couniry in,ouan or inio weiich in, pack.a. wiii be iron.nori.o 'l I N N g I 3 TH18 CERTIFICATE
. PREPARED BY(Neme iS ISSU.od AddreasAED ONIDENTIFICAfiO'l b TITLE AND THE BASIS OF AORSAFETV OF REPORT APPLICATIONANALYSIS REPORT OF THEg PACKAG q Babcock & Wilcox Company Babcock & Wilcox Company application l l P.O. Box 785 dated November 6. 1967, as amended. I i Lynchburg VA 24505 h I W
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[ 4 CONDITIONSini. conomon.i upon c riivic.i. iummno en. r.pr. pet. ., io crn pari ri. .. .ppiic.oi.. .no ne tpagon. .p.cie..o noiow g f' i (a) Packaging T8 h () ! 1 l (1) Model Nos.: g .: '660C and 660B
/pj- i i
nr , . 1 I (2) Desc[1'ption ikN . / p/e f g l I l! gl F ia e) . . . . . Model,No. 660C packagi)ng is"coqstr[uc ed as describ@in g; i Bl N ; h Wilc~ox Company's, application dated /N6vember 6.1967a Model No. 660B i L packaging is constructed in accoEdatice with Divisionsof Naval Reactors lT letter (NRiRR: l p (b) Contents ., s FRHG-#;hh2248)[dagd I[ k - 9' September'25,196 ! O' q I (1) Type and ' form of material".O'g !Mm
,,M x 1y f (b I I
N s e nf
's l W3; & q' Unirradiated fuel cluster.-
ll g ,s (>* l gi i (2) Maximum quantity of material per package i I ' I d;f , One fuel cluster containing U-235 as specified in Babcock & Wilcox I Company's application d, ted November 6.1967. [ l ll (c) Fissile Class III ' il l l! Maximum number of packages i 1 I per shipment. One (1) I i I i i I I I I I i I i I I I i I l u 1 b I i I j i I i 48 I I I L______-_-____________-_-_______-___________________.J ! i l
""C"*""'^ U S. NUCLE AR HEGULM ORY COMMISSION f CONDmONS (continued)
I I i/ I Page 2 - Certificate No. 5563 - Revision No. 5 - Docket No. 71-5563 ; h I N I I I l 6. The package authorized by this certificate is hereby approved for use under the l j general license provisions of 10 CFR 971.12. i l i
- 1. 7. Expiration date: October 31, 1989. I i i i I l
l i
!,' REFERENCES l g The Babcock & Wilcox Company letter ddted November 6,1967 (classified). !
Division of Naval Reactors suppl from R. E. Kosiba to Manager h:b ady Naval
- 8) dated September 25, 1969 fice, AEC.
I I FOR THE U.S. NUCL GULATORY COMMISSION y 1 i
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lj 'f - teAia , IfiSS I Date: 0072 5 m$ g % Sk 4 !
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p , - s i . g l l 3 / l b 41 1 44 l i i li, n d' o****++o@O l l I I l il G I d I n l 1 l 5 i i I i d I l I t I f V: l l ' I i I 1 i 49 i i l_______---------------_______________-__________
g----- _----------- -______--____---___---_______- _ _, 1 Is$[ "" so crR n CERTIFICATE OF COMPLIANCE I FOR RADIOACTIVE MATERIALS PACKAGES I l i e esRtwicArt NUMBER b REVISION NUMBER c PACKAGE IDENTipiCAtlON NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES 5580 2 USA /5580/B( )F
} 1 2 l !
PREAMBos a This certificate is issued to certify that the packagmg and Contents described inttern 6 below,ineets the apphcable safety standards set forth in Title 10 Code of i Federal Regulations, Part 71. "Packagmg of Radioactive Materials for Transport and Transportation of Radioactive Matenal Under Certam Cond6teons "
.j b This certificate does not reheve the consignor froen compliance with any requirement of the regulations of the U S. Department of Transportation or other l j apphcable regulatory agencies. Including the government of any country through or into which the package will be tran: ported l
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U.S. Department of Energy Safety Analysis Report for S5W Power Unit Division of Naval Reactors l shipping container dated August 9s 1968. g
;{ Washington DC 20585 s I I I
I e oocxtrNuuBER 71-5580 l 4 CONDIT#0NS This certificate is conditional upon fulfillmg the requ6rements of to CFR Part 71, as apphcabiqp and the conditions specified below. l 7 y (a) Packaging l (1) Model No.: S5W Power Unit I g I (2) Description i I
]
1 The SSW Power Unit shi,pptqg g ntajner assembly designed,tq $ hip and !! tori he(PUSC) y naval reactorispower a container units, and support l g The PUSC is c isdd essentially of thrag major assemblies: (1) the g outer frame s the inner frames and (3) the shipping container. I; I During shipme a the shipping container is .ted to the inner frame i in a horizdKfal position. Two trunnions we}d ito the middle section 1 of the s infco tainer support the Jower'en the container and I also pr the (n whereby the ce tittner can"be rotated from the horizon in(ship (p g) (titude to pertical (7dading-unloading) l y attitu the 16ner pam6$ hie jjnipnsturnefgtrunnionbases y whichaffboltedtol)heinrerfr'am contairjar. are $pppbrted'p je The inner fp me and shipping 1 elastictrbockguntsify*ythd~6~~p>ramejapdped"sta oth the inner frame h I and outW frampgg % ofprh [is lgt % secured t ll ; l cda
! : tf. y Approxim dimeppp:,os 4f>3Q',hre%ehdj&or asse6)ies of the PUSC are:
Shipping ainer: % jnchet diamptef by 23fef,nches; Inner Frame: lg g 109 inches h by 52 inSpsfelshbby 269 isthes length; Outer i Frame: 121 es width by 56-inches heigh 9t by 236 inches length. 3 Maximum weigh 4p the loaded PUSC is appFpitimately 127,900 lbs. I j y y V .
\
o r444 r ,l l I ii ji I 1 l j so l 1 l 6mm -ww. m ww,,, v, , ,, ,,, ,,, ,,, ,,, ,,, v,, ,,, , .
]
i 1
.]
y,,,,-------------------,,----,--------------,---------m I u.S. NUCLEAR REGULATORY COMMISSION l w+nc = ronu sisA ' CONDmONS(continued i l l l J
.Page 2 - Certificate No. 5580 - Revision No. 2 - Docket No. 71-5580 l l
l l l l l l l (3) Drawings l I I The packaging is constructed in accordance with Westinghouse Electric I l Corporation Drawing Nos. 936F963, Rev. 3 and 936F964. Rev. 2. I i l (b) Contents l l l 1 (1) Type and form of material- 1 I I Unirradiated fuel aassemblies 'of the following type, j l I
! (1) S5W Core 4 power unit with control rods installed and secured in I place by holddown mechanism. l l l I (ii) S3G Core 3 power unit with control rods installed and secured in l place by holddown mechanism. j l
i I (2) Maximum quantity of material per package l I I I One fuel assembly as described in 5(b)(1)(1) or 5(b)(1)(11). i I I (c) Fissile Class '" J
.. R REG 9 Maximum number of packag.es i
I per shipment: [y;), T One(1) I O( - Expiration date: March 31, 1988. Q I 6. g$
- 1. , _' '
4 j'y
/
Z, I M/ . 1 i
,E' \'k' REFERENCE ui .a u
/ , ,[ ()
<ICorftainer, $.,APD-0P(R)SA-820 dated !
I I Safety August Analysis Report 9,1968. 3 ( \ for JC S5W g Powerp Unit'Shippi<r}g/f a r
+ pgp>yqghh.NONEhRRCLATORYCOMMISSION
( f I
!f f h.. J ,N [ i I
[& Charles E. MacDorthld, Chief I Transportation'4elFtification Branch Division of Fuel Cycle and l Material Safety,!#4SS i ' ' SEP 0 61983 l Date: : 4 I ' I I ' I I I I 51 L _ m m . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,- . _ - _ - m _ m . .
,g=__--------------------x----------------- h---------_---+
""$i ea CERTIFICATE OF COMPLIANCE Uj C'R ' FOR RADIOACTIVE MATERIALS PACKAGES I i a cERr:FICATE NUMDER 6 REvi$10N NUMBER s PACKAGE IDENTIFICA1,0N NUMBER d PAGE Nunn .R e TOTAL NUMBER PAGES r 5595 0 USA /5595/8(U) 1 2 )
lb. PREAMB(f l e ini. certaicaie s. ...u.d io certs inai v tne packaa.no and contenti de.cribed in iiem s eeiow. meei. ihe appiacacie .aiety.iandard...i fortn in Tiiis io. Code I : gl of rooerai Reguiation.. Part 71," Packaging of Radioactive Matenal. for Tran. port and Transportation of Radioactive Matenal Under Certam Conditions " g : lj b This certificate does not reheve the consegnor from compliance with any requirement of the regulat4on. of the U S Department of Transportation or other I ll' appiicante regulatory agencie.. encludeng the government of any country through or into which the package will be transported I 1 ll 1 I I * 'a"MNES%'#.*f, ?" '."d *** ' ' '^"" ^**"."'E"E 4No'30FF"^13'EM8"E%'#fiCuioN i l U.S. Department of Energy Safety Analysis Report for Packaging: The t i P.O. Box E ORNL Uranium-Shielded Shipping Cask, ORNL Oak Ridge, TN 37830 E Report No. ORNL/ENG/TM-4. Second Revision l li i Ju 1 8? as supplemented, y dl efooc2tNuws ! (4T-5595 I li a Thi. CoNomoNs certificate 1. conditional upon fulfilimg the re
,g ire,rnent.V
*4 o of 10 CFR Part 7t. a. apphcable, and the cond ons specified beiow f l il 6 (a) Packaging $ '(} j (1) L nd M J Model Nos.:c,o x em .&
kl (2) Description ~ . i% *( ' be 5
+1 Mi C A '3 os / // ' /
Steel encased, uraniurn shjelded longitudinally finned shipping casks. The C) I Ni f f containment vessels for .both models meet) special form requirements and are held within ll-inch diameter by 17-1/2-inch high cavitiesF Positive closure y y of the' lids .15 accomplished by:
- twelvh"a 3/4-10 UNC bolts' for the Model No, i l
itl q N L and sixteen, 3/4-10 UNC bolts 'for [the.Model No. M. Both models have 3-inch deep fins, are mounted to[a 69-inch square skid, and are enclosed I I ! (, within a mesh personnel heat shield] j. ' . y 7 l l gi .t> -
.. . . m y gi The Model No. L has a 25-1/2-inch 0.D. (excluding fins); is 39-3/4 inches y g! high; has a 35-5/8-inch diameter, bottom lug ~ plate; a maximum uranium shield I gl thickness of 6-/34 inches; and a gross weight of 13,200 pounds. I E I 8
li The Model No. M has a 25-inch 0.D. (excluding fins); is 38 inches high; has a 35-1/8-inch diameter bottom lug plate; a minimum uranium shield thickness [ y ll of 6 inches; and a gross weight of 11,600 pounds. p di I l gj (3) Drawings I , g N N The packagings are constructed in accordance with the following Union l l Carbide Corporation Nuclear Division, Paducah Plant Drawing Nos.: Model g g No. L, M-ll572-EM-001-E through M-ll572-EM-003-E; Model No. M, M-11572-EM- 3 l 010-E through M-ll572-EM-014-E. I I ja! I W b 1 l ml W l l N si I i NT, I g I I W I g 52 4 N u _ _ _ _ _ _.____'I
1 l I
. . , , . , .,,,.. - , , , , . . , , , . , , , , , , , , , , . . , , , .., , ,.. . , ..,.,,, -i ,.;<-i.,,, ,.,< e l
conoITsous tcontinued) U*""*"""'""
'f *.
l Page 2 - Certificate No. 5595 - Revision' No. 0 - Docket No. 71-5595 g l I q i el R p l (b)' Contents [ l q (1) Type and form of material [ p: i R Solid, non-fissile radioactive material encapsulated to meet the N: W requirements of special form material as defined in 10 CFR $71.4. ;k: W k: l d (2) Maximum quantity of material per package [ k
- q. The maximum internal heat must not exceed 5,000 watts. W
- 6. Packages having internal he prpklerIthb watts must be shipped as exclusive lsl use.
(
, (g L b
l 7. The package authorized 1by, this certificate is hereby/ >. r g! g general license provisions of 10 CFR 971.12. appy)oved t, for use under the I 4
$ T . **f)> f; i
- 8. Expiration date:v.4)ctober-31,1988. r 7 / #
-i1; l
~ t. z ; +~
.)
q! OakRidgeNationalLaboratoryP,eportNo.ORNL/hNG/ 24,j$econd Re61on, June 1983, l' pi % .y. 4 .. _).% , % v L
)
9 ; DOE Supplement dated:- @p) , / < $ 4 g Septdmber(30(,j%TTT Qi1 % 1983. T y 1
-$ m I
l S$', 23 i {10.S.'NUCLEAp'REGUQTORYCOMMISSION p l l $g/ }hyb D O ,. , l l
^d $7 [
6 4
.g .wp */ I Ei l
l ll g hh j Transportation gCh'arlys"E. MacDona1{f1 Division of fuel Cy61e and Cetpcation
$ Chief Branch h
tl l Mqterip1 Safety, NMSS s
)TL g-4
,^A p( r t
Date: OCT 131983 ( l<l N c l-a
$s<I!
l s3 H .. l l l l L_______________-_ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _
i ! kl mani mac conu sie CERTIFICATE OF COMPLIANCE u.s. NUCLEAR REGULATORY COMMISSION L i W 'o c"' " FOR RADIOACTIVE MATERIALS PACKAGES l b REVISION NUMBER C PACKAGE IDENTIPCAfiON NUMBER d PAGE NUMBER e. total NUMBER PAGES e a CERTIFICATE NUMBER
, 5597 0 USA /5597/B( ) 1 2 t L
i PREAMete I a. This certificate is issued to certify inat the packsomg and contente described m item 5 below. meets the applicabie sateir standards set forth m Titie io. code { l of Federal Regulations, Part 71,"Packagmg and Transportation of Radioactive Material." f j l b. Th.: certificate does not revieve the consignor from compiiance witn any requirement of the reouisia ns of ine u s. oeoartment of Transportation or orner L I applicable regulatory agencies, meludmg the government of any country through or ento which the package will be transported ( J L l I r I
; a 7wiggvi,rgc,Aysys),gN
, ine easis or A sAreiv ANAi.vsis,REgT,o,r,v,u,EgggsgogogRegc,A,Tg , f i
[ l i i U.S. Department of Energy DOE application letter dated July 31, 1978, ( l DP-4 as amended. [ l Washington, DC 20545 L I [ L l , y-I . .. oocner NuwesR c 571-5597 { 4 CONDITIONS , , This cartsfacate is conditional upon fulfilling the requirements of to CF R Part 71, as apphcable, and the conditions specified below j (a) Pa ckaging ) c [ l L I (1) Model" No . * . Tungsten-Shielded Cask I l l [ I E. I (2) DescNption( 3_<< < [- 1 i The. packaging cbnsisks of aJright' circular cylinder with a hemispherical I bottom. It has-a maximum.outside diameter of 16 inches at the base. I The cask itself has' an outside1 diameter of 8 inches. "The overall l l I height is ,15-1/4 inches. " Inner cavity? dimensions are 3.120 inches in I { l diameter: by;6-1/2 inches, high., , Shielding is composed"'of a 2-inch f ] i thick iso, statically, pressed and! sintered tungsten alloy containing 95% t 1 i tungsten.c3.5% nickel.fand 1;5%(iron, with a,l/4-inch type 304L ; l I stainless ,steelfcladding:outside ;and a 1/8-inch type ,304L stainless E ! I steel scladding'inside,?The ga'sketed lid consists of, a 150-pound
~
[ l I flange to which the top shield plug is attached and'is held in place I. j by eight 5/8-inch studs .and bolts'. A capped 1-inch pipe is welded to [
, the underside of the cask lid .to position the, contents. The gross t i weight ofl th.e. basic cask is 381 pounds, s t I : C I A tungsten insert personnel shield and shipping pallet are used for C I shipping radioactive materials having; higher internal heat loads and I external radiation' levels. ". The gross weight of the cask, insert, heat f l shield, and skid is 565 pounds. y l C l (3) Drawings [
l [ l The packaging is constructed in accordance with Dak Ridge National I Laboratory Drawings No. M-11575-Di-001-E-Rev. 3, X30-11575-002-Rev. O, [ l and X3D-ll575-003-Rev. 4.
; t I (
l L I L I [ l l I I I I I I I 54 L ( I l _j
,_mm-----------
10Emm1 h conosinous (continued) " * " " * ** " "" ^ ' k Page 2 - Certificate No. 5597 - Revision No.' O - Docket No. 71-5597 d f_ b e I l I l (b) Contents l l '(1) Type and form of material' l N Solid radioactive material which will not decompose at temperatures of I 250*F (121*C) or less, encapsulated in a metal capsule which meets the 1 i l requirements of special fom radioactive material. l l (2) Maximum quantity of material. per package ! d' I G Not to exceed 50W themal decay heat. I g r~. -
)
4: 6. For material described in 5(h)(1)b,,ndDiM[c.d/rr 5(b)(2), the cask must be 1 li mounted to the shipping,peljet", the personnel shieldpust be in place, the l q tungsten insert must positioned in the cask cavity,)and the special fonn y g i contents the shielded must be held,' posi}{pf or normal lthinconditions the tungsten insert by a/sp)acer that will assure of transport ' d s 4,3 d 7. i For the material Aescribed _in 5(b)(1) but limited to no' m6re' than 25w per package l of themal decay,Theat,"thp? shipping s pallet, personnsi shield, and the tungsten - 'gll 4 insert need not"be used.*$:;:1. X .; / ff ., ' O y g Mjl 8.
?" ,? ) ' g. / $/p ,, n Prior to each pipment, the~ pac,,kage and gaskets,will be inspected. The gaskets N di shall be replaced with new gaskets' if;anydefects,are noted.- Gaskets must be
# I replaced not more than 6 months' prior to any(' shipment / ' h I l r () W 7,Nf [ Q i. ' Q '. ? '
l l 9. Prior to each shipmentsthe packagg(J][l.l[gbenleak sha tested 3 at.cm /sectol0'3 g d' usingthesoapbubble'te'st;orequiva15rit!}.g&Q 7 W' .&p U K g 9 Y. (, I d 10. j Within 6 months (prior to shipment, i ns pection. Repaigwill be made as appropriate c g( package welds?y I
]
l 11. The package authorizek hy this certificate is hereby approved for use under the g general license provisions -of 10 CFR 671.12. l t d d;
; I
- 12. Expiration date: March 31,1991.
j S I A i fif REFERENCES l g I U.S. Department of Energy application dated July 31, 1978, as amended February 13, b pl 1980, December 20, 1984, and January 16, 1986. I f 1 FOR THE U.S, NUCLEAR REGUALTORY COMMISSION l V i U d{ ' Charles E. MacDonald, Chief p Transportation Certification Branch
/ Division of Fuel Cycle and Material Safety, NMSS 8(! Date:
g IIAR 0 31986 , I 55 I .
_._ _.__._ a N I U.S. NUCLEAR REGULATORY COMMl8810N I sen.c
*= Pons sie CERTIFICATE OF COMPLIANCE ji l to crR n FOR RADIOACTIVE MATERIALS PACKAGES I
D REVISION NUMBER ..PACILAGE iDENTIFICAT.ON NUMBER U PAGE NUMBER e TOT AL NUM.ER PAGES I 1. CERTNUNUMBER 7 USA /5607/B( )F 1 3 I : PREAuste jl
. ini. e.n tic.i. ..u.o io c.rtity in.i in. p.ca.ging .no cont.ni. o crio.o m it.m s b.io.. . in..ppiecedi. t.iy et.no.co. i tortn in tit . io. coo. 11 I
i of F oer.: R.gui.tions. P.rt 71,"P ckaging ano Tran port tion of Radio.ctw M.I.rt.i" l 1 e this certificei. oo.. not reliev in. con. gnor from compii.nc. .iin any requiremoni of ine reoui.i one of in. u s o pertment at Tr.n port. tion or otn.r lII I appiicadi r.gui.iory g.nc. . incivamg ine oci,.mment et any coumry inrougn or nto .nien in p.ekap. iii be tren pois.o. I I I I
* '.".M'@^Ji'.'"d.T '"' *** ' ' *^"" ***."'vTe'EliJEIE*Ali!N U"Ei oOA* Spi"CaroN I
I ji I I I U.S. Department of Energy T-2 Shipping Package, Safety Analysis 1 I DP-4 Report. Draft: April 1980 as supplemented. l Washington. DC 20545 y l , , _ I I . naciceT Nuwa:R? ' j11 5607 I I a coNoiTioNs - .,i I Thi. certifica . is conoitton upon tuitisimo in. F.auliem.ni. of to cFR Port 71, .. .pplic.bi., .nd th. Condition. sp.citi.d b.lo. I s ... I I 2 . I I I i (a) Packaging 4 a g i ' i 1 I (1) Model No.: T-2 o I I , I I (2) Description >
, -/
4 p I i l l Packaging for irradiated reactor fuel, and' components consisting of a l I lead encased in steel cask removable containment vessel" insert and i I shipping case.' < f
. ,. m ,.3 , s y
s 1 . +, .. . y l The cask is a double-walledisteeljcircular cylinder with' thickened i shielding in the ' center portion, a The central cavity is '6.065 inches l l in diameter by 100. inches long._ Theflead shielding.is,8.0 inches 1 I thick along a 45-inch center section reduced to 4.2 inches at each 36- 1 I inch end section. The containment' vessel . is positioned within the i I cask. Cask closure is accomplished by a gasketed and bolted steel l' plug. The cask is enclosed in the shipping case which is 36 inches in I l diameter by 133 inches long welded to a 4-foot by 6-foot steel pallet. I i The maximum weight of the packaging is 18,400 pounds. N q l I I l I q l 1 l ' I ! N l l I j l 1 1 I I { i l I ! I l J 1 l i I 56 y 1
-.__-am w w--- rauru w------------ -- ---------------ra---a5
7"j?"'" ' 8' cowomous (continu.a) u.s nucttAn RtcOLATORY COMMIS$10N I 7 age 2 - Certificate No. 5607 - Revision No. 7 - Docket No. 71-5607 l ) l 5. (a) (3) Drawings I l (1) The shipping case is constructed in accordance with DuPont Drawing i Nos.: W716539 Rev. 0; 180191, Rev. 1; 180192 Rev. 0; 180193, a l Rev. 1; 180194, Rev. 0; 180197, Rev. 0; W716538, Rev. 0; 180195, l Rev. 0; 180196, Rev. 0; and 180089, Rev. O. l l (ii)ThecaskisconstructedinaccordancewithGeneralElectric j i Drawing Nos.: 919D755, Rev. 0; 135C5202, Rev. 0; 153F966, q l Rev. 0; and 106D3721, Rev. 0; or it is constructed in accordance g ; with DuPont Drawing Nos.: W239534 , Rev. 2; 147214, Rev.15; I g l 147215, Rev. 2, ag7Qg l l (iii)TheANLi Ys constructed in a e with Argonne National i Labora rawing Nos.: W0147-0227-DB v. 7; WO147-0228-DD, i Rev. i e i DC, 147-0229-DC,Rev.6;WO147-021@p,Rev.3;W014 t 4; and WO147-0312-DE, Rev. 2 l (iv)The@EAh insert is constr 'd acbancewithWesting- l l ho %s Hanf . ny Drawing N [3-3908 heets 1 through 4 l ) i aid 6, Rev. $; he6Kh e. 36134 eet 1, Rev. 3 and i l S t 2, Rev,i H G6 23 1 ?I, Rev. nd Sheets 2 l
' "'h # ""
N l J ~: I
;? ,
f l l (b) Contents
}
g f ')'W i > , i- f , j l (1) Type and orm j [ er : s l
! (1) IrraMatedT][dkuel,iktN rmM olid , oxides, nitrides, !
I and cerbjdes of uhnigni - 1 niilIQ or mi ranium-plutonium P I contain( ithin the AW t or RE ssel insert. The clad l l fuel may pain small quantities of NaK. The minimum i cooling ti musgbenolessthan150 ys. l (ii)Irradiatedclad el inhGf anf m dioxide enriched to up to 1 I 3.0 w/o in U-235 contained within the ANL insert or TREAT vessel insert. Average exposure of fuel not to exceed 18 megawatt days l per kilogram. The clad fuel may contain small quantities of Na i or NaK. The minimum cooling time must be no less than 90 days. I I (iii) Irradiated reactor components held within the container shown in Drawing No. WO147-0234-DC, Rev. 4. l I I I I I l l l I 57 ; l , i l l' -
- www w.rmas------------------- --
L__________________
U S NUCLE AR REGUuTORY COMMISSION 7"" ' " "^ cowomoNS (continued)
' Page 3 - Certificate No. 5607 - Revision No. 7 - Docket No. 71-5607
- 5. (b) (2) Maximum quantity of material per package.
Internal decay heat not to exceed 208 watts, and: (f) Forthematerialdescribedin5(b)(1)(1),fissilematerialnotto exceed 1.71 kg. (ii) For the material described in 5(b)(1)(ii), fissile material (U-235)nottoexceed300 grams. (c) Fissile Class for the material described in 5(b )(1 and5(b)(1)(fi),andlimite (2)11) I 5(p{C)gJ d5
- 6. The contents must be shippa[ fy. When loaded und rjetter, the package must be dried using Consumer Powec/ Company's procedure, "T-2 Ta Liner Assembly Drying Procedure,"Prt>c.No.iZET-Cl2,Rev.1,11/12/81. Q
- 7. The ANL Insert and T t resselrdance s insert must be leak tesfeified with the p h or to first use in Argonne and annually thereafter '19 4 'dures s NationalLaboratof&sDocued Nq. W0195-0054 5
^
f g ] k Q \ tC~R I
! 8. 'agb must~b 1a_ - d'ted in ac dance with i Prior to each procedures shipment, specified in Append thely .l 4 toj N $202, Rev. 2 arch 17, 1981.
t 1 # / I 9. The package auth) zed a h &,'se't;fice
' his-c s piby ppfove or use under the i general license se visi jofIDfCFR 97' L ,
b,
- 10. Expiration date: ch 3 9 ( .J h
l / J DuPont Safety Analysis Reporf/ aft April 1980. l l DepartmentofEnergysupplementsdajfd: 77 februargjl, R fi )Mril 8 and 20,1982; and ; q April 12, 1983. I I FOR THE U.S. NUCLEAR REGULATORY COMMISSION I I Charles E. MacDonald, Chief I Transportation Certification Branch Division of Fuel Cycle and : { l Material Safety, NMSS j g I Date: MAR 18 W I I l i f 58 L______________________- - - - i 3 l l l l
1---------------------------Au---A----------------------g
- NRC PORM sis U.S. NUCLEAR REGULATORY COMMISSION I
, i*ew o CFR n CERTIFICATE OF COMPLIANCE I FOR RADIOACTIVE MATERIALS PACKAGES I t a CERTlF CATE NUMBER b.REVtSION NUMBER c PACKAGE IDENTIFsCAYiON NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES 5641 8 USA /5641/AF 1 3 I y .. PREAMBLE I
- a. This certificate is issued to Certify that tne packaging and contents described in item 6 below, meets the appi6 cable safety standards set fortn in T6tle 10, Code I of Federal Regulahons. Part 71,Packagmg and Transportation of Radioactive Material." 1
, b This ceriencate does not rehevo tne consignor vroen compnance wiin ariy reaviremerit of the reguistions of ine u s. Department of Transportation or other I
, appucani reguietory agencies, inciudmo the government of any country througn or into which ine package wiii be transported. I
. 2
,I a I 3 TH18 CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION
- a 158UED TO Miame omr Amessi b TITLE AND (IDENTIFICATION OF REPORT OR APPLICATION l j United Nuclear Corporation United Nuclear Corporation application dated I
] 67 Sandy Desert Road February 1, 1982. I q Uncasville, CT 06382 I i 71-5641 l 1
j n w.DOcacT m DNuwBea.p C3 I
, /, I j
4 CONDITIONS Uf N/ Ttus certificate is conditional upon fulfilhng the requirements of 10 CFR Part 71. as applicable. and thefonptions specified below. j s.
*p I (a) Packaging ra@y Q
l l (1) Mode [)liop UNC-2500 AF g'
}. wF d I (2) Desc71ption Q k ed s c
/ [? # f C
I I Specific packagingIf )not r%equired/ pteof shipment is independent lS fety I
/ . . gi] U l i
(b) Contents offpackaging.
, ia
'y 3 [t ,Qs jn# _hWm(L t {
i i en 21 n Type and donn'of material 'y% bM T T@e n* e'5* fj d? ,'/ ,.,
~2 l
(1) f I
Wl . ^ Ab %q
? l% MV l Un{mrradiatedsfuel cluster yqqg $sj, odules'or other assemblies. l g g g~~ +7 (g s
(2) Maximum quan'tity dfs mate klpeh>shipofehi i L T Not to'jexcged . ~ % An qua/)tity . ', Q- 'H/ %g l i a Type of radioactivfma'terial; and I I y, I I Dry Shipment / k I
! % . df l l [ Interspersed hyrdogeno'us ma,teri$1'" limited to an H to U-235 atomic I I
I ratio of three (3) or'less.']' I I I Shipment limited to: I I I l (i) The stated dry safe quantities (without reference to notes or ! , I supplements), but excluding those parts named as " elements" as I f I listed in the following pages of Table 10.0-I to SNM License No. 368: I I I I I I I I I I I I i l I ! l l l l l 59 I I I I L. . .
. .~ .. t l 4
i
,,____________________________________________________m I
I coNOmON8 (continued) . .U S NOCLE AH REGUL ATORY COMMISWON l I 7 """ " l Page 2 - Certificate No. 5641 - Revision No. 8 - Docket No. 71-5641 l > I l
! l 1 o
I I { I j 5. (b) Contents (continued) l P.10.0-4, dated June 4,1976 l l P.10.0-5, dated June 4,1976 i l l P.10.0-6, dated June 4,1976 p I P.10.0-7, dated June 4,1976 I I I P.10.0-7A, dated September 28. 1978 l P.10.0-7B, dated May 6,1985 . l P.10.0-7C, dated May 13, 1983* l i l l P.10.0-7D, dated October 27,1982**; or i I I I *except Items 5b and 5d which are authorized by Certificate of I I Compliance N 149 8 { p I l
**except Bdonpagd .7D shall be limited to two l l ah ;
l clustg (ii) 700 s U-235; or Q j g U-235/ inch. I l (iii) S egt cated i fuel part not egceedihg I i l Modedl6d Shidin)e . p A WA J" l l i Shipgnt limite( O j { l ^ I (1) }-The stated ' safd quantit, withpy't/refe ce to notes or I l gypple'mhdts)l? t'4 41)(11 ' FpaWsinam 2as " elements" as l given the Ab te et m -table .;pf- g 1.- .{ {
e' ,. g (ii) 50 ram 235;; t
- g. y CO I
\
(iii) Asyglefa i tedl EtN@exce 20 g 0-235/ inch. (c) Fissile Class h III l
- 6. The name plate to which the Inddel/nuniber jkvafNxed rust be fabricated of materials I capable of resisting the fire 'testiofM0 CFR Part 71 and maintain its legibility. j I
- 7. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR $71.12. i I
- 8. Expiration date: April 30,1991. I I
I I I I I I I I I I I I I I I I I I I I I I 6o l l l L______________________________________________________! l l
I "jy nu eia* cowomows (continued; o s. wom As amuony comstoN l l l l l 1 l Page 3 - Certificate No. 5641 - Revision No. 8 - Docket No. 71-5641
, REFERENCES !
