ML20214J409

Certificate of Compliance 9183,Rev 4,for Model NAC-1. Approval Record Encl

ML20214J409
Person / Time
Site:	07109183
Issue date:	07/30/1986
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20214J396	List: ML20214J394 ML20214J409
References
NUDOCS 8608140626
Download: ML20214J409 (4)

Text

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nne roms m u.s. NUCLEAR REGULATORY COtttMSSION I r om CERTIFICATE CF CCMPLIANCE I to crR n .

FOR RADIOACTIVE MATERIALS PACKAGES i.a cERrwicATE NUMBER b. REVISION NUMSER c. PACKAGE IDENTIFICATION NUMBER d.PAGE NUMSER e. TOTAL NUMeER PAGES l 9183 4 g USA /9183/B( )F 1 3 1 : PREAM8tE l a. This certificate is issued to certify that the packaging and contents descni,ed in item 5 below, meets the applicable safety standards set forth in Title 10. Code l of Federal Regulations. Part 71. -Packaging and Transportation of Radioactive Material."

I b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other I apphcabie reguistory agencies. inciuding ine government of any country tnrough or into whien the package wiii ne transported.

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l 1 g i g is as guEoN Tu sAsis or A sArErv ANAtysis reg,7gr,NgGE,ogGNgego cgoN I

i Nuclear Assurance Corporation Nuclear Assurance Corporation application dated l l 5720 Peachtree Parkway June 30,1984, as supplemented.

I Norcross, GA 30092 I

I - ' C m ,71-9183 I # c; DOCMET NUWeER t ,

4. CoNOITiONs ~, ' \#

This cattificate is conditional upon fulfilhng the requirements of 10 CFR Part 71, as apphcable, and the conditions specified beiow.

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i (a) Packaging .

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I (1) Model No.:. NAC-1 -

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• I (2) Deschi'ption'N[x f- 1 1

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i Al steel and leadyshieldedcibippingscask'.~ Jhe cask is a right circular ,

i cyJinder with upper 7and lower steel enca; sed balsa impact limiters. l I The,overall dimensions are'i 214 inches;in length and 50' inches in , ,

I diameter, eThe ' gross 'weighFof-the caskii's approximat'ery 49,000 pounds.  :

I Th e_ i nners cayi tyyi s:178ti nche s _l ongf an'dyl3. 5 i nche s in! di amete r. The I

thicknesssoP the inneFsheld is 5'/.16sinch.and?T-l/4 inches for the =

l outer shel:lf.S'The,twoestain'less Isteel' shellsTa're weldid to a 2-inch i thicle. stain 16'ssisteelcshield discEat. the bottom. The' annulus between

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t I the-inner andiouter shells 11s fi1>ledhwith ' lead (max'mlead thickness I 6-5/8 inches, minimum 5 inches)'.x +

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I The liAfs. stainless steel / frustum of cone 7.5-incies thick. The lid l is secured.to, the cavity flange'by six, ASTM-A320, Grade L43,1-1/4 inch '

i diameter bolts. The seal is provided by twoipolytetrafluoroethylene l l 0-rings. Four trunnions, two located-on either side of the upper or  ;

I lower impact limiter, are provided Other cask features include two I drain valves located innthe bottom, shield disc, vent valve, head l closure gasket leak check valve, and rupture disc - pressure relief i

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

I I (3) Drawings l

The Model No. NAC-1 shipping cask is constructed in accordance with l Nuclear Fuel Services, Inc., Drawing No. E 10080, Sheets 1 through 4, i

q Rev. 21, as modified by Nuclear Assurance Corporation letter dated l July 24,1986.

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i l 8608140626 860730 i

l PDR ADOCK 07109183 C PDR l

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'"pm NA CONDmONS(continued) U.S. fdUCLEAR REGULATORY CONm!SSION l

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Page 2 - Certificate No. 9183 - Revision Nc. 4 - Docket No. 71-9183 g I

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5 (b) Contents l

(1) Type and form of material l I

(i) Clad, irradiated metallic natural uranium fuel rods. I I

(if ) Solid nonfissile irradiated hardware.

l (2) Maximum quantity of material per package l l

The cavity content must not,3xc_eed a thermal decay heat load of 625 g I

watts and (or fuel a weight,o@rin basket uset the 'cTsk00l4bbit luding aiuttf to limit weight ofofcomponent movement contents spacers I during shipment limited as follows:

fuel rods are additi%

j (1) 21 in t rods or 10 encapsulated (defecjt ve) rods l

(ii) 1,60tFMWD/MTU average burn-up 4 I (iii) at least 730 days after,irrs8iation I coQa.' e'd cs j -

- i (c) FissileC15di j I I b Ks4 jM l heiicdelivered to,,,'a carrier for 6.

