ML20132G262

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Certificate of Compliance 6386,Rev 9,for Model 235R001. Approval Record Encl
ML20132G262
Person / Time
Site: 07106386
Issue date: 07/23/1985
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20132G254 List:
References
NUDOCS 8508020541
Download: ML20132G262 (5)
v • d • e


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_& a -= =- & ifANm sanseranammia2TaNTa7k"Ta7tarnismisrnanna fe CERTIFICATE OF COMPLIANCE lj tocrR" FOR RADIOACTIVE MATERIALS PACKAGES Ej f i a CERTIFICATE NUMBER b REVISION NUMBER c PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBE g

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6386 9

USA /6386/B( )F 1

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a. This certificate is issued to certily that the packaging and contents desCnbed in item 5 below, meets the applicable safety standards set forth in Title 10, Code l$[

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of Federal Regulatrons, Part 71.

  • Packaging of Radioactive Matenals for Transport and Transportation of Radioactive Matenal Under Certain Conditions."

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b. This certificate does not relieve the consegnor from compliance with any requirement of the regulations of the U S. Department of Transportation or other N

apphCable regulatory agenCles. including the government of any country through or into whlCh the package will be transported.

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  • '.7*e'EPAIES^ EYE *,.*S'!!"7.' "^*'* ' ^ **" ^"^"*'*n"'r7tE ANo'Io'EE'r*c^$8N $?"E,"OE"cSC^A fcATiON A

gll U.S. Department of Energy Safety Analysis Report for 235R001 gi l

Division of Naval Reactors Shipping Container dated August 11, 1970, g}

R; Washington, DC 20585 as supplemented.

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gj 71-6386 E

c oOcxErNuMeER 4 CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below N s.

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(a)

Packaging l

l (1) Model No.:

235R001 E

Hl-(2)

Description E

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The 235R001 shipping container structure is horizontal, having an l

gi oblong cross section and is fabricated from 0.104-inch tnick carbon g

gll sheet steel.

The container is 313 inches long and has a naximum g

N weight of 4,640 pounds, empty.

The oblong cross section dimensions E

N; are approximately 35.5 inches high by 33.0 inches wide. The container E

d was originally designed to ship unirradiated fuel modules-of the E

[i A1G/A4W type.

Subsequently, the container has been adapted to ship l

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A1W-3 fuel modules using a strongback, partial AlW-R3 fuel modules g

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using module support assemblies, standard size or partial S8G fuel g

Nj modules by use of a special frame assembly and cradle clamps, S3G-3 E

i refueling modules using cell support assemblies, rodded or unrodded E

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l DlG fuel modules, rodded ASNPP fuel cells and rodded or unrodded D2W E

i fuel cells. The loaded container maximum weight is 12,421 pounds.

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(3) Drawings E

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The packaging is constructed in accordance with Container Research E'

Corporation Drawing Nos. 235R001, Rev. C, 235R004, Rev. C, and 235R005, l

Rev. O, and Westinghouse Electric Corporation Drawing Nos. 973D425, y

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Rev.1, 903E693, Rev. 3, Sheet 1, 2 and 3 of 3, and 947J076, Rev. O.

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d 8500020541 850723 ifj PDR ADOCK 07106386 E(j l

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ccnosisons (continu:d>

Page 2 - Certificate No. 6386 - Revision No. 9 - Docket No. 71-6386 d

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I (b) Contents I

l (1) Type and form of material N

q Unirradiated fuel assemblies of the following type, I

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N (i) A1G and A4W reactor cell without upper mechanism and with l

control rod, leadscrew and shipping fixture installed on rodded g

type modules.

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s (ii) A4W Reactor Test Assembly (RTA).

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8 (iii) AlW-3 module -without upperumechanism and with control rod, leadscrew,

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I and control ' rod holddown device' installed on rodded type modules.

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f (iv) AlW-Rs Pa tial Lower Module.

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  • l (v) Standard size S8G reactor cluster with regular or substitute 1

support adapters and regular control rods or.Boral poison rods j

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with controlirod holddown devicessinstalled.' If only one cell is j

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installed for balance, i

l shipped pe(container, a dummy'lohd shall be ;i gl r.

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(vi) cPartial size S8G reactor cluster with regular;or substitute N

~ support adapters 'and < regular._ c'ontrol rods or Boral poison rods 3

[with co'ntrol; rod holddown devices installed. [If only one cell is (i

(shipped per container,la~dugy. load shall be installed for balance.

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g (vii) S3G-3 refuel.ing cells, j O y p!with'a maximum of oneIO-1 reactor cell l

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yl assembly ~per; container.W. s. sD,'y (q

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,; x 3

(viii) DlG fuel module',' ro'dded.' $

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"A W R-y (ix)

DlG removable fuel ass'embly (RFA), unrodded.