. I l
I United Nuclear Corporation ' application dated February 1,1982. I I I Supplements dated: April 25,1983; and February 19 and 24, and April 25 and 28, ! l l 1986. ! ; I I I FOR THE U.S. NUCLEAR REGULATORY COMMISSION I I I I I I I l
, ggR
/
s . nacDonald, Cnief 4 ' I y Trans n Certification Branch l Division a$pelTF Cycle and I l y(j , HMSS I I Date: W 2 0 Mk Material o Ssfg$ ,
!, g 3 z- 4 ,
l
, s 4/
y < ,~ . d - o I q b O l g ' %@s@,,, a s[- 'i >$ gd g j l m f,/y, g i a atp l l So k y)f k 2h &k i 5 s q4u% e , l
<4 o +O l
l l l 1 4 ,#s. x ,tw 4 s a rs l a I I I I I I I I I I I l l l l l l l l l l l l 1 I I I i i I I l i l I I I I I I I 61 1 I I L... ..........- .... _ n.. _ w.... -
.... L
- ----------------------------------------------------g NRC PORM sie U.S. NUCLEAR REGULATORY COMMISSION I
** CERTIFICATE OF COMPLIANCE I w cFR n FOR RADIOACTIVE MATERIALS PACKAGES I CERTIFICATE NUMBER D REV48 TON NUMBER s PACKAGE IDENTIFICATION NUMBER 0 PAGE NUMBER e. tot AL NUMaER PAGE.S 5687 4 USA /5687/AF 1 3 !
of_.L. i
- s. inis comvicate i. issued to c.rtify tnat tne pack.ging and contents describ.d in item s beiow. meets the apphcabie savety sianderde sei tortn in Titie to. code 1 of Federal Regulations. Part 71. " Packaging and Transportation of Radioactive Material? l
- b. This certificate coes not reheve the consignor from comphance with any requirement of me reputations of the U S. Department of Transportation or other I ,
apphcabie reguistory agencies. including the government of any country through or ento which the package will be transported. I I I I 3 THFS CERTIFICATE t$ ISSUED ON THE BA8iS OF A SAFETY ANALY$l$ REPORT OF THE PACKAGE DESiON OR APPLICATION g
. issuto To m. .,W A#wssi b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION I
Nuclear Fuel Services, Inc. Nuclear Fuel Services, Inc. application dated 1 - P.O. Box 218 August 25, 1982 1 j Erwin, TN 37650 I l r, I 17 r 1
- re OaCxsTNuunRc O /71-5687 1 1 I
4 CoNo:TiONs b* V / This certificate is conditional upon furtunno the reghments of to CFR Part 71. as apphcable. and the, conditions specified below. 5 (a) Packaging [ / l
% %)
(1) Model No.: RMG-184 ~ g* l
, . m 'y ir l
,,4 I (2)lti
'@ scriptjony%, D , X /)s./Ap, I g The containm_ent, vessel-is;a .5-gallon bucket, DOT I
* *tiosure 1s;by means of' Jug-clamps ,used with lidaand new(Specification gasket for I 17H qeach shipment (. [Tpe outer cgntainiitr','(55-gallon D07 Specifica l l
steel drum'and.Sasketedilida.is c'16 sed by a 12-gauge bolted ring with y i b~ drop forged'lugsbone of which,,isc threaded, having~a 5/8-inch bolt. l I I i p1 gauge 41eeves filledhe eqnttinment
' t tamped' vermiculite vessehis and< firesupported retardant 'in,the 1outer. :
I
' 46' Q l I (polyurethane)foamj ' j5 pQ, ~
%. I I
I (3) *b}rawing w a:fy[r VN) v* MM 8 ,/i.v u:. x; ddtS.w[,- ,, (F)- 1 1 i f ,,t(,s N , (A l l The,ppackaging is\\" constructed *in accordance with' Nuclear Fuel Services, , I Incr, Drawing No. RMG-184.'Rei. A. Use of optional 5-gallon insulator I I bucket is.not authorized. tj ,yN', " l
' K l ,
l j ,1
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vr 1 , i g , I I I I I I I I I I I I I I I I I I I I I I e l
, I l I I I I I I 62 I I I
_________---------------------------------------------) I I L l
. . _ _ _ - . _ _ _ _ _ _ _ _ __J
l l I cowomoses (continued; u.s nucte An ntout4 Tost couuission ;
'"j "" " >
Page 2 - Certificate No. 5687 - Revision No. 4 - Docket No. 71-5687 i
- 5. (b) Contents (1) Type, form, and maximum quantity of material per package j (1) Oxides of uranium, at uranium densities not to exceed 3.2 g/cc.
Not to exceed one hundred pounds of product with the maximum enrichment.in the U-235 isotope not to exceed 10 w/o. H/U-235-ratio, considering all sources of moderation within containment vessel and maximum U-235 content must not exceed: 1 Enrichment Maximum U-235 Content
% U-235 H/U-235 Kilograms 1
2. Efig[A 10 0.40i 0.802 5 5
'Y A 1.203 1.604
@*h) 5 3 3 y'"#
+
.005 405 J
(/) e'7 66 3 f- 3M5 5 Qt 8k 2 3L605 g , 9k.. 10 . Cfq- - 4g (jjf Uranium .. ,ofine'Ifi',a " lum;dpnsitTitsexceeding3.2g/cc. Notdtoiexce 0m drgd sa'ds ,bt 1
@ enr.icipent1n9 f 1(iL ! 4. tipe!, pop;prodg to enqeed with 5 w/o.the maximum H/U-235 rati rcesof%derQ1bnwithincontainment Ovess'oi4cortsidpri e11&nd maxi 1 ( tegt 'must g exceed:
nric m n x mu UsblContent PU-235 i
+
N/U)-235Atilograms v
! .j
.gf 19 20 0.401 2 V' j ~10 J/ 0.802 3
4
'f WkyD 5 0.700 0.700 .
5 3 0.700 ] i 1 i 63
- - - - - ------ ---= =ss- -- -- w- i ra--yws- g .p 3 -- --- ---- - - --- - - - - - ,
l U.S NUN AR RmmHY COMMf55WN j Wi ' "" "** CON 0 MONS (continued) l Page 3 - Certificate No. 5687 - Revision No. 4 - Docket No. 71-5687 ; j l
- 5. (c) Fissile Class II and III l (1) Minimum transport index Maximum l to be shown on label Enrichment Transport for Class II % U-235 Index 1
3 0.2 7 0.4 10 0.7 ;
]
(2) Maximum number of Maximum r packages per ship Enrichment Number of ment for Class I packaoes R M U-235 b,\ [q p 5 1,550 390 l l q pD 33 i 10 7 O 234 < j l 6. Uranium enri tN't er than 6 w/o in t ,*]lk3k issk pe must be packaged
. within a 3- onmets or plastic bo t Vrrounded.by venniculite within ; I the 5-gall ocket. g # j (J .
- 7. During tradort and slo p
h
~
ei t
. .}
6 lJ4-inch v holes in the lid or i the option arrangement 4),"1 ~~ 've t hol n the sides of the. drum near topq be 9 wi it'o clude ry of rain water into : W the packag . '% ; bh ' f
- 8. The package ori ., ttMs 4 ir t I ds reby oved for use under the general 11cen $ provi , 0? I
- 9. Expiratton date / ptember 30 Rb l-2 o +
h f,,REFEREEE f( h%% Nuclear Fuel Services, Inc. application ~ dated August 25, 1982. ;. FOR THE U.S. NUCLEAR REGULATORY COMISSION l Charles E. MacDonald, Chief : Transportation Branch ; Division of Safeguards and : Transportation, HMS$
@24 W ; ; Date:
l 64 .! MMMMMMM HMMMMMMMMMMMM5 5 5W55 MMMMMMMMMMMMMMMMMMMMMMM L
l s l o
. s,
----_----------------- _--_----- g I mine ronu sie u.s. NUCLEAR REGULATORY COMMISSION h I ** CERTIFICATE OF COMPLIANCE J l
l to cia n FOR RADIOACTIVE MATERIALS PACKAGES I G PACIL AGE IDEN14FiCATiON NLlW d PAGk NUMBER e TOTAL NVMeER PAGEs b REVtSION NUMBER i a cenTiricATE NUMBER 5740 2 USA /5740/B( )' 1 2 j f, ...-, I a Tn certificate is issued io certify that ine packagmg and contenis described m item 6 below. eneets the applicabie safety stance ds aet toren iT.4. to, l of Federal Regulations. Part 7t. "Packagmg and Transportation of Radioactive Material." I o ins conificate does net relieve the consignor from compliance with any requirement of the reguistions of iM tis. Department of Transportation or orner I appucabie reguistory agencies. menuding the governmervt of any country inrougn or mto which the pack are wil be transported , I hl
; e. ,-.
I
* '."iss'EEo'*r*Er.5*.'**fE"'"' **" # *** ^"*"*'*eT "'Yt !Ado'"o'tE$ATEEN"ts"oEo'NErioN j
\ / [1 l Safety Analysis Report for Packaging (SARP) p t/e :t Oak Ridge National Laboratory q P.O. Box X Oak Ridge National Labo,atory TRU Californium ( if l Oak Ridge, TN 37830 Shipping Container, August 7,1981, Rey \ of !-
[ i 1 N Report No..ORNL-5409/RI., c.DoexsiNuwesR^ ' paun 5
'y 4
,} l
/k ( <
N e - -- 0 a coNomoNs t \y I l Tnsa cemhcate a conditional upon fulfillmo the requirements of to CFA Part 71. as applicable. and the conditions som4:ea 'wim /
+ vr <
=
g ( s q
./ x./ {
U (a) Packaging I' g i < L (1) Model No.: ORNL TRU Californium ShipppqdoptMrer f; (i ' u i e g (2) Description ;. [L ! g _
.,p # L 11 A 304L stainless . steel encased concret4 sM,4ihg cask. The outer (
shell consists of two',1/2-inch thicks ,66-inch diameter' hemispherical ( l heads ,ioined by a 6-inch cylindrical,section. The cylindrical cavity [ g g has a 1-inch thick stairlass steel-wall and b 3 inches in diameter x [ 4 l g 6 inches'long. Shielding .. consists of 720 inches of Bjackburn Limonite 1 concrete having a density ,cf hpproximatelj 175 lb/ft . Upper and .'
~
L I lower level" ball valves located at,the end of ' concrete filled plugs / T if l N define, isolates and seal the cavity. Both of these plugs have 04 ing s l sealss are bolted in place' and are protected with a;gasketed cover E
> {
g plate. . Fusible plugs are located in the cover plates and the shell. L i 4 L i 6 M The top ball valve and plug may be replaced by other plugs for multiple I: l source shipments. Sources are contained in special form containers. [ l The cask is mounted.onto a 1-inch, thick steel base plate by eight h l steel 2-1/2 inch NPS Schedule 40 pipe struts. The cask is transpgtted [ 1 on a special trailer. The package gross weight is 23,500 pounds i R; I-
\
l l. I f I R s , .
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g th um mmmmmm mmmmina mm mu njgamvim u mmeh ' >'. -
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'j
#twronMems.' i gggg g, g U1 a.' tt' - 0: ,
/ I' l '.
/
; Page 2 - Certifica'tp No.- 5740 - Revision No. 2 '- Docket No. 71-5740 bi
' iH
! 4
- Il p '
.g; i
- 5. (a) Packaging (continued) <- 3 j l e I;
t , ,' . (3) Drawingp ' 4 -< - ll T ll The package and special trailer are constructed in accordance with Dak Udge National Labora:.ary JORNtJ Drawing Nos. M-11234-EN-001-D through l p H 008-D, 012-1, 014$ E, 01.'-D dad 018-E, and M-12166-CD-0M/ D. ( Appendix 1 3 A, August b 1981, revision' af ORNL-5409/RI.) / 1
'l (b)/ ontents C \ > f j j o r
J U
.l (1) Type and F.orm %
isREG6, l Q 1 Tbo cantents
-(B&kelium(Bkcoh t of isotopes of Ame'riciut (Am), Curium (Cm),
)! Califo'rnium (Cf),' Einsteinium (Es), Mod Femium (Fm)
[l: j l l h f. 11
/'as I
a soliddhetal, oxide, oxysulfate, or dri falt), h>ntained in T Nl capsule (Q that meet the' requirements of spedahfom radioactive f-(
) ma teripl . i!
4py s .. r
,4 ..+
, #'j
~ l 4
( 2,' Maxiniugi quantity j,sf terial pey packay\ c' q { jl ]
,e For e content s
% k h) [ Q ~
Thrg.(3) grans
, y> and.td,e, m g rixMu2,*infer , y [valijtyt rat {Pexceed 5 watts.
. . ~ .
l-
- 6. /Ainimum of thdft [ripM*fS(y 11 [dIh(t TYftk ps0 Q e. l M< e e t Q })
t) ! t r/ g- % l i
- 7. csi IN,generalpackage license pfpvisiypjM auth'fDJzed CFJt by,0jMfj[N . f/y [i$g'! 7 1[ hen /dy approyE l l l l f 8. Expiration dat'e: ri1 b0, .
4 hUk'M f () 3 i / pa e lj j \ ' p, f 7
, REFEPOCE 'Ne , ; j f / c \# vf ,
w i l f Safety Ablysis Report f,ac Pd(.keging q#P)faf the Oak Ridge National Laboratory TRU l l 9 Californium Shipping Container, August 7,1481 revis, ion of' Report No. ORNL-5409/R1. I J , I FOR THE U.S. NUCLEAR REGULATORY COMMISSION f l,J ' I i j Cha es E. MacDonald, Chief l& _-l ,, i i Transpxtation Certification Branch I'- 1 Division of Fuel Cycle and 4 naterv1 Safety, NMSS if ~ i j, u i n.,te: Aea 2 9 :stu _ / j ,
, o lol !
l Nl .1 1 3 l~ ' I .j 66 I i 1 J l
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i'f
.a -
guurwntg1g9stwierWWE -n* , I , I U.S. NUCLEAR REGULATORY COMMIS$10N ! NRC FORM 81s I e-ci CERTIFICATE OF COMPLIANCE i, I S c'a - FOR RADIOACTIVE MATERIALS PACKAGES [~i . ceamcave
; 5754 nuweea m aeviSio~ ~uueca 4
c racn*oe iocarisicario~ ~uussa USA /5754/B( )F
. eice auussa 1
.. Tot L uuusta eaceS 2 ja i
'N i kM.a I
j a Tn uniticai....u.dio ceriie tnaiin. r pac = aging and conteni.d..crio.d in it.m s e.io.. ..t in.appiecani. v.iv tandard...ttortninTiii.io. coo. of F.d.ral Regulation., Part fli" Packaging of Radioactive Materials for Tran port and Transportation of Radioactiv. Material Under Certain Condetson." E [ l l e rne, o.niticai. do.. noi r.ii.v. m. con.igno, erom compi nc. .im any requirement of m. e.guie,ons or me u s o.panmoni of Tran.ponation or other i ; I appiicabi. reguietory agencies. Including the government of any country through or into which the packag. .ill be tran port.d. k j l l i I l 3 THi8 CE ofiFICATE
. paseaaeo iS IS.SUiO ON THE eASIS OF ev ru .+ 4aw,...;-
ALYSiS aEPOaT OF THe PACKAGE oeSiON Oa APPLICATION A $AFkT o virte ano iosuviric4 Tion or aeroar oa areticAfion / li l i Nucleer Fuel Services, Inc. Nuclear Fuel Services Inc. application I I I i P.O. Box 218 dated November 11, 1966, as supplemented. I; W Erwin, TN 37650 g N I . c_toccano Dwuueen b;. /r. b71 5754 I I ,g -
~t l,l 4 conoivio~S 1 i. e.ni... . . __a, upon ,u,,i,,ing m. ,,,._,,v, o , c,R ,t , . ., sop,.a ... .nd e._i-.
o .p.m.i._. l .
,H l (a) Packaging 9 O<
I X (1) Model No.: RMG-172 Y - 7, D j~ fi l
?)
i h /$y,y R (2) Descrigition / {g The containent vessel is a'6-inch JD by 4-1/4-inch bng Schedule 40 f g g g steel pipe 4.ith a. flanged and. gasketeditop closure.]The containment I i vessel is centered, and supported in-a 16l-inch JD by"*21-1/4-inch long I 0 steel druu of minimum 24 mgauge , thickness by' top and bottom stool 1 1 l i sections. - M it D'" <" i i %a u
- (p p $ 4 4
I (3) Drawing ln 3 l y , _
'T g 7[.! p l The container is' constructed in accordance with'Ndclear Fuel Services, I Inc. Drawing No. RMG-172. H- 1 l
~ - I \
(b) Contents l i l (1) Type and form of material ! i i 1 Uranium metal or compounds which will withstand a temperature of 800 C I (i g without pressure generating decomposition. The uranium may be enriched t'> any degree in the U-235 isotope. The contents shall be contained [ g g within two, 750 cc sealed metal cans. g i I I I I I lA I d' I N I 1 ( I I Il I ' ld- I s! I i I 67 I e I 1 I i
t i W. _ _ . _ . . -.______.._._-....-_,._..._.-..9 nact<>cwcisk V# * #""## CoNotilONS (confonued) l l! Page 2 - Certificate No. 5754 - Revision No ' 4 - Docket No. 71-5754 l l h- I
, (2) Maximum quantity of material per package '
l . Ten-(10) kilograms U-235, rovided the total weight of the contents !. q does- not exceed twenty (20 kilograms. 1
'I N
(c) Fissile Class II llll i Minimum transport index to be shown on label 4.5 l l6. 1 I The top stool section'shall be physically secured to maintain the internal. spacing within the drum in the evpqt the drum cover is lost. lal W I b M C (j f I c. I l 7. The package authorized byghfs% certificate ere ' is for use under the; pproved I l-l general license provisih3s 6f 10 CFR 671.12. f l l 8. Expiration date: Se'
%pJember 30, 1989. D ;!li a
M li l b) REFERENCES yk' ' d Nuclear Fuel Service,b \~ N.# s, Inc. application datefNovemberfil,1966.
- - / ff f Q
l g
/
El Supplement dated: y hetober 77 / 7 11,.1967[2s.i-
~' '
\jy!f jj C g I
; 43; Axc;1,/,g 'f ,f,, e, ,
r 3 L- ' . ;, I It T. U.Fi FOR I ! U.S.' NUCLEAR, REGU[ATORY COMMISSION I
't P<
I I d .u,, T
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a I / O ' Charles l E.fMa Donald,' Chief ja 1
.6 Transportation Certification Branch
'i.' 'f ', Division of Fuel Cycle and lI
- l. 1l l Material: Safety, ffiSS i n
I Date: 20 E '[ N; ~ i I I a I 1 i 1
- 1 I I I I 1 1 I I I I I li ' I l b I I I I I I I I
- o. g I I I I l 60 l i i I _ _ ._ ____.____,.,_,_.m____,_,y I L--__--_____---.__-_-____--___-_-__-____-_____-__-_- -_ - - - _ _ _ _ _ - - _ _ _ . _ _ _ _ _ _ _ _ _ _ - - _ - . - - _ _ _ _ . - - - _ _ - - _ . _ _ - _ _ _ _ _ _ _
l l
- u_
1 l 1 u.s. NUCLEAR REGULATORY COMMISSloN I nc ronu ein I E wi CERTIFICATE OF COMPLIANCE g to ce n ?' FOR RADIOACTIVE MATERIALS PACKAGES I t> REVISION NUMBER c PACKAGE IDENTIFiCAT.ON NUMBER o PAO NUMBER . TOTAL NUMBER PAGES i . cERTwicATE NUMBER 3 USA /5757/B( )F 1 3 a i 5757 E' 2 PRE AMBLE l ( . Tn .c.rtivic.i. . ..u.o io cortityin.iin.p.ck.gino no contenis o crib.o initem so io .m t.in..puc.ei...t.ty st no.ro..et tortn inTiti. io. coo.oi g r.o.r : n. oui.iion . Part 71. "P.ck.nmg of R.deo.ctiv. Material. for Trin. port nd Tr.n.portetton of Radio.ciiv M torial Unoer C rt m Condition. " g q I b ini c.rtitic.i. oo.. not r.ii.v. in. consionor emm compn nc. .ith any requir m.nt of in, reoui tion. of in. u.s. o.periment of Tr.n.portation or otn.r i '
.ppuc.ni. r.ouietury .o.nci... incivoing in oovernment or ny country inrouan or into wnien in pack.a. wiii be tran port o. I W
I I I i
' ' ^
* '.**Ee',"AA'E$^a'v'$.2'U!EE *** ' * "**."'rTI ANo'IEEEc'ATENEi p"oEA'Ar'EIc' AtioN I I g U.S. Department of Energy Safety Analysis Report for 55W Refueling ;
d Division of Naval Reactors Source shipping container dated February 14, y a; Washington, DC 20585 1968. I R I \ R l \ j c oocxEr NUu ER 71-5757 ; W 4 CONDITIONS I N vne. cortienc.i. i. conoition., upon voinising in r.auir. nt. of so era P.ri 7t. .. ppiic.ei.. .no in. conoition. .p.citi.o d.io-. N I (a) Packaging l g l 1 l l (1) Model No.: 55W Refueling Source g 8 l I 8 (2) Description W i 1 A I l f g l The one nested S5W Refueling within the ot6er,'h'avi c Source,shippingbg'ontainer sn' overall envelope consists of two structures, of 5 feet, l n 5 inches diameter'by 9 feet. 5-5/8 inch'esd ength. The outer structure, ; ! E the shipping container, is a ring of polyeth'ylene 11-1/2 inches thick l ;
,dl; with an OD of?6 feet 4 inches and length of afiprcximately 5 feet 2 1
'l inches. The@ polyethylene is canned in a 1/2 finch thick carbon steel I i I
shell. The inner. structure. the replacement'aridjinstallation container, I l fits into/the cavit'ycof the outer structure. This assembly consists g of a 6-{s/2' a l d atinch 0D.@5/8. inches lorigist' inlessG'entral tube. which g gj is plugg both? ends by %achined itainless stgel forgings. Three y d' cavitiestare machined (id the, bottom, erid " plug to codtain the neutron I i source assemblies. '{ A jacket 'oflead 1671nches thRk, encir'cles the 1 is to attenuate the I lg tube and,thisNnhermostMyerlof pofy'ethylen6 84/2 , shielding"6hes in thick, surrounds N central',diationk gamma ra the lead , shield ^and 3s canne
/u walkraofld 1/2dnch WiththTi;k carbon steel n y 3
( plate. Gross y weigh.ttisappfoiitaatelyd9,000 x, pognds. 1
, g.
sh< I i D ' U C , )#'Jh 1 y i y a i py a. - . - e o , 5 4 egy+ l ((
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, CONDmONS (continued l
l Page 2 - Certificate No. 5757 - Revision No. 3 - Docket No. 71-5757 I l l - I g I I l (3) Drawings l l The packaging is constructed in accordance with Westinghouse Electric I l Corporation Drawing Nos. 905D318, Rev. C; 905D315, Rev. F and 905D285, l Rev. A. l g I ' I i i I (b) Contents I i I l (1) Type and form of material I l i Neutron sources of the following type, I y I I I (i) Polonium-Beryllium special form radioactive material neutron i source. These sources may be either new or have surface contamination l l as a result of previous use. I I (ii) Radium-Beryllium special form radioactive material neutron source. l These sources may be either new or have surface contamination as l p I I a result of previous use. ll I l (iii) Plutonium 238-Bery111um special form radioactive material neutron I i source. These sources may be 'either new or have surface contamination l l i as a result of previous use
~U 'l s ; i I 3 I
(2) Maximum quantity. of' material per packa'ge0 . I
/1 l l (i) One, twp, or three neutron sources as described in 5(b)(1)(i) and I limited to a total content of not more than 800 curies and a 'l l combined surface contamination of3 not more{:than'an A2 quantity of l radioactive material. ,
Y' l 4 I
.f. / f; , .. (> gl 1
I (ii) One, two, or. three neutron sources 1as described in 5(b)(1)(ii) si and limited to a,totalcontentjof..not more than 940 curies, with I
, radium limited to not more tha'n 2.5. curies (gms) of this total. 3 i These sources are limited to'a combined surface contamination of 3 i not more'than an A2 quant.ity of radioo'ctive[ material.
1 I!!I!,6 ~ l I o ;l I (iii) One, two, or three ' neutron" sources as des c ~ribed in 5(b)(1)(iii) and limited to a total / content of not moFe than 925 curies and a I l comt,ined, surface contamination"of not mor'e than an A2 quantity of I i
, radioactive, material.
, 4V c l l
(c) Fissile Class A w
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u.s. NucLEAn neoutATony commission I l wneronu no nu coNomoNS (continued i l W I Page 3 - Certificate No. 5757 - Revision No. 3'- Docket No. 71-5757 y j l l l I I I I I l 6. The package authorized by this certificate is hereby approved for use under the I ) i general license provisions of 10 CFR 571.12. l 1 1 4 I 7. Expiration date: March 31,1988. I l l ' 1 REFERENCES I I I I l Safety Analysis Report for 55W Refueling Source Shipping Container, WAPD-0P(R)S-2473 i dated February 14, 1968. l N I f Supplement: Bettis Atomic Power Laboratory letter WAPD-0P(R)C-474 dated December 22, i li 1975. I l- y l !
'! FOR THE U.S. NUCLEAR REGULATORY COMMISSION i
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N C es E. MacDonald, Chief I l Transportation Certification Branch 1 l li s Division of Fuel Cycle and I I Material Safety, NMSS SEP 0 61983 . ' '. M H E G- (/ /, / I l! 1 Date: . g i b
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---- - -- - - y---...- ____________ ____, ! "s"J, ' "" '" CERTIFICATE OF COMPLIANCE l io cra n FOR RADIOACTIVE MATERIALS PACKAGES f i a CERTIFICATE 5758 NUMBER b REVISION NUMBER c PACKAQ$ IDENTIFICA TION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES 2 USA /5758/B( ) 1 2 2 PREAMBLE a Thee certif6cate is issued to certify that the packaging and contents descr6 bed initem 5 below, meets the applicable safety standards set forth in T6t6e 10. Code of Federal Regulations Part 71, "Packsgmg of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions " '
- b. This certificate does not reheve the consignor from Comphance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agences. includmg the government of any country through or into wfuch the package will be transported l "=:===
U.S. Department of Energy
- :====m==A,,-
Safety Analysis Report for S5W Core Barrel Divison of Naval Reactors Disposal Cask shipping container dated Washington, DC 20585 February 23, 1968. j e pocxETNuueEa-71-5758 1 a CONDITIONS This certificate is conditeonel upon fulfilling the requirements of 10 CFR Port 71, as apphcable, and the conditions specified below. l (a) Packaging (1) Model No.: S5W Core Barrel Disposal Cask (2) Description g The container is an u i H r 139 inches highs 58-inch inside y diameter and 111-1 d # The inner shell is either g 3/16inchcorrygal ' late or 1/2-1 [qqbon steel plate and the s q outer shell i W2-inch carbon steel pla't6 unted on a 1-inch base i plate. Shi ng consists of 26-inch thic p'4inforceds high density
- i. concrete a d the inner shell and on the bbt gms and 15 inches of I
carbon s 1 plating on the top. A l-inchJov rj plate is welded on l the top sear ntainer. The ' ainer har a protective cover i around relie of,3/,4- nc f plate () Gross weight is approxihlrtely 180; '
't ll , q e9 und;a' r2 o t v
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Nac ronu sisA l coNomONS (continued Gan i I I I Page 2 - Certificate No. 5758 - Revision No. 2 - Docket No. 71-5758 l I I I I I I l I (b) Contents I I ' I (1) Type and form of materia'l f i An irradiated S5W core barrel which meets the requirements of special I, , l j form material, with between 2 and 10 gallons of water and surface' ; I i contamination in the form of activated corrosion product. p ) y i I I I (2) Maximum quar.tity of material per package 1 Oneirradiatedassemblyasdescribedin5(b)(1). Surface contami-
! l I! nation shall not exceed 3.2 curies of radioactive material. The ; j I special form material shall not exceed 100,000 curies. Shipment shall j not be made prior to 30 days after reactor shutdown. ;
i y ; l '
- 6. Expiration date: March 31, 1988. j l
! REFERENCES l I -
I g I Safety Analysis Report for the S5W Core Barrel Disposal Cask shipping container. 3 WAPD-0P(R)SA-724, dated February 23, 1968. I I i
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Naval Reactors Memorandum G #1363;ldhted June 19,1968. G #1462; dated I i Supplements: t August 12,1968 and G #4470; dated December 12,19744,g }. l g K p p FORTHEU.S.NUCC.EAJREGULATORYCOMMISSION I
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Nj Transportation Certification Branch
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( w x t r,1,1"Safetys 1 NMSSD lgl l{ j SEP 0 61983 0 ,. ,.7
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l NRCFORMSIS U.S. NUCLEAR REGULATORY COMMISSION i
*=> CERTIFICATE OF COMPLIANCE l to CFR " FOR RADIOACTIVE MATERIALS PACKAGES 1
j 1 a CERTIF#CATE NUMtiER b REVISION NUMBER c PACKAGE IDEN flFICAf f0N NUMBE R d PAGE NUMBER e TOTAL fnVM8Eli PAGk$
f 5768 8 USA /5768/AF 1 4 2 PREAMBLE a This certificate es issued to certif y that the packagmg and contents described m item 5 below. meets the applicable safety standards set forth m Titie 10. Code of Federal Regulabons. Part 71,'Packagmg and Transportation of Radioactive Material" b This Certificate does not reiseve the consignor from compliance with any requirement nf the regolabons of the U S Department of Transportation or otner
{ apphcable regulatory agencees, including the goverriment of any country through or mto which the pacitage will be transported j
}
I 3 THIS CERTIFICATE 18 ISSUED ON THE BA$sS OF A SAFETV ANALY$l$ REPORT OF THE PACKAGE DESIGN OR APPLICATION ! e ISSUED 70 theme ener Adamast b TITLE AND IDENTIFICATION OF REPONT OR APPLICATION Babcock & Wilcox Company Babcock & Wilcox Company application !j P.O. Box 11646 dated January 29, 1982s as supplemented.- N j! Lynchburg, VA 24506 P Ii i b l c.oOCxf7NUMoER 71-5768 1 4 CONDITIONS
} This CFlificate is conditional upon fulfillsng the requirements of 10 CFR Part 71, as apphcable. and the conditions specified below I 1
i s i p I il l (a) Packaging l k (1) Model No.: BB-250-2 y I (2) Description > Inner container is 11-1/2" 10, 16-gage steel cylinder, 63-1/2" long,
,, with bolted and gasketed top flange closure and seal welded bottom i g , plate. Inner container is centered and supported in a 22-1/2" ID by l' minimum 74" longi 16-gege. steel drum by 1/4" diameter spring steel
((l rods and vemiculite. The outer cover is secured by either a 12-gage h f closure ring or six (6),1/2" diameter bolts. Maximum weight of R f packaging and contents is' approximately 650 pounds. (3) Drawing fl h($ The BB-250-2 packaging is constructe'd in accordance with Babcock & Wilcox'Drewing No. 10-F-771, Revision 5. 4
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I Page 2 - Certificate No. 5768 - Revision No. 8 - Docket No. 71-5768 I i . I I ' p (b) Contents I (1) Type and form of material i I (1) Uranium oxide enriched to a maximum 4.0 w/o in the U-235 isotope. l Chemically-bound or physically-bound water in mixtures is , l permitted. Slips or slurries that exhibit a visually discernible g liquid second phase are prohibited. I I (ii) Bulk uranium oxide (U0 or0 0 powder with a maximum density of f i 2gU/ccandenrichedkoam$xkm)um5.0w/ointheU-235 isotope. l j The maximum H/l' atomic ratio, considering all sources of , l hydrogenous material within the inner container shall not y
'jk.0 {j l 1 (iii) Uranium,compoundswhichwill]notjecomposeattemperaturesupto 7501F.! Uranium may be enriched to it maximum 5.0 w/o in the U-235. I I !
isotope. The maximum H/U atomic ratio, considering all sources. l l <of hydrogenous material within the inner, container shall not g i , exceed 1.5. #j i I W 4 d* I l I to a maximum of 4.0 w/o in the i 1 1, (iv)[: 7 Uranium'oxidepellets, enriched,.9 U-235 isotope. The~ maximum;H/U' atomic ratio, considering all l l sources;of: hydrogenous' material (within the' inner container, shall y I g 4 not exceed 3.0. J ~j j' "';; g
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sf , s. y l (2) Ma$1 mum quantity offinaterialider pa~cka'ge b )
]- .- . ,;)i } } ) , f - I l I (i)_ For the contentsidescHbed in" 5(b)(1)(1)ij E I l ,
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l l ! Total contents not to exceed 200 pounds, ith the U-235 conterit l j l g 3 i pot to exceed 2.95 kg. gThe contents shall be contained within p ( 1 two.-(2), 9-3/4 inch diameter by 12. inch high sealed stainitss W j j steel cans. Empty stainless steel _ cans will be tesed to male up P! l j the remaining space within tte inner container. l l j (ii) For the contents" described in 5(b)(1)(11): y i I Total contents not to exceed 315 pounds, with the U-235 content 1 i not to exceed 6.25 kilograms. The contents shall be contained I within 9-3/4-inch diameter by 12-inch high metal containers. I l Empty metal cans will be used to make up the remaining space
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within the inner container, y ) 8 1 ! I I I I I i R 5' I f I i I i E I l i 1 I
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, CONDITloNS (continued) . ' M ' "' "M # # UU* M" A*' E Page 3 - Certificate No. 5768 - Revision No. 8 - Docket No. 71-5768 l 1 l b
(iii) Forthecontentsdescribedin5(b)(1)(111) l l Total contents not to exceed 250 pounds, with the U-235 content a not to exceed 5.0 kilograms. Four (4) steel drums containing not I more than 1.3. kilograms U-235 each.shall be packaged in the . I shipping insert within the inner container as shown in Westinghouse l Electric Corporation Sketch SKA-252-1 and Drawing No. C7108D10. g The steel drums shall be constructed in accordance with U.S. g Military Standard MS 24347 with a maximum ID of 8.5" and a nominal I height of 15.4". I I (iv) Forthecontentsdescribe' din 5(b)(1)(iv): l 1 Total contents rnot;to; exceed 250 pounds, with the U-235 content g not to excesd40 kilogramst /Jhe contents Dall be transported I in 9-3/4-inch diameter metal' containers. Empty metal containers I l will(be~used to make up the remaining space within the inner # l container. 'g (c) Fissile Class ._ y x.t,- 7 M,A II and III I
. 2 (1) Minimum transport.index to be shownJon' I J label for Fissile Class II ; f I.3 1 l ~ r ( /.f
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(1) Forthe~confentsdescribedin'5b)(1)(i):l'i,, ( 3.6 l
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O.5 i m l ;pt;,i < l 11 l (2) Masimum number of packages lper shipment for i' l I Fissile Class III
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l' I (1) For the contents' described in 5(b)(1)(1): 30 i )h I (ii) For the contents described in 5(b)(1)(ii), 5(b)(1)(iii),5(b)(2)(iv): 200 l f l 6. The package authorized by this certificate is hereby rpproved for use under the l l general license provisions of 10 CFR 671.12. t I k I 7. Expiration date: January 31, 1988, I i R I l l 1 1 I I I i I i N i N N N i W I 1 N I N I I Il 1 i 8 l I N 76 I I I L ,w . . ---n . . aw. . . m . , m u . . . . . . . ~---aw. . .m. . . . . . . . . . )! .
