ML20132G262
| 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) | |
Text
p_---- _& a -= =- & ifANm sanseranammia2TaNTa7k"Ta7tarnismisrnanna fe CERTIFICATE OF COMPLIANCE lj tocrR" FOR RADIOACTIVE MATERIALS PACKAGES Ej b REVISION NUMBER c PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER f i a CERTIFICATE NUMBER g: 6386 9 USA /6386/B( )F 1 e TOTAL 4NUMBE gj ll 2 rREAustE Ej lf 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] of Federal Regulatrons, Part 71.
- Packaging of Radioactive Matenals for Transport and Transportation of Radioactive Matenal Under Certain Conditions." l$
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k 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 A fcATiON U.S. Department of Energy Safety Analysis Report for 235R001 gi gll l Division of Naval Reactors Shipping Container dated August 11, 1970, g}
R; Washington, DC 20585 as supplemented. In il E N' E gj c oOcxErNuMeER 71-6386 E 4 CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below N s. E i i f (a) Packaging l
(1) Model No.: 235R001 l E
Hl-l (2) Description E N l The 235R001 shipping container structure is horizontal, having an f
gi oblong cross section and is fabricated from 0.104-inch tnick carbon l g
sheet steel . The container is 313 inches long and has a naximum g gll 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
[ig! A1G/A4W type. Subsequently, the container has been adapted to ship l A1W-3 fuel modules using a strongback, partial AlW-R3 fuel modules g q! 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
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refueling modules using cell support assemblies, rodded or unrodded E l i DlG fuel modules, rodded ASNPP fuel cells and rodded or unrodded D2W E f
u-fuel cells. The loaded container maximum weight is 12,421 pounds. l t
g: (3) Drawings E i; El N The packaging is constructed in accordance with Container Research E' ll g
Corporation Drawing Nos. 235R001, Rev. C, 235R004, Rev. C, and 235R005, Rev. O, and Westinghouse Electric Corporation Drawing Nos. 973D425, ly y Rev.1, 903E693, Rev. 3, Sheet 1, 2 and 3 of 3, and 947J076, Rev. O. p I, E 1: Ei l' E E E Ni E ti R Nl 10 El Il 4 El Nl d
fj i 8500020541 850723 PDR ADOCK 07106386 El1 E
l R C PDR E(j I!.-------------------------------------------------------m) E
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l ccnosisons (continu:d>
I i Page 2 - Certificate No. 6386 - Revision No. 9 - Docket No. 71-6386 d I, p
- q. p I t l '
I (b) Contents I
l (1) Type and form of material N
q Unirradiated fuel assemblies of the following type, ,
I i N (i) A1G and A4W reactor cell without upper mechanism and with control rod, leadscrew and shipping fixture installed on rodded j/
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type modules. [p s (ii) A4W Reactor Test Assembly (RTA).
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8 (iii) AlW-3 module -without upperumechanism and with control rod, leadscrew, ?
I li and control ' rod holddown device' installed on rodded type modules.
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Ni (iv) AlW-Rs Pa tial Lower Module.
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N (v) Standard size S8G reactor cluster with regular or substitute 1
- l support adapters and regular control rods or.Boral poison rods j with controlirod holddown devicessinstalled.' If only one cell is j l! ~
installed for balance, i gl g
l shipped pe(container,
- r. i :, a ) 3:' a ) dummy'lohd
( J- a shall be ;i i l' (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 (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
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q yl assembly ~per; container.W. s. sD,'y
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3 (viii) DlG fuel module',' ro'dded.' $ #, s -
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removable fuel "A W ass'embly (RFA),
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R-unrodded.
y (ix) g '/ .
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q (x) AlG fuel cluster, fueled end. only ~of full A1G reactor cell, !
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'i rodded. '( ( b j
(xi) ASNPP fuel cell with control rod, and control rod holddown device I l installed. j gl 1 I q (xii) D2W side or central fuel cells with control rod and control rod !
A holddown device. l 8 .i (xiii) D2W corner fuel cells, unrodded. q (r s g! (xiv) STC fuel cells, unrodded. j E
(2) Maximum quantity of material per package :l B- u i :l (1) One fuel assembly as described in 5(b)(1)(1), 5(b)(1)(ii), l lj g 5(b)(1)(iii)or5(b)(1)(xi). -
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o p----------------------------------mm----mmuc--m-mmww- 6 1
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CcNDITIONS (contanutd)
J h Page 3 - Certificate No. 6386 - Revision No. 9 - Docket No. 71-6386 1! N P g J N j (2) Maximum quantity of material per package (Cont'd.)
[
] pl 1 E 1! (ii) Two fuel assemblies as described in 5(b)(1)(iv), 5(b)(1)(v),
1 5(b)(1)(vi), 5(b)(1)(vii), 5(b)(1)(viii), 5(b)(1)(x), lpN ll1j 5(b)(1)(xii),5(b)(1)(xiii),or5(b)(1)(xiv). 'N E
E f'l (iii) Four fuel assemblies as described in 5(b)(1)(ix). l h
1 (c) Fissile Class III g 1
nrm W j Maximum number of packages. m.. per shipment: g j ,\\- i .
jl (1) For the contents ' described in 5(b)(1)(iii)1 ,
a and limitedsin 5(b)(2)(i):
/,, 18 1l' 1 (2) s.
For the#contentsdescribedin5(b)(1)(1),5(b)(1)(ii),5(b)(1)(iv),
s .-
1 5(b)(1 (v), 5(b)(1)(vi), 5(b)(1)(vii), 5(b)(1)(vi11), 5(b)(1)(ix),
1 5(b)(1 (x), 5(b)(1)(xi), 5(b)(1)(xii),-.5(b)(1)(xiii), and j 5(b)(1 (xiv), as' limited in 5(b)(2)(1), 5(b)(2)(ii.), and i[l j
,l j 5(b)(2)(iii): { R ') y ') ( f_ , '1,. 4 g 1 ct >St/ / \ ,t . ;
Commingling of packages fo'r Fissile, Class {LIII . shipment is authorized provided L1 q 1 6. E 1 that the sum of the ratios ~of,the ' number of packages.of.an individual type to be N shipped to the;inaximum" allowable:n' umber of ' packages of that type per shipment
] does not exceed ijnity. F a ., ~ % . '
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- 7. Expiration date:[ January 31,719.88. 2 t u R'd M, C- p j ,
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m a mm 6Tm M CONDITIONS (continued)
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Page 4 - Certificate No. 6386 - Revision No. 9 - Docket No. 71-6386 Gi N'
REFERENCES l
l Safety Analysis Report for 235R001 Shipping Container, WAPD-0P(R)RD-357 dated August 11, 1970.
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Supplements: Knolls Atonic Power Laboratory letter A1G 25-159, dated October 2, 1970. Bettis Atomic Power Laboratory letters WAPD-0P(R)RD-444, dated October 9,1970; WAPD-0P(R)RD-476, dated October 26, 1970; and WAPD-0P(R)R0-488, dated October 30, H:
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 94, dated May 16,1972; WAPD-0P(R)0-199, dated December 13, 1972; and WAPD-0P(R)C-f 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, dated July 17, 1985. '*
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FOR THE U.S. NUCLEAR REGULATORY COMMISSION !
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Charle's E.\ MacDonald, Chief '
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. -Tran'sportation, Certification Branch
_ Division' of Fuel Cycle and
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, ; Material Safety, NMSS ME
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% UNITED STATES 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 i Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date: JUL 2 31985 l
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