ML20248B360

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Certificate of Compliance 9183,Rev 8,for Model NAC-1
ML20248B360
Person / Time
Site: 07109183
Issue date: 06/06/1989
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20248B358 List:
References
NUDOCS 8906090021
Download: ML20248B360 (8)
v • d • e


Text

..................-----........---.----.--------------s Ua NUCLEAR REIULATORY COtetAIS$10N k L E

CERTIFICATE OF CCMPLIANCE f(

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FOR RADf0 ACTIVE htATERIALS PACKAGES g.

c PME 3DFNTif 3GATION NUMBEH d PAGE I4 UMBER

e. TOTAL NUMBFA PAGES 1'a CE"YM$E Nugg

{ an HEYlSsON NUMBER 8

USA /9183/B()F 1

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certificate as assued to certsfy that the packaging and contents described in Itern 5 tesow, rnoets the apphcable safety standards set forth in Title 10. Code a.

l of poderal Regutstions. Part 71," Packaging afh? i 'ensportation of Radmactive Material."

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c. Thas certifscale does not eleve the consegnor trorn ccmphance with any requerernent of the regulations of the U.S. Department of Transportation or other I

appfacabb regulatory agencies. incbding the governrnent of any country through or into which the pack &ge will be transported.

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l Nuclear Assurance Corporation Nuclear Assurance Corporation application dated I

i 6251 Crooked Creek Road May 26, 1969.

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I ett to as condatonal upon futfittang ttie of 10 CrR Part 71, as apphcable nd the conditions specified th j

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(a) Packaging "q

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(2) Description

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MO A steel and lead shielded shipping c(ask.< The cask is 4 right circular

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cylinder with upper and lower 2 steel encased balsa in: pact limiters. The r

l overall dimensions are 214 inches in length and 50 inches in diameter.

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The gross weight of' the;caskiistapproximately' 49,000 pounds. The inner I

I cavity is 178 inches long Land 13.5(inches in diameterc The thickness of I

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the inner shell is"5/16; inch tand F1/4 inches for the outer shell. The I

two stainless steel shells are welded,to a 2-inch thick stainless steel

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l shield. disc at;the. bottom.7The. annuluCbetween thednner and outer

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j shellsisfilledwith.leadlnax..leadthickness6,5/8 inches, minimum 5 l

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inchsh j, Q

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The stainless-steel lid is a frustum of a cone' X 5 inches thick. The lid is t I

secured to the/cevity flange by six, ASTM-A320',' Grade L43, 1-1/4-inch

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diameter bolts. The seal is provided $y'~two polytetrafluoroethylene

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i 0-rings. Fourtrunnion).dwojecatedoneithersideoftheupperor

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lower impact limiter, are' prov'ided. Other cask features include two I

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drain valves located in the bottom shield disc, vent valve, head closure f!

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

l located in the cavity flange.

For transport, the cask may be enclosed

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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 accordance with I

l Nuclear Fuel Services, Inc., Drawing No. E 10080, Sheets 1 through 4,

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l Page 2 - Certificate No. 9183 - Revision No. 8 - Docket No. 71-9183 L

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(b) Contents l

l (1) Type and form of material 1

1 (1) Clad, irradiated metallic natural uranium fuel rods.

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(ii) Solid nonfissile irradiated hardware.

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(2) Maximum quantity of material per package shnhex8ebhefmn decay heat load of 750 The cavity content watts and a w f S,700 lbs includirkf ig t of component spacers I

(or fuel bask ed in the cask cavity t 9 4

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during shisney. Fuel rods are additionally lir% movement of cont gited as follows:

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(i 21 it act rods or 10 encapsulated (defective i

1 (11 1,600'HWD/NTU average burn-up J

coolingtimeafterirradiation 4 j

l (iii 40Mirafmum 165'd, N f7

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The cask cavityTinust be dry.-(no[ free water)(when ils]ivered to a carrier for transport.

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As needed, appropriat'e compon'ent' spacers (fuelcbispet and axial spacers for shipment of fuel rods). must be usedjirr the'casktavity to ifmit movement of t

contentsduring,4ccident~conditionsJofjtra4 sport.

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The cask may be shipped in'a"cinsed' shipping' container provided that the closed

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container,thecask-tie-downandsupport:systemandthetransportvehicle(trailer) meet the applicable requirements"of-the Department of Transportation. Tie-down devices which are a' structural part of(the. package must cmgly with 10 CFR 71.45.

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9.

When the cask is shippedein a closed shipping container',Mhe center of gravity of the combined cask,Tclosed shipping, container and trailer must not exceed 75 inches.

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) 10. When the cask is shipped in a closed shipping container, the internal heat i

1 load must not eiceed 750 watts, i

! 11.

