ML20042F461
| ML20042F461 | |
| Person / Time | |
|---|---|
| Site: | 07109183 |
| Issue date: | 05/04/1990 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20042F460 | List: |
| References | |
| NUDOCS 9005080348 | |
| Download: ML20042F461 (6) | |
Text
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l I ET" CERTIFICATE CF COMPUANCE u.s wucian neoumony consi
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i w ora ri FOR RADIOACTIVE MATERIALS PACKACES l
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- I 9183 10 USA /9183/Bf IF.
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cortefecate to tesad to certify tiat the packagmg and contents osecribed in item 6 below.rneets the applicable sefety stenaards i
oi reos,.i Reguntions, Part 71, sche 91ng and Transportation of Ra6Dective Ideter6al"
- b. vt s certificew ooos not reheve this cons +9nor from compheace with ear mu"'**" th"eguntens of the U.S. Department of Transpor i
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.poheebio regumiory eg.ncies,inaiuoing tne povemment of any country through or into which the package will be transported.
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Nuclear Assurance Corporation Nuclear Assurance Corporation application dated g;
l 6251 Crooked Creek Road May 26, 1989, as supplemented.
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I Norcross, GA 30092
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s Arv e mda" 71'-9183-
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' Cc'Ew u condmon.i upon sumino tie Nirements of 10 CFR Part 71, as appucebw, and the conditions necMed below,
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(a) Packaging T
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I (1) Model No.:
NAC-l' 3
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j (2) Descript. ion
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A steel and lead shielded shippingLcask. The cask is a right circular l,
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cylinder with-upper and lower steel encased balsa impact limiters. The g
i overall dimensions are 214lini:hesiin' length and 50 inches in diameter.
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The gross weight of-the' cask is approximately 49,000 pourids. The inner y
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cavity is 178 inches long'and 13.5 inches in diameter. The thickness of l
l the inner,shell is 5/16 inch'and 1-1/4 inches for the outer shell. The 11 I
two stainless steel shells are. welded'to~a 2-inch' thick stainless steel I
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l shield disc it'the bottom. The annulus between the inner and outer I
shells is filled with lead (max. lead thickness 6-5/8 inches, minimum 5 j
l inches),
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The stainless steel lid'is a frustum of a cone 7.5 inches thick. The lid is I
I secured to the cavity flange by six, ASTM-A320, Grade L43, 1-1/4-inch i
I diameter bolts. The seal is provided by two polytetrafluoroethylene l
l 0-rings.
Four trunnions, two located on either side of the upper or l
l lower impact limiter, are provided. Other cask features incl &iA two I
drain valves located in the bottom shield disc, vent valve, head closure l
l gasket leak check valve, and rupture disc - pressure relief valve synem located in the cavity flange.
For transport, the cask may be enclosed i
I in an expanded metal cage or closed shipping container.
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(3) Drawings I
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The Model No. NAC-1 shipping cask is constructed in accordt.nce with' i
Nuclear Fuel Services, Inc., Drawing No. E 10080, Sheets 1 through 4, I
Rev. 22.
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Pa'ge 2 - Certificate No. 9183 - Revision No. 10 - Docket No. 71-9183 l
l 5.
(b) Contents
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I (1) Type and form of material l
l (i) Clad, irradiated metallic natural uranium fuel rods.
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(ii) Solid nonfissile irradiated hardware, i
I (2) Maximum quantity of material per package I
I The cavity content pshobex
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e ne decay heat load of 750 I
watts and a weight of 3,700 lbs includirig ght of component spacers l
during shipnientf)ds'ed in the cask cavity tFuelrodsareadditionallylimjtedasfo 1
(or fuel baskel limit,, movement of contents (1) 21ibt trodsor6 encapsulated (defective) s..
Each defective rod 3i11-be encapsulated in either a 2.75-inch'hD failed fuel rod I
Rev. 9, oF91T.00; inch I.D. failed,fueP Bd can, rah.ing No.
c6n') as 'shoWhon Nuclear Assurance Corpo' ration D 340-108-D2,
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INuclearAssuranceCorporatjonDrawing>No(.
as shown on i
340-108-01*. Rev. 9.
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<ct.ns will be;be} shipped ih alsix\\rhdl capacity line\\ failed fuel rod Defe:tive rodsiencapsulated'i'n the L753 inch I. D.
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491-001.tJasshownon
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l Nuclear Assurance Corporation',_Draking No.
..Rev. O, and i
hdeft ctive rods' encapsulated inithe14.00-inch J.D. failed fuel rod m
i ecann will;be shippedgip;arthreec d Japac'ityklinert as shown on ro 4
Assurance Corporation 1 Drawing NoE347-211fF19, Rev. 5.
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'Nuc' lear W U! 3 y[bu[r[n u[p{g jg 4
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m 1,600 MWD /MTU avera b
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Mirimum 365cday & ge DM dh g h.h (Q
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i (c) Fissile Class #/
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- 6.
The cask cavity must be# r#dy(nofreewater)whendeliveIedtracarrierfor I
transport.
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As needed, appropriate component spaceri (fue'1' basket and axial spacers for i
shipment of fuel rods) must be used in the cask cavity to limit movement of I
contents during accident conditions of transport.
I i 8.
The cask may be shipped in t. closed shipping container provided that the closed l
container, the cask tie-down and support system and the transport vehicle (trailer)
- i. i meet the applicable requirements of the Department of Transportation. Tie-down I
devices which are a structural part of the package must comply with 10 CFR 971.45.
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I 9.
When the cask is shipped in a closed shipping container, the center of l
I gravity of the combined cask, closed shipping container and trailer must i
l not exceed 75 inches.