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(x) AlG fuel cluster, fueled end. only ~of full A1G reactor cell,

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rodded.

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l (xi) ASNPP fuel cell with control rod, and control rod holddown device I

installed.

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(xii) D2W side or central fuel cells with control rod and control rod A

holddown device.

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(xiii) D2W corner fuel cells, unrodded.

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(xiv) STC fuel cells, unrodded.

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l B-(2) Maximum quantity of material per package u

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l (1) One fuel assembly as described in 5(b)(1)(1), 5(b)(1)(ii),

l lj 5(b)(1)(iii)or5(b)(1)(xi).

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4'l I--_mm

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p----------------------------------mm----mmuc--m-mmww-6 o

1 w *: w u n a t' CcNDITIONS (contanutd)

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Page 3 - Certificate No. 6386 - Revision No. 9 - Docket No. 71-6386 1!

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(2) Maximum quantity of material per package (Cont'd.)

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(ii)

Two fuel assemblies as described in 5(b)(1)(iv), 5(b)(1)(v),

ll 5(b)(1)(vi), 5(b)(1)(vii), 5(b)(1)(viii), 5(b)(1)(x),

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N 1j 5(b)(1)(xii),5(b)(1)(xiii),or5(b)(1)(xiv).

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(iii)

Four fuel assemblies as described in 5(b)(1)(ix).

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(c) Fissile Class III g

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Maximum number of packages. m.. per shipment: g j

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For the contents ' described in 5(b)(1)(iii)1 a

and limitedsin 5(b)(2)(i):

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18 s.

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1 (2)

For the#contentsdescribedin5(b)(1)(1),5(b)(1)(ii),5(b)(1)(iv),

1 5(b)(1 (v), 5(b)(1)(vi), 5(b)(1)(vii), 5(b)(1)(vi11), 5(b)(1)(ix),

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5(b)(1 (x), 5(b)(1)(xi), 5(b)(1)(xii),-.5(b)(1)(xiii), and j

j 5(b)(1 (xiv), as' limited in 5(b)(2)(1), 5(b)(2)(ii.), and l,

j 5(b)(2)(iii):

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1 Commingling of packages fo'r Fissile, Class {LIII. shipment is authorized provided ct 1

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that the sum of the ratios ~of,the ' number of packages.of.an individual type to be N

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shipped to the;inaximum" allowable:n' umber of ' packages of that type per shipment l

j does not exceed ijnity. F a., ~ %.

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Expiration date:[ January 31,719.88. 2 t u R'd M, C-p i ~. % (J.

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CONDITIONS (continued)

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N Page 4 - Certificate No. 6386 - Revision No. 9 - Docket No. 71-6386 l

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REFERENCES l

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Safety Analysis Report for 235R001 Shipping Container, WAPD-0P(R)RD-357 dated August 11, 1970.

Supplements:

Knolls Atonic Power Laboratory letter A1G 25-159, dated October 2, q!

1970. Bettis Atomic Power Laboratory letters WAPD-0P(R)RD-444, dated October 9,1970; H:

WAPD-0P(R)RD-476, dated October 26, 1970; and WAPD-0P(R)R0-488, dated October 30, Hl 1970.

Knolls Atomic Power Laboratory letters A1G 25-181, dated April 9.1971; and l

N; A1G 25-191, dated May 11, 1971. Bettis Atomic Power Laboratory letters WAPD-0P(R)C-l f

94, dated May 16,1972; WAPD-0P(R)0-199, dated December 13, 1972; and WAPD-0P(R)C-gl 229, date't March 6, 1973.

Naval Reactors letters G#5078, dated January 26, 1976; g!

G#5776, dated September 8,1977;tG#5905,' dated January 23, 1978; G#5923, dated N!

February 22,1978; G#6095, dated August 17, 1978; G#6208.-dated March 8, 1979; l

H G#6373, dated September 4,1979; G#6813, dated October 17, 1980; and G#C85-0467, f:

dated July 17, 1985.

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fl FOR THE U.S. NUCLEAR REGULATORY COMMISSION i

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Ni Charle's E.\\ MacDonald, Chief '

-Tran'sportation, Certification Branch

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_ Division' of Fuel Cycle and

Material Safety, NMSS ME

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Dated:

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KfC UNITED STATES E

i NUCLEAR REGULATORY COMMISSION ej WASHINGTON, D. C. 20555

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Transportation Certification Branch Approval Record Model No. 235R001 Packaging Docket No. 71-6386 By application dated July 17, 1985, U.S. Department of Energy requested that the certificate be amended to include the addition of STC fuel as s authorized contents.

Because the fuel is less reactive than some previously approved fuel, the certificate has been amended to include the additional requested contents.

VCharles E. MacDonald, Chief Transportation Certification Branch i

Division of Fuel Cycle and Material Safety, NMSS JUL 2 31985 Date:

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