ML20209J042
| ML20209J042 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1985 |
| From: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| References | |
| NUREG-0383, NUREG-0383-V02-R08, NUREG-383, NUREG-383-V2-R8, NUDOCS 8511110338 | |
| Download: ML20209J042 (633) | |
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1 t NUREG-0383 o l Volume 2 Revision 8 , i 1 1 I l Directory of Certificates of Compliance l l for Radioactive Materials Packages j' I ! Certificates of Compliance i i 1 , 1 t l U.S. Nuclear Regulatory l Commission Office of Nuclear Material Safety and Safeguards ;
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o f NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications'will be available from one of the following sources:
- 1. The NRC Public Document Room,1717 H Street, N.W.
Washington, DC 20555
- 2. The Superintendent of Documents, U.S. Government Printing Office, Post Office Box 37082, Washington, DC 20013 7082
'I
- 3. The National Technical Information Service, Spa gfield, VA 22161 l
Although the listing'that follows represents the majority of documents cited in NRC publications, it is not intended to be exhaustive. Referenced documents available for inspection and copying for a fee from the NRC Public Docu-ment Room include NRC correspondence and internal NRC memorande; NRC Office of Inspection and Enforcement bulletins, circulars, information notices, inspection and investigation notices;- Licensee Event Reports; vendor reports and correspondence; Commission papers; and applicant and licensee documents and correspondence. t The following documents in the NUREG series are available for purchase from the GPO Sales i Program: formal NRC staff and contractor reports, NRC-sponsored conference proceedings, and I
. NRC booklets and brochures. Also available are Regulatory Guides, NRC regulations in the Code of +
Fadoral Regulations, and NucAser Reguietary Commission Ismances. : Documents available from the National Technical information Service include NUREG series , reports and technical reports propered by other federal agencies and reports prepared by the Atomic l Energy Commission, forerunner agency to the Nuclear Regulatory Commission. i Documents available from public and special technical libraries include all open literature items, i such as books, joumal and periodical articles, and transactions. Federal Register notices, federal and . state legislation, and congresssonal reports can usually be obtained from these libraries. Documents such as theses, dissertations, foreign reports and translations, and non-NRC conference [ proceedings are available for purchase from the organization sponsoring the publication cited. l Single copies of NRC draft reports are available free, to the extent of supply, upon written request { to the Division of Technical Information and Document Control, U.S. Nuclear Regulatory Com- i mission, Washington, DC 20555. Copees of industry codes and standards used in a substantive manner in the NRC regulatory process are meintained at the NRC Library, 7920 Norfolk Avenue, Betheads, Merylend, and are available - there for reference use by the public. Codes and standards are usually copyrighted and eney be purchased from the originating organization or, if they are Americon Nationel Standards, from the ; American Netionel Standards institute,1430 Broadway, New York, NY 10018. i f L I t I r V
NUREG-0383 Volume 2 Revision 8 Directory of Certificates of Compliance I for Radioactive Materials Packages
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- Certificates of Compliance n" W aT 2 n in "'"5 Division of Fuel Cycle and Material Safety Office of Nuclear Material Safety and Safeguards i U.S. Nuclear Regulatory Commission Washington, D.C. 20566 ,
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FOREWORD This directory contains a unmary Report of the U.S. Nuclear Regulatory ,i Connission's Approved Packages (Volune I), all Certificates of Compliance !l (Volune 2), and Sunnary Peport of NRC Approved Quality Assurance Prograns ,
' Volume 3) for Radioactive Material Packages effective October 1,1985.
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) The purpose of this directory is to make available a convenient source l'
of infonnation on packagings which have been approved by the U.S. Nuclear j Regulatory Connission. To assist in identifying packaging, an index by Model Nunber and corresponding Certificate of Compliance Number is ! 3 included at the back of Volumes 1 and 2 of the directory. A listing by l packaging types is included in the back of Volune 2. An alphabetical
; listing by Company nane is included in the back of Volume 3 for approved ; QA prograns. The Sunnary Reports include a listing of all users of each i package design and approved QA programs prior to the publication date of ; the directory. ) Shipments of radioactive material utilizing these packages rust be in cccordance with the provisions of 49 CFR 6173.471 ard 10 CFR Part 71, as applicable. In satisfying the requirenents of saction 71.12, it is the responsibility of the licensees to insure i.nemselves that they have a copy of the current approval and conduct their transportation activities in accordance with a Nuclear Regulatory Connission approved QJality assurance progran. Copies of the current approval r,ay be obtained from the U.S. huclear Regulatory Connission Public Document Room files (see Docket No. listed en each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR %71.12 does not authorize the receipt, possession, use or transfer of byprodJct, source or special nuclear naterial; such authorization nust be obtained pursuant to 10 CFR Pa ds 30 to 36, 40, or 70.
Please note that not all packages have been generally licensed in accordance with 10 CFR @71.12(d). If a person desires to use a package which is not generally licensed, please contact the Transportation Certification Branch, U.S. Nuclear Regulatory Connission, concernir,9 steps that must be taken to obtain a general license for the package. Connents which would nake future revisions of this Directory more useful are invited and should be directed to the Transportation Certificati n Branch, U.S. Nuclear Regulatory Connission. Transportation Certification Branch Division of Fuel Cycle and Material Safety,17155 U.S. Nuclear Regulatory Connission Washington, DC 20555 l 1 1 1 1
I uneron= sis U.S. NUCLEAR REGULATORY COMMISSION I I! osu CERTIFICATE OF COMPLIANCE il Ei 'o ca n FOR RADIOACTIVE MATERIALS PACKAGES lI
,k i crate cars Nuusta o sevissom Nuusta c FacxAca totNTwication suusen o emoe Nuusta 3 k 0361 2 USA /0361/B(U)F 1 . rotat4 Nr : seen pa PatAM8Lt 'l l' a rn. certaicareis ued to e.nw rnat tn packaging ar d contents d.scr.b.d initern s baio* rner re tn ppacabie sa'ety siancardi set tortn n Titi. io. coe.oe 'p j q) red.rai n.guianon Part 11. ' Packaging of Radioactiv. Materiets for Transport and Transportation oe Radioactiv. Mat.nal Under Certain Condetions " g I! b in.s c.nifica. do. not r . tn. constgnor vror- coinsianc. .itn any requwern.nt or tn. r guistions or en. u s o.panrn.nt ce Transponation or otner lt Et apphcab6. r.gulatory ag.nces. ancludsng tn. governm.nl of any Country through of 6Dto which the package wid b. transpon.d ,)
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h U.S. Nuclear Regulatory Commission NUREG-0361; Safety Analysis Report for the Plutonium )'y I; Washington, DC 20555 Air Transportable Package tiodel No. PAT-1 I p fl :q l' !g lI e occur u eca 71-0361 's
@(;rn...cre.coror.o s car. s condaions, uoan veni,ig te reque.rn.nts oe to em Part 11, as appicable. and tm. condetions specif'wd below
'l I )l If " (a) Packaging 'I I
!I fn: (1) flodel No. : PAT-1 {
I! (2) Description 1l lil y I; A stainless steel containment, vessel (designated TB-1) surrounded by a I stainless steel and redwo' od byeYpac'k/ (designated AQ-1). The contents ;II l are sealed withinga# stainless steel ' pro' duct can (designated PC-1) I ( inside the containment vessel. ^1# h I I i 8 The AQ-1 overpack is a right circular cylinder),s approximately 42-1/2 r" ;f
, y I inches long by,24-1/2 inches outside diameter.rThe walls of the
$ overpackr ponsist- of approximately 8 inches of gt'ain oriented redwood lL I 5 encased within double ' stainless stpel/dru'ms. Thesends of the drums $
h are doubly closed? fA;,c'gppertheat (conducting element and an aluminum / g: load distributer arelerdased withi ithefredwood.C ) J gl (, ,4y te mgg j (j
- l. The TB d 1} containment;ve33al,Js a proximate inches outside(yl 8-1 ,
I: length by 6-3/47, inches'Adtistdfd aineterW The millinum well thickness of the vpssel 'tyapproximdtie)y H LinchJf,The inft'erior cavity of the f ( g: vessel 154 ricjhtjc.ircula'd ctUrdef. 4-l/4 incPg diameter, with f 4 gi hemispherical endy.-EThe'vessellis*tlos,ed by JR,'l/2-inch diameter J ll bolts and dchbly sealed withla Qoppsrjpasketsaiid knife edges and an : ll elastomer O' r'ip. WJ Q' [ 0 N 4 W Tiu4 i l: i S' a . e [ I ' l'! I
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gb nac ronu staA U.S. NUCLEAR REGULATORY COMMISSloN sm CoNomoNs (cononuem l il (i Page 2 - Certificate No. 0361 - Revision No. 2 - Docket No. 71-0361 I ) l I!' !I
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1 S. (a) Packaging (continued) ) 3 fll (2) Descriptinn (continued) j The weight of the package is approximately 500 pounds. The weight of 1; the TB-1 containment vessel, when loaded with 4.4 pounds of contents j
; I; is approximately 41.7 pounds. 1 lI y!
b (3) Drawings and Specifications f' The Model No. PAT-1 packaging is fabricated in accordance with the lN l drawings and specifications in Section 9.0 of the Safety Analysis Report, NUREG-0361. j 1 1 l I! i n l l [:
, (b) Contents II
)
fI (1) Type and form of material jll p y ' I Plutonium oxide and its daughter products, in any solid form. The g lR,i plutonium oxide may be mixed with uranium oxide and its daughter 'g
'8 products, in any solid form.
1, I g h (2) Maximum quantity of material per package and adoitional permissible 1 g contents ,{ I y I l' (i) Maximum 2.0 kg total radioactive material, plus: maximum 16 grams 'g d of water and 10 grams of polyethylene or polyvinylchloride bagging I [g material. The maximum decay heat load of the contents may not i exceed 25 watts. 'I
)
k: (ii) Maximum 200 grams total" radioactive materici, plus: maximum one 'l l I: gram of water, maximum 200 grams of metal canning material (in
- d. addition to the PC-1 product can, Drawing No.1024), maximum 64 '(g l
I grams of aluminum foil or, honeycomb (in addition to the top 'I l [ g. spacer, Drawing No. '1015), maximum 175 grams of glass and maximum 35 grams polyethylene er:polyvinylchloride bagging material. The lli- , I g: maximum decay heat load'of the contents may not exceed 25 watts. 'I I I: I j I. (c) Fissile Class: .I; l I I, 6. The PC-1 product can (Drawing No.10'4) and the top spacer (Drawing No.1015) need not be used when the contents include 20 curies or less of plutonium. I ['I % I < N. 7. Prior to first use, each packaging shall meet the acceptance tests and standards E l specified in Subsection 8.1 and Section 9.0 of the Safety Analysis Report. ll I ( I, 8. i Prior to each shipment, the package shall meet the tests and criteria specified g l [ in Subsection 8.2 of the Safety Analysis Report, t 4 1 gl g 1 The package shall be prepared for shipment and operated in accordance with the I l lj i: procedures specified in Section 7.0 of the Safety Analysis Report. j g ,1 l ? h l 5 gagy;g, , .,., , . . ,
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. _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____,_,__y,______;
u.S. NUCLEAR cECULATO2Y COMMISSlHN ! g' Nac roam sisA CONDITIONS (contuwed i$ " g
!I 3
!I Page 3 - Certificate No. 0361 - Revision No. 2 - Docket No. 71-0361 f(l I:
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- 10. The systems and components of each packaging shall meet the periodic tests and I;
I criteria specified in Subsection 8.3 of the Safety Analysis Report. j 1 L
- 11. Repair and maintenance of the packaging shall be in accordance with Sections 8.0 and 9.0 of the Safety Analysis Report.
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- 12. The packaging shall be designed, procured, fabricated, accepted, operated, maintained, and repaired in accordance with a quality assurance plan approved by j}
84 the Nuclear Regulatory Commission for this purpose. I g J1 1 Throagh specfal arrangement with the carrier, the shipper shall ensure observance f 13. of the following operational controls for each shipment of plutonium by air:
,I 1
I 'i 1, (a) The package (s) must be stowed aboard aircraft on the main deck in the aft-I most location that is possible for cargo of its size and weight. No other y type cargo may be stowed aft of the package (s). {) 1 (b) The package (s) must be securely cradled and tied-down to the main deck of the aircraft. The tie-down system must be capable of providing package I f f restraint against the following inertia forces acting separately relative y f to the deck of the aircraft: Upward, 2g; Forward, 99; Sideward,1.59 ; y
,i j Downward, 4.5g.
f (c) Cargo which bears one of the following hazardous material labels may not be I 1, transparted aboard an aircraft carrying a package (s): 1 4[ d Explosive A 5 Non-Flammable Gas ; Flamable Liquid +g I Explosive B Explosive C Flammable Solid 't 1, Spontaneously Combustible Flammable. Gas ;>1 Oxidizer
]f 1
Dangerous When Wet Organic Peroxide Corrosive ,j J This restriction does not apply to hazardous material cargo labeled solely j'i
'; - t J as: .
I p 1 Poison 'l f; Radioactive I I Radioactive II Poison Gas I J J Radioactive III Irritant 1 Megnetized Mateirals Etiologic Agent-
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y g 1 j 1 14. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR $71.12. , j{, 15. The package authorized by this certificate is hereby approved for transportation 3 J of plutonium by air. [ T I I 16. Expiration date: August 31, 1988. t I I I I L l l 1 I i 1 L.______._ ____ m _ _m___ ______________ _________3
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Mnc FOR3 st4A U.S. NUCLEAR REGULATORY COMMISSION g (843) CONDITIONS (cononued/ k I- , F fj Page 4 - Certificate No. 0361 - Revision No. 2 - Docket No. 71-0361 l [ il : ? n l! : l REFERENCES I:l [ I Safety Analysis Report for the Plutonium Air Transportable Package Model Number PAT-1, [ l NUREG-0361, June 1978. l I, I! Sandia Laboratories application dated February 20, 1980. l J q! I ' l' COR THE U.S. NUCLEAR REGULATORY COMMISSION g F g! Charles E. MacDonald, Chief l Transportation Certification Branch 5l 1 Division of Fuel Cycle and li i; Material Safety, NMSS [ L e f Date: SEP 0 61983 i [
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- NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION
+a CERTIFICA1E OF COMPLIANCE
'o cFR n FOR RADIOACTIVE MATERIALS PACKAGES .l D REVISION NUMBER c PACKAGE IDENTIFICAf 6CN NUMHER o PAGE NUMBER e TOT AL NUMBER PAGES !
t a CERT 6F6CATE NUM8ER 3 4888 6 USA /4888/B( ) 1 h, __E a This cert,t,cate is issued to certif y that the packaging and contents described m trem 5 below. meets the apphcable safet y standaras set fortn in Title 10. Code $ of Feceral Regulations Part 71. -Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certa.n Condshons " k
- b. Tnis certihcate does not reheve the cons.gnor from comphance w:tn any requirement of the requisbons of the U S Department of Transportation o other b
appbcabee regulatory agenctes. mcluding the government of any country through or mto which the package wtH be tra1 sported 3 THIS CERT $lCATE IS ISSUED ON THE BASIS OF A SAFETV ANALY$tS REPORT OF THE PACKAGE DESIGN OR APPL 6 CATION a PREPAAED BY INaw and Awessa b itT EL AND IDENTIFICATION OF REPORT OR APPLICA7 TON ji Teledyne Energy Systems Martin Company application dated 31 110 West Timonium Road August 13, 1965, as supplemented. Timonium, itD 21093 71-4888 , c OOCKET NUMBER - a CONDITeONS This certAcate es conditional upon tuffelhng the requirements of 10 CFR Part 71. as apphcable. and the conditioris specified below 5 l (a) Packaging j
'N (1) flodel Nos.: Sentinel-25A, LCG-25A; Sentinel-25B, LCG-25B; gj Sentinel-25C, LCG-25C; Sentinel-25C3 -250,-25E, 'nl and-25F $0 (2) Description j h
The packages are themoelectr'ic generators. The major components 3 include the main housing, tungsten shield, housing flange, and electrical hj b connectors . The' approximate dimensions and weights for the various Model Nos. are as follows: j, 11odel No. Dimensions (inches) Weight (lbs.) 'n R Sentinel-25A, LCG-25A 25 OD x 25 3000 't Sentinel-25B, LCG-25B 25 OD x 25 3300 2000 )8 Sentinel-25C, LCG-25C 24 OD x 32 i Sentinel-25C3 24 OD x 32 1300 :j Sentinel-25D 25 OD x 27 3300 !g Sentinel-2SE 25 OD x 34 4200 , Sentinel-25F 24 OD x 32 1400 ls t
% 9 i (3) Drawings The packagings are constructed in accordance with the following Drawing !s Nos: lg l
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'. I' CONolTioNS (continued) f I~
Page 2 - Certificate No. 4888 - Revision No. 6 - Docket No. 71-4888
- 5. (a) Packaging (continued) l R' l (3) Drawing Nos, f
R. flodel No. Drawing Nos. I; ~ All flodels Isotopes, Inc. Drawing Nos.: 001-20000 001-20001 001-20002 ; 001-20003 l Sentinel-25A, LCG-25A .. nr _Jtartin Company Drawing Nos.:
# Of,t ii C fjN0013100 '
/ ,g*' G# N0013108
' N0013113 s PN1000003'k Q['
Sentinel 25B, LCG-25B V tiartin Company; Drawing F 5.:
% 1 N0013200 '
/
,7! , 4;x N00)3208
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wJ ~3x 7p ",~, Sentinel-25C, LCG-25C \ Isotopes. Inc. Drawing Nos.:
?, - ? . [001FC10000
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Sentinel-25C3 s V f M
, v 4 .- ( -001-70012 7 ,
c r# Sentinel-250 ..
~/ . O- (jgjits.r
*i. _ ._. 3 001-40019
_s , a Sentinel-25E " U. in s-7ie g g g t { i L ' Isotopes,,Inc. brawing Nos.:
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Sentinel-25F F,7.- f.j I ! p'i D> 001E10000 , J, P
'.J 001010000 '
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',e ~00lF10000, Rev.#H*
t ,/ _
- < >+ 001L70033 J'?
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.H' .o 001270024 Y i
'!h. 001-400065~' 4
'/ 001-40015' y
< 001 40017 ;g
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*as modified by Figures 1 and 9 of %
the April 26, 1985 application. (b) Contents (1) Type and fom of material li g (i) Strontium 90 titanate doubly encapsulated in a Hastelloy or Uniloy fuel capsule which meet the requirements of special fom I g
,! radioactive material; or jg (ii) tiodel No. Sentinel-25F nay have, s+. W w. 'luoride doubly l ' encapsulated in a Hastelloy or Unt/c tje' (1psule, with a Hastelloy l_
ln N. C-276 liner which meets the requirer..ents' u; opecial form radioactive ma terial . l l I (2) The maximun quantity of material per package i l l i 125,000 curies 6 1 w s rsi.r s - - - ws.rs w r v !
m a m K Ei M m m 5 2mm m maTK E3 N M M *Sf1 N %:EG N - '
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CONDITIONS (ccntinued) Page 3 - Certificate No. 4888 - Revision No. 6 - Docket No. 71-4888
- 6. A barrier (pemitting the free circulation of air) must be provided with sufficient separation distance to ensure that the requirenent of $71.43(g) will be net.
- 7. Eye-bolt shall be removed or covered during transportation to prevent their use as tie-down devices of packages.
- 8. Fabrication of additional packagings is not authorized.
- 9. The packages authorized by this certificate are hereby approved for use under the general license provisions of 10 CFR 971.12.
- 10. Expiration date: March 31,1986. ~
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,g G_.,s REFERENCES ~ C <,
Isotopes,Inc. applications [da'ted: September 15 and 16,1969; and March 30 and
.- April 20, 1970. y c.>
l Martin Company application dated October 28, 1965; with supplements dated: January 14,
; April 1, and July 21,L1966.~ , X Uj p O .,
Martin Company application 1967. dated;'ita,rch ,"21.(w . x, i Martin Company appli[ation dated Nuhust 16,.1967; hith supplements'-dated: September 1, and September 15, 1967. 2.
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n Isotopes, Inc. appitcation. dated Septenber. . - g i10; 0969;'with supplement dated: October 30, 1969. , -4 ' y ji;{j { jg , y~
,) VW au t 3 ; ) :i ; : n n .- c Isotopes, Inc. application dated:Decembertl6}fl968';l with supplements:p da 1968; and January 10, Ig69. t. . 3 ; ; fj l L' A ,, t,_ '
%g D '
Sentinel-25F - '. f)
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t Teledyne Energy systens applic'ation; dated April 26, 1985. i eP 4 A ,y 7- ' FOR'THE U.S. NUCLEAR REGULATORY COMi1ISSION ; i M[b Charles E. MacDonald, Chief j h Transportation Certification Branch j l Division of Fuel Cycle and !g Material Safety, NMSS INl
- h i
! Date: JUL 191985 >n
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Hl ,gs w ##,.r,.cse,,3 l'- - _ _ _ - _ _ _ _ - - _ _ _ _ _ m _ _ - - - - - - - - - _ _ - - - - w . ###a
p *4NSMEfihWMuWmJ=mwwammpwwwwwwummmmmmww E."Si CERTIFICATE OF COMPLIANCE 4; TG CFR F'
' FOR RADIOACTIVE MATERIALS PACKAGES f . cERrisicATE Nuvenn b REVI5e0N NUMBER c PACRAGE IDENilFICAf TON NUMBER d PAGE NUMBER e TOTAL NUuef M PAGES q' 4909 5 USA /4909/AF 1 2 i
l M Avet t l! i i q i a in.s certit.cate o issued to certify that tee packaging and contents described en item 5 beso*. meets Ineappocable safety standards set fortn in Titie to code of Fede*at Regulations. Part 71. ' Packagsag of Radioacteve Materials for Transport and Transportation of RadioaCleve Maternal Under Certain Conditions ' 5 O R. ints certificate does not reheve the cons.gnor from comphance witn any requirement of the regulations of tne U S Depaetment of Transportation or olner appocanie ,eguiaiory agencies .nciud:ng ine go. rnment of any country enrougn or into atucn ine pac = age ..ii be transported 4. d, j
" ':"ut:=== r**"' ' '"'" '~^"t=L'a =^t,===;='e ~c.rieN General Electric Company General Electric Company application dated i
1 P.O. Box 780 November 19, 1982, as supplemented. Wilmington, NC 28401
?; ;
, occath u ,H y 71-4909 4 CONDITIONS l
in.s cert fecate is corid+onal wport fulfsHang the reqwrernents of 10 CFR Part 71, as appbcable. and the cand bons specife1 beion (a) Packaging (1) Model Nos.: GE-21PF-1 and W-21PF-1 (2) Description Packaging as described and constructedLin accordance with 007 Specification i 21PF-1 except as shown in General Electric ' Company Drawing No. 769E237 (GE-21PF-1) - Sheet Nos.1 and 2, Rev. 3; 'or Westinghouse Electric l Corporation Drawing No. 360F05EQ01 (W-21PF-1) - Sheet No.1, Rev. 8-Sheet No' 2, Rev. 8; and Sheet No. 3, Rev. - 8. Maximum" gross weight of the package is 8,600 pounds-(b) Contents (1) Type and fonn of material Uranium hexafluoride f 6 I f (2) Maximum quantity of material per package and fissile class P i s.. In accordance with D0T Specification 21PF-1 lWj h
- j. 6.
i Prior to each shipment, the overpack gaskets must be inspected. These gaskets g must be replaced if inspection shows any defects or every twelve (12) months, g; whichever occurs first. i n d!' B 15; 7. > I The following conditions apply to the Model No. GE-21PF-1 packaging: b I h (i) For packagings which are not seal welded, the joints between the inner and [! outer shells (ends) and the side (end) panel moldings must be silicone g sealed. The inner and outer overpack gaskets must cover side (end) panel ll p g, molding joints (unless seal welded). Except for joints covered by a glued '!t I down gasket, visually inspect all silicone sealed joints and maintain in Il good repair prior to each shipment or outside storage (loaded or empty).
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i: gl! l]s I u I l 8 Il lN g
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" '~ " CONolTIONS (continued) li 't lE. Page 2 - Certificate No. 4909 - Revision No. 5 - Docket No. 71-4909 -b II 14 , >h -F !)
I ! ja (ii) Prior to June 30, 1985, all body seams and joints for the inner and outer 'h l3. shells (ends) and the side (end) panel moldings must be continuous welds. mi Welding must be by a fusion process in accordance with the American Welding lbl lN I Society Code or American Society of Mechanical Engineers' Code.
}1
- 8. The packages authorized by this certificate are hereby approved for use under k the general license provisions of 10 CFR 971.12. f!
h l
- 9. Expiration date: November 30, 1987. '
REFERENCES F
.rs H h t- 2 i General Electric Company application dated Novembe(r'19/1982.
,, \, v L.;;
Supplements dated: September (23,1983; and February 15 and'Itay 22, 1984. t, i g, e3 Westinghouse Electric Corp ration supplements dated: July 20 and November 21, 1983.
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FOR THE U.S. NUCLEAR'* REGULATORY COMMISSION Qi f6 s ,. .
~~
' h? h ' ': .
Charles E;4'acDonald,. Chief i Q w' Transportation'Certificaticn Branch f
'y
,n LDivision [off Fuel Cycle and ;p V: ';; ,
- : Material: Safety, fMSS ,8
;, E s
ii s Date: a.' b s;. N
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l m = = = = = = = = = = =WKKm = = E= =Wi s = = =** = = = = = = *~***' L******N5*- --- - N"."u[""" CERTIFICATE OF COMPLlANCE tl '0 C'" " FOR RADIOACTIVE MATERIALS PACKAGES f 1 a CERTIFICATE NUMBERD REVIS60N NUMBER c PACKAGE IDENilFICAYtON NUMisER d PAGE NUMBER , TOTAL NUVt4ER PAGES I 4949 5 USA /4949/AF 1 2
; I PREAUBLE l l] a Tnis certif.cate is issued to certity that the packaging and contents descnbed en item $ below, meets the appbcable safety standards set forth en Tette 10 Code t 'jj; of Federal Pegulations, Part 71. "Packagreg of Radioactive Ma.oriars for Transport and Transportation of Radioactive Matenal Under Certain Conditions " 'IN.lB. b This certefecate does not relieve tne consignor from compliance n'tn any requirement of the regulations of tne U S Department of Transportation or otner ' appacaose reguiatory agenc,es. inciuding ine go nment of any country intougr> or into wnich ine package *>ii de transported lI; ,
o I( onEPA E B r Amress b T LE AND IDE TF T F E OR A IC A T40N United Nuclear Corporation United Nuclear Corporation application dated Recovery Operations October 4,1979, as supplemented. Wood River Junction, RI 02894 i
, m, ,, _ 71-4949 4 CONDaTIONS '~
I;s This certificate is cond:tenal upon fuitelbrig tne requirernents of 10 CFR Part 7 t, as apphcable, and the conditions specified be60w (a) Packaging ' (1) Model No.: UNC-1484 (2) Description Containment vessel consists of a 5-1/4" ID x 36-1/2" long and 3/8" thick steel pipe with welded botton plate and bolted top flange closure. Containment vessel is centered and supported within a 65 gallon minimum 16-gage steel drum with DOT Specification 17H closure by plywood spacers, benelex, tubular steel spokes, and insulation materf al. 2 (3) Drawings Container is constructed in accordance with United Nuclear Corporation i Drawing No. D-5005-8017, Rev.1. (b) Contents
;!li (1) Type and form of material li N
Uranium oxide and compounds which will withstand a temperature of 750 4 without pressure generating decomposition. Density nay not exceed 5.3 g U/cc. The theoretical-density-moderator relationship for "U gf compounds" shown in Figure 309 XXIV, dated February 6,1970, Docket No. IL 70-36, or in Figure 1.D.17 of the UK Handbook may not be exceeded. F
- Uranium nay be enriched to any degree in the U-235 isotope. The #
maximum H/X atomic ratio considering all sources of hydrogenous material interspersed with the fissile material shall not exceed 0.5. fW l i I
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4 CONDITIONS (continued) l Page 2 - Certificate No. 4949 - Revision No. 5 - DocRet No. 71-4949 .W
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- 5. (b) Contents %
(2) Maxinum quantity of material per package W i Total contents not to exceed 65 pounds with the U-235 content not to exceed 25.4 kg. f II and III b) (c) Fissile Class b< (1) lijnimum transport index to 2.0 fg be shown on label for lass II 3; , n' (2) flaximum number of. packages per 50 $ shipment for Class III N
- 6. The package authoriied' by this certificate is hereby approved for use under the general license provisions of 10 CFR 671.12.
o .. 4; 7. Expiration date: November 30, 1989. l REFERENCES h United Nuclear Corporation application dated' October 4,1979.
~
g Supplement dated: Novemt er 14,.1979. . x , 9 'EJ
'FOR!THELU.S. NUCt. EAR REGUI.ATORY C0ftf11SSION I
Charles E. MacDonal'd, Chief Transportation Certification Branch 4 , i-i Divition of Fuel Cycle and Itaterial Safety, TUSS : Date: NOV 0 2 B64 ,
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L - 1 N - - --- 5a 1 'ociR7' CERTIFICATE OF COMPLIANCE 1 FOR RADIOACTIVE MATERIALS PACKAGES 1 a CERTIFICAYE NUMBER D REvis.ON NUMBER c PACMAGE IDENTIFICATION NUMBER o PAGE NUMBER e TOTAL NUMBEH PAGES 4986 17 USA /4986/AF 1 4
. PREAMBLE t
a This Certificate is issued to ceftery that the packaging and cMle"ts descnbed en item $ belo., meets the appucable safety standards se!' yin m Title 10. Code ' l [l of Federal Regulations. Part 71. Packaging of Radioactem Marenais for Transport and Transportation of Radsoactive Material Under Certa.n Conditions ~
!E b in,s certa.cre does not reneve tne cons.gnor trom compnance ..tn any reawrement of the regulations of ine o s oepartmeni of Transportanon or oiner l1 appe.cacie reguiatory agencies. .nciud.ng ine government or any country inrougn or inio .n en tne pac = age om be iransoorted l
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a "^* ' ' S'" ^~^""."' RTE L'"40,?"cff,84L"M"o'r"0MA "cario~ General Electric Company General Electric Company application dated P.O. Box 780 March 1,1982, as supplemented. Wilmington, NC 28401 4 71-4986 M
$ ' M c coCurtNuusca:
} a coNoirioNs in.s certa.cate .3 cond,tionar upon tuam.no ine reau. rem.nts of to crn part 7t. As appucane. and the cond,tions speca.ed be.o.
5 (a) Packaging i (1) Model Nos.: RA-2 and RA-3 (2) Description A fuel assembly and fuel rod shipping' container. Packagings are right rectangular boxes consisting of an outer container of wooden construction ! and a metal inner container separated by cushioning material. The netal inner container is 11-1/2 inches by 18 inches by 179 inches long and is positioned within a Model No. RA-3 wooden outer container , approximately 30 inches by 31 inches by 207 inches long. Cushioning % is provided between the inner and' outer containers by phenolic impregnated j i honeycomb and ethafoam, or equivalent. Closure is accomplished by ,; l bolts, latches, or equivalent. A pressure relief (breather) valve is p provided on the inner container, and is set for 0.5 psi differential. t The total weight of the packaging and contents is 2,800 pounds. (3) Drawings
]>
fk (i) The packagings are constructed in accordance with the following i GE Drawing Nos.: 769E229 Revision 1, Model RA-3 Wooden Outer Container lk 769E231, Revision 3, Model RA-3 Inner Container i E 769E232, Revision 3, Model RA-2 Inner Container { The RA-3 inner container may be constructed in accordance with i} Exxon Nuclear Company, Inc. Drawing No. XN-NF-304,416 Rev. 2; or ik Westinghouse Electric Corporation Drawing No.1685E66, Rev.1. !> E g; (4) Product Container q' Five-inch, Schedule 40, stainless steel, pipe fitted with screw type L or flange closure. Container shall be vented in the event it contains E f materials which decompose at less than 1475 F. r s;
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il CONolTIONS (continued) '> f ll , Page 2 - Certificate No. 4986 - Revision No.17 - Docket No. 71-4986 j It b!
;h
- 5. lh 11 (b) Contents l
}1 i
} g (1) Type and form of material $
!I g (i) U0, fuel assemblics with a maximum average U-235 enrichment of Bl; 3.3% by weight. Assembly rods are clad with a minimun 0.029-inch I
$ thickness of Zircaloy and a maxinum fuel pellet outside diameter l8 of 0.416 inch. Each assembly, made up of a maximum 8 x 8 square f(
}l g array of fuel rods, must have a maximum fuel length of 174 inches with a maximum fuel cross-sectional area of 25 square inches.
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'4 n qg6 A (ii) UO fuel assemblies'withia maximu.m average U-235 enrichment of I:
2.f% by weight? Assembly rods a'reiclad with a mininum 0.032-inch thickness of Zircaloy and a maxinun; fuel pellet outside diametsr[bf0.490 inch. Each assembly,<made up of a maximum 7 x 7 square array of fuel rods, must have a maximum fuel length of fl[: 1 g 4 174 in'ches with a maximum cross-sectional area of 25 square f i inches.1 "/ I [r
~
i ,y Q>s / W, (iii) 00s fuel rods [with a maximum U-235;enrichmentief 5.0% by weight.
. Rods are cladlwith; Zircaldy, Incaloy, Inconel,.or stainless steel !: h
.such that the" ratio of' clad to !fuel cross sectional area be at )
least 0.26,'and 'a maximum fuel pellet outside diameter of 0.508 !f linch. Each iodimust have a maximum length of 174 inches. The R ly i t clad rods'must'be 'bdndledl(contained) in the product container
;4 '
j', ig; i. lg' described n .1 %in 5(a)(4)j 9 il C !!l; 5 ,
)5 l6; (iv) UOf fuel rods witia , maximum U-235,enrichnent-of 6.5% by weight. ,D lI Ro8s'are clad with Zircaloy. . Incaloy, Inconel 'or stainless steel
- I
;6;l such-that the ratio of fclad to fuel cross sectional area be at :
leaste0.26, and a naximum fuel pellet outside diameter of 0.508 !!
}g!
l inch.
- Each rod rust have a maximum length of 174 inches. The :n
!gl clad rods must be bundled (contained) in the product container lt
': described in 5(a)(4).
;N I
(v) U0 fuel assemblies kith a mAxinum average'U-235 enrichment of I 3.$% by weight for assembly rods clad with a nominal 0.030-inch !j thickness of Zircaloy and a nominal fuel pellet outside diameter ll of 0.3565 inch. Each assembly to be made up of a 9 x 9 square in array of fuel rods with a maximum fuel length of 174 inches and a lI j maximum fuel cross-sectional area of 25 square inches. j l (vi) U0 fuel assemblies with a maximum average U-235 enrichment of 3.h% by weight for assembly rods clad with a nominal 0.030 inch 'I thickness of Zircaloy and nominal fuel pellet diameter of 0.3565 !N i nch . Each assembly to be made up of a 9 x 9 square array of ;I fuel ' rods with a maximum fuel length of 174 inches and a maximum 4 8 l cross-sectional area of 25 square inches. Each assembly will 'j
': contain a minimum of six rods containing U0,-Gd,,03 pellets with a !y minimum of two percent Gd3 0 by weight located in the interior of the assembly (non-perimet$r position). lgI s' !I si l 13 ll gl ;
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g L # % I3 ' I E \ '\ I f* ' conomons tcontinuess a I; Page 3 - Certificate No. 4986 - Revision No.17 - Docket No. 71-4986 4 1 l l [ 5. (b) Contents (continued) I! l I (2) Maximum quantity of material per package t I, i II (i) For the contents described in 5(b)(1)(i), 5(b)(1)(ii), 5(b)(1)(v);
$ and 5(b)(1)(vi):
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!g Two (2) fuel assenblies.*
I' . [ (ii) For the contents described in 5(b)(1)(iii) and 5(b)(1)(iv): I: Two (2) fuel bund.lesl* pg- !$ "C- s?f . 5 (A bundle >is., defined as an arrangement;of rods which are either j I> - contained within a product container or s' trapped together.)
. N
*Two short fuel assemblies or bundles may be subAtituted for a full 1
length fuel assembly or bundle provided _the. individual assemblies (or bundles) are shipped end-to-end and the' total length .does not exceed 174 inches. , I (c) Fissile Class
- 1 2 '
i
- 6. Each fuel asse5bly must be unsheathed or_ must be enclosed in an unsealed, polyethylene sheath which may not extend beyond the ends of the ~ fuel assembly.
The ends of the sheath may not be folded or taped in any nanner that would ! prevent the flow ~of liquids into. or out of[the sheathed fuelf assembly. - Polyethylene shipping shims may;be inserted-between rods within the fuel assemblies up- to a nuximum of 0.20. 9 H 2 O equivalent per cubic centimeter averaged over the assembly. 1 7. In lieu of the product container specified in 5(a)(4); except for UO, fuel rods i with U-235 enrichnent greater than 3.2%:and for~ rods described in 5(b)(1)(v), i the clad rods cust be bundled (bound with steel strappings at two or more ' ! locations) with a maximum cross sectional area of 20.0 square inches. The total breaking strength of the strapping nust be 30 times the weight of the bound ;
; rods.
- 8. The maximum spacing between adjacent rods within the bundle must be 0.012 inch. M The spacing must be maintained by the product container wall, metal strappings t
,g or peripheral metallic dunnage with a melting point greater than 1475 F within k
!I the bundle. )y I ;h
- 9. The package authorized.by this certificate is hereby authorized for use under f
gl the general license provisions of 10 CFR 971.12. )lp ' I
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- 10. Expiration date: March 31, 1987. 't l
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^ COND1TloNS (continued) 5 ~
E. g'- Page 4 - Certificate No. 4986 ~- Revision No.17 - Docket No 71-4986
< g REFERENCES General Electric Company application dated liarch 1,1982. .
( . Supplement dated: tiarch 15, 1982. , Exxon Nuclear Company supplements dated: June 24, 1981; January 11 and February 9,1982; and October 3 and November 19, 1984. Westinghouse Electric Company supplements dated: February 4,1983; and March 27, i 1984. c, :- )
;- =i. '
~
FOR THE U.S. NUCLEAR REGULATORY COMf11SSION j [ [ Charles E. MacDonald, Chief Transportation Certification Branch
- Division of' Fuel Cycle and
- Material Safety, TNSS Date: DEC1 g suu ^
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y-_.-----------------------------_-f-----------y-y--, ._ NRC FORM s1s l i +aai U.S. NUCLEAR REGULATORY COMMISSION !I lj C'" " CERTIFICATE OF COMPLIANCE ;l FOR RADIOACTIVE MATERIALS PACKAGES fl
- a CERTIFICATE NUMBE.R D REVISION NUMBER C PACKAGE IDENTIFICATpON NUMBER d PAGE NUMBER e tot AL NUMBER PAGES-5059 9 USA /5059/AF 1 2 j g,; 2 PRE AMBLE a This certificate as issued to certify that the packaging and Contents descnbod inltem 5 below. meets the appisc abte safety standards set forth in Title 10. Code of l
y Federal Regulations, Part 71. ~ Packaging of Radioact#ve Matenals for Tra 3rt and Transportat<>n of Radioactive Matenal Under Certa.n Condations
- i)
N b I This certitcate does not retieve the consignor from compliance with any swquerernent of the regulations of the U S Department of Transportation or other apphcable regulatory agencies, sncluding the government of any Country through or ento which the package w il be transported I: I! f a I t Ei 3 THtS CERTIF#CATE IS ISSUED ON THE BASsS OF A SAFETY ANALY$l$ REPORT OF THE PACKAGE DESIGN OR APPUCATiON e PREPARf0 BV #Name sad AJaeosst 1: D TITLE AND IOENTIFICATION OF REPORY OR APPLICATION g! Nuclear Fuel Services, Inc. Nuclear Fuel Services, Inc. application i P.O. Box 218 dated March 27, 1981. ! s{' I t Erwin, TN 37650 l' I! e oOCnEYNupeER l 71.gggg ; 4 CONOITIONS
,I:
This Certificate is Conditional upon fulfslling the recueroments of 10 CFR Part 11, as app?scable and the conditions specified below g!g a(a) Packaging 1 I' ll (1) Model No.: NFS Uranyl Nitrate Tank Trailer { I, II (2) Description i li 'I I f Bulk liquid insulated cargo tank trailer.. The 3,800 gallon tank trailer is lj of all welded construction iof Hype'304L2 stainless steel. )
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I (3) Drawing s k' L. ,4; I b i{l ' l 8< W O
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I. The tank trailer *~1s constructed in accordance with" DOT Specifications MC- 'I 1 310, MC-311, or#,C-312.. *
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.s f;(b) Contents '
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Type ands ._formTof s , ,-material;g((y 1 ,, 7 -- A ;))j; c ,f i' ) I , 3 Uranyl nitrate in dilute' acid solutionedThe maximum U:235 enrichment in il fgi the uranium r6ist nottexceed 20*e bypeight. The U-235' dontent of the solution 10 pams; perg liter.j { hnWcDC ll must not exceed d,
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) i, i
1 Page 2 - Certificate No. 5059 Revision No. 9 - Docket No. 71-5059 lb in I
- p 1
I ll 1 1 lg 1 5. (b) Contents (continued) ,N I 1 (1) Type and form of material (continued) (I
't 1
j The total uranium content must not exceed 357 grams per liter (1.5M_). The )ly 1 The HNOU0 (N0 )ha-6H c$nce$t 0 be ti$n will content must0.4M. normally not exceed 50 weight percent.The freezing g t 1 3 l i any of the solutions must be less than 72*F !pg 1 j (2) Maximum quantity of material per package Not more than 45,600 pounds net weight of uranyl nitrate acid solution. 1 III lj (c) Fissile Class j!; j 4 i Maximum number of packages per shipment One (1) !I
.I h 6. The solution must be at a temperature of 68 F or above at the time of packaging. )
I 1ll 7. Prior to delivery to a carrier for transport, for U-235 enrichments greater than ll 4% by weight the shipper must ensure that at no point along the proposed shipping i route that the ambient temperature will be less than 32 F. In the event freezing ,I weather is encountered the administrative procedures and controls as specified l
]4 in Nuclear Fuel Services, Inc. application dated March 27, 1981, must be complied i
f jll with for all U-235 enrichments. j i ljl 1, J 8. The package must be tested and maintained in accordance with Section 8.0 of the 1 Application, llI I. l
,1 j; 9. The package authorized by this certificate is hereby approved for use under the f general license provisions of 10 CFR $71.12. ! j, u
- l,g 1; 10. Expiration date: September 30, 1986. .
ll h h I REFERENCE'
\>I l
'n hl L
ll T Nuclear Fuel Services, Inc. application dated March 27, 1981. j
]l !I l.
J FOR THE U.S. NUCLEAR REGULATORY COMMISSION lb 1
- I li l5 f M[4-Charles E. MacDonal , Chief ly Transportation Certification Branch q Tl l
l Division of Fuel Cycle and !p j Material Safety, retSS ; I h 3 l-Date: SEP 0 G 1983 t I b 17 -t 16 L <_________ - _ m_ m m m_w_m_m.___ _ m____.:___________I i
_ _ WA 6 =:=Wom-N-;mmmmmpwwwwum=== . N" w cen r ' CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES : I t a CERTIFICATE NUMBER b MtVs5lON NUMBE R C PACIL AGE IOLNilfICAY60N NUMBER o PAGE NUMBER e tot AL NUMHER PALI 5086 5 USA /5086/B( )F 1 2
-f P8tE AMBLE a
This cerfificate is issued to certify that the packagmg and contents described m item 5 betow, meets the apphcable safety standards set forth in f atie tO. Code of Federal Regulations Pad 71. ' Pacmaging of Radioactive Materials for Transport and Transportat.on of Radioactive Material Under Certa.n Conditions-D This certiScala does not reheve the Consignor frcm comphance with any reqwrement of the fegulations of the U $ Department of Iransportatson or other applicable regulatory agencies encludeng the government of any Country through or tnto whech the package will be transported
- 7'Et,"0'ct^.i'ae"!'Jf%"' "' ' ' "'" ^'^"'l'rTs'fio',"o',0S*c^ft,OT'Jte"cMfMCc '
T 4 ,0N United Nuclear Corporation United Nuclear Corporation application dated 67 Sandy Desert Rd. April 22, 1980, as supplemented. Uncasville, CT 0638 c OOCKET NUMBfa 71-5086 M a CO* Ost#ONS l This certificate es conatonal upon fulfithng the requireerwets of 10 CFR Part 71, as apphcabhr. and the conditions specif,ed beso* I 5 (a) Packaging k (1) Model No.: UNC-2600 I, (2) Description The inner container is an ll-gauge steel box 96" long with a 25 square ! inch maximum cross section. The inner container is-supported in a 22-1/2" 10 by 102" long 14-gauge steel drum by an insertable cage forned by nine, 21-1/2" diameter by 3/8" thick steel plates spaced approximately 12" apart, with a channel formed through the center of
' the plates by angle iron. The-outer container closure is made with a
' 14-gauge or heavier drum lid with 12-gauge bolt locking ring with drop forged lugs, one of which is threaded, having a 5/8" diameter bolt. , j (3) Drawing The packaging is constructed in accordance with United Nuclear Corporation ' Drawing No. D-20354-6, Sheet 7. Revision No. 4. l (b) Contents i i (1) Type and fom of material i n 1 (i) Dry uranium-zirconium, uranium-aluminum alloys and compounds with y 3 1 densities not exceeding 1 kg U-235 per liter in the form of .h
! plates or sheets. Uranium may be enriched to any degree in the b U-235 isotope.
j: (ii) Dry uranium oxide pellets encapsulated in stainless steel, aluminum or zircaloy rods. Uranium may be enriched to a maximum 5.0 w/o I in the U-235 isotope. i; {f b j (iii) Moderated uranium-zirconium conpounds with densities not exceeding i8 y 1 kg U-235 per liter in the fom of plates and sheets. Uranium )lg g: may be enriched to any degree in the U-235 isotope. > i lN k W
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i CONDITloNS (continued) 1 : 1 Page 2 - Certificate No. 5086 - Revision No. 5 - Docket No. 71-5086 1 1 5. (b) (2) Maximum quantity of material per package 1 1 Ten kilograms U-235 and the net weight of the contents not to extced , j 308 pounds. II and III f 1 (c) Fissile Class h
'h!
1 (1) For the contents described in 5(b)(1)(i) k> 1 and 5(b)(1)(ii)- ,k 1
!!inimum transport index to be shown 10.0 j
) on label for Class II R{g Maximum number-of.. packages per shipment N P 10 [
i 1 for Class III U ' .
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' ,,7 j\ (2) For the co'ntents described in 5(b)(1)(fif): + t 4 s .
Maximum > number..of; packages per shipment, n .5 - g: a s for Class III
~
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t L 1 .%t , ._ i lk: 1 6. The cross-secti n'of the inne'r 'containe~r 'shalk' be limited to a'm I square inches f( the contents specified,i.n 5(b)(1)(1) and 5(b)(1)(iii) where [ the ratio of the.. weight-of U-235,to the weightcof. U-235 plus zirconium exceeds g h 0.074 or the ratio of the weight.bf U-235. toTthe' weight of U-235 plus aluminum y f a exceeds 0.22. UJ ';i, , v,[ [ { { { { j ;4
'; <~ '
> E E-1 1a -s ;;);,, ..
E 1 7. Optional banding (~of wooden'Iblocksito;: outside'ofmcontainer isJnot authorized ,R 1 .. ems.y r yt;1_ by 'this'certificatef ts herhby approfed' for use under the f
^
- 8. The package autho'I)ed rz g lf 1
general license provisions of 10 CFR.97.1,12. V!,
s/
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1 9. Expiration date: May 31 (/1990. eh + y 3 ' 2 REFERENCES , b h f , ,, n t,p
,f United Nuclear Corporation application dated April 22, 1980. !I f
lk l 1, Supplements dated: May 8,1980; and November 6,1984. h 1; f FOR THE U.S. NUCLEAR REGULATORY COMMISSION ) lI 1 3 1 M8Mee Charles E. MacDonald, Chief ll#l 11 Transportation Certification Branch i Division of Fuel Cycle and j' fj Material Safety, NMSS !y I
!I Date: May 221985 ju l
f i I f 19 N 1 I 1lL_m_________________________________________________
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. .<ai Fonas s1s ll I! 'o cra " CERTIFICATE OF COMPLIANCE UA NUCLEAR REGULATORY COMMISSloN .h FOR RADIOACTIVE MATERIALS PACKAGES If o sitvisioN NUugER c PACKAGE IDENr F1CArlON NUMBEa (f i e5088cearisicare muweta I, a eastusta 3 USA /5088/AF o PAG 6 NUMBea 1
. rOTAt NUMBEa PAGES 4 y l . T he c.,tetsc.f. .. e ueo to certify in.f tne p.ckaging .no contente d cnb.d snitem S below. meets tn. .pphcebi. ..f.ty stand ed. ct eorm in viti.10. 1 Cod.of q
5.o.r.i n.gui tions. pan n. pack.g.no or nao.o.cnv. u.teness for Tr n. con .no tran.pon non oe n.o o.ci.v. u.t.n.: uno.r cert..n condition. - Ei )] ) li o in,. c. tit.c.t. oo.. not rw.. m. con.4,nor trom comen nc. ..in any r.auer.m.nt of in regui.non. or m. u s o.p.nment of re.n.ponation or omer ,5 ;
.ppi,c w. ,.gui. tory g.nc .. .nciuo.no in. govemment or any country mrougn or into .nicn in. pack.g. .iis o. tran port o '
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)
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't i h a vs.s 18 . par eco ce,arwicare sv , .e is isset,o.o.u rwe, eases or a surry Asatvses atroar or rss eacmacs I'oesion l' o rirte suo aurwicario~ o, acecar on amication
.15
' gi Rockwell International Rockwell International application dated 'n gj 8900 DeSoto Avenue September 8,1980, as supplemented. 'y lj Canoga Park, CA 91304 j l Ij 4 li 'I l l' Ig 71-5088 e ooc cr~uu.ca j If
' I, . co~omous
!b :
I vn.. c.n.f c.i. .. cono.t.on., upon vf.inng m. c.ou.r.m.nts ce io cra p n n. .. .ppnc oi.. .no en. cono tion. .p.c t..o n.io. il l in . I( * (a) Packaging !I l; :n i I i I; (1) Model Nos.: D34710-1 and D34710-2 I R (2) Description l I'i g l Containment vessel is,a. 12.25041nch10 Schedule 20steelpipe,40to j , hl 41 inches long for the'Hodel No. D34710-1 and 50 to 51 inches long for 5 l the Model No. 034710-2, with 5/16-inch ' thick welded end plate, and f g-bolted flange [cl'osure with leak tight gasket.', Inner container is !B ! centered and2 supported in a 22.5-inch diamet'er' steel drum with minimum I I thickness 0f 18-gage. are fille,d;with.vemiculite. Void spaces between inrier,and outer container (/ j~ I; Gross weight of the package is 420 lbs g 1; n, Noi 034710-2. for the f, kodel D34710-1 d, 3 andL>480[lbsifor the Model N .I [: g: (3) Drawings 4 s$ [}Jww;['( \,p;;i q t5 O
;g
,j
;a i' The Model No.. b347'10-1; packaging fis,) ,
constructed in2accorda I I, followiO@ National LeaCConpanyiDrawing.Nos.: - Il; q q, yjg 't M S.7 y h 034710 S$ht l'off2,sIsble ft I #' Ij D34710 Sheet 2 od2 MIssUO2'e # d *k ,6? '4 y E! h6 j i
,k I,
h .Yh o h
,7,O 6 >,>
t a p g: I;l T V. *i A/% Jr E P lR
$ 4 I; )!g )
I I; j , i; j l I g 4 g i i b t b !I Er
)
20
)
I n s,.rmrw. w--1.r,.r ,v -ws, rvs-1-.rws,.,rr.cr n.s r,.r,. r, r r w w ww-,. , -,, ,,,,,, w . ,, , i.!
p======-------_-_-- --- .. ..,,__________,,,,,,,,,,, U.S. NUCLEAR REGULAT@DY C@MMISSION I NRC FORE 8 818A CONDmONS (contmued y GE
- Page 2 - Certificate No. 5088 - Revision No. 3 - Docket No. 71-5088 j
' y li I 'l t I 1 (3) Drawings (continued) )g C34711, Issue 3 h C34712 Issue 4
)ig d !g h C34713, Issue 1 h !I The Model No. 034710-2 packaging is constructed in accordance with the l 1
f following National Lead Company Drawing Nos.. j i 1l. 034710 Sheet 1 of 2. Issue 6
!p 1 !,
l,j C34799, Issue 1 'g 1 C34712, Issue 4 C34713 Issue 1 lI
;l I
D35846T-1, Issue 2, as amended by letter dated February 8,1978. l[! il h (b) Contents lil i For the Model No. D34710-1 packaging: lIl
.g 1;
li (1) Type and form of material lI
,1 li 1
j Uranium metal or alloy plate type unirradiated fuel elements with a , lj minimum active fuel length of 23-in ches. Uranium may be enriched to !, li 93.5 w/o in the U-235 isotope. . ly I (2) Maximum quantity of material per package lI If li - % ' j 2.025 kilograms U-235. i f)! . s .