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I Page 4 - Certificate No. 5768 - Revision No. 8 - Docket No. 71-5768 i a 4 I
' I I
I I I I y REFERENCES 1 i ' I l Babcock & Wilcox Company application dated January 29,1982. I I l I l Supplements dated: August 6 and 20, 1982. l t l i FOR THE U.S. NUCLEAR REGULATORY COM I ! i I I l g4A l Charles E. MacDonald, Chief- l l i Branch ; g e *C Division of Safeguards and l I I k,,. \ fC p. b, aifr- (Transportal on
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Tfa'asportation,NMSS I I , Date: SEP 8011N s '4 O,A l L l l [ I pp n &. ,
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= U.S. NUCLEAR REGULATORY COMMISSION t' to crn n CERTIFICATE OF COMPLIANCE W FOR RADIOACTIVE MATERIALS PACKAGES .h t a crRTiricart NUMBER
{ b REVISION NUMBEst c PACKAGE IDENTIFICATION NUMBER d PAOf NUMBER e TOTAL NUMBER PAGEs 5787 2 USA /5787/B( )F 1 2 huuste t a This certificate is issued to certify that the packagmg and contante described m item 5 below, meets the applicable safaty standards set forth m Title 10. Code l l Of Federal Regulations Part 71,"Packagmg and Transportation of Radioactive Material" I b This certificate does not relieve the cona'onor from compliance with any requirement of the regulations of the U S Department of Transportation or other I appiicabie reguiaiory agencies. merudmo the government of any country throuan or into which tne package wili be transported N l l r 2 Tgigca,vgsgue,o oN , rNe sisis o, a suerv aN4tvsrs,ae,,ga,1,o;,rgrycy,o,E,gogage,a,,g, e ( i l ( U.S. Department of Energy il t DP-4 Safety Analysis Report for Packaging (SARP) of theit Dak Ridge National Laboratory Shipping Cask D-38 j> N Washington, DC 20545 Report ORNL-5406, Rev. 1, August 7, 1981. 'N N N I e ooextr NuussR 71-5787 i e CoNotTIONS l This certificate is conditional upon fulfillmg the requirements of to CFR Part 71, as applicable. and the conditions specified below l l q l ( s l 1 W 1 l (a) Packaging l (1) Model No.: D-38 i l I
! (2) Description h R
l' > Packaging for fissile and large quantities of radioactive material 8 contained in special' form encapsulation. Plutonium is doubly contained. I g The inner cavity of the cask is a 300 Series stainless steel Schedule ' g 40 pipe with inside dimensions 6-1/16 inches in diameter'x 13-13/16 d W inches high.; The outer shell is a 300 Series stainless ' steel Schedule 30 pipe 20-1/2 inches high. Shielding consists of depleted uranium ti metal with a thickness of 2-3/4. inches Theitop opening plug is held in f i place by eighteen, 1/2-inch studs' equipped with nuts. The plug is sealed with a Neoprene gasket. The cask is mounted on a 14-inch i h ! (g . square x 5/8-inch thick base plate. Six of the studs are extra long so l l ((; that a protective shroud may be used during transport. The cask is bolted with four,1-inch bolts to a 3-foot square pallet. The package i W 4 gross weight'is 1,525 pounds. t i'l l (3) Drawings }jh I il The cask is constructed in accordance with Union Carbide Corporation, E l Nuclear Division Oak Ridge National Laboratory Drawing 5 lj Nos. M-12133-CD-126E Rev. 12 and M-12166-CD-022 Rev. 1. l i l f
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N n f f I I L I l' I i I P I I I I I I I , 1
EMm m m.= mmmmmm m m- = =m --- - ma m an'M3EfWMPER"ETE"3NfW35ETTT59tWTd3W3E'5tNINf5b ; E" ~"'" ' f' CONDITIONS (continued) Page 2 - Certificate No. 5787 - Revision No. 2 - Docket No. 71-5787 F
- 5. (b) Contents (1) Type and form of material l
(i) Solid radioactive material including U-235 encapsulated to meet l the requirements of special form radioactive material, , g I >' p i (ii) Solid radioactive material including U-233 and Pu-239 i encapsulated to meet the requirements of special form h radioactive material; plutonium bearing solid must have a E second special form radioactive material encapsulation, g{ l l I d (2) Maximum quantity of material per package y J at, y e The maximum internaf heati notbto' exceed 80 watts; H i l , , , , t, a R I l (i) For the" material described in 5(')(1)(1) b the mass of U-235 not to exceed 500 g. <: i 1 i y { i (ii) For the material described in 5(b)(1)(fi).the ,4 mass of U-233 or 8 ;Pu-239.not to exceed 350 g. - - h l
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l (iii) For any(combination 5(b)(1) ii)1the total combined of the' mass mat'erials described of U-235, U-233, in 5(b)(1)(1) a! and Pu-239 not to egeed'350 g. 4 4 p . (c) Fissile Class
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%j 6. Special form capsule may'.be held.within '
DOT Specification' 2R containers within 4 I f g the cask cavity. ,
$q 7. The package authorized by this certificate:is hereby; approved for use under the .W general license ~ provisions of 10 CFR $71.12.
i , j 4l 4
- 8. Expiration date: August 31, 1992. {Q j l
REFERENCE f Oak Ridge National Laboratory Report No. ORNL-5406, Rev. 1 August 7, 1981. !,
)w FOR THE U.S. NUCLEAR REGULATORY COMMISSION f l
bL 6Kdf Charles E. Mac o , Chief ki Transportation Branch H Division of Safeguards and E; fy Transportation, NMSS gj Nj AUG 7 B6T [i p g; q; Date:
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n...........x...................... ............ . I0eE" * ^" " " " * * " I C'8 " CERTIFICATE OF COMPLlANCE 1 8 FOR RADIOACTIVE MATERIALS PACKAGES I
- 1. CERTIFICATE NUMBER b REVISION NUMf>ER c PACKAGE IDENTIFICATION NdMBER d PAGE NUMBER 5795 0 USA /5795/B( )F 1 e TOTAL NUMBER PAGE5 3
[R g Eg PREAMBLE h M! . Tnes certific.i. is issued to cortify inai tne pack gmg .nd contents descrio.d in item 5 below, meets ine.pphc bie seiety st.ndards set fortn m Titie to. cod. g' or r. der.i n.gui.iions, pari 7i,-e.ca.gma of R.dio.ci,ve u.ieri.is ror Transport nd Transportation o# nadio.ciiv. u.teri.: under cert m conditions.- l l I b inis c.ri,ric i. do.s no
,ei.... ine cons,ano, erom compri.nce wiin any requirement or ine r.guisiion or in, u.s. ooportmeni or T, nspori.iion o, oin., I
.pouc.oi. regui.iory .g. net s. inciudmg in go..rnment or any country enrougn or into wnicn in. package wiii ne eransport.d a d
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! Oak Ridge National Laboratory Safety Analysis Report for Packaging (SARP) p E!P.O.BoxX of the Oak Ridge National Laboratory Foamglas I d Oak Ridge, TN 37830 i Shipping Container, ORNL-5407/R1, as N 81 supplemented. I 8i
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, n L (sD C 71 ,5795 I ,
J 4 CONDITIONS l inis certific no ss condition.1 ui on fuifiiling h"" the ( ,,w ents of 10 req CFR 0Tro,m\ Port 7i, s .pplic.ble, and in,condibons specified below ] f' (a) Packagitg h ! (
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(1) Model No.: ORNL foamglas h{
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l ( W ax . f{y t I I (2) Description yt_ Dy '
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{l g pli Packaging for fissile? material'. lContints 'are contained inside capped polyethylene or stainless steel _ bottles ?which are positioned within p
' i welded stainless steel ~ product cans.K Product cans are positioned in 8 R] 1/2. inch thick flanged containment: vessel consisting of a 4.81 inch f
[ [ I.D. x 18 inches long' Schedule:80 stain 1ess steel pipe (0.375-inch wall thickness) with a 1/4 inch; thick welded bottom plate. The flange j j l h g is sealed with a 1/8-inch thick x 5-inch I.D.'x 10-inch 0.D. silicone y e gasket and 1/2-inch thick blind flange by 8-3/4-inch diameter tolts, jh lil,j Void space inside the containment vessel may be filled with crumpled j i W aluminum foil. The containment vessel is centered and supported 1 1 fI inside a D0T Specification 17H 55-gallon steek drum by solid foamed . boron silicate glass (foamglas) and plywood discs. . Drum closure is by l l g! g g a 12-gauge bolted closure ring with drop forged lugs, one of which is p threaded and has a 5/8-inch steel bolt and lock nut. The package a (l! l 1, gross weight is 215 pounds. I I [ (3) Drawings l' l I i The packaging is as shown in with Union Carbide Corporation Drawing i i No. M-12165-CD-015-Es Rev. 3 and ORNL Drawing No. 83-17092 with the 1 4 top flange as .shown in ORNL Drawing No. 83-17092. 1 I i I I i I ; Ij l N i f I I I I I I i 1 I . { [ i l J I , . 80 t q ' l N_ I _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ . - - _ . - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - ~ ~ ~ ~ ' - ~ - -
I l U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 618A CONOfTIONS (continued) g l l Page 2 - Certificate No. 5795 - Revision No. 0 - Docket No. 71-5795 i f l i I n I I l (b) Contents l l (1) Type and fom of material l l l l Uranium enriched to any degree in the U-235 isotope, U-233 isotope, I I I and as metal or oxide. The maximum H/U atomic ratio, considering all sources of hydrogenous sterial within the product can. fog oxides nust l l not exceed 3.0. Density must be greater than 4.45 g U/cm . Plutonium- i
~
i i a s me tal . I { I l (2) Maximum quantity of mate l j ' 1 R $ 'f' o exceed 15 p sJi.8 kilograms)andthePu l The total cont l i metal conten to exceed 4.5 k11ograms'hp10 watts decay heat. i I III (c) FissileClassg I (1) Minimum shown an abel index to be ss II
/
0.1 A I l i
! (2) Maximbumber o a s !
j ship p for.Cla j i h{l'1000 O j han Pu-2 M @ I I
- 6. Plutonium must Mtai k . . .
For mixtures of anius ! 1 1 d b)f d-likedin5(b)(2), { l7. l the sum of the r mass limits must so exc t . s
$' p e - ss t ir rasgective approved g ,
i j I
- 8. Prior to each ship the wel d i s produc n must be le tested3using an eth avin as vity of 1x10"gk l atm-cm /s or better, glycol vacadioactive ma(terial nust in a capped polyethylene i l
or stainless steel botti eld tn the welded sta nie teel product can. I
- 9. The package authorized by this Ierkig khe by approved for use under the I general license provisions of 10 CFR 57. 2. '
I .10. Expiration date: ' April 30, 1990. l g 1 l ;
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, CONDITIONS (continued)
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'Page 3 - Certificate No. 5795 - Revision No. 0 - Docket No. 71-5795 g' ]
l l
) !
REFERENCES l U.S. Department of Energy application dated July 24, 1981. l 8 ; Supplement dated: September 13, 1984. 1 ., I I i FOR THE U.S. NUCLEAR REGULATORY COMMISSION l l I I B R %arles./4 Ch .dajponald, ChiefD I l l 1 yh Transportal 1DT Division of Fu Material Safet ASS ratification Branch cle and l y, I I l Date: APR 2 41985 g( M/ pA I l' i to i! i r A e \ s, t Ij W i %%[ ,
.. 1$$ q -
l! Q et Ak . Co go t9 +8 i 1l
- r li N k k Wf l, I
l I, B I I i I i I I I I N I I i I I N n I I I I I ,. I I l' I n i I i 82 I N I L______________________________________________________!
____________ s __a____________________________________, Ie w cra n 8 ""
- CERTIFICATE OF COMPLIANCE I I
FOR RADIOACTIVE MATERIALS PACKAGES
, . cens, . __ . n. . -..n . ~ e.. ....ca, - - .e, a..
5796 11 USA /5796/B( ) 1 . ,o,.k 9 n ,.o , i, usta A. Thise certificate is issued to certify that the packaging and contents descrited in itern 5 below, meets the appucable l safety of Federal Regulations. Part 71," Packaging of Radioactive Materials for Transport and Transportation of Radmactive Material Under Certam Conditions."
- b. This certificate does not reheve the Consignor from Comphance with any requirement of the regulations of the U.S. Department of Transportation or other W apphcable regulatory agencies,inciv6ng the government of any country through or into which the package will be transported. I -
i 1 i
* '"J!,"EsS'e'!A*.2.*?J' "/."$*** ' ^ *^'" ^"^'"i vTs'E'EI^ff#!$'578o^,"o'n"YETE., ion Advance Medical Systems Inc. Advanced Medical Systems, Inc. application i 1020 London Road dated June 15, 1987, as supplemented.
l Cleveland, OH 44110 y
.BocSatM. [.! O / 71 5796 b
- '" /
I a couomous i .' This certificate is condetsonal upon fulfilling the reqdr's a of to CFR Part 71 as apphcable, and iditions specified below N
'0 1 (a) Packaging ,
e ' 'p p (1) ModelNo.:k and 181361 , A
.f O a
N
> i., p-(2) Op+eription-rp. 1.y je
<@[ Q l t n ,, .
Oy,prpecks itbatii) ( heapassemh de Twputt 4 sr.h{ng y) p sembifes.1protecQbnfortelethera Tts cubical overpacks J c6vered Qif,g),ies?. Q gisas pentis'. Reinforcing %% teel straps and angles are e ded to
)
theml,to less He t qh 3 aced.t 6f' BM rs are Sovided to tMr Wruan/ooJimit facilitate (l openings fork Jift us kan eJ 9 (1' men 31i>e%6delNo.jlB1375are43.5"Lx l 39.75"W x 41"H wit,h a maxitium gro.85'Might of,$s750 pounds. Dimensions i of thh Model No. 1813 W irt 19 L x N.25"W i 44.5"H with a maximum i l] gross weight of 4,000 p'ounds. , I q %,, . i (3) Drawings ' g l
,1 .
i (1) The Model No. 181375' packaging is constructed in accordance with y Advanced Medical Systems, Inc. Drawing Nos. as specified in l Section 1.3.1 (p 1-11) of the application. 1 I (ii) The Model No. 181361 packaging is constructed in accordance with l Advanced Medical Systems, Inc. Drawing Nos. as specified in y Section 1.3.2 (p 1-12) of the application. y i I I I I I I I l i 83
I "ll " *'** conomous UK "M^* "UL*n Y CU""s'oN Page 2 - Certificate No. 5796 - Revision hcontinued)o. 11 - Docket No. 71-5796 I I I
- 5. (b) Contents l
l l I I (1) Type and form of material i I I 1 l (1) Cobalt 60 sealed sources that meet the requirements of special I l i form radioactive material; or I I i (ii) Cesium 137 in the fonn of cesium chloride encapsulated in sealed l l ; I sources that meet the requirements of special fonn' radioactive i I material or in sealed sources constructed and inspected in l l accordance with Picker Corporation letter dated January 4, 1980. l l (2) Maximum quantity of material per package l l (i) 13,680 e c h)aradioactivedecayheatloadnot ! I to e 00 watts; or AA I I 7A I l l l (ii) g exceed 17 watts.2M curies of cesium 137 with a I 6. The package 11 hppared for shipment - ceiddandunloadedin i I accordance Chsptgn h0perating Proc I I 3 e -; f) I . l l 7. The packag uthorizek isNet 1- - hereby goved for use under I I il the genera icense pr6vft sop}02CFR 12. l
- 8. Expiration te:- y
, Advanced Medical Obs b hi at e 15, Il8/.
Supplement dated: duIf7,1987. ' QI N I Q FOR THE U.S. LEAR REGULATORY COMMISSION I
- Jh M l
I Charles E. MacDonald, Chief I I Transportation Branch I l Division of Safeguards and I i Transportation, NMSS i i JUL 2 71987 i i Date: i l I I I I I I I I I I ; I I I I I l i l I I I I B4 I I I I _ . I
1
,,----------------------A---------------------------
l N*"
'o crR n CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES l e REVISION NUMBER c PACKAGE IDENTIFICATION NUMBER e PAGE NUMBER e TOT AL NUMBER PAGES j 1 a CERTIFICATE NUMBER j m 5797 4 USA /5797/B( )F 1 3 ; l l 4 PREAMBLE I
- a. This certificate is issued to certify that the packaging and contents described in item 5 below, meets the applicabie safety standards set torth en Title 10. Code I i l
l of Federal Regulations. Part 71, *Packagmg of Radioactive Matenals for Transport and Transportation of Radioactive Matonal Under Certain Conditions." l ) I I o. Tnis certificate does not relieve tne conegnor from compliance with any requirement of the regulations of the U S. Department of Transportation or other ) I I applicanie regulatory agencies. including the government of any country through or into which the package will be transported. I ] I , I ; I
" ' ' ' ^' ' ' " ^ " ^ " " " " " " " ^ " "
* "*M!P a E BY a io 3A% "') t E iE t T EOTO CATION I
i U.S. Department of Energy Safety Analysis Report for Packaging: The i i P.O. Box E ORNL HFIR Unirradiated Fuel Ekment Shipping i l Oak Ridge, TN 37830 Containers, ORNL/ENG/TM-9, November 1977, as i I amended. . I l < sCRR E G /hs I 1
' $" c'Ec* ate i. conditional upon fuifisiing tne rgehb io Crn dyns Pari ri. as specified deiow appiicanie5nd f (a) Packaging 9 'O l 1
dj (1) Model .: J $g i ng Contp49 er, and Outer I Innerl4 FIR Uni 4 ted Fuel Elemen l HFIRKinirradiated 91 Elemiifats hi pi : Container %
- l lr (2) DescIption j l l
.w.
/ d i 1 Ir Pac {ng fpy, Uni n r'r c intA DM, in g f6acbV6 matRdtl as fuel elements I I
l 8l for e High- %Is' otop 'l .;lFIR)NThe' container is a right circul_At cylinA csith; p 7* WHl hcarbonfMel s 1. Closure is [ q providedby16f da W Se.1 #1ts wh ' attach the lid to l j s the cylpidrical li' teQ shell i led with laminated l t Douglas p r pl od Mt@)Qpful tg ness o inches. A central I ; I 1-inch thickness of I cavity is ft) ped in the pQppend M ed w polyetheyle am. g The packaging or the in er HFIR fueQplement has overall dimensions y l of 25-inch OD by 450iiict} igga-jy-7/8-inch diameter by 30-1/4-inch I q deep cavity, and a 660 p nd grost weight. I E I N The packaging for the outer HFIR fuel element has overall dimensions I of 31.5-inch OD x 45.75-inch high, a 17-3/8-inch diameter by 31-1/8-inch l (i g deep cavity, and a 1,050 pound gross weight. ; I d q l I I ll I 1 a i N I k l r k i I I d I i 85 l i tj
. . . . . . , . . .... ,, . . . .. , }
l
i NRC FORM 618A U.S. NUCLEAR HEGULATORY COMMISSION CONDITIONS (continued) I I Page 2 -. Certificate No. 5797 - Revision No. 4 - Docket No. 71-5797 I I l l I f I
- 5. (a) Packagin'g (Cont'd) !
l (3) Drawings I (1) The packaging for the inner HFIR fuel is constructed in accordance with Dak Ridge National Laboratory Drawing No. M-20978-EL-003, l i Rev. 6. i I (ii) The packaging for the outer HFIR fuel is constructed in accordance- I with Dak Ridge National Laboratory Drawing No. M-20978-EL-002, I Rev. 6. gREG9 j (b) Contents (1) Type and h of materia
'O i Uranium andc16 djin 8-Alum,cermet, enriched 10-mils-thick, a up toJ3pihbe ./
U-235 isotope,j i (i) the pa 1 . descri, f j)(1)thOntentsare l Rev . q.i f j (ii)Nort 'k 'Tri nc _ . 3{f,()th gaboha}tcry Dr@mng No. D-42126, ntents are l f (Mscri . d p 4 L 1o d i : Rev. O / - 4 I (2) Maxi antf + 1 (1) content 1)(1 he .more than 2.7 kg of (ii) For the te ; described in 5 (1) ) not more than 6.9 kg of U-235.
- g (c) Fissile Class I g I !
- 6. Prior to delivery to a carrier for transport, the shipper shall ensure that at la )
no point along the proposed shipping route that the ambient temperature will be - less than 32'F; or, the shipment shall be made in a ' heated vehicle such that the - -I package temperature shall not be less than 32*F along the shipping route. l I
- 7. The package authorized by this certificate is hereby approved for use .under I general license' provisions of 10 CFR'971.12.
I
- 8. Expiration date: October 31, 1989. 8 l
l
.,, I l
l l l l 86 l l l l i . . .- .
. . ,.. , ., . , .s -
i }
1 U.S. NUCLEAR REGULATOHY COMMISSION I
""f"""^ CONDITIONS (continued)
( l i Page 3 - Certificate No. 5797 - Revision No. 4 - Docket No.' 71-5797 I { iI)- { l r I REFERENCES f 1 I C i l i Oak Ridge National Laboratory Report No. ORNL/ENG/TM-9, Nov.1977. [ A I Supplements dated: July 31,1978; and September 17, 1979. r l ; , I l Department of Energy capplement dated: December 14, 1983. t 8 L 1 ' HE U.S. NUCLEAR REGULATORY COMISSION F l R :oRg# ' g Char es , c id, Chief L
$ Transportation Ce@fication Branch [
g" Division fSddi cy 4 and ( 8 fety. S Matep f i Date: m284 gs -e O [ .
<( [. [,, O L i l] .
Y i i
,***++. r l
o t l' [ l t I { l ( l l i < l [ I. t I ( l C i, l c
"7 I l l....,---... ............ .. . ...- .. ........,.,!
__________._______________________3 "
""Sf""
ea
C'a "
- CERTIFICATE OF COMPLIANCE l
FOR RADIOACTIVE MATERIALS PACKAGES l t a CERTIFICATE NUMBER b REVISION NUMBER c PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES 5805 13 USA /5805/B( ) 1 3 i hEAuBte I
- a. Tnia cernhcaio is issueo io certify that the packaging and contents described m item 5 below. meets the apphcabie safety standaros set torth in Titie io. cooe 1 o, reoerai n.gulahons. Part 71. " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certam Condations."
l
- b. Tnia certincare does not reheve the consignor from comphance witn any requirement of tne reguistions of tne u s. Department of Transporintion or otner I app 4 cable regulatory agencies. Including the government of any country througn or into wnich tne package will be transponed. l t
I
*'**'" ' * ^ " " ^ " ^ " ' " " " " '
a PR P E B7 s' e A%re"sy ^ ' b E D iDE MEf O API' TION Chem-Nuclear Systems Inc. Chem-Nuclear Systems, Inc. application . I 220_ Stoneridge Drive dated April 29s 1982, as supplemented, a Columbia, SC 29210 I i 71-5805 I l g .[hechNuS E G f , , I 1 a CoNomoN. g p' " l l Tnis certincaio i. conoitionai upon vuieming ine r. peps or to crn part 7i. as appiicabie. ana($oyns sp l ] (a) Packaging pm 9 p a l (1) Model NEO CMS 5 xf~ g 4 Q - l (2) Descrjp on g3
+
hk C I A > ,8 The pt$aga is a 4 1 impact ]imiters. Th ,- n:a cask ed,,isad/ - [4e1 M[dedcaskw e1 cyljnderQ33-3/4 inches crushabic l p long ly 50-1 2.! nche : rp ximum cavi -Bimensions of a 36 indies in(j petert . 1 (hb #d I { shield ring at thsd to t i c p P. g Shielsling reduced to is 11 inchesby provided by the 6 inche O' es inf chemt,llnigd ( 5L' a fclosure, < hse plate and l I 5-1/4 i - w ag clos d lr VJ en speel encasemehi! pade u(a twoe (1/2-inch plates on the i ! Theouts1M,he sides and t lates total ng 2-5/8 inchesdrL,the end. The containment ) i vessel is a 1/44 nch thick cylinder with a 1/2-inch end plate. The f .I' shells are weld together with the lead shielding poured to fill the a annular and end spac40 )/ . ,,g'p' l The removable s flanged and recessed base plate weldment consists of l 3/8-inch and 1-1/4-inch outside plates and a 5/8-inch inside plate. l The space between the plates is lead-filled. l i l I i I l 1 I I . I ! I I I I I i 1 88 l l 1 l
l l
------------------------------ W==----------==========-
U.S. NUCLEAR HEGULAToRY COMMISSION [,fowsisA CONDITIONS (continued) Page 2 - Certificate No. 5805 - Revision No.13 - Docket No. 71-5805
- 5. (a) Packaging (continued)-
(2) Description (continued) The base plate is secured to the cask body by means of twelve,1-1/2-inch high strength bolts and nuts and sealed with two s11 cone 0-rings. The cavity is penetrated by a vent line at the closed end and a drain-line through the base plate. The vent line is sealed by a gasketed and shielded plug. The drain line is sealed with a 25 psig relief valve. Cask appendages i c removable tilti nions on the cask s n h trunnions and two, 4-inch Removable i t limiters are provided at the c ends and at the two, 8-in unnions. The fonner consist of a s of 6-inch diameter 1 ed, d tubes. Each impact limiterph bes approximately 6 inches ng 'h he end periphery. .Tosur nd impact limiter has 12 s, s 6 inches long 1
. 'about }ug inches long,
]
a round e sides.' s im iter hasksfx tubes about 6 inch long aro 1 g sqq ' itube actsg the trunnion
' impactA miter. s t .
The ca is s T dip Ilp t ) 3
' . (f Mis ted to the
] trans veh r ,
t , A ,gMde ' ovi . .
~
The gro 1gh . approxim@apy 70 a a t p i feski hs abo sunshade is' 200 pounds.
.(1 (3) Drawings h i \
The packaging Qnstructedinaccordance hem-Nuclear Systems, Inc. Drawing Nos.. MQ 100 Rev. J; C-1 D-0 01, Rev. 0; and C-111-E-0002, Rev. 0; and ATO D@i o 139-1, Rev. K; MOD 140, Rev. C; MOD 124. Rev. ; M 9- 7, ev. G; 0999-C-08, Rev. G; and 1000-D-0024-0, Rev. O. (b) Contents (1) Type and fonn of material Irradiated metal components packaged in secondary cont'ainers. (2) Maximum quantity of material per package Package internal decay heat load not to exceed 250 watts. l 89
- - - - _ _ _ - - _ _ _ _ _ _ _ _ - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l
"lR"A"* coNDmONS (continuM) U.S NUCMAR REGUL ATORY COMWSfdON Page 3 - Certificate No. 5805 - Revision No.13 - Docket No. 71-5805~ l 4 I P 1
- 6. (a) Both the inner cask cavity and the secondary container must be free of water when the package is delivered to a carrier for transport, g I
(b) Except for close fitting items, shoring nust be placed between contents. 1 secondary container and cask cavity to minimize secondary impacts'due to l l l
; accident sequence, il y
l I i (c) The maxinum gross weight of the contents, secondary container and shoring i i is limited to 9,220 pounds. I l- l l 7. Prior to each shipment, the silicone 0-ringseals (base plate and vent plug) R g must be inspected, the seals mus i new seals if inspection shows l any defects or every six ( , ol first.
- 8. Prior to delivery of t hckage to a carrier for tra ppt, the package containment I l be leak ed. The sensitivity of the testgall be at least 1 x i cavjtyshal}/sec(S 10- atm cm l l The packaging conthhmeha y shall be leak tes ed' dtiady and at least l l ivy 2) mon he sensitivity ? ' test sh 1 be at least 1 I N once.gvery x 10 atm em twg/s4 (STP) g(
- 9. The package aut ized by ttii' (tifiaje,is eIybpproved use under the s general license (novision oF 1.12. 4 j!
af ter December .
' chtiog'of agtional packagings s 198 r h ey.,. , ,jf, y C
b 10. Expiration date: ([J cemkr; 3<noh % > '- jf 1~ c.
!! yy< %p g I
71 s$
\ , NlnN y C~o {
ll Nl Chem-Nuclear Systems, Inc. V 11 cation @ date$' '4 Ap@r'1129,1982. OS l i Supplements dated: October 21 e 12, 1984. ' nd$vember 16,1983;4pdJ e#7AE U.S. NUCLEAR REGULATORY COMMISSIO ' 4 ,/POR l f)l U y i 1 8 8 Charles da-acDonald, hief ,! i Transportation Certification Branch ; e Division of Fuel Cycle ' and y i Material Safety, NMSS I Date:
. I e I I
%y I r y L. I d l l
- l b,...--.............._________________________Ji
.----- --- ------------------------------------------- 4 I
une Ponu sie u.s. NUCLEAR REGULATORY COMMISSION
*au CERTIFICATE OF COMPLIANCE I 10 CFR 71 I FOR RADIOACTIVE MATERIALS PACKAGES
! , REVISION NUMSER C. PACKAGE IDENT.FiCATION NUMBER d PAGE NUMBER e. TOTAL NUMBER PAGES 1 a CERTIFICATE NUMBER 1 ,
5814 4 USA /5814/B( )F 1 4 [ PREAMBLE b
- a. Thi. e.rtificai. au.o ic e rtify tn.i tn. p.ekaging ano contenti a..crio.o in it.m s d.iow. m tiin.appiicabi. .at.ty stenaaro...t fortn en Titie to. coo. [
of Federal R.guiahons. Part 71. "Packagmg and Transportation of Radioactiv. Mat. rial" l
- b. Tnis certificat. does not releev. tn. consignor from comphanc. witn any requirement of tne r.guistions of tn. U S. D.partment of Transportation or otn.r b apphcabi. r guiatory ag.nc . incivamg tn. government av any country inroven or ento wnien in. packso. ..ii be transpori.o. I l-l u
(
* ^ ''
l * '*sEI'E*^18 .,',**f'" " '"' *** ' ^ $^" ^"^"*."'E"E ,No'io'e2Cff'NEME,"O T MC#f." CATION l l U.S. Department of Energy Safety Analysis for Radioactive Material l Division of Naval Reactors Shipping Cask NRBK-41, 42 and 43 dated I Washington, DC 20585 March 11,1968 as supplemented. I en f7NUMBER;p-
,t. DOCKET
,- < ny [ )rJ1 a
-5814 k 4 CONDsTIONS t, T,3 %# /
Tns. c,isticai. i. cona,imnai upon suivining in.,,.quirements of 10 CFR Part 71. as .ophcabi.. and the contlitions specified b.iow. y .
,O e
! (a) Packaging ss l I .p i I (1) Modg Noh QBK-41, NRBK-42 and NRBK-pY g I
' (2) De'scription / (,)
I j04A @) j l Top loading cylihdri 1 lead shiel[de 102 stainless"hteel (fclad c f ., I , I for the shipment (of .$rradiated(test specisnens. Cask *rhave a one-inch l I pitck stafnless~ steel'plste-inte esRskid welded to $6 body. In L l ; addition,yhey haver #bited o A Gweldid, .48 fnch sqdare "I" beam ( ) i ikids utilized to'distribbi.e fWe cask"loadP, lie T cavi$y of the casks g i are formsd:by1/4-in'chjth d $tabless stee.)?surroulitied by poured lead [ l syelding swith a 1/2,-thch thM stajnless/ steel cylindrical sheet t I I outer.,shell.MIri[additfort MddliNobNRBKE43 cask has. a seal welded I i 1/4linch thickhstainlessfsthel'out6F'th9nnal ship 1d<h a 1/16-inch I l air gap between thh' prfmaryland,fsecohdary outer.\sfif eld. The physical characteristics of the cashaare (- i n' as follows: t if, , s- s< r i Q ,. % ) ), "y ( y n r j; l L I i l l [ I I I I I I I ( l l l l l l , I l l l l < l i I I I I I I I 91 l l
.im - - mmr - -- -- --- r - - - -- - -- -- --mur mer-- - ------- mmr-a r--nark ------- sur-isrs
-A-A- Aka---------------------------------------------
l N CONDITIONS (continued) 11 f. NUCL(~ Af4 fif GULATORY COMWSMON l Page 2 - Certificate No. 5814 ' Revision No. 4 - Docket No. 71-5814 i i l J l
- 5. (a)(2) Description (continued) !
Model No. NRBK-41 NRBK-42 NRBK-43 l l Outer Dimensions
! Diameter, in 26.5 21.5 21.5 Height, in 39 24 41 l
l Cavity Dimensions I Diameter, in 5 8 8 BREGg Length, in 16 9 27
? Approx. Loaded Weight, lbs
(, i 3,500 /g 6,000 g'iOOO Lead Shielding k y, p Thickness, in g 1 e6f7 A 6 Reference b 41 1, Sh.p) 43-0001, Sh. 1, Drawings Nos, b Rev.}, qd{$ .1,g g .PE G A and n Rev. B and Sh. ),' fa 42[M. ym'*j Sh.12, V Sh. 2, (Battelle Memorial q V' C ,of 2.- Rev. A, of 2. Institute) Qev.TB W l'"" fi "% "7
" - r f , Ig/,/4 5.(a)(3) Product 0@tainErf1 U The conten 5$f6n'fW ackage$ n n j T S,qkagc l' 47 b !
j" - Theinner;p ofuct'cdh thelpltaine64 c)rdthdct' A accorDance ed7 1n n inneftroduct with thecontainers. following Westinghouse ectrfcCohorti ying s.: Gj
'b Dra2ngNos.
