ML20205E757

Certificate of Compliance 9183,Rev 5,for Model NAC-1. Approval Record Encl

ML20205E757
Person / Time
Site:	07109183
Issue date:	03/20/1987
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20205E753	List: ML20205E748 ML20205E757
References
NUDOCS 8703310006
Download: ML20205E757 (5)

Text

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I I seni: pones sis U.O. NUCt. EAR REGULATORY COMMISSION I

I am CERTIFICATE CF COMPLIANCE I I socrR n __ FOR RADIOACTIVE MATERIALS PACKAGES

c. PACKAGE lOENiiF4 CATION NUMBER d PAGE NUMBER e. TOTAL NUMBER PAGEs ti REVISION NUMBER 1 ACE..it'$E'""SER 5 USA /9183/B( )F 1 3 ,

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e. This certificate is issued to certify that the packaging and contents described in item 5 below, meets the appl cable safety standards set forth in Title to. Code l l

of Fedeial Regulations. Part 71.

• Packaging and Transportation of Radioactive Material" l l

I I D. This certahcate does not reheve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportatioe or other I i I apphcable regulatory agencies. 6ncluding the government of any country through or 6nto which the package will be transported.

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s. rygrir,icays;ssgurse sAsis or A sArciv ANattses Regtgr,syggGgoesgogRpygioN I

I I Nuclear Assurance Corporation Nuclear Assurance Corporation application dated I I 5720 Peachtree Parkway June 30, 1984, as supplemented. l Norcross, GA 30092 i l , _

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~ ooexer wuu8u h l77. 9183 e

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a conoit.oNs + ,,5 This certificate es conditional upon fulhthng the requirernents of 10 CFFI Part 71, as apphcable, and the conditions specified below-l 5 n- l l .V I l (a) Packaging i  !

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I (1) Model' No. : NAC-1:' x I I :J J  %' '

(2) Description -

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A steel and lead shielded shipping cask., The cask is a-right circular i i cylinder with upperc and lower steel encased balsa impact limiters. I The'overa11' dimensions'are 214 inches -in length and 50 inches in i I

I diameter. ' The ' gross, weight"of]thelcask-is approximately 49,000 pounds. l l The inner cavity;is.178 inches;1ong and 13.5 inches in diameter. The i l thickness of the inner sh' ell is 5/1.6 inch and 1-1/4 inches for the g i outer shell.' .Theitwo stainle'ss stee1 ~ shells are welded to a 2-inch l l thicksstainlessJsteel"shieldrdise,at the. bottom. The-annulus between i I the inner > and outer shells 'is filled with -lead (max.;1ead thickness I I

I 6-5/8 inches, minimum 5 inches).-

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, The lid is stainless steel frustum of cone 7.5 inches thick. The lid i i

is secured to the cavity flange by six,sASIN-A320 Grade L43,1-1/4 inch l I

diameter bolts. Theiseal is provided byitwo polytetrafluoroethylene i I

I 0-rings. Four trunnions,,ltwo / located on either side of the upper or I lower impact limiter, are provided. Other cask features include two l drain valves located in the bottom shield disc, vent valve, head i l closure gasket leak check valve, and rupture disc - pressure relief i i

valve system located in the cavity flange, For transport the cask may i I be enclosed in an expanded metal cage. I I

I (3) Drawings l l I 1

i The Model No. NAC-1 shipping cask is constructed in accordance with i i

Nuclear Fuel Services, Inc., Drawing No. E 10080, Sheets 1 through 4, i Rev. 21, as modified by Nuclear Assurance Corporation letter dated i I

I I July 24, 1986. I I

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I I B703310006 070320 I l PDR ADOCK 07109183 _ _ _ _ - - _ _ _ _ _ _ l l _ _ 4 ,_ C P DR _ _ ._ ,, ,

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, ,' ' ' '% .* t CONOlTIONS (continued)

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Page 2 - Certificate No. 9183 - Revisicn No. 5 - Docket No. 71-9183 (

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5. (b) Contents (1) Type and fortn of material l (i) Clad, irradiated metallic natural uranium fuel rods. l l

(ii) Solid nonfissile irradiated hardware. l (2) Maximum quantity of material per package l i

The cavity content must not exceed a thermal decay heat load of 750 lr iinf luding weight of component spacers I watts (or fuel basket) use'd lihkhe 'cas lbl[li ba'vitf/to limit movement of and a weight of g,700 contentsI during shipmen Edel rods are additional 1 mited as follows: (

(1 ~D 21intactrodsor10 encapsulated (defect *fe) rods f (if 1,600: MWD /MTU average burn-up 4 r cooled ~for-at least 365 days after irradiation 6 l (iii u; < +- ll Y / /. g/ I g (c) Fissile ClassL/

b. Ny((h R, P) de g l

g g

6.