' For the Model No. D34710-2 packaging: lg
] !g 11
' lg I d (1) Type and form of ma'terial '
- s. ',
l h l MTR-type fuel' elements. t 1,
'n (2) Maximum quantity of nateriali(:l' {g y 1
1l -
!p I l;- 860 grams U-235.
- :l il '
ll li
!g I
1 1 l 1-. r tli
~i., !g 1 i 1 'p I,
l I
!I l, s I
I i I 1, I , !g l Il !i 1 ll 'I 14 f g 21 li !N I,
- ! _m _ _ _ _ ___ mm_ _m_mm _m___ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _la
_ _ _ _y____ ,_.___,, _ l$_____- gj l eenc Fonu sisA m Conomons econtinuem U.S. NUCLEAR REGULATORY COMMISSION I'
!n
( Page 3 - Certificate No. 5088 - Revision No. 3 - Docket No. 71-5088 l 1l 1 llI li 'I I; (c) Fissile Class !g 1 I ') l For the Model No. D34710-1 packaging: i
!bn
!! Fissile Class Il r
l Minimum transport index Max kilograms U-235 Transport j, ll i to be shown on label per container Index 'g lj 'l I 2.025 1.2 !N l;i 1.700 1.0 lI3 l: 1.400 0.9 1 q! 1.100 0.8 ll 0.800 0.7 )'y i Ij 0.500 0.5 l ll I (i For the Model No. D34710-2 packaging: j g Fissile Class II l l
'lg Minimum transport index Max grams U-235 Transport Il to be shown on label per container Index ll
;I I:
;h
!j! 860 0.7 l g! 500 0.5 I il l
!g i 6. For the Model No. D34710-1 packaging:
I lg I The H/X atomic ratio considering all hydrogenous. material between fuel elements (It l! within the inner container and the weight of the uranium shall not exceed: j g! Max kilograms V-235 > l per container e Maximum H/X t l j Il h 1 th 1 2.025 2.2- % l 1.700 2.6- I 1.400 3.2 !N lli 1.100 4.1 E ' ll 0.800 5.6
! I! 0.500 '8.9 jlg I, 0.350 10.4 I; 0.290 13.0 t
l {1t, ' Il [ k, i r l l f i li ' li 't N i i I ;; 1 i l =- 1 22 m I, h l l: b I
i p.m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m m_m_m m_ 2. __ i g n_ _ _ _ _ _ _ NRC FORM 018A U.S. NUCLEAR REGULATORY COMMISSION
&as CONDIT10NS tcontmuod) 1: 'I
) Page 4 - Certificate No. 5088 - Revision No. 3 - Docket No. 71-5088 )
ll il I, .I
! I
- 6. ;I 1l 1
1 (Continued) i l 1 For the Model No. D34710-2 packaging: } 1
'I j, The H/X atonic ratio considering all hydrogenous material between fuel elements !)
1! within the inner container and the weight of the uranium shall not exceed: il 1! ll Max grams U-235 I l! per container Maximum H/X ,j fll 'I q! 860 6.1 !g i 800 6.5 lI
$ 700 7.5 :I 1, 600 8.7 ,I li 500 10.4 l j
i y 400 13.0 t i r! 7. The packages authorized by this certificate is hereby approved for use under the 1 3 1l! general license provision of 10 CFR 971.12. l ll
;l
- 8. Expiration date: October 31, 1985. 'I 3l ,I J
1; e I
) REFERENCES lf
'I 1
1! I
;I J Rockwell International application dated September 8,1980. ;I 1
k University of Missouri letter (Gooden to Ladd) dated July 30, 1968; Idaho Nuclear h Corporation letter (Fox to Tingey) dated April 30, 1968; and Oak Ridge National i g j Laboratory, Neutron, Physics Annual Progress Report period ending September 1,1958, t
- I i
f pp 34-36. l ;I 1! l FOR,THE'U.S. NUCLEAR REGULATORY COMMISSION lI
;g f)!
5;< ,
,1
~'- .I
]!
ll J;
&J Char.les E.'MacDonald, Chief jI I Transportation Certification Branch ,1 l Division of Fuel Cycle and b
[ Haterial Safety, NMSS j l I [ Date: SEP 0 61983 !j l' lI 1 L A \ 1 Dl 1 : l l I I 1 lI J l l I 23 !
, .I
, ,- -y = = ,- - ,- = . - - - =r- = = - r T i = = <= a- - - - w= = = = =_= = = =~ = = =y = = = = = = = = = =# l ;
m.m._===KAAMXKiMENEWK*5MA=~*GNE N M N MW 6 "*** - 1 l 4l is PeAC e FOR'2 Sta U.S. NUCLEAR REGULATORY COMMISSION ' I ll i
'0 C'* CERTIFICATE OF COMPLIANCE '
FOR RADIOACTIVE MATERIALS PACKAGES I a CERTIF6CATE NUMt:(R tp Rt VI$40N NUMHER c PACK AGE IDt N tlFtCAf TON NUMt4ER d PAGE NUMt3ER e TOT AL NUMHER PAGE S 5149 5 USA /5149/B( )F 1 2
, PRE AMBL E l
]l a This certificate is issued to certify that the packagmg and contents described m item S below meets the applicable safety standards set fortn in Titse 10. Code ll of Federal Regulaf.ons. Pert T?, Packaging of Rad oactive Mater.ais tot Transport and Transportation of Ra$oactive Material Under Certain CondSons " ,
b 15 Thes certitecate does not reheve the consegnor from compliance witn any reqwrement of the regulations of the U S. Department of Transportateon or other i f acpl Cable regulatory agencies, includmg the government of any country through or ento whech the package will be transported h 4 ll i
'4 1
s 1 3 TMtS CERTIFICATE : a PREPARED 9V ArawIS (SSUED and A#esss ON TM( GAS!$ OF A SAFE TV ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPt.iCATION b TITLE AND IDENTIFICATION OF PEPORT OH APPUCATION Babcock & Wilcox Company Babcock & Wilcox Company application P.O. Box 785 dated September 20, 1979. Lynchburg, VA 24505 .
)
I c 00CKff NUMBEh t -
+
71-5149 4 CONOtflONS i This certificate is cond$onal upon fulfilling the requirements of 10 C7 R Part T t, as apphcab6e, and the cand4ons specified below - s (a) Packaging b' y-le [4, (1) Model No.: 814A l' it' h j In (2) Description j q > Steel container as described'in BaScock &=Wilcox Company's application p
- g. dated September 20, 1979.
(b) Contents 1
. -3 1 8
^ ,D (1) Type and fom of naterial
~
)n Unirradiated fuel cluster !b
't I (2) Maximun quantity of material per- package .
l> l! I One fuel cluster containing U-235 with inserted poison fixture as : l specified in Babcock & Wilcox Company's application dated September 20, lp I 1979. - lp l f,4l (c) Fissile Class III l1. I ' ;R Maximum number of packages per shipment or ' l q[! per railroad car Five (5) i dj
, -N: 6. !p b I; The package authorized by this certificate is hereby approved for use under the if l I. general license provisions of 10 CFR $71.12, it p
(, 7. Expiration date: October 31, 1989. I:. , I' w lp l s
'I i I !b b
l t I; 24 li l !N I.i I l
-w. ~ .w.............. . . .
. . . . . . . . . . . . _ _ . . .I I ,
s i s --,;,.s, ; .. 7
' '"" coNoITIONS (continued) lI:
it: I Page 2 - Certificate No. 5149 - Revision No. 5 - Docket No. 71-5149 ll
! l4, is REFERENCE
'It l
Babcock & Wilcox application dated September 20, 1979. f FOR THE V.S. NUCLEAR REGULATORY COMMISSION
^' ~!]
- ;') b Chief
!~Charles E. MacDonald, ~
1' Transportation Certification Branch
- c/
- Division of Fuel Cycle and ,
s Itaterial Safety, NMSS . OCT 2 51984' g Date: W-y}8 1: k: s K: k.
>> .bj l.
V.. i:
; I :-
li k1 . J'q
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i ; f
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L l
't
' 11 5
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'I
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, liI l g! -w l
l
1 l _ _ _ - zwrrrnws .vzwra:w'zwwessmunmnena._a xunarxraw ax:wrm ma wm www e NRC FOM3 61s 4 u, j
' 0 C" " CERTIFICATE OF COMPLIANCE U S. NUCLEAR NEGULATOHY COMMISSION FOR RADIOACTIVE MATERIALS PACKAGES i
, . usrincart w em a n new-oN Nuum s * *u aut not N i a it a r.oN * *m s a va it N~vme e t o ' at novm a v40e s 5341 6 I USA /5341/8( )F 1 2
, mt ava t . N.
Ts., o.,ta.we . .s ..ea rm,m m,r m, vaa 2.ng ano com cis ae.o.ce.nn nem neu;. ,, eee, ene.co-n.v,i, sonw n .eo nn e m r.o., to < ~ ie mear . seue uns .wt n e.mm n, sm a , m.~... 0, t aw , ono r,.nwwwon umuoaa.am.. oa w c e.um c,e ia .m !"] t. o N . in.s c ,1+we aves noi .coe,e me cons,no, r,em cm.,c.....c,
- min, r%.,e,, em unne ,egma- m .mne u t, cw o-o,e r.. .ncun u, eme, N i appi. cave eer.icm a.;enoes .m i.,+y the gowm-t o' aa, c c~ .m9 t~ moon or emo
- men tre rat b A y WW t.e l,a% Fred
$4 f sq N 1 W i 3
, 1-s
. -u .
a r_+.cart . .wu_o
. c%...r** easw a su e, aNu vs.3 _ un . r.o,_un. raunot
, _ .n om - ,on-u . n eu..o~
~
((q Babcock
& Wilcox Company Babcock & Wilcox application dated June 23, l P. O. Box 765 1967, as supplemented, h Lynchburg, VA 24505 $@ l p N 14
( ri 71-534) i'l;
,4 < m r r om
+4 < cc wr.ons
_ _ _ _ _ - _ _ _ _ _ h,, g< Th.s ce,tif.ca e is co,$d t.or,4: upon fut,m, J t% req;..,cments cf 1] CF R Part It as arDM atCr and the w 1 t.ont spet Aeq woe
$4 54 s l'1 la (a) Packaging d
p li 4 l y (1) Model No.: NFP-55 l (2) Description 1 l
"I Packaging as described and constructed in accordance with 00T Specifi- P!
' cation 6M except: (i) the containment vessel is linited to a 5-inch Schedule 40 steel pipe with threaded cap closure and welded bottom
{g plate; (ii) the outside drun rust have at least 55-gallon capacity; 14 and, (iii) the sides and ends of the containment vessel cust have at bI It l4 least 7 inches of insulation with the radial clearance between the d
'o insulation and the outer shell not exceeding 5/8 inch. fi M -
(b) Contents (1) Type and fom of naterial bs Uranyl nitrate or uranium oxides, of any enrichment in the U-235 8 isotope, provided the H/U-235 ratio does not exceed 20, considering J'l E all sources of noderation within the inner container. f.4 f.1 (2) Maxinum quantity of naterial per package pl b [4 b 8 Not more than 3.6 kilograns U-235 in a volume not to exceed 3.6 liters. > s
@ N, 1
,s i l4
+f g Ts h
i d l . Jf bl 9
.bl I4 s - Y f b; p . <mrzsarmwarswrmeaamrammasaammvarsamsarasanarzwrarumwesta
79DWatfET2f1Ti%Wl'iWi_%%"2fWTWMA@T2?1*A*1CE*iWMfi'1%Wi*2f y CONotTIONS tcontrnued) 71-5341 Page 2 - Certificate No. 5341 - Revision No. 6 - Docket No.
.b L4 9 pl g 5. (c) Fissile Class II and III f
(1) llinimun number transport index 1.3 f.4 to ba shown on label for Class II , b. "I (2) 'Maximun number of packages per 40 packages shipment for Class III @ $ 6. Pipe cap closure on the Schedule 40 pipe shall be sealed with teflon tape. r$ h[4 7. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR $71.12. b b] $j N b, 8. Expiration date: October 31, 1989. ,l, p. (4 k bt REFERENCES h h Babcock & Wilcox Cor.pany application dated June 23, 1967. pj !q Supplerents dated: January 5,1970; and May 14, 1980. h 11 FOR THE V.S. NUCLEAR REGULATORY C'litilSSION e 6C f . 9 Charles E. MacDona , Chief p$ Transportation Certification Branch d Division of fuel Cycle and liaterial Safety, f24SS f oa te: ect 2 s es4 3 y,l
- 4
$.4 F4 N4 - 14 : W h u
!s !4IJu!LTJamT&TaLT&T&Ta&TmsmTavaKKdamvarmr&TsamTaaJ.samTmLT.TRKA
g-----------------------------------_---_ %- __ _-y-_y--_-,,, I II I f*RC FOR4' sis i U.S. NUCLEAR REufLATORY COMMIS$loN iI ll l I! 'e0 u. C'" " CERTIFICATE OF COMPLIANCE .t FOR RADIOACTIVE MATERIALS PACKAGES !I ) b REVISION NUMBER c PACRAut IDENTIF eCA f epN NUMSt R q FAGE NLM8ER e 1.)t AL NUMBER PAGEs' h 1 a CERTIFICATE 5362 NUMBER 2 USA /5362/B( ) 1 f 2 g I 2 PREAMBLE 5, a This cetteticate is issued to certSty that thepackaging andcontents desenbod intterft $ below meets the appucable safety standards set h> rte an T4ie
'l f 0. Code g g Federal Regula00ns. Part 71. *Packagmg of Radioactive Materials for Transport and Transportation of Radioactive Material Undet Certs,n Conditions " ;g ]
I b j
' I, This certitutate does not reheve tne consignor from comphance with any requsrement of the regulahons of the U S Department of Transportawn or omee apphcab+e regulatory agencies. including the government of any country through or into which the package =AA be transported [I ,
i I! R l Il m' Ig' 9 3 TH45 CERT SV a PREPARED 6FCATE ISAmes3A g%eme og ISSUED ON YME BASI 3 07 A SAFETY ANALv$l$ NEPORT OF TP*E PACKAGE DEliGN OR APPLICATION ! t
}
b TlTLE AND tOENTiFICAfeON OF REP' ORT OR APPLICATHON U.S. Department of Agriculture U.S. Department of Agriculture application Radiological Safety Staff
- g. dated October 17, 1980.
g! Beltsville, MD 20705 ' d ) I i
;I; '
a OOC =ETNuueER 71-5362
' I; 0 CONDITIONS I; inis c.rtinces is cond.nonai uson fu n.n s tne requirements of to crR Part 7 t. as appucabie, and tne conditione specif.ed beow a
i (I: (a) Packaging l I i I' I I. (1) Model No.: Natick Irradiator ' fI (2) Description I The package is a cylindrical'.lsteel-encased, lead filled weldment 29-
~
g 3/4" OD by 58" high-enclosed }n ~a' double-walled inpact and fire shield r I I (overpack) 57" by 45" by 90" high mounted 'on a pallet 57" by 45". The i stepped cavity;is 9.56" ID by 8-1/4"s 12"#101by 27-1/2" and 20" ID by l 11-58". The source holder (drawer assembly)lis 9.48" OD by 46.625" l
, with 9-1/2" shielding on bottom and 12-1/8" on' top. A lead shielded g
cask insert assembly 20" OD by 9.52" ID by 12.12" is installed at the l' top of theTcask"and sthe entire assembly >is held 1.n place with a 1" I thick steel lid secured with . twelve.,l" bolts. A. cask drain line is s ! 1: sealed hith a pipe plug! A 39"l0D laininated plywood plug fills the f i space between the top (of the cask and the overpack. Plywood will be g positioned around the circumference of.the irradiator for support. ; tgli The cas,kj weighs. 16,000l1bs..{jiy 1
' ' j '+ 4 ~)is a
0.' { I r ' '* l v* 'J i t , !, w s
' + 4, j P ( g /,? '
i I ' y . n. y,; j I p
' tl s r 1
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;I g
i f5, "i gC. ip' ,
+
lt
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V' 4 j)h f, t 3 - Y.
!B i
k .> I b l > D l 5 i I I. t )> l l , h i I > l ^ I, 2E b ! f 1 L. , ,_ _ _ _ _ _ . _ _ _ _ _ _ g _ _ _ _ _ _ _ _ _ _ _ _ g _ _ _, _ _ _ _ _ _ _ _ _ 1
,_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,__ ,__ _y_ _ _y _ _ , , , _ _ ,
unc ronni essa u.s. NUCLEAR REGULATORY COMMISSION lI i g{tw coNomons (conemumn Il 'l ' Page 2 - Certificate No. 5362 - Revision No. 2 - Docket No. 71-5362 ( ll. ]'I ll 'I g F I; (3) Drawings y l E
' I; The packaging is constructed in accordance with Lockheed Nuclear 1 Products Drawing Nos. 442-2093, Rev. 0; 442-2094, Rev. 0; 442-2096, it' l(l!
( Rev. 0; 4422096 Rev. 0; 442-3002, Rev. 0; and U.S. Army Natick Research and Developrnent Laboratories Drawing No. FE-81-16, Rev. O.
,3 f
1 I d' (b) Contents 's d 't (1) Type and fonn of material g Cesium 137 sources meeting requirertents for special forn radioactive l}
)' g: material. y I; I i; (2) Maximun quantity of material per package i i
j s li 250,000 ci I l ;t l 6. Construction of additional packagings is not authorized, fi I' d' 7. The package authorized by this certificate is hereby approved for use under the y I general license provisions of 10 CFR 671.12, i 4, g f 3. Expi-ation date: October 31, 1986. j II l I+ y 4 REFERENCE , I > 1 U.S. Department of Agriculture application dated October 17, 1980. I p i
- j. FOR THE U.S. NUCLEAR REGULATORY COMMISSION j '
i , l YYs E Charles E. MacDonald, Chief Y k Transportation Certification Branch I j j Division of Fuel Cycle and 8 Material Safety, NHSS l 4 SEP 0 6 G87 1 3 Date: - ~. - jl i ) 1 1 1 'p
~J n p
i I .11 p l I 3 y 1 11 . li
-{
J
)p I 29 I )
l-ww-=www-wwm"m-wwww--===w-waw ===---ww ----ww.==- w.. wd 1
1 g - - - -- - - - - - - - - au mam-seamwassmanenenenenswarmnenw=ner== = wmmmewnmw,==_ ! l k' teAC FOAu s1s U.S. NUCLEAR REGULATORY COMMISSION Im CERTIFICATE OF COMPLIANCE I lI . C'" " FOR RADIOACTIVE MATERIALS PACKAGES
- i . cearwicats wveta e arvmon wueen c PAcaaue ietNralCAtlON NUMBER d PAGE NOVMH e rOr AL NUMtM R PAGES I
5450 21 USA /5450/AF 1 5 < l l/e.ieAusta j iR: a inis certiv. care inved to cert.ty inat ine pacmaging a,xt contents aescere o .a item 5 delow. meets tae appe caoie safety standards set torin n ritie to. coa. , ll of Federai Regulat ons Part 71 "Pacmaging of 84adroactive M.ite, a!s for Transport and Transportation of nad oacts.e Maienal Unoe, Certain Conditions ~ ! jI a inis ce,i,6 care ooe noi rei,es, vn. cons.gno, ero n compuance ..trt an, , eau rement of ine reguistens ce ine u s oepartment or t,anspo tat.on o, orn < { I appi c oie ,easato<v a pacies. inciuo,n, ine go.ernmeni o, an, count on,ougn o, ,nio .n.cn enepaaage .aineiraaipoeteo ! l 1 8 l
- - 4; 4
) 3 vs s crar,eicArt a m eaatois en issuto N -oN.m rueaa,.eu sas.s c,s A sa ErY ANAOSf 3 aEPORr OF rHE F4CaAGE DE$tCaN CiR APPUCAriON l o rittE 4No ceNriticAroN oe acPoar on areucatioN
$y Westinghouse Electric Corporation
] Westinghouse Electric Corporation application
- P.O. Box 355 dated December 17, 1980, as supplemented.
d) Pittsburgh, PA 15230
- h $
'd M i . occu, Nuvu. - 71-5450 It i d a caoim s h ta e ce<tacam in cono;tiona, upon fuitas,ng tne ,cou.<ements of to CFR Part 71. as applicable ano tne cond.tros spec #f.ed beenw j g, , (a) Packaging v i
i p N I iA (1) Model Nos.: p' ) 9 hj i i RCC, RCC-1, RCC-2e RCC-3, and RCC-4. I'l
>1
- (2) Description ba
! B Steel fuel element cradle assembly consisting of a strongback and 13 l adjustable fuel element clamping assembly, shock nounted to a 14-gauge N l i steel outer container by shear mounts. Neutron absorber plates are 4 required for the contents as specified. Gross weight for the RCC and h RCC-2 is 6,300 lbs., RCC-1 and RCC-3 is 7,200 lbs., and RCC-4 is 8,400 g l lbs. t i I
- (3) Drawings I i
I
- The packaging is constructed in accordance with Westinghouse Electric h
- Corporation Drawing Nos.
- 1596E24,1596E25, and 1553E31 fnr the RCC p
- g and RCC-2; 1596E24,1596E25, and 1553E30 for the RCC-1 ar.d RCC-3; and b l 1596E22, 1596E23, and 1548E55 for the PCC-4. N D
1 l (4) Fuel rod container reinforced 13-gauge steel box constructed in accordance h i with Westinghouse Electric Corporation Drawing No. CS650055, Pev. 7. 'l } W I 4 7 c p 1 i f
-p
} i
,b
.P
. I'
,p 20 lb lI
- - w- - - - - - w w w - - -__i.y - - - - - w - -_- - s , , - w - - - , - - - - - ,,,mm . . .m,, ,g, p l
l !- _.-.,_,- _ .,.-. ,--, .~., -,- -._ _.- --- -.--.-.,-. ,,...,-. ,,.,..- _ - - ---,,-.. - - _ ,--~ _ .--,- - .. - ,..- - - ,
p K @ % W d P N i* M T 2"A*1_WT l'ii 35ftdin'_E*1W1WiMM iMNITETil?l"1MTANT CONolTDONS (contonuedl t
' age 2 - Certifica te No. 5450 - Revision No. 21 - Docket No. 71-5450 el D
- 5. (b) Contents $p (1) Type and fom of material (1) Uranium dioxide as Zircaloy or stainless steel clad unirradiated fuel elenents. Two neutron absorber plates consisting of 0.19" f
pt
.g thick, full length stainless steel containing 1.3% nininum boron pl.
f4
<4 or 0.19" thick 0FHC copper are required tetween fuel elements of P the following specifications: I F d
~
d 14x14 15x15 ~14x14 15x15 17x17 16x16 14x14 'p Zr Zr Zr f Type Zr Clad Zr Clad SST Clad SST. Clad Ciad Clad Clad M Pellet diareter 0.344- 0.308-(non),in 0.367 0.367 0.384 0.384 0.322 0.322 0.3805 Rod dianeter 0.400- 0.360-(non),in 0.422 0.422 0.422 0.422 0.374 0.374 0.44 Maximum fuel length, in 144 144 120 120 168 144 144 Maximun rods / element 180 204 180 204 264 235 176 y. pj
, Maxinun cross section, p 1
(non), in sq 7.8 8.4 7.8 8.4 8.4 7.8 7.98 tiaxinu'i U-235/ elenent, kg 17.7 18.3 18.5 18.7 16.95 16.6 19.0 Pl D D (144"L) 19.8 (168"L) Maxinum U-235 g, enrichnent, w/o 4.0 3.65 4.0 3.65 3.65 4.0 3.85 h (ii) Uraniun dioxide as Zircaloy clad unirradiated fuel eierents contained within the flodel No. RCC-4 packaging. Two neutron f 14 24 absorber plates consisting of 0.19" thick carbon steel are required
'4 between fuel elenents of the following specifications:
17 x 17
,1 Type ZR Clad f p Pellet diameter, in 0.308 - 0.322 %
[4 0.360 - 0.374 N Rod diameter, in , tiaxinun fuel length, in 168 . Maximum rods /elenent 264 Faximum cross section, (non), in sq 8.4 flaxinun U-235/elenent, kg 19.3 ; Maxinun U-235 enrichnent, w/o 3.55 14
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T&TXXsamTJersammTarmrmTarmTamT.TmT&TarmTsv N
~
_N NT t i ', :D ll' CONDtTloNS (continuedl > I l I. Page 3 - Certificate No. 5450 - Revision No. 21 - Docket No. 71-5450 l l I B i t!
;q (iii) Uraniun dioxide as Zircaloy clad unirradiated fuel elements. Two O lI' neutron absorber plates consisting of carbon steel. 0.g35 inches %
'I I in thickness, with 4 n11s of Gd,03 (0.02 gn - Gd 730 /cn ) affixed 1 to each side of the plate are req 0 ired between f0eT elenents of i
the following specifications: 14x14 15x15 14x14 15x15 17x17 16x16 : Zr Zr SST SST Zr Zr Type, Clad Clad Clad Clad Clad Clad p Pellet diameter (non),in 0.344-0.367 0.367 '.0.384 0.384, 0.322 0.308-0.322 f ! r Rod dianeter 0.400 . ' ' ' /0.360- l (non),in 0.422 9 0'422
. 0.422 0.422 ' 0.374 0.374 .
I'.axinun fuel j) length, in 144 144 120 120 168 i ' 144 Maxinun rods / . i element 180 204 180 204 264 235 g flaxinun cross . n section, ;k (non), in sq 7.8 8.4 7.8 . - 8.4 ' 8.4 7.8 ' % itaximum U-235/ i A j element, kg 22.1 21.5' 23.1 ' 22.0 ' 19.9 20.7T (144"L) f
- , ~23.3 - '
i
} ~~ (168"L) i 1 Maxinun U-235 i i
enrichnent, w/o 5.0 4.3 5.0 4.3. 4.3 5.0
. {,
[q. (iv) Uranium dioxide as Zircaloy or stainless steel clad unirradiated .g je fuel rods of the following specifications:. 'n l3 8 I jl Type, SST Clad Zr Clad Zr Clad Zr Clad Zr Clad i
)Pelletdiameter(non),
;g in 0.384 0.344- 0.308- 0.322 0.3805 f[
i n j 't 0.367 0.322 's i l8 Rod diameter (non), in )n
> I. O.422 0.400- 0.360- 0.374 0.44 i 0.422 0.374 b i [Fuellength(nax),
g: !j q in 120 144 168 144 144 p I; ;3 I U-235enrichnent(max), .
.I I w/o l
lI ' [ Note 1) Note 2) 4.0 5.0 4.0 5.0 3.65 4.3 4.0 3.85
;l g 5.0 ---
g: Note 3) --- --- 3.55 --- --- lg y ll f I lu l' l' 't
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_ _ _ _ r_ _ _ - _ _ . _ _ _ _ _ _ - _ _ _ _ _ - ._ _ _ _ .- - -- CONDITloNS (contenus 4) Page 4 - Certificate No. 5450 - Revision No. 21 - Docket flo. 71-5450 Notes: (1) Two neutron absorber plates consisting of 0.19-inch thick, full length stainless steel containing 1.3% (minimun) Boron or 0.19-inch thick 0FHC copper are required I between the rod boxes. (2) Two neutron absorber plates consisting of carbon steel, 0.035 inch in thickness, glq- with 4 nils of Gd-203 (mininun 0.02 gm Gd-203/sq. cm) affixed to each side of % (3) Two the plate are required between the rod boxes. neutron absorber plates consisting of 0.19-inch thick carbon steel are l1 f required between the rod boxes. f a fa (v) Uranium dioxide as a Zircaloy' clad unirradiated fuel element. Two neutron absorber plates consisting of 0.19" thick, full p p e L4 length stainless steel containing 1.3% mininun boron or 0.19" thick 0FHC copper are required in the shipping container. The fuel assembly must have the following specifications: 4 17 x 17 Zr Clad Element Pellet dianeter (nom), in 0.322 . Rod dianeter (non), in 0.374 : tiaximun fuel length, in 144 itaximun rods /elenent 264 I
, i I tiaximum cross section, 8.4 ) (non), in sq .>) "I . tiaximun U-235/ element, kgs 17.6 )
tiaxinun U-235 enrichment, w/o 3.80 (2) 'taxinum quantity of naterial per package ., (i) For tt.e contents described in 5(b)(1)(1), 5(b)(1)(ii), and ./ 5(b)(1)(iii): )b j Two fuel elements. j
'M v4 fe, (ii) For the contents described in 5(h)(1)(iv): 'I l
01 Two inner containers containing not nore than 80 kilograns U-235. )[
$ (iii) For the contents described in 5(b)(1)(v)- ,
e) 4 One fuel elenent plus one dunny fuel assembly. p
- n j 5. (c) Fissile Class II and III f4 (1) Minimum transport index to be shown on label for Class II 1.2 f;p
- p
>d (2) Maxinun number of packages per shipment for Class 111 60 g 1
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k ll L oNDl Tion S (continued) d Page 5 - Certificate No. 5450 - Revision No. 21 - Docket No. 71-5450 b
- 6. Fuel rods nust be closely packed in the fuel rod container on no noia than an L equivalent metal-to-metal square lattice. Partially loaded fuel rod containers .
1 nust be fitted with a minimum of three, equally spaced blocks, of which the ' noncombustible portion of the blocks and the nethod by which they are secured . nust assure that the rods are maintained on no more than an equivalent metal-to-metal square lattice within the fuel rod container.
-) i
- 7. Each fuel assembly nust be unsheathed or must be enclosed in an unsealed, polyethylene sheath which will not extend beyond the ends of the fuel assembly.
The ends of the sheath must not be folded or taped in any manner that would -
- prevent the flow of liquids into or out of. s the sheathed fuel assembly.
Alternatively, the fuel assembly may be ' enclosed in an elongated plastic bag or sheath along its full length. At the botton end of.the fuel assembly, the bag will be cut off or folded back to assure that the entire cross section of the D$ f I lower end of the assembly is unobstructed. When folding is used, the portion of
, the sheath that is foldeo back will be cinched with tape 'near its end to hold it pt in place, and the length will be such that when the assembly is loaded in the d packaging, the folded sheath will be clanped in place in at least two grid q ,
locations. The top end of the bag may be gathered. together and taped closed. ' However, the top end then will t be slit on all/four sides. The slits will run perpendicular to the axis of the assembly and.will extend therinner distance between the top' nozzle pads and spring clamps'(approximately 6.0% of the length of each side). The slits will be nade in a plane near that fomed by the top of l the pads and clamps. ,
~
- 8. The package authorized by' this cert'ificate is hereby approved for use under the >l general license provisions of 10 CFR 971.12. >
i
- 9. Expiration date: ' Ja nua ry' 31 1986.
R l 1 REFERENCES , ' 7 Westinghouse Electric Corporation application dated December 17, 1980.
~
{( Supplements dated: January 21 and S'eptember 4,1981; March 8,1982; June 14 and October 4,1983; and April 8,1985. h R Department of Energy supplement dated: March 1,1984. >- h I; FOR THE U.S. NUCLEAR REGULATORY COMillSSION 1 y
)
Charles E. MacDonald, Chief lk h 1 Transportation Certification Branch h Division of Fuel Cycle and Material Safety, NitSS JlEl Date: 0W hl r 34 i i I
.........................................__..4
r=====_=======_^=s====_--==_==_m 6 Fi'A _-_______y]l I I F."S/ """ CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES l' k 'o csR " b REv>5 ION NUMBER C PACKAGE iDENT8FICAf SON NUMBER d P AGE NUMBE R . TOT AL NUMBER PAGE3
. I a CERTIFecATE NUMBER USA /5461/B( ) 1 3 y
( 2 PRE AMBLE 5461 1
')
a This certa.cate is issu.d io cen<ty mat me pacmaging and contents o.scrio.o initem s b.io.. me.ts tn. appocabi sat.ty siancares set tortn in Titi. io coo.oe pl 1 r.oerai neguisi.ons. Part 71. "Packagmg of Radioactiv. Materials for Transport and Transportation of Radio.ctiv. Mat. rial Uno., Certain Conditions
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1 ' .J e in,, c.,ta, cat, ao., not , .. m cons,gno,,,om compnanc. .,m any ,.go,,.m.nt o, m. ,.goiat,ons o, ine u s o.panm.ni ce Transponation or om., ,p i appocaei. r.guistory ag nc.es .nciuoing m. governm.ni or any country mrouan or into on.cn m. packso. .in d iranspon.o n 1 9
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,, , 'SS",,'J l" ', 5'S *"^"8'S,", 'rT,',Ro'M,CJe^ar',8%M "oM^&" car,cu 1 Oak Ridge National Laboratory Safety Analysis Report for Packaging (SARP) of l6 l j P.O. Box X the Oak Ridge National Laboratory TRU Curium ,b Shipping Container, Report No. ORNL-5147/RI, ll Oak Ridge, TN 37830 jl} August 7, 1981 Revision. j 1'
in 1 e oocREr NuusEa 71-5461 lI l .i 1 a coNoir,o,Nsin,s c.,1, , car, is cono,tona, upon cui,ai,ng in.nts o, io cr n Part ri, as appucaei.. ano ine cono.tions spec.v,.o b.io.
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y y s. i jl (a) Packaging g I l; ' (1) Model No: ORNL TRU Curium Shipping Container )1 i j 1 (2)
Description:
f f Packaging for solid radioactive'naterials. The container is a right l(p circular cylinder,29 inches in diameter and 30-7/8 inches high with a
)r 304L stainless , steel outer shell which'is)3/8-inch thick for the tg i; botton and sides' arid 1/4-inch thick for the' top. The shell for inner ![
j cavity is 8-1/4 inches in diameter x 19-1/4 inches deep, is fabricated from 1/4-inch thick 304L stainless steel platef and is recessed 1-3/8
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l l! inches from the top. The inner cavity for the radioactive materials is 6 inches in diameter x 8 inches high and fabricated from 1/4-inch j thick 304L stainlessisteel.iseven,-eights-inch thick lead fills the lg 1l 1: space between the 'sideslandz bottom of: the cavityrshell and the inner : cavity.%.The annulus;between ,th'e OUt'er shell and'jnner shell is filled lt il t {l is, closed with a concrete-with limonite concretei The~ inner cavity'ch thicE304L stainless steel and-lea'd' plug'which is~ enclossd sin' 1/4-in II fli 1 t Pl ate. "A 1/16-inch thick fleoprene gasket; serves 9s a seal between the top flange 20f the; plug arid ,the! cask. bodyt ' Eight,1/2 "-13 UNC-2 nuts fp lg on studs' hold the? plug <-flangeito^the: cask body &) A 3/8-inch diameter !g 1 1l 304L stainless steel bail'istused to lift theQlug. A 1/4-inch thick i 1: 304L stainless steel plate,, which c' overs t>.e: top 13UNC-2 nuts on i s tuds. The 'cOk,is equipped with four,1/2-inch thick lif ting and I j j tie-down ears'with two, 1-inch diameter holes per ear. The cask is ( 1 mounted on a ski'd. ;The gross, weight!of the cask and skid is 2,800 g i pounds. si X Y t
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p__=======a-------==---------------==mamm-m_ .m---a g ----_-.,g_-, _ 8sRC FORM 81sA ns san U.S. NUCLEAR NEGULATORY COMMISSION CONDITloNS (contmuod) f li Page 2 - Certificate No. 5461 - Revision No.1 - Docket No. 71-5461 j l i
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- 5. (a) (3) Drawing f{!
g l The packaging for the TRU Curium Shipping Container is constructed in accordance with Oak Ridge National Laboratory Drawing No. 11-12175-CP-078-E-3 (Report No. ORNL-5147/RI, August 7, 1981 Revision). j
- n Il {h li (b) Contents )
I ;>n f (1) Type and form of material l i: g! (i) I Transuranics, and fermium in theincluding form of metal, any isotopes oxide, chloride,of or curium, other salt berkelium I; l
,I contained in capsules that meet the requirements of special form ;I I, radioactive material. ;I 3
f (ii) Transuranics, including any isotopes of plutonium in the form of n' metal, oxide, chloride, or other salt doubly encapsulated in il Il I, capsules that each meet the requirements of special form radioactive j't ma terial . ll li
- l' (2) Maximum quantity of material per package j
- f. The maximum internal heat not to exceed 150 watts;
{4, ilI (i) For the material described in 5(b)(1)(1) a total of 10 g or any ll li combination of Am-242, Cm-243, Cm-245;;Cm-247, or Cf-249. I: x - ll
's f, (ii) For thi material described in 5(b)(1)(if a total of 3 g of Cf-251.
lEl, Ig I, (iii) For the material described in 5(b)(2)(ii) the total of any combination 'y I of.Pu-239 and Pu-241 shall be limited to 10 g. !p I: 6.
\ t : ". 'I Special form radioactive material capsules mayjbe held within D0T Specification ll l! 2R containers. ,. .
2 j h 7. The package authorized by this certiffiate is hereby~appr0Yed for use under 1: general provisions of 10 CFR $71.12. ' i .;
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- 8. Expiration date: June 30, 1986.
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y-------------------------------------,- -,,,,,,,,,,,,,, U.S. NUCLEAR REGULATO2Y CCCMIS$10N I j g *" NRC FORM 818A CONDmONS (conteued lj i, t l' Page 3 - Certificate No. 5461 - Revision No. 1 - Docket No. 71-5461 j!b I I; ,1 l l ll i :1 REFERENCE ll1 'l j, Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory TRU Curium Shipping Container, August 7,1981 Revision to Report No. ORNL-5147/RI. :g i I n 1 l FOR THE U.S. NUCLEAR REGULATORY COMMISSION 4 i 4l 'l lj n Charles E. MacDonald, Chief ig Jj Transportation Certification Branch lg 1 l, Division of Fuel Cycle and 'I Material Safety, NilSS li fl t Date: CD 0 6 M
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e--==--------==_--------_--------wNs------.ii-----_ E i I )3 lj! wac i+ui ronu sts CERTIFICATE OF COMPLIANCE U.S. NUCLEAR REGULATORY COMMISSION h li 'o crR " .i FOR RADIOACTIVE MATERIALS PACKAGES lN 1 e CERTIFICATE NUMBER b REVISION NUMBER c PACKAGE IDENTif tCAT*0N NUMBER d PAGE NUMBER h 5463 2 k 2 PREAMBLE USA /5463/AF 1 e TOT 3 AL NUM l; a This certificate is issued to certify that the packaging and contents described snitem 5 below. meets the apphcable safety standards set forth m Titie to Code of
'l lI Federal Regudations, Part 71, "Packagmg of Rad oactive Materials for Transport and Transportation of Radioactive Matenal Under Certain Conditions
- ll g '
i D That certificate does not reheve the consignor from comphance with any requirement of the regulatx>ns of the U S Department of Transportation or other li apphcable regulatory agencies, mcludeng the government of any Country through or ento which the package will be transported
;il I!
b li ;b I 3 ThaS CERTIFICATE IS ISSUED ON THE BAS 15 QF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLiCAYlON l a PREPARED BY gheme and A possi I b TITLE AND IDENTIFICAT10N OF REPORY OR APPLICATION '. I
}} Union Carbide Corporation Safety Analysis Report for Packaging (0ak Ridge
! Nuclear Division Y-12 Piant Foamglas Shipping Package for Enriched g! Oak Ridge Y-12 Plant, P.O. Box Y g Uranium) Report No. Y-DD-156, September 1974. +
(l Oak Ridge, TN 37830 ' N, i; e oOCnET NUMsEa 71-5463 ' 1 lI a CONOiTIONSThis certificate is conditionai upon fuit.Iling the requirements of 10 CFR Part 71, as apphcable. and the conditions speciteed below if I II '- (a) Packaging fl. (1) Model No.: FD l (2) Description :g Ll ly E! :I Packaging for uranium enriched ;in The containment ja 8-vessel consists of DOTiSpec 2A 'or,.the s2N metal U-235innerisotope.container 6-3/16 .R f s inches diameter by 8-3/4 inches high." 4The containment vessel is ji gj centered and supported within a 16-gage ' outer steel drum with a 14-l' gage head, 00T) Spec 6J or equivalent, by solid foamed boron silicate j! d' I glass. The ' outer steel drum is 22-1/2 inche'sidiameter by 22 inches !, high. The, outer steel drum closure must. be at?least a 12-gage bolted lg g ring with,' drop forged lugs, one of which is threaded, and having a [! 5/8-inch' steel bolt'and lock nut. The1 package gross weight is 145 pounds. h 'M' --^ ) N in i I
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3' It T wj, g1*& , - .,s', ;l The packaging;isias 2es'c,rlibed}andifabricated' in accordance with Union n : II!l Carbide Corporation," Nucle ~af DIYi5fon, Y-12 Plant Drawing No. E-T- l 55301. Ua ' e49 , sW j- ait b I , waM ,S m? ' {1 N l
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g; U.S. NUCLEAR REGULATORY COMMIS$lON I gt anc roau essa CONDITIONS (contmued) t*a3' g hl Page 2 - Certificate No. 5463 - Revision No. 2 - Docket No. 71-5463 :
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$ 5. (b) Contents .p t l
f i (1) Type and form of material (' El :t Uranium metal, alloys or dry compounds, of any enrichment in the U-235 I! [bh li isotope. k il (2) Maximum quantity of material per package not to exceed Type A quantity f radioactive material and: j j g 1 (i) Not more than 3.7 kg of U-235, or g
- 1) .
Not more than 19.0 kg of U-235 with the H/U ratio not more than g l (ii) 2, considering all sources of hydrogen within the inner containment 1 1 fl 3! vessel.
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i 1 I, II and III 1, (c) Fissile Class El l !g 1 (1) Class I For the contents described in 1, 5(b)(1) and limited in 5(b)(2)(i). lg . i l i For the contents described in f (2) Minimum transport index to be shown 5(b)(1) and limited in I 1 on label for 5(b)(2)(ii): !j 1,j !g 1 Class II J; 0.5 1 i lli j for the contents described in packages per lR (3) Maximum number of l j: 1! shipment - 5(b)(1) and limited in for Class.III ' ' 5(b)(2)(ii) I j 1, 1
- 2 200 -
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j; 6. The package authorized by this.' certificate .is' hereby approved for use under the lI jl the general license provisions of 10 CFR 971.12. , s 1 Expiration date: July 31,1986. ll x. :g J 7. 3; 't p
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Nnc Fonu sisA l;tecu y coNomonS (conanvedi U.S. NUCLEAR REGULATORY COMMISSION ] I: ll Page 3 - Certificate No. 5463 - Revision No. 2 - Docket No. 71-5463 l I:l I I! I; 1 REFERENCE I; g: l ;t Safety Analysis Report for Packaging (Oak Ridge Y-12 Plant Shipping Package for ;n ljl Enriched Uranium) Report No. Y-DD-156, September 1974.
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l Il! FOR THE U.S. NUCLEAR REGULATORY COMMISSION f li - df 4 / i b /I Charles E. MacDonald, Chief y Transportation Certification Branch l I: Division of Fuel Cycle and (ij; I ( Material Safety, NMSS I; yi lI: ,- tt I Date: N '[ I,l d 1l m 1,
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]I I; aan CERTIFICATE OF COMPLIANCE I FOR RADIOACTIVE MATERIALS PACKAGES il
. PAGE NUMBER . rof AL NUMBER PAGE3 fl to cra " e REVISION NUMBER c pac = AGE IDENT.FICATDON NUMBER i . cEnTiricaTE Nuusen USA /5468/Bf 1F 1 2 g 5468 2
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. r meaMsts .in. .ppi.e.oi. ....tv .i.nas,o ..i vorta in Titi. io, coo. or
. in c.ri.e. cat. inu.o to cert tv in.iin. p.c6.g.no ano contents o..crioso initern s e.io.. . 3 ll j, g r.o.r.i n.gui.non.. p.n n e.ck.a.no o, n.a.o.ciiv. u i ri.r. vor Tr.n port .no Tr.n. port.t.on os n.o.o.ciiv. u.i.n. uno., c.rt.in cono.v.on. -
il e in . c.n.e.c.i. oo not rei . in. con gnor from compi.ec tn any r.auer m.ni ce in. r.gu!.i.on. of in. u s o.p.nm.ni o eTren. con i on or ein., ;I'
;p Gl . .ppi.c.oi. ,.gui.iory g.nc .. incevo.no in. go rnm ni or .ny country inrouan or into .nien in. p.c6.g. . ii o. transport.o
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. o ., _ is issuto.o_~ rwe easis or a sarery anatvsis,ae,r,o,<a.r.o,
~o io i ic e e o rue,~ea,c.x4.Ge.ersic.
< ,c u..o.a .me,et.ic.a.t. ion.1 1 Nuclear Fuel Services, Inc., application dated il II Nuclear Fuel Services, Inc.
P.O. Box 218 May 1, 1967, as supplemented. j f: Erwin, TN 37650 ;y ql f I 71-5468 c oocarr uvusta i c co~omo~s il in,. c.na.c.i. is cono,t.on.i upon ruie.n no in. c.au.r m.nt oe io cra pari 75. .. ppi,c.o . .no in. cono.v.on. p.c.e..o o.io.
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If 5-(a) Packaging lI 3; f (1) Model No.: NFS-IX-A ) Iil (2) Description lIIg i I, Oak wood container 48" x 62".x 13-1/2" outside dimensions with an I E. internal cavity 36"-x 50" x 1-1/2"-lined with 0.020" thick cadmium. !B (3) Drawing ( '
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The NFS-IX-A' package is constructed in accor' dance with Nuclear Fuel
- p E, Services, Inc. , Drawing No. RMP-481, Rev. B. i p
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i; (b) Contents -L 4 tlg
,, . s g:
(1) Type and ' form of material jy j! E 1 Pu07 -UOf ceramic fuel pe!lets enclosed in aluminum, stainless steel, ltl 1 or Zircbnium tubes which havelbeer, welded closed'and tested to show 1; ll leaktightness. * )1 13 lI i, !I I 8l
't 8:
!n I: :
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" fi e -mm . -_ _- - -_ _- -_ _ _- _- - = - -- - = = m m m mu.uw.w w w w w = m m ..
a - - - _
,y_________________________________,,g ____,_______g __,,,j NAC FOA'2 610A U.S. NUCLEAR REGULATORY COMMISSION
, += coNomoNS (contmud li Page 2 - Certificate No. 5468 - Revision No. 2 - Docket No. 71-5468 Il li l ;l lli l
lI I;l (2) Maximum quantity of material per package )9 ll 't Total contents not to exceed 350 pounds and for the following w/o I l Pu02 /UO 2
, the slab thickness must not exceed:
h w/o Pu0,,* Slab Thickness, Inches
,1 ldl 100 0.60 i; 90 p
; 0.67 in 80 0.75 ;b i 70 0.86 60 50 0.94 5lI 1.05 40 1.12 j! g i 30 1.20 ;p i 20 1.26 ;b g
i 10 1.35 1 i 3 t i
*For UO containing 1% U-235 or more, the U-235 must be
,g il consid$redasPuindeterminingw/oPu0*
lii i 2 f (c) Fissile Class I
. 5. Interal cavity of the shipping container must' be filled with rubber or other '
g' packing material to maintain at least the specified slab thickness. Not more
,d e than 1/2-inch of elastic materials must be used for maintaining the slab thickness '
i I for fuel rods 1-inch diameter or less. E 7. The package authorized by this certificate is hereby approved for use under the I f - general license provisions of 10 CFR 971.12. 3
- 8. Expiration date: January 31, 1987.
%,l $
Bl REFERENCES I u Nuclear Fuel Services, Inc., application dated May 1, 1967. gi (' Supplement dated: liay 26,1967
'h!
l i FOR THE U.S. NUCLEAR REGULATORf COMMISSION i
; li
!it i
z* Char es E. MacDonald. Chief . I In! Transportation Certification Branch 1; I Division of Fuel Cycle and f Material Safety, fNSS Bf l, SEP M 1983 E; lg: Ja te: h Nl g I Il 1 il n h
- . . . ., . g. .. .
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y-----====--------m----------------------------_------y h llI kN 1 +RC aai FORM 61s CERTIFICATE OF COMPLIANCE U.S. NUCLEAR REGULATORY COMMISSloN 't 5 i { 'o cr R " FOR RADIOACTIVE MATERIALS PACKAGES d PAGE NUMBER . TOT AL NUMBER PAGES j
> Revision NuMetR c PACKAGE IDENM. CATION NUMBER 4 USA /5492/AF 1 3 h.. cERTwicATE 5492 muusER 1, 1 - E. _ E y a Tn.s certAcat. is issueo to certify that tne pack ages and contents describ.o initern 5 beio.. meets tne appocaba. safety stenaaros set fortn m T tte 10 Code of
{ Feoeral Regulations, Part 71. 'Packagmg of Radioactive Matenals for Transport and Transportat.on of Rao.opctive Mat. rial Unoer Certsen Conditions " ! [ lg f e inis cert.v. cat. oo.s not r.n... tn consignor from compnaa ..tn any reque.m.nt o# in reguiat.ons or in u s o.panment of transponanon or otner
;p b
2j appucadi. ,.gui.iory ag.nc .. .nciuomo in. governm.nt ce any country inrouan or into .nicn in. pack 9. .iii ne transport.o in h lh 1 , 3 THiS CERTIFtCATE 15 ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION ih 1 a PAEPARED SY them. and A,Afr.ssi b TITLE AND iCENTIFICATION OF REPORT OR APPLtCATION h Nuclear Fuel Services, Inc. Nuclear Fuel Services, Inc. application dated t P.O. Box 218 August 25, 1982, as supplemented. f) 1l Erwin, TN 37650 t i li l ! 71-5492 lI
'l c DOCKET NUMBER ll
'l 3 a cONomONS 3 in. certeicat. is cono,t.onai upon rune.no in. r.au.r.m.nts ce to CrR Pari ri, as appucaei.. ano in. cono.tions spec.ei.o d.io.
J $r (a) Packaging } fI (1) Model No.: RMG-181-I f r 1 (2) Description i t
-1; I The containment vessel,is a 5-inch hhedule 40 steel pipe with ASA I j,
j standard threaded pipe cap closure:at both ends with the bottom cap { j welded to the pipe and contains sealed'polyethlene bottles and/or g 1 sealed netal cans. The containment vessel ,is supported in a D0T 1 1 Specification'17H steel drum as shown in Drawing No. RMG-181-I. t -1l Vermiculite ds used to fill the entire void bstween the containment J 1 vessel and, outer container; 1/8" asbestos sheet is placed between both lI ends of the containment vessel and outer container; three inches of I 3 I kl vermiculite .% are located in bott.om and top of containment vessel. s . L 3 ' 7 1 (3) Drawing < 1 [ .Jli :
~
. m i 1
- r. _ .
The packagingtis constructed,i,n accordance with Nuclear Fuel Services, 'l 3 Inc. Drawing No; . RMG-181-I',ldated. November 22, 1982. A 3; h
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_- - - - _ _ - . . - .. _ . . - _ . _ _ - .. . .. ... k . w w w w w w w w ww w w ww.mm w mar = = = w w = = = = = = = = = = = = = = = = = = w wm = = = = = w w = =
p.- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - usgn=_- = = = = - _ _ m - = _Al- __ _- _ a Nec Fome sisA tcW:st U.S. NUCLEAR REGULATORY COMMISSION j CONDITIONS (cononued) I!
- l fl Page 2 - Certificate No. 5492 - Revision No. 4 - Docket No. 71-5492 j
Il : l l' !I
- 5. (b) Contents f
B f (1) Type and form of material j f I' (i) Uranium or any uranium compound or solution, any U-235 enrichment. fh I! (ii) U-235 as metal or oxide, or as compounds or alloys having a
- lj t
' maximum H/U-235 ratio of 3 considering all sources of hydrogen g l
i i within the inner container. I k (2) tiaximum quantity of material per package gi f 1: (i) For the contents described in 5(b)(1)(1): }
't ji Ten kilograms U-235 contained in a maximum of 100 pounds of ll
,. material.
j l. E (ii) For the contents described in 5(b)(1)(ii): Fourteen kilograms U-235 contained in a maxinum of 100 pounds of f
,4; [t 1
Nl material. 3 [
- 5. (c) Fissile Class II and III [.