ProductContaihiff,, < R,ev. 3 and 971D201, Rev. 4 IN-41 97102074
/g IN-42 IN-43 f )T{ h,.4 971D207t 971D207,Rev.Rev.33and and 9710201, 971D201, Rev. Rev. 44 IN-43 Melba 954F098, Rev. 4 and 904E122, Rev. 2 PR 979C200, Rev. 2 PS 979C106, Rev. 2 WPS 979C140, Rev. 2 T 979C145, Rev. 2 ZT 979C143, Rev. 3 I 9790155, Rev.1 i ZZ 979C144, Rev. 1 E
92 :
, - - - - ssr- - - - - - - - - - - - .i.resm -w-- unsr-- - -- - - - - -- - --- -- - - - - -- -
/l t i j
t m-------------- A-.._s'awaraturErntimebtagl31r&MEEEErWWrtNRWf!mEEEEEErWHI comuwon N****l%^
""l{ ' ""' conomonetcoatmuem ;
/ '
Page 3 - Certificate No. 5814 - Revision No. 4 NcMt No. 71-5814 i l I l .. l i ( l i E. (b) Contents .,
/' {
l t j I (1) Type and form af material , f a i l . I Byproduct and special nuclear material contained with(rJrreduct cont 11ners l
/ J I listed below. 'The contents shall be dry and unmodergted'Q) O X atomic ratio 2) unless specically authorized for the product container, j -
l I 1 '- I Model No. Product Container Nos. I I - I . l i NRBK-41 IN-41', PR, PS, WPS, T, ZT, Z, and ZZ t l l l NRBK-42 h Ib-4 g l f yh
! NRBK-43 IN-43, IN PR , PS , WPS , T, l l ZT, Z, and ZZ <. p )
l ' (2) Maximum antity l D of material ,ser package / 2/p 4 9 limited to a maximum of 350 fl <' i I l Thej ile con ts of the cask sh.al [ i equiy nt gra'ms 'U-235,. qThe 'bM6Vequiva t grams of U-235 is {; s ! t; I detemined by th tioil;df 0 'rM t U-235 + .4' per x grams U-F33 + package shall ( I I 1.6 4fgrams p16tp T h au @Qy heat 1 4 l not exceed ose; O d
. / f g, c p I il; l
- p. q.w M' MioWA ,
J
! Mode W o.. [MNik heh[Ooad;m ,
I Btu e I I, NRBK-4), v em < un
* (t'd 6 Hr G 6 9I = p~ % Ny
- s. a I
M?BK-4h < I.'210048
< ( L l l NRBK-43 7500 Btu /Hr [, N '
!p
%)
q i f W ii I (c) Fissile Class gf II , i, I' Minimum transportb4 d- toown
' j index f>eons[' w Nff d.2 label l s l
- 6. The "IN-41" product container may also be used to , ship NaK filled capsules j
i provided the following specifications and restrict. ions are met. , 1; J i (1) The NaK filled capsules shall be placed intp a, sted or stainless steel' l J
' container with walls at least 1P,4nch thick; a welded closure on one end r j and a pipe cap on the other end. o l j l '
i l-i (ii) The NaK filled capsules shall fft' irithin the container with a maximum play l' ) I of 1/2 inch in any direction. Inn (r fixtures may be used to provise the l' ,j i indicated degree of snugness. The capsules and container must be therenghly I I dry prior to loading. l , I , I i I F l l , I o t-I .b 3' I ,, 1 I 93 , I l l l l l
= == - - --- -- - - - - - - - - - ,: . a - -i r# # - - - - - - - - - --- --- - --- --- - = ru ms f
g ' i m__________.______________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ _ _ j
7 ,
!! i S CON 0 MONS (continued) U S. fdOCLE AR RCCULATORY COMMf5 MON l i '
l Page 4 - Certificate No. 5814 - Revision No. 4 - Docket No. 71-5814 l ! I i l , 1
' fc l l (iii) Sultable pipe ser:11ng compound shall be placed on the threads of the I l
I container top closure prior to tightening the closure. l 4 I L I i (iv) The sealed container shall be placed into an "IN-41" product container with l l a maximum play of 1/2 inch in any direction. Inner fixtures may be used to I ; i provide the indicated degree of snugess. Both. containers must be thoroughly I j i dr/ prior to loading. I 1 I l' i I I (v) The'muimum volume of NaK in the NRBK-41 cask and associated inner container ; 1' I shall be 50 cc. 7 ll I
- i. l l (vi) 'The WP.BK-41 shipping contai g covered with a wrapping of polyvinyl I l chloride (PVC) duripg the internal heat load of the I t shipment does not t , 0 BTU /hr(sanCjshipment is made its a closed I
truck. The app 14 requirements of 10 R")47 .87 rrust be satisfied i l i prior f.o wrapp I e caf.<. -l
?. Expiratin date: 9$riO;0,1980.3 <
f
> hp I I
REFEREkES I Safety Analysis forb*adiative f 42 and 43 dated I l March 11,1968. ( 'p i 1{ Sh}pg pgf.g$ . NRBK-4 V l Suppbr ents: Divihtn of heial ers lette 58 / dated [tane 19, 1968, S# I 1570L dated SeptemtgPj )l' ,D daETl'Te 19' 19gh S# 1658; dated I i I October 22, 1968, S# 1681;5 Q i 7, J 8' ' bpm;6;, 169 dated November 22, 1968, l l S# 1903; dated March * ,1969 . Ute I f(m)e, 2 S# l1969 and,*S# 2509; datedi June 1970 and Bettis Atom owerR - a tr MPDE /IH)-733,@ated October 10, I I f 1968, and Division o yal dedctb.ps 1.e e %5p , dateC April 1,1985; S# 86- I 3305, dated Februar.y 3 1Sp6 ands #"86Q132 x (fed 0 e 16, 988, and Bettis Atomic a - I i , l i Power Laboratory letter 1(A[p-D) PAS)-526Ndte ' June 20,1 l I l h y4 v l l l g F${H p.S UCLEAR REGULATORY COMMISSION l I I I I
,( 4 l l
Charles E. ac on , Chief g I L T"ansportation Certification Branch l I tivision of Fuel Cycle and I i Material Safety, WSS l
! Dste:
JUI 0 9 W ' ' j , I ., . g; I :, \ < g I I I I I e i H i g i lI 1 1 l\ l i I 94 I I '
/ l lmmygge .
. 7- . , _y ,
_l
, a l
+
I I E a cFa " CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES I D REVISION NUMBER c PACKAGE IDENTIFICATION NUMBER a PAGE NUMBER e. TOTAL NUMBER PAGES 1 e cannncArs NuMeCM 5828 4 USA /5828/B( )F 1 2 l I s *EAMets . I
- a. This certificate is issued to Certify that the packaging and contents described in item 5 below, meets the appiecable safety standards set forth in Title 10. Code I
oe e. der.i neguiaisons. Pari ti. eacksame and Tr.nsporiation at radioactive uatoriai - ' I b. This certificate do.s var reiseve it ii consignor from comphance with any requirement of the inguistions of the u s. Department of Transportation or other I apphcable regulatory agencies, w,tudsng the government of any country through or into which the psckage will be transported i I N
- TNiag gTj g 8ISS gUECN THE BASl8 OF A SAFETY ANALYSIS M REgT,OF 7, g PACgA,GEgS4GN OR APPLIC,AT Department of Energy " Safety Analysis Report for the TREAT Capsule i
l DP-122.2 Assembly Shipping Container," Report No. I Washington, DC 20545 LA-6606-MS, December 1976, as supplemented. I I , 9adei$r t F o 71-5828 4 CONDIT474 h8 This cerihete la conditional upon tieliang tna requ reents of 10 CFn Part 71, as apphcable. and fonptions specified below. y ,
.,Q I (L) Packaging .b i l
(1) Mode N GREAT n . j7 hf I (2) Def ption ' y l Pbitaging for R&A cpsu( ss)mb : e inner c ainer is a 1- l 141 4 thick plyyo0@ oA; c e red, wi'$ ga'uge steel t; with an 1 l mflining on top, bottom, I dpinged over. An outer t i I h e on ea Q"I"
'ir,terior idf.0beam;{ndj,0&lrich thg .caccppgainerqcopsi I 1911 (rjl cal, meta)j,t bated by 3 I ihtMes of,ghenolic5foa dnii suppott ' assembly' for e inner container.
I The.uterkont41ndri~s N i 'a metaljtpss framework. The
)( '
( % i l (3) Drawi gs pa[pegres'splghtfi sd ) J (i f D g ,
.f d ?r Q l ipg is as shown' The ReportpacNo ()/l,,A-6606-MS, December 1976..fgures 2, 4, 5 Gn '6 of Los A I
I
'/ $g ' . v yY ')
i fr ; I I I I I I I I I I I I I I i J 95 e
. NU AR H A ORY CONSSION :
l"ff 0"" *"^ cONomONS (continueW l Page 2 - Certificate No. 5828 - Revision No.' 4 - Docket No. 71-5828 l!
- 5. (b) Contents
' l I
(1) Type and fonn of material I (1) Fast reactor fuel pin contains plutonium which is hermetically' l sealed in 316 stainless steel thin wall tube which is further y encapsulated in a 1.125 00, 316 stainless steel with welded or p brazed end caps and contained within a 3-inch OD by 1/4-inch I thick wall steel pipe. The capsule assembly is as shown in I Figures 1 and 3 of Los Alamos Report No. LA-6606-MS, December 1976; or l g I (ii) Unirradiated ORNL-ORR shim rod assembly containing uranium enriched i U-235 isotope wit al ' (2) Maximum quanti R'N- sterial per pack l (1) For t
^
ontentsdescribedin5(b)(1)(i l Not Fissile material n oreMtthan60two grams (2)perfast cm over reactor ek fuel'a. h. Total plutonium I her 'f{ p material not to g 2.1 g.. l 1 (ii) b the con n 11(1'i ): l I g Rbt mor th a k] 2)se . :j. fE 'ssile mat 10not to exceed 1 I hram e) % package ' .not to exceed I Tot'a} U-2 l (c) Fissile Cla p]%j i I h, $.
% l l 6. The package authohNed by $kd ' cert s y appr for use under the Nfe1 i general license prpions of 1 ' C y
- 7. Expiration date: Oct h 1, 1987.
dFEpJNCES I i I T pp 3- % l 1
" Safety Analysis Report for the TREAT CapsuTe' Assembly Shipping Container," Los I Alamos Scientific Laboratory Report No. LA-6606-MS, December 1976. I l
Department of Energy, HQ supplement dated: April 7, 1983. Babcock & Wilcox Company supplement dated: August 6, 1985. l l FOR THE U.S. NUCLEAR REGULATORY COMMISSION I I l l I
&& Mr Charles E. MacDonald, Chief
\
i Transportation Certification Branch j [ Division of Fuel Cycle and - { i Material Safety, HMSS i I Date: N0Y13 m 96 I I 1 l - - - - - - - - - - _ - _ - - - - - - - - - - - - - _ - - - -- 1
i runer=wwwwww----------- - -- -
- A -- ------- ------ - = =----- -- ---4 l l E"$[
io crR n
""" CERTIFICATE OF COMPLIANCE I
FOR RADIOACTIVE MATERIALS PACKAGES l l 4 a CERTIFICATE NUMBER D REVISION NUMBER c PACKAGE IDENTIFiCA7 SON NUMBER g PAGE NUMBER e. TOTAL NUMBER PAGES j t 5830 4 USA /5830/B( ) 1 i i fmEAMBLE I
.. . ini e.onicai.i... u.o to c ruvyin.iin. pack.amo.nd coni nis o cno.oinitem s b io..m tain.appi6cani.safetystanoaros..itorininTiti.io. coa. I i oi r.o.rai R.gui.ieon., Part 71. "Packa0mg of Radioactiv. Materiai. for Tran. port and Transportation of Radioactiv. Materist Uno.r C rtam Conditions " l l e Tnis c rnvicm oo. not reii v. in. consignor trom compiiance wen any requir.m nt of ine reoui,etions of in u.s. o.partment of Transportation or otner I I applicabi. reguietory agenci.e. inciudmo in government of any Country tnrougn or into which in. package will b. transport.d. l l I I I
* '7'PL'"'L's*#d'..'"L"O '"' ' ' '*"" ^**'"."'#0'AN!"JE ti?"#r'lO,#LPOWs,'ATc' Ar,0N:
I Minnesota Mining and Manufacturing Company I Department of the Navy Naval Support Force Antarctica application dated June 28, 1968. l l FP0 San Francisco, CA 96601
; l
<cPnchNuREd'/,*. l .
- d. CONDITIONS Tn . c.rts. cat. . conoamnai upon voivinme o in. rg.kh, io crR pan vi, s.
ogn. .p.ca appiicao . .no
.a b.io. !
l g i i l
+g I i (a) Packaging (
4)' 9A I I i I I (1) Model 44/.: SNNb f, f O I f i (2) Descrgtion h O l 8 A thmoelectfrtc i ]r 16 inct iagletpr byh incties long l l P N gh . l e 7 e :< 1 t,ive/encio e 52 inches in i pack diam (dgepin tet by nche 1;F >>a I oneht 'ef th nerator consist I p . f1a ' ' ,p0-8 M g! of an guter BW } 6165e c ; Er p ( ielding; thermal l insula W p; the ec ndi ' heat pgy ce. Total weight i
't @U J g e g 11 W of the $hkage ff p Und W I (3) Drawings / I f
q The SNAP 21 ns Manufacturing Compa $nstructed Draying No. B-S in accordance whMinnesotaMi l gl in 3M Report No. d69pk f g{7-4014 and Drawings included I !
, i i I i i i l i i 1 I !
ll I Hi ( 1 l ifl I I W I
, I I I il 1 0 1 N N 4
i N I N I ( i l I 97 I I . _ _ _ l
""l ' ** * *
, conomous toontinued) as. m m u m m co m sa l
Page 2 - Certificate No. 5830 - Revision No. 4 - Docket No. 71-5830 l l l 5. (b) Contents l l (1) Type and form of material l l I I Strontium 90 titanate pellets doubly encapsulated by a thin inner i I liner and a 0.2-inch thick Hastelloy C primary containment capsule l l which meets the requirements of special fonn radioactive material. l l (2) Maximum quantity of material per package ! I I 33,000 c1 ' l l 6. The package authorized t RM certificate is pproved for use under the j general license provis of 10 CFR 671.12. l ; i y
- 7. Expiration date: 31, 1990. O i l l ge REFERENCE 4
j l I Minnesota Mining a nufactu ipan ic tedJune@,1968. b F- OR THE U. A EGULAkY COMMISSION N p (O k 1 g ! l l C) M W , dk i 0hl/ ald, C' ' lI I l [/'V A, D-i rtifi f Fue Cycl rial Safety, d n Branch I l i l i i p. Date: M0 2E g I , I I I N I k , I I I I I I I I I I I I I ; I I I I I I I I I I i 1 . I r I h I l ,e i j i I 3 E.
, , , , - . , - ~ , , ., ,,,, ,,,,,..,,.c ,,,.r ..,
i
i 1 i
,y ____________________________________________________
l l E"
C'""
CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL 8 PACKAGES ! I s eacnace iocutirication muuean a eaos muussa . Tovat uuusia emoss ia cenri,icara muusen o acvisio= uvueen 5862 4 USA /5862/B( ) 1 2 ; PREAuBLE
- 8. This Certificate la issued to Codify that the packaging and Contents described m item 5 below, meets the applicable safety standards set forth in Title 10 Code of Federal Regulations. Part 71," Packaging se Transportation of Radioactive Matersal."
- b. This certificate does not relieve the Consignor from CompherK e with any requirement of the regulations of the U S. Department of Transportation or other appiscable regulatory agencess. includmg the government of any Country through or Vio whicf' the package will be transported.
i 3 TH RTIF SISSuE THE BASIS OF A SAFETY ANALYS18 RE RT OF TM E S NO ppt ON I Teledyne Energy Systems Teledyne Energy Systems application dated < 1 l 110 West Timonium Road June 26, 1985, as supplemented. I Timonium, MD 21093 I ;
- fA M rau 9ni a k Q / e 71-5862 0 CONDITIONS E N ]
This Certif6cate is Conditional upon fulfilling the aq me is of 10 CFR Part 71, as apphcable, and gptions specified below.
, . y v (a) Packaging l (1) Modek,po.kSenginel-100F , <Y g I
(2) De [dption I ! l l s Tgefpackage, af,ttiente M @) t 4 k45.5inc spa$
.[jnounting O
in height with i I atesediameterot24plectit'geneesdexcju
~
,5 i pg , and weighs I approximately 2i600'po'und 'The" .rients include a Tungsten biological l shi,c,ld (10QQ5" h)3.A3 .
hj ti ,-T6'moddti Jh Mthipn%e alum $ hum (6061) i hous g padQat the base of I oGrer the aluminye prot,eStfye,gng'/p f} E l p' ping lpalStattachmentpoints. ' I (3) Dra gs dh f, J k9 7 l % ~7h/ /* ' l The pasfaging is constr0cted .i@xaccorilagCe with .4h@following Isoto" Inc. D'rew Nos.: '{ g F 1 010F10000 S$ets 1-3 (Rev. C), Generator Aksembly Sentinel 100F ! l 010-20000 Sheets .1-2 (Rev. B), Fuel Capsule' Assembly ! l 010-70003 (Rev.IPShja g J 010-70004 Shield Flug A}d.Bpdy M ,)h. y l 001-90064 Sheets 1-2 (Rev. A), Shipping Crate Sentinel RTG i i 001-90039 Sheets 1-2 (Rev. J), Sheet 3 (Rev. H), and Sheet 4 j l Pallet Assembly l l l l l ! l I I i I I ' I I I I J l l 99 i
\
1 l i l
._____.___-_-__________a
. , , , , , ...,, . , .,.; ,. 1 , ,,,., , , . , ;.., 3. .
"",,7""'* CONomONS (contmuM) 01 NO AR R ATORY COMWSSION l
l l
, Page .2 - Certificate No. 5862 - Revision No. 4 - Docket No. 71-5862 I
I i
- 5. (b) Contents I I
(1) Type and fonn of material 3 Strontium 90 titanate doubly encapsulated in a stainless steel liner l and Hastelloy or Uniloy HC capsule which meet the requireme.1ts of a special radioactive material. I I (2) Maximum quantity of material r package 1 370,000 curies. g !
- 6. Fabrication of' addit ckagings is not authori ,
- 7. The package author by this certificate is hereby app d for use under the 8 general license o 5.4 ns of 10 CFR 671.12. g
- 8. Expiration date pt 0 1990. ., ,
I
-fREF S h //
I I Teledyne Energy Sysff)s i on< aphj Q [%D._ . ,d l l Supplement dated: A$p t3k l N l . F bj3 h. f b g i
/ I,.j& }
ARREG63TORYCOMMISSION y l 40 W(p l l l k GLs
, ~CliieT '
l ton Certification Branch l l ; Division of Fuel Cycle and i a I Material Safety, feiSS I I I i i i SEPa o BBS I I Date: I I l ! l l 1 I I I I I ' I l I I : 1 I i l I j I- ! l I I I 100 l l 1 1 I ! l .. . l j
purk---------------------------------------------m I I senc Fomassts U.S. NUCLEAR REGULATORY COMMIS$10N I I emi CERTIFICATE OF COMPUANCE I I o C'* fi FOR RADIOACTIVE MATERIALS PACKAGES b REVISION NUMBER G PACKAGE iDENilFiCATION NUMBER e PAGE NUMBER e. TOT AL NUMsER PAGEs
$ a CERTiriCATi NUMBER 5874 5 USA /5874/B( )F 1 3 I r
l AEAMBLE a This certtheate is issued to certif y that the packagmg and contents described in item 5 below. meets the appucable safaty standards set forth in Title 10. Code l l l of Federai Regulations. Part 71 "Packagmg and Transportshon of Radioactive Matenal.** l I l b. This ceruhcate does not rehove the consignor from compliance with any requirement of the regulations of the U.S. Depar' ment of Transportation or otherI l apphcable regulatory agencies, meluomg the government of any country through or 6nto which the package wilt be transported. I I i i I l l 7,wis,g Ti,rge,Ags iss,ugy THE sAsis or A sarETv ANAtvsis,REgt or T,sygE Des 4cgogRergt c,Ag I, Department of Energy Safety Analysis for Radioactive Material : 1 Division of Naval Reactors Shipping Cask No. WAPD-40 dated I Washington, DC 20585 December 1984, as supplemented. I l n id. DOCKET DNUMBER py J1.-5.87,4 g % l # 4 CoNDITaoNs % 4 (,, 8 V/ l This certificate is conditional upon fulfalhng the requirements of 10 CFR Part 71. as apphcable. and the,conglitions specified below. l () % *f' l 5 I Q l *T y (a) Packaging .' - g ( U.) (1)Lfjodel No'.:1WAPD-(0
. .c.
+t s , m ' s- f[L f l7 A)$
O l, (2)tDescriptiori (;; e ) ,e r .g3 _ ,
. %R/ ( ( _Y, 7 is a" cylindrical, stainless steel Cf"TheWAPD-40,shihping,containef, bclad,leadshieldede shipping con}tainerusedto l
$ (" rand non-fuel test specimens.dThe' stainlessisteel~shell 1/2kinch) thick container?has and.an' inner.; an.Typeouter304 Typestainless
.304 I 4 I N
(," steel shells.1 shell;1/4-inch thicks inc10 Th'e"overalljsize}ofg..thelcontainer, Withding 9.875l an integral inches f of*1 l skid, is' 23.25 inches;in;diamster by;158 inches /in length. Gross l [ g q weight (includingskid)?ofthecontaineris'approximately28,000 pounds. The heat removal, capacity'is approximately 2000 BTU / hour. I g The' cylindrical inner cavity is 2 incher 16' diameter and 135 inches 4 ! [ N a in length., Inner containers are required,for all shipments. l j ] StainlessJsteel clad, lead shielded end' plugs bolt into each end, f l One-half inch' thick, plates are bolted over the end plugs to provide r; q g a total end pidg flange thickness of 1.0 inch for puncture r : g resistance. Metallic, pressure'-filled 0-rings between the end plugs 0 I and the container seal the package. The cask may be wrapped in l h H ! polyvinyl chloride when shipped in a closed truck. A special ! holddown cradle is used during truck shipments. This cradle weighs h 1 approximately 5,000 pounds. y j y a i r (3) Drawings l W L ( I-l The WAPD-40 cask is fabricated in accordance with Westinghouse Assembly Drawing Nos. 936F577, Rev. 11; and 936F578, Sheet 1, l ' l Oev. 9. and Sheet 2, Rev. 4. g 3
-]
101 i i
$$f "P .
coNotTNwes (conunuea; . u.s wcteAn necVLATORY COMMISSION Page 2 - Certificate No. 5874 - Revision No. 5 - Docket No. 71-5874 j
- 5. (b) Contents l ,
H i l.' I (1) Type and fonn of material I l l l l l l Byproduct and special nuclear material contained within inner I product containers. The contents must be dry and unmoderated (H to i l X atomic ratio <,2). l i I . I I (2) Maximum quantity of material per package I I I I The fissile content of the cask must be limited to a maximum of 350 l l equivalent grams of U-235. The number of equivalent grams of U-235 j i is determined by the equation: 1.0 x grams U-235 + 1.4 x grams g U-233 + 1.6 x gr I lugg l (c) Fissile Class [ II j l Minimum trahrt index to be shown on label O- l
- 6. Maximum deca tr r package must not exceed ,p, hr. l l
- 7. As needed, ing te sed to limit of contents under accident- l conditions transport. U d5 l # l
!v 8. The liftin runnions co (du ji ansport reclude.the'ir use j as tie-dow vice . .
,- 1 I 9. ThecontentNft at ini! H l1 '#
.k'i aximum measured n at t I I
gamma dose r (a 4 h l M tha side' the for normal I i conditions d no p g ' C3= 0-N)/F. A I where C the W ximum pe isshleammh rate he side- i I 3 = of the skinmrem/h;,J6Eno 1 cog 1ons. l N A =0ma.0 mremMr for shipmentshipments ed sturetural of irrad I i of irradiated I i terials fuel. and K.0 77 are%m/houpo$tt p ! I I I F = factor obtained directly from Table 1 or Table 2-(attached). i I I l For non-fuel whose principal isotope is not included in Table 1, an F factor I i must be determined based on calculated ratios of the limiting accident l i radiation levels to the nonnal condition radiation levels for each of the i i principal isotopes. I 233 I For U with approximately 30,000 hours of effective full power operaggn j l and greater than 17,520 hours of decay, the .F factors in Table 2 for U l i are conservative and may be used. l ! The maximum measured neutron level dose rate on the side of the cask must ! I not exceed 10.7 mrem / hour for normal conditions. I I l l L I I I I I I 102 I I - !______________________- ww=__w-________________________ll
I I LLS. NUCLEAR REGULATORY COMMISSION l I N '" " cowomONS (continued)
? age 3 - Certificate No. 5874 - Revision No. 5 - Docket No. 71-5874 l l 3 l
- 9. Continued l i
L l I For mixed shipments of fuel and irradiated non-fuel, the more limiting C3 l value must be employed. l 1 l I If C is below the maximum measurable level of the gamma instrument, other l methhds(e.g.,thermalluminescentdetectors,sourcestrengthcalculations) l I l must be employed to estimate the expected level for. comparison with C3 . i
- 10. Theacceptancetktsandmaintenanceprogrammustbeinaccordancewith Chapter 8.0 to WMD-RE0(C)-270, Rev. 3. l j l
l 11. The WAPD-40 shipping container may be covered with a wrapping of polyvinyl l chloride (PVC) during shi A h t the internal heat load of the i shipmentdoesnotexcee4'2 hpr(Rif(d 1 i wlV/hbtr hipment is made in a closed I I truck. TheapplicablegeqirementsofCon gg No. 9 above must be satisfied I I prior to wrappings V Tp l i
- 12. Expirationdat(bJuly 31, 1992.
o o l D) REFERENCES - /A I 1 Y I I I Safety Analysis Radioact M tett ip i kiskNo.Nb-40 dated I , l December 1984 ( -RE0(C)- f, t ou
. )
- ..g Q l g
l r Sf85- 8),{dMay6,1987 'l l l t NavalReactorsguppleme (Sf.87-2721) srdi, %g 7 ly .s, I r l
@ %[ [ l .- .-
' l l l h G L Ni Ug ' NUCLE GULATORY C0f911SSION I
hh C arles E onald, Chief l I l Trayosp.M tion Branch I i 'p%l i Yf j{1Vps on Safeguards and l Transportation. HMSS g 1 I D:te: I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I l 2" i l l
Attachment to USA /5874/8( )F Rev. S' Page 1 l Table 1 F Factors For Use in Formula C3 = (1000-h3 )/F J For' Irradiated Structural Material Shipments'Ly l Principal Isotope Isotope Energy and Yield Factor MeV. ' Manganese-56 0.47 ((0.99/ decay) 174 1.81 0.29 2.11 0.15; Cobalt-60 1.17 1.0 1492 1.,33 1.0 Iron 1.095 0.56 -1875 1.292 0.44 l.. f.: L f 1
- j. The F factor is a constant for each isotope because the energy spectrum of.the emitted gamma radiation of each isotope does not change as a function of tine.
104
v e R 0 0 ' 2 8 7 8 2 7 5 7 4 6 2 o) F 8, 0 3 6 8 2 4 5 6 6 7 7 t 3 2 2 2 3 4 4 4 4 4 4 4 ( 4 tB n/ e4 n7 h82 c5 a/e tA g 0 tS a 2 8 0 8 2 0 5 8 0 1 AUP 5, 2 9 9 6 0 5 7 9 0 0 0 1 1 7 1 1 2 2 2 2 3 3 3 3 3 F 1
/
)
_ A N 0 s 0 t _ 0 n 0 4 8 3 9 8 8 5 7 0 1 2 1 e 6 9 9 0 2 4 5 6 6 7 7 7 _ ( m y7 1 1 2 2 2 2 2 2 2 2 2 p a8
= i c
_ h e 3S D C l s a e r _ l u u _ 2 u F o0 0 3 6 8 3 3 7 0 3 4 4 m H8 0 0 0 2 4 5 5 6 6 6 6 e r5 4 2 2 2 2 2 2 2 2 2 2 2 l o3 6 b F2 a U T n _ i d e e t s a U i 0 9 9 9 0 2 9 4 6 7 8 9 _ d 2 1 1 1 3 4 4 5 5 5 5 5 r o r a 3 4 2 2 2 2 2 2 2 2 2 2 2 F r _ I _ s _ r r o o _ t F c a 0 0 5 8 3 1 9 8 8 7 6 5 F 6 3 2 1 8 7 6 6 6 6 6 6 1 3 3 3 2 2 2 2 2 2 2 2 F 2 0 4 9 8 7 7 0 4 0 6 5 2 9 4 3 3 3 1 0 9 9 8 8 8 7 1 3 3 3 3 3 2 2 2 2 2 2 0 9 8 8 2 7 0 6 2 0 5 2 2 3 3 3 3 1 1 0 0 0 9 9 7 3 3 3 3 3 3 3 3 3 2 2 l el n vu o iF i t t 0 0 0 0 0 0 0 0 0 0 0 csra 0 0 0 0 0 0 0 0 0 0 0 erer 1 5 0 0 0, 0, 0, 0, 0, 0, 0 f uwe 1 5 f oop 0 5 0 5 0 0 0 EHPO 1 1 2 2 3 4 5
3seumnenerywurnemnramenweresswwwrwenanananntem_merammmwanesmwwm Ia!,*" #" * " '" to CFR n CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS DACKAGES l 1 e CERTIFICATE NUMBER 6 REvlSiON NUMDER c PACKAGE IDENTIF. CATION NUMBER d PAGE NUMBER a TOTAL NUMBER PAGES 5875 3 USA /5875/B( )F 1 4 I l
, 2 PREAMBLE I a This certificate es issued to certify that tne packaging and contents described in item 5 below, meets the applicable safety standards set forth in Title 10. Code of Federal Regulations, Part 71. "Packageng of Radioactive Materiais for Transport and Transportation of Radioactive Material Under Certain Conditions."
l l
- b. This certificate does not reheve the consignor from compliance with any requirement of the reguistions of the U S. Department of Transportation or other I apphcabia reguiaior, agencies. inciuding ine government of any country inrouan or into wnien tne package wiii be transported. I I
l l l 3
" * ' " ' ' ^
l l
* '"1*l pee $^e'r'5'.2'fi, Ed".' *** ' ' ''" **^'"'*i T E"E ANo'Io'eI'ElA!E"8"E,"o7cfAP C' ATiON .l 1 1 lU.S.DepartmentofEnergy Safety Analysis for Radioactive Material Shipping I j Division of Naval Reactors Cask WAPD-39 and NRBK-44 dated March 11, 1968 I Washington, DC 20585 and August 15, 1968 as supplemented.
l 1
. epochNuR E G f , 11-5875 !
] 4 CONolTIONS j
k .h fA ne specified below inis ceriencate is condii,onai upon fuenuing tne rye 7.Ms of 10 CFR Part 71, as opphcable, and thfifd 8 # (a) Packaging 'd Q l (1) MAPD-39 and NRBK-44
'/J' l Model N hN ' ; M., g (2) Descriftyon k /
4
..f
(~) I 1 TheWhP 39caskIn' e NR$e$44cak re3hysica11y*Mearly identical I and t%}y are funct16n ljy identi al._e_; casks are 'tip loading cylindrical lead gleided p04Li l , t s iglesirstee'l -ti casksf used for shipment of g ; d. irradiated test / spec nn yThe ca Qtf"of the. casks 1rr'e formed by I 1/4-ildh thidfttainless7 shielding withsai /2*ine)pk,gelis,uIr~ounded
%i M by110'incisikr l of outer sfiell sThe risksfa]ro i s h lp[p;e J p a horizontst .inless sition on a! steel cy1Gdric I eam ; d$ch"ls eydip' pedQ{th'four nation tiedown- l steel swivel t"$r naion])blocksi (TheTphys(calf"chiracteri tjes are ; as l N f/ \ l Model No. /j,4 Q{A(APD-39 W 0 NRBK-44 1 OuterDimensions)
/ h I I
Diameter, in h,* }*., 126.75' ,b b "yf 'r' 26.75 l Height, in i 75 75 I I I I I I I I I I I I I l l l l l I I I l 1 f 106 I
.__-___________________________________________________.I l
l l 1
uS WCLEAR HEGWAToRY COMMISSION
! .7Cf* *'" coNomous(continu o I ~
l l Page 2 - Certificate No. 5875 - Revision No. 3 - Docket No. 71-5875 ! l . l-
! 5. (a) (2) Description (continued) l I Model No. WAPD-39 NRBK-44 I
I Cavity Dimensions -
)
l
! Diameter, in 5 5 I Length, in 50 50 1
I Approx. Loaded Weight, lbs 16 500 16,500 l l
! Lead Shielding Thickness, in h 10 q 10 l
I Reference h 39-100, Sh.1, Q 41-0001, Sh. 1 l Drawing h Rev. O, M ev. O and
; (Battelle Flemor al Sh. 2, Rev. (L-agd A;. 2, )
1 Institub0 Sh.3, Rev -af 3 Aw. O, of 2
- 5. (a) (3) Produ ontaine 3 q C
' Iage Thec(tentsof e: t be a d in inn roduct containers, f The igspr pro t*e en are c ~ ed acc nce with the t folldw$g W h a rrh fc on ing .