In lieu of the requirements of 10 CFR 571.87(e), the licensee must perform i

j periodic maintenance and testing of 0-rings, e ain and vent ball valves, relief valves, and rupture discs of the cask as indicated in the table given below.

ij During insctive 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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i Page 3 - Certificate No. 9183 - Revision No. 8 - Docket No. 71-9183 I

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l Cask Component Period Test / Action-

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Ball Yalve Each shipment Hydro test to 30 psig*

I Ball.Yalve Annually Replace seats and seals I

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0-rings Each shipment Test to 30 psig*

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0-rings Annually-Test to 100 psig*

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i Inner Containment Vessel Annually Test to 100 psig*

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I Cavity Relief Valve Annuah. Oy a ' 1 LTest 4Q' et point

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Cavity Rupture Disc hAfinuelly Replace %

Neutron Shield Tanks Q

l Rupture Disc 9"

Annually Replace Impact Limiters h'

' Annually TesttoEkig

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'There must ce no visual (V W Npressure gaugehindicati[ons"/>

j' of pressure component unde'r" test during'a?10-minute) test period.?Dtherwise,(drop for the corrective action I

I must be taken rand the test repeated until such time?ts'the component meets the I

specified tests.

(Test to pressures..equallto_or Areater than those indicated.)

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q l 12. The package shall be prepared for sshipment7and'operiiled 'in accordan'ce with the q

operating procedures in Chapter'7 of:the application.n -, '

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e i 13. Each packege must be malntained inTaccordance with the maintenance program in 4

l Chapter 8 of the application. ; f ",, ;^ ('

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i j 14. The package authorized by this certif4cate is hereby approved for use under the l

l general license provisions of 10 CFR 571.124 a'

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i 15. Expiration date: September 30, 1989.

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l REFERENCES '

I t Nuclear Assurance Corporation application dated May 26, 1989.

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l FOR THE U.S. NUCLEAR REGULATORY COMMISSION I

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l Charles E. MacDonald, Chief l

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Division of Safeguards and l

Transportation, NMSS l

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1 seRC FORF91e U.S. NUCLEAR LEGUUWORY COMMISSION CERTIFICATE OF COMPLIANCE araw io cm n FOR RADIOACTIVE MATERIALS PACKAGES b MEVISION pAMBER C PACKAGE IDENTIFICATION eiUMBLR d PAGE TAMptR

. TOTAL NUMBEft PAGES l

5 a CEREE fRadHLR 8

USA /9183/B( )F 1

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a. This cert #fecate as issued to certify that the pac 6 Jag ng and contents described en hem 5 tetow. meets the applu.able safety standards yJt forth in T41e 10, Code M

ot I-ederal Angulations, Part 7t,

  • Packaging and Trarmportation of Radioactive Materal" I

tt Ths, certifacele does not relseve $he consegnor from Complance with any requirement of the regulations of the U.S, Department of Transpor laSon or other l

Jipphcable regulatory agencess. including the guvernment of ar'y country through or into which the package will be transp6rted i

1 3 TH: 0 4

it IS ISSUE D ON THE (SASiS OF A SAFETv ANALYSIS ME T

THE DE3 OR APf'L CA ON i, Nuclear Assurance Corporation Nuclear Assurance Corporation application dated i 6251 Crooked Creek Road May 26, 1989.

I Norcross, GA.30091 i

. m P O 71-9183 l

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I The certificate es condetsonal upon futfalling the rautarements of 10 CFR Part T1, as applecab6e. and the cond<tions specified telow.

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(a) Packaging

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'f (1) Model No.: 'NAC-1,

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(2) Desbr tion

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  • _a,: (n-g A steel and lead shielded shipping cask.- The cask is'a right circular cylinder with uoper and lower _ steel encased balsa impact limiters. The r

i overall dimensioris are 214 inches in lencth and 50 inches in diameter.

l The gross weight of the cask'isTapproximately 49,000 pounds. The inner I

cavity is 176 inches long fand 13.5 inches in diameterrThe thickness of I

the inner shell ii S/16 inch and F 1/4 inches for the' outer shell. The l

two stainless steci shells are welded to a 2-inch thick ctainless steel shield disc at the bottom.1(The. annulusibetwcen theiinner and outer y

y shells ~is. filled with lead (max. lead, thickness 6-5/8 inches, minimum 5 inches),/e W-W s-y 4

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The stainless-steel lid is a frustum of a cone 7f5 inches thick.

The lid is l

secured to thercavity flange by six, ASTM-A320, Grade L43, 1-1/4-inch i

diameter bolts. The seal is provided.liy',two polytetrafluoroethylene i

0-rings.

Four trunnion).>two located on either side of the upper or I

lower impact limiter, are'prdvided.~ Other cask features include two I

drain valves located in the bottom shield disc, vent valve, head closure I

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

located in the cavity flange.