.!l!l' g (1) Minimum transport index n c
to be shown on label i for Class II I F I f For the contents described in I [; 5(b)(1)(ii) and limited in g 5(b)(2)(ii): 1.3 6.l > 4 (2) !!aximum number of I~ packages per shipment l l j. N t for Class III ' t ' l$ For the contents described' l1
;g g!
in 5(b)(1)(1) and limited l Il ; in 5(b)(2)(1): Eighteen (18) , l: 6. A minimum 1-inch thick by 4-3/4-inch diameter wood block must be inserted at 1 i L-l:; each end of the containment vessel so that the contents are between the wood 4 blocks. The specified thickness of vermiculite required at each end of the ; ! g; containment vessel may be reduced by an amount equal to the thickness of each e l g: wood block.
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p-------------A---------A------......... ...,,,,,,,,,,,, NaC FOmu sisA U.S. NUCLEAR REGULATORY COMMIISION CONDmONS (continued l cl 40 1
'l l / age 3 - Certificate No. 5492 - Revision No. 4 - Docket No. 71-5492 {p Ill i
.I l
I lt ll h 7. The package authorized by this certificate is hereby approved for use under the j p general license provisions of 10 CFR 971.12. jh
!n 1
1 8. Expiration date: January 31, 1988. lt li !>
!p.
l 1 f i REFERENCES f
!h l3 Ji Nuclear Fuel Services, Inc application dated August 25, 1982. ;g lj I' lR I
I Supplement dated: December 10, 1982. :l l FOR THE U.S. NUCLEAR REGULATORY COMMISSION [ I !I Mb Charles E. MacDonald, Chief l Transportation Certification Branch {j fll Division of Fuel Cycle and :, f' Material Safety, WSS i lll fp Date: SEP 0 61983 y j ea J l l h l-
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lt-- - - EEE- - 4EEEEi E EEEsm m s s - s - s--1sswwwnennanimunesNTas - - - -i I"a5 " ^"" " ""'**' " E r '0 C'* " CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES ! f 1 a CERTwicATE NuveER a REVtSJON NUM8ER c PACKACsE lOENTWICATION NUMBER d PAGE NUMBER e TOTAL NUMBE R PAGES gi 5517 4 USA /5517/AF 1 2 o PRE 4Mett 1 a Tnes cert.ficate es essued to cert.fy inat the packageng and contents desenbed en item 5 betow. meets the applicable safet y standaras set fortn in Tette 10. Code l Of Federal Regulations. Part 71. " Packaging of Rad.oactive Materials for Transport and Transporta: an of Ra$oacteve Matenal Under Certain Conditions "
- b. Th s Certificate does not relieve tne Consagnor from Compliance with any requirement of the segulations of the U.S Department of Transportation or other I appi.caoie regutatory agenc.es. .nciud no tne government ce any country enrougn or into n cn ine pacmage ..is be transported I
i
' * ' " ' ' " ' ' ^' ' ^
.P PA E BY a a ?," ' " " ' ' ' "
b E 4DE CT N Ef0TO ICA TION Nuclear Fuel Services, Inc. Westinghouse Electric Corporation application P.O. Box 218 dated December 15s 1967, as supplemented. Erwin, TN 37650 71-5517 c DOCKET NUMBER b ( a CONDITIONS This certificate is condetsonal upon fulfdtang the requirements of to CFR Part 71, as applicable and the f,ond.tions specified beow 5 (a) Packaging: (1) Model No.: BB 250-1 k (2)
Description:
In . lg. pl A urantun dioxide powder shipping container, consisting of a steel cylinder held . in the center of an- outer. container (two steel drums f welded end-to-end) by fire-resistant foam. 4 Inner container is-ll.5-inch ids gauge steel cylinder, 63.5 inches long, with bolted and gasketed top flange closure and seal welded ! t botton plate. Inner container is centered and supported in a 22.5- ' inch ID by minimun 74-inch long,16-gauge steel drun by fire resistant i 4 phenolic foan of AEC Material and Equipment Specification SP-9. i (3) Drawing: The packaging is constructed in accordance with Westinghouse Electric l Corporation Drawing No. C882D962 Sub. 5. ; l i i' lH
!b lHl N
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\ unc usu s'in CONDtiloNS (continued)
I )l Page 2 - Certificate No. 5517 - Revision No. 4 - Docket No. 71-5517 1 f)D D p 5. (b) Contents: }l f (1) Type and fom of material- ,
,1 Il Bulk uranium oxide (U0 2 r U38 0 ) p wder with a maximum density of 2 g U/cc and enriched to a maxim 0m 4 w/o in the U-235 isotope. The maximum H/U atomic ratio, considering all sources of hydrogenous material within the inner container cust not exceed 1.13.
(2) Maximum quantity of material per package: Total contents not toledceedb5bpSnds.,with the U-235 content not to
'U exceed four (4 skiTogra'ms. / .
'v MJ.
I */'., l (c) Fissile Class%Q t)
, 6. Prior to esch ship 5I6t, the lid gasket must be inspected.-The gasket must be replaced '.f inspectionishows any defects or every twelve (12)' "
months, whichever occurs first. "> XM , Q' ." D Q-N fJ 73 .
- 7. The package aut'horized by thNicertifichts is he'r$b'y approved' _for use under the general licens rovisions of 0 CFR .571. 2. rl
- 8. 5 Expirationg'date- (p; February n af , #
413}lll28 63 A1990.,pg7 r arr r>A:9l Xt ' m i n N;(n.' dg_ REFERENCES , Q
% f 32 M u. syn f, (~ ~
Westinghouse Electric Corporation-a'pplicatied) dated D6cember 15,-j967.
/, u G ;u W ^' f w "ij 1 Supplement dated: Janua'ryj l8,, 1968.
+,.%. p Q
#/ FOR THE U.S.' NUCLEAR REGULATORY COMMISSION l k A" L ), h gg Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and ,
l Material Safety, fliSS , i l Date: Feb 6 1985 1 i
)
f i l l 47 i t i - ar- w w - - - - - - - w w w w - - w w w w w ww w w w w- ww w w w ww w w w w'arEWW- - - ~ - - - ~ - - - - - - - -
..m _ _ .
_ _==_-----=------.--_---
$" CERTIFICATE OF COMPLIANCE ***
If .S[ "" C'" FOR RADIOACTIVE MATERIALS PACKAGES I .. . cror,, care wu.en e aevism uuusra e eacnaos iomnricatio~ ~uusea e pace wuusea .1ovat uuusea paces i
, 5552 0 USA /5552/B( ) 1 2 o _.
I: a inis c.rtificat. i issued to c.nity inat in. pack.ging and contents d crib.d init.m 5 b.6ow. me.ts in. .pphcaba. satety etandards set fortn in Titi. to. Cod.of 3j r.o.re n.guiai.ons. Port 71.
- Pack.geng oe Radio ctiv. M t.rtals for transport .nd Tr.nsportation of Radio ctsv. Mat.nal Under Certain Conditions "
ll l' e inis c.nie.c.t. ao.s noi rc v. m. cons.gnor erom compnanc. im .ny r.auer.m.nt of m. e.gui.e.ons of in. u s o.p.nm.nt oe transpon.i.on or om r I .poucaiS. r. gut.iory .g.nce.s. .nciud no m. gov.rnm.nt ce .ny country in, oven or into .n.cn in. p.ca. .iii o. iransport.d I s \
'^$'*
k *U'.".'5,C,',"MS^'r',i'**",,', S Department of Energy
' * *^"" ^"'*."'rT,'Ro',"c',0'", '
^ft,8,#L #" o.S^,'il " r,m Safety Analysis Report for Packaging: The ORNL
[1 Oak Ridge Operations 1 Gas-Cylinder Fire and Impact Shield. Report l P.O. Box E No. ORNL/ENG/TM-5/R1: April 1983. i i Cak Ridge, TN 37830 I I, I I; e oocurNowata 71-5552 ! rnis c.rt.eie.t. conomon.i upon ve it. inns m. r.au r.m.nts ce to Cra part ri. .. .ppocani.. no m. cond.t ons so.c,v>.d o.io. i [4CONOlvlONS (a) Packaging [li ! i l (1) Model No.: Gas Cylinder Fire Impact Shield i i l I (2) Description I i l l \ A protective overpack fop, gas gyliqders. The overpack is a nominal fl 80-gallon,16-gage (tdalfdruin withia'yelded steel closure flange. i j Positive closurp Wthe foam-filled 'gaskged lid is provided by 8, i r 3/8-inch diametV steel bolts. A 16-gagevsteel liner with a bolted i l and gaskete(N10sure provides a cavity ll-7/8^) inches in diameter by Il 30-5/8 inches high. The steel liner is centegd within the outer ' I I d rum. The3 space 4etween the steel liner- and outer drum is filled with ! fire resiTeant bracing Ts' used pheplic to ' foam meeting 20E-Specif1' cation SP-9. Wood l 5,andk6literc port .the .innerf her. Gasy~tylinders nominal 2, j 3, provide (containment. The gas cylinders are l l positioneldwithin, , tee liner hs.ing!pcdded thserts to prevent i , I moveme 2 Theroye pk(ageW&4Jnchen in dQmeter, 41-1/8 inches l l high a as hxiinumqilbss tM gpVoff 7pp, pounds? l l., y % g Q 4' g l I b [ ,
. Q h l The packagdg istconst.ructd.ddn accqrdance witbrawings in Figures A.1 I Q$Lfft,$/TM- E, April 1983.
throughA.6(jl ORNLRdpoh jg' 4o - e 4 P l)i l e +***M i1, Il l l 'I I' Ik I ; lN I ;g l' !g I I g
- 1 l
l ls-Il i II 4e ')h ' l bss-r-sawwwwwsase-------sewwsaww--wwsswwwww--w_w - - - - - -I l
g--------h===------h------------_,------_------y - NEC FORM 818A U.S. NUCLEAR REGULATORY COMMISSION g ** CONDmONS (contawd i g I [ 4 Page 2 - Certificate No. 5552 - Relision No. 0 - Docket No. 71-5552 I 3 I d, 'l i Ni 5. (b) Contents llI I (1) Type and form of materia! ( Tritium gas (uncompressed) i, l (2) Maximum quantity of material per package 'g iln E lly if Maximum decay heat load not to exceed 5 watts; maximum activity not to exceed 30,000 curies; internal pressure of containment vessel when il loaded not to exceed 11.8 psia at 70'F. g, j,, Hj 6. The package must be leak tested in accordance with procedure 16A dated !g
!g ti October 11, 1978.
Il Ui I The package authorized by this certificate is hereby approved for use under the 7. general license provisions of 10 CFR $71.12. ;j fl( g t, i, E 8. Expiration date: July 31,198E. !I I;; it
'l REFERENCES I f
g! af,, ,1 l g! lak Ridge National Laboratory Report No. ORNL/ENG/TN-5/R1, April 1983. i il
~',
qi Supplement dated: July 6,1983. ',n )g l A tg dl -% FOR THE U.S. NUCLEAR. REGULATORY COMMISSION Ig I -' !g Il g; Chnles E.)MacDonald, Chief i
;g
(; Tt . sportation Certification Branch lg I Divisioniof. Fuel . Cycle and
',l I; ;iMaterial' Safety -
'f!'
~
f Date: M 13 E .
;l l :l I:, v
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_---- -- m= = = = = = = m - -- A s A-wararanarwmmwamrmrma -- - I N lE +RC n> FORM sis U.S. NUCLEAR REGULATORY COMMISSION ' CERTIFICATE OF COMPLIANCE el l FOR RADIOACTIVE MATERIALS PACKAGES l fl io CFR i e CERT,F cATE NUUBER 5563 7' D REVISION NUMBER 5 c PACKAGE eDENT FICATION NUMBER d PAGE NUMBE R e TOTAL NUMBER F' AGES ' l USA /5563/B( )F 1 2 I REAMBLE a in.. c.,1 r. cat. .m. o io cen.,v inat in. pacmag no ano conteni.o..cr.e.o .n ii.m s o.io.. meet in.appi,cani. t.iy stanoaro. i eorin in t,ti. io. coo. l 1: , l1 o, reoerai neguiates. Pari 71. packaging or nao oactiv. warenai vor tran. port and Transportation of naa oactiv. uater ai uno., certa n condition. - l} n in,. cert.v. cat. ooes noi rei.. in. cons,9nor erom compi.anc. ..tn any r auirement of in reguiai.ons oe in. u s oepanment of Transponation or om., l1 appi cao. reguiaiory agence inciuo no me government of any country inrougn or into on.cn in. packag. ..ii no transporteo l[ ; R1 j f 3 THIS CERTIFICATE IS ISSUED ON THE BASas OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION a PREPARED BY #Aiame and Aderesst q1 b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION j Babcock & Wilcox Company Babcock & Wilcox Company application
.1 P.O. Box 785 dated November 6,1967. as amended.
1 Lynchburg, VA 24505
]
3a _ n n C r. , f 71-5563 3 c OOcuf1NuueER4_ -
@h 1 4 COuDiTiO,~S .s t ( ,
rn.. cen , car. ,. cono.tonai upon suiv,n.ng in. requ,r.rn.nt or io cra part ri. a appi.c oi.. ano to, cono.ilon. .p. cit..o deio. k 1 A 1s ;
- 4
() s .-
- f (a) Packaging yy )
E 1 C 4 li
'1 (1) Model Nos.: 660C and 6608 #
B 1 - n' j (2) Description M fll
~
7 .n a :11 -?, ina 'i
.) Model No. 660C packaging is ' constructed as describid)in Babcock &
1 Wilcox Company's. application:da'ted November 6, 1967 3 Model No. 660B j packaging is constructed in accordancei,with Division of Naval Reactors letter; (NRiRR:FRH G-f 2248); dated. September 25, 1969. y
- .- ;a, .aysio-- r !
l (b) Contents y , 1({!!!!4 , 7' ! 1 v ' _ , ' : . f .311 Q M q i %
] (1) Type and fom of material ~ &
h s 7 5- r2 1 / - s.s .: , .- 1 " Unirradiatdd fuel cluster. l . ' s ' ~
'W sy N
}
j (2) Maxinum quantity of material per package Y 1 .. . - A ! 1 One fuel cluster containing-U-2357as specified in Babcock & Wilcox l 3 A Company's application dated November 6,1967. ;
\
]L (c) Fissile Class III j
1 Maximum number of packages ,1 1 per shipment. One (1) ji 1 ,R ( ll
, f
. 1 ji l , f r l>I
'I
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! I: I l I'! I l SO I
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== -m-m-=Eram= 4ErrisrEErsaw==dwawrTemmarathw-Tm2rraym sac s w:v s =L CONDITloNS (continued)
)!
! , lb h4 h'l Page 2 - Certificate No. 5563 - Revision No. 5 - Docket No. 71-5563 gl lg' I l
- 6. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR %71.12.
{j:
'g
! 11
'b;
- 7. Expiration date: October 31, 1989. El k;
REFERENCES I h The Babcock & Wilcox Company letter dated November 6,1967 (classified). 'p: e n r- K l Division of Naval Reactors supplement (NR:RR FRH@#' 2248) dated September 25, 1969 ki B: from R. E. Kosiba to Manager, Sche'nectady Naval Reactors Office, AEC. v ny FOR THE U.S. NUCLEAR ~ REGULATORY COMMISSION }l g s] UA t R: T* ~
,, y C) NN -
q .
. y- -
l v .s
,D 9dg N Charles .f.
cDonald, Chief; [! f- TranipdrtatidalCertificatiod Branch i $.4 Divi'si6n 6f Fiielj Cycle and _) g g1 7$y i g 1-
^
r
.4 5t t-A;r_zMatehia)/ rgSafety, ry; INSS f.
7
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E. jy OCT 2 51984,, G%. p Date: qq~6 4% N.sp r_9$p 7 ,',..' ;b o F --
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ll,___________________- _________________________________, __ l E[""* l io cra " CERTIFICATE OF COMPLIANCE I FOR RADIOACTIVE MATERIALS PACKAGES !I li i a ctnrincart uuusta m aevision suusta c eacnacc ioe~rincario= ~uusta . aace nousea (; 5580 2 USA /5580/B( )F 1
. rorat 2 wousia jy aois l I
I; i ei,eauste
. ji rnis eertiric.t. is inued io c.rt.,v inat in. p.ca.ging .nd cone.nta d.seno.d initem s o.iow. me.ts in. .pp=.di. e.eety st.nd rdi set tortn m riti to. Cod. oe :q ll Federal Regul t ons, P.rt 71, "P.ck.gmg of Radio.ctiv. M. ten.fs for Transport and Tr.nsportation of Radio.ctiv. M. ten.1 Under Cert.in Conditions *
{g II E1 e Tnes certificate does not relev. tn. consignor from comph.nc. with .ny r.quirement of tn. regulations of tn. U S Department of Transport teon or otner
.ppuc.oi. regui tory g.nci.s. inci $ng in. govemmeni of any country inrougn or mio wnica in. p ca.o. wiii b. transport.d l
ll I! 4l i
* '" ,"'fi,ao'^a'v E*.'**".n'. OE', **** ' " "'" ***"*'*i, firIe'No'IoEElltio.'*oNep"ollIoEIE"cario~
Il i il U.S. Department of Energy Safety Analysis Report for S5W Power Unit l t y 1l Division of Naval Reactors shipping container dated August 9,1968. I Washington, DC 20585 lg I i l l Ij i
. oocxer ~uuna 71-5580 lII
's 4 CoNoirloNS Tnes c.rtificate is condition.I upon fulfilhng tne requer m.nts of 10 CFR Part 71, .s .pphc.bl.. .nd tne conditions specife.d below
,i .
ll (a) Packaging I l 1 (1) Model No.: S5W Power Unit i Il ! l (2) Description l l l h The S5W Power Unit shippin cb I g assembly designed t$ ship , d n' stoN
'qtainer tlk (PUSC) naval reactor is a container power units. and support r lly I The PUSC is com.prisdd essentially of thray major assemblies: (1) the l-outer frame, (2)lthe inner frame, and (3) the shipping container. ll I ted to the inner frame I I
During in a horizoWal shipmeht, position.the Twoshippingtrunnions container welde is b6]Cto the middle section I l fgj of the shipping container support the lower'end of the container and I also prgide thejans whereby the copts16er caDe rotated from the I
- 1) horizon attitude to hedertical (7Bading-unloading) l whichar]eboltedto~ Intheinlnerf attitude)aT T r (shipping) ' fami?;he Il l
ll e inner, f(a 9 trunnion bases 3The inner frame and shipping y it(th'e oig}ldin(ons turnri i l f l contaiqsc are suppor elasticfppockyounts; - 9 dframe/and pe3stal through W 1eh I secured t70th the inner frame 80 '3 l i gj W s%
& l I! and outeY framphNb, '
- 6. h "esch lJ j N
l' Approxim dimenpions[#1vtp # r asseitbjies of the PUSC are: l i Shipping Dd tainbr?"'95 jndiW41am Y by 23&Jnches; Inner Frame:
.y; li 109 inches 4 I! th by 5findhps> 1bh
- 269 w'hes length; Outer i Frame: 121 $heswidthbF56pinchesheig by 236 inches length. I Maximumweight'dptheloadedPUSCisappfQimately h 127,900 lbs.
fl l ( %*d l l li , l i 'I l i lli I I g li Ig I 3l 0' !gp l tg 1 l I; 52 Q li , l k
)
L________________________________ - - - - ----- ----- - - i - 1
7___ORM l NAC F 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION O *31 l I il I l Page 2 - Certificate No. 5580 - Revision No. 2 - Docket No. 71-5580 JI I fI I I h l h (3) Drawings g I < i I l The packaging is constructed in accordance with Westinghouse Electric Corporation Drawing Nos. 936F963, Rev. 3 and 936F964, Rev. 2. l
]lj (b) Contents l f l li i lj (1) Type and form of material l 1
Unirradiated fuel aassemblies of the following type, l b l (1) S5W Core 4 power unit with control rods installed and secured in ' l lj place by holddown mechanism. i 1 l 1 (ii) S3G Core 3 power unit with control rods installed and secured in l place by holddown mechanism. q l I h (2) Maximum quantity of material per package l II l One fuel assembly as described in f(b)(1)(1) or 5(b)(1)(ii). i ll 'I I III (c) Fissile Class
, t, l
~ ,
}[ Maximum number of packages , n c Q j ,I, fj One (1) q
~
per shipment: s < < f, , lj I cv ge, i i 3 6. Expiration date: March 31,1988, i 1 l',
~
/, ;
fl REFERENCE / f c'. ' () j fl
+
(<- j
' - 2 m g li Safety Analysis Report lfor S5W Power . Unit: Shipping, Container, WAPD-0P(R)SA-820 dated y T
August 9,1968. i y- // , p 1 n _ , 7% f, . . , 0 l3l J, , ,
; ;FORITHE'U.S. NUrLEAD REGULATORY COMMISSION l l
hl ' If}} . Y D l [#h} b..h[ h,/ j f1; ' f,', C'narles E. MacDonild, Chief i 1 ' ,) Transportation (Carlification Branch I h
'f Division of, Fuel Cycle and I I
h ~' q g terial' Safety, fetSS 1 I SEP 0 61983 l i J; Date: l I i li 1 1, ! l II \ l l i I I 1, y I 53 I I i li l I Is wwigww--_ - - - - - -
-w w---------------
n===i 5 A ATmit1*AT's_TEMFAWl_ iMKi=W:wwSN8Nm!*LNeumnSemeemwN _ Rl : ennNRC FORM Sia CERTIFICATE OF COMPLIANCE U.S. NUCLEAR REGULATORY COMMISSION '
%l'0 C'" " FOR RADIOACTIVE MATERIALS PACKAGES i
t a CERTIFICATE NUMBER e REVISION NUMBER C PACM AGE IDENTIF ICAT60N NUMtit.R a PAGE NUMBER
~ e TOT AL NVUtsER PAGES .
5595 0 USA /5595/B(U) 1 2 ;m PREAMBLE ' I l' O This cert.ficate is issued to certify that tne packaging and contents described m item 5 below. rneets tne apphcab6e safety standatos set fortn en Titre t O. Code lg; or rederai segutations. Part ri. eacnag.no of Rad.oactive Materiais for Transport and Transportat oa ot Rad oactive uate, .i unoer c ta,n condet ons ~ ek' h ll; b in,s cert.e. care does not reueve tne consignor erom compi.ance ..in any requ.rement of ine regutar.ons et tne u s oepartrneni of r,ansportat.on or a:n.r appucao= regutatory agenc.es .nciuding ine governmene or any country ineougn or into nica tne pacama. -m be transponed fi p ld! N
* '"JEPllEE^.7d'a'*.e".'Jfae'."'
a *** ' ' ""'" ^*" "'E"Ei fdd,"!E UEc'A!JE$fM"OPOf=*Ef" cation : U.S. Department of Energy Safety Analysis Report for Packaging: The P.O. Box E ORNL Uranium-Shielded Shipping Cask. ORNL , Oak Ridge, TN 37830 Report No. ORNL/ENG/TM-4, Second Revision - June 19.83, as supplemented. l r . - ~
. c ceCutNuueca L '71-5595 4 CONDITIONS _\ t"
' ( .
Tnes cert 4f.cate is cond*tional upon fulfilbng tne requ rernents of to CFR Part 71. as apphcable. and the cand.tions specified below 1 5-(a) Pa ckaging fu co - , (1) Model Nos.: , band M C# rf: l A ' lR' (2) Description / I Dd- ' C H. li
..\ ,
..s
- - / . %i 8>
Steel encased, uranium shielded longitudinal.ly- finned shipping casks. The g containment held withi.n.;ll-inch vessels for both diameter by'models 17-1/2-inch.highmeets special form Positive cavities. requirements closure and are 'p of the lids iss accomplished!by:, twelve,13/4-10 UNC bolts'for the flodel No. lI; L and sixteen, 3/,490 UNC* bolts ifor ;the Model No.11. Both models have 3-inch deep fins, are. mounted .to?a~ 69-inch square skid, and-are enclosed 1 1 E-I y within a meshi ,s personnel a , x_ % - ., heat {,!shield.;* g
,. N t t >n_
f it p
.~
The Model NoY,,L,has 'a 25-1/.2-inch 0.D. -(excluding fins); is 39-3/4 inches y; l,g' high; has a 35-5/8-inch diameter; bottom lug plate;-a maximum uranium shield it
!I: thickness of 6'/34, inches; and a gross weight ofsl3,200 pounds, t g
8 vg N.. U The liodel No. M has a 25-inch 0.D. (excluding fins); is 38 inches high; has i a 35-1/8-inch diameter bottom l1ug plate; a~ minimum uranium shield thickr.ess i [g(! of 6 inches; and a gross weight of '11,600 pounds. i i lr (3) Drawings lI:
\
\ l l
The packagings are constructed in accordance with the following Union l [i Carbide Corporation, Nuclear Division, Paducah Plant Orawing Nos.: Model No. L, M-ll572-EM-001-E through M-ll572-EM-003-E; Model No. fi, M-ll572-EM-
- g
'p gl g 010-E through M-ll572-Eti-014-E. lp p
I. ;N l' 'N I, if lB n I! r i lW
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I N l s4 , . ul 8 , , r I p l I l _I _ _ - _ _ _ _ _ -- -- --- - - --- -- - s- - _ _ _ _ ,.is s- - - - # ri n rsssssss <- w I
i MEMknsx=EEEEEEEKi~KLWIIMEs?Atarrnm KEEkmm LX~REWstMnEn5 ,
" '5 " # ' " '
CONDlTSONS (contmuod)
!Wl )
Page 2 - Certificate No. 5595 - Revision No. 0 - Docket No. 71-5595
)
;n (b) Contents (1) Type and form of material j
!9 Solid, non-fissile radioactive material encapsulated to meet the , requirenents of special form material as defined in 10 CFR 971.4. (2) Maximum quantity of material per package h' ? Ig The naxinun internal heat must not exceed 5,000 watts.
- 6. Packages hafing internal heat gre[ter h[k hgwatts must be shipped as exclusive "S*' ,
( :p
- 7. The package authorized b[ this certificate is hereby app (roved for use under general license prodslons of 10 CFR 971.12. lp
,,)p T .,
< )
p 8. Expiration date:g)0ctober 31 1988. / g b k/ ' Ah \ REFERENCES Bl g g -- ,y [. I Oak Ridge National Laboratory Rep {rf o. ORNL/fNG7k4,hecond Re6 ion, June 1983.
, ,s DOE Supplement date'd:- Septe::ber130, ISB3. Z2Lch) N /< k )N qt) Q'iY
$j[ y,.
Q?C%
- k. ' ' '
DTf!Q~NUCLEA[REGUQTORYC m f %5.
, ~ }
t g; 9 l,b s p# . vs. - d;y
; ~
I 4 h J$k@6 > 6 V:w
' )Q y w
% b;;;\. "/ ll W,
f . h /g/ .)grChar,QDE. L Transportation Cer f1 Ha cationonal Branch 3, ' Chief ! l fg- Division of Fuel b}y le and !), i g. ger q(ety,fNSS
' " lI Date: OCT 131983 >
>l i
't
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h Ik
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i i I i 1; n 4 g 55
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map m a si:1 m a m KEEGim a m KAWK&. AdsgGmulnenanangrilELE.%Nai%-W .X
! wnCFORM$1s I i. ui U.S. NUCLEAR REGULATORY COMMISSION t I; to CFR 7' CERTIFICATE OF COMPLIANCE r FOR RADIOACTIVE MATERIALS PACKAGES i f 1 a CERTIFICATE NUMBER D REVIS80N NUMBER C PACKAGE IDE NTifiCAflON NUMBER 0 PAGE NUMBER e TOT AL NUMBER PAGES '
5607 5 USA /5607/B( )F 1 3 ' e4tE AMBL E l a inis certificare is issued to cert,ty inat the packagmg and contents described in item 5 belo.. enects the apphcable safet y standards set fortn en Titie 10. Code gl or r.oerai aequist.ons. part ri. "eacmag ng of aao.oact .. wa'er ais for Transport ano rransportat.on oe naa.o.ct v. varer.ai unoer certa.n cono t.ons - I, b Tn,s c.rt,t.c.c. oo.s not rene . en. cons gnor trom comeiianc. ..in any requirement or tn reguiations os in. u s oepa,trnent of Transpo tat.on or utner l i appucani ,eguiaior, agenc .s mcioomg in. gov.mm.ni or any country inrougn or into on.cn tn. pacmag . ii no iransporteo I g
=ii s Twis CERTinCATE a PREPARED BY rhame and isA.:Ryryssa issufo ON THE BAST $ OF A SAFETY ANALYSIS FeFPORT OF THE PACKAGE OEssGN OR APPLICATION '
b TlTLE AND IDENTIFICAflON OF MPORY OR APPLICATiON - [! E.Savannah g I. DuPont de Nemours and Company River Laboratory T-2 Shipping Package, Safety Analysis Report, Draf t: April 1980, as amended. dAiken,SC 29801 ' l'
- c2tchtNUR E M_ s,50/
f
~
,5 4 CONOITIONS ..
% %- ' '~ / ,3 This certificafe as condit.onai upon fulf:famg th. regtMerMs of 10 CFR Part 71, as applicabl., and the band 4ons specefied beso.
l5 N) ' r (a) Packaging i l Q R-gl (1) Model Nol O T-2 ., ,q g; I r wV ff d ', (2) Descripti}on 4 / l. I
-<% ), y (q/;l .
Packaging for irradia'te' dl reactor fuel')a'nd components ' consisting of a h lead encased s hipping, ca se. in steelicasks remov' able~ containment vessel insert and ' I; O> C '
, 3,,j !q hyk T*. c '
p! I , l E,; The cask is a ' double-wallet stdal c[ircular cylinder with thickened l shieldin[,in the conter poi'tiib4) L The. central cavity is 6.065 inches [ in diameter:by 100' inches-lo'ng4The31ead shielding is 9-1/2 inches y' thick along .a 45-inch ~ center section. reduced to 5-5/16 inches at each s 36-inch end'section. Th'e contaimne'nt vessel is-positioned within the I. I; cask. Cask closure is accomplished by a gasketed and bolted steel plug. The cask.is enclosed in the shipping case which is 36 inches in y f diameter by 133 inches.long welded to a 4-foot by 6-foot steel pallet. i The maximum weight of the p,ckaging(is - e , 18,400 pounds. l ' I! g i I I l I l ! L ! li i . 1 4 l ll' i l I
' k>
' !il r
! I i IE I g 56 N 9 i 5 ! I 5
-______________________________,__________,r,,m_.b
meesh ----i=OaA= = KKK=3==_=
=_ g CONDmONS (contmued h:=c :.
la 4 g'Page 2 - Certificate No. 5607 - Revision No. 5 - Docket No. 71-5607 @ l - I i l 'S. (a) (3) Drawings !)) E (1) The shipping case is constructed in accordance with DuPont Drawing ll E. B Nos.: W716539, Rev. 0; 180191 Rev.1; 180192, Rev. 0; 180193, Rev.1; 180194, Rev. 0; 180197, Rev. 0; W716538, Rev. 0; 180195, j
$ Ig Rev. 0; 180196, Rev. 0; and 180089, Rev. O. lp
'N (ii) The cask is constructed in accordance with General Electric )
ja Drawing Nos.: 9190755, Rev. 0; 135C5202, Rev. 0; 153F966, Rev. 0; and 10603721, Rev. 0; or it is constructed in accordance j!, with DuPont DrawingsNos.: FW239534.Rev.2;147214,Rev.15; 147215, Sheet 2GReval 2'; and '147216,/Rev.1. g n \ , *' ' %d E (iii) The ANL ins'ert'is constructed in accordance with Argonne National 1 hl
'n Laboratory) Drawing Nos.: W0147-0227-DD, Rev.' 7; W0147-0228-DD, Rev. 6 fW0147-0229-DC, Rev. 6; W0147-031-DD,Rev. 3; W0147-0234- jy DC, RevT 4; and W0147-312-DE, Rev. 2.
g. G ' Co N. x ,. 1 (iv) Thel, TREAT VesseVinsert is constructed /in accordance with Westinghouse ,l r Hanfofd Company' Drawing ,Nos.:3 H-3-39082, Rev. Oi H-3-36134, ,5
'I Re d ; and H-3-36823, Rev} 1.' (2~
\ II e.
V
<f !t / (
Contents - air as primary.doo(lant ?y f W{ I f (b)
. ;g F ' '
wN y 8 ,J , (1) Type andfform (fyter'la
'u- - -
FIh[ .' .k
.p
. , , 4h
> [1
,1 (i) Irradf ated ciad'.'fuelfIn the, togof solld metal.' oxides, nitrides, and ' carbides of: Ora 61um,Iiplutenh',To/imixed umnium-plutonium
^
isdrtsor The clad l)3
!g conta'ihed fuel map containwittiin the Afqu.pnti sm'all i ,tfe's /REAT ofilla or K. Vesstljinsert.
The minimum llI cooling time nust be no less'than 150 day I en . s (ii) Irradiated [ lid fuel pins of uranium Ilioxide enriched to up to
, 3.0 w/o in U-235 contained within thE ANL insert or TREAT vessel
)j insert. Average exposufe Isfuel not to exceed 18 megawatt days ly per kilogram. The clad fuel may contain small quantities of Na :s or NaK. The minimum cooling time must be no less than 90 days.
llI (iii) Irradiated reactor components held within the container shown in I l l Drawing No. W0147-0234-DC, Rev. 3. ) i i I I I
'l i !I I
I i , I l l l l l' i d 57 I , g I! I w _.....-_...-__ ------_.......------,----------
-------A----- .wrutwarannetwarmerm __2 U'
y' " * coNotiloNs (continued)
"#^ '
~
ge 3 - Certificate No. 5607 - Revision No. 5 - Docket No. 71-5607 ;g; l' I t. I5, (b) (2) Maximum quantity of material per package. Internal decay heat not to exceed 208 watts, and: % F (i) For the material described in 5(b)(1)(i), fissile material not to A j exceed 1.71 kg. i (ii) For the material described in 5(b)(1)(ii), fissile material f (U-235) not to exceed 00 ams inI (c) Fissile Class for the nabrt 1 describ d n 5(b')( )(i) I and 5(b)(1)(ii), and ginited in 5(b)(2)(1) and S(b (2,)(ii) {
- 6. The contents must be shIlpped dry. When loaded underwater,(the package rust be lE.g dried using Consumer' Poser Company's procedure, "T-2 Cask Liner Assembly Drying i,
,t Procedure," Proc. tb. EE&T-Cl2, Rev.1,11/12/81. !
'/ I J -y i
! 7. The ANL Insert end-Treat Vessehinsertt must
~
sted prior-to be leak'f'e.3 first use y and annually thereafter in accordance with'the procedures specified in Argonne National Laborator.ies Document No? WOl95-0054-ES-00F ; X _ it u.. 4 ~ f l,_ (,) 7 f[K . Prior to each shfpcent, the:packa$e ' rust be le'aktested in'accordance with [f procedures speciffv' ed in Appendix Aito HFEF/N @lM'6202,.RevJ. 2, March 17,1981. v. 9. j } { } g 3 3;y ' e [E
- The package authorized bylthis certificate'is hereby approved for use under the $
general license provisions of;10.CFR 571/12. U~ 'A ~
'A ~ 'O
~
y .; 9
- 10. Expiration date: Ma'rch 31, 1987.i. gy O j s, s j
,- p(, ~
f
, , . REFERENCES ps- <
o DuPont Safety Analysis Report, Olaft' April 1980.. .
. ~ i Department of Energy supplements dated:
9 ., 3 g February 11, April 8 and 20,1982 and ) April 12, 1983. i: 9 FOR THE U.S. NUCLEAR REGULATORY COMMISSION @ n Charles E. MacDonald, Chief k
' ' N Transportation Certification Branch i Division of Fuel Cycle and ;1 Material Safety, NMSS q ge: SEP 191983 !O HI I
d
----- <r.r----- <---- e,.r r-1.<r.r-us++ -3.r#w wr. rwa <- - -,.r r# - - , , . r#wd!.
y======--a===5-------------------- ....--- ..-----,.-- ,,, _ I, I I! eenC ronu sie u.s. NUCLEAR REGULATORY COMMISSION I I ui CERTIFICATE OF COMPLIANCE I lj; +'o CFR " FOR RADIOACTIVE MATERIALS PACKAGES I 1 a CERTIFICATE NUMBER b REVISION NUMBER c PACnAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAutS' 5641 6 USA /5641/AF 1 2 g g
. 2 PREAMBLE i a inis certificate is issued to certify tnat tne packagmg and contents described mitem 5 below. meets tne applicable safety standards set fortn m Title 10. Code of ll l Federal Regulations. Part 71. Packagmg of Radioactive Matenals for Transport and Transportation of Radsosctive Matenal Under Certam Conditions " Ig
!{ b inis certificate does not res.ve tne consignor from compliance witn any requirement of tne regulatKms of tne U S. Department of Transportation or otner fl appiseme reguistory agenc.s. inciuding ine govemmeni of any country inrougn or into .nica ine pacasse -iii be transported ;g ll ll 1:
Il 'I
- 3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION a PREPARED BY (Name and AJeressl b TITLE ANO IDENTIFICATION OF REPORT OR APPLICATION jl 1 i i gl United Nuclear Corporation United Nuclear Corporation application dated !g i; 67 Sandy Desert Road February 1, 1982.
Ei Uncasville, CT 06382 lll ilR, I I I; c OOC ET NuMsEa 71-5641 l lI a CONoiTiONS i l I inis cert,ticat. is condinonai upon furfin,ng ine requirements oe 50 Crn part ri. as appiicabie. and tn. conditions specit,ed beio. 'I l i
'l 1 '- (a) Packaging !I l:i !I (1) Model No.: UNC-2500 j I. :g l (2) Description ll ill ig El Specific packaging is not, required. Safety of shipment is independent 13
,E; of ptckaging, p pf 21 C (j {*g
( (b) Contents
%)
'h e )t lg g (1) Type and form of material L'm R. ,.,'. / ',
~
!ll It Unirradiated fuel l clusters, modules orfother assemblies. !I I; W 19, N / ge r n y f (2) Maximurdquantity o'fiiaterialfper shtdme5t y/w j
gl c7 : ml ..
! }f f !,
il Not to gceed a Type (A,/ quantity'*of} radioactive material; and l
;g y .
s n ,me . . -
?
3,n + ,,, w
,\
I; i Dry Shi,pm,,ent
^
9 ,. j p ? ,,4' ge J' i ;//),, p p> I , ru :
~ -
I; [ Interspersed hyrdo lI j: ratio of th'ree (3) genous nateria,lilimited
- or116s's.T . ; m; to aE)H to U-235 atomic 'I W
s t ;I q' "
. -@ g(h I Shipment limf'ted to: 3 l
g *vp ~ I (i) The stated dry safe quantities (with'out reference to notes or 1, supplements), but excluding 'those parts named as " elements" as j given in Table 10.0-1 (Ip 10.0-4 through 10.0-70), as approved on '
- l. or before May 18, 1983 to SNM License No. 368; or i g,
i I: I; (ii) 700 grams U-235; or p ll I: (iii) Single fabricated fuel part not exceeding 40 g U-235/ inch. , I y (I
- 1. 39 ll( )
I, j I ++ # r- - v-- ##-- --- #vw- wo.rswvs#-r-vvwr rw-- sw r- w- - - -v + - - - - ys- - l
----------------_____--_..___,g_,_________________,
N#C FonM sisA nsn U.S. NUCLEAR REGULATORY COMMISSION lI c0nomons (connnus) ! Page 2 - Certificate No. 5641 - Revision No. 6 - Docket No. 71-5641 j
!I
'l I
,, 5. (b) Contents (continued) l Moderated Shipment I!
1; Shipment limited to:
]I N
!g li Il I (i) The stated wet safe quantities (without reference to notes or I t h supplements), but excluding those parts named as " elements" as il lj!
g given in the above referenced table; or lj l <g dl (ii) 500 gram U-235; or i n 1 Il I I; (iii) A single fabricated fuel part not exceeding 20 g U-235/ inch. l3l
'l f (c) Fissile Class III
( 6. The name plate to which the model number is affixed must be fabricated of materials I L' capable of resisting the fire test of 10 CFR Part 71 and maintain its legibility. lll
,1
- 7. The package authorized by this certificate is hereby approved for use under the (j
g general license provisions of 10 CFR 971.12.
!,1 j
I. I l;
- 8. Expiration date: March 31,1986. 1 g
'g 1,i lIg
-I I '
REFERENCES
;l; 'l
) United Nuclear Corporation application dated February 1,1982; ly I:
I Supplements dated: April 25 and June 1 and 21, 1983. il ig I; I q.- ln g g; :g
- g. -
i, , [ FOR THE U.S. NUCLEAR REGULATORY COMMISSION l Il -
, 3 j,l t tg s w ll Char es.E. MacDonald, Chief !I h Transportation' Certification Branch I Division of. Fuel Cycle and ll il l Material: Safety, NMSS I; " l I, Date: SEP 0 61983 -
i l !y I t: l I li I g 1: I. {R p I
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l li 'I Ig l l! jy 1 l, !g 1 L' 6o 'l
!i L - . w . - . . u . . . . . . w w w. - - w. w . w. - a w . . . . . w . . . . . . . . _ _ . ...3 l
l
3=---------_-----------__________ I U.S. NUCLEAR REGULATORY COMMISSION il llI une ronu s18 on CERTIFICATE OF COMPl. LANCE J i s
'o ct R " FOR RADIOACTIVE MATiERIALS PACKAGES 'l '
b ALVASION MurtSER e 8' ACKAGE LDENTiHCA T ON NUMBER 6 PAGE NUMBER i . CERTIFICATE NUMSER 5687 3 USA /5687/AF 1 e TOT3 AL NUM I; a mAMatE i i; a Tn..certiticat. u.o to certity tn.itn.p.ca.gy no content.o..cre.o init.rri s e o..,n i.in.. cpi,c di...t.ey st.no ro...t eorin n Titie to. coo.ov g' g r.o.r i n.gui.uon.. p.rt ri e cs.png or amo.o.ctiv. u. .rwi. for transport no transport.t.on or a.o.c.ciiv. u.t.n. uns., cert..n cono i.on - eg B) e in . c rtie c t. oo not rei . in. cons.gner fro,n corna anc. n ..m ny r.gwr ,i.n oe te. e.gui.e.on. or in. o s o.p rt=nt >e Tren. port t.on or oen.r 7
;g I; .ppuc.oi. e.guistory .g.acies. .nciuoing ine governm ni oe any coontry r rouan or nto nicn ine p.ck.g. win e. tran.pon.o I; 'I Il I iAPPticATION I, 3 THis CE,RTtHCATE iS ISSUE.D.O.N THE Basis OF A SAFETY ANALYS1$
o TiTtE Auo miencATion REPORT o RtP OF THE PACKAGE CESt,GN O' ORT oR AmicATo 1
. PRE Aafoev,a. ~ .,. , ' '
i Nuclear Fuel Services, Inc. Nuclear Fuel Services, Inc. application dated g! d! P.O. Box 218 August 25, 1982 j)l Erwin, TN 37650 ;I fj :p Il ll l' . oocacTNUMaEn 71-5687 ) l1l lI
;g lI1;, 4 coNoiTio,,NSrn, c.r ,,c.1.,,cono,non.iupon ,un,innain.
1 au,,,,n.n, o,io cra p.rt73....ppuc.es...noin,cono,t,on.sp.c.,,.o J M5 (a) Packaging g f (1) Model No.: RMG-184 !y
!I ll Il (2) Description 1 I 1 The containment vessel is:a 5 79allon bucket, DOT Specification 17H. i f Closure is by means;of 31ug-clamps -used .with a new lid and gasket for ,f f
i h each shipment. (The' outer container,a'55-gallon DOT Specification 17H Il steel drum and gasketed lid is closed by a 12-gauge bolted ring with i 1 drop forgedslugs, one of which is threaded, having a 5/8-inch bolt. ls l il l The containment vessel is supported in the outer container by two, 26 gauge sleeves filled with tamped vermiculite and fire retardant polyurethane;I1 [i foam. ,.
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f (3) Drawing '\ ) i - m
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i; . l , . L \ El The packaging is con'str'ucted in'accordance with Ndelear Fuel Services, ll
! Inc. Drawing No.cRMG-184, Rev.s A. Use of optional'5-gallon insulator ,1 E bucket is' not Jauthorized.- l :t !31! ' ' , $L l i 4 -
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i mac ronas e18A U.S. NUCLEAR REGULATORY COMMISSloN I iea coNomoNS (cetmued 8 Page 2 - Certificate No. 5687 - Revision No. 3 - Docket No. 71-5687 {I
.I :b
;h 1
I ll
!I li '
I 5. (b) Contents 1 )t
'n l (1) Type, form, and maximum quantity of material per package (i) 0xides of uranium, at uranium densities not to exceed 3.2 g/cc.
fl l Not to exceed one hundred pounds of product with the maximum }!g lj enrichment in the U-235 isotope not to exceed 10 w/o. H/U-235 - N i ratio, considering all sources of moderation within containment {gg j vessel and maximum U-235 content must not exceed: in i B Enrichment Maximum U-235 Content N i'!
!g % U-235 H/U-235 Kilograms {j
;il lI! .i 1 20 0.401 :p
- l 2 10 0.802 ll Il! 3 5 1.203
}; 4 5 1.604 lB A
.g! 5 3 2.005 l
!I}
I 6 3 2.405 ij l 7 3 2.805
' dlj 8 2 3.205 lg in
[ g 10 9 2 2 3.605 4.005
,5
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Il l (ii) Uranium oxide or metal, at uranium densities exceeding 3.2 g/cc.
,d 1! Not to exceed one hundred pounds of product with the maximun enrichment in the U-235 isotope not to exceed 5 w/o. H/U-235 E
ratio, considering all sources of moderation within containment f, vessel and maximum U-235 content must not exceed:
< g; ll Enrichment Maximum U-235 Content g: % U-235 H/U-235 Kilograms d!
Il 1 20 0.401' i I: 2 10 0.802 I l1 3 5 0.700 gl 4 5 0.700 5 3 0.700 x ' iI
- 1:
il . g' , II Hi E I;i : g:
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l [usQrd-~ = = = =usid= = ==~-- Vmhhrmww.,;.m ,--w 1 a.j 7 ,; - -
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I NRC FORh1816A U.S. NUCLEAR REGULATORY COMMISSI w coNOITsoNs (continued) j
!i Page 3 - Certificate No. 5687 - Revision No. 3 - Docket No. 71-5687 ik p^
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'l i
11 and III f 5. (c) Fissile Class (1) Minimum transport index Maximum
)>
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to be shown on label Enrichment Transport f t for Class II % U-235 Index A ik i 10 3 7 0.2 0.4 0.7
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- n
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Maximum il i (2) Maximum number of packages per ship Enrichment Number of Packages j ment for Class III % U-235 y 3 1.550 lIl 5 390 'I i 7 330 il 10 234 ;>l'
- 6. Uranium enriched to greater than 6 w/o in the U-235 isotope must be packaged f, within a 3-gallon metal can or plastic bottle surrounded by vermiculite within ;
the 5-gallon bucket. l
.h l
i
- 7. During transport and storage, the eight (8),1/4-inch vent holes in the lid or ;
the optional arrangement of four (4), 1/2-inch vent holes in the sides of the drum near the top must be covered with tape to preclude entry of rain water into the packaging. I
- 8. The package authorized by this certificate is hereby approved for use under the j]i g
general license provisions of 10 CFR 971.12. (
- 9. Expiration date: September 30, 1987.
.h di !p N
j, REFERENCE Nuclear Fuel Services, Inc. application dated August 25, 1982.
)) FOR THE U.S. NUCLEAR REGULATORY COMMISSION j
i E ) ' lg lg, Charles E. MacDonald, Chief Transportation Certification Branch fg l If Division of Fuel Cycle and ! E! Material Safety, NMSS ) i
!g SEP 0 61983 lg Date:
IRI f e I dv-rm,----r-yr-v--wwy r v - -- - - - - -~ --- - - l
Il --________-----__________aa____._____________. I ll I;! oce hmC FORM sie U.S. NUCLEAR REGULATORY COMMISSION tI l io CFR " CERTIFICATE OF COMPLIANCE .I l FOR RADIOACTIVE MATERIALS PACKAGES II
- 4 CERTIFICATE NUMBER b REVISION NUMBER c PACKAGE IDENTsFCATION NUMBER d PAGE NUUSER l 5740 1 USA /5740/B( )
I, a PREAusLE 1 e 2TOTAL NUM I: a in.s certihcaie s issued to cert,ty inat ine pac kagma and contenis descnbod instern s 6.iow. meets tne appi.cabie safety sianoa rds set forth m Titie io.cooe at
!I g' y Federsi negulations. Part 71. "Packagmg of Radroactive Materials for Transport and Transportation of Radsoactwo Matenal Under Certam Conditions "
lg N b This certificate does not reheve the cons gnor from comphance with any requirement of the regulations of the U S. Department of Transportation or other I! apphcable regulatory agencies. includmg the govemment of any country through or into which the package will be transported [I
;g I!
Il !n g?
- 'tL
, g! 3 THIS CERTWICATE IS tSSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DES'GN OR APPLICAflON
! a PREPARfD BY theme and A#essi D TITLE ANO IDENTIFICATSON OF REPORT OR APPLICATION i
+
Oak Ridge National Laboratory Safety Analysis Report for Packaging (SARP) of the
}it; P.O. Box X Oak Ridge National Laboratory TRU Californium
}
g! Oak Ridge, TN 37830 Shipping Container, August 7,1981, Rev. of i 4 gl Report No. ORNL-5409/Rl. e I! I 4-c OOC =EY NUueER 71-5740 " i
' I; a CONOIT:CNSThis certificate is conditional upon fulfsihng the requirements of to CFR Part 71. as apphcable, and the c I.
ga F_ yl (a) Packaging b a g. s ll (1) Model No.: ORNL TRU Californium Shipping Container g; H p k (2) Description X g i [; H g A 304L stainless steet_ encased concrete shipping cask. The outer o i shell consists of. two,01/2-inch thicy,66-inch diameter hemispherical li t I! heads joined by a'6-inch cylindrical section. The cylindrical cavity il has a 1-inch thick stainless steel wall and>is 3 inches in diameter x U IT I 6 inches lon k Shielding consists of 30 inch'es of B '* concretehavingadensityofapproximately175t]b/ft}ackburnLimonite . Upper and ! [ lower level ball valves located at the,end of concrete filled plugs l g define, i isolate, and seal the cavity.') Both of tfiese plugs have 0-ring i ll seals, are' boltediiniplace.and are/ protected withia gasketed cover i ll the cover plates and the shell. Ei plate.T' Fusible'plugs-are if[ ,- 3loca,tsd 1i (i(! > W ! 8l l ! The top.. ball valve andsplug may*be; replaced _by otfier plugs for multiple j source shipments. Sources are-contained in special form containers. fy ' s . Wyl} } lL" ', y' g k[! i g g: The cask-is mo'unted onto?a il in}ch7 thick steel base plate by eigh - i i steel 2-1/2. inch NPS Schedul l40%ipe-struts. (The cask is transported i tj on a special, traileri, The package gross weightfis 23,500 pounds. g, <, g y, , +a 9 s - 4 x N)
/l g:
t g M y , 1, ,- i o pr , [ ill i II { ) r I; I II ! 'l n t , in l 1 I 64 )s u; _ ................................,............k i g
$==---------- u.s. NUCLEAR REGULATORY COMMISSION fI
!! wac rone sieA gj *a CONDmONS (contmued j
\n
'i Page 2 - Certificate No. 5740 - Revision No.1 - Docket No. 71-5740 f
ih I !g I
'Ilj !;
lI; 5. (a) Packaging (continued) !y
!g
; I'
' (3) Drawings !I
'l l i I
f The package and special trailer are constructed in accordance with Oak s'I Ridge National Laboratory (0RNL) Drawing Nos. M-11230-EN-001-0 through lj I 008-D, 012-E, 014-E, Ol7-D and Ol8-E, and M-12166-CD-019-D. (Appendix llg N! A, August 7, 1981 revision of ORNL-5409/Rl.) . fl 8i (b) Contents lp i.
,igl (1) Type and Form of Material i,
'y l
juli The contents consist of isotopes of Americium (Am), Curium (Cm), ig Berkelium (Bk), Californium (Cf), Einsteinium (Es), and Fermium (Fm)
'l as a solid (metal, oxide, oxysulfate, or dry salt), contained in ll1
[i capsule (s) that meet the requirements of special form radioactive il g gj i material. j I; is I (2) Maximum quantity of material per package j; l 8l l i Ei For the contents described in 5(b)(1): ,1 y 4 Three (3) grams and the maximum internal heat not to exceed 5 watts. '{ lh 6. A minimum of two lifting ribs shall be used to lift'the package.
