ML20245K276

Certificate of Compliance 9183,Rev 9,for Model NAC-1

ML20245K276
Person / Time
Site:	07109183
Issue date:	06/23/1989
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20245K248	List: ML20245K244 ML20245K276
References
NUDOCS 8907050080
Download: ML20245K276 (5)

Text

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w.C M m u.s. NUCLEAR CEGULATORY COMM'SSION CERTIFICATE OF COMPLIANCE

• aM io Crn n FOR RADIOACTIVE MATERIALS PACKAGES 1.c.CEH1f}gjE NUMBER b

IS80N NUMBER

c. P MBER d PAGE t4 UMBER

e. TOTAL NUMBER PAGES 2 MtEAMBLE

a. This certrfecate as issued to certify that the packaging and contents described in item 5 below, meets the applicable safety standards set forth in Title 10, Code of Federal Regulations Part 71," Packaging and Transportation of Radioactrue Material."

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 apphcable regulatory agencies, including the government of any country through or into which the package will be transported.

3 THIS CER I IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS R T OF M E DES GN OR CA ON I

I Nuclear Assurance Corporation Nuclear Assurance Corporation application dated l 6251 Crooked Creek Road May 26, 1989.

Norcross, GA 30091 OF-[s.,-9183 1

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4. CONDITIONS Sk

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I This certificate is conditional upon futfelhng the requirements of 10 CFR Part 7t, as appicable, and the conditions specrfied below.

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I 0-(a) Packaging I

(1) Model[)lo.: 5hAC-1

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(2) Des [ri ion N

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A steel and lead shielded shipping cask.' The cask is Oright circular I

cylinder with upper and lower steel encased balsa impa'ct. limiters. The 1

I overall dimensions are 214' inches ~in length and 50 inches in diameter.

l The gross weight off the' cask is approximately.49e000 pounds. The inner r

cavity is 178' inches 41ong iand 13.5' inches in ' diameter.1 The thickness of i

the inner sh' ll is 5/16Srichland.121/4 inches for the; outer shell. The e

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two stainless steel shells are' welded to a 2-inch thick stainless steel shield disc at thelbottomN(-Th'e: annulus-6etween thefinner i

I shellsMs filled with lead; max. lead thickness 6-5/8 inches, minimum 5 I

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inches)."/g

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E The stainless;. steel lid is ('fr'ustum of a cone & nches thick.

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9.5 i The lid is i

I secured to the) cavity flange by six, ASTM-A320; Grade L.'3, 1-1/4-inch I

diameter bolts.

The' seal is provided by two polytetrafluoroethylene 1

0-rings.

Four trun'nionsMwotlocated tn mither side of the upper or l

lower impact limiter, are-provided ? Other cask features include two drain valves located in the bottom shield disc, vent valve, head closure i

i gasket leak check valve, and rupture disc - pressure relief valve system I

located in the cavity flange. For transport, the cask may be er. closed I

in an expanded metal cage or closed shipping container.

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(3) Drawings I

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

Nuclear Fuel Services, Inc., Drawing No. E 10080, Sheets I through 4, I

Rev. 22.

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8907050080 890623 PDR ADOCK 07109183 I

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conomous toontinued)

Page 2 - Certificate No. 9183 - Revision No. 9 - Docket No. 71-9183

5..

(b) Contents (1) Type and form of material (1) Clad, irradiated metallic natural uranium fuel rods.

(ii) Solid nonfissile irradiated hardware.

(2) Maximum quantity of material per package The cavity contentsnushnk ex ed a thermal decay heat load of 750 watts and a weight hf '3,700 lbs incliiding* weight of component spacers (or fuel basket) \\ sed in the cask cavity tHiniit movement of contents during shipsent: Fuel rods are additionally limited as follows:

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'q (i) 21 intact rods or 10 encapsulated (defective) tods (ii) 1.,600 MWD /MTV average burn-up

... e QJ (iii) $ Minimum'Sp5'daycoolingtimeafterirradiation 4 FissileC:lasls k' ki

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5 Thecaskcavityrmustbedr[JO($offr'ee wafe'r)fwhEn Melisered to t~.

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As needed, appropriate component spacers.(tuel basket and axial spacers. foi shipment of fuel rods)7must be usedjin. the} cask cavity to limit movement of contents during, accident. conditions ofLtransport.

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The cask may be $ hipped ~ir I[c16sidIhihp'ind co5taineY provided<that the closed container, the casketie-down and support system and the transport vehicle (trailer) meet the applicable' requirements of the' Department of Transportation. Tie-down devices which are a# structural part'ofuthe. package must com l ith 10 CFR 71.45.

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When the cask is shippedjn a closed shipping containef,'3)p y w t.<..,

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the center of gravityofthecombinedcask,ys~losedshippingcontainerandtrailermust c

not exceed 75 inches Y

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10. When the cask is shipped in a closed shipping container, the internal heat load must not exceed 750 watts.

11.

In lieu of the requirements of 10 CFR 571.87(e), the licensee must perform periodic maintenance and testing of 0-rings, drain and vent ball valves, relief valves, and rupture discs of the cask as indicated in the table given below.

During inactive periods, the maintenance and testing frequency may be disregarded provided that the package is brought into full compliance prior to the next use of the package.

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l Page 3 - Certificate No. 9183 - Revision No. 9 - Docket No. 71-9183 I

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Cask Component Period Test / Action l

i Ball Valve Each shipment Hydro test to 30 psig*

I Ball Valve Annually Replace seats and seals i

I 0-rings Each shipment Test to 30 psig*

l 0-rings Annually Test to 100 psig*

Inner Containment Vessel Annually Test to 100 psig*

l Cavity Relief Valve Annually T st/at set point l

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Cavity Rupture Disc hAnnually Replace (4/1

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Neutron Shield Tank J Q

l Rupture Disc

'Q Annually Replace

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ImpactLimiters(9

' Annually Testto;5psif*

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• There must be no visual (pressure gauge)-indications of pressure' drop for the I

component under' test during a;10-minute; test period. -Otherwise,' corrective action l

must be taken an'd the test repeated until such time.as the component meets the I

specified tests.' (Test to p,ressures. equal.to or greater than those indicated.)

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12. The package shall be prepared for shipment'and operated"in accordance with the i

operating procedures in Chapter 7 of the application.

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13. Each package must be maintained.in accordance with the maintenance program in l

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h Chapter 8 of the application' y

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l 14 The package authorized by this certificate is hereby approved for use under the I

N general license provisions of 10 CFR 671.'12.

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15. Expiration date:

September 30, 1994.

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'RhFERENCES['

I Nuclear Assurance Corporation application dated May 26, 1989.

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FOR THE U.S. NUCLEAR REGULATORY COMMISSION l

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Charles E. MacDonald, Chief l

Transportation Branch i

Division of Safeguards and l

JUN 2 3 1989 Transportation, NMSS l

Date:

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UNITED STATES l

NUCLEAR REGULATORY COMMISSION

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,j WASHINGTON, D. C. 20555 e

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Transportation Branch i

Approval Record Hodel No. NACU Docket No. 71-9183 Revision No. 9 i

Revision No. 9 is being issued to correct the expiration date for Certificate of Compliance No. 9183. The correct expiration date is September 30, 1994.

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%.ANAaAl Charles E. MacDonald, Chief Transportation Branch i

Division of Safeguards JUN 2 3 ;ggg and Transportation, NMSS Date:

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