N notedu d j g , except where 0 DrawijhPNos. ProducOnta tfie ; l i ~ Qs ps "~ v) y IN-39 9 , Rev. and 9710201, Rev. 4 i X 00, Rev. 2 PR f i l N l PS WPS hQ C106, Rev. 2 79C140, Rev. 2 'i T 979C145, Rev. 2 l! q ZT Z k %A Ag 979C143, Rev. 3 979C155. Rev. 1 4 I ZZ 979C144, Rev. 1 l l HW (or Hoke) 1801, Rev. D (Hoke Corporation Draw- ; I ing) and 272E526, Rev. A (General i I Electric Company Drawing) i C7 965D391, Rev. 2 I ZC7 9650391, Rev. 2 , I l. I I 1 3 N I I' l i l l l l- 1 I 107 i L________________________. ___________________________
[ ';",C/ ""* mmONS (continue @ U.S. NUCLE AR HEMATORY COMMISSION l l l
. Page 3 - Certificate No. 5875 - Rem s m No. 3 - Docket No. 71-5875 l
.i I
] I I
l 5. (b) Contents 1
]
I (1) Type and fonn of material l Byproduct and special nuclear material contained within product containers. l The contents shall be dry and unmoderated (H to X atomic ratio (2) I unless specifically authorized for the product container. I I (2) Maximum quantity of material per package l (1) The fissile cont 350 equival n f$ of U- 5. 11 be limited to a maximum of umber of equivalent grams of l U-235 is ned by the equatio , grams U-235 + 1.4 x 1 grams + 1.6 x grams plutonium. j . (ii) Up Mix, C7B3 or C7B3A Irradiation Test e Rods in inner l cotaTn(r"C7"and"ZC7". If less than-Six rods are to be i 1 s ed, sh fissile materials incl in the "C7" or. l 1 inners iners. There ~ to 50Lpquivalent grams I "4(J"235init U- 7 cad F r- r
.Tendero eq ment total (of. 3054 equivalent I ;
ms of U-235
; 1. uGa;1entgramQfU-235-is gr'ams U-235 1.4 x grams U- l termined
+ 1. grtify:,,n A h tonquajip/)in, 10 ti than, six dB7" rods are to y
shi 175< if (n M r$4 Ud359nay be#placed in each I the d7
- lr p r
;HH n c tainers 0winith wS31d be otherwise I em ty. ath" ' ' ;
lr p' " conta n'91x, "CW or "ZC7" sealed . I i con. ' SJ [i t M kp .inum e . tope even though I on p mo @be" y)nt y be .y. i (c) Fisr9eClassh I / (1) Minimum trar F)index -Forthecont6qhs I to be shown on Tabe describe sin 5(b 8 (2) Minimum transport index
% n g mf ed in 5 2)(1): ' 3.2 For the contents described in I to be shown on label i 5(b)(1)(and 5(b)(2)11): limited in 10 j i
i i l' ' I I N 1 I I I I I L I I I I I I I I, I I I I a los l l i i I a
m_ _ _
""U**"" * * * * * "
""C "'***** conoarsons ccontinued) l h
il h Page 4 - Certificate No. 5875 - Revision No. 3 - Docket No. 71-5875
' U h
- 6. Maximum day heat per package shall not exceed 8,400 8tu/hr.
h 7. The "HW" product container may be used to ship test specimens containing small q quantities of water and pressurized gas. The total internal pressure of the : la product container shall not exceed 1,050 psi at a unifonn temperature of 400*F. . C Expiration date: April 30, 1988. j 8. REFERENCES , 1 f.Safety Analysis for Radioactive Mate-11 Spp E ask WAPD-39 and NR8K-44 dated ? March 11, 1968 and August 15, 19
'I Division of Na a teactors letters S# 1387 h ed May 14, 1968, S# :
Supplements:1638; dated October 17, ISB%, # 1570; dated September S# 1597;19, dated : h' September 19,1968, S# 165F, dated October 22, 1968, S# 1681; ember 7,1968, S# I
/c 1690; dated November 2257968, and S# 1903; dated March 19,19WJand Bettis Atomic Power Laboratory lett APD-CL(IH)-733 dated October 1 (1968;$ ision of Naval
#l Reactors letter Z# 8
% 05, et A k' ril 1,1985. .f- l h
'g b f.. O THf%5')N L ]EGULATOR MISSION ;
)
!j <t f- A1 :
ft c
$ hk gg)g e rg
@y625W E cDona d,'Chipf uf g ert$<j t oa ar( ch i
L i L !
d II o# e
l' l k 8 E , 109 t i p 1 L_____ _ _____________________________________________s j i s AR R R uuissa C'"" CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES [ i e cERTincATE NUMBER to REVIS#oN NUMBER c PACKAGE IDENTWICATION NUMBER e PAGE NUMBER e TOTAL NUMBEm PAagg 5894 4 USA /5894/AF 1 3 PREAMBLE
- a. This certificate is issued to certify that the packagmg and contents described in hem 5 below, rneets the apphcatde safety standards set forth in Title 10, Code of Federal Reguletsons. Part 71 " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certam Conditions."
b This cert >1 scale does not releeve the consignor from compisance with any requirement of the regulations of the U.S. Department of Transportation or other apphcable regulatory agenClos. Including the povernment of any country through or into which the package will be transported. i l a,' * '"'*EE,"Ife'o^e'/ f ! ' ,'O'!E.",' *** ' ' **'* ^"^."'TTE No'ic'eTElfloJS8L,"o,'J?!Il" CAT,oN U.S. Department of Energy Safety Analysis Report for 2.7 New Fuel - Division of Naval Reactors Shipping Container dated July 15, 1968 Washingtons DC 20585 g supplemented. y . .FoocONUueER'"h f3 / 71-5894 8 ) a coNomoNs %R t f This certificate is conditional upon fulfilhng the reatnreyta of 10 CFR Part 71. as apphcable. and thiftoInditsor's spec 6fied below f
- s. .m
- yd (a) Packagin 7n .-G (1) ModdNo.: %. Fuel /.I /
- cp y {.s!
(2) Description (y . ~r' f f ; 'l y a n w,4 , h. . The.Model/No. E %t ueT t6ntainer.was designed;to ship and store (p new and urtirradiate(, f l$fueTmodules. Adapters are used to (d permit additforial'sh p 09rpb55W hb ' Core R3 'A1W tor R2, and SIC d Nl Type I 1fuelmodult@ThsA . a- i ssembly consists of two major k l components, aFinne&ddithi n$ e hich holds the, fuel module and an outer container which"suppdtt?s"ttyi i@nneFi;ontainer. iThe steel outer fy conthinerisipproximately24.5incheswidebyl24.5incheshighand 128 inches long. The'tross,sectioh of the outer container is octagonal, the steeFshell thichne'ss 'is 0.1875 inch ASTM A 283 GR.B. The outer shell is sufrounded by a framework of steel stiffeners and rails. , The inner container is constructed from Type 304 CRES plates. 0.1875 g inch thick and is 7. W inches squa~re and 99 inches long. Bolted closure i is provided for each ' container. The gross weight of the package ranges i from approximately 1,500 to 2,000 pounds. I { I I I I I i I i I l I i I a i I 1 i I 5 i I 5 I I I , I i i 110 l ____ -_______ -------.________;________________- _________.5 i l l U S. NUCLEAR REGULATORY COMMISSION l 7"3 Page " '" 2 - Certificate No. 5894 - Revision coNDmONS (continued) No. 4 - Docket No. 71-5894 g l l I l 1, (3) Drawing i l The packaging is constructed in accordance with Westinghouse Electric l Corporation Drawing No. 924J152, Rev. 16. l l l (b) Contents j (1) Type and form of material ! i I Unirradiated fuel assemblies of the following type: l l l (1) S5W Core R2 standard module or corner module; l (ii) 55W Core R3 ag lie r corner module'; (iii) A1W standardclusterd cluster; j i (iv) ShoreTypeIstandardc. luster; O l .(v) re Type I fuel subassembly-y-I (vihS5W tandard module /lftermod ; I (vi A1WCork as 1 1,
- f. Q (2) pximum pj ma EN&T [ { !
l (49'One as' AM 'd i 1N(6)(1g),5(b)(1)(ii),- l 11 ) ,~ .i Jt )(vi)g ~ i l 5(b)((' l l (ii)g9wof EC in 5 )(v). l (iii) pc fuel as em , des ibed (b)(1)(v11). I l I (c) Fissile Class O III Maximum number of pa agkpefphh I (1) Forthecontentsdescribedin5(b)(1)(1), No more than 1 5 i ,5(b)(1)(iv),5(b)(1)(v),and one total core's 5 y andlimitedin5(b)(2)(1)and worth l i : i 5 l 1 I I I I I I I I I I I N I l I l l 111 I I__________________,__-_________________________!, i U.S, NUCLE AR REGULATORY COMMIS$lON Ir$ . CONDmONS (conf /nued) Page 3 Certificate No. 5894 - Revision No. 4 - Docket No. 71-5894 l l (2) For the contents described in 5(b)(1)(iii) 25 total, with the l l number of packages i I and5]b)(2)(111):b)(1)(v11)andlimitedin5(b)(2)(1) and 5L as described in l I 5(b)(1)(vii)and l l limited in I ! 5(b)(2)(111) not to l I exceed four l l l l 6. Expiration date: July 31, 1992 I l; l l I I I ' l REFERENCES j ! Safety Analysis Report for 2.7 Q eg gContainer,WAPD-0P(R)S-2650 dated ! l July 15, 1968. gA (/ I l Supplements: Bettis A ower Laboratory letterNp0-0P(R)S-2800 dated i September 3,1968 and@tD-0P(R)S-3425 dated August 14, g9, andl Depa Energy letter G# 62 pated July 13, 1979. l i ! C/ k.y FOR THE LEAAEGULATORYCOMMISSION. ! l Q) ^ O l l g e + I h I 2 6 E%, t,n K , .:.hachpald, fef i t \ - - -T v 'ti fBranc i J T g ef4 ) !! ;ig(dff 'of 'fe$uar . and I l i anme o2 I l 7*gt,aa"T l , 'h, 5 [i ') l o , ! Yk *
- Y' s !
I I I I I I I I I I . I I I I I I I I I I I I I I I I I I I I l l' I I I I I l 112 L . ... . ... . . . . .= . . . l p------------_-------------------------------------- I NRC FORM Sie U.S. NUCLEAR REoULAToRY COMMISSION I == CERTIFICATE OF COMPLIANCE I C'"" FOR RADIOACTIVE MATERIALS PACKAGES I ti sevisioN Nuusta c eAcxace IDENTIFICATION NUMBER e PAGE NuMeER e. TOTAL NUMsER PAGES i a cenTiricAte NuMeta 5908 12 USA /5908/B( )F 1 3 l7 ' 1 , PREAMBLE j i e This cenificate is issued to certify that the packaging and contents described in item s beiow, meets the applicabie satety standards set forth in Titie 1o. Code of Federal Regulations. Part 71.
- Packaging and Transportation of Radioactive Material." j l
l b. inis cenificate does not reheve tne consignor from comphance witn any requirement of ine reguistions of the u.s. Department of Transportation or otner ) appiicabie reguiaiory agencies. inciuding ine government of any country inrough or into wnsen tne package wiis be transported. l I . I l . l I E DE G O PPLICA l 3 TNisgi,rgrysys,ugoN TNe eAsis os A sArsTv ANALvais,riegTgt,HE PACK I I Babcock & Wilcox Company Nuclear Materials and Equipment Corporation ! P.O. Box 785 application dated May 3,1974, as supplemented. , l Lynchburg, VA 24505 i i l , soMT.IIddfQJ1-5908 I I 4 conDmoNs g G6 4' / l Tnis certificate is conditional upon fulfilhng tne regulfsmehts of 10 CFR Part 71. as apphcable snd the, conditions specif6ed below. l y I s ' /(()< l l (a) Packaging &h t f' (1) Modelho.: sD0,T-6M @ x . 3 Type B g/7" $ g' ! j (2) Delc[iption \ h ! l He't,il packaging a5 h1 I%de crib r%:p , kh+.[ Q) &a d c nstructed in accorda.nce with 00T I I 1 l $1 U l Spe~cification V 3.{ / 6M.)3 M -} g s[_theb/j ,[ ( ~ j i (b) Contel)ts' i en b[i;dg %% M 9N rnpor f ,'pg Y m,/m i s (1) Type and Jfdm%f dateria ' ll , M FM' $2 I DQC 2 l s ih N9 $ l j (ibm Solid' radioactive cinat'eralpi . j f gdp to 'V 250*F#rCarbidefcompouh. dsTare%ot authorDed; ich will'not or decompose at te i l 1 , % ((jgQ gQ' (*;.,y i t (ii) ,UO pror U0 2mixtures,1jf the fom"of/ t powder or,tompact pellets; or I ,ij , "W& (iii) Plutonium nitrate or uranyl nitrate so{utton in flame sealed O I I . glass'atnpoules or screw top plastic vials, each within one or ' ' more additionill plastic, vials wihh' taped lids, and within a sealed product caCor-polyethylene' bottle containing a sufficient I amount of vemiculite t'o absorb twice the liquid contents present; I l i or l I I I I I I I I I I I i I 1 . I i I 113 I I I l t ------------------------------q $"# CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMiG560N Page 2 - Certificate No. 5908 - Revision No.12 - Docket No. 71-5908 l t l (b) Contents (continued) I (iv) Plutonium sources in excess of 20 curies per package must be at l least double encapsulated in a metal capsule such that the sources i meet the requirements for special form radioactive material. I I Inner and outer capsules are individually leak tested during - I fabrication per ANSI N542-1977, procedure A2.2.3 (He pressure bubble test), or equivalent. l i I (2) Maximum quantity of material per. package and fissile class I (1) For the mat Mr imum hydrogen h (1)(1), the maximum fissile age .for Fissile Class I is material g j as fo . p Maximum fissile material O Hydrogen riaterial i F1 e per package,. per package, I 'i . grf kilograms f ,j/ grams 1 1 h' Tk: O l 3<. 9 ;j Q-233 g.5 O s.4 i Meca tay, b'est . libation, the limit for-' I i
- l. (ffu-2 f 0.Uyt
& hwatt thei p9C~ ~ i p Trdexces of 20 curies l f i per Joust 4h h t t ' nn ofh $1, me alloy or reactor. i s-l ce' u L / p')(1). ~ l l (ii) FMthene des ' (1 maximum U-235 I I log for ur ud iswi H/X e. 3 and the I l minw transport i be ass gned g ach pacEage for Fissile Class l .as follows: I 1 Maximum Kgs U-23 kkkp Minimum Transport Index l I ; J l 4.2 0.1 [ 5.4 0.2 l i i I 7.3 0.5 i . I 9.1 1.0 I ) l I l j (iii) For the material described in 5.(b)(1)(ii) the maximum quantity I l l of U-233 is 500 grams at an H/V ratio not to exceed 20 contained within a package size of at least 55 gallons. Each shipment must l l i i be limited as follows: I I I 1he minimum transport index for Fissile Class II.is 2.5 l l l'l The maximum number of packages for Fissile Class III is 51. l .I I " I I l I I 114 l L_____________________________________________________ ! u l ------------------------mA----------------------------- NRC FORM M8A .N R OM COMSSN , CONDITIONS (cont /nued) Page 3 - Certificate No. 5908 - Revision No.12 - Docket No. 71-5908 1
- 5. (b) Contents (continued)
(iv) For the material described in 5.(b)(1)(iii) the maximum quantity j of material is not to exceu! 20 curies radioactivity and 40 ml of solution. Fissile material must not exceed 10 grams. - l l 4 (v) For the material described in 5.(b)(1)(iv) the maximum quantity of plutonium is 100 curies. l
- 6. Two steel through bolts may be installed between the lid and bottom of the steel )
drums. 1
- 7. Venting may be provided 1 m in the drum lid backed by a minimum 1/2-inch thic lt refractory pad. q
- 8. Maximum decay heat package must not exceed 10 wattg
- 9. The package aut eg this certificate is hereb ,4ppr '
for use under the general license ovi H n f 10 CFR $71.12. D
- 10. Expiration daip4 Februa .
991 4 h O . ) q H , td () k d\! rme O , Nuclear Materials an W qui . f% ACyrp 1 i ) ~ i e a > ,' L atio//tfh e 'd 1974. G s Westinghouse Electri rpork . {d )-620 ed May 8, 1973. DOE, NR supplements dah March 28, ; , Ju 9, 1 Allied Chemical Corporation $ port No. ICP-1061 Decembh1974. Monsanto Research Corporation apphap egn y 10, 1980. FOR THE U.S. NUCLEAR REGULATORY COMMISSION Charles E. MacDonald, Ch ef Transportation Certification Branch
- Division of Fuel Cycle and Material Safety, NMSS Date
- N0 5 EW:
115 nenneww nn-------------- --- - -- - --== ==- -- -- ---- ------ - - - .
- )
N"* " " " ""***" C'"" CERTIFICATE OF COMPLIANCE l FOR RADIOACTIVE MATERIALS PACKAGFS I j '] t e CERTIFICATE NUMBER
- b. REVISION NUMBER c PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES j 5910 4 USA /5910/B( )F 1 2 l s PREAMeLE l e This certificate is issued to certify that the packagmg and contents described in item 5 below. meets the applicable safety stanoards set forth in Title 10. Code l of Federal Regulahons Part 71,
- Packaging of Radioactive Materials for Transport and Transportation of Radioactive Matenal Under Certain Conditions."
l
- b. This certificate does not relieve the consignor from comphance with any requirement of the regulations of the U.S. Department of Transportation or other I applicable regulatory agencies, including the government of any country through or into which the package will be transported.
l ' ' ' " ' ^ " ^ " * '."PE"lA'E8's'/fl'.'**".'J%"' *** ' * **" ^"'."'T1"E No'ic'E0fr*iefT fJEUS"O T%A*AP lCATiON Babcock & Wilcox Company ' Babcock & Wilcox Company application dated P.O. Box 785 March 6,1970, as supplemented l y , Lynchburg, VA 24505 i ! <<EkChNuS E Oy49)0 4 CONDITIONS This certificate is conditional upon fulfilling the r e h# d a of 10 CFR Part 71, as applicable, and th# dgons specified below. (a) Packaging (1) Model g : 9(IFD-SA [,7 A I i (2) Descrhion \ M Q l
- l S & CA .ji Fuel aentainer if ~4 gag [s'teki hamaximOutsidecross l l g
4,uafe.dnohj tygasketed 43 closure. Fuel I ) conthinerissectTifnal pper ar a off1 ge ,of,slott R angle iron, with an open . I outs M dimkn ibns' hl ~P W . m. t nd birdcage are l 1 cons Wucted ht;cpr bc4 [y G J$n'sho,t/$6itaine )1 App ix A, Figures 1 i and 2 We , < rc ( rat appM tion dated November 6, i l 1967. -p ,7 g I I (b) Contents Y #[ -' -g l (1) Type and f 'pf material . I Uranium enriched inpe U-23 isot 1 I uranium oxide fuel e em ladjs0,pe2th ittl bondedany enrichment, Zircaloy 2. Elementas sintered I dimensionsareapproxim%s ate 1 0.090" x 3.5" x 96". l (2) Maxinum quantity of material per package ! !{ I I I Total contents not to exceed 240 pounds, with U-235 not to exceed four l l (4) kilograms. I I l l 1 I I l I I I l l l l
- 1. I I
F I I l l l L 116 I I I R,-------- .. . , , . , . . , , . , , , , , ,,. ,,,...v ,. , , , ,, . l I U.S. NUCLEAR REGULATORY COMMISSION l I ((0"** CONOlTIONS (continued) I ' Page 2 - Certificate No. 5910 - Revision No. 4 - Docket No. 71-5910 1., I I I l 5. -(c) Fissile Class III I I Maximum number of packages I per shipment Nine (9) I ! 6. The package authorized by this certificate is hereby approved for use under the I general license provisions' of 10 CFR 971.12. .j
- 7. Expiration date: October 3 pgREGg . ;
j h l l REFERENCES O . 1 l l . Q I dated March 6, Babcock & Wilcox Com app { e h Westinghouse ElectrhorporatNin a li tTo tj' ember 6, 7. l V 1 es 1 o - g . h X i k ii i 0 ,: ULA COMMISSION @ Yg . . si .. 9 , , g Y/ T , ion Id, C rtif on Branch Divii on of Fuel C d 1 h Material Saf ty. S ) I Date: D 2 41984 kkk I I I ! i I I I i l I I I I I 117 i s ,---------------------------------------------------g senc roned sis U.S. NUCLEAR REGULATORY COMMIS$10N I emi CERTIFICATE OF COMPLIANCE I to CrR 7' FOR RADIOACTIVE MATERIALS PACKAGES D REVi$lON NUMBER C PACKAGE IDENTIFICATION NUMBER e PAGE NUMBER e. TOTAL NUMsER PAGES l 1 a CERTIFICATE NUMBER g 5914 3 USA /5914/B( )F 1 3 l - Ra* mbt I
- a. This certshcate is issued to certify tt st the packeging and contents described in item 5 Delow, meets the apphcable safety standards set forth in Title 10. Code I of Federal Regulations. Part 71,"Packagmg and Transportation of Radioactive Matenal." I
- b. This certificate does not rehove the consegnor from co(nphance with any requirement of the regulations of the U.S. Department of Transportation or other I apphcame reauistory so.nciec. inciuding tne government of any country inrouan or into whien the packsee wiii be transported-l l
l
- 7NigTgr;C,Ags;sugoN TNe aAsis or A sArsTv ANALvsis REgR,T O,r,T,N,egggs o oggC,AT
, 4 l l l U.S. Department of Energy Safety Analysis' Report for 57.5 x 108 Core i Division of Naval Reactors Cartridge Shipping Container dated May 6,1968, I Washington, DC 20585 as supplemented. l _ m D C ,p / renDOCKET NUGADER 7 em 4 71-5914 i
- 4 CONDITIONS % 'U # V/
l , This certificate es conditional upon fulfilhng the requirements of 10 CFR Part 71, as applicable, and the,contlitions specified below 3 3 i /d < p() I l , -[ ) c, <, ~ - ' x l (a) Pack' aging - M (3M. s [j?rv,Y $ F) I , i (1)Model No.:? 57.5 ' 108' Core CartrNigel mm I I l < - 1 / %(m) l i (2 M - Descriptiori.'$j M 'f mas, 3 s[ .hm(()\ p kf ,/. p p ;/ %m i i 3 Th e Model'No.557.5 xzl08 CoretCartridge, Shipping Container was I designed for, the shipment 3and! storage lof- new and<unirradiated s I fissile' material. T n I 1 (, barrel assembly _ an,$ 'his fu'it' consists of'two basiciassemblies, l aa l and supports6the= cargo land;1s supported on a shock-support shipping i
- radle that 1's floor mounted'to a transport vehicle. The overall I i : height of the assembled unit'is 155-3/16 inches'and the maximum I ,
planform envelope dimensions 'are 108 by 182'in'ches. The barrel I i assembly 7 consists of two concentric cylinders, an inner barrel and I ! an outer. barrel, and a top plate. The inner barrel measures ! ! i approximately;100 inches in heightL and is manufactured from 1/2 inch i i thick stainless steel- plate rolled:into a 57-inch diameter cylinder I i and welded to a stainless steel flange on the top end, and a l I stainless steel plate on the bottom end which is drilled and tapped I l I for thirty-two 3/4-inch diameter bolts for fastening the outer barrel. i The outer barrel is of carbon steel construction, slides over the inner barrel and is attached to the inner barrel at the bottom flange, lI I l i i i The outer barrel is 61-inches in diameter, approximately 149-3/4 l l l inches high and is made from 1-inch thick carbon steel plate. A top I l l flange is welded to the barrel for securing a bolted top plate that I I encloses the cpen end of the barrel, and a middle flange is welded l l l i
- i. i 1 I I I I I I I i
118 I I I I I .....i l l t 1 l .i .S. f40CLI AR REGULATORY COMMISSION CONDITIONS (cont #nued) Page 2 - Certificate No. 5914 - Revision No. 3 - Docket No. 71-5914 I I I
- 5. (a) (Cont'd)
(2) Description (Cont'd) to the barrel to provide a means of attaching the barrel to the shipping cradle. Within the barrel assembly a hoisting rig for i handling the core cartridge is secured to the top plate with four, : l-1/2-inch diameter jackscrews and four, 2-inch diameter ACME j thread bolts. The core cartridge is suspended from the top flange i ' of the inner barrel. The shipping cradle stands approximately base plate, fou'rteen 8-inch, 96-inches schedule 40 high s ard pensph e'b1Ees, 10 shear mounts and a support ring. Th assembly'is su gpyandattachedtothesupport ring whic turn rests against and it )ttached to the ten shear mountsQatmountonthetopringofthf pping cradle. The ) four@en steel pipes are welded at their to the 1-1/4-inch thick'ste base plate and the 2-1/4-jnc) f k top ring. 'Six stops an6eigh~ti. /2-inchdiameterbolyse(ure shipping cradle to l thltfloor 4ransport vehi 1 < .7he grosi.pight of the pggkaging i pou nd w ,foaded withieither an.S5W Type q 2 o,r R2, or-an o 3 o Ltt,idge, th g ekage weight is ) 48[000poundt,.7 y M -l (3) wings # b % 9, 4; The,4acksgingjsc(9n$iI-)m]- b e f t4 p acco ' ce w Westinghouse Electric Cooperation',9rawiQ 06, f C, 9 14, Rev. D and 90lJ916, b 'j7)% Rev@g. ' k ' h (b) Contents /g ^ (1) Type and opn of material Unirradiated fu aNuembfjeshi following type: (i) 55W-2 or R2 unirradiated naval reactor fuel core cartridge containing a full complement of control rods secured in place by a holdown cap. (ii) 55W-3 or R3 unirradiated. naval reactor fuel core cartridge containing a full complement of control rods secured in place by a holdown cap. (2) Maximum quanity of material per package Onefuelassemblyasdescribedin5(b)(1)(1)or5(b)(1)(ii). ; 119 -----------------r---swww-s------------------------- l l qac ** mA cowomous (continu.o; u.s. Noctc An RtcutATony couvission Page 3 w Certificate No. 5914 - Revision No. 3 - Docket No. 71-5914 i a 1 (c) Fissile Class III ! Maximum number of packages per shipment: One(1)
- 6. Expiration date: July 31, 1992.
REFERENCES Safety Analysis Report for 57.5 x 108 Core Cartridge Shipping Container, WAPD-0P(R)S-2599, dated May 6, 19 Supplemented by Bettis A RM 6wer Laboratory g WAPD-0P(R)S-2801, dated l September 3,1968. Tp I FOR THE U.S. NU REGULATORY COMMISSION fX ( b s it r ns Z ipacDonald gk (tion Bran ief is' g ggg7 asy; iw. , SafeguardQnd n gn, NM l i (f) e - l Date: _ l_M- __ I ' [" ( 4O 4O i I I I N ic k # 5 I I I I I I I I I I I I , I I l' kl l l l : I 120 l l_______________________,y______________________ w \ i.-----------we----------------------d---------------4I . I UA Hl.,kLEAR REGULATORY COMMISSION I I sen.c *m Ponal sie CERTIFICATE OF COMPLIANCE I w orR 7' FOR RADIOACTIVE MATERIALS PACKAGES - l I c. PACKAGE IDENTIFICATION NUMBER g Pt.QE NUMBER NUMeER D. REVISION NUMBER USA /5916/B()F 3 l i . ceRTire$iIi 5 6 1
- e. TOTAL NUM.E ,
I : eRcAMets / l / I .. Tni. e.nificn i. u.a io c.nivy inst in. p.ekaging .ea coni.ni. a critas in ir.m s b.io.. m i. tn..ppiicao4. iv.tano.ro. i.ortn :n Ti.si to.cooe l-i of F.deral R.gulation.. Part 71," Packaging and Transportation of Radlors ctiv. Material." l I n. Tni. c.rtificev, ao.. not rei v. ine con gnor from compnnce wein any requiremerit of ine e.guistion. of ne u.s. o partmerit of Tran.portation or ein.r l l eppiicabi. r gui.iory ag.nc . mciuding one government av arr, ;:ountry throuan or into wmen t.i. pecange weil be tran. ported. , I I . r a t,NisjERTgc,AgeissguoN TNs sAsis or A sArtTv ANatvaisysgt or T,NgAegsysy o4APeggioN I I General Electric Corporation Monsanto Resear.ch Cwporatbn application I Vallecitos Nuclear Center dated March 1,1502. - I " l J, Pleasanton, CA 94566 - l I #' I m JsE n+5ns %8 4 CONDITIONS Tni. c.rtificat. s. conditional upon fuifilling tne e.g R. of to CFR Part 71, s. appin;sbl. and ' ptiona ap.cif14d %% i / I s * /' . (a) Packaging k ' p.y . I I (1) ModeNJio.: 2501 ! (2) Descr b ption h4 g r< .~2 h ' C' s% (g 374
- f. ) ,-
s ,i , o ( . s i l shjelded gnater section. I I Thdackagir)g(coniibottom.p,c-abnthh cctmo'n top,an n sectionsh ' a,sp'tof twp' extension seetions. , I Shieljling isdprovid64 fn FYiiilt P t3on byMccessivp layers c" ' ,. l trow, leadgetifBenp1It s 4 1 ai:t l'imfjes ar neluded in dhe >I o k' i i diie gectiorsib60lte the adjacent i topan((bottoW$ectiot.. sectiofiandboljeQof 3 p ykid g adle ass y. The crosu I sectiqbgeometrylistbaffia, ; ctagonalpj8" acrossjthe flats. The , x> ; I length ranges from a M roximat l l weight 6f t 450 lbs. ~Q p 'y\l23 tg~g4 feet with9, maximum gress' (3) Drawings j f; l The packaging is c6e$tructed t jn acpjydahife with the " followTrc Monsanto l Research Corporation Dragng*fys.Tg , E 2501 - AA00, Rev. 2 D E501 . AG00, Rev. 2-l E 2501 - AA01, Rev. 2 1 D 2501 - AH00, Rev. 2 / i 1 E 2501 - AA02, Rev. 3 D 2501 - AIDO. Rev. 3 1 E 2501 - AA03, Rev. 2 I I I ' I ' , 4 l I i I l ' I H 's-- l It x l 121 _-wl x m - _ - run w r h _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ w _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ ,, % "* " '" " cowomON3 (conhnued) U.S #4UCL F2 RECutMony COMmss>ON l l 1 oge 2 - Certificate No. 5916 - Revision No. 6 - Docket No. 71-5916 l l I
- 5. (b) Cortents I (1) Type and form of. material l.
Po.Se, Am-Be, Pu-238-Ba, and Cf-252 neutron sources. Sources must ! Lee t. the requirements of special form radioactive material. I I (2) Maximum quantity of material per package 1 1,509 curies of PoBe, or Am-Be, or Pu-238-Be* or 8.25 curies of CF- l 252, I load gene h h t exceed 60 watts of decay . Wutonium T4,,hxcess' of twenty (20) curies per ekage must be in the fonn of refirl or metal alloy; or contained wit ouble encapsulated l I sleel t be leak tested I stairdPg$1y, independ gpurce R stcapsules. Bothcapsulfs show3 no leakagg r-A tes aving a minimum I sensijfstJtv of}6 4{.B 48"Cand atm leaking to I lx1ff fat (d. g' tm-cm (~%/sec "' (a e . l l (c) FissileClaI i ; l For packagt. ont1 hg - I [
- 6. The contents must A se 'ri theHhi t" iti , f the- ckaging by the source assembly, dmf loc yi @ bJ mbly m@ be of sufficient l g
length and diameterMo prty positi ,ps of th y rce in the shielded I position. b ( p f g i d, The nameplates must be 4 r cated of materials capab resisting the fire test of 10 CFR Part 71 an A{naintain their legibipy. 7. l /~ 8. ' The package authorized by this rNficYtbTkhe by approved for tise under the a general license provisions of 10 CFR 571.12.' I ' I J 9. Expiration date: April 30, 1992 l n I s; / ' I I I I ' I i ' 1 O. F I I o I! I' 122 l 1, i. m____mm__________m__________. .i. , ,,4,________________________.______________________.----- uc uone osa *'*""'"#""'**#'*" ""~ conomous (continued) ' N ge 3 - Certificate No. 5916 - Revision No. 6 - Docket No. 71-5916 REFERENCE Monsanto Research Corporation application dated March 1,1982. FOR THE U.S. NUCLEAR REGULATORY CC:9 FISSION g, Charles E. MacDonald, Chief Transportation Certification Branch .k a S Date: APR 0 2 BS7 D ix C(f . < ' o$ g wq ;7 4 o 7 a k~ si f ' O r % - E i to k , <p g fy"tuk v b O, , G 4d) <g f o 4 ,k k * + c >F 1 L '.k I 123 I. a h s 1 . g I I I I E "" 'o can " CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES I c PACKAGE iDENTiHcArtoN NUMBER d PAGE NUMBER , a cemrencATr NUMeta e newsioN NUMBEM 5926 10 USA /5926/B( )F 1 e TOTAL 3 NUMBE l 2. PREAMBLE h I a This certificate is issued to certiry that ine packaging and contents described initem s beiow, meets ine apphcenie safety standards set forth in Teii. io. code et l l Federal Regulations. Part 71," Packaging of Radioactive Materials for Transport and Transportation of Radioactive Matenal Under Certain Conditions." g I b This certificate does not reheve the consignor from compliance with any requirement of the regulations of the u.$ Depa1 ment of Transpo#tation or other l l apphcabio regulatory agencies, including the govemment of any country through or into which the package will be transported. l l l 7Nis4s,a,grgigssueo,ogs,sAsis , or A sArrty ANAtvsis,neg,ogt,N,egsysgogcg,, I General Electric Company General Electric Company application dated l l P.O. Box 460 January 25s 1980, as supplemented 1 I Pleasanton CA 94566 I e I I 71-5926 l l s oocnet NUueta I Th c rt to is condillonal upon fulfilhng the requirements of to (,FR Part 71. as apphcable.end the conditions specified below. I I I * (a) Packaging i I I l (1) Model No.: GE-100 l l (2) Description I I I l A steel encased lead shielded shipping cask. The cask is a double- l walled steel circular qndf( 41/4-inch diameter by 27-1/8-inch l i,) l high with a centr lQ v dy 7-5 EF 3ch/piameter by 10 inches high. l i I Approximately 8inchesofleadsurrotyd he central cavity. The I cask is equi ith a cavity drain line lifting device. Closure I 1s accompli by a gasketed and bolted st lead filled plug. For I l' additional elding leads tungsten or uraniumpiners may be inserted I i i in the cag caQty% The maximum wei - .the pdgkaging is 4.800 ll l l pounds. g ( G ? O l l (3) Drawing [ Q l The p gin s Eons,trhtted in iac phiange' with e following General 'N l Electri omp riwig 7 729f872 M Rev. 2 2904729 Rev. 3; I i i 129D473 : Rev ^and 17 T J ' V'f l . ; l ~ i c> < L f % i l l Q . i i h &g{&h ** I h l 0 o S ljl I l Ij >Fht. w nn44 ,i al l l l !lI 1 I I !, )t l i i 1 l fW j l' m i w__--~~--- J 1 I U.S. NUCLEAR REGULATORY COMMISSION Nac FonM sisA l pa coNomONS (continued l y l ) l I I Page 2 - Certificate No. 5926 - Revision No.10 - Docket No. 71-5926 ; I I I ! I l l ! l I ! 5. (b) Contents l I I I (1) Type and form of material l I I I (i) Byproduct and irradiated special nuclear material in the form of I I fuel rods, or plates, fuel assemblies, or meeting the requirements l of special form radioactive material; or l y N (ii) Solid nonfissile irradiated metal hardware and reactor control l g ! %I rods (blades). I ! (2) Maximum quantity of material per package g [t i Radioactive decay heat not to exceed 400 watts and 500 grams U-235 ! equivalent mass fissile material. (U-235 equivalent mass equals U-235 l I 1 mass plus 1.66 times U-233 mass plus 1.66 times Pu mass.) l I I I Plutonium in excess of twenty (20) curies per package must be in the- l form of metal, metal alloy, or reactor elements. l l I II l (c) Fissile Class . n H. R E n l ) l Minimumtransportindextobeshownof1'ad(1 s Contents 5.(b)(1)(1): l l l <v g \ l N' .sq)'o' 5.6 I i i i i s' 6. Shoring shall be provided to minimize movement of contepts during accident conditions of transport. - 'L l l l !;; e p Tw(s /[. _Pfj g I 7. At the time of delivery of the loaded;packagej to;a carrie,r.for transport, the l I package contents'shall be dry and the fissi) Inaterial
- unpoperated o (H to X g f
s atomic ratio less than 2). q# , _ ) il , y . ., l , ,- v q l j Prior to each shipment the silicone rubber 11{d gasket shail. be inspected. The ( ~ i i 8. ' y silicone rubber gasket'shall be replaced;if inspectGn sh'6ps any defects or g I every twelve (12) months, whichever occurs ;first;i tavity-drain line shall be y I sealed with appropriate sealant appliedito threalds of pipe plug. y i nl m t l
- 9. The package authorizcd by this certificate is" Nereb pproved for use under the J l
f[ general license provisions of 10 CFR 571.12. - l
- 10. Expiration date: Decembe'r 31., 1987. t JJ l
. ~ y , Ni l 81 l I l! i I li ! i i I l y 10 .g (j 125 !g R {iww.rwwwwwwwwwwwwwwwww.-----.......www,,,.,,r,wwwwwwww_gwb NatC PORM si4A U.S. NUCLEAR REGULATORY COMMISSION < (643) CONDITIONS (confirmed / g I l Page 3 - Certificate No. 5926 - Revision No.10 - Docket No. 71-5926 I I I I REFERENCES I General Electric Company application dated January 25, 1980. l ! Supplements dated: August 26, 1980; and September 7, 1982. I I FOR THE U.S. NUCLEAR REGULATORY COMMISSION I I ^ i Charles E. MacDonald, Chief i Transportation Certification Branch I Division.of Fuel Cycle and , 1 Material Safety, NMSS l l ! l Date: SEP 0 61983 j 1 1 I 1. I l g v-- [3,R R fig gQ l . c .t <f &g . O l: q ,? ; 9.! - l LQ .; d' L) \ / .gk}/ L, 1 ? ,C,'y jfg i C s ' fi; /f i O 5 ,- P l , k '"[f n, ;. ,t , l L f r' rh ~, l~ l . I) k. ,:: , t ' i ': k ,. - ' ' jl, ' ;u L i j .ul[a[f,p w [' n ,? ,,% 4
- 4:. j. f.