'I l8 I 7. The package authorize'd by this certificate is hereby approved for use under p Ij general license provisions of 10 CFR 971.12. - I
< g I,
f
- 8. Expiration date: -Hay 31, 1986. i
.i g I
llg REFERENCE- g
!g Il -. .
jn Il Safety Analysis Report for Packaging (SARP);of.the Oak Ridge National Laboratory TRU j: Californium Shipping Container, August 7,'1981 revision"of Report No. ORNL-5409/RI. FOR THE' U.S. NUCLEAR REGU' ATORY COMMISSION
'jd,f '
p
'l Charles E. MacDonald, Chief I Transportation Certification Branch }i g Division of Fuel Cycle and ill i i gl Material Safety, NMSS I lg u di SEP 0 61983 p lj Date- '
n I, I !I i n I !,i ( 65 f l6n n n . . ~.x. . . . . . .. . . a.-. . . --w. ---. . . w. .h
i m= _===Wi==EEFK4WiE==~=X====sC*A=====_*J5'1 nun m M W M**_ --- NIC FORM 61s ll . im CERTIFICATE OF COMPLIANCE U.S. NUCLEAR REGULATORY COMMISSION
- lE io CrR n . FOR RADIOACTIVE MATERIALS PACKAGES i
I N. g 1 a CERTIFICAfd NUMBER D REVISION NUMaER c PACKAGE IDENTIFICATION NUMtlER d PAGE NUMBER e TOf AL NUMBER PAGts i 5754 4 USA /5754/B( )F 1 2 g PREAMBLE a- If a ints certif.cate as issued to certify that tne packaging and contents described an item 5 below meets tne applecatwo safety standards set fortn en Title 10. Code j q' of rederai Reguiateons, Part 7t. -Packaging of Radioacteve Materials for Transport and Transportation of Radioactive Ataterial Under Certa n Condit ons7
} b in,s cerne.cate does noi reneve ine cons.gno, iron compi.ance witn any requirement of tne reouiat.oro of tne u s oepartment of Transportat.on or otner
{ applecable regulatory agencses anCludeng (ne government of any country tnrougn or into wntcn Ine package will be transported , N i l8l
)
3 THIS CERTIF6CATE IS ISSUED ON THE BASas OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DES GN OR APPLICATION a PREPARED BW INameaN Acesst b itTLE ANO sOENTIFICATION OF REfM)RT OR APPLICATION Nuclear Fuel Services, Inc. -Nuclear Fuel Services, Inc. application P.O. Box 218 dated November 11, 1966s as supplemented, i Erwin, TN 37650
/ 5754 :
c OOCKET NUMBER - I. a CONDITIONS Tn . cert.t.caie is cond,i onai upon vuitanno tne requirernents of to Crn eart 7t. as appi. cab > . and the cor d. cons so.vried tmio. 5 [I
, pf (a) Packaging p t 0
(1) Model No.: RMG-172 E-1 (2) Description E i k The containment vessel-is a 6-inch'ID by 4-1/4-inch long Schedule 40 g. j steel pipe with a flanged and gasketed '. top closure. The containment :W vessel is centered and supported in a 16-iach ID by'21-1/4-inch long h steel drum of minimum 24 gauge thickness by top and bottom stool ) sections. p l (3)' Drawing f,\ The container is constructed in accordance with Nuclear Fuel Services, !i ' Inc. Drawing No. RMG-172. ;b I (b) Contents (1) Type ana fann of material 's
,' g i
' !I Uranium metal or compounds which will withstand a temperature of 800*C lI without pressure generating decomposition. The uranium may be enriched j' i , g to any degree in the U-235 isotope'. The contents shall be contained within two, 750 cc sealed metal cans. j l i d; {y I ll
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--------------------ssi r-,gsreserer---- s r --- s r r www ,a. sww wwess- iI i
_ ______ m_ _ _ _ , . _ _ _ _ . - , . . - . . _ _ _ , . . . , . , - . , . ..-.. , , , _ , . _
CONDITIONS , continued) Page 2 - Certificate No. 5754 - Revision No. 4 - Docket No. 71-5754 (2) liaximun quantity of material per package Ten (10) kilograms U-235, provided the total weight of the contents does not exceed twenty (20) kilograms. Il kl (c) Fissile Class Minimum transport index to be shown on label 4.5 t,I
- 6. The top stool section shall be physically secured to maintain the internal ,M ri spacing within the drum in the event the drum, cover is lost.
- 7. The package authorized by tthis certificate is hereby. approved for use under the t
~
general license provisions'of 10 CFR 571.12. I, _ 8. Expiration date: Sehtkmber 30, 1989. x REFERENCES
~
~
Nuclear Fuel Services, Inc. applicition dated
- November 11, 1966.
Supplement dated: Oc'tober 11, 19671 i , K i FOR?THEIb.'S' NUCLEAR REGULATO
~
- 3 <si;, })l
~
v -
' Charles E.' Ha Donald,l Chief 'N('
E iTransportation Certification Branch
' "if , Division of Fuel, Cycle and
/ Material Safety,'fMSS ,
+ r f7 y , 7 Date: 26 M 1
I
! l 1
I
,f il il t
Il Hi il I 67 I t lII i
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ijunCronessie I aai u.s. NUCLEAR REGULATORY COMMISSloN h I +** C'" " CERTIFICATE OF COMPLIANCE .L FOR RADIOACTIVE MATERIALS PACKAGES l-h .cERTwicATE NUW8ER b REVIS@ NUMBLR c PACKAGE IDENiiHCATiON NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES h 5757 3 USA /5757/B( )F 1 3 j 1 PREAustE ll a This certshcate is essued to certify that the packagmg and contents described mftem 5 below, meets the appocable safety standards set forth m Title 10. Code of ll i: r.derai R.gJabcns. Part 71. -Packagmg of Radioactive Matenals for Transport and Transportation of Rad *oactive Matenal Under Certain Conditions " ] I b lJ This cerbicate does not releve the consignor from cornphance with any requirement of the regulations of the U S. Department of Transportahon or other I sopiscaeae ,oguistory agencies. .nciudmo tne govemment of any country enrougn or into which the package wiii be transporied-lt lll l 1 (1 '====~ ~ ~~:== ==c==A,- p l U.S. Department of Energy 1lr 4 Safety Analysis Report for SSW Refueling y I! Division of Naval Reactors Source shipping container dated February 14s I Washington, DC 20585 1968. lt i i r I I il I; 71-5757 e ooc Er NuusE. ltl
,Ik a coNomoms This certihcate is conditional upon fulhlteg the requirements of 10 CFR Part 7 f, as apphcable. and the conditions specified below I
' I; 'l (a) Packaging l l]t ll (1) Model No.: S5W Refueling Source !c II li I{ (2) Description if 3
I; ll [I The S5W Refueling Sourcetshipping, container consists of two structures, one nested within the others 'having' an' overall envelope of 5 feets { dl 5 inches diameter'by'9 feet, 5-5/8 inchestlength. The outer structure s i I the shipping container, is a ring of polyeth'ylene 11-1/2 inches thick k 1 h I, with an OD 0D6 feet 4 inches and length of approximately 5 feet 2 !t I inches. The polyethylene is canned in a 1/2-inch thick carbon steel ' shell. The, inner structure, the replacement and/ installation container, lr ' f g! fits into7the cavityrof the outer strutture. Thli assembly consists ji i f of a 6-lJ2' inch OD,179-5/8 inches ]6nigst'ainless(central tube, which ll is pluggdd at bothrends by 'niach'ined stafhless steel forgings. Three if I ~ cavitie57are machined {ip the botton) brid ' plug to c'en'tain the neutron 7 I !t I source assemblies. TA 46? inches thlEk, encir'les c the 't central', tube andithis^ jacket ~of lead',3cf ,t.hielding*is to attenuate the hiiiereost,ls~yer r gI gamma radiatiohg A wdlldf hiolkethylene78-1/2 inches thick, surrounds t [l the lead ,sgieldcar6 1s canged M thta 1/2 pinch thTtk carbon steel t g plate. I w we' ighgis;approiiiphtel;y-19'000 Gross mv.m s pounds. t i{i &4 w yQ -) %p) . O
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r I O % i b (! how e - r .I c Ii Il k I t m li lltt r i[ ' ll I I-tt
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+u conomons (continues >
l}i 1 j Page 2 - Certificate No. 5757 - Revision No. 3 - Docket No. 71-5757 ij p l I ll I
!I (3) Drawings
{ j j The packaging is constructed in accordance with Westinghouse Electric Corporation Drawing Nos. 905D318, Rev. C; 905D315, Rev. F and 905D285, i, i t g J, Rev. A. I; In
!B I
l (b) Contents lh t (1) Type and form of material 'j f1 g Neutron sources of the following type, i
)y if1 lgl 1 (i) Polonium-Beryllium special fom radioactive material neutron 1 source. These sources may be either new or have surface contamination !b as a result of previous use.
f (ii) Radium-Beryllium special form radioactive material neutron source. j f I These sources may be either new or have surface contamination as i h; a result of previous use. ln l ' it li Plutonium 238-Beryllium special form radioactive material neutron lI fj! (iii) source. These sources may be either new or have surface contamination j 1, as a result of previous use, 1, lI 's (2) Maximum quantity of material per package < l !I (i) One, two, or three neutron sources as described in 5(b)(1)(1) and I ]l ll 3 l limited to a total content of not more than 800 curies and a combined surface contamination of not more than an Ap quantity of j i j!I radioactive material. i i f; - lsl
~
% (ii) One, two, or three neutron sources'as described in 5(b)(1)(ii) and limited to a total conten't/of not more than 940 curies, with
~
iN $ radium limited to not more than'2.5 curies (gms) of this total. h f These sources are limited to a combined surface contamination of
;l I
f f not more than an A2 quantity of radioactive ' material. lR li ' l! (iii) One, two, or three neutron' sources'as described in 5(b)(1)(iii) ll li and limited to a total content of not more than 925 curies and a 'l combined surface contamination 'of not more than an A2 quantity of I fj radioactive material. ,
, lj i,
1 j' I !g (c) Fissile Class !I 1 I
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CONDmONS (continw V U.S. NUCLEAR REGULATORY COMMISSION I y ll j r jl Page 3 - Certificate No. 5757 - Revision No. 3 - Docket No. 71-5757 J
]l it- '
- y
[ !I { 6. The package authorized by this certificate is hereby approved for use under the d general license provisions of 10 CFR 571.12. {j i i,g ' Fl J p
- 7. Expiration date: March 31, 1988. ! I l! REFERENCES t !
fj! Safety Analysis Report for S5W Refueling Source Shipping Container, WAPD-0P(R)S-2473 : dated February 14, 1968. i Supplement: Bettis Atomic Power Laboratory letter WAPD-0P(R)C-474 dated December 22, g Il i 1975.
- D
'g
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!1 FOR THE U.S. NUCLEAR REGULATORY COMMISSION li l
Charles E. MacDonald, Chief
- h~ -
it -
)i Transportation Certification Branch 'l l
}i Division of Fuel Cycle and 'l j
Material Safety, NMSS 1; SEP 0 61983 f 1; Date: 1 1 3 I! r y O o 3 *
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Ig 1i I w U.S. NUCLEAR REGULATORY COMMISSloN
.h 1 +ac n> ronu sis CERTIFICATE OF COMPLIANCE 1 'o CrR r' FOR RADIOACTIVE MATERIALS PACKAGES ll j
c PACKAGE IDENTeF6CATeON NUMBER d PAGE NUMBER e TOT AL NUMBER PAGES f , a CERTIFICATE NUMBER D REVISION NUMBER 2 USA /5758/B( ) 1 2 j 5758 j 1; 7 PREAMBLE j
. Tois cert.t.cc. is issu.o to c rt.vy tnai m. packag,ng ano contents o.scrio.o initem s o.io.. m ts in. appi.cani. safety stanoaros s i eorin .n r.ti. io. coa.ot 1l jg y r.cerW Regulations. Pad 71, " Packaging of Raoicactive Matenals for Transport and Transportation of Radioactiv. Material Under Certain Conoihons '
1 o in.s c rtificat. oo noi re .. tn consignor from compiianc. w.tn any r.quirement of ine reguiations of tn. u s o.partment ce Transportation or otner J 1, appiscani. reguiatory agenc.es. .nciuo.no in govemment of any country enrougn or into wn cn en package weit e. transported. lk i 1
'N %
- THIS CERTIFICATE IS f$$UED ON THE SASISb OF A SAFETV ANALYSIS REPORT OF THE PACnAGE DESIGN OR APPLICA TITLE AND iOENTIFiCATION OF REPORT OR APPLICATION I
k a PREPARED BV f Aiew and AJisresst Safety Analysis Report for S5W Core Barrel f f U.S. Department of Energy Divison of Naval Reactors Disposal Cask shipping container dated f, 1 Washington, DC 20585 February 23, 1968. lg lI h I 1 1 c DOCnET NUusEa 71-5758 llI a CONDtTIONS ;I 1 Tn.s c rtie.cc. is conon ons upon ruitang m. r.au.r m.nts of io crR Part 7i. as appi.cani.. ano in, conoitions specir..o e.io. 1: il (a) Packaging f (1) tiodel No.: S5W Core Barrel Disposal Cask lI 1[ 'I h (2) Description
!I
{h The container is an upright cylinder 139 inches high, 58-inch inside ll diameter and ill-inch foutside' diameter., The inner shell is either jI f' 3/16 inch corrugated' plate or 1/2-inch / carbon steel plate, and the jj i outer shell isfl/2-inch carbon steel plate mounted on a 1-inch base 1 plate. Shielding consists of 26-inch thick; reinforced, high density 1 i concrete around the inner shell and on the bottom, and 15 inches of In carbon steel plating on the top. The A 1-inch cover I I the top to seal tthejcontainer. con'tainer ha'g plate is welded s'a protective cover on lll l f around phe' relief vane of 3/4-inch' thick plate.qGross weight is 1! approximately q 180s000 f8 4 pbundsO i v(g >C i)l i r k (3) Drawing _ .y
,yg 9 *1 Mej ' <
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I The packagingeisiconstructed!In accor[ dance with Westinghouse Electr in Corporation Dr' awing to. 926J485 p 6' 7 !i a l g w=m.ps; v y> . si
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cs' 1, g/ 3 l, QP r) v". W* G,r,, ' lp J. g \ I)g 1 / I! 1, h 4n 4 Ju ;z r h lI il
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, ou CONDmONS (continued I
il ll, Page 2 - Certificate No. 5758 - Revision No. 2 - Docket No. 71-5758 I , il, I !I li ll li (b) Contents Il li !i th (1) Type and form of material f f An irradiated 55W core barrel which meets the requirements of special ll fann material, with between 2 and 10 gallons of water and surface l contamination in the form of activated corrosion product.
!g Hl i )
(2) Maximum quantity of material per package i fg' One irradiated assembly as described in 5(b)(1). Surface contami- fl l ill nation shall not exceed 3.2 curies of radioactive material. The special form material shall not exceed 100,000 curies. Shipment shall j I; y L not be made prior to 30 days after reactor shutdown. g 1 fI 6. Expiration date: March 31, 1988. I i' I REFERENCES j Safety Analysis Report for the 55W Core Barrel Disposal Cask shipping container, i Li WAPD-0P(R)SA-724, dated February 23, 1968. 1 Supplements: Naval Reactors Memorandum G #13635d E ated June 19, 1968, G #1462; dated August 12,1968 and G #4470; dated December 12, 1974;
, i FOR THE U.S. NUCLEAR REGULATORY COMMISSION
) t i l l
NA[bbd Charles IE. MacDonald, Chief j Transportation Certification Branch Division of' Fuel . Cycle and ; 3 Materia 1> Safety, NMSS2 SEP 0 61983 ' J2' l 1 i I Date: l:i; t s
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.u FORM sta CERTIFICATE OF COMPLIANCE U.S. NUCLEAR REGULATORY C FOR RADIOACTIVE MATERIALS PACKAGES fl ll'80'"7' b REVISION NUMBER c PACKAGE IDENTIFaCATiON NUMBER O PAGE NUMBER
' . CERTIFICATE NUMBER 5768 7 USA /5768/AF 1 e TOY 4AL NUMBE i , PRE._ :,
e.tv .t.no.ro. t vorin m riti. io Coo.oe ly
. rn.. c.rtiesc.t. . . u.o to c.nety in.iin. p.ck.gmg .no content.o..creo.o initor i s e.io...
- t. in..ppuc.oi.
i; Ig i F. der.1 Regue.hons. Part 71, "P.ck.gmg ov R.dio.ctiv. Mat.r af. :or Tr.n. port eno Tr n. port. tion av R.oio.ctive Materi.I Under C.rt.in Condition.
- 13 e. inis certivicat. oo not ren.v. in. con.ignor trom compn.nc. ..in any requirement of ine r.gui. tion. ce in. u s o.p rtm.nt ce r,.n port.iion o, otn., l Xl
.ppiic.o . reguietory agencies. Inciuomo in. governm.nt or any country enrougn or into =nica in, p.ck.g. will o. tran. port.d- lJ I; in Nl lI 3 THiS CERTIFICATE IS ISSUtD 04 THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION b MLE AND IDENTIFICATION OF REPORT OR APPLICATION I
a PREPARED BY JNeM and A# essa g[' Babcock &WilcoxCompany Babcock & Wilcox Company application jl 609 N. Warren Avenue dated January 29, 1982, as supplemented. jg lgl Apollo, PA 15613 'g I di e DOCKEi NUMBER 71-5768
.I l8l i CONDmONS ;I lI in,. c.rtenc.t. .. conoition.i upon weing in. r.quir.m.nr. o, ic Cr A part ri. .. .ppnc.oi.. .no in. conoition. .p.c e..o n.io-ll; 'l (a) Packaging (1) Model No.: BB-250-2
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ll (2) Description jll AI Inner container is 11 1/2" ID.:16-gage steel cylinder, 63-1/2" long, il with bolted and gasketeditop: flange closure and seal welded bottom il [g plate. Inner container is centered and. supported in a 22-1/2" ID by j
;i minimum 74" long,' 16-gage steel drum by 1/4", diameter spring steel lg I
g! rods and vermiculite. The outer cover is secured by either a 12-gage j
'd closure ring;cr six (6),1/2" diameter boltsL Maximum weight of ll E. packaging .and contents is approximately 650 pounds. 'I 1, v .
ll 8 (3) Drawing,D f( f r'
, 71, s b; p '. ((
i j i l g(! The BB-250-2 packhging .is constructed *iri accordance with Babcock & p Wilcox ; Drawing No.10-F-771,- Revision ~ 5'. 72 dj Il w, y
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_____---___--___-__--_________________g___,_ g! NRC FORM S1SA j ce conolinons (continuea) U.S. NUCLEAR REGULATORY COMMISSION ll li } I' b l Page 2 - Certificate No. 5768 - Revision No. 7 - Docket No. 71-5768 dl l' i ))
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li: II in (b) Contents I; li (1) Type and form of material )) I i (i) Uranium oxide enriched to a maximum 4.0 w/o in the U-235 isotope. {
- gt Chemically-bound or physically-bound water in mixtures is permitted. 1 Slips or slurries that exhibit a visually discernible liquid gl I' second phase are prohibited.
tl I t (ii) Bulk uranium oxide (U0 or V 0 powder with a maximum density of l j 2gU/ccandenriched$oam2xYm)um5.0w/ointheU-235 isotope. ' lg t The maximum H/U atomic ratio, considering all sources of hydrogenous isl material within the inner container shall not exceed 1.13. I ! I (iii) Uranium compounds which will not decompose at temperatures up to I;
; 750*F. Uranium may be enriched to a maximum 5.0 w/o in the U-235 l isotope. The maximum H/V atomic ratio, considering all sources of hydrogenous material within the inner container shall not
[}l lg I exceed 1.5. d Il; (iv) Uranium oxide pellets, enriched to a maximum of 4.0 w/o in the I U-235 isotope. The maximum H/U atomic ratio, considering all %g sources of hydrogenous material within the inner container, shall l not exceed 3.0. ;{il d q (2) tiaximum quantity of material per package ! E R: g, (i) For the contents described in 5(b)(1)(i)- y[p p I Total contents not to exceed 200 pounds, with the U-235 content l f not to exceed 2.95 kg. The contents shall be contained within I g t two (2), 9-3/4 inch diameter by 12 inch high sealed stainless ll i g- steel cans. Empty stainless steel cans will be used to make up ll the remaining space within the inner container. f i g N: i ll (ii) For the contents described in 5(b)(1)(ii): )'I I h(' g' Total contents not to exceed 315 pounds, with the U-235 content not to exceed 6.25 kilograms. The contents shall be contained !I I d within 9-3/4-inch diameter by 12-inch high metal containers. [ dl Empty metal cans will be used to make up the remaining space fj I' within the inner container, 4. di g- )[ I. El I i i t' l lll d' l I 74 l lI I
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5----===---------------h--------------3.-__ U.S. NUCLEAR REGULATORY COMMISSION I j NRC FOR48 618A y na CoNolisons (contmuesi
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l !1 i !g 1l. l Page 3 - Certificate No. 5768 - Revision No. 7 - Docket No. 71-5768 j l li i il 1lt 1l (iii) For the contents described in 5(b)(1)(iii) j l i 1! Total contents not to exceed 250 pounds, with the U-235 content ;b 1 not to exceed 5.0 kilograms. Four (4) steel drums containing not ) more than 1.3 kilograms U-235 each shall be packaged in the 1 f j shipping insert within the inner container as shown in Westinghouse l)t 3 f Electric Corporation Sketch SKA-252-1 and Drawing No. C7108010. 1! The steel drums shall be constructed in accordance with U.S. j!g li Military Standard MS 24347 with a maximum ID of 8.5" and a nominal I height of 15.4". ll
'g 1
(iv) For the contents described in 5(b)(1)(iv): f Total contents not to exceed 250 pounds, with the U-235 content
! not to exceed 4.0 kilograms. The contents shall be transported i T
in 9-3/4-inch diameter metal containers. Empty metal containers 5 1 1 will be used to make up the remaining space within the inner )
'E I container. .I 1
- l. (c) Fissile Class II and III f (1) Minimum transport index to be shown on h I label for Fissile Class II. !g I 't j, (i) For the contents described in 5(b)(1)(1): 3.6 >
I
! (ii) For the contents described in 5(b)(1)(ii),
1 5(b)(1)(iii),5(b)(l(iv): 0.5 l 1 F 3 (2) Maximum number of packages per shipment for F 1 Fissile Class III P b 1 l (i) For the contents described in 5(b)(1)(1): 30 {
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2 (ii) For the contents described in 5(b)(1)(ii), ,g 3 5(b)(1)(iii),5(b)(2)(iv): 200 1p p 1 B j 6. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 671.12. 1 1
![p Expiration date: September 30, 1987. j 1 7. 'y 1
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I wac ronu ma u.s. NUCLEAR REGULATORY COMMIS510N am, conomons (contuurew i lI
-l Page 4 - Certificate No. 5768 - Revision No. 7 - Docket No. 71-5768 '1 n
j il 1
! lI
;I l REFERENCES i l
l j i Babcock & Wilcox Company application dated January 29, 1982. th i Supplements dated: August 6 and 20, 1982. !p in
, FOR THE U.S. NUCLEAR REGULATORY COMMISSION [h l
-; !N
,I Charles E. MacDonald, Chief ;I Transportation Certification Branch 'I Division of Fuel Cycle and il l Material Safety, NMSS il Date: t SEP 0 61983
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st = = = = = = = = = = = = m m - - - - m int -- mm m . . . . . . . .. . . . . . . . .. . . . . . . . . . , I lg ss CERTIFICATE OF COMPLIANCE Ii 'o CrR " FOR RADIOACTIVE MATERIALS PACKAGES !N d PAGE NUMBER j b REVISION NUMBER C PACKAGE sOENTsHCATiON NUMBER e TOTAL NUMBER PAGES a CERTlHCATE NUMBER 5787 1 USA /5787/B( )F 1 2 2 PREAMBLE ll a Tnis cert.ncate is issued to cert.ey inat tne pacnaama and cor tenta descr. bed initem s eeio.. meets tn.appi,cabi. saeety standa rds sei forin .n ritie io. Code of .g rederai Reguistions. Part 71. Packaging of Radaoactive Matenats for Transport and Transportation of Radioactive Matenal under Certam Conditions
- j b This cert.f.cate does not rea, eve tne consignor from comphance itn any requirement of tna regulations of tn. U S Department of Transportation or otner appi cae reguiatory agencies. .nciuding ine governmeni of any country enrouan or into on.cn tne package .ai ne transported j)t i
it i {I i 3 THis CERTIFCATE iS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACK AGE DESIGN OR APPLICATION a PSEPARED By meme and Aww) b TITLE ANO IDENTIFICAflON OF REPORT OR APPL 4 CATION
,I Oak Ridge National Laboratory Safety Analysis Report for Packaging (SARP) of the l Post Office Box X Oak Ridge National Laboratory Shipping Cask D-38 )i l Oak Ridge, TN 37830 Report ORNL-5406, Rev. 1, August 7, 1981. lgp
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- c. oOCnET NUuBER 71-5787
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! a CONDITIONS l l Tnis cert >hcate is condit onal upon fulfdieng tne requirements of 10 CFR Part 71, as applicable, and tne conditions specified belo. 'I ll r!I f'{a) Packaging
. in l ggl (1) Model No.: D-38 !g l
)
l l (2) Description ll
; :l Packaging for fissile and large quantities of radioactive material contained il lg' in special form encapsulation. Plutoniun'is. doubly contained. The inner cavity of the cask is a 300 Series stainless steel Schedule 40 pipe with j!,
g, jgl inside dimensions 6-1/16 inches in diameter x 13-13/16 inches high. The !g 1 dl outer shell is a.300 Series stainless steel Schedule 30 pipe 20-1/2 inches ll
'd high. Shielding: consists of depleted uranium metal with a thickness of ;p I 2-3/4 inches .The top opening plug is held in place by eighteen,1/2-inch lll studs equippedTwith nuts. The plug is sealed with a Neoprene gasket. The
}:.
l cask is mounted on a 14-inch square x 5/8-inch thick base plate. Six of the studs are' extra long so that a protective shroud may be used during il i l g! g in gl transport. The cask is bolted with four,si-inch bolts to a 3-foot square ' i
'n dl pallet. The package gross' weight is'1,525. pounds.
El O' llI di I; (3) Drawings ' in
.i The cask is constructed in_accordance with Union Carbide Corporation, g! Nuclear Division; Oak Ridge National Laboratory Drawing Nos. ti-12133-CD-126E !g ld! Rev. 12 and M-12166-CD-022 Rev. 1. !p I I
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i 1p I; !I I !I t in di 'l I' lt I h p I, II ;,. 4 lh d' > I' > I 77 ( :. ' aI v , ,w w w w w w w w w w i d w w - - = = - = = w - w = - =r- - - - - - - - - - - - - - - = = - - + - - w'n l
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U.S. NUCLEAR REGULATORY COMMISSION lI (! +G NRC FORM 618A CONDmONS femtinued l'
!E Page 2 - Certificate No. 5737 - Revision No. 1 - Docket No. 71-5787 l-ll I:
l' 'I I! 5. (b) Contents I; i)n V l (1) Type and form of material (i) Solid radioactive material including U-235 encapsulated to meet h fl l l1! the requirements of special form radioactive material. (f '
'h lHl (ii) Solid radioactive material including U-233 and Pu-239 encapsulated !p 8: to meet the requirements of special form radioactive material; f plutonium bearing solid must have a second special form radioactive material encapsulation.
lh
,h f
(2) itaximum quantity of material per package ff The maximun internal heat not to exceed 80 watts; lt i
- h (i) For the material described in 5(b)(1)(i) the mass of U-235 not to il exceed 500 g.
(ii) For the material described in 5(b)(1)(ii) the mass of U-233 or Pu-239 not to exceed 350 g. (iii) For any combination of the materials described in 5(b)(1)(1) and 5(b)(1)(ii) the total combined mass of U-235, U-233, and Pu-239 not to exceed 350 g. i (c) Fissile Class 1
- 6. Special form capsule may be held within D0T Specification 2R containers within j;ig the cask cavity. !
l8 4 7. The package authorized by this certificate is hereby approved for use under the
.$ general license provisions of 10 CFR 571.12.
E ( 8. Expiration date: July 31, 1987. l REFERENCE i t gl Oak Ridge National Laboratory Report No. ORNL-5406, Rev.1, August 7,1981. E i 8 4 FOR THE U.S. NUCLEAR REGULATORY COMtilSSION l4 > Char es E. acDonald, Chief Transportation Certification Branch Division of Fuel Cycle and flaterial Safety, NMSS SEP 0 61983 late: i m 0 p amm.wr-x
i lA!_m_==_=X=l h 45==5=======M N 38!MMMMMMMM* N .M.MM.MNW
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! . CERTIFICATE OF COMPLIANCE N l '
I 'o CrR " FOR RADIOACTIVE MATERIALS PACKAGES D Revision NUV0ER c PACR AGE IDENt.F.CA rbON NUMtiER d PAGE NUMBER e TOT AL NUMBEH PAGES
. I a CERT 1HCATE NUMBER 1
5795 0 USA /5795/B( )F 1 3 i I k
. PREAMBLE a Tn s cert +cate is issued to certity that the paciaaging and contents described m item 5 beto* meets the appocabie sa'ety standards set fortn m Tetra io Code N:
iH g lg av rederal Regulations. Part 71. " Packaging of Radioactive Materiais for Transport and Transportation of Radioactive Material Under Certain Conations " E b Tn,s cert,s cue does not renew ine consignor trom compnance .rin any reufemeni of tne requianons o tne u s oepartment o# T,ansponanon or oener s l appocaeie reswoory agencies. ,nciudeg the go.ernment at any country enrougn or into nien ene pacsage ** be transpo,ied b h. ' li p. i "
'" ' ^" '
i I l ' '7'EEPIfES^ek'$.'*e*fd fM **** ' ^ "'" '"'*."'0"E A$o'"c'EOECAlS*8ke"OEOMA iCATION k.
! ' Oak Ridge National Laboratory Safety Analysis Report for Packaging (SARP) ); ;
i P.O. Box X of the Oak Ridge National Laboratory Foanglas b Oak Ridge, TN 37830 Shipping Container, ORNL-5407/R1, as ,bj supplemented. 71-5795 (t c OOCKET NdMBER - a CONDITIONS j This cerbficate is conditionat upon tutfrinng the requirements of to CF R Part 7 t as appncable, and the condit,ons specit,ed beinw ni : a s t
- (a) Packaging K 0
(1) ?!odel Nr.: ORNL Foamglas F j 0 l 1 f (2) Description [0 Packaging for fissile naterial. Contents are contained inside capped p polyethylene or stainless steel bottles which are positioned within 0 welded stainless steel product cans. Product cans are positioned in E 4 1/2-inch thick flanged containment vessel consisting of a 4.81 inch l I.D. x 18 inches long Schedule 80 stainless steel pipe (0.375-inch wall thickness) with a 1/4-inch thick welded bottom plate. The flange (4/ f l is sealed with a 1/8-inch thick x 5-inch I.D. x 10-inch 0.D. silicone p i gasket and 1/2-inch thick blind flange by 8-3/4-inch dianeter bolts. B i j ,; Void space inside the containment vessel nay be filled with crunpled B l aluminun foil. The containment vessel is centered and supported N l inside a 00T Specification 17H 55-gallon steek drun by solid foaned ( boron silicate glass (foanglas) and plywood discs. Drun closure is by .g a 12-gauge bolted closure ring with drop forged lugs, one of which is gf threaded and has a 5/8-inch steel bolt and lock nut. The package >
$ gross weight is 215 pounds. ,9
, 4 Dl (3) Drawings p l j The packaging is as shown in with Union Carbide Corporation Drawing No. fi-12165-CD-015-E, Rev. 3 and ORNL Drawing No.' 83-17092 with the
'N I top flange as shown in ORNL Drawing No. 83-17092.
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; L; IN.
lf (b) Contents [j 1[ (1) Type and fonn of material h)
's
[ F i Uraniun enriched to any degree in the U-235 isotope, U-233 isotope, I l{1 and as metal or oxide. The naximum H/V atonic ratio, considering all
@< sources of hydrogenous material within the product can fog oxides rust p i J' not exceed 3.0. Density must be greater than 4.45 g U/cn . Plutonium i 1 a s me tal . lgt 4
l)] I j (2) flaximum quantity of material pergpackage J l
-j 1
e ns h 2 l'tyjf, I The total contents not to exceed 15 pounds (6.8 kilograns) and the Pu 3 metal contents. not' to exceed 4.5 kilograms" and .,10 f watts decay heat. l !. g 3 ,}"'
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- ) (c) Fissile Class %
II and III [
;) t' 1; (
il3 (1) liinimum transport ,index to be 1 i '
' i shownvod: label for Class II 60.1 L i .j b ., ,jf '
l (2) itaximun number of : packages per , shipment for Class III / (g_: '., i> 1
,u ,
}3 1000 j
5. Plutonium must contain more Pu-240 than Pu-241. ?
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l 7. For nixtures of' uranium. isotopes identified in'5(b)(1),and licHted in 5(b)(2), y[ ' j l the sum of the ratios of' the contentjis > 1 nass limits must 'not exceed ' unity./ / otope; !1 ; mass % J,to,,their respective i> approved 'f
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] 8. Prior to each shipnent, the welded stainless steel! product',ca'n rust be le tested3using an ethylene glycol vacuumL test having'a sensitivity of 1x10-gk
't a tm-cn /s or better. The radioactive naterial must be, held in a capped polyethylene g(
j j I or stainless steel bottle . held in the welded stainless = steel product can, g 1 t i 1 9. The package authorized by this' certificate 1Nher$y approved for use under the L- ] j general license provisions of 10 CFR 671.12. ( l l10. Expiration date: April 30, 1990. i [ ' I 1 1 t l' I g: 1
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t ' COMoiTIONS (continued) 8'
.E 71-5795 l Page 3 - Certificate No. 5795 - Revision No. 0 - Docket No.
s 4 ,, 4 REFERENCES :b ' 1 4 U.S. Department of Energy application dated July 24, 1981. hl p 4 1 1 Supplement dated: September 13, 1984. 4: 4 FOR THE V.S. NUCLEAR REGULATORY C0!! MISSION , l _h! 1 1
. %8 dI m [
8 + U'" Charles'E. HacDonald Chief . l' (((' Transportation' Certification Branch Division of Fuel Cycle and
.fl'
'n 4 x(( liaterial Safety. NMSS lp 1 yf . ii i s '
- 8 i Date: APR 2 41985 e- I W
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1.m = = = =mm = = =pm# sci 4WaiiMWs =%A*3marmnenanenswynmunwtarmnuwm,unwrwrarte mynwnner C NRC FORJ sit L- +us CERTIFICATE OF COMPLIANCE U.S. NUCLEAR REGULATORY COMMISSION > lL. to Cr R " FOR RADIOACTIVE MATERIALS PACKAGES , t a CERflFICATE NUMt6ER D REYrSiON NUMBER c PACKAGE IDENisFICAt40N NUMBE R o PAGE NUMBEH e TO T AL NUMBE R PAGE S q 5796 9 USA /5796/B( ) 1 2 g PREAMBLE i a I This .ertshcate .s ssued to certify that ene packagmg and contents desc ribed in item 5 below meets the apphcable safety standaras set fortn in Titte to Code ' Of Fedefa: RegAations Part 71, ' Packageng of RaJioact.ve n,taterials for Transport and Transportation of Radioactive Material Under Certa.n Conditions ^
- b This certificate does not reheve the consignor from comphance w th any requiremer9 of the reguiahons of the U S Department of Transportation or other appucabee regulatory agencies enchadmg the government of any country througti or mto which the package will be tra.) sported e
F . 3 THis CERrep< ATE IS ISSUED ON THE bas.5 OF A SAF6TV ANALYSTS REPOR T OF THE PACK AGE CESIGN ON APPUCATION
& PREPARED BY rName sad adavess) e TITLE AND IDENTIFICATION OF REPORT OR APPUCATION *
$ Advanced Medical Systens, Inc. Advanced itedical Systens, Inc. application
! 1020 London Road dated February 26, 1982, as supplemented.
[ Cleveland, OH 44110 g i 71-5796 > [ c DOCKET NUuer.P f a coNOiTic+,s ' This certif*cate is conditiones upon fulfishng the requirerrects of 10 CFR Part 71, as apphcable. and the condit.oris specif.ed been* f5 t (a) Packaging s N y (1) itodel Nos.: 181375 and 181361 l (2) Description 5 Overpacks that provide impact and thermal protection for teletherapy ~ L head assemblies or source exchange assemblies. The cubical overpacks j consist of laminated 2 x 4 hardwood naple panels bolted together and - covered with 16 gauge steel panels. Reinforcing steel straps and angles are welded together and spaced to limit the openings between then to less than 6 inches. Skid runners are provided to facilitate fork lift usage. Dimensions of the Model No. 181375 are 43.5"L x 39.75"W x 41"H with a maxinun gross weight of 3,750 pounds. Dinensions - of the flodel No. 181361 are 39"L x 34.25"W x 44.5"H with a maximun gross weight of 4,000 pounds, i ; (3) Drawings I (1) The flodel No. 181375 packaging is constructed in accordance with ) Advanced liedical Syste , Inc. Drawing Nos. as specified in Section 1.3.1 (p 1- , of the application. f;p
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L (2) The tiodel No. 181361 packaging is constructed in accordance with !i. Advanced tiedical Systens, Inc. Drawing Nos. as specified in 9 Section 1.3.2 (p 1-9) of the application. :E
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CONotiloNS tcontsnuedi ft l; y i .Page 2 - Certificate No. 5796 - Revision No. 9 - Docket No. 71-5796 i: E, I} 5. (b) Contents i s' ql (1) Type and form of naterial B' (i) Cobalt 60 scaled sources that meet the requirements of special {, fonn radioactive material; or I (ii) Cesiun 137 in the fom of cesium chloride encapsulated in sealed g g sources that neet the requirements of special forn radioactive material or in sealed sources constructed s and inspected in accordancej with Picker Corpo.rationiletter ." dated January 4,1980. {l g fv ' 3 (2) Maxinum quantity of material per package ~ ' , fl (i) 13,650 curies of cobalt 60 with a radioactive decay heat load not to'ei'eed c 200 watts; or " - W" l A, N (,, , (ii) 2',200 curiesiof cesium 137 with.a> radioactive" decay heat load not j! l [to' exceedil7Lwatts. , _* /1 1 ( . g
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- 6. The packages authorized by this certificate are-hereby approved for use under the general license provisioiis(of 10tCFRil71.~12.
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;8 Expiration daten02Julyi31,1987tQ;, pa L3 - y ;e j v } %y< -
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p- d 'RNERkiCES v, n mwp u w . ,. Advanced Medical Systems, Inc.', appli.catio'n dated ' February 26, fl 982. jB
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'/ FOR THE U.S. NUCLEAR REGULATORY COMiilSSION
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> $Gu Char es E. MacDonald, Chief ;g Transportation Certification Branch lt Division of Fuel Cycle and il l Material Safety, ftiSS if j il Date: .AR 2 21984 li;II
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'0 C'" " CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES i . caans cart Nuveta e navisioN Nuueen c encaAce ieeunncanou muue.ta a cau Nuusa n . totat nuwee n caoss j 5797 4 USA /5797/B( )F 1 3
< eneaume a a rn,. ce,i,,,ar.
.. u.o io con.,, mai m. pac u o,ng ano cone.-r. ee.c,.o.o m ir.m s ooio.. me.iiin.appncao ..a .iv .ianoaro. .., vo,in ,n T,ie. io. Coo.
of Feoeral Aegulations Part 7t, Pacisagmg of Radioactwe Maienals toe Transport and Transportation of Radioactav. Materiai Under Cutaen Condittons " D a IN,5 Cert.ficat. do.5 *10t f.hev. In. con $sgoor from CompleanC. .*tn any reqwf. ment of in f.gulations of tne U S Department of Iransportation Of otner app,.cani. <%saro,, ag.nc , mciuo.no in. go..rnment on any cou n try mrouan o, into on.cn in. puug. ..u o. iran. con.o
- 8 1
- 7*.E'.",aTss7M%fJ" f ***'* ' ^ ''"*""'f?"e'f~'oTleOsc^fl5$$!!"l"36*AT'canou y U.S. Department of Energy Safety Analysis Report for Packaging: The t P.O. Box E ORNL HFIR Unirradiated Fuel Element Shipping
't Oak Ridge, TN 37830 Containers, ORNL/ENG/TM-9, November 1977, as 24 ;
8 amended. 4 71-5797 e occut ~uusen 2 e coNoirions
- 4 rr,. c.rtiv. cat.
cono,,,onai uoan eve,n.no en
.4 r.qu., ,n.nt, or ta crn pa., n as appi.cani.. .no m. cano, tion. .p.c.,,o n.io.
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- s (a) Packaging 4 (1) Model Nos.: '
4
'i , j Inner HFIR Unirradiated Fuel Element Shipping Container, and Outer HFIR Unirradiated Fuel Element Shipping Container d ,
i g (2) Description
,g l ir Packaging for unirradiated fissile radioactive material as fuel elements
$ for the High Flux Isotope Reactor (HFIR). The' container is a right j circular cylinder with an ll-gauge = carbon steel shell. Closure is !
g provided by 16, 3/8-inch diameter steel bolts which' attach the lid to g. the cylindrical steel shell. The steel .shell is filled with laminated Douglas fir plywood with a minimum thickness of 6 inches. A central cavity is formed in the plywood, and lined with a 1-inch thickness of
, polyetheylene foam.
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The packaging for the inner HFIR fuel element has overall dimensions of 25-inch OD by 45-inch high, a 10-7/8-inch diameter by 30-1/4-inch deep cavity, and a 660 pound gross weight. The packaging for the outer HFIR fuel element has overall dimensions ltp
!N R
j( of 31.5-inch OD x 45.75-inch high, a 17-3/8-inch diameter by 31-1/8-inch deep cavity, and a 1,050 pound gross weight. j!, d, r lu . i d ! i I !b I e si 't I; !N
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conotrious ccontmues> Page 2 - Certificate No. 5797 - Revision No. 4 - Docket No. 71-5797
- 5. (a) Packaging (Cont'd) ,
(3) Drawings l (i) The packaging for the inner HFIR fuel is constructed in accordance with Oak Ridge National Laboratory Drawing No. M-20978-EL-003, Rev. 6. (ii) The packaging for the outer HFIR fuel is constructed in accordance with Oak Ridge National Laboratory Drawing No M-20978-EL-002,
! Rev. 6. R{g (b) Contents p ,\, ' % (; gl ti s se -
'.q (1) Typa and {onn of material {
W . . g. Uranium as U 0 and clidjin difm-Al inum, 10-mils cernet, enriched thick, and: up to 93% in;the
- U-235 isoto l
3 uf O(N / . R (i) 4 orF~ the packaging described in'5(a)(3)(i) the contents are lt described in Oak RidgeJNational; Laboratory Drawing No. D-42118, i cRev. J.
,q , , ([ { \ y r.') } f
,j (ii) FFor the'. packaging" described 41rf 5(a)(3)(ii) the -contents are g (described 11n Oak Ridge 'Natio~nal-Laboratory Drawing No. D-42126, lg ,
~ ;b Rev. Gi { - !]j jl(
(2) Maxirda quankity f--mate al per pabkage. C,
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, 3 (i) FoKthe contents descr,ibed in 5(b)(1)(i) .not' more than 2.7 kg of y lp U-235.<p*_)
h (ii) For the contents described in 5(b)(1)(ii) not more than 6.9 kg of !b: U-235. .i z yt i , _ U -b- { (c) Fissile Class I f
!I:
Prior to delivery to a carrier for transport, the shipper shall ensure that at l ;' 6. 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 j@j package temperature shall not be less than 32*F along the shipping route. ;;
!I
- 7. The package authorized by this certificate is hereby approved for use under lI general license provisions of 10 CFR 971.12. J
, 8. Expiration date: October 31, 1989. l I i l I
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= l Lll _______________________ _ _ _ _ _ _ _u
hc= = = = = = =X= =_= = i -WTWENEWTENTWTT8f2f . .. ._ _ . _ ._ __ _ - T. 1 T T _. . lR!'
, l l' CONDITIONS (continued) fl iX; !
l-Page 3 - Certificate No. 5797 - Revision No. 4 - Docket No. 71-5797 I ' E. fl' REFERENCES I; I Oak Ridge National Laboratory Report No. ORNL/ENG/TM-9, Nov.1977. 4; 3 Supplements dated: July 31,1978; and September 17, 1979.
-1 j Department of Energy supplement dated: December 14, 1983.
1 pi 1 e FOR _THE U.S. NUCLEAR REGULATORY C0411SSION te 2 ..'>d. A L^. t u 4 . -s a /,j
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3 [ b Char' es E. MacDonald, Chief p; 1 s Transportation Certification Branch it' 4.' 1 Division of Fuel Cycle and h Material. Safety, MSS 1 NJ
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CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES D HEVissON NUMBER c PACKAGE IOLNitFiC AtION NUMBER d PAGE NOUf ER e YOT AL NUMBER PAGES 1 & CERTIFICATE NUU9ER 5805 13 USA /5805/B( ) 1 3 PAE AL tfLE a This certificate is issued to certif y tnat tne packag,ng and contents described in item 5 below. meets tne apphcabie safery standards se t forth m Title to. Code of Federal Regoiations Part 71. ' Pacsaging of Radioactive Materials for Transport and Transportation of Radcactive Material Under Certain Conditions " D Ints Certificate does not relieve the consegnor trorn comphance with any requirement of the regyfations of the U S Department of Transportation or other f apphCabee regulatory agencies. incluJeng the government of an) country through Or ento *fhCh the package well be transpvrted i b 7 Lk AND IDE #F CAT OF f APP CATION PAEPA E BYI A se t Chem-Nuclear Systems, Inc. application Chem-Nuclear Systems, Inc. 220 Stoneridge Drive dated April 29, 1982, as supplemented.
.i Columbia, SC 29210 g 71-5805 y c oOCut Nousta ,- _
4 CONDITIONS This certificate is cond teonal upon fulfsthng the requirernents of 10 CF R Part i1 as apphcable and the conditions specif.ed below s
- 6 (a) Packaging !
(1) Model No.: CNS 3-55 (2) Description - 4 The package is a steel-encased, lead-shielded cask with crushable g 4' impact limiters. The basic cask is a steel cylinder 133-3/4 inches y long by 50-1/2 inches in diameter with maximum cavity dimensions of n 36 inches in diameter by 116 inches long reduced to 111 inches by the R shield ring attached to the lid cover. Shielding is provided by
' b E
6 inches of chemical lead in the sides and closure base plate and q 5-1/4 inches in the closed end. j The outside steel encasement is made up of two,1/2-inch plates on the 't i sides and three plates totaling 2-5/8 inches on the end. The containment .6 , vessel is a 1/4-inch thick cylinder with a 1/2-inch end plate. The bi ! b shells are welded together with the lead shielding poured to fill the annular and end spaces, j
't ii 4 The removable, flanged and recessed base plate weldment consists of lg.
3/8-inch and 1-1/4-inch outside plates and a 5/8-inch inside plate. 't 6 The space between the plates is lead-filled. .b 4
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! l l- I;l Page 2 - Certificate No. 5805 - Revision No.13 - Docket No. 71-5805 lIl ik -
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' lI i g: 5 (a) Packaging (continued) l I !lg
'I '
j I (2) Description (continued) I
- I i l
f 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 silcone 0-rings. ll i i i I 'y l ( The cavity is penetrated by a vent line at the closed end and a drain Iu g I line through the base plate. The vent line is sealed by a gasketed I j [; and shielded plug. The drain line is sealed with a 25 psig relief {j
- valve. i >
CaskappendagesiciddMt , nh fftf'ng trunnions and two, 4-inch ll ll l' I removable tilting trunnions on the cask 1 sidet?} I t Removablefqp&J act limiters are provided at the casit; ends and at the llI I two, 8-inch-trunnions. The fonner consist of a ' series of 6-inch j/ l f' diameter closed-end tubes. Each impact limiterJhas" tubes approximately ) !l g! 6 inchesQong bro 0nd x the end periphery. The closurefend impact limiter l I has 12 tubes, sixiabout 6 inches long an,d7 sit about two inches long, ~ !gl i l' around;th'e sides. lethe]sclosed:endT i mpict(ljmiter hastsix tubes about l' acts'asflIthe t } j l; 6 inches!long impact 4jmiter. "
. arousdithe['sidesk
{ p 4\ A gass'ekedttube U ; 6 Y}x N ll l L The cas(is secured' hor zontaljy 1^ / skid which,,is motmted to the 2 !g e lg ) I transport vehi,cle,for'shi '^ i sunshade *is 'providdd. ;l i I, m -m - l H s pp
.,:a il j The gros Weight N$the ' ei lI i l! approxim[ately 70,000fpoundsy,;7De(ege sk d%ighs aboup4',200 edinghthe pounds. skidfand l
- 1 6 's u (j,uCQ f CQ (3) Drawings Y gyp \
g
- 4 The packaging ifconstructed in accordance with Chem-Nuclear Systems, I
- Inc. Drawing Nos ti MODS 100, Rev. J; C-111-D-0001, Rev. 0; and C-lll-E- I 1
[(E ll 0002, Rev 0; and ATCot-DrasingtNosh 1WD 139-1, Rev. K; MOD 140, Rev. C; MOD 124, Rev. 0; 0999-M7,ritev. G; 0999-C-08, Rev. G; and 1000-D-0024-0 Rev. O. l g . I I; I l (b) Contents b ! I (1) Type and fann of material llli 'I> l r ! I: Irradiated metal components packaged in secondary containers. l g i 1[ g j li (2) Maximum quantity of material per package I l-1 i i Package internal decay heat load not to exceed 250 watts. i l l' i I I I I: I , If I I E8 I I! I L-------------_.=___=_-------__J
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CONotT1oNS (contmued) i , Page 3 - Certificate No. 5805 - Revision No.13 - Docket No. 71-5805 y
- 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. t J (b) Except for close fitting items, shoring must be placed between contents, J secondary container and cask cavity to minimize secondary impacts due to ( l accident sequence. [ (c) The maximun gross weight of the contents, secondary container and shoring h is limited to 9,220 pounds. M)t l
- 7. Prior to each shipment, the silicone 0-ring seals (base plate and vent plug) {
must be inspected, the seals must be replaced 2with new seals if inspection shows f any defects or every six (6) isonths','whichever 0cc0rs first. q
- -
- q
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i Prior to delivery of the' package to a carrier for transport, the package containment tl
- 8. 1 be leak tested. The sensitivity of the test.shall be at least 1 x 1
cavjty 10~ a tmshal}/sec cm (ST(). , j The packaging containment cavity shall be leak tested initially and at least Il ~ ive..(12) months'. The sensitivity of the test shall be at least 1 ll once q x 10~"gvery twg/sec (STP).
~
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- 9. The package authorized by this certificate +is hereby approved for use under the [
g' general licensesprovisions of 10 CFR 671.12. Fabrication of additional packagings af ter December 31, 1983 is not fauthorized. E
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- 10. Expiration date: December. 31, 1938. L:
I' -REFERENCES K l' L 1 Chem-Nuclear Systens, Inc.~ application dated April 29, 1982. t Supplements dated: October 21 and November 16, 1983; and June 12, 1984. p FOR THE U.S. NUCLEAR REGULATORY COMfilSSION f
't:
E i ig h be. acDonald, hief 5 j Charles . Transportation Certification Branch :g l Division of Fuel Cycle and !g Material Safety, NMSS lt l Date: JUN 131984 g}' i ,
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i m _.rmw < w_wr.r w.r_.rg,.r_ w rw_.r rm_ g.r.r.r r.r. w_ _ _ re,.r r_ _ _ _ _r r _ _ _ - . __ . _ _ _ __ __ --~.- - -_
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- C'" " CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MNiERIALS PACKAGES i i a CERT 4 CA7E NUMBER O HEVISiON NUVBER C PACK ALd IDtNTWICAt:ON NUMBER G FAGE NUMBER e YOT AL NUMBER PAGE S b 5814 3 USA /5814/B( )F 1 4 2 PREAMBLE 1% a This certit. cat. es essuco to certrty that the packaging ano contents oescribed en item 5 below, meets tne appiecable satety stanoaros set fortn m Titie 10 Cooe
[q oe reoew negsat.ons. Part ri. eackaging or nao.oacew. uarer ais for Transport ano Transportation of nao.oact .. uaieriai unoer certa +n cono,t.ons ~ . !4 o Tn.s cei.tica,. ooes nct re se in. cons,anor eron come ance .an any reau r. ment oe in. reewanons oe in u s oepanment or transponat.on or otner
- lH appi cacie regsatory agenc es .ncioo,ng ine governmeni of any couniry inrougn or .nio wn.cn in. pacang. ..ii be transported ll , i
, I&
; ' a '-'a::3,7,m"="'"c"""'~~;'x:::::::=r*=" :;. ,'c,,,oN U.S. Department of Energy Safety Analysis for Radioactive Material Division of Naval Reactors Shipping Cask flRBK-41s 42 and 43 dated Washington, DC 20585 tia rch 11, 1963 as supplemented. -f
, , , _ 71-5814 ~
a CCNoitioNs This Certiftca?9 as COndit'Onal 6.pon fulfdhr'g tne requirernents et to CFR Part 7 , as apphcable, and tne conoitions Spec.f.ed benow (a) Packaging
$8 (1) Model Nos.: NRBK-41, NR8K-42 and NRBK-43
- (2) ~ Description 3
- Top loading cylindrical lead shielded 304L stainless steel clad casks '
for the shipaent of irradiated test specimens. Casks have a one-inch thick stainless steel plate integral skid welded to the body. In addition, they have bolted on, all welded, 48-inch square "I" bean l, skids utilized to distribute the cask load. The cavity of the casks are fomed by 1/4-inch thick stainless steel surrounded by poured lead shielding with a 1/2-inch thick stainless steel cylindrical sheet '
, obter shell. In addition tiodel No. NRBK-43 cask has a seal welded 1/4-inch thick stainless steel outer themal shield with a 1/16-inch air gap between the prinary and secondary outer shield. The physical characteristics of the cask are as follows:
R: fF . W W N Y l A f 5 , s: f'f; *r a>! l3 i Il a w,a,ra w w w w w w w w w - - a,ere tra w w w,ar c .re w w,,,r,are w w w ,.r,,c,ec,,r, w,,c,,,w; m m m
~- _. __ . . _ . _ . - - . . . . .. -. .. ... . . - - - _.
i ' m u m m mm n as h a m m m ms'e m mm m m m m m m m m Ma s u m mEM~i m a miiss n a m m a sh s m &q ll p , ' CONDITIONS (contonued) , Page 2 - Certificate No. 5814 - Revision No. 3 - Docket No. 71-5814 j lhl l
'B
- 5. (a)(2) Description (continued)
NRBK-41 NRRK-42 NR8K-43 flodel No.