The cask transport.  % cavity W must A -4 be dryr(nd(free

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@gnter) y l

h0 9nt'espetesTpone A[ ,//

As needed,happrop'riathcom, I

7. %h basketfand antal spacers for I shipment of fue'T rods $msstAbei ds p j (th @l(k caitt;p? to 135f t movement of accide t-cruyditichst e l a rt . * '  %  ;

contents during % 0

8. n $ Wbe' drai The neutron shielWtanksimust S " dCand miditt'ained h)a dry condition in

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accordance with Section 7 of the appTicatic'n,'as/ supplemented. I Q, - W+ ~ ( '

In lieu of the requirements of 10 CFR 571.87(e), theld)censee must perform I

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periodic maintenance and testing of 0-rings, dra.in and vent ball valves, relief l i

valves, and rupture discs of the cask as indicated in the table given below. l 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 I of the package.

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l , U.S. MUCLEAR REGULATCRY COMMISSION [

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l Page 3 - Certificate No. 9183 - Revision No. 4 - Docket No. 71-9183 {

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I Cask Component

• Period Test / Action I

I Ball Valve Each shipment Hydro test to 30 psig*

Ball Valve Annually Replace seats and seals I l '

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0-rings Each shipment Test to 30 psig* f I 0-rings Annually Test to 100 psig*

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l Inner Containment Vessel Annually Test to 100 psig*

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l Cavity Relief Valve Annually Test at set point  !

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Cavity Rupture Disc Neutron Shield TankJ

, gh An a hhip R eplace

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l Rupture Disc Q Annually Replace f Impact Limit Annually gT to 5 psig*

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• There trust (be no visual'*(pressure gauge Nationso pressure drop i l for the com af 10Mnnte test Ppe(riod. Otherwi se, b y

corrective,ponent un'deg,, test dutfugsaction musLtgbe takerwand thes I j as the component meets 2the'speiMidd t'e I l  : I I or greaten,than thoseEi~ psi'catedJ ' a(Test f, to p{rissures equal tol )

I 10. Fabrication of additi , ac 9 i s nA t'liorl d ' i

11. The package authorized t ocerti her approvD for use under the I i general license poivisioni)6ft0U'CFif71d125*7 W

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l 12. Expiration date: September 30, 1989Q-@ -

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I vy[] REFERENCES D I l N_s ,x Df I '

Nuclear Assurance Corporation appTibation ~dateqlune 30,1984 l l Supplements dated: September 10, 1984; and July 24, 1986.

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l- FOR THE U.S. NUCLEAR REGULATORY COMMISSION l

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M Charles E. MacDonald, Chief I

I ll Transportation Certification Branch I lg

y Division of Fuel Cycle and l Material Safety, PNSS l lll l Il Date

AL 3 01986 I ll l

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-______________________________________________________  ; I

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neery y  %, UNITED STATES

- o NUCLEAR REGULATORY COMMISSION lr, j WASHINGTON, D. C. 20666 h,, ,o$

Transportation Certification Branch Aparoval Record Model io. NAC-1 Package Docket No. 71-9183 By application dated July 9,1986, as supplemented July 24, 1986, Nuclear Assurance Corporation proposes to attach auxiliary shielding to the Model No. NAC-1 cask in the form of a 1/4-inch thick copper plate within the neutron-shield tank at the time of manufacture. This auxiliary shielding will reduce the yxternal gamma k%f5 rates by at least 35%

(viz: (0.635 cm)(0.67 cm- ) = 0.425; e- = 0.65 ). Since the gama dose rate at 6 feet from the cask surface (for the metallic fuel rods) under normal conditions was estimated as 0.54 mrem /hr, loss of the copper shield would increase this dose rate to 0.729 mrem /hr. The applicant has estimated this dose rate conservatively to be 0.824 mrem /hr.

Since these estimates are well under the regulatory limit of 10 mrem /hr for normal conditions, the requirement of 10 CFR Part 71 will be met under both normal and accident conditions with or without the presence of the auxiliary shielding.

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Cha es E. Mac ona d, Chief '

Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date: R30W