The cask cavity transport. M must be .gdry '(nj A - ['d., free wat'er)

' fj f w ch' ,~. delivered to,a! carrier

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7. As needed, appropriate component lspacerst(fu 1 basket and axial, spacers for

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I shipment of fuel ' rods) must be,used in the cask cavity',to '

limit movement of

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contents during accidentTconditions' f: tra'nsport. h

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8. The neutron shield' tanks must'be drained >and. maintained in a' dry condition in I accordancewithSection}ofthe'applicatf,on,'as< supplemented. .

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9. In lieu of the requiremeds;of 10 CFR 671.87(e), the l'ic'eNsee must perform periodic maintenance and testing of 0-rings, drain and vent ball valves, relief f valves, and rupture discs of the cask,a.s indicated in the table given below. g During inactive periods, the maintenance and' testing frequency may be disregarded I provided that the package is brought into full compliance prior to the next use of {

the package.

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' '~";" W**"* l conomons (continued) l L

Pag? 3 - Certificate No. 9183 - Revision No. 5 - Docket No. 71-9183 l l

Cask Component Period Test / Action l Ball Valve Each shipment Hydro test to 30 psig*

Replace seats and seals

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Ball Valve Annually 0-rings Each shipment Test to 30 psig* l 0-rings Annually Test to 100 psig*

l Inner Containment Vessel Annually Test to 100 psig* l l.

Cavity Relief Valve Annually Test at set point r c

Cavity Rupture Disc nn4ua y REG 9Weace (

Neutron Shield Tank b '/h (

Rupture Disc s Annually Replace)

Impact Limiters Annually Test;t'o psig*

g9 ,'x% . . gy ~ (

GTheremustbenovisual(pressuregauge)._ indications [ofpresquredropforthe (

component under I!est duringea410_-dtinutestest p'er:icdi Otherwise, corrective action t must be taken and.the test r'epeated until such timefas the coinponent meets the [.

specified test. '(Test to pressures equaltto orfgreater ', than those indicated.) r F- , . Q.J 1: p.g.1:- , 5 t 10 Fabrication of additionalc pack' age'sais pot 7authorizede ,

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11. ThepackageauthorizedbFkh[scet i ickh herebyf ahproved for use under the [

general ifcense provisions ofi10:CFRJ 671212 W:hi ,i CO l

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12. Expiration date: September 30,k9890 I

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REFERENCES

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Nuc1 car Assurance Corporation applicatfon da.ted June-30,1984. I

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. Supplements dated: September 10, 1984; July 24, 1986; and February 10, 1987. [

FOR THE U.S. NUCLEAR REGULATORY COMMISSION f V

L Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and L Material Safety, NHSS I I

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Transportation Certification Branch Ap)roval Record Model 40 . NAC-1 Package Docket No. 71-9183 By application dated February 10, 1987, Nuclear Assurance Corporation (NAC) requested a revision to the Model No. NAC-1 package (cask) for the shipment of irradiated metallic fuel with reduced cooling times from two years to one year and increased decay heat load from 625 watts to 750 watts.

STRUCTURAL The proposed changes have no significant effect on the structural properties of the cask.

THERMAL The proposed reduction in cooling time from 730 days to 365 days increases the decay heat load from 625 watts to 750 watts. This increase in heat loading would not significantly alter the cask's thermal behavior during normal or hypothetical conditions.

The cask was originally designed to transport 150 day cooled PWR fuel with a maximum heat load of 11,500 watts (42,000 BTU /hr.), and was designed with a neutron shield tank to reduce the neutron dose rate. The neutron shield tank would be empty during the shipments proposed in this amendment. This would allow the neutron shield tank to act as a thermal barrier during hypothetical accident conditions. The presence of this thermal barrier kee)s the cask's critical components, i.e., 0-ring seals and cavity rupture disks, well below their maximum operatin There is no melting in the gamma (g temperatures lead) during accident shielding. The requirements of 10conditions.

CFR 971.43g are met by shipping the cask in a closed container.

CRITICALITY Since the enrichment of the metallic uranium fuel rods is natural, no criticality hazard exists either for the nonnal or accident conditions of transport.

2 SHIELDING MC requests an amendment to permit the shipment of irradiated natural uranium fuel rods cooled for one year (versus the 730 day cooling time in the present certificate) in the Model No. NAC-1.

The above condition of one year cooling time is acceptable. This is based on appropriate comparison of the metallic fuel with a conservative PWR reference fuel source term.

Comparison of pertinent parameters indicate gasma dose rates for the Model No.

NAC-1 cask when loaded with one year cooled metallic fuel to be 5.6% of the PWR reference fuel. Similarly, the neutron dose rates for the cask are 0.05%

that of the PWR reference fuel.

The applicant's accident dose rates (with shield tank fluid removed) are at one meter from the cask surface as follows: (1) a gamma dose rate of 6.68 mrem /hr, and (2) a neutron dose rate of 10.8 mres/hr (erroneously reported as 3.34 mrem /hr and 0.4 mrem /hr, respectively).

The NRC staff is in agreement with these dose calculations and results.

The above changes will not affect the ability of the cask to meet the requirements of 10 CFR Part 71.

h:

Char' es E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date: EN

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