! Outer Dimensions 26.5 21.5 21.5 ,
' Diameter, in Height, in 39 24 41 g Cavity Dimensions fI
~
8 8 Diameter, in 5 . 9 27 j Length, in 16
' Approx. Loaded 6,000 tleight, lbs 9,000 3,500 p
Lead Shielding
' Thickness, in 10 6_ 6 )
} 41-0001, Sh.1, 42-0001, Sh.1, 43-0001, Sh. 1, Reference Rev. B and j J Drawings Nos. Rev. A and . Rev. A and Sh. 2, Sh. 2, Sh. 2, g (Battelle tienorial Rev. B, of'2. .Rev. C, of 2. Rev. A, of 2. Ins ti tute) X(
- 5. (a)(3) Product Containers The contents of the package.nust:be. packaged in inner product containers.
t The inner product containers are constructed in accordance with the following y
- p i tJestinghouse Electric Corporation Drawing .Nos.:
lh Product Container Drawing Nos. IN-41 971D207, Rev. 3 and 9710201, Rev. 4 l . 971D207, Rev. 3 and 971D201, Rev. 4 g IN-42 IN-43 9710207, Rev. 3 and 971D201, Rev. 4 IN-43 tielba 954F098, Rev. 4 and 904E122, Rev. 2 , PR 979C200, Rev. 2 ,, PS 979C106, Rev. 2
> WPS 979C140, Rev. 2 979Cl45, Rev. 2 f'
i T !gW
! ZT 979Cl43, Rev. 3 '
Z 979C155, Rev. 1 l ~ ZZ 979C144, Rev. 1 i 1- i
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is - m _- = = = = = = =~A = = = = =_ _ -__
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CoNolTioNS tcon*onued) I lI ' Page 3 - Certificate No. 5814 - Revision No. 3 - Docket No. 71-5814 l ' li is '
- 5. (b) Contents iR l4. (1) Type and fom of material tii Byproduct and special nuclear material contained within product containers listed below. The contents shall be dry and unnoderated (H to X y l4t atonic ratio 2) unless specically authorized for the product container. '
lg I Model No. Product Container Nos. t*l NRB K-41 IN-41, P_R, PS, WPS, T, ZT, Z, and ZZ ( %, C H r- (,.8 .
, t NRB K-42
, N '- SIN-42'a nd 'PR l/ f -
- t. ,
NRBK-43 '! IN-43, IN-43-Melba ! ,PR, PS, WPS, T, ; i
,'J
' ZT, Z, and ZZ -
c.~ '/. (2) flaximun,. quantity of material per package 1 ' The fi!!sile contentiof the cask shall 'b limited to a naximun of 350 equivalen' t grans ofell-235. The, number?of; equivalent grams of U-235 is determined by the;eq'u' a tion: -1.0"x gra'ns U-235 + 1.4'x. grams U-233 + 1.6 x' grams plutoniun; / The maximun decay, heat load 'per package shall not exceed those listed' below; ~~" /- - Nu . ;,, T : ..- I flodel ' No . 'Haximum Decay Heat Load 7 0,i4::s: NRB K-41" ~ G 3(84,00
;, - Btu /HR,,
<9 NRB K-4? ,s 2100 Btu /Hr'
.s c s_
* 'i <
NRB K-43 -7500 Btu /Hr s
', y, (c) Fissile Class II j
tiinimun transport index to be'shown'on label-3.2 )
- 6. il The "IN-41" product container may also be used to ship NaK filled capsules l i provided the following specifications and restrictions are met.
l{> l l i (1) The NaK filled capsules shall be placed into a steel or stainless steel container with walls at least 1/4-inch thick, a welded closure on one end lg i l and a pipe cap on the other end. ' lt
,8 l l (ii) The NaK filled capsules shall fit within the container with a maximum play il t
of 1/2 inch in any direction. Inner fixtures may be used to provide the indicated degree of sr.agness. The capsules and container must be thoroughly j i l dry prior to loading. Is n h
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_ _ _ _ _ _ . . _ . _ _ _ _ _ . _ _ _ _ ~ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ CoNoliloNS (continued) Page 4 - Certificate No. 5814 - Revision No. 3 - Docket No. 71-5814 (iii) Suitable pipe sealing compound shall be placed on the threads of the container top closure prior to tightening the closure. (iv) The sealed container shall be placed into an "IN-41" product container with - a maximum play of 1/2 inch in any direction. Inner fixtures may be used to N provide the indicated degree of snugess. Both containers must he thoroughly dry prior to loading. (v) The maximun volume of NaK in the NRBK-41 cask and associated inner container shall be 50 cc. g te 4
- 7. Expiration date: April 30,1988.
-' ' REFERENCES E
' E; j
g* Safety Analysis for Radiative flaterial Shipping Cask No. NRBK-41, 42 and 43 dated (,, 1 fia rch 11, 1968. Supplenents: Division of Naval ~. Reactors letters S# 1458; dated June 19, 1968, S# 1570; dated September,19,1968,' S# 1597; dated September 19,1968, S# 1658; dated October 22,1968, Sf 1681; dated November 7,1968, S# 1690; dated November 22, 1968, fp 1 S# 1903; dated flarch 19,1969, S# 2000; dated June 2,1969 and S# 2509; dated June 10, 1970 and Bettis Atonic Power Laboratory letter.tlAPD-CL(IH)-733, dated October 10, 1968, and Division of Naval' Reactors letter Zf 85-1605, dated April 1, 1985. f FOR THE U.S. NUCLEAR REGULATORY C0ftMISSION ' w e Charles E. MacDonald, Chief g Transportation Certification Branch I Division of Fuel Cycle and i ,
- ftaterial Safety, NtSS 'lg APR 2 9 sang 3q 1 Date:
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I' lb i I! nac ronu sie I; ..u, CERTIFICATE OF COMPLIANCE U.S. NUCLEAR REGULATORY COM
'o CFR T' li FOR RADIOACTIVE MATERIALS PACKAGES .h ki e REvis#ON NUMBER c PACKAGE lOENilF.CAf TON NUMBtR d PAGE NUMBER h ,. CtRTrFicATE 5828 NuusER 3 USA /5828/B( )F 1 e TOT 2 AL NUM I i PaEAustE ll
. .uu.o io c.n.tr in.iin. p.ck.ging no content. o.scr.o.o initem s d.io.. meeti tn. .pphc.di. ..e.tv .i.no.ro. i eortn m riti. io. coo. oe p l'g . in.. c.n.t.c.
r.o.r.i n.gs.tions. part ri e.ca.g.na of n o.o.ctive u.teriari for Transport no Transportation ce n.a.o.ctive water i uno.r c.ri..n cono,t ons - ' I- e in s cert t. cat. oo.. not r ... in. con..onor trom corr ph nce -itn .nv requer.m.ni of in regui.t.ons o'in. u s o.p.nment ce Tr nsponstion or ein., , Il .pphe.o.. r.gu iory g.nc .. inciuo.no in. gov.mment o' .ar country inrouan or 'nto *n'ch tn* pack.a. *l'8 be tr.asport'o - I k I I ! 3 THiS CERYtFtCAff
. PREPARED rS ISSUED.ON BY rhome.ad J&ess TM BAS.S OF A SAFETV ANALYSIS t, TITLE AND REPORT IDENiaFICAYtON OF THE OF REPORT OR PACK AGE DESIGN OR APPLICATtON APPLICATION
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g Los Alamos Scientific Laboratory " Safety Analysis Report for the TREAT Capsule i n ej University of California Assembly Shipping Container," Report flo. lt l' Los Alanos, NM 87545 LA-6606-MS, December 1976. ;b I! I;
,b I! 71-5828 '>
e oOCnET NUweER u l . CONDITIONS I This certi'.c.i. . conoition. upon tu:tanno tn. requw.m.nts at to cF M Peri 7t. .s apphc bi.. ano in. conditions specified below ')
)
1 f: I,
' (a) Packaging j ll (1) Model No.: TREAT !
l~ I! d; (2) Description ' l'i Packaging for TREAT capsule assemblies. The inner container is a 1-g g inch thick plywood box; covered with 14-gage steel sheet; with an interior "T" bean; and 0.020-inch cadmium . lining on the top, botton, i lfl and on each side of the central divider; and a hinged cover. An outer I: container consists of two cylindrical metal tubes, separated by 3 inches of phenolic foan, and a support assembly -for the inner container. I l The outer container is held within a netal truss framework. The gl. g I; package gross weight is 1,800 lbs. l8}
'p I: (3) Drawings '
'p; I; 'n '
1: The packaging is as shown in Figures 2, 4, 5 and 6 of Los Alamos b I ( Report tio. LA-6606-MS, December 1976. ;j ! r !, 1: !B I !N d; p d; t) I i ( :] (i g di N. Ei , s l t 14 N ;b 4 l $l I; R !' 1; ! l R: - n w w w w w w v sgw wmxinss11.:aciMiV1wmir w1fammmwxWw wxnwssm xx= = =i , -=w l 1
p___________________.-___________m _____________________. l y mac roam sisa gl * *M CONDmONS (continued u.s. NUCLEAR REOULAToRY COMMISSION j fy i .g 1 71-5828 lg i Page 2 - Certificate No. 5828 - Revision No. 3 - Docket No. .i h I l !I hl I
- 5. (b) Contents :p l
(1) Type and form of material ] f +
!g li J; (i) Fast reactor fuel pin contains plutonium which is hermetically 1, 3 sealed in 316 stainless steel thin wall tube which is further Ihl It encapsulated in a 1.125 OD, 316 stainless steel with welded or '
brazed end caps and contained within a 3-inch OD by 1/4-inch ji -j l thick wall steel pipe. The capsule assembly is as shown in l{B t, Figures 1 and 3 of Los Alamos Report No. LA-6606-MS, December lg 1 1 1976; or !g 1 (ii) Unirradiated ORNL-0RR shim rod assembly containing uranium enriched ll 1 U-235 isotope within aluminum plates. Ig (2) Maximum quantity of material per package ,
]
1] i li g 1 1; (i) For the contents described in 5(b)(1)(1): g; Not more than two (2) fast reactor fuel pins. Fissile material ll' j not to exceed 60 grams per cm over package length. Total plutonium i gi g or other fiss?'e material not to exceed 2.1 kg. )l (ii) For the contents described in 5(6)(1)(11): .3 1 Not more than two (2) assemblies. Fissile material not to exceed A f 7 grams ~ per cm over package length. Total U-235 not to exceed R I 4 350 grams. li y y! 1 (c) Fissile Class I f:g, 1, l The package authorized by this certificate is hereby approved for use under the 1 6. general license provisions of 10 CFR 971.12. ljl jl
- 7. Expiration date: October 31, 1987. fj 1( t y
1 REFERENCES 1 @u l l
" Safety Analysis Report for the TREAT Capsule Assembly Shipping Container," Los ;{E f3 1 Alamos Scientific Laboratory Report No. LA-6606-MS, December 1976.
Department of Energy, HQ supplement dated: April 7,1983. gf 1 g FOR THE U.S. NUCLEAR REGULATORY COMMISSION 1 L l 1 g; ' 3 Charles E. MacDonald, Chief p, i-g 1 Transportation Certification Branch 1 Division of Fuel Cycle and ti i Material Safety, ft!SS Li , 4ll' h j SEP 0 61983 -
.n, pl j Date:
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$3 %NNN_NANM'MNi . _ _ _
P4RC FORM 618
+= U.S. NUCLEAR REGULATORY COMMISSION 1 S C'" " CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES 1 a CERTIFtCATE NvuBEH tp REVISION NUMBER C PACK AGE IDENTIFtCATION NUMBER e TOT AL NUMBEsq PAGES :
d PAGE NUMBER 5830 4 USA /5830/E:( ) 1 2 PAEAMBLE a This Certrficate es issued to certif y that the packagtng and Contents described in item $ beloe. meets the apphCable safety standards set forth in Titae 10. Code ( of Federal Regalations, Part 71. ' Pachaging of Radeoactive Matena's for Transport and Transportation of Radioactive Matenal Under Certain Condations " l! O Tnis certificate does r.
- reheve the consignor from compharice with any requirement of tne regulations of the U S Department of Transportation or other
!! apphCabte regulatory agenCaes. encludtng the government of any Country through or into which the package n H be transported 4
' 3 THis CERTIFICATE IS ISSUED ON THE BAS;$ OF A SAFETY ANALYSTS HEPORT OF THE PACKAGE DESIGN OR APPLICATION i a PREPARED BY e%ame amt Addvsst t) TITLE AND sOENTiflCATION OF REPORT OR APPLtCATION -
l Department of the Navy Minnesota Mining and Manufacturing Company Naval Support Force Antarctica application dated June 28, 1968. FP0 San Francisco, CA 96601 gi 71-5830 M c DOCKEi NUMBE$1 e 4 CONOiTIONS Tfus certificate es conditional upon fulfilhng the requirernents of 10 CFR Part 71 as apphcable, and the conditions specified below 5 (a) Packaging (1) Model No.: SNAP 21 (2) Description A themoelectric generator 16 inches in diameter by 30 inches long packaged in a right circular metal protective enclosure 52 inches in dianeter by 68 inches high. Main components of the generator consist of an outer Berylco-165 housing with flange; U-8 Mo shielding; themal insulation; themoelectric modules; and the heat source. Total weight of the package is 1,900 pounds. (3) Drawings The SNAP 21 is constructed in accordance with Minnesota Mining and Manufacturing Company Drawing No. B-SK-37-4014 and Drawings included ;g in 3M Report No. MMM-3691-33.
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' '^ ,g CONolTioNs (continued)
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Page 2 - Certificate No. 5830 - Revision No. 4 - Docket No. 71-5830 f
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- 5. (b) Contents '
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(1) Type and fom of material I l Strontium 90 titanate pellets doubly encapsulated by a thin inner liner and a 0.2-inch thick Hastelloy C primary containment capsule which meets the requirements of special form radioactive material. (2) Maximun quantity of material per package 33,000 ci a p 1- , 4
<- Q,l'i A C U f f
- 6. The package authorized bysthis' certificate is hereby, approved for use under the general license provisions ~'of 10 CFR $71.12.
m
- 7. Expiration date: Jul )31,1990.
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f i . .p -s REFERENCE f, '[' " ; ! f,
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Minnesota Mining and:Manuf acturing Company applic'ati,on dated June ~28,1968. f't IK N 3, ._ ,_ c_. a , ,, .
^(^ FOR THE U.S;" NUCLEAR REGULATORY COMMISSION R l ' }~ w E
l fn r a % :-) ; . 3,, ,
.E lk 0/ ..r, g,t t. ) t 0 .
Charles E. MacDonald, Chief Y N.
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,', ..' Transportation' Certification Branch i
->' Division-of Fuel Cycle and j-r js Material Safety, fMSS y Date: MO2E ;_ , ,
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i; II: !lI l lR; 'l ! I I I I t I d' 97 I I! I l' I f_f_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . , _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
p--------#==- _=ca- =2..am_a_m.* M Jra w r z T srsra v a a 4 U NRC FORM sis U.S. NUCLEAR REGULATORY COMMISS: N cas CERTIFICATE OF COMPLIANCE 7N ) I io CFR n FOR RADIOACTIVE MATERIALS PACKAGES I' i a CERTinCATE NUMBER D REvtSiON NUMBER c PACKAGE IDENtlelCATION NUMBER d PAGE NUMBER e TOT A '. NUMBER PAGE S q 5862 4 USA /5862/B( ) 1 2 E PREAueLE p' a Tnis cenincare i ...ueo to certify inat tne pacmaging ano contents oescrioeo in iiem s oeio.. meets ine apphc oie safety stanoaros sei fortn in Titie io. cooe ll of Feoeral Regulations. Part 7t. Packaging ano Transportation of Raoioactive Material" ; l D Tnis certificate ooes not reheve tne consignor from comphance .itn any requirement of tne regulations of tne U S. Department of Transportation or otner I; apphcame ressatory ag.ncies. inciuoing tne government of any couniry tnrougn or into nien ene pacmage iii de iransporteo , i i lll i 3 THIS CERTIFICATE iS ISSUED ON THE BAS.S OF A SAFETY AfwALYSIS REPORT OF THE PACKAGE DESsGN OR AP*LICATION Mi a ISSut0 To meme omf Meess# b TITLE AND IDENTIFICATION OF REPORT OR APPUCAT60N i 4' i g! Teledyne Energy Systems Teledyne Energy Systems application dated ,b Nl 110 West Timonium Road June 26, 1985, as supplemented. {h Il Timonium, MD 21093 ;8 1-I! lEb I! c. OOC =ET Nuusta 71-5862 il l N i a CONOiTIONS i I! Tnis certificate is conoitional upon fuitrahng tne requirements of to CFR Part 71. as apphcable, and tne conditions specified belo. ! I, I N: s i Ii W I (a) Packagi ng ;p Ij; i lil' (1) Model No.: Sentinel-100F I N I !i g (2) Description N y i l llll The. package, a Lthermoelectric generator, is 45.5 inches in height with I l a base diameter of 24.5 inches (excluding mounting pads), and weighs I lli approximately 2,600 pounds' The components include a Tungsten biological I l1 shield (10.705" x 13.837" 00) which is within .the aluminum (6061) l g i outer protective housing. ; Four 6061-T6 mounting pads at the base of p g, u.:e aluminum housing provide the shipping pallet attachment points. p 1: " h Il (3) Drawings , l 1: n l [ The packaging is constructed in accortlance with the following Isotopes, l Inc. Drawing Nos.: 1: 010F10000 Sheets 1-3 (Rev. C), Generator Assembly Sentinel 100F h I! 010-20000 Sheets .1-2 (Rev. B), Fuel Capsule Assembly a ll 010-70003 (Rev. A) Shield Body i I 010-70004 Shield Plug- I l , f p 001-90064 Sheets 1-2 (Rev. A), Shipping Crate Sentinel RTG 001-90039 Sheets 1-2 (Rev. J), Sheet 3 (Rev. H), and Sheet 4, l i ll Pallet Assembly i I I l 1 l l l l 1 l 1 , I ' l I i I I I I I 99 I l l l
E 2*'P 5 m':m^.--@_ - . . - AL-A AL. 2% L .X
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- M K @P M K M -
CONDITIONS (contanoed) Page 2 - Certificate No. 5862 - Revision No. 4 - Docket No. 71-5862 .R
>l >
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- 5. (b) Contents (1) Type and fonn of naterial Strontium 90 titanate doubly encapsulated in a stainless steel liner and Hastelloy or Uniloy HC capsule which neet the requirements of special radioactive material.
p (2) ,ttaxinun quantity of naterial per package f i 370,000 curies.. W! hj
- 6. Fabrication of additional packagings is not authorized, h' 7. The package authorized' by this certificate is hereby approved for use under the f y
' general license provisions of 10 CFR 671.12. E.
;p!
- 8. Expiration date: .Septen'ber 30, 1990. .9)
- 3 P
REFERENCES 4
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E: H
.y Teledyne Energy Systems appl'ication dated Dune 26l[1985. tj
^ '
Supplement dated: August 30,11985. .; ., y .
;x* . .
FOR THE"U.S. t4UCLEAR REGULATORY C0t1PISSION
>\
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J, Char es . flac ona , C ef Transpo'rtation Certification Branch !l Division of Fuel Cycle and d
- y Material Safety, fitSS i
SEP 3 01985 ltI
,W Date:
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""5N sa " ^"" " * * " '
j ; to crR n CERTIFICATE OF COMPLIANCE
' FOR RADIOACTIVE MATERIALS PACKAGES t a cERTwsCATE NUMBER e REVISICN NUMBER c FACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES '
5874 4 USA /5874/B( )F 1 3
/ PRE AMBLE a
This certificate is issued to certrfy that tne packagang and contents descarbed in item 5 belon. meets the applicable safet y stancards set forth in Tatle 10. Code of Federal Regulaf.oris. Part 71 ' Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions " b This Cef tsfsate does not rebewe the consignor from Comphance with any requirement of the regulations of the U.S Department of Transportation or otner apphCaDie regulatory Agencies encluding the governr9ent of any Country thfough or snto which the package will be transported
, a PREPA E SYr at Ae ss b i E AND t il C EPOR O AP ICATION Department of Energy Safety Analysis for Radioactive Material Division of Naval Reactors Shipping Cask No. WAPD-40 dated Washington, DC 20585 December 1984, as supplemented.
;h s
71-5874 c DOCKET NUSABER a COND4TIONS . This certificate is coredrtional upon fulfishng t*4 requrernents of 10 CFR Part it, as apphcable. and tf'e conditions specified below (a) Packaging (1) Model No.: WAPD-40 (2) Description The WAPD-40 shipping container is a cylindrical, stainless steel clad, lead shielded, shipping container used to ship irradiated fuel and non-fuel test specimens._ The container has an outer 304L stainless h steel shell 1/2-inch thick and an: inner' 304L stainle'ss steel shell 1/4-inch thick..with 10 inches of lead between the shells. The overall size of the container, including an integral-skid, is 24 inches in i diameter by 168 inches in length. Gross weight (including skid) of the container is approximately 27,500 pounds. The heat removal capacity is approximately 2000 BTU / hour. The cylindrical inner cavity is 2 inches in diameter and 135~1nches in length. . Stainless steel clad, i , lead shielded end plugs bolt into each end._ One-half inch thick plates are bolted over the end plugs to provide a total end plug flange thickness of 1.0 inch for puncture resistance. Metallic, i pressure-filled 0-rings between the~ end plugs and the container seal lli the package. A special holddown cradle is used during truck shipments. lH This cradle weighs approximately 5,000 pounds. (3) Drawings {
; 5
' The WAPD-40 cask is fabricated in accordance with Westinghouse Assembly !N
' Drawing Nos. 936F577, Rev.11; and 936F578, Sheet 1, Rev. 9, and Sheet 2, Rev. 4.
jlN 1 5 E 5 i' I lg.' l N h l I! I r N in l! 100 N
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mamuamKKKEa Ximum ~ - - -
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CONDITtoNS (controued) Page 2 - Certificate No. 5874 - Revision No. 4 - Docket No. 71-5874
- 5. (b) Contents (1) Type and fo~m of material Byproduct and special nuclear material contained within inner product containers. The contents must be dry and unmoderated (H to X atomic ratio ( 2).
(2) Maximum quantity of material per package is: The fissile content of the cask must be limited to a maximum of 350 equivalent grams of U-235. rThe-number of equivalent grams of U-235 is determined by the ceqEa, tion: 8 'l!0 'x; grams U-235 + 1.4 x grams U-233 + >B! 1.6 x grams plut, onium. "( , [ (c) Fissile Class 11- f$ h .'2 :Wl flinimum transport index to be shown on label " I Q s?s flaximum decay heat per packa.ge rust not exceed.2,000:BTV/hr. 6. W $$ ' -
- / J: . 'T As needed, shor'ing must be= used to limit' movement of contents -under accident I{l g;
- 7. '
conditions of4gransport. ?ffi
> q q 34 ;
q \{ , E V
- 8. The lif ting trunnions rust be? cove. red during transport ~ to preclude their use as h]
h tie-down devices;. xW 3p, 154{ A qw;iIss l{ 9jV
, D E 2
The contents of the co'ntA~ineY must:IE $libit'ed so that-the maximum measured gamma
- 9. 7 dose rate (above-background)lonithe'si'desof;th'e cask for nomal conditions does not exceed the valu'e defined by C o 3-
=' (1000.A N )/F.T y c. :
f]!
'f E,
Ej
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where C the maximtIm pemissible'gama) dose rase on the side h 3 = of the caskein, mrem / hour for nomal conditions, gj El
/ .
N 00.0 mrem / hour for shipments of airradiated sturctural ;K A = materials and 37.0 nrem/ hour [for: shipments of irradiated
.N N
fuel. j H F = factor obtained directly from Table 1 or Table 2 (attached).
. t.
- p
! For non-fuel whose principal isotope is not included in Table 1, an F factor must be determined based on calculated ratios of the limiting accident radiation H l levels to the nomal condition radiation levels for each of the principal isotopes. j For U 233 with approximately 30,000 hours of effective full power oggation and j greater than 17,520 hours of decay, the F factors in Table 2 for U are ;I
,1 conservative and may be used.
!I I
ll The maximum measured neutron level dose rate on the side of the cask must not j i f exceed 10.7 mrem / hour for nomal conditions. n 1 i l Bj i i n i 101 s? mmJln l
m KRsTAN%NNTEWftEftL*S?SSE?ER*L'tL*Eff6% CONDITIONS (contonued) Page 3 - Certificate No. 5874 - Revision No. 4 - Docket No. 71-5874 ! O y
- 9. Continued For mixed shipments of fuel and irradiated non-fuel, the more limiting C3 value must be employed. ,
If C sis below the maximum measurable level of the gamma instrument, other methods (e.g., thermal luminescent detectors, source strength calculations) must be employed to estimate the expected level for comparison with C3 .
- 10. The acceptance tests and naintenance program must be in accordance with Chapter 8.0 to WAPD-RE0(C)-270, Rev. 3.
i - s
- 11. Expiration date: May 31, 1990.2a ' L]' 'C"A(2 ,1 REFERENCES
. J r Safety Analysis for Radioactive Material Shipping Cask No. NRBK-40 dated December 1984 (WAPD-RE0(C)-270, through Rev. No. 4). ~ "
og '. ,
,3 Naval Reactors supplement dated:C July 3, 1985 (S#85-1328).
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{(i , FOR THE U .SilNUCLEAR REGULATORY COMMISSION [ -
;, e' ' - -' ; l < ' .
cf p } (( pg7p - [ C, 's .' , ) Ch a , C fe !
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' #Transpo'rtation" Certification Branch
, ' Division of Fuel CycleTand
~f ; Material' Safety, NMSS' .
i, s < Date: R 25135 Pc ~ J. "
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Attachment to USA /5874/B( )F Rev. 4 Page 1 Table 1 F Factors 1 For Use in Formula Cg = (INA )/F For Irradiated Structural Material Shipmmts by Principal Isotope Energy and Yield Factor Isotcpe MeV (s/ decay) 0.47 0.99 174 Manganese-56 1.81 0.29 2.11 0.15 1.17 1.0 1492 Cobalt-60 1.33 1.0 1.095 0.56 1875 Ircn-59 1 292 0.44 IThe F factor is a cxmstant for each isotope bemuse the energy spectrum of the emitted rya ==na radiation of each isotope does not change as a function of time. 103
j Attadisumt to IJSA/5874/B( )F Rev. 4 Page 2 Table 2 F Factors For Use in F Cg = (1000-N g )/F For Irradiated Fuel Shipsumts Effective Hours Full Power Hours Decay Operation 720 1440 2160 4320 6480 8760 17,520 43,800 87,600 { 100 339 339 330 219 200 194 192 208 698 500 338 338 325 219 203 198 198 237 648 1000 338 337 318 219 206 203 206 268 629 5000 332 317 283 230 228 229 250 382 606 10,000 317 300 271 242 243 248 278 427 607 15,000 310 294 269 249 253 258 292 445 610 20,000 306 290 268 254 257 265 300 457 612 25,000 302 286 268 256 260 267 305 464 617 4 30,000 300 285 267 257 263 270 308 466 624 'f 40,000 295 282 266 258 264 271 310 472 637 50,000 292 279 265 259 264 272 311 472 651
A=._iW&A L. a g eanemassapete %_w=.....mm m m x...__
" " "" # " ""'**' "l Es"a3 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES i
'o cFR 7'
[ c PACKAGE IDENTitiCAT60N NUMBER 0 PAGE NUMBER e TOTAL NUMBER PAGES : i a cERriricATE NUMBER b REVISION NUMBER USA /5875/B( )F 1 4 5875 3
, I $ PRE AMBLE a This cert ficate is issued to certif y tnat the packaging and contents described in item 5 below. meets the applicable satety standaras set fortn in Title t O. Code l$' o, Federai nequiat,on. eari ri. eacmaging o, sadioactive cateriais vor Transport and Transportation of sadioactive uateria! unoer certain condition. -
i q f5 b inis certihcate does not reneve tne consigno trom cornphance witn any requirement of the regulations of ine U S Department of Transportation or otner ; I applicable regulatory agencies. includ.ng tne government of any country through or irito whicn the package will be transported H. hlN' 'm=~;:a== ~s~ ~ ~ ~~ ~~~"s*:',m;mmm?==,c ,,0N U.S. Department of Energy Division of Naval Reactors
~
Safety Analysis for Radioactive l'aterial Shipping Cask WAPD-39 and NRBK-44 dated March 11, 1968 Washington, DC 20585 and August 15, 1968 as supplemented. : 71-5875 c oOenET NUMeER . 4 cOND: T >ONS This Certsficate is Coriditional upon fulfilhng tne requererneets of 10 CFR Part 71, as apphcable, and the conditions specAed below i 5 (a) Packaging i , (1) Model Nos.: WAPD-39 and NRBK-44 (2) Description The WAPD-39 cask and the NRBK-44 cask are physically nearly identical and they are functionally identical. The casks are top loading cylindrical
^
lead shielded 304L stainless steel clad casks used for shipment of irradiated test specimens. The cavity of the casks are formed by 1/4-inch thick stainless steel surrounded by 10 inches of poured lead shielding with a 1/2-inch thick stainless steel cylindrical sheet outer shell. The casks are shipped in a horizontal position on a steel "I" beam skid which is equipped with four combination tiedown-swivel trunnion blocks. The physical characteristics are as follows: . Model No. HAPD-39 NRB K-44 h Outer Dimensions [K:
*' Diameter, in 26.75 26.75 3 Height, in 75 75 1 E
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Tla ra w as % w ._ ____ Il: ' l- CONDtTloNS (contonved) 1 I! Page 2 - Certificate No. 5875 - Revision No. 3 - Docket No. 71-5875 4 I l f5. lI-(a) (2) Description (continued) 1 Model No. WAPD-39 ~NRBK-44 1, - 3 Cavity Dimensions Diameter, in 5 5 Length, in 50 50 ; Approx. Loaded
, Weight, lbs _l6,500 16,500 ;h
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Lead Shielding i j Thickness, in. 10 10 Reference. 39-100, Sh. 1, 41-0001, Sh. 1, Drawing Nos. Rev. O, Rev. O and - , (Battelle Memorial Sh. 2, Rev. O and -Sh. 2, Ins titute) Sh.3, Rev.-0, of 3 Rev. O, of 2
- 5. (a) (3) Product . Containers .
The contents of the package nust. be packaged in inner ' product containers. ; The inner product containers ~ are ' constructed in accordance with the - ! following Hestinghouse Electric Corporation Drawing Nos., except where
- noted
Product Container Drawing Nos. l N IN-39 971D207, Rev. 3 and 971D201, Rev. 4 1 PR 979C200, Rev. 2 PS 979C106, Rev. 2 '
, HPS 979Cl40, Rev. 2 T - 979C145, Rev. 2 L ZT 979C143, Rev. 3 Z 979C155, Rev. 1 j!
ZZ 979Cl44, Rev. 1 lp Hu (or Hoke) 1801, Rev. D (Hoke Corporation Draw-ing) and 272E526, Rev. A (General Electric Company Drawing)
%)N C7 965D391, Rev. 2 i
, ZC7 965D391, Rev. 2 ' 1
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p . . . EEE. .p. .EEmp. . .p -i~E.XA ~. la Em ._. . .~a n} &____.___ ' ll CONDiTloNS (continued) l ! I ll, I t Ei h l' Page 3 - Certificate No. 5875 - Revision No. 3 - Docket No. 71-5875 lR
, 1l 's ig= ' El 5. (b) Contents E.
(1) Type and form of material [I Byproduct and special nuclear naterial contained within product containers. The contents shall be dry and unnoderated (H to X atnmic ratio (2) , unless specifically authorized for the product container. , (2) Maximum quantity of material per package (i) The fissile contentfof seldask shall be limited to a maxinun of 350 equivalent grams of'U-235. The : number of equivalent grams of kl U-235 is determined by the equation: 1 x grams U-235 + 1.4 x grams U-233 + 1.6 x grams plutoniun. 1 (ii) Up toisix, C7B3 or C783A Irradiation Test 0xide Rods in inner container."C7" and "ZC7". If less than six C-7 rods are to be 4 shipped, other fissile materials may.be included in the "C7" or "ZC7" inner containers. There can. be .up to 509. equivalent grams ofJ-235 in each C-7 rod, for a' shipment total- of 3054 equivalent grams of U-235. >The number of s equivalent grams of U-235 is detennined by the equation: 1.0 x' grams U-235 +~1.4 x grams U-s 233 + 1.6 x grams plutonium.' If 1ess s 1 than. six "C7" rods are to be shipped,175 ' equivalent. gramsl of U-235 nay be placed in each
,l of =the "C7" and "ZC7"; inner : containers which would be otherwise empty. Each; such shipment;nust contain six, "C7" or "ZC7" sealed inner containers within the split aluninum envelope even though one-or more' of the-inner containers:nay be empty.
(c) Fissile Class ~ 'II (1) liininum transport index For the contents ,
- ; to be shown on label , described.in 5(b)(1) i
, and linited in 5(b)(2)(i): 3.2 i (2) fiinimum transport index For the contents described in !:
l to be shown on label 5(b)(1) and limited in 5(b)(2)(ii): 10 I
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- 6. Maximum day heat per package shall not exceed 8,400 Btu /hr.
- 7. The "HW" product container may be used to ship test specimens containing small quantities of water and pressurized gas. The total internal pressure of the product container shall not exceed 1,050 psi at a uniforn temperature of 400 F. ;>
- 8. Expiration date: April 30, 1988.
REFERENCES ' I Safety Analysis for Radio 3ctive flaterial Shipping Cask WAPD-39 and NRBK-44 dated ; March 11,1968 and August 15, 1968. T g .Cs f . Supplements: Division of Navil Reactors letters S# 1387;-dated flay 14, 1968, S# 1638; dated October 17, 1968,S# 1570; dated September 19, 1968, S# 1597; dated i September 19,1968, S# 1653; dated October 22,1968, S# 1681;; November 7,1968, S# ' 1690; dated November 22S1968, and S# 1903; dated !! arch 19, 1969'and Bettis Atonic Power Laboratory letter WAPD-CL(IH)-733 dated October 10, 1968;' Division of Naval Reactors letter Z# 85-1605, dated, April 1,1985.
~
'^
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?FOR,THE U.S. NUCLEAR REGULATORY COMMISSION ,
. Char es p 62.y
. facDona d, Chief Transportation Certification Branch Division"ofsFuel: Cycle and '
Ma terial: Safeti, itiSS Date: II E-1 i i V iik j t
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- l
{l: e Tnis certiv. cat. do.. not r i v. in con.ignor vrom cornaiianc. .itn any r.quer m.ni or in. r.gviation or m u s. o.partmor i oe Tran portstion or otn.'
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appiscani. reguistory ag.re. . mciudma in. gov.mment or any country tnrouan or into unica ine package wi o. transported lh
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n I 3 THiS CERTtFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION [a a PREPARED BY dhame and AJJtess A b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Safety Analysis Report for 2.7 New Fuel U.S. Department of Energy Shipping Container dated July 15, 1968, {g Division of Naval Reactors 'g Washington, DC 20585 as supplemented. f I 71-5894
; e ooc ET NUMBER
- 4 CONDITIONS Tnes c rtificat. is conditionat upon fulfatimg tne requir.m.nts of to CFR Part 71. as apphcable and tn. condihon. .p.cifi.d belo.
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- I (a) Packaging y f
(1) Model No.: 2.7 New Fuel l L i ,t i (2) Description !t The Model No. 2.7 New Fuel container was designed to ship and store J new and unirradiated SSW: Core R2 fuel modules. Adapters are used to [( g, f pemit additionalishipments of SSW Core. R3, Alu Core R2, and SIC Type i{I I: I fuel modules. The container assembly consists of two major components, j'l l an inner container which holds the fuel module and an outer container !! Al which supports the inner container. The steel outer container is approximately 24.5 inches wide by 24.5 inches high and 128 inches lI {p I long. Thefeross section of the outer container is octagonal, the steel shell thickness is 0.1875 inch,' ASTM-A283 Gr. B. The outer {j g( shell is' surrounded by a framework of Jsteel stiffeners and rails. The t inner container is constructed from Type' 304 CRES plates, 0.1875 inch 'r thick and is 7.76 inches square ~and 99 inches long. Bolted closure is , .( provided for each contain'er. The l gross weight of the package ranges I l{i f j i from app'roximately 1,500 to 2'.000 pounds. s x - lt 1 i m lI R1 < I L 1
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- i nac ronu sisa U.S. NUCLEAR REGULATORY COMMISSION ]I a **3n CONDmoNS (cehg s !,
Page 2 - Certificate No. 5894 - Revision No. 3 - Docket No. 71-5894 ll
;I
!I 1 :p p (3) Drawing
=
0 The packaging is constructed in accordance with Westinghouse Electric !
] Corporation Drawing No. 924J152, Rev.16. l
[ (b) Contents 6 ! j (1) Type and form of naterial l Unirradiated fuel assemblies of the following type: ; (i) SSW Core R2 standard module or corner module; f f (ii) S5W Core R3 standard module or corner module; il y! (iii) AlW Core R2 standard cluster or half cluster; ,1 f1 f I il (iv) SIC Core Type I standard cluster; 1 j (v) SIC Core Type I fuel subassembly; [ r I 3
- ) (vi) SSW Core 2 standard module or corner module; I (vii) AlW Core R2 subassembly.
1 [ (2) Maximum quantity of material per package }Y (1) Onefuelassemblyasdescribedin5(b)(1)(i),5(b)(1)(ii),5(b)(1)(iii)l
]lj 1
5(b)(1)(iv) or 5(b)(1)(vi). I
~1 2,
(ii) Two fuel assemblies as described in 5(b)(1)(v).
;j' (iii) Four fuel assemblies as described in 5(b)(1)(vii). l 1
j (c) Fissile Class III [h
'I :
1 Maximum number of packages per shipment: l 1
=8 (1) For the contents described in 5(b)(1)(i), No more than j 5(b)(1)(ii), 5(b)(1)(iv), 5(b)(1)(v), and 5(b)(1)(vi) one total core's j andlimitedin5(b)(2)(1)and5(b)(2)(ii): worth i 1 1 (2) For the contents described in 5(b)(1)(iii) and 25 total, with the 1 5(b)(1)(vii) and limited in 5(b)(2)(1) and number of packages i 4
5(b)(2)(iii): as described in 5(b)(1)(vii) and gll limited in g 5(b)(2)(iii) not . A to exceed four : 1 4 l Expiration date: January 31, 1988 { 6. l l, 110 l Lu.ssrzsxxRh0irwv++ymrwmc+v#sv+w xyhmme,,,g,3
m_m m a m n u m mum m m m m m m m miumim a n a . . . . . . . . . . . . . . . . . . . , , , , I NRC FORM 618A U.S. NUCLEAR REGULATORY COMMISSION h (*
- CONDmoNS (continued)
(R l lt i Page 3 - Certificate No. 5894 - Revision No. 3 - Docket No. 71-5894
- n
;I l lI i
REFERENCES )
;i l Safety Analysis Report for 2.7 New Fuel Shipping Container, WAPD-0P(R)S-2650 dated j)i i July 15, 1968. b
'k t
Supplements: Bettis Atomic Power Laboratory letters WAPD-0P(R)S-2800 dated September j>
'g l 3,1968 and WAPD-0P(R)S-3425 dated August 14, 1969, and Department of Energy letter t G# 6291 dated July 13, 1979. 't i
i i I i FOR THE U.S. NUCLEAR REGULATORY COMMISSION P lI Charles E. MacDonald, Chief 'l i Transportation Certification Branch I ( Division of Fuel Cycle and Material Safety, NMSS f l Date: SEP 0 61983 [ t i P i
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..........x...................,I CERTIFICATE OF COMPLIANCE U.S. NUCLEAR REGULATORY COMMISSION !
li 4'o3,crR n ,b l FOR RADIOACTIVE MATERIALS PACKAGES !b
- q. cERTocATE NUMBER D REVISION NUMBER c PACKAGE sPtNTsFsCATION NUMBER d PAGE NUMBER . TOTAL NUMBER PAGES L 5908 10 USA /5908/B( )F 1 3 j i a rREAMeu 'I -
ll . Tn.. cert.,, cat. .. .au.o to c rtity tn.iin. p.c6 9.no .no coni.nt.o cr o.o init.m s o.to.. m r. in. .p. soi...v er e i.no ro...i vortn in r.ii. io coa. , g r.oeral Regulation P.rt 71. " Pack.ger.g of R.d.o.ctiv. M teri.t. for Tr.nsport and Tr.nsport.teon of Ru o.ctiv. Mat. rial Unoer Certam Condition. ' s
's g
I' o in . certies.t. oo.. not r.+. ene cons.onor from compa.nc. Ritn any r.quu.m.ni ce in reguiat.on. or in. u s o.partm.ni or Tran. port i.on or otn., B 1 E! .ppi,cm. r.gui tory g.nc .. .nciuoino in. governm.ni ce .ny country inrougn or .nto .n cn tn. p.cm.o. ..ii n. ir n port.o ,p I' ' I! {h B I 3 THIS.CERTOCATE PREpAREoar IS m isSUEO
.na4ON THE BASIS OF A SAFETY ANALYSIS e i in TirtEREPORT OF THE PACKAGE ANo ioENTwiCATiON oESIGN Or REPORT OR APPucATiON oR Apeuc4 TION .h i
h Babcock & Wilcox Company s! 609 N. Warren Avenue Nuclear Materials and Equipment Corporation application dated May 3, 1974, as supplemented. f j I; Apollo, PA 15613 's di
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c ooc.ET NuMsER 71-5908 g 4 I CONOiTIO,NS in,. c rt. ,c.i. i. cono.t.on.i upon evir.mna in. r auw.m.nt. o, io crR e.rt ri. .. .ppisc.o . .no in. cono. on. .p.cie,.o o.io. ,1
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i' Il (a) Packaging 't I ! f (1) Model No.: DOT-6M Type B n! i q (2) Description I.l I;
- r. - -
Metal packaging as described. ' and constructed in accordance with 00T
! Specification 6M. ~V/ !n l ! i,
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-g f (b) Contents .
j i (1) Type and fdrm of material . l' . . .- - I (i) Solid radioactive. materials which' will not decompose at temperatures !p up' to 250 F. Carbide: compounds #are not authorized; or
,ih 1
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'y g . , s y (ii) U0{;orU02 mixtures in_the. form of, powder or; compact pellets; or ;j g - m '
2 I (iii) Plutonium' nitrate' or~dranil' nitrate solution;in flame sealed lIl I; glass ampoules or'scfeK top ' plastic' vials, Jeach within one or more additional plastic l vials with taped lids, and within a {b
'N sealed; product' can or7 -
p ~ olyethyle~ne bottle %ntaining a sufficient l
}g! amourit of vermiculite -to absorb)tsice th.e' liquid contents present; D g: Or ' ')
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__,lI 7_RC l N IN FOAM 818A---_.-_.--.......... CONDITIONS (contmuod) U.S. NUCLEAR RE'1ULATORY COC2'ISSION {lI j I J 1 J lg Page 2 - Certificate No. 5908 - Revision No.10 - Docket No. 71-5908 lI
] ll
;b fl1 ;3 h (b) Contents (continued)
Plutonium sources in excess of twenty (20) curies per package (iv) must I be at least double encapsulated in a metal capsule such that n h the sources meet the requirements for special form radioactive
] material.
>W lI 3
7 Inner and outer capsules are individually leak tested during lj j 1 fabrication per ANSI N542-1977, procedure A2.2.3 (He pressure !y 2 bubble test), or equivalent, l3I h (2) Maximum quantity of material per package and fissile class f >l i (1) For the material described in 5.(b)(1)(i), the maximum fissile al 3 material and maximum hydrogen per package for Fissile Class I is j! Ji lj as follows: !gi I l Maximum fissile material Hydrogen Material p fj Fissile per package, per package, grams ta
!I Material kilograms f
y
- 1 1.6 - 20 1!
U-235 Pu 0.9* 11 6.4 I} 1R 1 U-233 0.5 il 1
$ !I
*Because of the 10 watt thermal decay heat limitation, the limit for f Pu-238 is 0.02 kilograms. Plutonium in excess if twenty (20) cu
- 1 per package must be in the form of metal, metal alloy or reactor '
1 fuel elements. ', 1'
$ lI3 l' (ii) For the materihl described in 5.(b)(1)(1) the raximum U-235 loading for uranium bearing materials with an H/X g 3 and the ll f minimum transport index to be_ assigned to each package for Fissile jl j
fj Class II is as follows: , l 1, {gg Maximum Minimum 1, 1 Kgs U-235 Transport Index In g
. J.
0.1 Il 4.2 f 0.2 !3 , f 3 5.4 7.3 0.5 1.0 1 g [ 9.1 :s For the material described in 5 (b)(1)(ii) the maximum quantity ;g 1, (iii) of U-233 is 500 grams at an H/U ratio not to exceed 20 contained : I fI! within a package size of at least 55 gallons, Each shipment il j f, shall be limited as follows: ' I li !g I The minimum transport index for Fissile Class II is 2.5 i s 1; The maximum nunber of packages for Fissile Class III is 51. !I l f m h; [ I! l '__________________.___.____________________________
y-----------Aa------ I _ _ _ - - . . w m . - - . . . g 2 . ,x,g w e g w.anura
! NRC FORM SMA
*O
. CONDITIONS (continued)
U.S. NUCLEAR REGULATOXY COZilSItON Ej Page 3 - Certificate No. 5908 - Revision No.10 - Docket No. 71-5908
)
Ii I ,1 l lI I,i 5. (b) Contents (continued) 't l l Il I (iv) For the material described in 5.(b)(1)(iii) the maximun quantity of material is not to exceed 20 ci radioactivity and 40 ml of ' q solution. Fissile material shall not exceed 10 grams. l g! t l (v) For the material described in 5.(b)(1)(iv) the maximum quantity 4l : of plutonium is 100 ci. ' l ll fp 6. Two steel through bolts may be installed between the lid and botton of the steel d rums . y E! ll 7. Venting may be provided by a 1-inch diameter hole in the drum lid backed by a f; y
'I; minimum 1/2-inch thick Cerafelt refractory pad. !gj li
- 8. 'pl Maximum decay heat per package shall not exceed ten (10) watts.
- 9. The package authorized by this certificate is hereby approved for use under the
[! g general license provisions of 10 CFR 571.12. fI ll 1 10. Expiration date: Februa ry 28, 1986. I El i g I t
,I lj '
i g. ll REFERENCES i I! ' i I Nuclear Materials and Equipment Corporation application dated May 3,1974. l ( Westinghouse Electric Corpcration supplement (WAPD-RS(CC)-620) dated May 8,1973. g' gl DOE, NR supplements dated: March 28,1979; and July 19, 1982. ld N; 1l I, Allied Chemical Corporation, Report No. ICP-1061, December 1974. - 0 i f Monsanto Research Corporation applicttion dated January .10, 1980.
! FOR THE U.S. NUCLEAR REGULATORY COMMISSION !
I II l M Charles E. Mac cnald, Chief ! ( Transportation Certification Branch ; i s' Division of Fuel Cycle and i I! Material Safety, NMSS ; l I! l E. ll l r i SEP 0 61983 ( Date: I; i l I
,. i14 brasurh*h= = = = = = = = = = = = = = = _ __ g ewywwwwwwm ,
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- NIC FORM S1s U.S. NUCLEAR REGULATORY COMMISSION B i
1 +sa CERTIFICATE OF COMPLIANCE i o crR n FOR RADIOACTIVE MATERIALS PACKAGES E! < D REVI540N NUMBER c PACKAGE IDENTIFICATrON NUMBER d PAGE NUMBER i a CERTIFICATE NeJMBER 5910 4 USA /5910/B( )F 1 e TOTAL 2 NUMBER i l
. PRE AMBL E a This certificate is issued to certtiy that the packaging and contents described in item 5 below, meets Ine apphcable satt ty standards set forth m Title 10. Coae gs of Federal Regdat ons. Part 71. ' Packagmg of Radioactive Matenats for Transport and Transportation of Radioactewe Materaat Under Certam Conditions "
b b Tnes cert ficate does not reheve the consignor from comphance with any regsrement of the regulat ons of the U S Department of Transportation or other appheabie reguatory agencies. Incruding ine governmeni or any country inroven or mio wnicn ine pacsage weii be transported y!