I d !, f 0t 9 - g A:. .,- s ; -W:y e s s~ g . g , 'f.i g' s> l / N ., 'h i l R ll 126 ll ruwwwwwwwwwwwwww----------------------------_w- -w--- -w 1" CERTIFICATE OF COMPLIANCE f"sS[""" C'" " t a CERTIFICATE NUMBER FOR RADIOACTIVE MATERIALS PACKAGES b REVISION NUMBER C PACK AGE IDENTIFICAT ON NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES l h 5939 12 USA /5939/B( )F 1 3 I l a eeEAuett i 1 a This certificat is issu.o to certsey inat in. packagma ano contenis o.scribeo in it.m s below. m..is in.applicabie sa fety standaros set iorin m Titi.1o, coa. I q or r.o.r.i R guisiions. Part 71,-Packaging of Raosoactiv. Mat. rials for Transport and Transportation of Radioactive Material Uno.r C rtain Conoitions " g l b This certit. cat. ooes not r.n. in. consignor erom compiianc. witn any requiremoni of in. reguistions of in. u s o.partm nt et Transporistion or otner 3 1 appucabi. ,.guiatory as.nc . inciuoing in government or any country inrougn or into wnien ene packag. win b. iranspori.o 1 I I-1 1 * '"N',"lA'EE^.'v'<S'JfM',"^* a ' * **" ***."'E"E Eo'EE'Ec^fTWENtr"ON' Sold?"c, TION ) General Electric Company General Electric Company application dated I I 1 P.O. Box 460 February 21, 1980, as supplemented. 1 Pleasanton, CA 94566 E 1 fl! , e foocktNUN hy39
- 0. CONDITIONS % %=# ' [ A Tnes certificate is conottional upon fulfiihng the rg.p.ets of 10 CFR Part 71, as applicabt., ano the condigns sp cified below s.
Q - 1 1 (a) Packaging s (,) N p 1 T N (1) Model Np 1500 %; h f[$ '[ A l y (2) Descrihon f x g ,, i c-g l 3 i A stepl encased 1sa hieldePshipp p Icas^k. The caTd is a double- I d lI walled steel circulaMcklinderdidnph?d.iameter by 4jkinches high I ' with *p-tentral'!cavith7-iinch diameterJy;25,iriches h}gh. The diameter i 3 I 1 Xinches <by'cbne corgstruction at the is reduced f^ rani 31 inchesitoy! ryximatelyJ1.1 inc((e's of lead surround l top 721/2 inchesto.f,thelcaj(k . 1 y 1 4s ; } l , 1 the lifting ceqtral cajity.,/ The@HlagampQhedjhk a gasl@ted and boltedpquippe deviceMClosurE l I 1 steel leidtfilled, 'pl69. A protectiveJcket congjgt'ing of an upright a li circular cy1jnder with?open b I f diametrically;across the top {ottom andSprotrudi'ng andhertically do the sides attaches box section to l g a square inches high by'4 pallet,h,-3/4 inches wide across the-box section. Dimensions of i the pro fl 1 1 cylindrical diameter;is 35-1/2; inches Jnd the pallet is 59-1/2 inches The outer I squa re. The maximum weight of(thedackaging is approximately 15,000 I %[, pounds. I f f (3) Drawings fI $ The packaging is constructed in accordance with the following General I % Electric Company Drawing Nos.: 129D4748, Rev. 3; 12904749, Rev. 3; I and 129D4750, Rev. 3. l {f/ Lifting and/or tie-down devices which are a structural part of the I g 1 package must be in accordance with the above drawings. I 1 1 1 1 1 1 M i i i 1 1 1 i 1 1 1 127 1 1 1 l ---------_ -__--_--____---w__ ..,______________ -_-_-__, l ,--------------A------------ -------------- . $",c roRM 618A - U.S. NUCLEAR REGUL ATORY COM'/t$550N CONDITIONS (continued) . I Page 2 - Certificate No. 5939 - Revision No.12 - Docket No. 71-5939 I I I I l' l l S. (b) Contents l I (1) Type and form of material l I
- (1) Byproduct material and'special nuclear material meeting the l requirements of special form radioactive material and antimony I pins encased in stainless steel; I (ii) Byproduct material in the form of 90SrF 0" 1 CsC1; 2
l (iii) Solid nonffssile irradi metal hardware and reactor control ! rods (blades) ke i (iv) Stainle encapsulated solid Co-60 sources. I (2) Maximum ity of material per package Q ; Not to ce decay heat generation of J,1p w and-1 (1) ((pm5(b)W bove: g i p t. . a, g-ur et 'r3 package C I I P utonium if of~ be in the forn I metal , me a loy CRr act rF fg1 element nd 500 grams l r' p235e '[ Js. t v-r $v'alet, mass uals U-235 mass 3 (ii) 5(1 h,11 i . e l % I l 4 00c$rp.N ',h l (iii) Ite )(1)(iv)-above / \ g , 1 O i ! l 200,00 es. h I f (c) Fissile Class kpgg III I Maximum number of packages per shipment 22 i f I I {
- 6. For the contents described in Item 5(b)(1)(ii) above:
l l { 90 l SrF Rev. 8;must be encapsulated and H-2-66758, Rev. 0;inoraccordance with Vitro Drawing Nos. H-2-66759, l l l 137 CsC1 must be encapsulate'd in accordance with Vitro Drawing Nos. H-2-66760, Rev. 0; and H-2-66761, Rev. O. l
- l. , .;
' The 90 SrF and 137 CsC1 capsules after fabrication must' be leak tested using a i l method rate (air at standard i j temperaturehafing sufficient leakingsensitivity to 10-2 atm) ofto10" detect a leag'atm.cc/sec. l l I! and pressure Any capsule I with a detectable leak may not be delivered to a carrier for transport. j l I i l- I i l 128 I i l I I I l num--.mm--m-mm--------------.------------------mm---m-m .S. N M AR H A R SSION li ""7 """ - CONDmONS (continued) ir I! Pa ge 3 - Certificate No. 5939 - Revision No.12 - Docket No. 71-5939 h' W I . . I 7. . The package authorized by this certificate is hereby approved for use under.the I general license provision of 10 CFR $71.12. f 8. Expiration date: December 31, 1987. ! 4 I ) l REFERENCES I I General Electric Company application dated February 21, 1980. ~ l Supplements dated: September 8,198 usQg and April 12, 1985. Oak Ridge National Laboratory 8(,1 datedApril3,198!. I Supplement dated: May 7 0. O q ORY COMMISSION FORTHEU.S. NUCLEAR)E , I, N g ; - . q <c t a nJ1d',Chiefh l ,( 6 Chap Tr4nspp esk' tatertificatioMranch c y Hvilsfonn 1]Cyc}e and g (f) shwL tamri t Sf [Q)gVf) Date: uAY n 11!BS _ 4 i - - Q h l, A k k W f' 1 I I I I i i i I 129 l------....------------ . ............ .............. d i r _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - - - _ _ _ _ _ _.- - - - y I mne pone sie u.s. NUCLEAR REGULATORY COMMISSION I I ** CERTIFICATE OF COMPLIANCE I to crA " I FOR RADIOACTIVE MATERIALS PACKAGES I t a CERrlFi UMBER ti Al ON NUMBER cPAC A EN IF GAfi MBER e PAGE NUMBER e TOTAL NUMBER PAGES I N PREAM8d u i a. This Certificate is issued to Certify that the packagmg and contents described m item 5 below, meets the apphcable safety standards set forth in Title 10. Code j i of Federal Regulations. Part 71," Packaging and Transportation of Radioactive Matertal" l l b Tnis certificate does not ream ine consignor from comphance wiin any requirement of the reguistions of the u.s. oopertment of Transportation or other I I apphcabia reguistory agenc s. .nciudmg ine government of any country inrouan or into wnien tne package wisi be transported. N l N I I l l ' ^ *^"" ^"^"*'S l l l * '* a E"?o'C'28,,5f'l " '*' '^8 t "'07L',"401 *!##EME,"00A S'?Tc'arloN I I I I I I General Electric Company General Electric Company application dated I l l Vallecitos Nuclear Center dated May 30, 1985, as supplemented. I I Pleasanton, CA 94566 I I n p m I I . l ooexar Nuwe:Ri(~~ 71;5942 I e CONDITION $ 4 h#
- V 2 Tnts certsfacate is conditional upon fulfatimg the,esquirements of 10 CFR Part 71, as apphcable. and the conditions specified below
.c 7 p , i 3) l l (a) Packaging k [ j). ! l (1) ModelId.: 00 2 x M d I i 4/ WA //// I ,1 (2) Des,crjption [$* V \ ) [h, gVy ,f; \g61 (I) l 1 l i l A stfel encasedileId[ shielded shipping cask' enclosed by na double-walled i I i prote'ctive jacket,of the same1 shape withTa rectangular baseplate. The i I cask *is a double-walled steel ciredlar cy11nder' 37-inch-diameter by i I I 65-jnch high'yith afcentralicairityi15-inch-diameter by-40-inch high. I Approximately?10.25 inches"ofi lead { surround the central cavity. The cask I l is equipped"with a cavity "draih iline, pressurOEeliefivilve set at'100 - ! i' psig,-and liftihdl. device.J Closure fis? accomplished byl silicone rubber I l gasketed and bolted' steel' lead: filled ' plug'. ' The maximum gross weight of I I I thepackage(contents,caskassembly,proJectivejacketandbase)is i 35,500 po,unds. 1: .C w e .,1 I i a .a i l The cask niay'be modified with a"14-inch high ca'vily extension with an i I I additional silicone rubber gasket. The modiffed cask is 79 inches high. I l The maximum gr'oss weight of the package (contents, modified cask assembly, I i protective jacket and base) is 40,200 pounds, l i s > ,i g (3) Drawings ; l' I I The packaging is constructed in accordance with the following General I I It l Electric Company Drawing Nos.: 129D4768, Rev. 3; 129D4769, Rev. 4; and I j 129D4770, Rev. 5. i l > I I i i Lifting and/or tie-down devices which are a structural part of the I l I package must be in accordance with the above drawings. I I I I I I I I I I I I I I I I 13o I I I %--------------------------------------------------J .___________________________________a_,_____________- D "# CON 0lTIONS (continued) LLS. NUCL FAR REGUL ATORY COMW5SION L ( ; ^ l ge 2 - Certificate No. 5942 - Revision No.13 - Docket No. 71-5942 f L
- 5. . (b)' Contents (1) Type and form of material
-(1) Byproduct, source, and special nuclear material as solid oxide or h metal in the form of fuel rods, or plates, fuel assemblies, or meeting the requirements of special form radioactive material. . (ii) Co-60 metal contained within sealed liner and sleeve described in f Neutron Products, Inc. Drawing Nos. 240139, Sheets i through 3, [ Revision No. F and 24013 Revision No. . [ (2) Maximum quantity f$ahe 1perpcNgk Not to exceed pounds (including shorin ,knd h ) (i) 740gm)6 -235, provided that the maximum U- 3 enrichment does not f excgg ig percent; or f7 g (11) 1.560 gm U-235hiirovided that th materi is in the. form of [ M7btype fuel:elemsats fwith a q6in active length of 23 [ ipches; or Cl / /" ' \ ? ii [ Q4 lb ,) 4 [ (iii) 220 gm fissile 2ma n (4 al er . 8 f// % ,f/$ p , l (iv) 1(,650gmtd0 235p pr6vt%7W ;' emaximumU-2%enrichmentdoes i no ye,xcee'd2h 35 wei ' c nd the"fdel material is in the f fon of 8840dQue 114 M 6-iisih-diame& ' minf(atig activ& fuel len thPof)37 ijsches; or4" y pellets with a Yf " WjW j4f/ A' : (v) those fathes presented' nIfigure 1. U0,, (e'f ght Limits for Model 700 Shippingf container, of Exhibit A to this, application, applicable to fuel-materia n the form of rods with a minimum pellet diameter ! of 0.40 inch; o j g,, g dA p (vi) 5,100 gm U-235, provided the fuel is in the form of ETR-type fuel i elements (GETR Fuel) with each element containing no more than L 510 gm U-235 and inserted in the spaced stainless steel fuel I shipping basket described in GE Drawing No.106D4150, Rev. 0 ; or l l (vii) 6,200 gm U-235, provided the fuel is in the form of MURR TRTR L type elements containing not more than 775 gm U-235 per element; [ loaded and spaced in the stainless steel fuel shipping basket as ( described in MURR Drawing No. 1228, Sheets 1 thru 5, Revision 0. [ l. Fuel elements shall have at least 150 days cooling time since [ j 1ast reactor operation; or [ 1 ( ! (viii)' 3,510 gm U-235 provided the fuel is in the form of MTR-type fuel ! ] elements with each element containing no more than 351 gm U-235- [ and inserted in a spaced stainless steel fuel shipping basket r l described in GE Drawing No. 106D4150, Rev. 1 for GETR fuel. A shoring device to limit vertical motion of the fuel elements must ; be. included; or L 131 .k l l m------Au----------------------------------------------4 I I I I Y$ ~ ~ coNomons (continuem U K "*" "M ^ *' C MU S I I I I I ! ge 3 - Certificate No. 5942 - Revision No.13 - Docket No. 71-5942 i l I I l 5. (b) (2) (continued) j ! (ix) 7,020 gm U-235 provided the fuel is in the form of MTR-type fuel l l elements with each element containing no more than 351 gm U-235 , I inserted in a spaced stainless steel fuel shipping basket described l l in GE Drawing No. 10604150, Rev. 1, for 24-inch length fuel. I I Each shipment must contain 20 fuel elements in 2 fuel baskets l with the spacer plate shown on GE Drawing No. 21886061, Rev. O, I l located between the baskets. A shipment may contain less than 20 i l l elements provided each absent element is replaced by an aluminum ; I or steel spacer in the form of an open-ended pipe with a minimum y outer I 0.125diameter inches. of 2(R ir{ch&lgnd I I Qtpbsphce mdst Sb(A minimum ufficient lengthwall thickness of to replace I l the absen theVelement;or ptg-g l ! (x) 235 provided the fuel is in form of MTR-type fuel l l 7,000 hith each section containing no ritdre than 175 sectio'ns w gm g U-i insprted;^into the stainless steel Cask:Dividdr (fuel shipping i I baskit) showin:14 eneral Electric G r'y Drawing No. 183C8253, a l ReMfl . Wherhj3shipmentcontaips, than the paximum number l l (f0) of fuelssectiops.feitpty f/e1 6 tion basket spaces must be , I pfpvided with sp plomiqum"or stei1[ spacer in t(ij) form of an open- g i ended pipe withra minipum; outed diameter of 2.5- g i minimum will thIc^kness of 0.125dn'ches ' The spa,jnches cer must be of and a I I to 'theabsenkfuelseiitions;or I sgicienp0ength)e! tsc k vm g j l (xi) 6,300 gmsjo:235/provi fuel issin'the forp of MTR-type i g i fueP'q1ements[ ohs 6Ctfo'ns, ithMachifuel elegiept or section ; I havidsf an average 11inear>4ensity ofeno morq;than 13 gms U-235 I I per inch of. length. (Each fuel element or section is inserted into 3 1 I the stain 1pss steel ca'sk(divider s}iown ifIGsneral Electric I Company'Dr'awfng No.183C8'257, Rev. O, tMipn a shipment contains I l i less than 'the mazimum number of fuel elements and fuel sections, l l empty fuel basket spaces snustabe provided with an aluminum or steel y i i spacer in the foi1n ofianhpeMended pipe with a minimum outer I ! i diameter of 2.5 inches and a minimum wall thickness of 0.125 I I inches. The spacer must be of sufficient length to replace the l absent fuel assembly and sections. l l i i 1 1 I I I I I I , I I .l ' l l I I l l l l I I I i 11 I . 1 [ i i 1 I I I I I 132 l L-----.,----- _ --- -- - Wl I l I l *** CONDtT10NS (continued) S E RNAM CON 510N l l I l .; l t I I ge 4 - Certificate No. 5942 - Revision No.13 - Docket No. 71-5942 l I l 1 (b) (3) Maximum quantity of radioactive decay heat per package l l 5. (i) 6,500 watts for dry shipments, or l l l 1 (ii) 1,500 watts for wet shipments, provided that the cavity shall l 1 I contain at least a 1,000 cu in air void (at standard temperature 1 and pressure) at the time of delivery to a carrier for transport. l l ! (c) Fissile Class III l I I Maximum number of packages per shi ent 2 I I I
- 6. The liner required for Co-60 tiiet ich c e n[tf et the requirement for.
special fonn radioactive,ma'teMal, must be dried, eytested,andback-filled l with an inert gas in accordance with Enclosure 2, Rev f to Neutron Products, g l i Inc. letter dated Feb(ua'ry 28, 1986. Q g I I I r, T p.., / h,p 1 I I
- 7. Shoringmustbeprovided'toajnimizemovementof ' tpnts dam)ng accident conditions of transport. 4/ '%
g 8. the requ1@ents of special I I priortoeachshjpment(excipt;fo form radioactive material),'th& p ckggbalus cont'biittmee'ingktestedbyjmethodcapable be i I of determining that a leskage.'of ?l07 atm cm}7s'/ at'itandard lea tediperature and I l } [ / } l pressureisnotexceedsd{Mconerub5edIdgaske Priortoeachshipmentth7s 2)must-reinspected. l l 9. _ This gasket (s) must;be replaced;iC rispedi idhos*?any deffeys or every a l l i 12 months, whichever'occursifirst. .Cavitydraipjfnemust;",besealedwith ~ I appropriate sealant ' of, applied to thre6ds/)of I l S pipe ~plup.(")N"' J , 10. The appik, . i must tm ffrp/ annually that the pressureg,teTief valve is oparable l g l at 100 psi ~g . g 9 y/ , L .Jg P l I I 1 11. When needed, sufficient antifreeze $ the. cask must be used to prevent damage of I any component of the package due to freezing. l
- 12. Fabrication of additional packagings is not authorized. l l 1 l
1
- 13. The package authorized by this certificate is hereby approved fL sse under the l I
I general license provisions of 10 CFR 971.12. I I 3
- 14. Expiration date: July 31, 1990.
l I I l I I R I f I I I I I I ' t l I I I l 133 I l I I I ; I l l wy c au ws ,O ,,,,,ON ,,c,n,,nu,,, u s awa w,mm co,,wsm l,i I I I I ! ge 5 - Certificate No. 5942 - Revision No.13 - Docket No. 71-5942 l l I I i i l I REFERENCES I I I l General Electric application dated May 30, 1985. , 1 I I Supplements dated: June 5 and 7, August 7, and September 16, 1985; and February 28, I g i May 8, July 11, August 15, and November 26, 1986. I I I l University of Missourf letter dated March 20, 1980. I ! Appendix 6-A regarding University of Missouri's quality assurance program is not l l considered part of this application. g i I NeutronProducts,Inc. supplements {djteh e bh h/,1985; and February 28, March 11 l and 31, and April 1 and 10, 1 l 9 q j l D FOR THE U.S. NUCLEAR ATORY COMMISSION l l e _e i , L I i t'% pc Charles El Ha pal _d, Chief d ,I i N, Rx Transportptihn Cirtificationf)Janch ; I iJ Division of Fu liCicle and l l- h. IC [S J'fla~teFisT5sf ty/ NMSS r 1 I I Date: MAR 131987 ID 9hk Mg .[ $p: n -' IRdh \n ph$f g?y ng$ i l 3 i , ). T l <:q, %$ @h, g l ~n y l, I e e* Mr I ,I t f-d, n n de, r V I 1 I I I I I I I I I I I I I I I I I I I li l I 1 I I I I I I I I I I I I I I i I i 134 l 1 1 I....-______.............a.n__n___..............___I a l mic Ponas ets U.S. NUCLEAR REGULATORY COMMIS$10N tse CERTIFICATE OF COMPLIANCE io CFR 7' FOR RADIOACTIVE MATERIALS PACKAGES c PACKAGE IDENTIFICATION NUMBER l i a CERTIFICATE NUMUER b REVISION NUMBER e PAGE NUMBER je. TOTAL NUMBER PAGES 5950 5 USA /5950/B( )F i 1 3 2 PREAMBLE i 4. This certtfacete is issued to certify that the packaging and contents tiesenbod ln item 5 below. meets the applicable safety standards set forth in Title 10, Code i of Federal Regulations. Part 71,"Packagmg and Transportation c,f Radioactive Material." I b This certificate does not renove tne cone.gnor from compiiance w.th any requirement of the reguistions of the u s. o.oartment of Transportation or other I applicable regulatory agencies, including the government of any country through or into which the package will be transported. I I I 3 TNIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION I a r88UED TO I4mse amt Amesst t TITLE AND IDENTIFICATION OF REPORT OR APPLICATION I I Battelle Columbus Laboratories Battelle Columbus Laboratories application I 505 King Avenue dated August 21, 1981, Columbus, OH 43201 i l , s.MiTNI)Rh D p ,71-5950 i I a CONOifiONS ha v This certificate is conditional upon fulfilhng the,requ ,ments of 10 CFR Part 71, as applicabie, and 4, con @tio f I s s /s i I (a) Packaging Q I #D,, (1) Mod ^)No.: ._BCL-4 / - m/ ,, g l G y . ~ . l (2) Desgrfption / 1 r ...n,\ 8 ez; , / ., ( ~ l Steel encased lead $shi,elded The pdc () age is provided ! with recessed ~ plug , type lid';shihpiggjackage. s l tTd-down dgvices .and 'reliehyAl.ve,,(vehtt i,ine, and drain, lice penetra-li , tions. Containment."forj the contehts[js(jrovided by affinner can aspemblytobby material 3 form has dimensions, i n specia)M. l'oir ':' Jiiel,packagQ' 'm/ $ I I weight, Q: anCshiglding}a}s 'n l A . htl; f 'nh yf4.8(% I 1 ()) G[Q[ Exterior!ExteFiorddi[ameter~,'Hnth@ 6 26.4 \3 ' VCavity height,Yidi .. 9 42.5" i l 'b Cavity diameter,.in 99F# 6d OQ I ys), Lead shie'ldi.ng,Jiri 48f ~ 1 i Loaded weight, Ib gy200 (Inci 270-lb skid) 4 f (3) Drawi ng vw ! s v w s m b. .e +p+" < The packaging is constb6cted in Aicordance with Battelle Memorial 1 Institute Drawing No. BCL4-01, Sheet I and 2, Rev. D. ; i o a I [ 135 E l I US "
- coNomows (continued; o s numn ntcut.uony comssion g l l l
l Page 2 - Certificate No. 5950 - Revision No. 5 - Docket No. 71-5950 I i I l I I I I I
- 5. (b) Contents l
<. I l Type and form and maximum quantity of material per package. ,1 ! Byproduct material, source material and special nuclear material not to l l exceed 400 watts decay heat in solid metal or oxide form packaged within an i I . inner can assembly or the material meets the requirements of special form I I radioactive material and limitations on fissile loading for the Fissile l l Class as follows: l l Inner can assembly: l I l Battelle Memoria RM nfti ute Drawing Nog Rev. C. i I j l Fissile Class Q 650* O- I l > l Fissile Class L I (/) N 2000* W -j.,h ! l l *(gramsUQJ5equ t t~ mass) ,c 2 I () l l (c) Fissile Ch's lk pijl! ' l i n J, e O er of acita l l l i Maximum per shipme fo ss y - J( { g
- 6. The U-235 equiva nt mes t 1 l i
~ by thg(kdllog method: l l U-235 equivaQjmt mIss)Eth0 j .75 t e9 U-233 mass plus I i 1.60 times Pu ss.
- b F i 7
I 7. ^ At the time of delive'ry#pf the loaded" I kage to a far er for transport, the i package contents must bd ll) dry (contents of. inner &&n assembly must not decompose l l 1elegterial unmoderated (H to X I i up to aratio atomic temperature less than 2)of 7$0*F) andl(2) iso And 3 Maitpthe fiss{t(' ttial the dose rate will not excee l 10 millirem per hour at three (3) feet from the external surface of the package. l i l I I 8. The maximum gross weight of the cavity contents must not exceed 180 pounds l l (inner can assembly, radioactive material, etc.). j l I I I j l I l I .I i ) I I I I i I I I I I I I l l I I ) i l l l l l l l l l ' 136 l l l . ___________=____________________________! l l s I 1 l U.S NUctE AR nEcut ATODY COMMissl0N I "'"N coNomoN8 (contmuod) l I I I a g l Page 3 - Certificate No. 5950 - Revision No. 5 - Docket No. 71-5950 I I I I 1 I i l 9. In addition to the requirements of Subpart G of 10 CFR Part 71, each package l 1 must meet all of the acceptance and periodic tests specified in Section 8.0 of g ] I this Application. l ! I I I j I The following item in the thermal acceptance tests (8.1.6) is changed as follows: I l l (4) The acceptance criteria must be that the maximum measured temperature of l l any portion of the cask must not exceed the temperatures indicated in ; i Figure 3.3 of this application by more than 25'F. In this comparison, g I solar heating and ambient temperature differences between Figure 3.3 and I ount. I I the test data must be taken intc
- 10. The following item in the Th ction 8.0 of the Application, cedure ( 1(If g I is changed as follows:Q I g. Remove pressur hre port according to l l
tion line the loading ffetedure. and tape Use teflon insert plug in pre (}ptible or other,c sealant1 I in j threads. gQ pA ! 11. The package aufho'rized by \certifica.te [ approgg for use under the l g general license provisions ~ CFR 7121 l I g v: [ O , L,2 ' 'C r" m
- 12. Expiration datst - August m h., s ,I l .
'g') fv i #<f ' 5 8 { l i Df5 sgm3,e.vqnFTg . i e g 5, %.s l l I Q EQ2EFEREN4 %c y l 4 jc %d yQ k $'F% 7$hy Cf) > I Battelle Columbus Lab, doratoriesl'applj,catio d 21, Augus't l ;ated 1981. I I l Y,f T l i N' '4 t/ A" FOR THEAS. NUCLEAR REGULATORY COMMISSION I i ' 'h 9 ! ! l O . j #f~gggt[d Charles E. Mac ona , Chief Rz/ l l Transportation Certification Branch g i Division of Fuel Cycle and y i Material Safety, M4SS g 0 Date: I I I I I I I I I I I I I I I I 3 I I I I I 1 l m l i i I l .. ... t i I *as U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE I l . mCFRn NAC Fones sts FOR RADIOACTIVE MATERIALS PACKAGES I N 3 a CERTIFICATE NUMBER b REVISION NUMBER c PACKAGE toENTIFICATION NUMBER d PAGE NUMBER e. TOTAL NUM0ER PAGES l 5957 13 USA /5957/B( )F 1 6 g A ' a.EAMBLE in,s c.nir cate is ..suea io cen,,y inat ine packaging ano contenis oescrio.o in item s ooiow. meets tne appi.canie sarety siancaro set fortn in ritie io. coas l l of reoeral Regulations. Part 71. " Packaging and Transportation of Radioactive Material." l l n Tnis certificate ooes not rei. eve the consignor from compiiance wiin any requirement of tne reguistions of the u s. Depenment of Transponstion or other I I appi csoie reguiatory agenc.es. mciuoing ene government of any country enrougn or mio whicn the package wiii be transported I l 3 1 I q I I "' ' * '"'Esit'"I% s 'Al'.',*r*f'l. " '"' *** ' * **" ^"^"."'TTLE Eo'"o'EEi"Cffl$'8"E "O'TTfSfiCADON- 8 I I I I I I I Cintichem, Inc. 'Battelle Columbus Laboratories application l l l P.O. Box 816 dated June 20, 1985. I i Tuxedo, NY 10987 i r '. m* a i I toOcvt7 NuueER Y s y3.gqgy I 4 CONDITIONS 1 ,, ' C Tnes certsfacate is conoitsonal upon fultilling the requirements of to CFR Part 71. as applicable, and tne,conortions specified below I s . s / I I I N (a) Packaging'~ W ,r I I s I l i i (1) Hodel No.: BMI-l e > \C g g I (2)' Description i 1- l. e ("'- 1 3 l I I ;A steel-encased lead shielde'd s' hipping cask. TheMsiccaskbody p * -is a cylinder. 33.37 inches in diameter by 73.37 inches high formed ! i by two concentric stainless steel shells whose annular region is i i f filled with lead. The outer,1/2-inch thick shell'ha's a 0.12-inch I I thick plate spot welded tofit, providin'g a.0.06-isch thick air gap i I I . insulator. The inner shell is 15.5 inches inside-diameter by 54 I inches inside length. .Thel cask' lid is a stainless steel weldment I I lhaving 7.75 inches of lead shielding.1 The cask' lid is secured to l i the cask by twelve steeltstuds which.are welded.to the cask body. l g i The cask is provided with a drain line with nsedle valve and plug, I I pressure gauge, and a-pressure relief valve.1 The total cask weight, a I including maximum contents of 1,800 lbs, is 23,660 lbs. N I I l (3) Drawings l l l l The cask is constructed in accordance with the following Battelle I I Memorial Institute (BMI) Drawing Nos.: 43-6704-0001, Rev. B; and i I 41-4409-0003, Rev. B. I I I I I I I I , I I! I I I I I I I I I i 1 Y l l 1 1 I : l 138 I j l I l l ; l 1 cam m mm m m mm m m m e spr u mg - m m m mm m mm===== = ===m === ============= ==mL l l l I i
- amm w U.S NUCL E AR REGUL ATORY COMMIS$lON CONDITIONS (continued) l Page 2 - Certificate No. 5957 - Revision No. 13 - Docket No. 71-5957 I -
- 5. (a) Packaging (continued) : l J
(4) Product Containers l The various authorized product containers are constructed in accordance l with the following Drawing Nos.: i 1 I (1) Inner can assembly as shown in BMI Drawing No. 00-000-421, , j Rev. C. l (ii) Basket Assembly as shown in BMI Drawing Nos. BCL-000-500, )j i Rev. A; BCL-000-501, Rev. A; and 0048, Rev. A. i I I (iii) Fermi 1 rir per casting assembly as shown in BMI l I Drawg . K 28: Rev. to May 12, 1966. l (iv) I44 et Assembly as shown in sDrawing No. 1020, Rev. B or i D GA Drawing No. 9590001, Rev. . ailed fuel assemblies must 1 i ess steel tubes with j i k be seal welded in aluminum or cr wa,11andendcapthicknesses-of east 0.015 inch. I L (v) k 'Assembi defin hs mod fled , - I Drawing No. BCL-000-500, i88tI2 Drawing Nos. 00-000-236, Rev. C, Rev.'4 l f% anLBC 000-507, ev' i a (? O i l s'$ ~ y an rags aN defi M by BMI Drawing No. l p (vi) Ea~00-000-ke i'391 m ddl. Atom c' Intern tional Drawing No. AIHL, I @ (MS8DR 0619-O' Vr'espectiv41y. I 1)D!"In$p pfF g l ! j shownfin neKcanatsetEy. l % Union Carbide Corporation J 1 Drpwinhfl;o.A0401,'R6 pal fj (b) Contents / g Yn (1) Type and form of material i %4 Intact'irradiapd e n N PITk-r o% BRR-type fuel assemblies (1) e containing not more than 200 grams U-235 per assembly I prior to irradiation. Uranium may be enriched to a maximum I 93 w/o in the U-235 isotope. Active fuel length shall be I, approximately 25 inches. (ii) Intact irradiated Enrico Fermi Core. A fuel assembly 1 containing not more than 4.77 kgs U-235 prior to irradiation. Uranium may be enriched to 25.6 w/o in the U-235 isotope. I! B R d f l m l- m------------ K "' conomons teontmvem US * "ULM"' CO*S Page 3 - Certificate No. 5957 - Revision No. 13 - Docket No. 71-5957 i [ [
- 5. (b) Contents (continued) f I
( l (iii) Greater than Type A quantity of radioactive material which may [ l include uranium enriched in the U-235 isotope, U-233, plutonium,. as metal, oxides, or compounds which are thermally stable up to [ l , i 6001F. Plutonium in excess of twenty (20) curies per package j i must be in the form of metal, metal alloy, or reactor elements. [ l I (iv) Greater than Type A quantity of byproduct material meeting the l requirements of special form radioactive material. l (v) Greater than Type A quantity of byproduct material in normal [ l form as metal, oxides, or compounds which are thermally stable [ up to 600*F. l g Q{g [ l (vi) Irradia'iie .riga Type fuel ass ies described in Section 6.6 [ of he1 application pp. 6-23 tHr gfh6-24(c)) . l (vii) feradiated S80R fuel elements 0.56-1 D by 18.7 inches long i i py 0.010-inch wall thickness of JasJel' N. The fuel material l l full I l LtC0is UZr % % y enriched//f'y in U-235.-p l \ l (viip.,j 176 Intact rradia.tedrCF 5)fup1 grams %235per/ assembly,assembliesc[nt'ainingnotm l j i prior to irrd~dtation. Uranium may , { g ( be enriche'd 6amaximbm93fw/ojintheU-235 isotope. Active ; ! t _ fuelpleni hajl'bb"28'$f nches. / , y l L Nhi % (ih Solid,rionfissils r1"rWW J 1 N l I I M/9, whiett*may 4 fated! hardware ~' contain .a I pMencapulatsdfis MyA/t M7 ddl xidewastelenriched_j)ntheU-235 l l (x) Q}rradiated@luranium o! C }riKin) tors. d,isotope &! i i ' to a' nominal (93 Wo'which'are thermally stable up to 800*F. l l sp/p 'tky)P " N l l l (xi) Irraifiated uranium enriched in thew-235 isotope meeting the - I { l requifpments,of special form r,adi~olihtive material. l ] l (2) Maximum quantithfInterkalNr h$ckage l i I i The minimum cooling time of each fuel assembly and rod is 90 days, i I maximum decay heat generation per package not to exceed 1.5 kw, and i I the external dose rate not to exceed 10 mrem /hr 3 feet from the 1 l external surface of the cask and: l ' l 1 i (i) For the contents described in 5(b)(1)(1): I I I l l Twenty-four (24) fuel assemblies as contained in product i I containers specified in 5(a)(4)(ii) or 12 fuel assemblies as ' I g contained in product containers specified in 5(a)(4)(v). l l l i I I I I i l R l W I I I i 140 g I I i - - - - - - - - - - - - - - - - - ,1 c' # .. / l - -------,_-----,_---________,_- _.. >..~.>c?. w_--- I v n=u m ********##** l l cono\TIONs toontinued) Page 4 - Certificate No. 5957 - Revision No.13 - Docket No. 71-5957 7 l l l .i l y r ; i
- 5. (b) Contents (continued) p l- 1 I (ii) For the contents described in 5(b)(1)(fi): I I I I One (1) fuel assembly as contained-in product container l specifiedin5(a)(4)(iii). y !
