ML20236F671

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Certificate of Compliance 6386,Rev 10,for Model 235R001. Approval Record Encl
ML20236F671
Person / Time
Site: 07106386
Issue date: 07/30/1987
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20236F656 List:
References
NUDOCS 8708030420
Download: ML20236F671 (5)


Text

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N2C FORD 61s U.S. NUCLEAR REGULATORY COMMISSION I 1 iso CERTIFICATE OF COMPLIANCE J l to CFR t' FOR RADIOACTIVE MATERIALS PACKAGES E 1 s CERTIFICATE NUMBER D REVISION NUMBER c PACKAGE IDEN11FlCATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES g 6386 10 USA /6386/B( )F 1 4 lg ,

2 PREAMBLE i a This Certif Cate is issued to Cer1Lfy that the packaging and Contents described m item 5 below, meets the apshcable safety standards set forth m Tetie 10, Code E

q of Federai seguiat,ans pari ri. "enciiaging and Transportation of naa oact,ve Material" E. <

4 e in,. Cert,viCate does not rei, eve tne cons,anor from Compiiance witn any requirement of the reouiat'ons o'ine u s oeoartment of Transportation or otner ,E:

$ appitcaele regulatory agencies. includmg the government of any Country through or into which the package will be transported k ,
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N J U.S. Department of Energy Safety Analysis Report for 235R001
il jE l1 Division of Naval Reactors Shipping Container dated August 11, 1970, E Washington, DC 20585 as supplemented.

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1 C oOCxETNuueER 71-6386 l

E 4 CONotTIONS This Certificate IS Condebonal upon fulfilling the requiremerits of 10 CFR Part 71, as applicable. and the Conditions specif#ed below L:

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j (a) Packaging

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's jg, (1) Model No.: 235R001 lK:

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M (2) Description F

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}j' The 235R001 shipping container structure is horizontal, having an oblong cross section and is fabricated from 0.104-inch thick carbon f i

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<j sheet steel. The container is 313 inches long and has a maximum J j weight of 4,640 pounds, empty. The oblong cross section dimensions 'E:

1 are approximately 35.5 inches high by 33.0 inches wide. The container E!

was originally designed to ship unirradiated fuel modules of the E!

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4 AlG/A4W type. Subsequently, the container has been adapted to ship AlW-3 fuel modules using a strongback, partial AlW-R3 fuel modules f

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d using module support assemblies, standard size or partial S8G fuel 'E:

Q modules by use of a special frame assembly and cradle clamps, S3G-3 El l 1 refueling modules using cell support assemblies, rodded or unrodded lE li y OlG fuel modules, rodded ASNPP fuel cells and rodded or unrodded D2W k j) f fuel cells. The loaded container maximum weight is 12,421 pounds. fj f4 (3) Drawings I: i lEgi h  !

q The packaging is constructed in accordance with Container Research l5;E Corporation Drawing Nos. 235R001, Rev. C, 235R004, Rev. C, and 235R005,1 !

Rev. O, and Westinghouse Electric Corporation Drawing Nos. 973D425, Rev.1, 903E693, Rev. 3, lheet 1, 2 and 3 of 3, and 947J076, Rev. O.

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0 8708030400 070730 5:

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' Page 2 - Certificate No. 6386 - Revision No.10 ) Docket No. 71-6386 l

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! (b) Contents l

E (1) Type and form of material l

Unirradiated fuel assemblies of the following type, l

l (i) AlG and A4W reactor cell without upper mechanism and with I control rod, leadscrew and shipping fixture installed on rodded I type modules.

(ii) A4W Reactor Test Assembly (RTA).

(iii) AlW-3 module without upper mechanism and with control rod, leadscrew, and control: rod holddown device installed on rodded type modulesh '

(iv) AlW-R3' Partial Lower Module.

? (v) Standard size S8G reactor cluster with. regular or substitute support adapters and regular control rods or Boral poison rods with control rod holddown devices installed. If only one cell is shipped per container, a dummy load shall be installed for balance.

l ly (vi) Partial size S8G reactor cluster with regular or substitute support adapters and regular contro! rods or Boral poison rods

! 4 with control rod holddown devices installed. If only one cell ,

is shipped per container, a dummy load shall be installed for N

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! balance.

l (vii) 53G-3 refueling' cells, with a. maximum of one 0-1 reactor cell y assembly per container.

M (viii) DlG fuel module, rodded.

M (ix) DlG removable fuel assembly (RFA), unrodded.