.H E
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! 3 THIS CERTWICATE IS ISSUED ON THE BA$l$ OF A SAFETY ANALYS35 REPORT OF THE PACKAGE DESaGN OR APPUCATION a PREPARED BY theme and addressi b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Babcock & Wilcox Company Babcock & Wilcox Company application dated f P.O. Box 785 March 6,1970, as supplemented ji g
Lynchburg, VA 24505 t e oOccT NuueER 71-5910 3 a CONDITIONS Tnas certificate is conditional upon fuifelhng tne requirements of to CFR Part 71. as apphcable, and the condebons specified below ' i s .R' (a) Packaging E E El (1) Model No.: NNFD-SA-2 la gi (2) Description g;
'g.
fuel container is a 14. gage steel box with a maximum outside cross
~
'E r
sectional area of 8.5 square. inches, with gasketed lid closure. Fuel I , i container is supported in an open birdcage of slotted angle iron, with Ei outside dimensions 2' x 2' x 12'! maximum. Container and birdcage are l]j constructed in accordance with design shown in Appendix A, Figures 1 and 2, of Westinghouse Electric Corporation's application dated Novembei 6, ggi
'E 1967.
i 1 (b) Contents (g 4
; (1) Type and form of material gj
- Ri' Uranium enriched in the U-235 isotope to any enrichment, as sintered
~
,K uranium oxide fuel elements., clad with bonded Zircaloy 2. Element 3 E
I dimensions ar- approximately 0.09C" x 3.5" x 96". , h i (2) Maximum quantity of material per package Total centents not to exceed 240 pounds, with U-235 not to exceed four ,I (4) kilograms. 8
- E
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115 n { --------____----------------------------,---wr-ans-re ,
p - - - - a i m = = = = = = i m_m_==_illis fal=T& Tai _ii N _ N _TEWJEMf_____ l CONDITl0Ns (continuedi E 4: I r Page 2 - Certificate No. 5910 - Revision No. 4 - Docket No. 71-5910 : L ! > g' ! 4: R-I:' g 5. (c) Fissile Class III R; dl Maximum number of packages 4; per shipment Nine (9) p 6. The package authorized by this certificate is hereby approved for use under the > y general license provisions of 10 CFR 971.12. 3
# 7. Expiration date: October 31,198i.; R E G ,,,
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1s ji REFERENCES (-) pt Rf' . -Q p i % . 4 ; Babcock & Wilcox Comp $ny application dated March 6,19_70. -
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Westinghouse Electric Corporation,'s;applicatiori da~tedjNovember 6,11967. p, y ,.> ;
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' *-,f FOR~,THE;fI,-
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y____ , q_-------------2---------____.--___m___________ _ _ U.S. NUCLEAR REGULATORY COMMISSION jI l i NRC FORM 618 CERTIFICATE OF COMPLIANCE i li m !I ljiocrR" FOR RADIOACTIVE MATERIALS PACKAGES c PACKAGE eOENilf sCAYpON NUMBER d PAGE NUMBER e TOT AL NUMBER PAGES b REVILoN NUM0(p f i a CERTIFICATE NUMBER 2 USA /5914/B( )F 1 3 q 5914
's t: PRE *ust E e 'y
. Tnis ceriAcat. is .ssu.o to cert >ey anat tn. packaging eno contents oescrie o mitem s e.iow. me.ts the appucadie ss .tv tanoaros set torin in Titi. io. coo I
1l r.aerai n.guistions. Part 71, "Packagmg of Radioactiv. Materials for Transport and Transportationi of Radeosctiv. Material Under Certam Condit g 1, ,i 1 e in,s c.rtieicai. oo.s not r a.v. in consignor vrom compname witn any r.quirement of me reouistions of in. u s o.partment av Transportanon or oin., 's appucam. r.guistory ag.x .. .nciuomo in. government of any country inrouan or mto n.cn in. pactaa. . is e. transport.o 4 %
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ll ":"*,='rs'l,'L'""a'Ja= " ' * "" '~^"t'1Tla'#Apr TWg="oRrJnio~ in 1 U.S. Department of Energy Safety Analysis Report for 57.5 x 108 Core !; f Cartridge Shipping Container dated May 6,1968, ju flj Division of Naval Reactors Washington, DC 20585 as supplemented. ;p
.I lj in 1,
e oocxEr~UueER 71-5914 ) 1; I F I 1, a co~OivioNsin.s certiv cat. is conoir.on.i upon tuivanns tne requ<em.nts of to era Part 71. as appocaese. and ine conoitions speciti.o d.io. ll 1 (a) Packaging f'
- I 57.5 x 108 Core Cartridge
))!g 1! (1) Model No.: il Al lI 1l (2) Description :l h il f /
The Model No. 57.5 x 108; Core: Car,tridge Shipping Container was designed for the shipment and storage' of new and unirradiated fissile material, j a barrel assembly and a Ib t This unit consists,of two basic shipping cradleV The barrel assembly house assemblies, band supports the cargo In ll l' and is supported on a shock-support shipping" cradle that is floor ll
-l mounted to'a" transport vehicle. The overall" height of the assembled ji unit is 155-3/16 inches and the maximum planform envelope dimensions lI l ~
t The barrel assembly consists of two concentric ili f are 108 byjl82 inches, The 1 cylinders, an inner. barrel and an outer, barrel, and a top plate. inner 1 ll from 1/2[ inch thick' stainless, stee i cylinder _and welded toJa-stainlessM} teel flange 6iPthe plate toprolled'into end, and a a 57-inch Jj I stainless steel plate'onTthegbott'om'end which is' drilled and tapped lil ibolts forf, fastening the outer barrel. jN f; for thirty-two'3/4-_ inch di' ape The outer-barreltisjof carbon i #ste'el construction 7 slides over the!I f;! l inner ba'rrsl arid'is'att'ach'e'dito f thelinner barrelfat the bottom flange. The outer \baJrel"is 6h-inchessin diameter, approximately 149-3/4 inches high. and is made from 1-inch < thick carbon steel plate. A top
)'s i 1l flange is welded to the barrellfor securing (5 bolted top plate that I L i 1 encloses the openg end of the barrels and'a: middle flange is welded to the -
p 1 V .I r .
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1 W ~l? % llI 1 I l i
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31 1 jn 1 1, lI l lIl L .i t 'n , I 1D ( __ mm _ _ _ _ .! ! L __ _ m_=_m. _ _ __ _ _ _mm. . _ _ _ l
NAC Fonts 614A
&O U.S. NUCLEAR REcuLATORY COCZISSl!
CONolTlONS (continued) Page 2 - Certificate No. 5914 - Revision No. 2 - Docket No. 71-5914 lit
)I
!f
- 5. (a) (Cont'd) 1lg (2) Description (Cont'd) lh barrel to provide a means of attaching the barrel to the shipping }
cradle. Within the barrel assembly a hoisting rig for handling the {l p core cartridge is secured to the top plate with four,1-1/2-inch j diameter jackscrews and four, 2-inch diameter ACME thread bolts. The f core cartridge is suspended from the top flange of the inner barrel. lu t The shipping cradle stands approximately 96-inches high and consists ;b of a base plate, fourteen, 8-inch, schedule 40 steel pipes, a top 1 j ring,10 shear mounts and a support ring. The barrel assembly is jlN suspended and attached to the support ring which in turn rests against !g
; and is attached to the ten shear mounts that mount on the top ring of 'i t the shipping cradle. The fourteen steel pipes are welded at their 1 ends to the 1-1/4-inch thick steel base plate and the 2-1/4-inch thick lH
,1 1 top ring. Six stops and eight,1-1/2-inch diameter bolts secure the lN 1
shipping cradle to the floor of the transport vehicle. The gross t h weight of the packaging is 28,800 pounds and when luaded with either an S5W Type 2 or R2, or an S5W-3 or R3 core cartridge, the package I! jy weight is 48,000 pounds. ll
- N (3) Drawings >
(R I j l The packaging.is constructed in accordance with Westinghouse Electric Corporation Drawing Nos. 923J706, Rev. C, 901J914, Rev. D and 90lJ916,
@in Rev. D. 1l
!g (b) Contents -
I (1) Type and form of material l>h 4 _ j Unirradiated fuel assemblies of theI following type: I)I (i) S5W12 or R2 unirradiate'd naval reactor fuelicore cartridge containing a full complement ofl control . rods secured in place by a holdown Ik cap. N 3
.l (ii) S5W-3 or R3 unirradiated naval reactor fuel core cartridge containing a full complement of control rods secured in place by a holdown j
j cap. '
- ' b in ! In
- 1 (2) Maximum quanity of material per package lN
- i 1
ll One fuel assembly as described in 5(b)(1)(i) or 5(b)(1)(ii).
- i ik
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NRC FORM 818A U.S. NUCLEAR REGULATO2Y COMM12S g CONDITIONS (continued / 4 43' j !, a 3
)
j Page 3 - Certificate No. 5914 - Revision No. 2 - Docket No. 71-5914 J! l' n III 'l 1 (c) Fissile Class lh 1 j Maximum number of packages per shipment: One (1) j 1 6. Expiration date: January 31, 1988. !N l i 'N li ll 3 REFERENCES
)
J I l Safety Analysis Report for 57.5 x 108 Core Cartridge Shipping Container, WAPD-0P(R)S-2599, dated May 6, 1968. lj jl 1!
)
1 Supplemented by Bettis Atomic Power Laboratory letter WAPD-0P(R)S-2801, dated September !y
]3! 3, 1968. !)I 1
FOR THE V.S. NUCLEAR REGULATORY COMt1ISS10N lI li .h 9 :n 1; M [L Charles.E. MacDonald, Chief
=Y )
1, LTransportation Certification Branch ;R Division of Fuel Cycle and fl 1 Material Safety, NMSS f[ i 1l f !i; l' SEP 0 61983, :n Date-J
!)
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M isWilia.c=itiQaNwsNImmsw2SmN_w=_==:No-m. -- N 1 +OC u, FOR3 61s U.S. NUCLEAR REGULATORY COMMISSION - 3 '0C'" CERTIFICATE OF COMPLIANCE l FOR RADIOACTIVE MATERIALS PACKAGES i a CERTIFICATE NUMBER tp REvlS40N NUMBER c PACKAGE IDENTit*CA? ION NUMBER 5 d PAGE NUMBER e TOT AL NUMBER PAGES ' 5916 5 USA /5916/B( )F 1 3
) 1 PAEAMOLE 1 a inis certiricate is issued to certif y that the pacmaging and contents c'escrioed in item 5 belo*. meets the appocable safety standards set fortn in Titie 10. Code
.j of Federal Regulations.Part 71. ' Packaging of Radioactive Matenals for Transport and Transportation of Radioactive Material Uncer Certain Conditions "
- 3 o ins, certaicate does not rei,e.e tne consignor tram compnance . in any requirement of in. requianons or tne u s Department of Transportanon or otner
.$ appbcacie regulatory agencies. mcrudmg the government of any country tnrough or into which the package will be transported di i
3 THIS CERTIF*CATE is ISSUED ON TQ BASIS OF A SAf ETY ANALYSIS REPORT OF THE PACKAGE DESsGN OR APPLICATION a PREPARED BY (Name sad deesse b TITLE AND BOENTIFICATION OF REPORT OR APFtsCATiON
.R 3 General Electric Corporation !!onsanto Research Corpora. ion application 3 P.O. Box 460 3
dated March 1,1982. 5 Pleasanton, CA 94566 9
~71-5916 -
c DOCKET NUMBER I a CONDtTIONS 3 , This certificate is conditional upon fulfilhng tne requirements of 10 CFR Part 71, as apphcable, and the conditions specified tvlow 4 a s-1 (a) Packaging 1 i. f 4 (1) Hodel No.: 2501 g - (2) Description 4 i 1 The packaging consists of an interchangeable shielded' center section, connon top and botton end sections,'and up to two extension sections. i Shielding is provided in the center section by successive layers of y iron, lead, and Benelex-70. Balsa impact limiters are included in the ! q top and botton section. Each steel section is bolted to the adjacent i section and bolted to a steel ;I-beam skid-cradle assembly. The cross !
~4 8
section geometry is basically foctagonal 48" across the flats. The length ranges from approximately 12 to 16 feet with a maxinun gross l weight of 17,450 lbs. , 1 3 (3) Drawings
-1 1 :
4 The packaging is constructed in accordance with the following f!onsanto iN d. Research Corporation Drawti.f Nos.: >>
- p f E 2501 - AA00, Rev. 2 E 2501 - AA01, Rev. 2 D 2501 - AG00, Rev. 2 ,
3 D 2501 - AH00, Rev. 2 E 2501 - AA02, Rev. 3 1 1, il E 2501 - AA03, Rev. 2 D 2501 - AI00, Rev. 3 h(It
;9 p
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$*_m =_ = m R d * * * = = E E k m L= =_= N ___ , $ CONDITIONS (contonued)
I 71-5916 l4; Page 2 - Certificate No. 5916 - Revision No. 5 - Docket No. 9 6 l# i E f H Ei (b) Contents (1) Type and fom of material Sources rust Po-Be, Am-Be, Pu-238-Be, and Cf-252 neutron sources. ; neet the requirements of special form radioactive material. l (2) Maximun quantity of naterial per package t
'1,509 curies of PoBe, or An-Be, or Pu-238-Be* or 8.25 curies of CF-4 252. n y. j TN h : l~ s 1 .
(Heat load generated by'the contents must not exceed 60 watts of decay
.C' -
heat.) s
- Plutonium in> excess of twenty (20) curies per package cust be in the fom of metal or netal alloy; or contained within double encapsulated Both capsules must be leak tested stainless,s' teel source capsules.no leakage for a test having a ninimum independently,'and g~ st show3atm-cn /sec (air at~ 25*C and 1 atn leaking to sensigivity of lx10 1x10 ,atn) .
s I (c) FissileCiss$ . I For packages containing Pu-238. . - i
- 6. The contents must,be secured in the. shielded position of the packaging by the .'
source assembly, 'and locking device. The , source assembly nust be of sufficient i l
!g f, length and dianeter to provide positive. positioning of the source in the shielded lg lg! g lg posi ti on . 'E E'
I4! The nameplates must be fabricated of naterials capable of resisting the fire l 7. ; E test of 10 CFR Part 71 and maintain their legibility.
- 8. The package authorized by this certificate is hereby approved for use under the j!$
general license provisions of 10 CFR 671.12. lE
- 9. Expiration date: April 30,1987. lEn
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,\l; CONDITIONS (continued) 3; I
!! Page 3 - Certificate No. 5916 - Revision No. 5 - Docket No. 71-5916 :
l I. Il REFERENCE , I. h: Monsanto Research Corporation application dated fiarch 1,1982. l lH; 15; FOR THE U.S. NilCLEAR REGULATORY C0ftftISSION [%, Charles E. fiacDonald, Chief e. R ; Transportation Certification Branch
~ Division' of: Fuel Cycle and fiaterial Safety, Nf1SS t
k~ Date: JAN 2 81GRC i 1 i 1 i i ! i i f6 t lH' : is: l , ,e f ;
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m. g_ --__---u__----_ -__m--_-_-----____-____a___ _ _ __y__, 5 lj I U.S. NUCLEAR REGULATORY t 4l 4.m wac roRM s1s CERTIFICATE OF COMPLIANCE il l:j 'c CFR " FOR RADIOACTIVE MATERIALS PACKAGES j c PACKAGE IDENitFICATsON NUMBER d PAGE NUMBER e TOT AL NUMBER PAGES i D REVISION NUMBER e CERTIFICATE NUMBER 3 5926 10 USA /5926/B( )F 1 ll I, a PREAMetE t.in. .ppuc.oi. i.e.tv siano ,as set vorin in Titi. io. coa.ot 'y gl . in,s cena. car. ,s ,nu.o to certsy in. in.p.ca.g ng .no contents o.scrio.o init m s e.io..m g r.o r.i a.gul.tsons. Part 71. ~ Packaging of Raoio.ctiv. Materials for Tr.nsport and Transportation of A.oso.ctiv. Materi.i Onoer Certain Conoitionsig~' 1; o Tn.. certie. cat. oo.s not r ine consignor f rom compi .nc. ..tn any r.auirement or ine regui.t.ons of in. u s o.partment of Transportation or otner lh l :n l 4:
.ppuc.e . regui tory g.nc.s. mciuoing en. gov.mment et any country inrouan or into .nich tn. pack a. wiii ne transported
)
Il 'n 1l 3 THIS CERTIFtCATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION Nj D TITLE AND IDENTIFICATION Of REPORT OR APPLICAT10N f a PREPARED BY (keme sN AJaresst Ri it! General Electric Company General Electric Company application dated 5't d, P.O. Box 460 January 25, 1980, as supplemented lh t
$l Pleasanton, CA - 94566 i in E!
71-5926 f c DOCxET NUuetR
!3 8 ,1 CO~Dif,0~STn,s c rt.e. cat. is conoit.on.i upon tuiriiing in, reau.rements of io crs Part 7i, as appi.c.ei.. .no in. conditions specie .o oeio.
'l 4;
Wi !H 5-(a) Packaging ) E t f (1) flodel flo.: GE-100 E; (2) Description j is: j; A steel encased lead shielded shipping cask. The cask is a double-i y( walled steel circular cylinder, 20-1/4-inch diameter by 27-1/8-inch ! j high with a central cavity 7-5/8-inch ' diameter by 10 inches high. ! 1:
~
Approximately 5-7/8 inches of lead surround the central cavity. The
~
!i cask is equipped with a cavity drain line and lif ting device. Closure -
lNI di l 8: is accomplished by a gasketed and bolted steel lead filled plug. For i N additional shielding lead, tungsten or uranium liners may be inserted in the cask cavity. The maximum weight of the packaging is 4,800 j i
+
pounds. .. 4
- pl i
i :n l (3) Drawings ;b
~
The packaging is constructed in accordance with the following General Electric ' Company Drawing flos.: 129D4727, Rev. 2; 129D4729, Rev. 3; ' j ib
! 12904730, Rev. 2; and 129D4731, Rev.1. !
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------------------------------------ ---g-f__ -- g_ -f _ - - ,
NRC FOAM 610A U.S. NUCLEAR REGULATORY COMMf3SIO y GW CONDET1oNS (continued) k li !I I: Page 2 - Certificate No. 5926 - Revision No.10 - Docket No. 71-5926 1lg l ll i
!I li il i
f 5. (b) Contents
)
i n (1) Type and form of material I )i
;i it (1) Byproduct and irradiated special nuclear material in the form of lp
- ! fuel rods, or plates, fuel assemblies, or meeting the requirements p
;j of special fom radioactive material; or
;\ ;j r
(ii) Solid nonfissile irradiated metal hardware and reactor control
! l' i rods (blades). )!n I (2) Maximum quantity of material per package !E i i it
;l
!j Radioactive decay heat not to exceed 400 watts and 500 grams U-235
)
j f equivalent mass fissile material. (U-235 equivalent mass equals U-235 mass plus 1.66 times U-233 mass plus 1.66 times Pu mass.) l ly g in Plutonium in excess of twenty (20) curies per package must be in the ll
; a i
form of metal, metal alloy, or reactor elements. I a li j (c) Fissile Class II j Minimum transport index to be shown on' label g q Contents 5.(b)(1)(i): lp-i 5.6 !g I l=
- lm
- 6. Shoring shall be provided to minimize movement of contents during accident q conditions of transport. jlN 1
i 7. At the time of delivery of the loaded package; to a carrier for transport, the 't lg package contents shall be dry and the fissile material unmoderated (H to X 'I
;1
- atomic ratio less than 2). '
fi i
- 8. Prior to each shipment the silicone rubber lid gasket shall be inspected. The l i
silicone rubber gasket shall be replaced;if inspection shows any defects or i every twelve (12) months, whichever occurs :first. - Cavity, drain line shall be jly sealed with appropriate sealant applied'to threads of pipe plug. !p
- 9. 'l 1
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 971.12. {lh h 1 10. Expiration date: December 31, 1987. 4 :n
;b a
1 !$
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i [ I# 1 h ig[gy,;3 0 . - w. - wr.rwr, ;-wr-wisr-rwr -r,iirsirarssir,.r,.r,.cs, irsirs v. - r,.r,.r- r.r- - ,- ,, ,.ri,w -- - ,. ww -
e__ -______--______________._______ _____..______, I U.S. NUCLEAR REGULATORY COMMISSION ll nac
+w ronu e18A conomons (continuem }
g
!I Il I Page 3 - Certificate No. 5926 - Revision No.10 - Docket No. 71-5926 ;h
.I I I 1 'n l \s\
IlI I g I REFERENCES i I; n General Electric Company application dated January 25, 1980. l I Supplements dated: August 26, 1980; and September 7, 1982. 1)1! I! FOR THE U.S. NUCLEAR REGULATORY COM ISSION p y l i lR umG1JJ d
'll l\ i Charles E. MacDonald, Chief I g!
g Transportation Certification Branch y 4, Division of Fuel Cycle and g lj Haterial Safety, WSS I
'l 3
s I! Date: SEP 0 61983 g I; I IlI ll !, i !i I I: ll Ir ll 1
!1 1
1 It i l I 'l E. ll 1: 'l El l \s \ I 'i ! I !g I ! l I, !i i: .i
!I l{ il i
I :q I 3 I 'l I i Il, l I l . l l Ilt !l ll ll l I 'l l ll l Il il' I lj l Il; !I N- : 1 I ll I N! l (I !! j-; os j L . s . # . . w r# . v r- w .c # u w + # + - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
~_ _ - -. _ - . - - . _ .
I t
%=m.= M eiEEAAW54M WEEEA* N "M"NN - - - - - -
N """ CERTIFICATE OF COMPLIANCE "! lE . '* CF" " FOR RADIOACTIVE MATERIALS PACKAGES I
, i a cERTiricaTE NUMBER D HEVISION NUMBER c PACKAGE IDENTIFicATtON NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES 5939 12 USA /5939/B( )F 1 3 ll. / PRE AMBLE a This certtiscate as issued to certify that the packaging and contents descrted en item S below. meets the apphcable safety standards set torin in Title 10. Code jg. of rederai seguiat,ons. Part n. Pacmag.ng of nao.oactme uarenais for Transport and transportation or sad.oact.ve u.itenai unde, ce,ta n condinons-J lR b Th.s certiScate does not reheve the consignor from comphance with any requerement of the regulations of the U S Department of Teansportanon or otner ' lk apphcab.e regWatory agencies including the government of any country through or anto whech the package will be transported t ' (R ;
IR;
! ' 7'JEPifEE^e'v'A*2' JAM "^* ' ' **" *",*l'r7te'Ea'Ec'E0fi*cffl'EUS"OO'*ETEcanON '
General Electric Company General Electric Company application dated ' P.O. Box 460 Februa ry 21, 1980, as supplemented. ; j - Pleasanton, CA 94566 j bi c OOCKET NUMBER 4 CONOiTaONS , This certAcate is condational upon fulfdhog the reqwrements of 10 CFR Part it, as apphcable, and the conditions specarved below . (a) Packaging l (1) Model No.: 1500 l l (2) Description i A steel encased lead shielded shipping cask. The cask is a double- ! walled steel circular cylinder, 31-inch diameter- by 48 inches high with a central cavity 7-inch diameter by 25 inches high. The diameter is reduced from 31 inches to 17-1/2 inches by cone construction at the top 7-1/2 inches of the cask. Approxinately 11 inches of lead surround i the central cavity. The cask is equipped with a cavity drain line and . lif ting device. Closure is accomplished by a gasketed and bolted p) PJ steel lead-filled plug. A protective jacket consisting of an upright circular cylinder with open bottom and a protruding box section , l' diametrically across the top and vertically down the sides attaches to : a square pallet. Dimensions of the protective jacket are 60-7/8 ' j inches high by 49-3/4 inches wide across the box section. The outer : cylindrical diameter is 36-1/2 inches and the pallet is 59-1/2 inches l square. The maximum weight of the packaging is approximately 15,000 l pounds. (3) Drawings k The packaging is constructed in accordance with the following General Electric Company Drawks Nos.: 129D4748, Rev. 3; 129D4749, Rev. 3;
) -
and 129D4750, Rev. 3. )j , Lifting and/or tie-down devices which are a structural part of the l package rust be in accordance with the above drawings. ;
$y y
- 26 F
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a w w w w w w w ww w w w w ww ww w w w w r 's w w w w w w w w w w w w w 'aust w w w w ret v m w w w w est s w e s t
&~i KA R m_=_m_ 65$
h m _= = w m m - = = = m a m m - m - m a m = _ m_ilillim_m u m - - A M W A_m m l lf , E CONolTtoNS (continued) [}U
;H lI. l l !E- Page 2 - Certificate No. 5939 - Revision No.12 - Docket No. 71-5939 18 lt i ja 5. (b) Contents W
(1) Type and fom of naterial I (i) Byproduct material and special nuclear material meeting the fl ' requirements of special fom radioactive material and antimony pins encased in stainless steel; 90 CsCl; i (ii) Byproduct material in the fom of SrF2 or (iii) Solid nonfissile irradiated netal3hardware and reactor control rods (blades);or.'f ,, {
- (iv) Stainless steel encapsulated solid metal Co-60 sources. ,
(2) Maximum quantity of naterial per package
- j Not to .exc'eed a decay heat generation of 3,120 watts and ;g
; (i) Iten 5(b)(1)(i) above- Il
' Plutonium in excess of 20 curies per package must be in the form I
- of metal, metal alloy or reactor fuel elements, Land 500 grams '
U-235 equival.ent cass. (U-235 equivalent. mass equals U-235 mass t
.plus 1.66 times'Pu mass.) ,t ,
~
Item 5(b)(1)(ii) aboye: lEitj (ii) E 458,000 curies. }ll
'tj i.
(iii) Item 5(b)(1)(iv) above: Ej E 200,000 curies. p! l f (c) Fissile Class III fb {~ Maxinun number of packages per shipment 22 Ej
- k i 6. For the contents described in Iten 5(b)(1)(fi) above: %b, 90 SrF Rev. b;nust and H-2-66758, be encapsulated Rev. 0; or in accordance with Vitro Drawing Nos. H-2-6 lp :
137CsC1 rust- be encapsulated in accordance with Vitro Drawing Nos. H-2-66760, Rev. 0; and H-2-66761, Rev. O. f{ 90 137 CsC1 capsules af ter fabrication must be leak tested using a The SrF and !p method hahing sufficient sensitivity t detect a leag rate (air at standard i temperature and pressure. leaking to 10'2 atn) of 10" atm cc/sec. Any capsule !h l 3 with a detectable leak may not be delivered to a carrier for transport. lN
'l l
lW I l 2:7 li l :
......m...-.m.._.-----,._.m_ a t
l i um====RifAMMLP=EkbM M M M M M I! WW1MW b ll CONOlTIONS (continued) E N; M> A: Page 3 - Certificate No. 5939 - Revision No.12 - Docket No. 71-5939 i .b R b, 'W R; t
,W
#4
- 7. :)
H. The package authorized by this certificate is hereby approved for use under the 'b 1 general license provision of 10 CFR 571.12.
)k
- 8. Expiration date: December 31, 1987. j b
b REFERENCES 'p'
,8 General Electric Company aoplication dated February 21, 1980. 9 Supplements dated: September 8,1982; August' 17, 1984; and April 12, 1985.
Oak Ridge National Laboratory-letter dated April 3,1980. .p 9; Supplement dated: May 7, 1980. > b FOR THE U.S. NUCLEAR REGULATORY C0ftMISSION j
'n f n.
Charles E. riacDonald', ~ Chief-U lh Trans po r t a tion : Certi fica t i on Bra nch ;8 Divisiori of Fuel Cycle and Material Safety, Nf tSS j l
;g in Date: liAY 01 1985 ;>
- n I
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p----------------------------- - Errs---- I macFonusis U.S. NUCLEAR REGULATORY COMMISSION i I osin CERTIFICATE OF COMPLIANCE g so cFa r' FOR RADIOACTIVE MATERIALS PACKAGES ! o aEvisioN NousER c PACKAGE IDENTIFICATION NuuBER d PAGE NuuBER e YOYaL NUMBER PAGES g t a cEntiricArs NuueEn 5942 10 USA /5942/B( )F 1 4 g l l f _ PasAusLE l l! a This certificate is issued to certify that the packagmg and contents described m item 5 below. meets the apphcable safety standards set forth m Title 10. Code of Federal Regulations. Part 71,'Packagmg and Transportation of Radioactive Material." ; l I 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 (j apphcable regulatory agencies. meluding the government of any country through or into which tne package will be transported l 1 Il f;a7NgryFgg$ISSyOE THE BASIS OF A SAFETY ANALYSl$ RE T TNE P S O APPLICA ION
.R
- l j General Electric Company General Electric Application dated flay 30, 1985, j P.O. Box 460 as supplemented. I f;
g Pleasanton, CA 94566 I: I I' c oocxtrNuweEn 71-5942 j I o coNoirioNs This certibcate is conditional upon fulfilhng the requirements of 10 CFR Part 7t. as apphcable and the conditions specahed below j k I >
\
I;; s g (a) Packagi ng [ i , I 700 l II (1) Model No.: (2) Description lf I I! A-s' teel encased lead shielded shipping cask enclosed by a double-l walled protective jacket of the 'same shape with a rectangular baseplate. The cask is a double-walled steel circular cylinder, 37-inch-diameter [l g, by 65-inch.high with a central cavity 15-inch-diameter by 40-inch ( high. Approxinately 10.25 inches of lead surround the central cavity. D h g! The cask'is equipped with a cavity drain line, pressure relief valve set-at 100 psig, and lif ting device. Closure is accomplished by a ll l silicone rubber _gasketed'and bolted steel lead filled plug. The lli naximum gross weight of the-package (contents, cask assembly, protective jacket:and base) is 35,500 pounds. f l The cask may be nodified with a 14-inch high cavity extension with an additional. silicone rubber, gasket. The modified cask is 79 inches [l g! high. The. maximum gross weight of the package (contents, modified g l cask assembly, protective jacket and base) is 40,200 pounds. ll l (3) Drawings Il The packaging is constructed in accordance with the following General f g! Electric Company Drawing Nos.: 12904768, Rev. 3; 129D4769, Rev. 4; gi and 129D4770, Rev. 5. , I I Lif ting and/or tie-down devices which are a structural part of the I package must be in accordance with the above drawings. I l l 1 I : l' I I I I l 129 l I e
!, __---s----__------------_____-----------------------
i
m m -- EEm mm m a Elim m m m = = m CONolTioNS (contonued) Page 2 - Certificate No. 5942 - Revision No.10 - Docket No. 71-5942
- 5. (b) Contents (1) Type and fom of naterial Byproduct, source, and special nuclear material contained in solid oxide or metal fom and in special fom. ;,
(2) ffaxinun quantity of material per package Not to exceed 700 pounds (including shoring), and (1) 740 gn U-235, provided that the maximum U-235 enrichment does not exceed 6 weight percent; or f.
?
j l (ii) 1,200 gm U-235, ;provided i that the fuel naterial is in the fom of ttTR-type fuelfelements with a minimum active fuel length of 23 ll,
-i nches ; or.
(iii) 220_ ga fissile material; or ' l (iv) 1,650 gm U-235, provided that the maximun U-235 enrichment does not exceed 3.5 weight percent and the fuel material is in the fom of 80 rods' loaded with 0.376-inch-diameter, pellets with a minimum active fuel length lof(37 inches; or ' (v) 'those values presented. in Figure'1, 00,, Weight i.imits for flodel 700 , iShipping Container,:of Exhibit'A to this application, applicable ,f, to fuel material,in thef fom of, of 0.401.nch; or . i rods with. a minimum pellet diameter f (vi) 5,100 gm u-235, provided ,thelfuel is in the fom of ETR-type fuel 5 eierents (GETR Fuel) with each element containing no nore than lN 510 gm U-235 and; inserted in 'the spaced stainless steel fuel ;b shipping basket described .in GE Drawing.No. 10604150, Rev. 0.; or (vii) 6,200 gm U-235. ,provided the fuel is in ~the fom of fiURR TRTR type elements containing not nore -than 775 gn U-235 per element; Mpl ' loaded and spaced in'the stainless steel fuel shipping basket as W described in MURR Drawing No.1228, Sheets 1 thru 5, Revision 0. l8 Fuel elements shall have at least 150 days cooling time since last reactor operation; or j g
, h-(viii) 3,510 gn U-235 provided the fuel is in the fom of fiTR-type fuel 9 elements with each element containing no nore than 351 gm U-235 N and inserted in a spaced stainless steel fuel shipping basket described in GE Drawing No.106D4150, Rey. 1 for GETR fuel . A
!j I 1, shoring device to limit vertical motion of the fuel elements nust )
be included. Ib
!W (ix) 7,020 gm U-235 provided the fuel is in the fom of MTR-type fuel elements with each element containing no nore than 351 gn U-235 /j inserted in a spaced stainless steel fuel shipping basket described !,
in GE Drawing No.106D4150, Rev.1, for 24-inch length fuel. Each shipment trust contain 20 fuel elements in 2 fuel baskets !g p
! with the spacer plate shown on GE Drawing No. 21886061, Rev. 0, ,I l located between the baskets, ! 130 ljl n
i I CONDITloNS (contmued) @
.h Page 3 - Certificate No. 5942 - Revision No.10 - Dacket No. 71-5942 (
lR
'k N
i
- 5. (b) Contents (continued) k (3) Maxinun quantity of radioactive deca / heat per package -l R
(i) 6,500 watts for dry shipnents, or g V l 1 (ii) 1,500 watts for wet shipments, provided that the cavity shall E E contain at least a 1,000 cu in air void (at standard temperature
' and pressure) at the time of delivery to a carrier for transport. (
(c) Fissil'e Class III 3
.k Maximun number of packages per shipment 2 g
- 6. The radioactive material rust be in the fom of fuel rods, or plates, fuel fg assemblies, or meeting the requirements of special fom radioactive material, E
- 7. Shoring nust be provided to minimize movement of contents during accident conditions t of transport. g
- 8. Prior to each shipment (except for contents meeting the requirements of special be leak tested by a method capable f
fom radioactive naterial), the' pack 'E of determining that a leakage of 10~gge
~
a tm cm ,musj/s at standard temperature and p 9 pressure is not exceeded. W N
- 9. Prior to each shipment the silicone ' rubber (lid gasket (s) nust be inspected.
This gasket (s) must be replaced if . inspection shows any defects or every twelve l (12) nonths, whichever occurs first. J Cavity drain fline rust.be sealed with g p appropriate sealant' applied to threads of ' pipe ' plug. N
- 10. The applicant rust confirm annually that the pressure relief valve is operable N at 100 psig. l k
- 11. When needed, sufficient antifreeze in the cask must be used to prevent damage of y 4 any component of the package due to freezing. ,R 9
- 12. Fabri ation of additional packagings is not authorized. f
- 13. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 971.12. }'s lN i
- 14. Expiration date: July 31, 1990. ,N iN R
ju i , t e' l [ l [ ! l
' [,
[ n; h 131 m I dl~ N b j mm smm_w_ _m_w_ _ _ - _* _ _ _ _ _ - 9 l l
M_ Mmm.=5FAAA_._._llT___.________.________-.____._______._____ __ l'; . _ . i[ CONOf TIONS (continued) I g Page 4 - Certificate No. 5942 - Revision No.10 - Docket No. 71-5942 r I
! fli lIl 'b REFERENCES l %
(i General Electric application dated May 30, 1985. j th f Supplements dated: June 5 and 7, August 7, and September 16, 1985. l Ri University of Missouri letter dated March 20, 1980. .h [ g' Appendix 6-A regarding University of Missouri's quality assurance program is not considered part of this application. i i B i g.
+
FOR TH'E[U.S.' NUCLEAR REGULATORY COMMISSION '
~ t/
ll , l' I, , I '
;i g Charles . MacDona d, Chief y d' ,. Transportation Certification Branch W l' Division of Fuel Cycle and '
I k! I; -
, Material Safety,'fllSS hi I Date: SEP18 M "- I
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g--===_-----__e.----- ,._ _ _ ,,_ _ h U.S. NUCLEAR REGULATORY COMMISSloM ,6 lI l' NRC FORM 418 CERTIFICATE OF COMPLlANCE .!I l 4l aca,o crR " FOR RADIOACTIVE MATERIALS PACKAGES c PACKAGE iDENTW BCATiON NUMBER d PAGE NUuBER f D REVISION NUMBER h- . ctRTwlCATE NUMBER 5950 4 USA /5950/B( )F 1 e TOT AL NUuB 3 , f l' 2 P cAusto J a This certificate is issued in certify that the packag.no and contents described initern 5 below, meets the applicable sa'oty standards set forth ) in Title 1, ig Federal Regulabons. Part 71,"Packagmg of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Con 1, I b This certificate does not releve the consignor from comphance with any requirement of the regulations of the U S. Department of Transportation or other in appucase r.guistory agencies. .nciuding ine government of any country tnrouan or .nto wnicn tn. pacmage wiii ne iransported 1l !h I lt I,' k f a Twis ceRTiricATs is issuso ca Tse sAsis or bATirLE a PREPARED BV (Neme and Aderosar sArsTv ANAtysisOFREPORT ANO sDENTiriCATION Or Tse PAcxAct ossicN OR APPticATiON REPORT OR APPLICATION Battelle Columbus Laboratories application f Battelle Colunbus Laborateries dated August 7, 1981. jlg 505 King Avenue lp fli Columbus,OH43201 ! li lNl 1 1 1 e oOcneT Nuusta 71-5950 4 CONDITIONS l This certificate is conditional upon fulfishng the requirements of to CFR Part 71, as applicable and the conditions specified below I l;i (a) Packaging ljl (1) Model No.: BCL-4 ) h il l' !p l (2) Description !I llj jI Steel encased lead shielded shipping package. The package is provided f with recessed plug-type lid and'gasketed, bolted closure, lifting and il tie-down devices ard r'elief valve, vdnt.line, and drain line penetra- @jy f tions. Containment for the contents is provided by an inner can l l assembly or Ay. material in special form. The packaging has dimensions, I weight, and: shielding as follows:
^
. lle 1
,3 b C 64.8 ;I f W;n Exterior r - height, in Exterior. diameter, in
'l n
Cav_ityiheight; in s
- 26.4 42.5 '[
j h Cavity'dfameteriin(ii' '
- 6. T-
]1,
<< s l
_y Lead shieldingHn j , 8.43 ) 1 I,
~
I '13,2002(Inci 270-lb skid) ll k (' Loaded' -Q(j,weight,f{bO["j @ j
' 13 <
_, i I g A l (3) Drawing s 7 , f s gj g a O; i s.b. ;- in g j! , The packaging is: constructed..in'ac_cordance with18attelle Memorial ll Institute Drawing No. BCL4-01, Sheet =1 fand 2,1Rev. D. ' ly 1l D[,. . [ / p I
.j. i lh li ~ ,n I 'o : p 1
lI I ;g I, n I ! n I
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I i !I ll lI 1l i l' l 133 lh I i 1 w, r # <_ wu_ _ _ , wsw ryw w r#_ v,#,.r_ _ _ _ _ r_ r_ #_ _ _ _ . _ _ _ _ _ _ _ _ l l
---------------------___--------_-_,----y--,---,g;--,-,
NRC FOAM sisA U.S. NUCLEAR [EGULATO":Y COMMISSG N I gj *a CONDmONS (continued i l I 'I ll 'l li Page 2 - Certificate No. 5950 - Revision No. 4 - Docket No. 71-5950 :n lli I li ll t ;p fIt 5. (b) Contents j lI I! Type and form and maximum quantity of material per package. !h I! 't li Byproduct material, source material and special nuclear material not to f exceed 400 watts decay heat in solid metal or oxide form packaged within an !>5 gi inner can assembly or the material meets the requirements of special form in radteactive material and linitations on fissile loading for the Fissile
;j g
Il Class as follows: h li II I Inner can assembly: ll
}[; Battelle Menorial Institute Drawing No. BCL4-49 Rev. C.
'I f Fissile Class I 650*
I! 11
- ( Fissile Class III 2000* ll I !I f * (grams U-235 equivalent mass) fI; (c) Fissile Class I and III lj !n Maximum number of packages !n I! per shipment for Class III I One (1) !g t
'I d 6. The U-235 equivalent mass must be determined by the following method:
I I: U-235 equivalent mass equals U-235 mass plus 1.75 times U-233 mass plus I; 1.60 times Pu nass. il l I } 1
- 7. At the time of delivery of the loaded package to 'a carrier ~for transport, the ll package contents must be (1) dry (contents of' inner can assembly must not decompose ;I
[: g up to a temperature of 750 F) and the fissile material unmoderated (H to X i l g atomic ratio less than 2) and (2) so limited that the dose rate will not exceed il l 4l 10 millirem per hour at three (3) feet from the external surface of the package. f I l 8. The maximum gross weight of the cavity contents must not exceed 180 pounds llg l (inner can assembly, radioactive material, etc.). 'I l; ' $, R Il R I. .
.g I.
1 l i !g I I I ( l - l>, k
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s w w w w w w w w w w w w w w w w w - - - - WC- - - - - - ,-rsr- - - w - _ - - - _-_ _ _ r- - -_ __ _ _ _ __ - - Ia
+ - -
+ A M N ifi m m m m A T w- i m m m a m y-i m m m m r a w n w a ,q U.S. NUCLEAR REGULATORY COMMISSION l
g NCC FORM 418A CONDIT10NS (continued' LW q Page 3 - Certificate No. 5950 - Revision No. 4 - Docket No. 71-5950 4; l l j R p
- 9. In addition to the requiro em of Subpart G of 10 CFR Part 71, each package hl must neet all of the acceptance and priodic tests specified in Section 8.0 of this Application. f
; i l n' i
; The following item in the thermal acceptance tests (8.1.6) is changed as follows: '
$ l, (4) The acceptance criteria must be that the maximum measured temperature of '
any portion of the cask must not exceed the temperatures In this indicated in comparison, <f l Figure 3.3 of this application by more than 25 F. j solar heating and ambient temperature differences between Figure 3.3 and :p i the test data must be taken into account. i I
- 10. The following item in the Test Procedure (8.1.3), Section 8.0 of the Application, h is changed as follows: ,>
- g. Remove pressurization line and insert plug in pressure port according to j e.
the loading procedure. Use teflon tape or other compatible sealant in ig f4 threads. IS 11. The package authorized by this certificate is hereby approved for use under the I general license provisions of 10 CFR %71.12. k
- 12. Expiration date: September 30, 1986.
l4: lW' 1 4:
@p REFERENCE q
4 (; Battelle Columbus Laboratories application dated August 7, 1981. i h4: t FOR THE U.S. NUCLEAR REGULATORY C0 tit 11SS10N f 4 l 4 i' d' M (L Charles E. MacDonald, Chief Transportation Certification Branch pd d' L; 4 Division of Fuel Cycle and gl Material Safety, fatSS f' fk l d
, Date.
SEP 0 61983 :g e g-g k )) i-4 6 4 135 l , 4 - MRATJE"sOrgNv w w w Ww v#w vygyggeyg w w w_TgryWm
l _
$N 'h 5 k 8' kb NM -
4 N
% .RC e FOR'1 sis U.S. NUCLEAR REGULATORY COMMISSICN -
% '0C'"7' CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES
[ i a cEamicarE NuMetR o aEvlSION NUMBER
' c FACKAGE IDENM6CA T60N NUMBER d FAGE NUMBER e rOr AL NUMBLR FAGES 5957 12 -
PAE AMBL E USA /5957/B( )F 1 1 6 p
. h in,s cert r.cate is .ssoeo to cen e, inai tne vacaag.ng ano content, aescr,ee;in item s beio. meets theappocaeie e sar t< sianoaros set tortn in T ite io coo.
Of federal Regulations. Part 71. ' Packaging of Radioactive Materiais for Transport and Transportahon of Radioactive Matenal Under Certain M Conditions ~ 0 This certie:cate coes not reneve the consignor from comphance with any requ,rement of the regulations of the U S Department of Transpo<tation or other apphCaDie reQJatory agencies includeng the government at Say Courttry through OF *ntO wnsch the package will be transported f
' '"JE,"4' a E "S'e','f,'"!'f %.',",' "*' '
- S^'"'
**^'"."'f?"E No',"c'E T,"c^fr'8Es hi"c 'i"#*N'a, i~r o Battelle Colunbus Laboratories 505 King Avenue Battelle Columbus Laboratories application dated June 20, 1985. I Columbus, OH 43201 l
c oOcnn NuMeEn 71-5957 4 CONDsTIONS l Tn s cen t. cat .s cono,t ona, upon fuit,mng ine requ.rernents of io cr A Part ri. as apphcatie. ano tne co, o.isons spec t.eo eem. s p (a) Packaging b p (1) flodel No.: BMI-l ;h 5 (2) Description l~
;hl i
A steel-encased lead shielded shipping cask. The basic cask body is a ! k, cylinder 33.37 inches in diameter by 73.37 inches high fomed by two ! concentric stainless steel shells whose annular region is filled with
@ lead. The outer 1/2-inch thick shell has a 0.12-inch thick plate spot lh 4 jh l welded to it, providing a 0.06-inch thick air gap insulator. The il
{ inner shell is 15.5 inches inside diameter by 54 inches inside length. The cask lid is a stainless steel weldment having 7.75 inches of lead j shielding. The cask lid is secured to the cask by twelve steel studs !p which are welded to the cask body. The cask is- b line with needle valve and plug, pressure gauge,provided with a drain 't and a pressure !b relief valve. The total cask weight, including iraximum contents of h 1,800 lbs, is 23,660 lbs. (3) Drawings
@ll l
b y The cask is constructed in accordance with the following Battelle '9 l tiemorial Institute (BMI) Drawing Nos.: 43-6704-0001, Rev. B; and I 41-4409-0003, Rev. B. i 4 in il l
!lb
!b
- s
{N il
@8 i
il
'l 136 I l
I m_m_m_v__m._______m_____________________________ -___
m mL*_m m_h4W m.=L@M1M_MNMAm .m.._ T ll_^ZT Tl . _ _ __ _ _ ___ ( ' CONDITIONS (contmuod) ll l. I Page 2 - Certificate No. 5957 - Revision No.12 - Docket No. 71-5957 N k I; g! 5. (a) Packaging (continued) ll I; (4) Product Containers , I; The various authorized product containers are constructed in accordance [ gj with the following Drawing Nos.:
!i (1) Inner can assembly as shown in BMI Drawing No. 00-000-421 I Rev. C.
i; f (ii) Basket Assembly as shown in BMI Drawing Nos. BCL-000-500, f
~
i Rev. A; BCL-00,0,501; uReyD.A.; and 0048, Rev. A. g g . Il (iii) Fenni' Fuel Element copper casting. assembly as shown in BMI . I; Drawing No. K5928-5 0049D, Rev. to May 12, 1966. . 1 R, ; ;> (iv)eBasket Assembly as shown in BMI Drawing No.1020, Rev. B or , [i g'
'GA Drawing No. 9590001, Rev. A. Failed fuel assemblies nust y 1
M be' seal; welded in aluminum or stainless steel tubes with h 1 '., j wall and.end cap thicknesses .of at least 0.015 inch. h 1 11 * , b 1 '(v) Basket Asssnbly defined by BMI Drawing No. BCL-000-500, j " Rev. A, as nodified by BMI Drawing Nos. 00-000-236, Rev. C, l and BCL~-000-502, Rev. B.-
~ ' '
g 5 . (v'i) Basket Assembly 4a'nd ? storage can defined by BMI Drawing No. l 1; 00-000-391, Rev. C,:and Atomic International Drawing No. AIHL, . h _ k (i S80R 0019-01,
. Rev.;A, respectively. i di j'
]
y (vii) Inner can assembly as shown in Union Carbide Corporation Drawing No. 101501, Rev. A. ; N 14
' ' 't 1l (b) Contents ,
b 1, ll (1) Type and fonn of material j
'N 1! Intact irradiated MTR- or BRR-type fuel assemblies containing l l' (i) not more than 200 grams U-235 per assembly prior to irradiation. llp l! I lj Uranium may be enriched to a maximun 93 w/o in the U-235 isotope. Active fuel length shall be approximately 25 lk " l li, inches, j l
(ii) Intact irradiated Enrico Fenni Core. A fuel assembly containing !,g lj not more than 4.77 kgs U-235 prior to irradiation. Uranium ll l .nay be enriched to 25.6 w/o in the U-235 isotope. il l lj i ]
.I I
l ll if l I ll lI ju l il l i 107 l I .. __ m
,,d,
Page 3 - Certificate No. 5957 - Revision No.12 - Docket No. 71-5957
- 5. (b) Contents (continued) {N -
4 (iii) Greater than Type A quantity of radioactive material which may ig include uranium enriched in the U-235 isotope, U-233, plutonium, b* p1 as metal, oxides, or compounds which are themally stable up to 6 00 *F . plutoniun in excess of twenty (20) curies per package i must be in the fom of metal, metal alloy, or reactor elenents. t (iv) Greater than Type A quantity of byproduct material meeting the requirements of special fom radioactive material, p/j t cl (v) Greater than Type A quantity of, byproduct material in nomal fom 9} b t as metal, oxides, or compounds w'11ch are themally stable up to 600 F. -l (vi) Irradiated Triga Type fuel assemblies described in Section 6.6 of h b the application (pp. 6-23 through 6-24(c)). F (vii) Irradiated S80R fuel elements 0.56-inch OD by 18.7 inches long by 0.010-inch wall thickness of Hastelloy-N. The fuel material is UZrH fully enriched in U-235. p, (viii) Intact irradiated CP-5 fuel assemblies containing not more than j 176 grams U-235 per assembly prior to irradiation. Uranium may >, be enriched to a maximun 93 w/o in the U-235 isotope. Active - fuel length shall be 28.5 inches. (ix) Solid nonfissile irradiated hardware which may contain encapsulated
- fission r:.onitors.
14 s
$ (x) Irradiated uraniun oxide waste enriched in the U-235 isotope up f4 to a nominal 93 w/o which are themally stable up to 800 F. p (xi) Irradiated uranium enriched in the U-235 isotope meeting the r requirements of special form radioactive material.
(2) Maximun quantity of material per package f, The minimum cooling time of each fuel assenbly and rod is 90 days, p [ naximum decay heat generation per package not to exceed 1.5 kw, and # the external dose rate not to exceed 10 nrem/hr 3 feet from the external A {a surf ace of the cask and: D e- (i) For the contents described in 5(b)(1)(i): 3
' Twenty-four (24) fuel assemblies as contained in product containers !F specified in 5(a)(4)(ii) or 12 fuel assemblies as contained in product containers specified in 5(a)(4)(v).
{iba{ 6mmm
;w f
-em-mmmmmm__.mm.mJ
! m wfEATfL'Iscm IaFEstGNEut www E5562w CONDITio NS (contonued) E Page 4 - Certificate No. 5957 - Revision No.12 - Docket No. 71-5957 6
, 5. (b) Contents (continued) '
(ii) For the contents described in 5(b)(1)(ii): One (1) fuel assembly as contained in product container specified in 5(a)(4)(iii). (iii) For the contents described in 5(b)(1)(iii): L 480 grams U-233 or 480 grams Pu-239 or 800 rams U-235 as contained in product container specified in 5(a)(4)(i . It l (iv) For the contents described in 5(b)(1)(iv): Gamma sources securely confined in the cask cavity to preclude secondary impacts during accident conditions of transport. Themal heat generation rate is limited to 200 watts. (v) _For the contents described in 5(b)(1)(v): Contained in product containers specified in 5(a)(4)(1) and 1imited to 200 thermal watts. (vi) For the contents described in 5(b)(1)(vi): Thirty-eight (38) fuel assemblies as contained in product containers specified in 5(a)(4)(iv). Fuel assemblies with an initial enrichment # (U-235 in U) of greater than 70 w/o U-235 are limited to 19 / assemblies per product container. Shipments of less than 19 assemblies with a U-235 enrichment greater than 70 w/o nay be combined with assemblies of 70 w/o U-235 or less provided: x/38 + y/19 _ 1; x = no. assy's _ 70 w/o U-235, y = no. assy's ,W 70 w/o U-235. (vii) For the contents described in 5(b)(1)(vii): d Twenty-four (24) fuel elements per can and six sealed cans per basket as described in 5(a)(4)(vi). Each of the six cans may contain up to 818 g U-235 and 158 g hydrogen. The cask is limited K to 4.908 kg U-235. g (viii) For the contents described in 5(b)(1)(viii): Twelve (12) fuel assemblies. fG f I _ i L~ ~~ M557MidKQLE!]kluCutW3iihDWMigbfdeM;iERrFjvjud
~
Akrv s,mg s ~ ~ ~ '
r .mm-----w,--===wwwwswam$ { conomons ccontinuem w t f Page 5 - Certificate No. 5957 - Revision No. 12 - Docket No. 71-5957
! k 11 k tl >
j{ 5. g (b) Contents (continued) f (ix) For the contents described in 5(b)(1)(ix): 5 Thermal heat generation rate is limited to 200 watts. l (x) For the contents described in 5(b)(1)(x): Twenty-four (24) containers each limited to 352 rams U-235 as I'g contained in product containers specified in 5(a (4)(vii). The ' decay heat per conkainerlis limited, to 20 watts. The containers must be leak tested in accordance with. Union Carbide Corporation
~
letter dated' November 17 1380. . (xi) For the' contents described in 5(b)(1)(x )O '
. p' Twenty-four (24) capsules each limited to 100 grams U-235.
;W
'. h
'N (c) Fissile Class ~ '-
f..f . (I, a'nb, III s -
.[
1 - f i d; (1) Class'I *
' ~ .For the cont'ents s ecified=in 5(b)(1)(iii) )p
'and limited ,in.5(b (2)(111)..
b OmW .h (2) Maximum number of . packages per' shipment C5
.Fon the contents specified'in 5(b)(1)(i),
11)S5(b)(lD(vi),5(b)(1)(vii), j as Fissile Class III :5 T)(viii),$ _ ix),and5(b)(1)(xi); a and limited'in,5 i ' 5(b
, 11), #a-vi),;5(b)(2)(vii , 5(b
~
'5(b viii), :I 5(b '1x),and5(b)(2)(xi):
l One (1) package.
- 6. For Iten 5(b)(1)(iii),
!}1 !.. following equation ismixtures satisfied:ofifissile enterial are authorized, provided the f lI (1 ' E- 11 X Y Z I g +
g + g 6 [I; 1, where j I l; X = Grams U-233 to be shipped I l Y = Grams Pu-239 to be shipped lt [! Z = Grams U-235 to be shipped i I i f 7. Except for contents described in 5(b)(1)(ii) and 5(b)(1)(iv); and limited in I! 5(b)(2)(ii) and 5(b)(2)(iv), the cask cust be shipped dry. I 1;
!l; 1
il R: 1 I p I I; ' l l I l g; 140
l
____________________ _ _ _ _ ______a --
1 NA @ _ %%MNWAN
'E l \\l CONDITIONS (continued) ll, l' Page 6 - Certificate No. 5957 - Revision No. 12 - Docket No. 71-5957
.8
\
if 1R' lgl 8. If the cask contents of 5(b)(1)(ii) or 5(b)(1)(iv) are shipped wet, the licensee il nust confirm that the pressure relief valve is operable (set pressure - 75 psig).
!G When needed, sufficient antifreeze in the cask must be used to prevent damage of any component of the package by freezing.
- 9. Loading and unloading operations of the contents described in 5(b)(1)(iii) and limited in 5(b)(2)(iii) nust preclude contact of water with the contents.