l I i I I i (iii) Forthecontentsdescribedin5(b)(1)(iii): I I I I 480 grams U-233 or 480 grams Pu-239 or 800 grams U-235 as . contained in product container'specified in 5(a)(4)(i). l ) l (iv) Forthecontentsdescribedin5(b)(1)(iv): l ) l Gamma sou gh cu 1 chfdobdinthecaskcavitytopreclude ! t I I onditions of transport. I l I secopd rj mpacts during acc16en Th eat generation rate is nytted to 200 watts. I, y: g j i (v) (or the contents described in 5(b)(1 i l CC Cont 5}iieps,200 thermal ./ watts ,in product containe. I Ie ! I l Qf limited'to 4 M 'N AM d' d O I l (v Fortheicontentsdescribe/ 5(b)(1)(vi)Q l ' Thi t 8) U ssemb'11sas,contai$edinproduct nersspec)fted l ( l @ con initiskenrichment Xb n 5(a)(4)(jj).3 Fuetsssemblies withi an2 3 I I limited to'19;ajsemM e Shipments of I OlesshthirQ19.a'sssmb"lls,s(perproddetcontainer. Sith..aU-235enr19mentgreaterthan 1 l Q70 w/o' mayibs"60mbinbd with'as~i:einblies4f 70 w/o U-235 or less l - provideil: B UEji/38J+y/,19.51;x ~ i l I U-235, y = no. assyt s i!!!'70 p w/ii U-235'.)'{no, assy's 4 l l y y ~ 1 ! (vii) Forthcontentsdescribedin5(b3('1)(vii): Twenty-fou [2'ffue'1'elhe 4 er can and six sealed cans per basket as descri ed'in 5(a)(4)( i). Each of the six cans may I g contain up to 818 g U-235 and 158 g hydrogen. The cask is i i I i limited to 4.908 kg U-235. ' i (viii) Forthecontentsdescribedin5(b)(1)(viii): l l 1 I g i Twelve (12) fuel assemblies. i I I I I l l I N a f l I I I I ! I I I R I 141 l I - --________ - -- _-_-___________________a- ...= .- "l? '" "" . coNDmONS (conUnved) Il #" NUCL E AR Nt Gill ATon y covMinioN Page 5 - Certificate No. 5957-- Revision No.13 - Docket No. 71-5957 j E 5.- (b) Contents (continued) I ! I I I (ix) For the contents described in 5(b)(1)(fx): I l I i Thermal ~ heat generation rate is limited to 200 watts. ,1 i l (x) For the contents described in 5(b)(1)(x): l l I I Twenty-four(24)containerseachlimitedto352gramsU-235as l l contained in product' containers specified in 5(a)(4)(vii). The I i decay heat per container is limited to 20 watts. The containers . l i must be leak tested in'accordance with Union Carbide Corporation , i letter dated November 17, 1980. y -(xi) For the gikinhd bb (b)(1)(xi): Tw A ur (24) capsules each ) 1 to 100 grams U-235. l (c) Fissile s I dj!f I l (1) CIAM I g (g'. For thyhytefits specified in 5(b)(1)(iii) pq1mifedfin5(b)(1)(iii). j l i (2) MTimumnumbdr: e e mf @i ; i contents s ec ' ed in 5(b)(1)(1), y ppckages p'er ' ship', ment 5 )t i f 5(b (i t fissil as,/ lassIII;m J )d(1) yfii)l.95 1) lx), an)d 5)g)(1)(xi); (b)(1 (vii) .ii I I U > 4 ~%ft < , in'5 2)1),5(b)(2 11), I ! d }'imited[/,5(b)()(}vi),5(b)(2 }(vib viii), I h ~ d,yu M $)( ! ) Mix 1 and5(g)2)(xi): l l p ^gc p l '( I,hef1)fp&[kage i I 6. For item 5(b)(1)(fii , I thefollowingequatio)n,mixturesof'fissilemateria.1 is satisfied: D re authorized, provided 1 I g X + g k+ p' kg 1, where I I X = Grams U-233 to be shipped i Y = Grams Pu-239 to be shipped I l Z = Grams U-235 to be shipped' I l ! 7. Excetforcontentsdescribedin5(b)(1)(ii)and5(b)(1)(iv);andlimitedin i i i I 5(b) 2)(11) and 5(b)(2)(iv), the cask must be shipped dry. I I I I I I I I I I I P I I h l I I I I 142 i l i S.( i ,.---- ---------.----- ----------- _-----..-- -- ly I U1 NUMAR REGULARY COMWS$10N h I "[ "
- CONOmONS (continued) J Page 6 - Certificate No. 5957 - Revision No. 13 - Docket No. 71-5957 l y l
- 8. Ifthecaskcontentsof5(b)(1)(ii)or5(b)(1)(iv)areshippedwet,the l l
licensee must confirm that the pressure relief valve is operable (set i I l l I pressure - 75 psig). When needed, sufficient antifreeze in the cask must be used to prevent damage of any component of the package by freezing. l l I l 9. Loading and unloading) operations of the contents described inl 5(b)( i g 1 I 10. The presence and effectiveness of the Boral poison plate in the' Basket i p I Assemblies as shown in BMI Drawing Nos. BCL-000-500, Rev. A; 0048 Rev. A; and I ! I 00-000-236, Rev. C, must be verified by neutron measurements prior to first use I and records maintained of such verification. Verification of the presence of l the Boral must be made in each subsequent use. l i l 11. h A9d provided the sum of the product Contents 5(b)(1)(1)and5Jbh(x)containersandfuelasspbfiesd l I q l l ; I Q* My I i l 12. Contentsmustbe+shurelyconfinedinthecaskcavigtoprecludesecondary i impacts during Acc'ident conditions of transport. l
- 13. Prior to each!cse[a'dequacy of containment $il;Iust.A demonstrated by l l performanceeffthe16%testdescribedinS f90 7.1.1 of the application.
l J I l
- 14. Gaskets and Eeals (cas d nel a t s be repla g at least every 12 l months or e#, lier if visibl' e-degfedat o echr$. l p,
- 15. The package uthoriId tibcertWic e h Feby app ed for use under the l 5
l I generallicenseproyJstonsieff W3QQ9 4 !67 .12'. .'; ;jfj g' g g i l % 1 ! 16. ExpirationdiO: A$u's'tt:31, . h i (Q [.lfcp y 4 -- I h d f. REFERENCE 5f h l s l l y/A 'L { W Battelle Columbus Laborato es consolidated applicat f , dated June 20, 1985. l I \ l n l > k i $ >,( y F,0R THE'U.S. NUCLEAR REGULATORY l CO l i I Charles E. MacDonald, Chief l Transportation Branch l i Division of Safeguards and i 1 i Transportation, NMSS i l l M 21 fRT I I Date: I I I N a I 1 l p F i 1 F- i 143 l l ! -- = .........-..--- .______________________________________________________y I NRC PORM eis I sus > U.S. NUCLEAR REGULATORY COMMISSION I ! l CERTIFICATE OF COMPLIANCE I '8 0'" " FOR RADIOACTIVE MATERIALS PACKAGE 8 I j l 5 a CERTIFICATE NUMBER b REY 1SION NUMBER s PACKAGE loENTIFICATION NUMSER e PAGE NUMBER e TOTAL NUMBER PAGES i 5971 7 USA /5971/B( )F 1 3 i I .. mAuste I i a. The certificate is issued to certify that the packagmg and contents described in item s below. meets the appucabie safety standards set forth in Title to. code I i of Federal Regulations. Part 71,"Packagmg and Transportation of Radioactive Material _" . I l
- b. This certificate does not reheve the consignor from comphance with any requirement of the regulations of the U s. copertment of Transportaten or other I l j appucabie reguistory agencies. inciuding the government of any country through or into which the package will be transported- 1 I I l
I j I
- 3. THI
{ f6 FICA $ISSU THE BASIG OF A SAFETY AnsALY$10 RC T OF THE PA AG S oR APPL CA ON I General Electric Company General Electric Company application dated i P.O. Box 460 May 30, 1985, as supplemented. l l i Pleasanton, CA 94566 i I i I n n-E ooexit NupesR P* /,J1-59 71 I I I e coNomONs Le Vi I This certificate is conditional upon fulfithng the requ syrnehts of 10 CFA Part 71, as apphcable and theyonditions specified below I i a r i I i (a) Packaging .g d# il I v i 1 -l (1) Model,N'oi p.IP0-200 -/ ! i V) N .. % i, .x ,L, i I (2) Description [ ./ I , j A teel encase $dshih hip i fc" a sk. The cask is a double-i walled steel circular' cylinder 20s1/44nch s dianeterlby 53 inches high i i i vith a centralbcavit).J 5/8-inch diamet'epby 3 37 inches;;high. Approx- i 1 lmately 547/8 ihchestof lead surroundithe' central caV The cask is I I i qqttj p ped %1 th a ca v i tyddra,ip pl i ne ia n'd dl i f,,,tiClnposu dev re isi ce .ity . I i I I a'cc'omplishid#by4a, silicone rubbirigahketed :and bolted: steel lead I l libers may*lbe 'irisertedi1Mthe ;ciskicavityr ~ A protective ljacketfi s ^ i i I consijting of an.' spright ci'cu18r491'ihder r with op'e63 bottom and a i I protzuding box section dianietricallpa' cross the top and vertically 7 I I down thersides attachesIto' a tsquaie 'palJet. Djmensions of the protective jacket'ari 45-3/8 inches'highsby 37-5/8 inches' Wide across the box l I 26 3/4 inches and the )i l section. pallet is 47-1/2 OThe inches outer square. cylindrical The rnaximum diameter is[Teight of thel packag l 1s approximately 0. 000 pouqds. g .li g y I I 9 ff }.7 "b k I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I l l l 144 l l 1 l ______________________-------_________________.I ,s_____________________________________________.__ _ l c'"*
- conoITsons ccontinued) n mun namn comsm .
I Page 2 - Certificate No. 5971 - Revision No. 7 - Docket No. 71-5971 l 1 I l
- 5. (a) Packaging (continued) I I
I l (3) Drawings l l l l The packaging is constructed in accordance with the following General i I Electric Company Drawing Nos.: I I l I 12904756, Rev. 1 129D4758, Rev. 1 ' I 129D4757, Rev. 0 12904759, Rev. 0* ! *All components are to be considered safety related. y i I (b) Contents l l l (1) Type and form of t 9REGg l 1 l (i) Byprodutfari special nuclear mat rhl in.ethe fom of fuel rods, ! I or pyt(es", fuel assemblies, or meetin requirements of special I i fonns ra'dioactive material; or I ., M I T Sol.id 'nonfissile irradiated metal haf~dnaregeactor control rods l l (ii)fbl,ades);sahds actor start-u g6s. i i U $N '._- 4 () i I (2) Maxilnumquantityfof eirf[er ge, i Rad 'o ctive deca a po hto 8 watts an 500 grams U-235 I ' equ valent niass.y i (Uf236 equiva fi 'malfs eq,uals U 35 mass plus 1.66 I l "; riass'!)k', **w l l timesj)l-233'.%$bmass 3 plu.s?li(6 ll I l '[iii y@p[J b I l Plutonium in:exc'ess of dw 1 I form of igetalbmeta12a116 ,Orereacto) yj ly' cup elements @ijs per p@pckage must be in thel (c) Fissile Class 1 1 Minimum transport ..iridex to be shown on label # v (b Contents 5.(b)(1)(1): 2.3 i I I I &v 44gP g , ! 6. Shoring must be provided to minimize foovement of contents during accident i l conditions of transport. l ] I ! 7. At the time of delivery of the loaded package to a carrier for transport, the i I package contents must be dry and the fissile material unmoderated (H to X atomic I I I ratio less than 2). I I
- 8. Prior to each shipment (except for contents meeting the requirements of special l l form radioactive material), the pack be leak tested by a method capable i t
I of determining that a leakage of 10~3ge atm cm musg/s at standard temperature and l I I pressure in not exceeded.
- 9. Prior to each shipment, the silicone rubber lid gasket must be inspected. This I, gasket must be replaced if inspection shows any defects or every twelve (12) i months, whichever occurs first. Cavity drain line must be sealed with appropriate ;
sealant applied to threads of pipe plug. I I i 145 l I -____c___--------------------------------------------___; ,.______,_______________________________________________7 I - I l 3 ** '+" coNomoNS (continued) US NUMP Rt GULATCHY COW 5stON 1 l l Page 3 - Certificate No. 5971.- Revision No. 7 - Docket No. 71-5971 l 1 I l i I I I I I I 10. Packaging must be' maintained in accordance with Chapter XVII, Cask /Fireshield i l Maintenance, in Enclosure E of General Electric Company's application dated I I November 15, 1984, as cited in Certificate of Compliance No. 5980. I I I l 11. Fabrication of additional packagings is not authorized. I l i 12. The package authorized by this certificate is hereby approved for use under the I y I general license provisions of 10 CFR 971.12. I I I I I
- 13. Expiration date: July 31,1990. I I
I I General Electric Company a h j j\fition dated May 30,198d)s I Supplement dated: Apri $9,1986. I Cg 'ih., s FOR THE, . .;S,/NUCLEAh REGULATORY COMMISSION I Lu Yh s i l l lm $$' q)C3;?(f'j- 0 l i q 7 f r ~ c I I l g Char;les_ E' MacDona f ie i @g,,x3Yk%,gMTransportation, l I i cn _so " w,aq wp" Cycie end 'l o4 vision or rue,Certfrication Bra i sa Material tSafety,@SS I ,! oate: MM 13 8 h kva[h6[o2fjhfEMY Co l i e*] < w'vyyJ *y9 g li I i o sh(}'s* i ! }( i l s n A, M 4.. l l l .' l I I l l l l l I I I i l ' I I I I I I I I I I I I I I I I I J l I I I I I I I I . i I 146 a l I I ___----------------- __ I &bN l l s--c a- Ac-a-A w-a,-w ; ,_ _ _ _ _ _ . . m . . - - - . - ._- - - U.S. NUCLEAR REGULATORY COMMISSION C' CERTIFICATE OF COMPLIANCE I 1 I +RCes FORM 018 io CFR 7' FOR RADIOACTIVE MATERIAL 6 PACKAGES l l D REVISICN NUMBER c PACKAGE lOENTIFICATiON NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES h USA /5979/B( ) 1 2 g p[ I o CERTIFICATE 5979 NUMBER 6 lN PREAMBLE a Th,. ceristicare is iisued io certify inai tne packaging eno contents oeienbed in item s below. menis ine appiicabie natety standaras iet tortn in Tiii.10. code I oi reoerai neguianon.. par 7i. -packaging o< naoioactive uaieriaia tor Tran. port ano Tran.portation or nacioaci~e unioriai unoer ceriam conoition.-- 1 is! I b This certificate ooes not reheve the consignor from comphance with any requirement of the regulations of the U.S. Department of Transportahon or other i I apphcable regulatory agencies, including the government of any country through or into which the package wiH be transported. l ) l I i D I l l I i g g l 3 a.THIS PREPARED CERTIFICATE BV (Name and AddresuIS ISSUED ON THE BASIS b TITLE OF A SAFETY ANO IDENTIFICAitON OF REPORT ANALYSIS OR APPUCATION REPORT OF THE PACKAGE DESIGN ll Alpha-Omega Services, Inc. Alpha-Omega Services, Inc. application dated I ! 16220 Gundry Avenue June 1980, as supplemented. I 3 !;l Paramount, CA 90723 I M 71-5979 y gi e# i i . c TOOCO NuiEn E. o i, . Hl ( aThisCONOmONS ,_ i V *( o l certificate is conditional upon fulfilkng the requirepeets of 10 CFR Part 71, as apphcable and the,c deons specified below f' n (a) Packaging T 0-O a*?> p / d (1) Model<No.: (5979 W h+- I (, (2) Desebption %$,%\M ., ' p/ pj 1 l g! F. :0 Q j re- ) 3 cobalt sources) Configuration of l g l g! A the~ shipping container outer containerlis for tel'peasu bok_like ether py ?ing approximately 38" x 50"I x 40". ' The? box is lined'twiths4;5" of plywood;with a.0.125Sputer steel shell I h I welded to an, exterior ang frainewor~kr Transyerse<s, trips across the bottomfaciljtate,useLoft od-lift andLlif, ting jfgs are provided at l the four top corners.4T) Merfshield yestel issessentially a 24" )gl q diameter, leadsfilledhb&rrepsh6pid. configurattoni Three different y I cylindri' cal plug isse'rts indibolfedTend, caps pgyide flexibility to I 4 I Hj accommodate several tsizes and shapekof sources.J Gross weight is approximate 5,000 lbs/QW ' l ] f s AN s g- (3) Drawings 4 r). g d! 'rk 1 iM N The packaging is consti 0<ctedsin"sc'cordance t with Alpha-Omega Services, Inc. I di Drawing Nos.: 0090, Rev'. Of0091, Rev. 0; 0092, Rev. 0; and 0093, I ilj I # 1 Rev. O. I n; d' I H; I N' I I d{ i ( IMi l i N l s:l i dj i N: I I ni I L s I 9 e i g! 147 y i i I------------..--er................% ......-m-.......- .i ",";y "" ** conomons (conunued) U*****"*'* **C""" l l l l- Page 2 - Certificate No. 5979 - Revision No. 6 - Docket No. 71-5979 ll. 1 . I I '5. (b) Contents l (1) Type and 'fom of material l I Cobalt 60 or cesium'137 as sealed sources which meet the requirements I of special form radioactive material. I j (2) Maximum quantity of material per package l 1 1 j 15,000 curies Co-60 or 3,000 curies Cs-137, with decay heat load not I to exceed 200 watts. I ABREGn ~ i
- 6. Lifting eyes shall be c ehr blocked to preM te as tie-down attachments. '
l , ] 7. The shield ' vessel c1gres shall be' equipped with gas ! ,
- 8. Bolts used to secuhthe shield vessel closure caps shal,1% secured against l loosening by vibgioRdur.ing transport. ]/ A l
) 9. The package au ized b 1 rtif1cate is ., y'approvegor use under the l 1 ] general licens..yovisionsjo 0g FR,JJT . ^2 g 1 i
- 10. Expiration datg e. July 1.$ ' ' .. * 't L;
0 > I i h=- / f I (f) 'w. [T I ( kf ' l,, N g'[j l y EAM C L ; ~ , 1 ) gi I i 5 4 g g Alpha-Omega Services, c. ap 1815 el -Q J g Supplement dated: Apri4(1 1983. 7 FOR THE V.S. ,Ct AR REGULATORY COMMISSION. l, g ***$ eGs Charles E. MacDonald, Chief Transportation Certification Branch I g Division of Fuel Cycle and l l' g I Material Safety, NMSS l I Date: I - 1 I a l I li I
- g. e g
E I I I I I I I ' l l l a ' R- I I I i 148 g i I L_-_________________________________________________j ,, y------------------ a- AaAA--=-a a-a-mesemmmmmmmmmemmmmmng j I NCC FORM eis U.S. NUCLEAR REGULATORY COMM10$10N ... m CERTIFICATE OF COMPLlANCE s_ .I w crR " FOR RADIOACTIVE MATERIALS PACKAGES , l b REVISION NUMBER c. PACKAGE 6 DEN'lFICATION NUMBER d PAGE NUMBER e. TOTAL NW4ER pat 3ES I 1.0 CERTIFICATE NUMBER 5980 9 USA /5980/B( )F 1 3^ l l N .q . PREAMBLE j e This certificate is issued to certif, t hat the.Achaging anC curim 8 described m item 5 N1ow. meets the apphcable safety standards set fort i m Title 10. Code l l j of Federal Regulations Part 71. 'Packagirg CA.dioac%, Meenes for Transport and T transportation of Radioactive Material Uver Ct; tam Canditions." l ]
- b. This certificate does not reheve the consigorp from comphance with w.y requirement 'of f ne regulations of the U S. Department et Trar $7rth on or other ! )
.} appucable regulatory agenc4es. Includmg the govemment of as eountry through or into which the package will be transp':prted. I ]' 5 1 n m==== ~ - y; General Electric Company
- ,======A. >
4 General Electric Company application dated p P.O. Box 460 November 15,-1984, as supplemented. N Pleasanton, CA 94566 - Il :j ] W , I m don 71-5980 I I <-; j 1 cs_occmNuueeR L. o / t ~ I a coNoivioNs .g v' . '. #( j l { Thw certificate is conditional upon fulfilhng the rcqtarepents of 10 CFR Part 71 ts appucable. and the sont# ns @ecified below h {l E (a) Packaging Q ' "(, j (1) Model No.:% GE-600 A $ Ji h g , ; cn e dZ, ; 9 i: 1 (2) Descrip"tfon 3%- / O_ 1, A steel; f encased iT( lead \ shielded' shipping v, // h[j> cask. The basic cask body is a }(1 cylinder 34 inches inidiameter by 59.12Moches high formed by two concentric steel shells whose annular r6gion is filled with 6 inches [ l s of lepd. The' cavity 11s'20-1/21nches IDty 46. l inches' high, 3/8-inch i{p ,' ' j thickxstainless' steel' cylinde'r.7 , A receded plug-type cask lid, consisting E; l of a steel weldment fillediwith!1ead, is secured to the cask body by 0 'i i six l-inch diameter steel'boltsi i A silicone rubber gasket provides [ l the seal.f. A protective jacketirhsisting of a double-walled structure l i [ of 1/2-inch thick carbon steel pistes >As placed over the cask and [p! ! bolted to'a steel pallet by eight 2-ir.:5 diameter' steel bolts. The gi i cask has one 1/2-inch diameter drain lit.e- from the cavity to the outer E: y s hell . The cask.is shipped in .the upright position. Trie tt tal weight R: j of the package is approximately 23.300 pounds when loadeg. [ h (3) Drewings ! .h a . h y The packaging is constructed in accordance with the following General h = Electric Company Drawing Nos.: 12904742, Rev. 2; 12904743v Rev.1; ' i <g and 129D4744, Rev. 2. : [d @k. j Lifting and/or tie-down devices which are a structural prtYf, the oackage rust be in accordance with the aboveterawings. [t , )
- D
.d I. j (b) Contents ,' F .i (1) Type and form of material'
- !i . , I Byproduct material and hradiated special nuclear material in sMid or a solid oxide form, but specifically not loose powders. Contents are to I
; be clad, encapsulated or contained in a metal encasem>nt of such I E l material as to withstand the combined effects of the internal heat load and the 1475*F firt with the closure pre-tested for leak tightness, h
- Also, byproduct materia' and irradiated special nuclear material it l
., ,s ,,,, meet; ,_ing the requiremeM5 . , ,, s , . <, w , of spg,ial form radioac,tiveEter.b.b t--mmmmm --mm _- _--eJ 7 ;, r i '\ "} t . s m , grurmururumrmururgymnrurerurmrumL1Eh%-- ------- - mm -- ------- - - - - g i l ycrohm \ ,_ c'onomous tcontinued) ' " * ""***M" ' Page 2 '- Certificate No. 5980 - Revision No. 9 - Docket No.' 71-5980. l l ]j g a g - I
- 5. '(b)( (2) Maximum quantity of material per package l
Plutonium in excess of twenty (20) curies per package must' be in the l fom of metal, metal alloy or reactor fuel elements, and g. t q- l I! (1) For the contents described in 5.(b)(1) the maximum decay heat not i i' to exceed 600 watts and the fissile content not to exceed 500 I fj grams of U-235, 300 grans U-233, 300 grams Pu, or a prorated quantity of each.such that the sum of the ratios does not exceed l i j uni ty. When the contents of this paragraph tre in the form of g. 1 irradiated reactor fuel, the fuel must have been cooled for a e i minimum of 90 da r and gy po than .10,000 ci of noble gases - I 'l 3 mustbeava114b,1 $6 rm tKe gbg rod plenums. The I ) ight to.1 x V' e fue}/sec cm under nonnal-caskmustAb conditiongji transport; or l / (ii) For hcontents described in 5.(b)(1) th[,,seximum decay heat not t 1 to exceed 600 watts and ithe fissile content fot to exceed 1200 1 ffssil provided: (1) the' fissileanaterial is contained in I j p gr t 4 trd % s Ali ximum in hners ength_ofJ9- constructed- ' Finch ncfies 58i~edule (2) p more than four I 40 pipe lwith 1 fuch liners LirQhippea;aP 'ne d3)each r contains no a 1 -qqre than 300 g,ramy fissile a )2the cask , rovided with a i 1 osition ' (g latticQhin inw** aration between the liners. I ( )M .%p%EWFSIT dIIIS ?,lt S l l i j (c) FissileClg F l 1 ! l b $, Minimundrans% h.J % ,tel pork /jindex;.to /{F orthe/c[ontentsqpecifiedin g (1) i ll J; shown d abe1Mor%1asCl.$.A$ (11)iand liqjted in I g, ) 8.4 jl i (2) Maximum number #of packages For 31 ; per shipment for CladIII (1) and limited in Li 4(b)thecontentsspecifiedin k k 7 6(b)(2)(ii). 5 11 l h [ Two(2) l , { 6. The'U-235 equivalent mass must be determined by the following method: ! I L , U-235 equivalent mass equals U-235 mass plus 1.66 times U-233 mass plus 1.66 times I Su mass.
- l. l l
- 7. Package contents must beltry and the fissile material unmoderated (H to X atomic l ratin lessLthan 2), j l
, w 1 1, 1
- 8. The cask must be ddlivered to a carrier dry and the cavity drain line nust be I closed 620*F.
with a plug fich will maintain its seal at temperatures up to at least l g I d .j ? )., [, 15o I i 'a : I haEnt grant zwwwmpum prumagpgmargur gym mm m3 mu nu mmm e ma mmmm e m m merm um i . y .\ O v . )' ~ s 1 s,,.. , ,,,,.,,,,,., ,,...,,,.i...,,.,, l .S N L AR R ULATORY COMMIS610N j" C ""'" "" coNomoNS (continued) l ' Page 2 - Certificate No. 5980 - Revision No,' 9 - Docket No. 71-5980 l I I I
- 9. Prior to each shipment, the silicone rubber lid gasket (s) must be inspected. I This 9asket(s) must be replaced if inspection shows any defects or every 12 1 !
months, whichever occurs first. Cavity drain line must be sealed with appropriate l sealant applied to threads of pipe plug. g I
- 10. Fabrication of additional packaging is not authorized. 'l i
- 11. . The package authorized by .this certificate is hereby approved for use under the I general license provisions of 10 CFR 97).12. l 1
e 13. Expiratiot date: March 31,1990. 3 J Rp6iLCB egg l l General Electric Company's a a on dated November 1 , . l l Supplements dated: Febr 25 and March 8, 1985. O l ! { % FOR THE U. rW N E EGULATORY COMISSION j d %g ' 4 n , b h 3) Ii i h<> q pI <r N gwh r i d acDon ,e I H () Tran tio ertif tion Branch 3 fq(dy% @ Mi1 p.--og;g s 4O ((#%"d O y l i l ! !< Y***Y l, di l 8: I Nj I ( y ,d I 4 p I l, i e 81 di F s 151 i k ............................... ........... ...... wwwwwwww------------------------A---------------------, ""E "" " 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOf.CTIVE MATERIALS PACKAGES lj 1 a CERTIFICATE NUMBER b REVISION NUMBER c PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER ~ a TOTAL NUMBER PAGES l 5984 . 4 USA /5984/B( ) 1 2 1 2 PREAMBLE I
- a. This certincate is issued to certify that tne packaging and contents described in item a below, meets the apphcable sa'at r standards sei forin m Titie io. Code of Federal Regulations. Part 71," Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions." ,I
- b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U S. Department of Transportation or other I applicable regulatory agencies, includmg the government of any country through or into which the package will be transported. I I
I I * 's"'*4PMS'Bv'A'a,.'%"f"J".', *** ' ^ **"" ^"*"."'E"E Eo'io'ETJc^f15ENEPoORP0" cation I I J. L. Shepherd and Associates J. L. Shepherd and Associates application 1 740 Salem Street dated September 12, 1974, as supplemented. I Glendale, CA 91203 l e e[%cQ Nu B E G iiWwn I a cONomoNs V' " l This certshcate is conditional upon fulfelling the r e s of 10 CFR Part 71, as applicable, and( dyns specified below s. Q~ ll ] (a) Packaging y ; ) $g I (1) Model : 59( . y' h (2) Description L A prg tive verpat cLprovi e .ylpact resistance, and thermal I l resittance S ts s which ;tontain'ed wit 6tn a single snug- I fittig shie( ink W l .nf.",Thd'6verp,eckconsistsofa l vented-)s teeliffetedY q : ood outef contajner. Dimensions g of the erpapgoappfiii5a 9 in dianieter b 43" high and the i plywo ickriest gappr ".;p end 6" on the top I 61 weig t ncipdi' weight g'S,the sidef<y, a and bot ThK fh I qf,g e contents is approxima 1,780 p6bnd ' t Q> gvif g \ (3) Drawings q LW O l l a I The Drawing overpack Nos. A-0068-2C-lis con}Muq&,tgdndW0068-20.is accordakice with J. L. Shepherd & l l The inner shielded container is constructed in accordance with J. L. ll Shepherd & Associates Drawing No. A-0068-1B or DOT Specification 7A lp packaging. The special form source capsule is constructed in accordance lli with J. L. Shepherd & Associates Drawing No. A-0068-10 or to meet the I requirements of special form radioactive material. l I l' .- 1 I l I l n I I I i 152 l i 7 . 1,--------e j i l s I i l <------------------------------=&---------------------m j "8^ '" L ^" " # $ " l $"[ CONDITIONS (continued) , Page 2 - Certificate No. 5984 - Revision No. Docket No. 71-5984 'l
- 5. (b) Contents (1) Type and fonn of material Cesium 137 as cesium chloride sources doubly encapsulated in stainless- !
steel tubes to meet,the requirements of special form radioactive ma terial . , , J (2) Maximum quantity of material per package 12,000 curies.
