ML19225A319
| ML19225A319 | |
| Person / Time | |
|---|---|
| Site: | 07105942 |
| Issue date: | 06/12/1979 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML19225A313 | List: |
| References | |
| NUDOCS 7907180848 | |
| Download: ML19225A319 (4) | |
Text
.
f or m N H C 618 U.S. NUC L E AH HE G U L A TO R Y CO ?.".'15 SION (12 73)
CEHT!HCATE OF COMPLI ANCE 10 Cr H il f of H. win urt he Wter s ils Pack ages 1 (al C rt a e Numt rr 1 f td He in No Ifc' Pa
- 1. (d ) P u.7s No1.(el T c t No. Pages 2.
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iter i as Ih-nl et o n s ( 1 ) C F H 1/U 1PJ anet 14 Cf H IUJ) an.1 ' er taan 14ti 19 10 s an 1 14G 19 100 of the Department of Ir anspr u t ion () in ;er ous Carties He iol it n;r's (4G Cl H 146 I t)).
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? hd The pu L i pn a an<l c ontents drw rit rf in atm b l.. la, rm ets t he s i e t, st eu f u t!s u. f.u t h in ' o! par t C o f T ief e 10. C<,de c.f I nievi f(equi J +ons, Par t 71,"Pai., ov;of Hofeu: tae Ma t er i.,is f ;r T r an' por t an41 T r anv;r t it on of H.n h1uttie 'f at eri d Uri. ler Cer t on C(ov lit n ins.
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T h e. u r t i t o
< ! es ro.t r el awe t h e t on',r; v ar f ro rn ( o rr.iih.
ch cny reiunernent af the re patations of the U S Dep uto ent of
<e s
i r ontp ie t a t i.o or e q her al,idiuble re1olatory alanues, inc lu f o ;the 4 >.er ninent of any countr y throt di or n.to c hu h t he p n.L i m nill f.e t r a i.. r t ia l.
3 i his certif u ste is isser t an the ha s of a saf et y analy sis repor t of the pu k eye tieu ;n nr a ppl u..t io n 3 Ld Pr epatri by n',
m f i L!..s) 3(td I i t le and id e n t if a anon of repor t or apph: anon General Electric Corapny General Electric Application dated Decembei 23, P.O. Box 400 1968, as supplemented.
Pleasanton, CA 945G6 71-5942 3ni o o,.t t.
4 m.iH om l h es ( er tif n ate is r n.ht n n st up rn t he f ulidhr:q o f t he r -;u ent s 4
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, Off,e ' C4 ? f r jil P ! rls e f ts l I d p f e r e f u e s (a)
Packaging (1) itodel I;o.
GE-700 (2)
Description A steel encased lead shielded shipping cask enclosed by a double-walled protective jacket of she sane shape with a rectangular base-plate.
The cask is a double-walled steel circular cylinder, 37-inch-diameter by 65-inch high with a centtal cavity 15-inch-diameter by 40-inch high.
Approximately 10.25 inches of lead s.rround the central cavity.
The cask is equipped with a cavit; dral, line and lifting device.
Closure is acconplished by a gasketeJ and bol ted steel lead filled plug.
The maximum weight of the packaging is
?3,000 pounds.
The cask may be rodified with a 14-inch high cavity extension.
The modified cask is 79 inches high and weighs 28,000. pounds.
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Page 2 - Certificate No. 5942 - Revision No. 2 - Docket No. 71-5942 5.
(a) Packaaing (Continued)
(3) Drawings The packaging is constructed in accordance with the following General Electric Company Drawings Mos.:
237E325, Rev. 2 106D4150, Rev. 0 116D4331, Rev. 0 195F127, Rev. 0 289E646, Rev. 1 289E647, Rev. 1 289E642, Rev. 2 (b) f ntents (1) Type and form of material Byproduct, source, and special nuclear material contained in solid or metal oxide form.
(2) Maximum quantity of material per package (i) 740 gm U-235, provided + hat the maximum U-235 enrichment does not exceed 6 weight percent; or (ii) 1,200 gm U-235, provided that the fuel material is in the form of MTR-type fuel elements with a minimum active fuel lene of 23 inchas; or (iii) 220 gm fissile material; or (iv) 1,650 gn U-235, provided that the maximun U-235 enrichment does not exceed 3.5 weight percent and the fucl material is in the form of 88 rods loaded with 0.376-inch-diameter pellets with a minimum active fuel length of 37 inches; or (v) those values presented an Figure 1, UO, Weight Limits for Model 700 Shipping Container, of GE application dated February 25, 1970, applicable to fuel material in the form of rods with a minimum pellet diameter of 0.40-inch; or (vi) 5,100 gm U-235, provided the fuel is in the form of ETR-type fuel elements (GETR Fuel) with each element containing no more than 510 gm U-235 and inserted in the spaced stainless steel fuel shipping basket described in GE apnlication dated February 25, 1970 and GE Drawing No 106D4150, Rev. O.
409 335
Page 3 - Certificate fio. 5942 - Revision fio. 2 - Docket flo. 71-5942 5.
(b) Contents (Continued)
(2) Maximum quantity of mater.al per package (Continued)
(vii) 6,200 gm U-235, provided the fuel is in the form of MURR TRTR type elements containing not more than 775 gm U-235 per element; loaded and spaced in the stainless steel fuel shipping basket as described in MURR Drawing flo.1228, Sheets 1 thru 5, Revision 0.
Fuel elements shall have at least 150 days cooling time since last reactor operation.
l (3) flaximum quantity of radioactive decay heat per package (i) 6,500 watts for dry shipments, or (ii) 1,500 watts for wet shipments, provided that the cavity shall 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)
Fissile Class III Maximum number of packages per shipment 2
6.
The material specified in Paragraph 5.(b)(1) shall be clad, encpasulated, or contained in a metal encasement of such material and construction as to with-stand the combined effects of ir.ternal heat load and the 1475' fire with the closure pretested for leak tightness or in accordnace with the statements and representations contained in GE application dated February 4, 1969.
Shoring may be provided to minimize movement of contents during transport.
7.
The applicant shall confirm annually th=.t the pressure relief valve is operable at 100 psig.
8.
When needed, sufficient antitreeze in the cask shall be used to prevent damage of any component of the package due to freezing.
9.
The total radioactivity in the coolant shall not exceed the limits specified in 10 CFR 971.36(a)(2).
10.
The package authorized by this certificate is hereby approved for use under the ger.eral license provisions of 10 CFR 371.12(b).
11.
Expiration date:
April 30,1930.
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Page 4 - Certificate flo. 5942 - Revision flo. 2 - Docket flo. 71-5942 REFERENCES General Electric application dated December 23,1/8.
Supplements dated:
February 4, 8, and 27, 1969; February 25, 1970; and April 4 and June 7, 1972.
Additional References Required for the Contents Limited In Item 5.(b)(2)(vii).
University of Missouri application dated January 10, 1979.
Supplement dated: flay 22,1979.
FOR THE U.S. IlUCLEAR REGULATORY C0" MISSION
(( j(
du b
Charles E. MacDonald, Chief Transportation Branch Division of Fuel Cycle and flaterial Safety Da te: dI3d 1 E IS' 409 337