! 10. The presence and effectiveness of the Boral poison plate in the Basket Assemblies as shown in BMI Drawing Nos. CCL-000-500, Rev. A; 0048, Rev. A; and 00-000-236,
- Rev. C, must be verified by neutron-measurements prior to first use and records maintained of such verification. Verification of the presence of the Boral nust be made in each subsequent \use.
- 11. Contents 5(b)(1)(1),and 5(b)(1)(x) may be mixed provided the sun of the product f
I containers and fuel; assemblies does not exceed 24. lni 12. Contents must be ' securely confined in the cask cavity to preclude secondary I lil impacts during accident conditions of transport. p i I 13. Prior to each usi, adequacy of containment vessel' rust be denenstrated by perfonn- A R ance of the leak ^ test described in Section 7.1.1.1 of the application.
]r ,.
A
- 14. Gaskets and seals' (cask and fuel canister) must be replaced at least every 12 '
- W nonths or earlier if visible degradation cccurs, j M
[5 M li 15. The package authorized by this certificate is hereby approved for use under the j general license provisions of 10 CFR 671.12. M i 16. Expiration date: Augus t 31, 1990.
. i,-
[j REFERENCES g Battelle Columbus Laboratories consolidated application dated June 20, 1985. FOR THE U.S. NUCLEAR REGULATORY COMMISSION ' i M
' i I
Charles E. MacDonald, Chief Transportation Certification Branch . Wision of Fuel Cycle and R$ 1 Material Safety, PfiSS f
,g; Date: AUG 151985 l i8 l
) l! ;
+
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- 3 J@ M IaU * " " " *
- l
'8 0 " " CERTIFICATE OF COMPLIANCE
@ FOR RADIOACTIVE MATERIALS PACKAGES j
f i a ctRrwicatt NUMBER t> RL VISiUN NUMBEM C MCKAGE IDLNTSCA tlON NUMB 4R d MGE NUWER e tot AL. NUUutR PAGES i j 5971 5 USA /5971/B( )F l_ 3
, [PREAkutE
- A i
l Ths5 Cerref< ate 5 eS$ued 10 Cef tif y that the pac) agsng and contents descr* bed en item $ belo. meef t the apphcable 58 f ety standards set fortn en Titie to, code I ll of Federas negwat.ons. Part 7L packag, rig of eacioactwe uateriais for Transport and Transportation of nadioact,ve Mater.ai unoer certa,n cond.t.ons - lI b in.s certdecate does not releeve tne consignor from cornphance .ein any requirement of the regulations of he U S. Department of h ansportation or other il appucwe requiatory agenc,es. .nc4ud.no tne go.e,nre of any country enrougn or into .n.cn ene pac age .ai de transpo,ted i' lI .' {i;
' ' " ^ " " ^ " ' " "
* '**Et,".'l5's'I4*a'",
a iA "1 a f4 O EWC 0 FO T APT"CA T1086 General Electric Company General Electric Company application dated P.O. Box 460 tiay 30, 1985. b 4 Pleasar. tan, CA 94565 h i ^ l ) c occuv Nuuoca 71-5971 j 4 coNoir o~s > ini cert r.cate .. cona,t,ona, ucon ruininn, tre reau,,ernent, of io cra e.. 7 t. .. appocaeie. and tne cond+on ,pec.,,ed ne,o. l . 1
; Ms '
i
- 8
; (a) Packaging j (1) flodel No.: 200 i y
t j (2) Description > U-i A steel entesed leac @dda shipping cask. The cask is a double- ' ' walled steel circular cylint , 20-1/4-inch diameter by 53 inches high i with a central cavity 7-5/f-i.*rh diameter by 37 inches high. Approx-inately 5-7/8 inches of letsi m G und the central cavity. The cask is
- equipped with a cavity dra1n line vi lif ting device. Closure is accomplished by a silicone rubber gasketed and bolted steel lead filled plug. For additional shielding, lead-filled stainless steel ;
l liners may be inserted in the cask cavity. A protective jacket consisting of an upright circular cylinder with open bottom and a l ' protruding box section diametrically across the top and vertically ; down the sides attadas to a square pallet. Dimensions of the protective jacket ar (5-3/8 inc* , s high by 37-5/8 inches wide across the box section. N c. iter cylvdrical diameter is 26-3/4 inches and the j pallet i! ;r-11! inches n.are. The naximum weight of the packaging , is appros)nneh 10,000 pounds. y
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I li . F: l In B: ki gi I. 142 ;f-i l 1 0 ! 1
.a m uNie w s-wu mm mmfans'w amm mm uw-= = = = = w w mmw e w ww w w w ww w w w.w w w w war nw,..,, - - , , - , . . . , , - - , - . - - , , -
-~-.-.,,,.cn . - . - - - - - . - - , . - - - .
N ? N ATE"EMMNSMN..f_
^ ' coNomoNS (continued)
) d Page 2 - Certificate No. 5971 - Revision No. 5 - Docket No. 71-5971
- 5. (a) Packagirig (continued) )
; }, (3) Orawings jj The packaging is constructed in accordance with the following General
+!
f {f u: 8( Electric Company Drawing fios.: I 12904756, Rev. I 12904758, Rev. 1 129D4759, Rev. 0*
}
129D4757, Rev. 0** i lg *All components are to be considered safety related. E ** Item 14 must be 47.5"x4"xl" , d. , (b) Contents p c j (1) ' Type and fom.of material i (1) Byprodudt and special nuclear material in the form of fuel rods, or. plates, fuel assemblies, or ineeting the requirements of special F fom radioactive material; or I. 1
.$ol'id nonfissile irradiated rnetalihardware,'re' actor control rods (ii) f(blades),' and reactor start-up sources,
[ g; i-
, , p.
'g!
(2) Maxi _mun quantity of .mateiral per package' E
^
Radioactive decayheht not to exceed L780 watts and 500 grams U-235 I: equivalent mass. (U-235 equivalent mass equals U-235 mass plus 1.66 [: times U-233 mass plus ~ 1.66 times Pu mass.) g. 0 Plutonium in excesstof twedy (20) curies per package cust be in the a 5: fom of metal, metal alloy, or reactor elements. i k:
'Il (c) Fissile Cisss [0 '
E
< Hinimun transport index to be shown on label Contents 5.(b)(1)(i): p p
2.3 P
- 6. Shoring rust be provided to ninimize movement of contents during accident jj conditions of transport.
A
- 7. At the time of delivery of the loaded package to a carrier for transport, the P P
d package contents rust be dry and the fissile material unmoderated (H to X atomic ratio less than 2). j
- 8. Prior to each shipnent (except for contents meeting the requirements 6f special j forn radioactive material), the pack ).
i of detemining that a leakageatm of 10~3ge rus3 temperature cn /s at standard be leak tested and by a meth ) i i i pressure in not exceeded, j
- 9. Prior to each shipment , the silicone rubber lid gasket must be inspected. This jl p
- gasket must be replaced if inspection shows any defects or every twelve (12) f months, whichever occurs first. Cavity drain line rust be sealed with appropriate ja sealant applied to threads of pipe plug. l d 1n #j f
................._.__..__J 8 -- .
m - - - - ._.._,.-....c. _ . , _ , - , . _ ,---__%__ - - - . ,,
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- t. CONDl110NS (contrnued}
i
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8-Page 3 - Certificate No. 6971 - Revision No. 5 - Docket No. 71-5971 ! WI ll 10. Packaging must be maintained in accordance with Chapter XVII, Cask /Fireshield M Maintenance, in Enclosure E of General Electric Company's application dated ;>i November 15, 1984, as cited in Certificate of Compliance No. 5980. i' a g
- 11. Fabrication of additional packagings is not authorized.
- 12. The package authorized by this certificate is hereby approved for use under the k:
general license provisions of 10 CFR 971.12. i: P
)!
l( 13. Expiration date: July 31, 1990. ,_ I 1 N 1
,- t y',
e Tb D 0 () , , REFERENCE 1 .V 3 , < f General Electric Company {ahplication dated flay 30, 1985. , , 3 q e j, i d . FOR THE U.S. NUCLEAR, REGULATORY C0ft11SSION 'y h ? ' rs m ;n Vj
.JQ ~
, l,;I . ,~
^
~
s' ] 1 N} = Charles E. itacDona .: Chief i-
$[ ,~^ Transportation Certification Branch t, i
s 1 ,l' ^ a
- Div'ision'of fuel Cycle and ;h 34 . Q;rr o f j lNaterial > Safety, fMSS l>
Date: NE '
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__ _ _ _ . - _ _ _ _ _ .[RM5WAAW4=AM @ m m.= W _* =C= = N N M M N - I NRC FORM 618 CERTIFICATE OF COMPLIxNCE U.S. NUCLEAR REGULATORY COMMISSION '. i l < e .a. > Y' ' C'" FOR RADIOACTIVE MATERIALS PACKAGES 'h 4 o atusio~ woea a i eau oe 'oe~r.,,cario~ %usea a e.ua ~uum a .vorat uussae oes y 4 i . cear. cue 5979 ~uueta 6 USA /5979/B( ) 1 2 p p .> maume in.s cen,r,cate .s.sse o io cen,e, m.i me paca.g.ng .no cor ients oescr oea m iiem s de c. me is ine.ppnc.nie s.t.ty si.no.ros see,ortn e r.iie io cose ) L .
!)
l( of feoer.1 Regu4t ons. Part 71. P.C..Q'ng Of R.dio.cieve Ma:en.is for Tr.nsport .nd vrknSport.fion of Radso.ctive M.ieri i Under Cert.m Conostions '
! l o in.s cen r care ooes not ree.e e ine consignor from comob nce witn any regerement or me requi.nons of ine u s Dep.rtment oe Tr.nspon.i,on o, ome, l>>
appocante regautor, .genc es. ncioo.ng me go.ernment of any counir, mrougn or into *nicn me pacuse ..n de iransponeo ;l' d, N 4 ')
$ 2 rms cear.. care is issuno.o~
. mm.ao ev ,s e ..m vs 8 sis o, . s ,erv .~.usis asno, vnte ~o r.c, r~a enca.ca iu~rnication o, asroar oes.o~ ca mucar,c4 oa reocaria~
n,i > 4 Alpha-Omega Services, Inc. Alpha-Omega Services, Inc. application dated ) t June 1980, as supplemented. ;> A 16220 Gundry Avenue <D Paramount, CA 90723 19 W 71-5979 { r c DOCKE T NUMBER I
, co~onio~s ini. cente.c.ee ,s cono.i.on.i upon ,se.n.ng tr. requ,rements Cf 10 CF A Part 7L .5.ppbc.ble ano the conoitsont specified tWow ju s .g (a) Packaging 5 I
- (1) Model No.: 5979 i (2) Description A shipping container for teletherapy cobalt sources. Configuration of 's the outer container is box-like measuring approximately 38" x 50" x 40". N
.I The box is lined with 4.5" of plywood with a 0.125" outer steel shell welded to an exterior angle framework. Transverse strips across the j 9
bottom facilitate use of a fork-lif t and lifting lugs are provided at 'y the four top corners. The inner shield vessel is essentially a 24" ) diameter, lead-filled, barrel-shaped configuratie;n. Three different 'I cylindrical plug inserts and bolted end caps provide flexibility to 1k I acconmodate several sizes and shapes of sources. Gross weight is approximately 5,000 lbs. !j (3) Drawings ;ig
,1 The packaging is constructed in accordance with Alpha-Omega Services, Inc.;Iil Drawing Nos.: 0090, Rev. 0; 0091, Rev. 0; 0092, Rev. 0; and 0093, 3 i
Rev. O. ;I id I I lII l- , d' : I d, I 4; I d I i, I I I l! I i, I I, I t I I '. I W I45 l cf i- .... - -- ......... --- w.----- -- -- --....------I
MN_WWMW 4 N%NA_EW1M%%iN I ._ . _ jt' CoNolTloNS (contsnued) e Page 2 - Certificate No. 5979 - Revision No. 6 - Docket fio. 71-5979 3 1
;j 5. (b) Contents 1
1 (1) Type and fonn of material
- 1 Cobalt 60 or cesium 137 as sealed sources which meet the requirements
}11 1
of special fom radioactive material. j (2) flaximun quantity of material per package
'1
;1 15,000 curies Co-60 or 3,000 curies Cs-137, with decay heat load not
- 1
't to exceed 200 watts. * ,- o c- -
\,, ;.'l l 6. Lif ting eyes shall be covered dr'b' locked to prevent ute as tie-down attachments.
1 1 7. The shield vessel closures shall be equipped with gaskets.
.1
- 1 8. Bolts used to secure the shield vessel closure caps shall be secured against
( loosening by vibration during transport. . j 9.
~
The package aut$orized by th1s' certificate is,he by approved for use under the -
- 1 general license' provisions 'of.1,0 CFR 971.12. l ;
1 , ? 1 10. Expiration date: July 31,1990. ' . t j I REFERENCES I , i . J Alpha-Omega Services, Inc. application.dat,ed June 1980.- 3 1 -
',p j
Supplement dated: April 12, 1983.
.l
~
FOR THE U.S. NUCt. EAR REGULATORY COMt1ISSION f 1 s , lf]
- p hl l
y Charles E. MacDonald, Chief Transportation Certification Branch {Q g Division of Fuel Cycle and )
'I Haterial Safety, NMSS 'n Date:
I, I 1 H I il I !b s, jh I, s i ju l I!
,, i,ln I l,l i.
li 146 1, l,I N L_________________________-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ m_ _m m ,J!
__ ___._ M A'A N 'N W A======Am*wwwm5 WAW - " ** *
' $"a5N" CERTIFICATE OF COMPLIANCE io cr R " FOR RADIOACTIVE MATERIALS PACKAGES D REVl510N NUMBER C F'ACKAGE IDENt,HCATION NUVtlER d PAGt NUMBER e TOT AL NUMBER PAGES .
t a CERTIFICATE NVMBf R ' 9 USA /5980/B( )F 1 3 5980 PRE AMBLE a Th.s certificate as issued to cert #f y that the paciiaging and contents described in item 5 below. meets the appsicable wiety standaros set forth en tette 10. Code O f Fedetal Regulations, Part 71. ~ Packaging of Radioacteve Materiars for Transport and Transportat.on of Radioactme Material Under Certa.n Conditions l b This CertiftCafe does not febeve the cortsegnor from compliance *+th any requirement Of the regulations of the U S Department of Transportation or othee appiecable regulatory agencies. including the government of any cJu n try through or into which the paciiage will be transported
' ' '"ik',".'Ls's'M.'*a'!fC,' ' ^ *^" ^"."W"c' a
No',"o'tOS"!fsoN $?" ,"oM&?,"C, Tion General Electric Company General Electric Company application dated P.O. Box 460 November 15, 1984, as supplemented. ; Pleasanton, CA 94566 71-5980
} c OCCeLET NUMBER '
a COND*TIONS This Certtf cate is Cond.tional upon fulfilhng the requirernents of 10 CFR Part 71. As apphcable. and the cand tions specified below 5 (a) Packaging (1) Model No.: GE-600 (2) Description A steel-encased lead shielded shipping cask. The basic cask body is a cylinder 34 inches in diameter by 59.12 inches high forned by two concentric steel shells whose annular region is filled-with 6 inches k of lead. The cavity is 20-1/2 inches ID by 46 inches high, 3/8-inch h thick stainless steel cylinder. A recessed plug-type cask lid, consisting g of a steel weldnent filled with lead, is secured to the cask body by B' six l-inch diameter steel bolts. A silicone rubber gasket provides ) the seal. A protective-jacket consisting of a double-walled structure l of 1/2-inch thick carbon steel plates is placed over the cask and , bolted to a steel pallet by eight 2-inch diameter steel bolts. The 'y cask has one 1/2-inch diameter drain line from the cavity to the outer 'pl s hel l . The cask is shipped in the upright position. The total weight 'N of the package is approxinately 23,300 pounds when loaded. j (3) Drawings )
'n The packaging is constructed in accordance with the following General ;h Electric Company Drawing Nos.: 12904742, Rev. 2; 12904743, Rev.1; jh and 12904744, Rev. 2. @I
; Lifting and/or tie-down devices which are a structural part of the package rust be in accordance with the above drawings. ll
!I (b) Contents {Nl (1) Type and form of material il Byproduct material and irradiated special nuclear material in solid or solid oxide fom, but specifically not loose powders. Contents are to lIlI I
be clad, encapsulated or contained in a metal encasement of such material as to withstand the combined effects of the internal heat l load and the 1475 F fire with the closure pre-tested for leak tightness. g f Also, byproduct material and irradiated special nuclear material meeting the r_equirem_er.ts of special fonttradioactive naterial,__ llI l 4 ,
. . ,<. 4.. .
y ,..., ...,----------n
- 4. .
147
%M_N4Mb5MI5NNMTN1N_W_MMMMMMM d'
il' > CoNDITloNS (continued) > l ( Page 2 - Certificate No. 5980 - Revision No. 9 - Docket No. 71-5980 9 b
- 5. (b) (2) flaximum quantity of naterial per package j Plutonium in excess of twenty (20) curies per package rust be in the j q fom of metal, metal alloy or reactor fuel elements, and y i
i 'D 4 (i) For the contents described in 5.(b)(1) the naximun decay heat not t to exceed 600 watts and the fissile content not to exceed 500 i l3 grams of U-235, 300 grams U-233, 300 grams Pu, or a prorated > quantity of each such that the sum of the ratios does not exceed unity. When the contents of this paragraph are in the form of ( g irradiated reactor fuel, the fuel must have been cooled for a p minimun of 90 days,3 and no more, than 10,000 ci of noble gases b
~
rod plenums. The > cask must nust be leak tight for. be available to 1 xrelease 10-3 atn-cm(frora the fue}/sec underl non conditions of transport; or (ii) For the' contents described in 5.(b)(1) the maximun decay heat not ;kp 1 to exceed 600 watts and the fissile content not to exceed 1200 W grams fissile provided: (1) the fissile material is contained in N y({$ standard waste-liners constructed of;5-inch Schedule 40 pipe with a maximun inside length of 39-5/16' inches (2). no more than four 4 lg.
' such liners are shipped at'one: tine,-(3) each liner contains no l
'y t
P more than 300 grams fissile, and'-(4) the cask is.provided with a e positioning lattice to maintain Lseparation between the liners. >
}
. p (c) Fissile Class , 'II[andIII $. j g
I i (1) Minimum- transport index tolbe' i p l For the contents specified in shown on label for Class:II S =5(b)(1)~ and limited in f
'N 4 5(b)(2)(i). ;h
{ q
, , 8.4 ' -'
g (2) Maximun number'of packages For the contents specified in p I per shipnent for Class III i 5(b)(1) and limited in 'l {l ,, 5(b)(2)(ii). [ Two (2) i l 6. The U-235 equivalent mass must be determined by the following method: 1 ll h f U-235 equivalent mass equals U-235 nass plus 1.66 times U-233 mass plus 1.66 times !lI Pu mass. f7. Package contents must be dry and the fissile material unnoderated (H to X atomic ) ll I; ratio less than 2). b I 8. I The cask must be delivered to a carrier dry and the cavity drain line nust be I [; i closed with a plug which will maintain its seal at temperatures up to at least I 1 620*F. I l l% l 1 r ll 1 u e i 148 i i I ____________________________________________w.mm_m_t
CONOlTioNS tcontinued) Page 3 - Certificate No. 5980 - Revision No. 9 - Docket No. 71-5980 F1 a 4' 9. Prior to each shipment, the silicone rubber lid gasket (s) must be inspected. fg This gasket (s) nust be replaced if inspection shows any defects or every 12 months, whichever occurs first. Cavity drain line rust be sealed with appropriate
-j . sealant applied to threads of pipe plug.
1
-1 10. Fabrication of additional packaging is not authorized.
4l f 11. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 671.12. 1 1 13. Expiration date: fia rch 31, 1990. 1 :- d, - REFEREllCES - i
-1 l General Electric Company's . app'.lication dated November 15, 1984.
I 1 t Supplements dated: Februa)y' 25 and flarch 8,1985. $ 1 b i _ FOR THE U.S. NUCLEAR REGUI ATORY COMfilSSION k I k
.Rl 1 -
1 b' B 1 Charl es. . H cDon d, o te R 1 Transportation Certification Branch l> Division of Fuel Cycle and ll [ g Material Safety, fftSS jl hlDate: APR 011985 [ e i i s ij R ij k i, p h 1:
' d I I :W y
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l M T'St2NNAuiM5'nNu^mS2WSNE_S**WN***DW***J$***
! fvRC FORM sts
+ am U.S. NUCLEAR REGULATORY COMMISSION
C'" " CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES :
1 a CERTIFICATE NUMEnER b HFVIMON NUMBER = PAC 8L AGE IDENilF IC AT'ON NUM9E R d PAGE NUMBER e TOTAL NUMBER PAGES 5984 4 USA /5984/B( ) 1 2 4 PREAMBLE ( I a This cefhhcate es issued to Certify that the packaging and corite9ts described m item 5 belci , rr ets tne apphcable safety standards set fortn in Tatie 10. Code ll Of Federal Regulat*cns, Part 71. ~ Packatng of Radioactive Materiars for Transport and Transportation of Ra$oactive Material Under Certarn Conditions ' k b Trus cert.ficate does not 'eheve the cons gnor from comphance w,tn any requerement of th; eegul.t.ons of the U S Department of Transportat*on or ciner fk apphcable regulatory agencres, including the government of ariy country thsough or ento w*uch tee package weH be transported It pi 3 THIS CERitFICATE IS ISSUED ON THE Basis OF A SAFE TV ANALYSIS REPORT OF THE PAcal AGE DESIGN OR APPLsCATION a PREPARED BV iName and aaPosss b TITLE AND rDENTIFICAYtON OF REPORT OR APPLICATION J. L. Shepherd and Associates J. L. Shepherd and Associates application 740 Salen Street dated September 12, 1974, as supplemented. Glendale, CA 91203 a g
< DOC ETNUMeER: 71-5984 y a CONDITIONS This certificate is cond.fional op9n fuitilhng the requerernents of 10 CFR Part 71, as appbcable, and the conditions specified below .
s (a) Packaging k (1) Model No.: 5984 l (2) Description 'E E
'E A protective overpack which provides impact resistance, and themal F-resistance for its contents which are contained within a single snug-fitting shielded inner Type A packaging. The overpack consists of a [
p vented-steel jacketed, laminated plywood outer container. Dimensions of the overpack are approximately 28" in diarneter by 43" high and the ln-k; plywood thickness is approximately 4" on the sides and 6" on the top II and botton. The total weight including weight of the contents is approximately 1,780 pounds. (I i (3) Drawings 'g; R:
' y The overpack is constructed in accordance with J. L. Shepherd & Associates I Drawing Nos. A-0068-2C-1 and A-0068-2C. E i
i
.i
!g The inner shielded container is constructed in accordance with J. L. 1 Shepherd & Associates Drawing No. A-0068-1B or D0T Specification 7A t packaging. The special fom source capsule is constructed in accordance l3 in
, with J. L. Shepherd & Associates Drawing No. A-0068-10 or to meet the requirements of special fom radioactive material, j!8 4
>k i l
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l t I y l 150
! l
-- ------- ----,.rsr- ----- - - -- rwwwwww-- r-r- -- - ,.rwws.rw,.rww.cs w-r r-wu
'4 ' CONDITloNS (continued) 3 ,
- 1 Page 2 - Certificate No. 5984 - Revision No. 4 - Docket No. 71-5984 3
4 1 5. (b) Contents il j (1) Type and forn of naterial Cesiun 137 is cesium chloride sources doubly encapsulated in stainless lg; steel tubes to meet the requirements of special form radioactive 4 naterial. 4 j (2) Maximun quantity of material per package l 12,000 curies. _ - c- _'p~ il 6. Contents nust be positioned witNn a'sinhle snu[-fitting shielded Type A packaging M within the protective overpack. The Type A packaging nust have a metal outer wall and neet the requirements of D0T Specification 7A packaging, { j 7. New construction of[operpacks are not authorized under this Certificate of
- q. Compliance.
4 , - ), .. ,. 4 8. The package authorized by this 'certicate is hereby _ approved for use under the j general license l provisions of 10 CFR 971.12.
./ .
t 3 '
- 9. Expiration date: , Ma rch 31, 1990. ' '
; p
~.
p t ,,., - J-nn. # N, i' 8; > 1, g . sis,'1 i t'
.iREFERENCES ])lJ. L. Shepherd and Associates' application dated.c_; September 12, 1974.
3 . _.x g y,s ' G
- 3 'f ,
Supplement dated: January 20, 1975. .
}i "
7~
.j, FOR THE V.S. NUCLEAR REGULATORY COMMISSION
> . A ; ,, % ~3~
f i n 3 Charles E. flacDona d. Chief
- 1 Transportation Certification Branch ;
Division of Fuel Cycle and j
'ji Material Safety, fitSS i g
3 lR
$' Date: MAR 181985 4
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EE-----rea--- ----_- l i NaC ronM sis U.S. NUCLEAR REGULATORY COMMISSION Y ll i+sai CERTIFICATE OF COMPLIANCE in lj io crn it FOR RADIOACTIVE MATERIALS PACKAGES !N f , . canYwicA'E NUugER tp AEviSiON NUMBER c PACKAGE DENTIFiCATeON NUMBER d PAL 0 NUMBER e TOT AL NUMBf R PAGES 6002 2 USA /6002/B( )F 1 2 jll
- 1. caEAustt a in,s cert,', cat. is inued to cen,ey maiine pacing.no and contents descrieed mitem s oeio.. meetsine appiscadio safety siandards set fortn m Tiiie io. Code of y] Federal Regatations. Part 71. " Packaging of Radeoactive Matenals for Transport and Transportation of Rad *oactive Material Under Certam Conditions "
;g lg 3: o in.s certificate ooes not reheve tneconsignor from cornphance with any requirement of tne regulations of the U S Depanment of Transportation or other y appacw. reguistory agenc.es. inciuding ine government of .ny country enroven or into on.cn ine package m de transponed-
{l p 1 Jl fh l 1; 3 THiS CERTIFICATE a mPAaEo av m sSa ISSUEo a,e u ON THE BASIS OF Ao SAFETY ANALYSIS REPORT Tmt ANo ioENTiricAfiON O nEPoafOFOa THE PACKAGE DEST,GN OR APPL! CATION wPticATiON i f f U.S. Department of Energy Division of Naval Reactors Safety Analysis Peport for 53W/S4W New Subassembly shipping container dated j g 1 Washington, DC 20585 October 28s 1968. 'g L 1, lI 1; e ooc =ET NUusEn 71-6002 lly 4 CONDIYiONS l i Tnis Certificate is Conditional upon fulfsfling the sequirements of to CFR Part 7i as applicaolo. and the conditions specified belo. l 3
- 1 l
(a) Packaging j 1 (1) Model No.: S3W/S4W New Subassembly i 1; j l, I i (2) Description b l u f The 53W/S4W New Subassembly shipping. container is fabricated from a I l q 43-1/2 inch length of l ASTM AL312-304l_6-inch Schedule 40 seamless pipe. A 6-inch 150 lb socket type flange is welded to each end of this pipe. j g 1 1, Both ends of the' container are closed with an end plate and eight 3/4- ~ g 4 1 10 CRES boltland nut combinations securing'each end plate. One of the ,g end plates *tncorporates a 0-15 psi pressure ghge and a 7-10 lb relief I ( valve. Eight lugs are welded to the OD,-of, the' pipe body and are used I p for lifting and' handling the containerQGross Veight of the packaging I f l i isapproximately187(Ibs.
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/ (3) Drawings { ^if ,17 : O in lj y 4 ' N[ p % "QfQ ,
R l,g ) The pac) aging (i_shconstructedciegascerdance with Westinghouse Electric I jl Corporation Drawing Nos.30l[4 3ORiv. 2. 901F340i' Rev. C, and 901F459; I l 1, Rev. 3. , , 'fgMMbg{ N jd i j wa;t}// g Q l i 1l % c, g) 4 i 9y y yg go
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, ,5 I ,n g Page 2 - Certificate No. 6002 - Revision No. 2 - Docket No. 71-6002 lh l-I il ll l
l (b) Contents j gi
'l s' (1) Type and form of material !n in Unirradiated fuel assemblies of the following type, it Il 1
I (i) S3W/S4W Core 1 new subassembly. l! q! g (ii) S3W/S4W Core 2 new subassembly. l ll 8 li ;l I (iii) S3W/S4W Core R2 new subassembly. I il l (2) Maximum quantity of material per package j (fi One fuel assembly as described in 5(b)(1)(i), 5(b)(1)(ii) or 5(b)(1)(iii). lIl gf .I R' II l (c) Fissile Class III
'N lI Maximum number of packages per shipment: 6 ll l 6. Expiration date: March 31, 1988. )
I, il REFERENCE ;b ll R 1: Il safety Analysis Report for S3W/S4W New Subassembly, WAPD-0P(R)S-2894 dated October 28, 1968. , ll i d' !p g FOR THE U.S. NUCLEAR REGULATORY COMMISSION lI ll i l 11 y Charles E. MacDona d, Chief !g I g Transportation Certification Branch 'g Division of Fuel Cycle and g Material Safety, NMSS lnR i I SEP 0 61983 il l lj Date ;b I, di lI1 1: I; Il di il ji 1: l l' i il I l l' i I! lE. l'. jI l I I! il l E. il 1, iI l ;l i li !'N di n lI f 133 lh
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jE, '8 C'" 7' CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES 1 a CERTIFICATE NUMBER D REVIS40N NUMBER c PACKAGE IDENT6FICATiON NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES - 6003 6 USA /6003/0( )F 1 5 i it 2 PAEAMBLE Il s Thes certificate is issued to certify that tne pacaagang and contents described in item 5 below. meets the apphcable lafety Standards set forth in Titto 10. Code ( of Federal Regulations Part 71. ' Packaging of Radioactive Marenals for Transport and Transportat.nn of Radioactive Material Under Certain Condrtions~ b This certif.cate does not relieve the cons gnor from comphance witn any requ6rement of the regulations of the U S Department of Transportation or other appl
- cable regulatory agenC'es. Includsng the government of any country through of into which the package will be transported ;
i l PREP ED SY (As a s D T EA D DE lF T F E A A TION U.S. Department of Energy Safety Analysis Report for fi-130 shipping Division of Naval Reactors container dated December 30, 1968s as ; Washington, DC 20585 supplemented. ' c DOC =Et NUueen 71-6003 a CONDITIONS This certificate is condit.onal upon fuit.fteg the requirements of 10 CFR Part 71, as app;icable. and the conditions specified besow I. 5 (a) Packaging (1) flodel No.: f1-130 (2) Description The !!-130 shipping container is an upright cylinder 84 inches in diameter by 158 inches overall height. The container walls consist of a finned 1-inch thick outer shell (fabricated from either carbon steel, carbon steel with stainless steel clad, or solid stainless steel), 10 inches of lead shielding, and a 1-inch thick inner pressure 2 vessel (fabricated from carbon steel clad with stainless steel). The P top of the container is covered with a shielded closure head which is bolted to the container and seals the pressure vessel. An access opening with a bolted shield plug is provided in the closure head for loading and unloading spent fuel. l The pressure versel has an inside diameter of 55 inches. The central i .! region contains a secondary heat exchanger (not used during shipment) ' surrounded by a 1/2-irich thick carbon steel backup cylinder 29 inches i in diameter. The annulus which cenains between the backup cylinder ' and the pressure vessel provides a space 13 inches wide and 130 inches l high for spent fuel. The spent fuel is contained in the annulus by module holders designed for the particular core to be shipped. H in , j l1 i:
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O ~ _M I; . , IN lj CONDITIONS (continued) y 1, 'I l E! ! 8' Page 2 - Certificate No. 6003 - Revision No. 6 - Docket No. 71-6003 ! [Il q S. (a) Packaging (cont'd) (2) Description (cont'd) . The container has external penetrations to the pressure vessel for i steam and water relief lines and a fill and drain line (which are capped during shipment) and a pressure sensing line which remains open : to a pressure gage during shipment. The container also has penetrations , which do not open to the pressure . vessel for secondary heat exchanger g lines (which are capped during shipment) and a temperature sensing , line. , .
. . . , . ~: i For LilBR spent fuel shipnents', 'the-heat _ exchanger and associated }q structures have'been removed, external penetrations plugged and seal p welded, and,an ' external shield and energy absorber added during E1 modifications. E!
b The contakrIer is supported on its transport vehicle by an "A" frame h structure. Gross, weight of the loaded . container without its support gI J structu.re is approximately 228,000 pounds. A k-(3) Drawings ' - j{ The packaging is ~ constructed in'accordance with General Electric Drawing Nos. 247E209. Sheet .1,.Rev. .R;; Sheet 2 Rev. ' K; Sheet 3, Rev. [! g T; Sheet 4,; Rev. V; Sheet: 5 of L 5, Rev. F and 247E228, Rev. F. 3:
.R For LWPR spent fuel shipments",ithe' container has been modified in A accordance with Westinghouse' Electric' Drawing II76J48, Sheet 1 Rev. G, Sheet 2 ~Rev. E'and an external. energy absorber added in accordance j y with llestinghouse Electric Drawing 1525E32, Rev. ~A. g ,
)l (b) Contents k (1) Type and form of na'terial .
Irradiated fuel assemblies, activated corrosion products and structural 'n parts containing up to 40 gallons of residual contaminated water. The %g fuel assemblies and structural parts are of the following types: ;h! (i) S3W/S411 fuel subassemblies of core type (ii) S5il fuel modules of core types 2 or 3. ! i (iii) S5W corner fuel nodules of core types 2 or 3. , (iv) DIG fuel modules of core types 1 or 2. s lN r s l i
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(2) flaximum quantity of;inaterial per package j[
' i (1) 52 fue1~ assn 1blies as described in.-S'(b)(1)(i).
g , (ii) 12 fu'el' assemblies kh d' esc ibed.in 5(b)(1)(ii) or 9 fuel i and 4 fuel assemblies
;asdescribed-inL;5'b)(1)(iii).? assemblies as 'desc'ribed in 5(b) i l
8 (iii) 6- fuel assemblie<,' as tdescribed in 5(b)(1)(iv) and !
'4 fuel assemblier as described in 5(b)(1)(v). l (iv) 9 fuel assemblies as described in' 5(b)(1)(vi) and i 8 fuel asietW fes as. described in 5(b)(1)(vii).
\
g: (v) i 10 fuel assemblies as described in 5(b)(1)(viii). ( tl' E (vi) 9 fuel assemblies as described in 5(b)(1)(viii) and one fuel i I; I. assembly as described in 5(b)(1)(ix). !j. I (vii) 1
;glj 9 fuel assemblies as described in 5(b)(1)(viii) and k
gi one structure as described in 5(b)(1)(x). t l gl (viii) 3 fuel assemblies as described in 5(b)(1)(xi). I E k-f (ix) 4 or less fuel assemblies as described in 5(b)(1)(xii). l (x) 6 fuel assemblies as described in 5(b)(1)(xiii). N I ! Shipments shall be further limited by shielding and thermal requirements as follows: y [l l
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I; I: Page - 4 Certificate No. 6003 - Revision No. 6 - Docket No. 71-6003 h> N i
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f 5. (b) Contents (cont'd) lH (1) Shipment of contents specified in 5(b)(1)(iv) and 5(b)(1)(v) and 1 lEi li limited in 5(b)(2)(iii) shall have a decay heat load not to exceed 33,500 Btu /hr per shipment. ,j. [ (2) Shipment of contents specified in 5(b)(1)(vi) and 5(b)(1)(vii) and f
- limited in 5(b)(2)(iv) shall be made in a stainless steel M-130 container h By and shall have a decay heat load not to exceed 18,960 Btu /hr per shipment.
i (3) Shipment of contents speciffid in 5(b)(1)(viii), 5(b)(1)(ix) and 5(b)(1)(x) and linitedsin~5(b)(2)(v),_5(b)(2)(vi) and 5(b)(2)(vii) shall be nade at a' tine after shutdown as. determined from Bettis Atonic Power 1.aboratory report WAPD-0P(PP)S-4401 dated June 29, 1979 c and shall,ha9e a decay heat load not to exceed 28,620 Btu /hr for the shipboard; core and 30,000 Btu /hr for the prototype core. (4) Shipmentfof contents specified in 5(b)(1)(i), 5(b)(1)(ii) and 5(b)(1)(iii) and limited in 5(b)(2)(i) and 5(b)(2)(ii) shall be made no earlier than 72 days af ter. shutdown and shall have a decay heat load not to exceed 33,500 Btu /hr' per shipment. I l (5) Shipm_eht of contents specified in 5(b)(1)(xi) and linited in 5(b)(2)(viii) shall have a heat load.not to exceed 48,000 Btu /hr and a residual water.f quantity 'not to exceed 4.6 gallons. (6) Shipment.of contents specified :in 5(b)(1)(xii) and limited in 5(b)(2)(ix) f shall have a heat' load not .to' exceed 3,672 BTV/hr. (7) Shipment of-contents specified in 5(b)(1)(xiii), and limited in 5(b)(2)(x) i l' shall have' a heat load not to exceed 27,600 BTV/hr and a residual water quantity not to exceed 7.5 gallons. III , (c) Fissile Class Maximum number of packages per shipment: one
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- 6. For shipments involving the contents specified in 5(b)(1)(ii) or 5(b)(1)(iii) the M-130 package shall be inspected to verify that boron poison plates are in ,
i tie .T.odule holders. @f i l 7. For shipments involving the contents specified in 5(b)(1)(viii), 5(b)(1)(ix) or !g l i 5(b)(1)(x) the thermocouples and thermocouple cases if included or the vacant lIP module holder shall be located -in the mid-position of either cage and module j holder assenbly, il i 8. Shipments shall be made in the dry condition, except for residual water as l i limited in 5(b)(1), 5(b)(2)(5), and 5(b)(2)(7). llp l p 9. Expiration date: May 31, 1988. l in 137 ilI
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} CONotTIONS (continued) % Page 5 - Certificate No. 6003 - Revision No. 6 - Docket No. 71-G003 h REFERENCES Safety analysis report for it-130 shipping container, MAO-E8-703 dated December 30, 1968. .! i ..' Supplements: Naval Reactor letters A#2256 dated February 24,1969 and G#1931 dated : flarch 3,1969; General Electric Company letter 0NP-74520-526 dated April 3,1972; ' Naval Reactors letter G#3207 dated April 27, 1972; General Electric Company letter ONP-74520-528 dated April 28, 1972; Naval Reactors letter G#3250 dated June 6,1972; , General Electric Company letters ONP-74570-635 dated October 25, 1972; ONP-74570-654 dated December 4,1972; ONP-74570-66G dated December. 12,1972; ONP-74570-682 dated - Janua ry 12,1973; ONP-74570-69G dated January 31,-1973;-0NP-74570-687 dated February 6, 1973; ONP-74390-65 dated itarch 26, 1973; DLGN-85570-854 dated September 24, 1973; ; DLGN-85570-901 dated January 10,197d; Naval Reactors letter C#4061 dated January 29, i 1974; General Electric Company letters DLGN-85570-924 dated February 15, 1974; DLGN-85570-923 dated March 6,1974; DLCN-85570-969 dated flay 24, 1974; Naval Reactors i letter G#4991 dated November 25, 1975; General Electric Company letters ONP-74340-l JTT-73 dated December 17,1975; CGN-85570-ll45 dated September 9,1976; CGN-85570-1146 dated Septenber 10, 1976; CGft-85570-1140 dated September 14, 1976; Bettis Atomic j Power Laboratory letter WAPD-R(K)-1378 dated August 30,' 1976; WAPD-0P(PP)S-4401 dated June 29, 1979; Naval Reactor letters G#6197 dated July 13, 1979; G#7136 dated ; March 17,1932; and UAPD-LD(CES)SE-181 dated. September,1981; WAPD-LP(CES)SE-96 dated February,1982, WAPD-LP(CES)SE-170 dated July 1981; and Naval Reactors letter G#7582 dated September 7, 1983. FOR THE U.S. NUCLEAR REGULATORY C0f tflISSION r Charles E. FMcDonald, Chief Transportation Certification Branch Division of Fuel Cycle and
!bterial Safety, Nt!SS Date:
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u.s. NUCLEAR REcOLATO".Y COMMIS$CN l Il! mac ronu sie CERTIFICATE OF COMPLIANCE i
'l I +ui I 'o CrR r' FOR RADIOACTIVE MATERIALS PACKAGES d PAGE NUMBER e TOT AL NUMBER PAGES c PACMAGE IDENTIFICATION NUUDER L REVISION NUuBER USA /6049/B( jr 1 3 ';
fl l i . CERYtFiCATE NUWsER 6049 2 I, r PaE AustEa This certihcate is issued to certify tnat tne packagmg and contents descnbed instern 5 below. meets the apphcabie s
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'g ij Feoerai Reguistions. Part 71. -Packaging of Radioactwo Matenals for Transport and Transportation of RaJ osctive Maten lg lI
${ O This certificate does not red. eve the consegnor from comphance witn any requirement of tne regulations of tne U S Department .h of E!
aophcame reguiatory agencies. inciuoing ine government of a.,y country enrouan or into wnicn tne package wiii be transporteo 'n I! 't ti T OF THE PACKAGE DESIGN OR APPUCATION b "YLE AND IDENTIFICATION OF REPORT OR APPLICAT10N h, I, 3 THIS CERTIFICATE
. PREPAREo av ,N l$ iSSUEo ON THE SAsis and A#essJ OF A SAFETY ANALYS:S REPOR )t U.S. Department of Energy Safety Analysis Report for 426A and 4268 !y
) n shipping co9 tainers dated January 31, 1969,
'! Division of Naval Reactors as upplemented.
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Ul Washington, DC 20585 ip i 71-6049 I! !I [ c OOC =ET NuusER ti l 4 CONDITIONS l i t ,. . Tnis cert.ocate is conostionai upon euivining tne reauir.ments o, io crn eart ri. as apphcab llI La (a) Packaging
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;i; (1) Model Nos.: 426A and 4268 ll I; l (2) Description The Model Nos. 426A and 426B ' containers are used to ship and store new {
f q unirradiated SSW Core:R3' core cartridge assemblies, new unirradiated :p
;3 S3W Core R2 fuel subassemblies, and new unirradiated SlW Core R3 core ll I cartridge assemblies. The 426A container', the basic design for this lI l
series of shipping and storage containers, is. a horizontalThe cylindrical ; jl container, 3 metal weldment 73-1/2" diameter by 226 inches-in length. j 1
', mounted on wooden skids, is 82-9/16 inches high and weighs 6,000 :
pounds empty. The~426B container i_s essentially identical to the 426A g; ,
,r container in all r_espects except for, length. The'426B container was g
(; :p i made 292. inches long (66 inches longer than the 426A) to accommodate ;l
;8l the no longer existing SIW-4 instrumented core cartridge and weighs l l
7,900 pounds empty. 3The fcontainer. assembly consists of three major i I j, subassemblies': . - the ' upper :section, the lo'wer section, and the cradle
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which sup" ports the core within:the container assembly and supports the new fuel assembife The maxiinumigross weight of-the 426A container is i
' 's 27,960 lbs. :~~ .
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i gl NRC FORM 818A U.S. NUCLEAR MEULATORY COMMISSION g! t*4h CONDITIONS (continued / RI II Page 2 - Certificate No. 6049 - Revision No. 2 - Docket No. 71-6049 I! l 1 : l ! (3) Drawing j I I g The packaging is constructed in accordance with Applied Design Company I I Drawing No. 426A401, Rev. C. ! l ? lli (b) Contents (1) Type and form of material g i ) i
- r. Unirradiated fuel assemblies of the following type, !
I i l (i) S5W Core R3 cartridge assembly, with all control rods installed i j
}i and restrained in a fully inserted position with rod holddown ;
lg; caps. ; ; it q! (ii) S3W Core R2 fuel assemblies, with covers of borated steel secured i i l' in place over the assemblies, in the S3W/S4W New Core Component t l Adapter Kit. Il ; ! f (iii) SlW Core R3 cartridge assembly, with all control rods installed and restrained in a fully inserted position by a control red gl! l holddown plate. t E, Hj l (2) Maximum quantity of material per package j i [j One fuel assembly as described in 5(b)(1)(1), 5(b)(1)(ii) or 5(b)(1)(iii). I f lil (c) Fissile Class III j , I Maximum number of packages i I per shipment: I one ' i fI I
- 6. Expiration date: Janua ry 31, 1988. ,
g! ! i gj ~ l REFERENCE l 1l . i ll Safety Analysis Report for 426A and 426B' shipping containers, WAPD-0P(R)S-3105, dated January 31, 1969. ' {i; , l t i, , i , i I 1 lli, ! R. . II I; ' l i I t I ,i %" 1 i: t I lp I 9 I. -
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!g l I I Page 3 - Certificate No. 6049 - Revision No. 2 - Docket No. 71-6049 l I ;I l !I i !g 1 ll I Supplements: Bettis Atomic Power Laboratory letters WAPD-0P-(R)S-3373 dated June 11, lg 1 1969, WAPD-0P(R)C-71 dated March 6, 1972, WAPD-0P(R)C-139 dated August 4, 1972, WAPD-OP(R)C-145 dated August 11, 1972 and WAPD-0P(R)C-164 dated October 6,1972. ja ,
1 i , I FOR THE U.S. NUCLEAR REGULATORY COMMISSION l !) ll !i 11 Charles E. MacDonald, Chief il j Transportation Certification Branch j l
] Division of Fuel Cycle and 1 Material Safety, NMSS j!y 1! lg 1 SEP 0 61983 l i
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jt, to crR " CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES
"** " l t a cERTwrCATE NUueER ti AEvissON NUMBER c PACKAGE IDENTIFICATION NUMBER d FAGE NUMBER e TOT AL NUMBER PAGES '
! 6058 8 h PRE AMBLE USA /6058/B( ) 1 4 a This certifcate is issued to certify that the packaging and contents described in item 5 below, rnects tne appbcable safety 16tandards set tortn in Tit of Federal Regulations. Part f1,' Packaging of Radioactive Matenals for Transport and Transport.ition of Radioactive Matenal Under Certain Conditions D
This certificate does not reheve the consignor from comphance with any requirement of the regulations of the U S Department of Transportation or oth : appbcable regulatory agencies anCluding the government of any Cou n try through or into wh#ch the package will be transported I l
- 7',E"A7efe'v'd*,Si'fE2 *** '" ^**"*e"'T7tE ATo'Io'WiS*c^ffl8N s" WMAA ^
- CAT,0N U.S. Ecology Protective Packaging, Inc., application P.O. Box 7246 dated flarch 4,1974, as supplemented.
Louisville, KY 40207 ; 71-6058 9, c DOCKET NUMBER m a CONDITIONS lE This certiftcate es conditional upon fulfilhng the requirements of to CFR Part 71. as apphcable, acid the conditions specified below lW i y1 s I (a) Packaging : (1) Model No.: B-3 (2) Description The packaging consists of a lead shielded steel weldment in the shape f of a right hollow cylinder with a bottom and a recessed, plugtype i - gasketed and bolted : lid. The packaging provides a minimum of 6 inches ;W of lead shielding. Packaging features include lifting and tie-down devices ano a drain to the central cavity. The maximum weight of the f loaded packaging is 30,000-pounds. %l
;N The outer shell is of a laminated steel . constructed and is 41 inches )'
in diameter and 57 inches high. The two laminates are of plate material iN 1/2-inch and 1/4-inch in thickness. The inner shell is of 1/2-inch f thick steel plate. The internal cavity dimensions are 26-1/2 inches
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in diameter and 43-1/4 inches high. The lid is of the same cnnstruction ! as the sides and botton and is secured to the body of the packaging by !g N twelve,1-1/4-inch diameter by 2-inch long high strength bolts and N sealed with a silicone 0-ring. lN i l in , l lN
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~ CoNolTioNS (contonued]
Page 2 - Certificate No. 6058 - Revision No. 8 - Docket No. 71-6058 :, i S. (a) Packaging (continued) (3) Drawing The packaging is as described and constructed in accordance with : Battelle tienorial Institute Drawing No. 9958-8501-0001E, Revision B or Revision C, as amended by Union Carbide Corporation letter dated November 3, 1979. (b) Contents n - r (1) Type and fom of material 'C w,e, '
... g P ~ J (i) Byproduct 3and uranium enriched in the,:_.U-235 isotope, U-233 or pluto (iiurias solids, non-powder, and dry,.-which will not decompose at temp'eratures up to 575 F and packaged ithin DOT Specification 17Hiteel druns.
C, , x. . ' x i l (ii) Byproduct,an'd uraniun enricheo .iu5the U-235" isotope, U-233 or fplistoniun'which'ceets the requirements of special fom radioactive
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- material . 3 ) . ,
Byproduct mathidl and ura'niupi riched in the U-235 isotope, f (iii)[ U-233, or plutonium as solidsdnon-powder, and... dry which will n lf@ l
-r decompose'at temperatures!up -to.575'F, packaged. within a nominal ;
a
'l/2-inch thick (24-inch 00) polyethylene Highi~ Integrity Container (HIC). ; Liquids must be solidified in'Chentree Iron Oxide mix in P
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ansteel container. ; Smal.l!itens,-including glassware, must be placed ineFgal . steelcontainefs~ and compressed (as required). A v+~ b 0 j, m &" ; ~
;@H j
(2) Maximun qua'ntity of naterial 'per package <W (S ^ i 'f/ h Forthecontentsdescribedin5(b)(1)(i)Sh5(b)(1)(ii): m E J i l Not to exceed 400 N'ktts7 thennel ~de'cayi 1 i ~ l For the contents described in 5(b)(1)(iii): fE ified liquid 'n
' The HIC must be limited to 200 A radioactivematerialandnotnor$quantitiesofsolid2 quantities lNof o than 50 A N radioactive materials. The maximun themal decay heat load must not exceed 15 watts.
j I o i il I: I: I! l't i N N
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g y . i CONDITIONS (continued) f Page 3 - Certificate No. 6058 - Revision No. 8 - Docket No. 71-6058 ; i f l
- 5. (b) (2) (continued) f l
For the fissile contents described in 5(b)(1)(i), 5(b)(i)(ii), and ! l 5(b;(1)(iii) not to exceed the following: l Fissile E.! Material flaximum per Package (grams) flaximum hlg: H/X U-235 350 l g 500 U-233 200 '! N! 450 !
' ' Plutonium
- 200 r-- 800 h C0 l, j
Q} g. of each fissile {m~aterial to its maximum per pac unity, i 4 i ii s s *3 / (,) ! f4 *PlutoniuYin excess of 20 curies per package 'must be in the fom of Lg, ! reactor. y fuel.ss fuel s elements, metal, or,ymetal'- alloy. i (c) FissileCfa'ss \ f it' b I t
/ *2'l'kI II Q' For contents containing) # #~e\
I -
% }cial40e clear { m O Nrial: %
l , 7Q .lhch ij p Minimum transport -f ' ll labei.indexA, %q
~e-&,f . ' 10.0 h I
to be shown.on
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g 6. so < e, , - 4 g# s a v~
% i ll g
For gamma-emitting spe>c~iah fom ma,ter c fat least'5,' inches,0f additional lead
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E. y n' shielding must be'added-asfaQinjngt Q.) i :ai y h5 i1114 sides',within the> internal cavity. p
- 7. _
9&N '~5 e ' y
},1) The total weight of'the c{ontents includingsadditional lea'd7 shielding a requiredshallnot'e(ceed9,000 pounds.42 "
y jH f 8. Prior to each shipment he lid 0-ring shall be. inshecied. The 0-riag shall be j l replaced with a new 0-ring i gl months, whichever occurs fir ti. Kf p y( inspection shows.any defects or every twelve (12)
' i f . g!
9. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 671.12. E l I! l 10. l Il Expiration date: February 28, 1985. g p Ilf 1 Il I I !N I:l I !N I! ) t si l1 p !
's ,
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!l 164 N R I ' I I L I ______________________________________,m_y
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cw e r ' ' ' " conourions ccontinues> I l ll4 . l i
.g! Page 4 - Certificate No. 6058 - Revision No. 8 - Docket No. 71-6058 :
l l lRI'
' ;5j
;Hi I;
E REFERENCES l ! l El i i l i i Protective Packaging, Inc. application dated fiarch 4,1974.