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i 10. When the cask is shipped in a closed shipping container, the internal heat I
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I load must not exceed 750 watts.
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l l Page 3 - Certificate No. 9183 - Revision No. 10 - Docket No. 71-9183 l
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I 11. In lieu of the requirements of 10 CFR $71.87(e), the licensee must perform l
l periodic maintenance and testing of 0-rings, drain and vent ball valves, relief i
valves, and rupture discs of the cask as indicated in the table given below.
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During inactive periods, the maintenance and testing frequency may be disregarded l
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provided that the package is brought into full compliance prior to the next use of I
I the package.
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Cask Component Period Test / Action I
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l Ball Valve Each shipment 7 rHydro test to 30 psig*
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I Ball Valve AnnuaDy h It CRep' late seats and seals I
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l 0-rings th Ea'ch shipment Testto30$sig*
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0-rings Annually Test to 100*p,sig*
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Inner Containment Veisel Annually Testto100ps[g I
TestMat ethnt [/
l CavityReliefVa(6 Annually 2
l Of SW
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Cavity Rupture? Disc 1 Annually
. Replacer 2
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. 31 4y*;
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l Neutron Shield Tank 7$ I;
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I Rupture Disc,
Annually,;,_.O - ( Replace.- ?
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l ImpactLimiters)
A6nuallygpq! q Test _to75 psig*
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- Theremustbeno. visual'(pressuregauge)indicationsofpressuresdropforthe I
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I component under. test during a 10-minute test seriod. 0therwise;u corrective action I
must be taken and the test repeated until sucLtime as the component meets the l
l specified tests..(Test to pressures ' equal to.or greater than'those indicated.)
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i 12. The package shall be prepared for shipment land operated in~accordance with the i
i operating procedures in Chapter 7 of the application. A v I
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Each package must be maintained in accordance.with the maintenance program in l
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l Chapter 8 of the application.'
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i 14. The package authorized by this certificate is hereby approved for use undt.r the l
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l general license provisions of 10 CFR 671.12.
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I 15. Expiration date:
September 30, 1994.
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I Page 4 -_ Certificate No. 9183 - Revision No. 10 Docket No. 71-9183 1
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l REERENCES
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I l Nuclear Assurance Corporation application dated May 26, 1989.
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j Supplements dated January 29.and March 20, 1990.
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l FOR THE U.S. NUCLEAR REGULATORY COMMI'SSION l
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Charles E. Mac en
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Transportation, NMSS Q I
MAY 0 41930
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UNITED STATES 1
g NUCLEAR REGULATORY COMMISSION 5*
E WASHINGTON, D. C. 20555
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APPROVAL RECORD Model No. NAC-1 Certificate of Compliance No. 9183' Revision No. 10 l
By application dated January 29, 1990, as supplemented March 20, 1990, Nuclear Assurance Corporation requested an amendment to Certifict.te of Compliance No. 9183
'for the Model No. NAC-1 package. The amendment was requested to reduce the number of failed fuel rods which may be shipped in a cask from ten failed rods'to six or less failed rods. The failed fuel rods will be shipped.in small diameter failed fuel canisters placed in a six rod capacity basket or in large diameter failed fuel canisters placed in a three rod capacity basket.
The application included a structural evaluation of. the new cask baskets and the new fuel containers. The evaluation was based on 30-foot drop g-loads which were previously determined for the cask (i.e. 96 g side dro) and 76.6 g bottom drop).
The fuel containers were evaluated for bending and buc(ling of the shells.
The baskets were evaluated to show that no permanent deformation would occur. The maximum normal operating temperature of the failted fuel containers and the basket was calculated to be 211 'F.
The structural evaluation was based upon material properties.at 250 *F.
The results of the evaluation showed that the stresses in the container and the basket are lower than thr; yield stress.
The staff concludes that the design of the fuel container and basket are adequate.
The reduction in contents will not affect the ability of the package to remain subcritical. The uranium fuel is naturally rsnriched and cannot be made critical with, or without, light water moderation. Also, dose rates outside the package will be lower than those for the previously approved payload of 21 intact rods, i
The application included a revision of the operating procedures for the NAC-1 package.
Procedures for loading sound intact) and failed fuel rods were provided j
in the application. These included loa ing procedures for the cask, the small diameter (2.75 inches I.D.) failed fuel canisters and the large diameter (4.00 inches I.D.) failed fuel canisters. The NRC staff reviewed the revised operating procedures and found them adequate.
The changes do not affect the ability of the package to meet the requirements of 10 CFR Part 71.
dv Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and Transportation, NMSS
-Date:
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l LIST OF USERS FOR CERTIFICATE - 9183 FOR MODEL - NAC-1.
CHEM-NUCLEAR SYSTEMS. INC.
ATTN: MS. SUSAN KINTNER 220 STONERIDGE DRIVE COLUMBIA SC 29210
. DEPARTMENT OF ENERGY ATTN: MR. JAMES F. LEONARD DP-4 WASHINGTON DC 20545 DUKE POWER COMPANY ATT13: MR. W.
B.
TUCKER 422 SOUTH CHURCH STREET CHA%LOTTE NC 28242 GPU NUCLEAR CORPORATION
' ATTN; MR. THOMAS SNIDER P.O.
BOX 388 FORKED RIVER NJ 08731 NORTHEAST NUCLEAR ENERGY CO.
ATTN: MR.
E.
J. MROCZKA P.
O.-BOX 270 HARTFORD CT 06141 NUCLEAR ASSURANCE CORPORATION ATTN: DR. ALAN H. WELLS 6251 CROOKED CREEK ROAD NORCROSS GA 30092 I'
1 PAGE 1 04/,24/1990 10:40:55 4
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