For transport, the cask may be enclosed l

in an expanded metal cage or closed shipping container.

I I

I (3) Drawings i

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

Nuclear fuel Services, Inc., Drawing No. E 10080, Sheets 1 through 4, I

I Rev. 22.

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l Page 2 - Certificate No. 9183 - Revision No. 8 - Docket No.- 71-9183 5.

(b) Contents (1) Type and form of material 1

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

(ii) Solid nonfi.ssile irradiated hardware.

(2) Maximum quantity of material per package The cavity content shobex bhefma decay heat load of 750 watts and a w ' ht f 3,700 lbs includirh/ ightofcomponentspacers

.I (or fuel bask Mm R movement of contents during shipp.

Med in the cask cavity t t.

Fuel rods are additionally linpted as follows:

(i 21ih'iactrodsor10 encapsulated (defective s

(ii 1 /00 MWD /NTU average burn-up a:

j (iii Mitilmum '365'da cooling time after irradiation 4

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y (c) Fissile C, lass 9

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The cask cavity *iinust be dryT(

reewaffr)(when' del 1[eredtoacElrierfor 6.

transport.

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As needed, appropriate,?must be 'usedjinl the} cask cavity 7.

t an shipment of fuel rods) contents during, accident-conditions;off transport.

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.ng~fgcontainer provided 4 hat the closed 8.

The cask may be shipped Tn'a! closed",shi container, the cask tie-down and.supportesystem and the transport vehicle (trailer) l meet the applicable requirements ~of the~ Department of Transportation. Tie-down J

devices which are a' structural part of(the. package must comply with 10 CFR 71.45.

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When the cask is shipped An a closed shipping container,4he center of I

gravity of the combined cask,'wlosed shipping container and trailer must j

not exceed 75 inches.

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l 10. When the cask is shipped in a closed shipping container, the internal heat i

load must not exceed 750 watts.

I I 11.

In lieu of the requirements of 10 CFR 671.87(e), the licensee must perform l

l periodic maintenance and testing of 0-rings, drain and vent ball valves, relief j

i valves, and rupture discs of the cask as indicated in the table given below.

i 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 1

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the package.

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conomous (continued) l 6

1 Page 3 - Certificate No. 9183 - Revision No. 8 - Docket No. 71-9183 I

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Cask Component Period Test / Action I

Ball Valve Each shipment Hydro test to 30 psig*

I Ball Valve Annually Replace seats and seals l

l 0-rings Each shipment Test to 30 psig*

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0-rings Annually Test to 100 psig*

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1 Inner Containment Vessel Annually Test to 100 psig*

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Cavity Relief Valve Annuallyb Th et point

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Cavity Rupture Disc

,hAnnually Replace %s a

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Q) l Neutron Shield Tank s l

l Rupture Disc S-~~#

Annually Ceplace 3

Impact Limiters l.!)h

) Annually Test to Jj/sig'* 2 NMN f}i l

  • There must be n.o visual (pressure sgauge)~.indicationstof' pressure' drop for the I

component under test during~a10-minute) test' peridd.? :Otherwise,'porrective action l

must be taken'and the test repeated until such time?as?the component meets the specified tests; (Test to' pressures.. 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 operating procedures in Chapter 7jof the application.t l l!

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Each package must be maintained.inIaccohdanc'e$1th the' maintenance program in l

Chspter 8 of the. application. " ' ~ <

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14. The package authorized by this certificate is hereby approved for use t er the l

l general license provisions of 10 CFR E71.12.-

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15. Expiration date: Septeinber 30, 1989.

'REFERENCESd hi l

Nuclear Assurance Corporation application dated May 26, 1989.

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FOR THE U.S. NUCLEAR REGULATORY COMISSION j

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YnY Charles E. MacDonald, Chief l

l Transportation Branch Division of Safeguards and

.g Transportation, NMSS I

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UNITED STATES

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ej WASHINGTON, D. C. 20555 p,

NUCLEAR REGULATORY COMMISSION 5

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p Transportation Branch Approval Record Mode 1 ho. NAC-1 Docket No. 71-9183 Revision No. 8 By application dated March 28, 1989, NuclearAssuranceCorporation(NAC) requested renewal of Certificate of Compliance No. 9183 for the Model No. NAC-1 shipping package. No changes in the package design were requested.

NAC has submitted an updated Safety Analysis Report (SAR) dated May 26, 1989, which incorporates all revisions made to the SAR since the certificate was last renewed on October 1, 1984.

The certificate has been revised to include the operating procedures in Chapter 7 and the maintenance program in Chapter 8 of the May 26, 1989 application as conditions of the certificate.

l The certificate of compliance has been renewed for a five year term which expires on September 30, 1994.

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Charles E. M8cDonald, Chief Transportation Branch Division of Safeguards JUN 8 619g and Transportation, NMSS l

Date:

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