- 6. Contents mest be positione s g Ating shielded Type A packaging I h
within the protective o .. The Type A packag i t have a metal outer I wall and meet the req nts of D0T Specification 7 kaging. )
- 7. New construction ofhrpacks are not authorized under th ertificate of Compliance. r
- 8. The package authkfzed by rticate is he roved fAuse under the I generallicensefatovisions' + (#
FR @ R 3
- 9. Expiration datekMarch 31,$1 .,
d %%~ f3 E V-(f) Y,4 k f h bo G s g 1 ;l E t :l t fA o 3 N J. L. Shepherd and Asso es' p1 ti j e er_12. 6) . Supplement dated: January 975. FOR THE U.S. LEA REGULATORY COMMISSION g%G2.4 C ries E. MacDonafd,' Mief Transportation Certification Branch Division of Fuel Cycle and Material Safety, wiSS Date: MAR 181985 153 l I I N* a crR n CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES
- a CERYlFICATE NUMSER ti REYl8 ION NUMBER C PACKAGE IDENTIFICAYlON NUMHER d PAGE NUMBER e TOTAL NUMBER PAGE9 i' 6002 2 USA /6002/B( )F 1 2 l i PREAMBd I a Thi certificate is issued to certify that the packaging and contents de cribed instern 5 beiow.me is the appiicabie safety standards set forth in Titie 10. Code of I Federal Regulations. Part 71, Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions "
I b This certincate does not releve the consignor from compliance with any requirement of the regulations of the u s. Department of Transportation or other I appucabie regulatory noences. including the governmant of any country throvoh or into which the packaos will be transported-1 I T 8 ',"'sgERgrgA, p p r sau,,Ey oN tNE,eAsis or A sArEn ANALvais,RE,gg , , , , o ,o,r v,agAj,EgpN,ogcA,Jgno i U.S. Department of Energy Safety Analysis Report for 53W/S4W New I Division of Naval Reactors Subassembly shipping container dated I Washington, DC 20585 October 28, 1968. I I I c. oocxer NuuecR 71-6002 4 CONDITIONS Thfa cert)ficate la conditional upon fulfilling the requirements of 10 CFR Part 71, as applicabse, and the conditions specified below. l (a) Packaging l I (1) Model No.: S3W/S4W New Subassembly I I I (2) Description l l The S3W/S4W New Subas }y container is fabricated from a 43-1/2 inch length M A- - nch Schedule 40 seamless pipe. l A 6-inch 150 1 t type flange i d to each end of this pipe. I Both ends of container are closed wi n end plate and eight 3/4-l 10 CRES bol dnutcombinationssecuring).a h end plate. One of the
- 1. end plates orporates a 0-15 psi pressure @gand a 7-10 lb relief l valve. ,ht ogsareweldedtotheOD-of% pe body and are used g for lif and ng the contain oss ght of the packaging l l 1s appr ately 1
.% () (3) Drawing ( jf .. O The pa Corpora in nD hcI $ . te s,R [ r i V. n 41th tinghouse Electric Rev. C, ead 901F459; n N'd'td ! h ; , p'/ 1F3 i "' O #o +o u 4 4*** i i l I i 154 i L.____________________________________________________r l_____________________________________._______.____.___ I l i . I e u.s. NUCLEAR REGULATORY COMMISSION l ,p,n,on. 3.a . CONDmON8 (continued g i 1 i - Page 2 - Certificate No. 6002 - Revision No. 2 - Docket No. 71-6002 i I I I I ) l I l (b) Contents' ! I I i (1) Type and form of material i I I I Unirradiated fuel assemblies of the following type, I I I (1) S3W/S4W Core 1 new subassembly. l l ; i I i (ii) S3W/S4W Core 2 new subassembly. l I I i (iii) S3W/S4W Core R2 new subassembly. I i, i I l (2) Maximum quantity of material per package l l 1 i One fuel assembly as described in 5(b)(1)(i), 5(b)(1)(11) or 5(b)(1)(iii). I I I I (c) Fissile Class III I I I Maximum number of packages per shipment: 6 l l l 6. Expiration date: March 31,1988. ! I I i i i 1 ,L. , REF$RENEE L/ E G i ,/ I i I l 1 .iafetyAnalysisReportforS3W/54WNewSubassembly,WAPD-0P(R)S-2894 dated I l l October 28, 1968. y 'o l l l ,'. ..s , l ,' ' FORTHEU.S.NUCLEARkGULATORYCOMMISSION i l l 50 ..r:, . .95 4 l l Qj N.* /U. s /e ,. I I J. %
- F:'
; ." s ,c C les.,EdMacDona d, C)ief ; , i r t tification Branch ; i T'v 4Transpo,rtition D $ i % f Fuei.CCe)icieland l i (f) k'g>l 't 1 I 'H - '3 ' lia $1'Safstf;NMSS4 l 1 i SEP 0 61983.1 L 3;;}; . > I I Date: ; ,,(Q:m(:.?hsg! w LO I ,l W N Ap > gn?y' ' Q I ; w z- s V l g i ),, , ' R W' Q g h /,,? \k l Y p p yr El l l l 1 l !l 1 I I I 'l I I li l l l 1 i 155 ll l l ( , fi,wc,w - ww gww.v ,vwar----- -- -- -----swr.r---- wwww wwwwww. ww-T I! I l tummmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm======mmmm========_m sene ronu sie u.s. NUCLEAR REOULATORY COMMISSION sai io Cra n CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES j ~ CERTIFICATE NUMBER 6 RiviS10N NUMBER c PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e. TOTAL NUMetn PAGEs 6003 7 USA /6003/B( IF 1 % i a PacAMet I a Tnis c.riifeste is issu.d io c.riify inat the pecuagmg and contents eescribed in item s below. meets the apphcabie sa'etr standards sei forth la Titie 10. code I of racerni negutahons. Part 71,"Packageng and Transportation of Radioactive Matenai" I b This certetscate does not rehove the constgnor from comphance witn any requirement of the reguishons of the U S. oopertment of Transportation or other I appicable regulatory agencies, mciudmg the government of any country through or into which the package will be transported. I I s vNisgTi,r;c,Ays;ss,UycTNe , eAsis or A sArrry ANatvsis,aEga;Tgt,NgcgeysgOga gC,AgON I I U.S. Department of Energy Safety Analysis Report for M-130 shipping l Division of Naval Reactors container dated December 30,1968, as I Washington, DC 20585 supplemented. e3 OCo l g - _c. ooCxsT Nuwasas .~ J71-6003 g d CONDITIONS it 5A # W d l = This certificate is condetsonal upon fulfilhng the requirements of 10 CFR Part 71, as apphcable, and the gen $tions specified beiow 3 g. *j. l (a) packaging (V l rv Q4 (1) Model nod lt 130 ^ 'M . l @ N , . 4 y (2) Description ((4(x Ad ' , , [/g,1, M , .. '" l I The'M-130 shipping; container ,ifan upright 1 cylinder 84('j)ches in n I diameter by 1581nches sverall height. t The-container Walls consist of I ; a finned 1-inch thick outer)shell((fabr,1catsd from eithfr, carbon l steel., steel), 10 carbon,stee,liwitk'd.st'ainleis inches of~1ea ,steelDelad, or,solidtstainless y t l l vessel (fabrjjated from ca$1elding,;andJa"l-inch; rbon!steelfcladwithTstainlefusteel). thick' inner The pressure i i top of the container is"c'oyered W th,a shielded -closure
- head which is I l bolted;to the c66tainer d!ansea N thQ pressure'vesse1 N An access b I cpeningwitha:bditedshieldblogisiptovide'dinthe'cjosureheadfor I loading"and unloading spent fuel, v pJ s
y v G ,,s W. . fl . g The pressufe vessel has aniinhideldiameteY of 55 iEches. The central t l not'us'ed during ' shipment) q W region surrounded contains.a secondary by'al l/2-inch thick carbon heat" exchanger (backup cylinder 29 inchesI steel lj s in diameter. The annulus which remains;between the backup cylinder I l and the pressure vessel,provides a? space 13 inches wide and 130 inches l high for spent fuel. Themspent fuel'is contained in the annulus by l l g i module holders designed for the particular core to be shipped. i i rl l The container has external penetrations to the pressure vessel for I L steam and water relief lines and a fill and drain line (which are I I capped during shipment) and a pressure sensing line which remains open l to a pressure gage during shipment. The container also has penetrations l I y ; which do not open to the pressure vessel for secondary heat exchanger l ; lines (which are capped during shipment) and a temperature sensing. I i 1ine. I I i l l I I I I I I I I i 156 I I I Lum..r...____--------------------------------J l ~ ? CONomONS (continued) ' U 5 ' * * * " M" M U"* Page 2 - Certificate No. 6003 - Revision No. 7 - Docket No. 71-6003
- 5. (a) Packaging (cont'd) l i
(2) Description (cont'd) For LWBR spent fuel shipments, the heat exchanger and associated structures have been removed, external penetrations plugged and seal welded, and an external shield and energy absorber added during modifications. The container is supported on its transport vehicle by an "A" frame structure. Gross weight of the loaded container without its support ! structure is approxima 22 0 0 po s. (3) Drawings j f0 [i i i Thepackaginjhsconstructedinaccordancewi eneral Electric l Drawing Nos.2247E209, Sheet 1, Rev. R; Sheet 2 . ev K; Sheet 3, Rev. T; Sheet 43Rev. U; Sheet 5 of 5, Rev. F and. 247G28, Rev. F. y p q/ 'f For LWBR, ppent fue)(^ shipments, the copt'Efrier has been modified in accordance with We'sti bouseE]ectrje Wing 1176JJ8, Sheet 1Rev.G, ' Sheet 2* Rev. E and sp px'pern'alepergy bs6rber added- n accordance with Westinghouse w 1El t ic Drawing 15 5632, Rev. A. ', Larm..4j p .7 , ~,,.w (b) Contents I"" g jL h[, g, ,I.l..? gG JOQ.4' v: W O* ~ (f) . R 1 ; (1) Type and form'iflina'terfii 0 F 38 j'; j i fl j : flf'7 hyi"; %/ p 1 *t ] (" - , i Irradiate t uel~ f assemblies, lac v'ated? corrosion pr6 ducts and structural i 1 parts coittajning up to .40cgallohsTof residual contaminated water. The l ), fuel assemblies and stfucturalinaEts'sWof the'f511owing types: l 9 me < j (1) S3W/54Wfuelsubassembliesofcofe;y type 2. 1 + - W ] (ii) 55W fuel modules of. core $typ'es 2 or 3. n s ,t r j (iii) S5W corner fuel modules of core types 2 or 3. : i l ] (iv) DIG fuel modules of core types 1 or 2. ' i J (v) DIG removable fuel assemblies of core types 1 or 2. ; 1 ] i (vi) SIC /S2C fuel modules with control rods. j (vii) SlC/S2C peripheral fuel modules. 1 1 1 (viii) S3G-3/3A fuel module with or without control rods. 1 (ix) SAD cell. 157 1 - --- s w - - - - - - - * ,.rs s - - - - - - - - - - - - - - - - - - - - il ?** conomoNs tcontinued) U S '"
- M
- A * '* S S'O N I I
I Page 3 - Certificate No. 6003 - Revision No. 7 - Docket No. 71-6003 I l 5. (b) Contents (cont'd) l l l l (1) Type and form of material (cont'd) l I I l (x) S3G-3/3A irradiated thermocouple and thermocouple cases. l l (x1) LWBR blanket fuel modules. l l l l I (xii) LWBR reflector fuel modules. 1 I l (xiii) LWBR seed fuel modules. I l (xiv) S8G full z elOlk without control rod. l (xv) S8G p fal size fuel cell with t thout control rod. I (2) Maximum quan ty of material per package w O i l l (1) (f52 fuel assemblies as described is 5tb)(J)(1). 9 l g I l (ii) /* Q[12fue%h 4 h/ I lassemblies as- d.ese (d<1'n5(b)(1}11)or9 fuel l l I assembl{ekas pesch1 s 5(b)())(ii) bedand{4ir(dbe/fuel assemblies i i I c;fasdesce,1 bed l'in5($)Q)( V I l s ., : i (iii) }"" 6 fuel alse$ p 2 a ,11) Q.4 + - v. ~~e l mblis.asdesed [in r5f t0(1)(Ib) and l l l (f) 4 fuel (a.ssemblied a } {deQtjbed ig5(b)(1)(V). I I WTa : M - :g v ** I I (iv) Q9fuelassembl{aj))ppl![yb; es described.in'-S(b)(1)(vi) and i I $8 I l \r,fuelyassemblieBasedeshRbbd ,y y g;p g: in 5(b)())(vii). y l (v) '10 fuel assemblissycle'scriEecl in 5(6)(1)(viii). I l j g eo s%) l 5 (vi) 9 fuer assemblies as described intS(b)(1)(viii) and one fuel I i assembly as, described in 5(b)(1)(ik). I I JT f.- p Q r I i ! (vii) 9 fuel assemblies as' described in 5(b)(1)(viii) and j l one structure as described in 5(b)(1)(x). , I i i (viii) 3 fuel assemblies as described in 5(b)(1)(xi), I i I l t I l (ix) 4 or less fuel assemblies as described in 5(b)(1)(xii). I 4 l l l (x) 6 fuel assemblies as described in 5(b)(1)(xiii). I l (xi) 4 fuel cells as described in 5(b)(1)(xiv); or ! ') i 2 fuel cells as described in 5(b)(1)(xiv) and I j i 2 fuel cells as described in 5(b)(1)(xv). I f I i 1 l I ( l I l l Ij 1 l l I l 1 l i i I l 1SB l l l l -----------------wwwwwwww----www----- +----------------= lll 4 l i .. . 1 wp m u w , conomons tcontinued) "*""****C"W"
- I ,
Page - 4 Certificate No. 6003 - Revision No. 7 - Docket No. 71-6003 i j I 1 l
- 5. (b) Contents (cont'd) l ,
I i Shipments shall be further limited by shielding and thermal requirements I as follows: l (1) Shipment of contents specified in 5(b)(1)(iv) and 5(b)(1)(v) and l limited in 5(b)(2)(iii) shall have a decay heat load not to exceed n 33,500 Btu /hr per shipment. I I . (2) Shipment of contents specified in 5(b)(1)(vi) and 5(b)(1)(v11) and I ! limited in 5(b)(2)(iv) shall be made in a stainless steel M-130 container l and shall have a decay he t opd-ngt, to exceed 18,960 Btu /hr per y shipment. Y T C .a (3) Shipment of coftphis specified in 5(b)(1)(hii), 5(b)(1)(ix) and I 5(b)(1)(x) ajidimited in 5(b)(2)(v), 5(b)(2)ty4) and 5(b)(2)(vii) I shall be madF'at a time after shutdown as determi ed from Bettis I Atomic PoKF Laboratory report WAPD-OP(PP)S-4401 'ated June 29, 1979 and sha U ave l dpcay heat load not to exceed 2 .620 Btu /hr for the l; [ shipboa core'Agd[30,000 Btu /hrforth'jfo'totypecore. l f A N g, (4) Shipment
- of contents $pecified 1/i 5(b)(
/) #d (~) 1), 5(b)( )(ii) and 5(b)(1)(iii) I N ) b)(2)(fj) A )(J hall be )made no earlier iN i and 7f' than 14fted days in 5(b)(2)(f) and 5(shal)*have a decay fisit load not to aftercshutdowntind l .yG A exceed *33,500. Bt"u/hr (f) Vq! % 'p[e"r-$ kg /f.O,' y l p l i (5) Shipment of c'ont7e71ts! speb jf(b)(1)(xi)2)andlimitedin5(b)(2)(viii) I l shallheyeaheat ; xceedi48 i ; waterqdangity'no'f'loadnott tfExee'sdf4i6 ' jalfons,000~ W Btu /hr?and a residual l I v q 'g f.g.s g 4;r Cy I (6) Shipment $f eqntents s3ec'ifiid[ inn (ti)(k)(xii)dnd limited in 5(b)(2)(ix) l shall have 'a, heat load not'toiexdeed 3,672 BTU /hr. m Z- q9 l (7) Shipment of contents specified in 5(b)(1)(xi11), and limited in 5(b)(2)(x) s N shall have a heat load ^not to/ exceed 27,'600 BTU /hr and a residual I ; water quantity not to excsed 715 g'llons. a I (8) Shipment of contents specified in 5(b)(1)(xiv) or 5(b)(1)(xv) y as limited by 5(b)(2)(xi) shall have a fully loaded container i heat load not to exceed 15,400 BTU /hr per shipment. R I (c) Fissile Class III l l Maximum number of packages per shipment: one l
- 6. For shipments involving the contents specified in 5(b)(1)(ii) or 5(b)(1)(111) W the M-130 package shall be inspected to verify that boron poison plates are in I the module holders.
l I l ' I 159 l
- __ _ _ _ . _ _ j,i
1 k------------------------------------------------ A6-, il *? ' D* "* conomous (continuen U S "U " ^ * *"" * ' "Y"" ' " Il i I Page 5 - Certificate No. 6003 - Revision No. 7 - Docket No. 71-6003 I 1 I I l 7. For shipments involving the contents specified in 5(b)(1)(viii), 5(b)(1)(ix) or l l 5(b)(1)(x) the thermocouple and thermocouple cases if included or the vacant l I module holder shall be located in the mid pos4 tion of either cage and module i I holder assembly. I I I l 8. Shipments shall be made in the dry condition, except for residual water as l l limited in 5(b)(1), 5(b)(2)(5), and 5(b)(2)(7). g I I I 9. Expiration date: May 31, 1988. I I I I I I I l gBREGuz l l &g l i I @D A>o i I .L l l u@i %n x cn >. !2- $O l 1 l 9 s :; l l cx b; JCL di D l e pr/.M, wE i r n e . i g tSjcjqm l l 'I L l l @ h g j ,I g) r "<@, em +e v 1 11 )k.' y7f 4 V l i i i I I I i I I i i i i i i I I I i I I I I b 11 N I I I I I I I I I I I i l I I 160 1 I I
- l. ., . . . . . . . . . . : : . .. .. . . .
.==,.,,,,r,', a ) l I I J * ^ ' " * ~ U* "" " # # #'* *0" l l , CONDmONS (continued) I I l li l Page 6 - Certificate No. 6003 - Revision No. 7 - Docket No. 71-6003 I ) I i ' I I l REFERENCES '! , I l l I Safety analysis report for M-130 shipping container, MAO-E8-703 dated December 30, I j 1968. l ] l ! Supplements: Naval Reactor letters A#2256 dated February 24, 1969 and G#1931 dated l l March 3, 1969; General Electric Company letter ONP-74520-526 dated April 3, 1972; i i Naval Reactors letter G#3207 dated April 27, 1972; General Electric Company letter i J' l ONP-74520-528 dated April 28, 1972; Naval Reactors letter G#3250 dated June 6, 1972; I 3 I General Electric Company letters ONP-74570-635 dated October 25, 1972; ONP-74570-654 I dated December 4, 1972; ONP-74570-666 dp,ed ppcomper 12, 1972; ONP-74570-682 dated l January dated February 6, y i ted September 24, 1973; i i 12,1973; ONP-74570-698 1973; ONP-74390-65 DLGN-85570-901 D.M974; Naval Reactors datedlett %14nuavA 31,G973,g(DN g I i dated Company 1974; General Electric January (9etters DLGN-85570-924 dated 4ebruary M,1974; DLGN- 1 I 85570-923 1974; DLGN-85570-969 dated May 24, 1974 Naval Reactors l i 1 dated letter G#4991 March dated Nover6,isir 25,1975; General Electric Company' htters ONP-74340- ) 4 , JTT-73 dated December 1 1975;'CGN-85570-1145 dated September ,A976;CGN-85570- , l l l 1146 dated September 101, 976:4CGNpB5570-ll48 dated Septe der 14, 1976; Bettis Atomic l l Power Laboratory letter ^L l l l June 29,1979; Naval Reactor lettebsTGr6197Aaled APD-R(k)hl378datedfugusV3p}3,1979;G7136 3 Qu]y}fl976; WAPQ)4)P(PP)S-44 dated I l il March 17, 1982; andWAPD-LD(CES)SE-181/datedSeptemberi1.981;WAPD'-Le(CES)SE-96 I I ! jated February, 1982,iAPD-LP(CES)SE9 70 g dated 4uly11981: Naval Re&ttors letter fG#7160datedMay 18,1982; ~ s 'e,tterfG#7582/dsted Siptember 7, l 1983- (/) $f ?QVl r i l i I () andNavali. M;.1 f ,s I I Reactor,f1-)e@s$tNUCL ,'e"j? w@ i I i - e 4.FOR JHE ycty3. ug l 1 ,,. 9" ;% mg#}. gg o C9 l, s .. . e g, d [ I .) l Charles E. MacDonald, Chief I ' ^ transportation" Branch I i( Division 'of Safeguards and I j Transportation, NMSS l . i i JUN 5 90 ll l Date: I i i 1 I i I i i I I I I I N I l ( I I I I I E 161 1 1 I I__________-___-------_m.. - . . . . .._mm... ... ..._t ,____-______-___ ___ ___-_ ______=_-- ___ _ ______ ____ ,m __., I sene ronu sie = u.s. NUCLEAR REGULATORY COMMISsloPo CERTIFICATE OF COMPLIANCE h l to cFR " FOR RADIOACTIVE MATERIALS PACKAGES 0 D REVISION NUMBER c PACKAGE IDENTWICATION NUMBER 0 PAGE NUMBER e. TolAL NUMBEA PAGES .f ! i . CERTIFICATE NUMBER 6049 3 USA /6049/B()F 3 1 h L, ' HEAMBLE h ( a This certificate is issued to certify that the packaging and contents described m item 5 below, meets the appucable safety standards set forth in Titie 1o, code N i of rederal Regulations. Part 71,"Packagmg and Transportation of Radioactive Material." I I b This certificate does not reheve the consignor from compi ance witn any requirement of the reguistions of ine u s. Department of Transportation or einer jI' I apphcable regulatory agencies, mcluding the government of any country through or mio which the package will be transported. 'I l h l I
- 1. N
' " ^' I * '*siE**J.'f a ,'#13' "' *** ' ' '" ^"^."'E"E A'o'io'EEEc'S$U"E,"oOA* APE"cArioN lI U.S. Department of Energy Safety Analysis Report for 426A and 426B liI i Division of Naval Reactors shipping containers dated January 31, 1969, Washington, DC 20585 as supplemented. ll> I f c oocxErNUuBER. 1 71-6049 fI 4 CONDITIONS This certaticate is conditional upon fulfalhng the requirements of 10 CFR Part 71. as apphcable, and the condibons specified below ,i , d i M! l I (a) Packaging f I, (1)J Model Nos.: 426A and 4268 i l l:i ql! I (2)'~ Description I W I .The Model Nos. 426A and 4268 containers are used to ship and store ! [ q new unirradiated 55W Core R3 core cartridge assemblies, new unirradiated S3W Core R2 fuel subassemblies, and new unirradiated p bi q S1W Core R3 core cartridge assemblies. The 426A container, the k' I basic design for this series of shipping and storage containers, is l' l a horizontal cylindrical metal weldment 73-1/2" diameter by 226 N , inches in length. The container, mounted on wooden skids, is l g 82-9/16 inches high and weighs 6,000 pounds empty. The 4268 p y container is essentially identical to the 426A container in all h l l respects except for length. The 426B container was made 292 inches E long (66 inches longer than the 426A) to accommodate the no longer E l f,{ existing S1W-4 instrumented core cartridge and weighs 7,900 pounds ' empty. The container assembly consists of three major subassemblies: f t i the upper section, the lower section, and the cradle which supports l-i the core within the container assembly and supports the new fuel F: I assembly. The maximum gross weight of the 426A container is V i 27,960 lbs. 5: 1 1: i L i l- I i 1 ! i i: i R. i 1 ; i l i i i ! l N i I i I I i It i l 162 f i i .ir--------,-------------------------------------------- i I i l Ul " ""~ CONOmONS (continued) U'O' NUCLEAR REGULATORY COMMISSION ) 4 Page 2 - Certificate No. 6049 - Revision No. 3 - Docket No. 71-6049 l l (3) Drawing The packaging is constructed in accordance with Applied Design l Company Drawing No. 426A401, Rev. C. i l (b) Contents l (1) Type and form of material l l Unirradiated fuel assemblies of the following type, ) l l (1) S5W Core R3, par 3rigeII ly, with all control rods I installe(9 JBstra1he J ' fullyinsertedpositionwith rod bw caps. l l (ii) Shore R2 fuel assemblies, with s of borated steel , i ~ ured in place over the assemblie the 53W/S4W New Core ! I .onent Adapter Kit. I (11Qj SlW 3 artridge asse j'./thallf,put.rolrodsinstalled i j g and res p in "fpJly i ; r,ted positW by a control rod i holddow,p. . i
- O (2) i pKmum n d
9 eftM- a { M fuel s) 5 5( 1)(111 '9 3s.Nh (' j(1),p)(1)(11)or (c) Fissile yJhss 7 (h/ s III V. Maximum numbe,g ,of package ~ per shipment.(/ one
- 6. Expiration date: July 31p19 3 (
REFERENCE Safety Analysis Report for 426A and 426B shipping containers, WAPD-0P(R)S-3105, dated January 31, 1969. 163 MEMMMMM M EMMEMMMWWMMM M MMMKWWhMWMMMMMMMWHMMMMMMMgggM U."el' "" "" cowomons (conunved; o s umAn necouTORY COMMISSION Page 3 e Certificate No. 6049 - Revision No. 3 - Docket No. 71-6049 1. l.. I Supplements: Bettis Atomic Power Laboratory letters WAPD-0P-(R)S-3373 dated June 11, ; l 1969,WAPD-0P(R)C-71datedMarch6,1972,WAPD-0P(R)C-139datedAugust4,1972,WAPD- , i OP(R)C-145datedAugust 11,1972 andWAPD-0P(R)C-164datedOctober6,1972. I I FOR THE U.S. NUCLEAR REGULATORY COMMISSION I I i Charles E. MacDonald, Chief I Transportation Branch i I I R R EMSW on of Safe rtation9uards NMSS and ho Date: JUL 2 71987 O i , 4 ! I k #p i I l et .4 l J l w % / I !.. <C O ) *s,. tk ,e I o s , ! 4 ef
- yr M !
I I I I I I I I I I l I I I I I I I I I I I I I I I I I I I I I ( l l' I I N I I 164 l ti 1 _ __ _________--___________-_A p______________________________________________________,I U.S. NUCLEAR REGULATORY COMMISSION I senc Fomes ets a l I om> CERTIFICATE OF COMPLIANCE I 1 I io CFR n FOR RADIOACTIVE MATERIALS PACKAGES C PACKAGE IDENilFICATION NUMBER d PAGE NUMBER e. TOT AL NUMSER PAGES 1 a CERTIFICAff NUMBER D REVISION NUMBER 6058 9 USA /6058/B( ) 1 4 y
- i. I l PRwsses l
- s. This certificate is 6Seved to certify met the packaging and connnts described in item s below, meets the apphcable safety standards tot forth in Title 10. Code )
i l of Federal Regulations, Part 71." Packaging and Transportation of Radioactive Material." i p l l b. This certsfacate does not reheve the consignor from Comphance with any requirement of the regulations of the U.S. Department of Transportation or other l apphcabie reguistory agencies. including ine government of any country enrough or into which ine package will be transported. I I I I 3 THi TIFICA S SSU THE BASIS OF A SAFETY ANALYSIS RE Y OF TH E 8 QN OR A Cintichem, Inc. Cintichem, Inc., application dated i l l March 31, 1985, as supplemented. I I i P.O. Box 816 I l l Tuxedo. NY 10987 I I ,, h DdCf(ET N 8$R ]hgg I I a CoNomONS y v Tns. conivicai. . conditional upon fummng megeah, rnen , sui of iO cm eart n. a. apphcanie. a cm.d b.iow-l I I s * /' (a) Packaging l (1) Mod [1[No.h . ./ [ l D [1 }'/ I s[cription % ' Q l l (2) g ;;7 ,ff f l I The" packaging Yonsi t of[ lea sh de teel weldh in the shape I oPa right3hollowic'klindedylt a t W ahd a recessed plugtype f l , ' id' The pac ging1jirovides a mtdum of 6 inches l i of lead klejdinir? rednc)dde/,lifti 7nd tie-down I I desketed dhfcesandla5drai to,. anpbolted):' qn Pack hlrf The' maxi weight of the l I I loapedpackaftpfis3p% , ;l p ' 4 a f{eaVity! s ! " 9 %- I I I Q C $?6 >! The ,ou'ter shsllti's[$faa and p0 Jp b]teldhtEel - nstructe[/)nd! is 4 l in diiimeter dnd 57 iinchethffh".Ghe ;. 1aminatef9re of plate material I l i 1/2-i'ndh,,and 1/4-inch fn' tijckness. j inner shg11 is of 1/2-inch l i I thick st,egl, plate. The Tntepnll~ cavity dimen s are 26-1/2 inches I I in diameter,and 43-1/4 inches high. The 1 f the same construction as the sidet,and bottom and is secured to body of the packaging by l l twelve,1-1/4-inchfhiameterpy2-nch)^enghighstrengthboltsand i sealed with a siliconsjQ 7 tingr g l i I I I I I I I I I I I I I I I I I I I I I I I I I I I I ' f 165 ( I l . I I E _ .. 1 l l l 7,C * * ^ coNomONS (conunuedf "$'"" "# # "Y " $' " I i j 1 I l I \\ ; i 1 r Page 2 - Certificate No. 6058 - Revision No. 9 - Docket No. 71-6058 I k ! I i l I I I I l l i 5. (a) Packaging (continued) l l l I I (3) Drawing l I l { I I q The packaging is as described and constructed in accordance with I l Cintichem, Inc. Drawing No. 330E2053E, Revision E. J i l l (b) Contents ! i i I (1) Type and fom of mate i l (1) Byproduc REG 'anium enriched h -235 isotope, U-233 or I , i pluto solids, non-powder, an r which will not decompose ! j i 1 l at teq tures up to 525'F and packag thin DOT Specification 'l ' I 17H 1 drums. I i (ii) odQa d uranium enriched in J, hem 3Qotope, U-233 or 3 l oniunt meets the requi of special fonn radioactive erial . l () g ,, y l l (iii) product ma r an u'raniu qf'idhedinthb-235 isotope, I I I- ' 233 %com, r Qu td fuaM[dsol$ds {owdpr, an y which will not I - stures ur , F, garckag ithin a nominal I I l ,h 2-1 icif fiK)E ye hyleneOligh tegrity Container ' i @; HIC). d$ hst < ; pii l ron Oxide mix in i teel Tnerg k a l I t 'iYied ,i l J6emtr uding g sware, must be I i l- d I a . compreQd (as required). l l l (2) Maximum ptity of t &rgpa ' gQ I l For the con described i 5(b)(1)(1) b)(1)(ii): Not to exceed 400 ps e al ay[ l l For the contents described n 5(b)(1)(iii): l l The HIC must be limited to 200 A y' I radioactive material and not mork quantities of solidified liquid i than 50 A2 quantities of other I radioactive materials. The maximum thermal decay heat load nust not l l exceed 15 watts. I I I I I I I I I I I I I I I I I I I I I I I I 166 I I I I ra c ro w *** " "'""'** * * *
- l g. r, conotreous (continued)
! Page 3 - Certificate No. 6058 - Revision No. 9 - Docket No. 71-6058 I ; r l l n' 1 l l
- 5. (b) (2) (continued) l j l
For the fissile contents described in 5(b)(1)(1), 5(b)(1)(.ii), and I l 5(b)(1)(iii) not to exceed the following: I I I I I Fissile Maximum per Material Package (grams) l l ' l l l U-235 350 i 1 U-233 -200 I I Plutonium
- 2 4 I I i
I or, pro-rat c h b xB REG-es such that th the ratios of the quantity l i of each fi terial to its maximum rpackaging does not exceed i .) i unity. n I i i A V . I N *Plutonhm in excess of 20 curies per package t be in the fonn of I l reac{g f 7, uel elements, metal, o, -16td1 a p. l l (c) Fissile $s - . II Q ! Forcon$scontainn- e; q )%> cial nu ea 'e jal: q O l l I Minimum}ttans nd" . to be shpp on ' 10.0 l g 6. For gamma-emit}1139 spec fony;1np r i i u l,t ( le inches,,,of additional lead I shielding may r ddedi u1Indi jld 9 11 sid6)within the internal I cavi ty. 4 g l l 7. The total weight Jpp contents _hgaddiional d shielding as may be l l required shall not eM 9,000 pounds. N 8. Prior to each shipment, the%d 0tring shajj hinspected. The 0-ring shall be I d replaced with a new 0-ring if inhect,%n Wws any defects or every twelve (12). I months, whichever occurs first. l l l 9. Prior to the shipment of contents described in 5.(b)(1)(1), the package must be ! leak tested as specified in Section I of the application, j 10. The packaging rust be maintained in accordance with Section I of the application.
- l l 11. Fabrication of additional packagings is not authorized. l l l 12. The package 6uthorized by this certificate is hereby approved for use under the !
A general license provisions of 10 CFR $71.12. 1 1 ( [
- 13. Expiration date: December 31, 1990. j.
f~ l l I a I 167 ' , i ( ,. .. -_ ._..________________________l - wacjou na" coNomONS (continued) U.S. NUCLEAR REGULATORY COMMISSION I Page 4 - Certificate No. 6058 - Revision No. 9 - Docket No. 71-6058 P l I l-1 I I l REFERENCES l l Cintichem, Inc. application dated March 31, 1985. l l l l Supplements dated: August 30 and October 31, 1985. I I I l E . ! FOR THE U.S. NUCLEAR REGULATORY COMMISSION l I 9Wey:b" Dharles E. MacDo ief I l l yh Transportation Cert 1 Division of Fuel Cycle Materici Safety, MiSS on Branch a l}}