,s '
g 1 lj N Supplement dated: Augus t 12, 1974. Qll
< i Battelle Columbus Laboratories supplement dated April 12, 1979.
j Union Carbide Corporation supplements dated: November 3,1979; and December 21, 1983. g ' i N; F0P-THE l
,lll (b. [h D'Csi(/f ju.S. ,t!UCLEAR REGULATORY lg' ~b s9 lq N Charles E. flacDonald, Chiefs T, Transportation Certification l Branch !
l %l res W C' x . Division of Fuel Cycle and ' ~~, :N
- E
!8l
' E Q) eA Q\x tiaterial Safety,';y /
,f1-ftiSS i
y? .g s - .. g' ' Date: JAN 0 61984% ) g; ; g 7 N f EW[N.,,d D/g'c c 1. ( _ . . 'g w ) i .2 [6 <
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%%Vr?MTan"T3aTEminE'utSna7NishsanwT7marMtswatn i NXC FORN 618 U.S. NUCLEAR REGULATORY COMMISSION
+ssi
" " " CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES 1 a CERT ACATE NUMBER D REWSION NLwSER CPAChAGE DENTIFICATiON NUMBER d PACE NUMBER e TOTAL NUMBER PAGES '
6078 9 USA /6078/AF 1 2 PRE AMBL E a This cendcate es issued to certify tnat tne packaging and contents described in 11em 5 below. meets theapphcable safety standards set fortn in Title to Code of Federal Regulations. Part 71. Packaging of Radioactive Matenais for Transport and Transpuation of Ha$oacteve Matenal Under Certain Conditions ~ b This cert-hcare does not reheve the consegnor trori comphance with any requerement of the regulations of tne U S Depart rient of Transportation or other apphCab4 regulatory agencies, including the government Of any Country through Or into which the package will be transpor1ed j 3 THIS CERTfFICATE IS #SSUED ON THE BASIS OF A $AFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION a PREPARED BV (Name and Admessi e TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Combustion Engineering, Inc. Combustion Engineering application dated 1000 Prospect Hill Road December 10, 1979, as supplemented. Windsor, CT 06095-0500 71-6070 *
- c. DOCKET NUMBER a CONDITIONS This cert ficate is condrtsonal upon fulfilhng the requirements of 10 CFR Part 71. as applicable, and the condet'ons specified beinw I I* (a) Packaging
+ :
(1) Model Nos.: 927Al and 927Cl (2) Description A steel fuel bundle shipping container consisting of a strongback and ' fuel-bundle clamping assembly, shock mounted to a steel outer container. A minimum 1/4" thick, 6" x 6" x 8" high steel separators are bolted t ' between fuel bundles. The Model No. 927Al container is approximately 1 N 43" in diameter by 189" long with an approximate gross weight of 6,200 ! lbs. The Model No. 927C1. container is approximately 43" in diameter by 216" long with an approximate gross weight of 7,000 lbs. #(! lg (3) Drawing The Model Nos. 927Al and 927Cl containers are constructed in accordance l with Combustion Engineering, Inc. Drawing No. NFM-E-4108, Sheets 1 1 ! thru 4, Rev. 1. '
~, N
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m m - m E i E s sfifs L N N *2f1 w m uu CONDITIONS (continued) page 2 - Certificate No. 6078 - Revision No. 9 - Docket No. 71-6078
- 5. (b) Contents lg (1) Type and fom of material (i) Model No. 927A1: fuel bundles consisting of 0.38" diameter lH; uranium dioxide fuel pellets clad in 0.028" thick zircaloy tubes 8- in a 14 x 14 square array with a 0.58" pitch. Each fuel bundle i consists of a maximum of 176 fuel rods at 4.1 w/o enrichment in the U-235 isotope.
(ii) Model No. 927Cl: fuel bundles consisting of 0.325" diameter uranium dioxide pellets clad in 0.025" thick zircaloy tubes in a 16 x 16 square 3rray wi+h a 0.506" pitch. Each fuel bundle y consists of a maximum of-236. fuel rods at 4.1 w/o enrichment in j the U-235 i,sotopeh* ' ' '~ ' ' ij . j ,g;
,. g , -- u- ,g ,
(2) Maximum quantity of material per package , , j
. 'd Two (2) }{jx 14 fuel bundles containing not mohe than 35.0 Kgs U-235; I or Two (2) 16 x 16; fuel
- bundles containing/not'more than 35.0 kgs U-235.
(c) Fissile ClqIs y ') li' 2 III j jg ^
- iff ; ; s Maximum nqmb'er of packages \ der sh'ipmEntGfs Eight(8) f -
, e.- ~; V.A m p (%;f :
- 6. Each fuel assembly shall'ibe unsheathed forjshall~be enclosed iriran unsealed, ,
polyethylene sheath which~will not;extendjbeyond the, ends of the fuel assembly. ; The ends of the shbath shall?not bei folded for\ taped in any manner that would
~
prevent flow of liquids into"or out of.Ithe:Ish'eath'ed; fuel as_sembly, j l
'tb,' '
s s iA Q? 1g i
- 7. The package authoriz'ed by this certificatetis hereby approved for use under the h general license provisions of 10 CFR'971'.12. . %
, "/7 @c(; lM N
- 8. Expiration date: June 30,<1990., t-I $* 3 1, ,A, fr V !j
% /w rs I, REFERENCES g l
i l1 1l Combustion Engineering, Inc. application dated December 10, 1979. l#N I j E. Supplement dated: May 30, 1980. l b l FOR THE V.S. NUCLEAR REGULATORY COMMISSION ;pl Il. i El lNE
.I Nt Charles E. MacDona d Chief ;
, g! Transportation Certification Branch i Division of Fuel Cycle and I Material Safety, NMSS l i mu e as i 167 g i Date: l l________---________________---__,_____________________e
I. I ji wRc rona sie U.S. NUCLEAR REGULATORY COMMISSION iI I i$ni m err " CERTIFICATE OF COMPLIANCE ,1
]
FOR RADIOACTIVE MATERIALS PACKAGES !I
's CERTiHCATE NUMBER b REVISION NUMBER c PACKAGE DENTlHCATION NUhs4 d PAGE NUMBER e TOTAL NUMBER PAGES h
m EA _ . 6115 2 USA /6115/AF 1 2 j m
] a Tnas c.rtificat. is issued to c.rtify tnat tn. pack aging and cont.nts d.scrib.d init.m 5 b.lo.. me ts in. appncaba. safety standards s.t fortn en Titi.10. Cod. of g r.d.rai n.gulations. Part 71. " Packaging of Radioactiv. Matenals vor Transport and Transportation of Radioactiv. Matenai Under C.rtain Conditions
- ll
!g 1 o inis c.rtificat. do.s not r eiev. tn. consignor from compnanc. itn any reuirem.n oe in. r.guiations ce in. u s. o.panment or T,ansponai on or ein.,
11 1 appi,cani. r.guiatory ag.nce.s. inciuding in. gov.mm.nt ce any country inrouan or into .nien in. packag. .in o. transoon.d. lll i in
} I I
f a rms_c,ER,r;reA,r,sgUEoge,eAsis
, p or A sArery mAtysis,PEgrgr,ig4ggsgoggicm 4
lj E.I. du Pont de Nemours & Company E.I. du Pont de Nemours & Company Report l Savannah River Plant No. DPSPU 75-124-1, June 1975. lll il
]j Aiken, SC 29801 j
. oocKer NUuscR 71-6115 8
l i
. _,i Tnis e c.ncat. is conditionai .pon vuivining tn. r.quir.m.nts on to Cra Pan 7t. as appncani.. and tn. I consti 1
- I (a) Packaging l
l (1) Model No.: R1010-0032 l l 1 (2) Description l g l, j l l i Packaging for an instrumented unirradiated test fuel bundle. The 'I I contents are held withlotan Tn,n'er(c,ontainer by six cushioned aluminum I
)
clamp assemblies, bpited to six,1/2-i% thick steel supports welded l to the bottoms and sides of the inner contaijter. The 338-1/4-inch by
~
l I! 10-inch by Pl/2-inch inner container is congtructed from 1/4-inch ljl l' thick 304 stainless steel plate. The inner container is held within a ll 1 l, 455-inch by 24-1/2-inch by 18-1/4-inch carbon steel outer container, O i and is su,pp,orted by<urethane foam cushfoning material. Positive i h closure,4s' accom'pi,is1d4 for,_the inne'r;{ arid outer containers by Lolted 1 I lj cover plates. Thr $tMge"g$5 de ght'lis 8,350 unds. lj (3) Orawin , f g lj The pachging fabricated N Laboratoples AME tDrawirid M, placcordance Rev with AT$onne National R lb Rev. 0; & R1610-)9927-RE,t MH IO,.T4il@l010-0036DC, I
; ,ea% O,':; m b Q $& (Q ,
l y b y/,y) f dy;
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i: kNN ti h l h I h i s k ;N h 'I h iI n l, li i i h I l; 16s h i i Lm_v. _ __ _ _ __ _ m_ _ _ _ __ _w_m_ _ _ _ _ _ _ _ _ _ _=_ m_ m 7z i . l 1
mm_mmemummmmmm-mammmammmmmumammm&mja,,,,,,,,,,,,,,,,,, _ NRC FOAM 818A U.S. NUCLEAR CE!ULATORY COMM12SION
&O CONDfTIONS Scontinued)
! Page 2 - Certificate No. 6115 - Revistar No. 2 - Docket No. 71-6115 II i
il l3
- 5. (b) Contents :l (1) Type and form of material Unirradiated, instrumented, fast test reactor (FTR) type fuel, containing l1 l p
t sintered U0 pellets with maximum 93.2 w/o enrichment in the U-235 ;i isotope. Tke fuel element bundle consists of 19 FTR type fuel elements j I t I arranged in a triangular array in a hexagonal can, 0.056-inch separation maintained by wire wrap, and 0.028-inch separation between the outer j fuel elements and shroud can maintained by wire wrap. The fuel element j is 0.230-inch diameter, has a 36-inch active length, and 0.015-inch jy l wall 316 stainless steel clad with welded end plugs, lgl i (2) *1aximum quantity of material per package il
'l Not to exceed 3.0 kg U-235.
f III !p-
; (c) Fissile Class lI l
Maximum number of packages per shipment One (1) lN il
- 6. Prior to shipment each of the 18 eye bolts in the outer container cover plates I,I shall be replaced with 1/2-inch diameter bolts. 'a jb l 7. The package authorized by this certificate is hereby approved for use under the ;h I general license provisions of 10 CFR 571.12. lN
;I
- 8. Expiration date: September 30, 1987. j REFERENCE l 5.I. du Pont de Nemours & Company Report No. DPSPU 75-124-1, June 1975. ))b
.A i
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lR t FOR THE U.S. NUCLEAR REGULATORY COMMISSION ll i > t ji Cha es E. MacDonald, Chief 't Transportation Certification Branch 'y Division of Fuel Cycle and lp Haterial Safety, NMSS ,h 1 i SEP 0 61983 Date: f
~
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y - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ _ _ - - , - - - - - - h NRC FORM s1s l U.S. NUCLEAR REGULATORY COMMISSION i 1 mai ic crR i' CERTIFICATE OF COMPLIANCE 1 FOR RADIOACTIVE MATERIALS PACKAGES f ,i e cERTiricATE NUMBER b REVISION NUMBER c PACMAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES ! g 6134 3 USA /6134/B( )F 1 2 lj 2 PRE AM&E a This certificata is issue 1 to certify that the packaging and c sntents described mltern 5 below. meets the apphcable safety standa ros set forth m Title 10. Code of 1l
], Federal Regulations, Part 71. "Packagmg of Radioactive Matenals for Transport and Transportation of Radioactivs Matenal Under Certam Conditions
- l; b This certificate does not rebeve the consignor from comphance with any requirement of the regu.ations of the U S Department of Transportation or other appiicabie resviatory agencies. inciud.no tne government of aisy countr> enrouan or into wnien ene package wiii be transporied .
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!* '"P5 P E' ev er an* ?" b E ANO lC E ? C TION " M" A CATION 4
f U.S. Department of Energy Division of Naval Reactors Safety Analysis Report for 11.9 New Fuel Shipping Container dated April 22, 1969 f y 3; Washington, DC 20535 as suppiemented. g h E 1 1; c OOcxET NUMBER 71-6134 )1 a CONDITIONS This certificate is conditional upon fulfsiting the requirements of to CFR Part 71. as applicable, and the conditions specified below I 1
.t l* (a) Packaging f'
l (1) Model No.: 11.9 New Fuel ([y :
$ J l (2) Description '
k The 11.9 New Fuel container consists of a two section hori7ontal
, )'
j(li 1 cylindrical shell approximately 31: inches diameter by 239 inches long. The shell is reinforced by internal bulkheads and is parted along an 1 axial plane into 'an upper and lower section.- The bulkheads are
~
!:]
Fy 1l designed to frame a central chamber within which the module to be l
'l carried is supported and held in place by cradle frames and clamps. l) j The cradle . frames are supported from shockmounts which are attached to ij y brackets inside the container shell. ;The container incorporates 'j features ~for lif ting, hoisting and/for purging and pressurizing to 5 j
~
1 1! psig of nitrogen. The fuel module is' shipped with. design control rod j
'l and lead screw installed and either with or without the motor tube e installed. When shipped with a' motor tube, the leadscrew and control 3{' rod assembly is-held in place by the design leadscrew restraint latches. j y When shipped without a motor. tube, the leadscrew and control rod i y assembly is held in place by a.special plug and holddown cap which r
.j. bear against the top of the leadscrew and are anchored to the closure ;
1 block by two,1-3/8" diameter bolts o'r two,1-5/16" diameter b9lts fcr
% Core 4 or Core 4A respectively. . Shipments may be made by motor vehicle, E 1 rail, cargo aircraf t, or water transportation. The maximum weight of Q l
i the loaded container is approximately 5,100 lbs. j 1 1 1 ia (3) Drawings
~
j l L The packaging is constructed in accordance with Westinghouse Electric 1 Corporation Drawing Nos. 961D919, Rev. 4, Sheet I thru 5 of 5 and !i 1l j 903E166, Rev. 6, Sheet 1 of 1. i 11 11 1 1l J i Z fE T E K E ET2T5WER E E RM /E T TXW'fM Efz z ppwWw rar w w v pw wis - st w ww w -- y w w m n c
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mmc. , - A= = = == = =-w=3s#NHLTP*N l Wl' NRC FORM 818A g
+ sa' conomous (continuest U.S. NUCLEAR REGULATORY COCMISStoN E
jl( Page 2 - Certificate No. 6134 - Revision No. 3 - Docket No. 71-6134 lI
'n $ 'y R
j D 8:
- 5. (b) Contents j (1) Type and form of material f lh Unirradiated fuel assemblies of the 55W Core 4 or 55W Core 4A type with control rod installed. A control rod holddown cap and plug rust )]>
he installed when shipping without motor tubes. % f l 14! g (2) Maximum quantity of material per package One fuel assembly as described in 5(b)(1). )'p! III M (c) Fissile Class i p 4 lq Maxinun number of packages per shipment fl f 6. Expiration date: January 31, 1958. lg p l
!R' 5 REFERENCE f N h #
1 Safety Analysis Report for 11.9 New Fuel shipping container, WAPD-0P(R)P-iS9 dated April 22, 1969. j
's
% FOR THE U.S. NUCLEAR REGULATORY COMMISSION s
;4i p
' f Mk Charles E. MacDonald, Chief i
Transportation Certification Branch Division of Fuel Cycle and Material Safety, NiSS
?
SEP 0 61983 , oate: . B' ! p
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i l 1 4, ll feRC FORM S1s Il U.S. NUCLEAR REGULATORY COMMISSION II iS am CERTIFICATE OF COMPLIANCE 3 h S C'" " FOR RADIOACTIVE MATERIALS PACKAGES lI b REVISION NeuSEA c PACKAGE IDENTW6CATK)N NUUSER d PAGE NUMBER e TOTAL NUMBER PAGES h.a t . .,_ ctRTwicATE 6142 NUMBER 2 USA /6142/B( )F 1 2 j 1; a in..c.naicat. .inu.o to c.ria ine.er v packag.ng ano contents o.scnocuniteen s e.io.,me.isin.appucabi...r ety staaoaro et sorinin r.ti. io. coo.oi :y
} F.;eral R.gvlations. Part 71. "Packagmg of Rao*oactiv. Maten=ls for Transport end Tra 1sportation of Radioactiv. Matenal Unoer Certain Conditions * 'g li e in. cene cat. oo not re . m. cons.gnor trom compnance m anY requirem ni ofin. reguistion.or m. u s o.panm nt or Tr n ponation or otn r ll appocaei. e.guiatory ag.nc .. inciuo.no me governm.ni os any country mrouan or into on.cn in. package .m o. iranspon o i
}4
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In ll t 2 rniSac,-err.wicA.TE_iS Pa E . 6SSUE,D aA . ON THE, BAS.S OF A SMTV _ALYSt$,RE,P, 1LE m N1. AGE ORT _OFF-1 THE PACKcA1._ A - cA DESIGN
- OR APP.L6 CATION r T i g, f U.S. Department of Energy Safety Analysis Report for Bettis Disposable f J! Division of Naval Reactors Waste shipping container dated September 30, 1969. p
{ Washington, DC 20585 lt tR
,1
!I 1, c oOcxEr NUusER 71-6142 !g 4 CONDITIONS h ini c.n, rice. is cono,tonai upon vuivin.no m. r.quir.m.nts of 10 CFR Part 71, as appocable. ano tne coriditions specifi.d 1:elow ;l A il 5-1 3,
(a) Packaging '. t, 1 1 t (1) Model No.: Bettis Disposable Waste !pg 1
't 1,
(2) Description ,1 i
)%
j The packag1ng consists.,of;a disposable concrete vault enclosed in a reusable steel overpack. ' The ' con' crete' vault is a poured concrete j 1 block measuring'51" s'quare by 49" high k The inner cavity is centered y [ 1 in the vault,and 'may be one of two sizes: ',15" square by 16" deep or 1l 27" square by'28" deep. The smaller cavity is surrounded by 18" of 3 structural ' concrete on the bottom and. sides indsby 15" on the top; the lrL
;I
], larger cavity is surrounded by 12" hn the bottom and sides and by 9" ;I
+ on the top! The overpack is a weldment'of 2-1/2" by 5" rectangular E 1 steel tube ~s to 1/2". steel plate.and' is sized and'honstructed to snugly {
1! enclose' the concrete vault.TThs lid'IsTsimilarly constructed and is 't { secured Cto the overpack' by ,a bolted 'andI qasketed ' closure. The overall i t li dimensions of the package ~are 64" by" 64". .The gr'oss weight is approximatelyil f 16,000 pounds. . . - -Alx' -% - if
),
m w- . ,8 1 (3) Drawings 9
~7
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't J The packaging is' constructediin .accordance withlestinghouse Electric g 3
Corporation Drawing Nos. 945F976',' Rev.;4; 930C940, Rev. 4 and 976C870, lt l Rev. 3. f) 4 1 %/ J w 1 lr
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j 172 i 1{ 1 t_w = = = =__ wwwwww ww w ww w ww w ww ww www w w w w-w ww.w w ww w ww w w ....r f
= = = = = **2"JmmutwzMrmst - - - --- mm -- . . m._ . . m. .. . . . . ,
NRC FORM sisA U.S. NUCLEAR REGULATORY COMMISSION l g g sm c0NDmoNS (continued) lp 4, Page 2 - Certificate No. 6142 - Revision No. 2 - Docket No. 71-6142 l l Ur El llI il lyh 4! (b) Contents l> ( (1) Type and form of material .R
- n fq Byproduct and special nuclear material in the form of radioactive waste which has been packaged in smaller cans or pails or as unpackaged {g Wl solid waste sealed in poured concrete. j 1
!# D
$ ;n
"! (2) Maximum quantity of material per package
,h I!
110 equivalent grams of U-235, where the number of equivalent grams of j h {g U-235 is determined by the equation: 1.0 x gram U-235 + 1.4 x grams y U-233 + 1.6 x grams plutonium, y l t
- (h (c) Fissile Class III p n
.E f Maximum number of packages per shipment 2 ig' f 6. Expiration date: tiay 31, 1988. j
?
;8 B
4 i
,B REFERENCE f h l f !q: Safety Analysis Report for Bettis Disposable Waste shipping container, WAPD-0(A0)-5029 j;g jgl dated September 30, 1969.
ll l4 FOR THE U.S. NUCLEAR REGULATORY COMMISSION !h
!D .)
lh
! j Charles E. MacDonald, Chief Transportation Certification Branch b Division of Fuel Cycle and g
{ Material Safety, NMSS lg SEP 0 61983 $y> lg Da te: 1 h
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m===ae-A=MARiWs==K=M M=W= M=W===mmage_i_m1Fmwp_st=_- N www ey Ia5[ " " " CERTIFICATE OF COMPLlANCE N, to CrR 7' FOR RADICACTIVE MATERIALS PACKAGES i taCERTw CATE NUMBER D MEVISiON NUveER c PACKAGE IDENTGICATION NUMBER d PAGE NUMBER e TOT AL NUMBER PAGFS 6144 10 USA /6144/B( ) 1 3 I .. PREAMBLE ; ll a This certificate is assued to certef y tnat tne packaging aad contents described in iterr. 5 twtow. mee's the applicable safet y standar ds set fortn in Titto 10. Code ig' of rederal Regulations. Pan 71,' Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions " , lll b in,s ceriibcate does not rei.e tne consignor f rom compnance airn any requirement or tne reguianons of ine u s. Depanmeni of Transportation or orner la] apphcaele regulatory agencies. including the government of any country tnrough or ento wnich the package will be transported
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f P ? CATION . U.S. Ecology Nuclear Engineering Company Application P.O. Box 7246 dated December 21, 1979. Louisville, KY 40207 M 71-6144 + c DOCKET NUMBER - + 1 4 CONOtTIONS This certshcate is conditional upon tuifilhng the requirements of 10 CFR Part 71, es appbcable. and the conditions specified below 5 (a) Packaging
, (1) flodel No.: B-2 (2) Eescription The packaging consists of a rectangular, double-walled box of welded mild steel construction with dimensions of 142 inches by 91 inches by 54 inches high which encloses secondary containers. The naximum weight of the loaded package is 42,000 pounds.
The double-walled box consists of an outer 1-inch thick steel shell ! and an inner 2-inch thick steel shell separated by 56 shock tubes, eight on each end, and ten on each of the two sides, top and bottom. The shock tubes are constructed of both 6-inch Schedule 40 and 8-inch Schedule 30 pipe. The tubes are 5 inches in length and are welded to the exterior of the inner box. The cover of the outer box is secured by forty-six,1-1/4-inch diameter high strength bolts. The lid of the inner box is sealed by two lengths of Garlock single lip closure seals and the seal pressure is naintained by steel springs which force the seal lip against the walls of the i inner box. (3) Drawing
! The packaging is constructed in accordence with Kenasco Corporation Drawing No. 6901-002B and Bill of Material No. 6901-002C. ;
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}1 (1) Type and fom of material i
gj Radioactive material as solids, in nomal or special foms packaged
, Ec within DOT Specifica tion 17H, 55-gallon steel drums, or other secondary ! r containers which meets the requirements of DOT Specification Type A ,
packaging. (2) ftaximun quantity of material per package l Greater than Type A quantity of radioactive material, not to exceed 5 watts and 5,000 poundslincludirig weight of the contents, secondary
~'
container (s), and shoring.
- 6. (a) For any package cont ining water and/or organic substances wMch could radiolytically generate combustible gases, detemination must be nade by ;
tests and measurements or by analysis of a representative package such that the following criteria.are net over a period of time that is twice the #! h expected shipment time:
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The hyd ogen generalAd must be linited to a molar quantity that would be no nore than 5% By volume (or equivalent limits for other inflanmable
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gases) 'of the seconda'ry cogtainer gas void if present at STP (i.e. , no more than 0.063 g-noles/ft at 14.7 psia:and 70"F). For any pacicage delivered to a carrier for transport, the secondary container 4, mus t be preoared for shipnent in ~ the same nanner in which .detemination for gas generation ;is nade. Shipment ' period begins when the package is prepared (sealed) and'aust be completed within twice the expected shipment time. (b) For any package containing naterials with radioactivity concentration not exceeding that forzlow specific activity material, and shipped within 10 days of preparetion, or within 10 days af ter venting of druns or other , secondary containers, the detemination in (a) above need not be nade, and
; the time restriction in (a) above 'does' not apply.
- 7. Dunnage nust be provided in the shipping cask cavity sufficient to prevent novement of the secondary containers relative to the outer packaging under nomal or accident conditions. ;
j 8. Prior to each shipment, the inner and outer lid gaskets must be inspected. The t gaskets must be replaced with new Garlock Model 23 Split Klozure if inspection :
! shows any defects or every twelve (12) nonths, whichever occurs first.
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__._i__._i_.____- U CONolTiONS (continued) Page 3 - Certificate No. 6144 - Revision No.10 - Docket No. 71-6144 jb l
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- 9. The package authorized by this certificate is hereby approved for use under the !
general license provisions of 10 CFR 971.12. l 10. Expiration date: January 31, 1990. REFERENCE . Nuclear Engineering Company application dated December 21, 1979.
- lii FOR THE U.S. NUCLEAR REGULATORY COMf11SSION W ci l ' . : ', (
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Material Safety,;NfiSS 4 Date: APR 2 4 MR8; *
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I _ ._ -_. __ _ __ M4NadifMWE=XM@hMN% IMNL ' l l Ip' i i NRC FORM 618 U.S, NUCLEAR REGULATORY COMMISSION k-an CERTIFICATE OF COMPLIANCE E 4: +' crA " FOR RADIOACTIVE MATERIALS PACKAGES t 4
.E D REVISION NUMBER C PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER g 1 e CERTIFICATE NUMBER e TOTAL NUMBER PAGES {
6'.72 4 USA /6172/B( )F 1 2 'E d PREAMBLE ih:
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$i a Tnis certificote is issued ta certity inat tne packaging and contenrs described in item 5 below, meets the appucabie safety standards set forth in Titre t O. Code of Federal Regulations. Part 71.
- Pacsaging of Rad oactive Materials for Tran . port and Transportation of Radioactive Materiai Uncer Certain Conditions." l:
l$f I b This certificate does not reheve tne consignor from comphance witn any requirement of tne regulations of tne U S. Department of Transportation or otner appocabie reguiatory agencies. inciuding ine government of any country inrougn or inia wnicn ene package . ie de iransported .h-
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E I 3 THsS CERT.FICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLeCATION g a PREPARED BY #Na*w and A&fressi b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION
.h Babcock & Wilcox Company Babcock & Wilcox Company application dated E P. O. Box 785 December 2,1969.
Lynchburg, VA 24505 Alh c DOCKET NUMBER k E l8 J l k a COND T.ONsTnts certificate is conditione upon vuirining tne requirements of to Crn Part 7i. as appuc oie. and ine cond.nons specit.ed beio. lli f* (a) Packaging [ E 4! ! p. (1) Model No.: 961A 5:
'E (2) Description Steel shipping container constructed in accordance with Applied Design Company, Inc. Drawing Nos. 961 Al, 961 A2, 961 A3. Steel angles shown as j!g l
Items 6 and 10 on Drawing Nos. 961 A3 and 961A2, respectively, shall be at 'E I least 2 inches high. p F k (b) Contents i E. E (1) Type and fom of material 3 E
'E Clad reactor preassemblies as described in application dated December 2, F-1969. Uranium may be enriched to any degree in the U-235 isotope. ,E k
(2) liaximum quantf ty of material per package f1 Not more than 2.9 kilograms of U-235. 5lE;
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i CONDITION % (continued) Page 2 - Certificate No. 6172 - Revision No. 4 - Docket No. 71-6172 i
- 5. (c) Fissile Class III ;
Maximum under of packages ! per shipment Three (3) ;
- 6. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 571.12.
- 7. Expiration date: October 31, 1989.
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Babcock & Wilcox Company. application dated December 2,1969. (~; i
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hi NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION { l CERTIFICATE OF COMI'LIANCE , l i ll ml 'o CFR " FOR RADIOACTIVE MATERIALS PACKt.GES c PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES D REVISION NUMBER 1 a CERTIFICATE NUMBER 2 (li 2 PREAMBLE 6188 3 USA /6188/B( )F 1 I a This certi icate f is issued to certify that the packagmg and contents described enitern 5 beiow. meets the apphcable safety standards set forth m Tetle 10 Code of ll Federal Regulations, Part 71. "Packagmg of Radioactive Materials for Transpon and Transportation of Radioactive Material Under Certam Conditions ' lg l lN;j 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 E h apphcable regulatory agencies, mcludmg the government of any country through os Lito which the package will b9 transported ll
!b I! lB ll 3 THis CERTIFICATE IS ISSUE 0 ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION h
- a. PREPARED BY ihame arid Aesresst b TITLE AND IDENTIFICATION OF PEPORT OR APPLICATION
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Safety Analysis Report for 25.0 Spare it U.S. Departinent of Energy Module Shipping Container dated February 6,1969, j!g d f Division of Naval Reactors I Washington, DC 20585 as supplemented. !n i Il 13 1. I! c. oOCKET NUMBER 71-6188 ll
!I l ! a cONomONS This certificate is conditional upon fulfilhng **ie requiremerits of 10 CFR Part 71 as applicable, and the conditions specified below l I l ly i
f (a) Packaging ll, 4 p I! g! (1) Model No.: 25.0 Spare Module !jg N: (2) Description 'lj Il il ll! y The container, constructed of;1/8-inch carbon steel plate, is circular Il in cross section, 40. inches ' diameter,/and approximately 360 inches l d ( long. It has a-removable upper half shell employing a stainless steel y closure flangefwith a rubber 0-ring gasket,for sealing. The four main p If 1j handling points of the container are located'on the sides at the ,g container base. Steel skids run the full leiigth of the container.
!N '8 Each fuetmodule'to be transported is clamped into a removable trough- lll
( g shaped strongback which is shock mounted',to the" interior of the lower i jE
'Th'e flandedl carbon, steel st'rongbsck with"Its stainless steel g
intervals with stamped I shell. liner i stationiumbers b323 inchest,long identifyingitho e holesito haVin'g's' be use hole'siat regular}d'in clam )i N i particular fuel. module.QEach"fdeLmodule type has'its own clamping lnl E ih u'se and arb stored within the ji i arrangehent;Wh'enz some aafpel clamps,.wi,llrnot
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dddulej lskins bej,'talled 'in the sealed container, R Ii contai n'e'r'. the container 'isfpurged;-and prefishized3 kit'h dry 3itrogen gas. Maximum l f g weight of@'1oaded ww Jcontainerg,ishapprogimately 10sli80 lbs. !jg e u #-m s g v g - d (3) Drawings yf T.tN4 u* M2 \@- h n E /l, % The packaging 'i(' constructed in)with accordance& Westinghouse Electric h f' Corporation Drawing Nos. ,901E851, Rev.1,' Sheet 1 thru 9 of 9 and I N g! I 901E440, Rev. 2, Sheeif Ifthrk'9-of 9f' j!g i; ' u 1: ll Il i i:
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ll, mac ronu sisa u.s. NUCLEAR REGULATORY COMMISSION fMn CONDmONS (continued ll l Page 2 - Certificate No. 6188 - Revision No. 3 - Docket No. 71-6188 I I :b t I S. (b) Contents lll li (1) Type and form of material
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l 1 I Unirradiated fuel assemblies of the following type, !lh
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n (i (i) AlW-3 new fuel module with control rod and upper control rod fh g s drive mechanism installed. j II (ii) Partial AlW-3 new fuel module with poison rods as shown on Westinghous i I Electric Corporation Drawing No. 927J942, Rev.1 and poison rod lock-in device as shown on Westinghouse Electric Corporation ip ! lj Drawing No. 938F030, Rev. 2. l (2) Maximum quantity of material per package. (i) One fuel assembly as described in 5(b)(1)(i). i l l 1 El i (ii) Two fuel assemblies as described in 5(b)(1)(ii). !p, ! in (c) Fissile Class III I l Maximum number of packages per shipment ll j f nine (9) } I 6. Expiration date: January 31, 1988. ig-E,l g (1 . g Q l REFERENCE - k l 11 I Safety Analysis Report for 25.0' Spare Module Shipping ContaiEer, WAPD-0P(R)SS-ll56 l l I dated February 6,1969. - 4 !,g l .. ii . - i y Supplements: Bettis ' Atomic Power Laboratory letters WAPD-0P(R)SS-1107 dated October 21,1968, WAPD-0P(R)SS-1333 dated July 3,1969 andlWAPD-0P(R)SS-1530 dated December it i 10, 1969. l i! .t J~ i il p -
.;sq. g lt I i I- ~FORTbEfU.S.NUC'LEARREGULATORYCOMMISSION ilg I !g
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l Char es E. M cDonald, Chief ' I! Transportation Certification Branch {l l I, Division of Fuel Cycle and !g fl Material Safety, NMSS p ( Da te: SEP 0 61983 {! h ll> i il l r I t I t'N i
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A=_=..=iF1-@ KAWWW=13HEiM92222WW=====_=__.- R av m ss a ' Ia CERTIFICATE OF COMPLIANCE
'C'"" FOR RADIOACTIVE MATERIALS PACKAGES c PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES i b REVISION NUMBER I a CERTiflCATE NUMBER USA /6206/AF 1 2 6206 7 PPEAMBLE a This Certificate es issued to ceftsf y that the pack agmg and Contents descnbec in item $ below. meets the applicable safely standards set forth i Cf Federal Regulations. Part 71.
- Packaging of Had*oactive Matenals for Transport and Transportation of Radioactive Mater at Under Certain Co l
b This certificate does not reiteve the consignor from compliance with any requirement of the e.gulat<ons of the U S Department of Transportation or other k applicable regulatory agencies including the government of any country through or into which the package will be transported : E R AP ATION a We D T LE AND DE IF CAT ON a PREPA ED8Vr a ' Babcock & Wilcox Company Babcock & Wilcox Company application dated P.O. Box 800 April 10,1985. Lynchburg, VA 24505 6
- c ooCxtr NuuBEa - 71-6206 k a cONoir,0~s
-a This certificate es conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the cond,tions specified beso*
,s (a) Packaging a
(1) Model No.: flodel B (2) Description A fuel assembly shipping container consisting of a steel strongback, clamping assembly, shock mounted to a steel outer container. Two, 3/16-inch thick, 8-5/8-inch high and full length stainless steel plates containing 1.5% mininum boron are positioned between adjacent fuel assemblies. The outer container is approximately 40 inches in diameter by 200 inches long. W
!Nl (3) Drawings HI The container is constructed in accordance with Babcock & Wilcox f'-
Company Drawing Nos. PE-5?F, Revision 2; PE-53F, Revision 1; and PE-54F, Revision 1. p fB (b) Contents H (1) Type and fom of material N U0 sintered pellet diameters ranging from 0.30 inch to 0.60 inch. 7 f Uranium may be enriched to a maximun 4.05 w/o in the U-235 isotope. i The pellets are clad in ninimum 0.020-inch thick zircalloy or minimum @ l l 0.016-inch thick stainless steel rods. The rods are assembled into fuel assemblies with a maxinum cross section of 8.6 inches by 8.6 jly i
!g inches. The void volume within the fuel assembly must not exceed two times the volume of U0 2 in the fuel assembly. ,
(2) Maximum quantity of material per package ' Two fuel assemblies containing not more than 18.8 kg U-235 per assembly. g , j II
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i CONCtTioNS (continued) Page 2 - Certificate No. 6206 - Revision No. 7 - Docket No. 71-6206 il
! 5. (c) Fissile Class II and III f{ tiininun transport index to be shown on label for y Class II 6.3 1 I(1)
E (2) Maxinun number of packages per shipment for Class III 20 j
- 6. Each fuel assembly must be unsheathed or must be enclosed in an unsealed, 1 f
polyethylene sheath which will not extend ,beyond the ends of the fuel assembly. ;' The ends of the sheath must notibeifoldedior taped ,in any manner that would prevent the flow of liqui.ds into or out of the sh'eathed fuel assembly.
- 7. There must be a clamp _ bow to restrain each spacer grid and.end fitting. The ratio of assembly weight to the number of clamp bows must not exceed 168.
I S. Fabrication of additional packagings is not authorized. '
- 9. The package authbrized by tMs certificate is hereby approved for use under the l general license; provisions of 10 CFR 671.12. i J, I
- 10. '
Expiration date:u ,' May 31,1990. s = .
'1 REFERENCES' g
Babcock & Wilcox Company application dated April 10, 1985. .
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. :. . . k FOR THE' U.S. NUCLEAR REGULATORY'C0titilSSION ,
h Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and [ Material ' Safety, NMSS i Date: ilAY 0 9 M l I i !8 l ; is jN R
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q--_____m --_______________- _________________________ ,lI I I I U.S. NUCLEAR REGULATORY COMMISSION ! N i unc ronu sis CERTIFICATE OF COMPLIANCE If i. e FOR RADIOACTIVE MATERIALS PACKAGES lIl Il io Crn r' b. REVISION NUMBER c. PACKAGE IDENTiFICAYlON NUMBER d PAGE NUMBER . TOT AL NUMBER PAGES 1 a CERTIFICATE NUMBER 4 1 'y 1 USA /6227/AF ( ;6227 ln y nl z eReAMRtEa Tn.s c.rt.ncat. v .s .ssu.o to certie inat m. packas.no ano cont nis o.seno.o initem s o.io.. m is tn. appucani.sa ,g I, F deral Regulabons. Part 71. -Packagmg of Rad.oectiv. Matenals for Transport and Transportation of Radioact.v. Matenal Unoe g 'N I; o Tn.s cern,.cai. oo not ren v. m. consignor from cornonanc. ..m any r.quir.m.nt of te,. r.gurat.ons at in. u s. o.partment of Transportation g or o
$ apphcat9. r.gulatory ag.ncies. mcludmg tne govemm.nt of any country tnrougn or mtc wnicn in. packag. well be transporteo. !)
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'N Il 3 TN.S CERTIFICATE iS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACMAGE a PPFPAPED BY (Name and Addresst I
l D 1H Oak Ridge Y-12 Plant Report Nos. Y-DD-152 !g Union Carbide Corporation June 1974 (DT-2), YDD-153, July 1974 (DT-5), Ql H P.O. Box Y Y-DD-160, December 1974 (DT-7). )l lg E Oak Ridge, TN 37830 t I
!g i 71-6227 I! . DOC ET NUMBER
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l ElaCONDmONS !I lj rnis certiv. cat. is cono t.onai upon euivinma m. requir.m.nts of to crR part ri. as appocaoi.. ano in cono.t ons spec.e.ao e.io*. 'lI li 3: a (a) Packaging j gl ll I, lg l (1) Model Nos.: DT-2, DT-5, and DT-7
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lli il Il (2) Description il 8 l l Packagings for Type A,quantit Contents are centeredouter?stgel lwithin' ydrums gof 3byuranium metals, alloys, industrial fiberboard {j 6 having a minimum ' density of 14 lbs/f t '. /J k g g; Q g l' ,
*i_ II l The DT-2 issan 18-gauge DOT Specification 17fCsteel drum 22-1/2 inches I 8l in diameter;by 33 inches high; it has a 14-gauge lid closed by a 12- I gaug? bolted ring with drop-forged lugs and'a 5/8-inch steel bolt and l
[ lock nut-
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g holds t,h[., A 16-inch x( <16-inch contenthplates. ,The,packsge gioss weight is 220 pounds. x 0.5-inch"cavitf"inj!gth o nt
- 6 7,-
The DT-5{is an 182 gauge)90TsSpecification 17H steel drum; 22-1/2 N ! ll i inchesindiameterbp33,! inches by li f a 12-ga}ug,e bolted ring with dro%igh;4 f t has, a 14?saug {l f and lock ' nut.6The> inner container ris a* DOT Specification 17H drum; 14 {j N gll diam'etert 24-5/8 jinbhes {high. . The' paclUige gross weight is d,ygy j pQ f g inchesipj g' < tyy. ag 330 pound,s - V, gl; il l fr 4n' m.'
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NRC FORM steA o U.S. NUCLEAR REGULATORY COMMISSION I conomONs (continuas
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h Page 2 - Certificate No. 6227 - Revision No.1 - Docket No. 71-6227 lj 1 1
!i li :I Il f 5. (a) (2) Description (continued) 'I i
l The DT-7 is a 20-gauge D0T Specification 37A steel drum; 16 inches in g diameter by 24-1/2 inches high; it has a 14-gauge lid closed by an 18- jl l gauge bolted ring with drop-forged lugs and a 3/8-inch steel bolt and lh l{l lock nut. The inner container is a 12-quart tinned can 8-5/8 inches k g f in diameter by 13 inches high with a press-on lid. The package gross lNl gj I, weight is 75 pounds. j I (3) Drawings !g gli 1
!gI 1: The containers are constructed in accordance with drawing found in the !g ti
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Oak Ridge Y-12 Plant reports: !I ig (i) For the Model No. DT-2, pg 7 of Report No. Y-DD-152; I lIl (ii) For the Model No. DT-5, pg 7 of Report No. Y-DD-153 (as revised !g I by letter to report Y-DD-153 recipients from R. J. Fraser)- y
!; y i
(iii) For the Model No. DT-7, pg 7 of Report No. Y-DD-160. I f (b) Contents , j n; & (1) Type and form of materials !g li 'y I [5 g. Uranium of any enrichment in the U-235 isotope. I t y (1) A flat plate of uranium metal with dimensions no greater than 16 I q inches x 16-inches x 0.4 inch, held in the'.Model No. DT-2. i l l (ii) Uranium metal or alloy as;a single piece with no dimension greater !,g i llj than 14-inches held in'an. inner DOT Specification 17H container j ll (14 inches in diameter by124-5/8 inches high) in the Model No. il DT-5.
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1, (iii) Uranium metals, alloysior; dry compounds held' in the Model No. ; I DT-7 within a 12-quart l tinned can,' 8-5/8, inches in diameter by 13 y, I ly inches high with'a press-on lid. '; jg l j 1, lg i (2) Maximum quantity of material 3per package notIto exceed a Type A quantity I g! of radioactive material. ,p g): g s- jl (i) For the material described in .5(b)(1)(1) not more than 32 kg of I; I uranium. J j'y f[ l y (ii) For the material described in 5(b)(1)(11) not more than 20.0 kg (p-of U-235. f (iii) For the material described in 5(b)(1)(iii) not more than 250 g of I U-235. { i g I; l i I (v) For the material described in 5(b)(1)(iii) not more than 500 g of , t-I U-235. ) ! I' 184 i 4 l L; _ m _ _ _ _ _ _ m _ _ _ _ _ _ m . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ J!
_---------------_____________________________________,f! U.S. NUCLEAR RE ULATCGY COMMQON f NRC Au FORM UM CONDmONS (continuedi !l g !g I lt Il Page 3 - Certificate No. 6227 - Revision No.1 - Docket No. 71-6227 :l li :I ll !I li *p i II and III i
!y p (c) Fissile Class N lpl (1) Minimum transport index to be shown on if label for Class II. 1lI I
[!I (i) For material described in 5(b)(1)(i) and limited in 5(b)(2)(i) 1.1 l jf i
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(ii) For material described in 3.4 !) l 5(b)(1)(ii) and limited in 5(b)(ZHii) lI. i (iii) For material described in 0.1 ;j l 5(b)(1)(iii) and limited in 5(b)(2)(fii) !I i lg (iv) For material described in 10.0 ;p l 5(b)(1)(iii) and limited in 5(b)(2)(iv) :l lh j i (2) Maximum number of packages per shipment as Class III. f (1) For material described in 122 ;p 5(b)(1)(i) and limited in 5(b)(2)(1) lR i ;N i (ii) For material described in 37 il
! 5(b)(1)(ii) and limited in 5(b)(2)(ii)
(iii) For material described in 200 !g 5(b)(1)(iii) and limited in 5(b)(2)(iii) !I lp (iv) For material described in 10 lI 1 5(b)(1)(iii) and limited in 5(b)(2)(iv) it j l 6. The package authorized by this certificate is hereby approved for use under the ll 11; general license provisions of 10 CFR 571.12. j)n l$ 7. Expiration Date: March 31, 1987. .I Nj !N
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NRC FORM staA m U.S. NUCLEAR REGULATORY COMMISSION l conomans (continuem Page 4 - Certificate No. 6227 - Revision No.1 - Docket No. 71-6227 {in lt 19 ll
!I REFERENCES lI in p
1 Oak Ridge Y-12 Plant report Nos. Y-DD-152, June 1974; Y-DD-153, July 1974 with revision !b per R. J. Fraser letter to report recipients dated July 17,1974; Y-DD- 160, December I 1974. ! q 1; FOR THE U.S. NUCLEAR REGULATORY COMMISSION i 3} ! 1: Charles E. MacDonald, Chief ! 1l Transportation Certification Branch , li Division of Fuel Cycle and ' li Material Safety, fMSS ! ji SEP o a 1983 Date: i 1 ! 1 1l 1;l r l y
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36MJOE@2' MINLTSMLR= =id'n8Mm = = = = =H8NNWWT*LW_ _ _ _ _ _ IS CERTIFICATE OF COMPLIANCE t OR RADIOACTIVE MATERIALS PACKAGES 4 to cr A " c PACKAGE IDENT*FICATION NUMBER o PAGE NUMBER e TOT AL NUMBER FAGES ' b REVISION NUMBER T a CERTIFICATE NUMBER 7 USA /6244/B( ) 1 3 6244
. PREAMBLE
- a. This certificate is issued to certif y tnat the packagmg anc cor+ tents described m item 5 below, meets the apphcaole safety standaros set fortn inTitle 10. C>de of Federal Regulat,ons Part 71. "Packagmg of Radioactive Materials for Transport and 1 ransportation of Radioactive Material Under Certa n Conditions "
b This cert,ticate does not rehe-e the consegnor f rom comphance m.tn any requirement of the regulations c' the U S Department of Transportatiors or other apphcacie regulatory agencres. ncluding the government of any country tnrough or into which the package wdl be transported. D Ti LE AND ICE IF T ON O E R AP ICATION PREPA E BYthe A ress Chem-Nuclear Systems, Inc. Chem-Nuclear Systens, Inc. application 220 Stoneridge Drive dated May 14, 1984, as supplemented. Colunbia, SC 29210 e oOCxEr NUuBER 71-6244 4 CONDITIONS This certificate is cond<tional upon fulfillmg the requirements of 10 CFR Part 71. as apphcable, and the conditions specified betow (a) Packaging (1) Model No.: CNS 4-85 (2) Description . The package consists of a steel and lead shielded cask. The cask is positioned within an overpack constructed of steel and honeyconh na terial . The gross weight of the package .s 46,000 pounds. The mild steel cask is approximately 111-1/2 inches in length and 58 inches in dianeter. The walls, top, and bottom are of 2-inch thick - steel plate. Shielding is provided by 2 inches of lead within the walls and 2-inch thick steel walls of the cask. The cask lid is secured to the cask body by twenty-four, 3/4-inch diameter bolts and is sealed by a compressible polyurethar.e seal. Lifting devices are ' attached to the lid and body of the cask. The cask is positioned within an overpack approximately 139-1/2 inches ; in overall length and 89-3/8 inches in diameter. Aluminun honeycomb naterial is confined by an outer steel shell 3/8-inch thick and an inner steel shell of 1/4-inch thickness. The overpack cover is of the same construction as the rest of the overpack and is secured to the walls by eight, 5/8-inch dianeter bolts. Lifting devices are welded ! to the outer shell of the overpack cover. (3) Drawings 1 i The package is constructed in accordance with Nuclear Maste Systems Drawing No. D-6930-1, Rev. F (Sheet 1 of 2) and Chen-Nuclear Systems Drawing No. D-6930-1, Rev. E (Sheet 2 of 2). [N (E u>ll i i b l*P l !p.
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L conomons tcontinued; '"" ^ " ' ' I; I; Page 2 - Certificate No. 6244 - Revision No. 7 - Docket No. 71-6244 tij I (b 6 i i k
\Y I. il gi 5. (b) Contents :N
' I: ;g 1 l (1) lype and fom of material R Il lH
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- I (i) Greater than Type A quantity of hyproduct material as process solids, either dewatered, solid, or solidified, in secondary
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container (s) which meet the requirements for DOT Specification 7A j packaging; or ,I it } (ii) Greater than Type A quantity of byproduct material as solid metal components in secondary containers, as required. jg
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, (2) Paximum quantity, ofy naterial per package, / Iq y g 4. - % a ,3; Not to exceed 10 thennal watts of byproductY material. The contents ' may includeNfissile materials provided the mass 'linits of 10 CFR 671.53 j;i are not exceeded. g i
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- 6. (a) For any package containing water and/or organic. substances which could g
'n radiolytically generatefcombustible gases,'detennination aust be made by .N tests and measurements or by, analysis ,0ffa . representative package such that j
I .h the following criteria areinet over a' period tof time that'is twice the ', expected shipment time':- lt . J n, '. / " 4 f ' m s
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j ;g g (i) The hydrogen generat5d,must be limited to a: molar quantity that would
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- be no more than15% by vol.ube i(M gases) of the secondary. cogtainer(equivalent limits lI gas void. if present at STP for other (i.e., no inflamna l
', more than 0.063 g-moles /ft. lat; 14.7; psia and /0'F)('or i iE q 2 . ~- > ;7 . n ;o ,I s
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,g (ii) The second.ary container an;d cask cavity must be,inerted with a diluent !g 3
! to assure that oxygen mustibe limited to 5% by, volume in those portions !g 4 of the package which could 'have hydrogen greater than 5%. lI 7 %,
.g For packages to be delivered to a carrier for tra'nsport, the secondary container must be prepared 'for shipmentlin'the same manner in which deter-i j i
j g' mination for gas generation is 'made. Shipment period begins when the !gg
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is prepared (sealed) and nust be cmpleted within twice the expected l I' lt i
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n ! f (b) For any package containing naterials with radioactivity concentration not j g. q! exceeding that for low specific activity material, and shipped within 10 !]g , i i l; days of separation, or within 10 days after venting of drums or other !g j secondary containers, the detemination in '(a) above need not be nade, and it li the time restriction in (a) abtve does not apply. I lI
- 7. il f The lif ting lugs on the outside of the overpack shall be covered during trans-g port to prevent their accidental use for the purpose of tie-down or lifting. ljg I.
i 1 8. Shoring shall be placed between the secondary containers (or activated con- I I It ponents) and the cask cavity to minimize movement during nomal conditions of trans port, ll j ! li{ i I 18a I I!-- - I I
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;N s CONolTIONS (continued) l; ;
l ', g i N. g, Page 3 - Certificate No. 6244 - Revision No. 7 - Docket No. 71-6244
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il }I j' 9. The lid polyurethane seal shall be replaced prior to final closure for each jg ,
} 8' shipment.
.i 8, 10. Fabrication of additional packagings af ter August 31, 1984, is not authorized.
- 11. The package authorized by this certificate is hereby approved for use under the
($ lgl general license provisions of 10 CFR 671.12. '
; l lg gl 12. Expiration date: August 31, 1989.
REFERENCES l f Chem-Nuclear Systems, Inc. applicstion dated liay 14, 1984. 4. H: Supplenent dated: August:3, 1984. FOR THE U.S. NUCLEAR REGtlLATORY C0f*t11SSION SL Charles E. Mcdonald, Chief Transportation Certification Branch Division of Fuel Cycle and liaterial Safety, NMSS Date: APR 2 41985
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'o crR 7' CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIALS PACKAGES t a CERipFICATE Nuv8ER D REVISION NUMBER c PACK AGE IDENTIFICATION NUMBEM G PAGE NUMBER e TOTAL NUMBER PAGES '
6272 9 USA /6272/B( ) 1 3 j PAEAVBLE l' a This cerfehca:e is issued to cert,ty that the packaging and contents described m item 5 below, meets theapphcable safet y standards set forth en Tetle 10 Code of Federal Reguiahons Part 71. Packagirig of Radioactive Materials for Transport and Transportation of Radioacteve Material Under Certain Conditionsf' b This cert;ficate does not reheve the consignor from comphance with arty requirement of the regulahons of the U S Department of Transportation or other 4 h apphCable regulatory agencies, including the government of any Country through or into which the package edl be tran5porled a e oE
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i j . U.S. Ecology Protective Packaging, Inc. application P.O. Box 7246 dated June 24, 1974, as supplemented
! )f. Louisville, KY 40207 i
i (4 71-6272 )? c DOCKET NUMBER . I 4 CONOiff0NS This certshcate is condehorat t, con fulfdhng the requirements of 10 CFR Part 7 f. as appucable. and the conditeoris specified tw tow 5 I i (a) Pa ckaging: l (1) ifodel No.: 6272 (2) Description ' i A protective overpack having a double-walled, low-carbon steel shell ! is (3/16" outer wall and 20-gauge inside wall) with rigid polyurethane f-foan (nominally 7" thick) thermal-shock insulation between the walls. The edges of the overpack are reinforced with 10-gauge steel angles i If welded to the outer face of the walls and internal diagonal 14 guage 18 steel plates. Overpack lid closure is provided by three,1" steel h rods which extend the full width, welded to an end plate at one end j and secured by a pin at the other end. Enclosed within the overpack lY l k b is a bolted and gasketed low carbon steel inner container. The container fj will be either of two similar designs, M-3A or M-4 The gross weight}}