! (x) A1G fuel cluster, fueled end anly of full AlG reactor cell, l rodded.

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! (xi) ASNPP fuel cell with control rod, and control rod holddown l device installed.

l (xii) 02W side or central fuel cells with control rod and control rod i holddown device.

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[ (xiii) 02W corner fuel cells, unrodded.

j (xiv) STC fuel cells, unrodded.

l (2) Maximum quantity of material per package N

N (i) One fuel assembly as described in 5(b)(1)(1), 5(b)(1)(ii), f W

5(b)(1)(iii)or5(b)(1)(xi). j k, (

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I CONOlTIONS (continusd) l l Page 3 - Certificate No. 6386 - Revision No. 10 - Docket No. 71-6386 I  !

ii 1 l (2) Maximum quantity of material per package (Cont'd.) l l

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(ii) Two fuel assemblies as described in 5(b)(1)(iv), 5(b)(1)(v), lN 5(b)(1)(vi),5(b)(1)(vii),5(b)(1)(viii),5(b)(1)(x), 1 l

l i 5(b)(1)(xii),5(b)(1)(xiii),or5(b)(1)(xiv). j lN I

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(iii) Four fuel assemblies as described in 5(b)(1)(ix). .g in l (c) Fissile Class III I l Maximum number of packages per shipment: l 1 y 4 i (1) For the contents described in 5(b)(1)(iii)  ; j andlimitedin,5(b)(2)(1):

i 18 i i I l (2) For the contents described in 5(b)(1)(1)', 5(b)(1)(ii), 5(b)(1)(iv), R g 5(b(1(v),5(b)(1)(vi),5(b) vii),5(b)1)(viii),5(b)(1)(ix), l i 5(b (x),5(b)(1)(xi),5(b) xii), 5(b) 1)(xiii), and llg y 5(b (xiv), as limited in 5 2)(1),5(b(2)(11),and lp ,

i 5(b (iii): 4 !N l

! E Commingling of packages for Fissile Class III shipment is authorized provided

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lg that the sum of the ratios of the number of packages of an individual type to i

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g be shipped to the maximum allowable number of packages of that type per shipment I i does not exceed unity. p ,

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7. Expiration date: July 31, 1992. N N

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I CONolTIONS (continued)

Page 4 - Certificate No. 6386 - Revision No. 10 - Docket No. 71-6386 l

l l REFERENCES I

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

l l Supplements: Knolls Atomic Power Laboratory letter A1G 25-159, dated October 2, i 1970. Bettis Atomic Power Laboratory letters WAPD-0P(R)RD-444, dated October 9, 1970; i WAPD-0P(R)RD-476, dated October 26, 1970; and WAPD-0P(R)RD-480, dated October 30, i 1970. Knolls Atomic Power Laboratory letters A1G 25-181, dated April 9.1971; and i AlG 25-191, dated May 11, 1971. Bettis Atomic Power Laboratory letters WAPD-0P(R)C-

' ' 94, dated May 16, 1972; WAPD-0P(R)C-199, dated December 13, 1972; and WAPD-0P(R)C-l 229, dated March 6, 1973. Naval Reactors letters G#5078, dated January 26, 1976; i G#5776, dated September 8,1977; G#5905, dated January 23, 1978; G#5923, dated i February 22, 1978; G#6095, dated August"17.- 1978; G#6208, dated March 8, 1979; I G#6373, dated September 4, 1979; G#6813, dated October 17, 1980; and G#C85-0467, I dated July 17, 1985.

l FOR THE U.S. NUCLEAR REGULATORY COMMISSION 1

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Charles D acDoTmd, Chief l Transportation Branch-g g Division of Safeguards and y Transportation, NMSS at JUL 3019&

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[ -) , ,,g NUCLEAR REGULATORY COMMISSION g

,t WASHINGTON, O. C. 20555

%, T...../ l Transportation Branch Approval Record Model No. 235R001 Packaging Docket No. 71-6386 ,

Revision No. 10 l By application dated June 25, 1987 (G# 87-1684), Division of Naval Reactors, U.S. Department of Energy, requested renewal of Certificate of Compliance No. 6386. No changes have been authorized to the package design since i approval of latest supplemented dated July 17, 1985.

The certificate of compliance has been renewed for a five year term which expires July 31, 1992.

i i

M Charles E. MacDonald, Chief Transportation Branch l Division of Safeguards and '

Transportation, NMSS Date: M 30 W  !

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