ML20044B899
| ML20044B899 | |
| Person / Time | |
|---|---|
| Site: | 07106003 |
| Issue date: | 03/03/1993 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20044B897 | List: |
| References | |
| NUDOCS 9303110360 | |
| Download: ML20044B899 (8) | |
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I U.S. NUCLEAR REGULATORY COMMISSION senc ronni ste CERTIFICATE OF COMPLIANCE I
I cm I
w CFR n FOR RADIOACTIVE MATERIALS PACKAGES I
1.a. CERTIFICATE NUMBER
- b. REVISION NUMBER t PACKAGE IDE.NilfICATION NUMBER d.PAGE NUMBER
- e. TOTAL NUMBER PAGES 6003 15 USA /6003/B( )F 1
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- 1. ' 2. PREAMBLE I
- a. This certificate is issued to certify that the packaging and contents described in item 5 below. meets the arwcable safety standaros set forth in Title 10. Code I
i of Federal Regulations, Part 71,"Packagmg and Trensportation of Radioactive Matenat" l
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- b. This certificate does not reheve *he consigner from comphance with any requirement of the regulations of the U.S. Department of Transportation or other l
l apphenbie reguistory agencies, inciuding ine government of any country through or into wnich tne package wiis be transported.
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- 3. THl3 CERTIFICATE LS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION a ISSUED TO theme sw Mersal
- b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION I
U.S. Department of Energy Safety Analysis Report for M-130 shipping l.
E Division of Naval Reactors container dated December 30, 1968, as I
l Washington, DC 20585 supplemented.
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' c. DOCm HUuBER 71-6003 1
I 4 CONDITIONS E
This certificate is conditional upon tuffilling the requirements of 10 CFR Part 71, as apphcable, and the coblastions specified below.
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(a)
Packaging l
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(1) Model No.: M-130 1
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J (2) Description'
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The Model No. M-130 shipping container is an upright cylinder 84 inches in g
i diameter by 158 inches overall height! The' container walls consist of a i
finned 1-inch thick outer shell, fabricated from either carbon steeT, carbon I
l steel withfstainless steel clid,7or solid stainless steel,10 inches of lead
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shielding, 'and a 1-inch'-thick; inner pressure. vessel fabricated from carbon g
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I steel clad with stainless steel..The top of the container is covered with a g
I shielded closure head which :is bolted.to the contain~er and seals the pressure l
l vessel. An access opening with a bolted shield plug'is provided in the i
E closure head for loading and unloading spent fuel.)
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The pressure vessel has'an inside diametereof 55 inches. The central region contains a secondary h' at exchanger-(not" used during shipment) surrounded by e
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1/2 inch thick carbon steel backup cylinder 29 inches in diameter. The I
N annules which remains between the backup cylinder and the pressu e vessel I
l provides a space 13 inches wide and 130 inches high for spent fuel. The spent l
fuel is contained in the annulus by module holders designed for the particular i
i core to be shipped.
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The container has external penetrations to the pressure vessel for steam and
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water relief lines and a fill and drain line (which are capped during I
l shipment) and a pressure sensing line which remains open to a pressure gage l
g during shipment. The container also has penetrations which do not open to the I
pressure vessel for secondary heat exchanger lines (which are capped during g
I shipment) and a temperature s'ensing line.
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9303110360 930303 I
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CONolTiONS (continued) g Page 2 - Certificate No. 6003 - Revision No. 15 - Docket No. 71-6003 f
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I 5.(a) Packaging (cont'd) g I
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(2) Description (cont'd) i I
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For LWBR spent fuel shipments, the heat exchanger and associated structures I
I have been removed, external penetrations plugged and seal welded, and an l
l external shield and energy absorber added during modifications, g
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The container is supported on its transport vehicle by an "A" frame structure.
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Gross weight of the loaded container without its support structure is I
i approximately 228,000 pourids.
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I (3) Drawings l:
l The packaging is construciedEin acco[ Nance, w,ith General Electric ci
[3 ?O g-l Rev. K; Sheet 3, Rev.
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Drawing Nos. 247E209', Sheet 1, Rev. R; Sheet (2,4 s
T; Sheet 4, Rev.,0; Sh'eet 5 of 5, Rev. F and 247E228, Rev. F.
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I For LWBR spentifuel shipments, the container has bien modified in accordance l
with Westinghouie Electric Drawing 1176J48, Sheet.1 Rev. G, Sheet 2 Rev. E and g
j an externalrenergy absorber added in accordance with Westinghouse Electric p
i Drawing 1525E32, Rev.:Acx f'
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(b) Contents
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f (1) Type and form of materialj au e
y Irradiateb ; fuel 5ssemblies,' activa'tAdlIcorrosion products :and structural parts 1
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containing up to 40 gallons'of iresidual contaminated water.
The fuel N
f assemblies and structural parts are of;the following types:
(i)
S3W'/S4W fuel' subassemblies of core type 2.
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(ii) 55W Iue'l: modules of cide thes 2 or 3. O I
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(iii)
S5W corneh fuel, modules of core types 2 or 3.
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(iv)
DIG fuel modules' off cors-typess 1 or 2.
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DIG removable fuel assemblies of core types 1 or 2.
1I, (vi) 51C/S2C fuel modules with control rods.
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SIC /S2C peripheral fuel modules.
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(viii}
S3G-3/3A fuel module with or without control rods.
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I (ix)
SAD cell.
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- gwwg;qqmE"A*G:"Jfriwwaarmw.anc.m<wwwnWW CONDITIONS (continued) i
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Page 3 - Certificate No. 6003 - Revision No. 15 - Docket No.
71-6003 i
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- 5. (b) Contents (cont'd)
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(1) Type and form of material (cont'd) i f
(x) S3G-3/3A irradiated thermocouples and thermocouple cases.
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(xi) S8G full size fuel cell with or without control rod.
(xii) 58G partial size fuel cell with or without control rod.
l (xiii) S5W-4A recoverable irradiated fuel modules with control d
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rod.
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(xiv) S7G recoverable irradiated fuel; cells.,
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d (xv) D2W fuel cells' wit'h' control rods.
I NR-1 fuel ' odules with or without control rods.
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4 (xvii) ATC fuel modules with or without control rods.
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(xviii) AlW-3' recoverable irradiated fuel modules.
Fuel modules that use control. rods shall' have control rods. inserted.
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4 (2) Maximum quantity o,f material.,per; package.
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l (i) 52 fuel assemblies"as described in 5'(b)(1)(i).
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g (ii) 12 fuel assemblies 'as described 'in 5(b)(1)(ii) or 9 fuel q
assemblies as-described in.5(b)(1)(ii) and 4 fuel assemblies j
as described in 5(b)(1)(iii).
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(iii) 6 fuel assemblies as described in' 5(b)(1)(iv) and f
4 fuel assemblies as described in 5(b)(1)(v),
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(iv) 9 fuel assemblies as described in 5(b)(1)(vi) and k
8 fuel assemblies as <iescribed in 5(b)(1)(vii).
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l (v) 10 fuel assemblies as described in 5(b)(1)(viii).
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(vi) 9 fuel assemblies as described in 5(b)(1)(viii) and j
one fuel assembly as described in 5(b)(1)(ix).
j (vii) 9 fuel assemblies as described in 5(b)(1)(viii) and one structure as described in 5(b)(1)(x).
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COHO lTlONS (contonved) ij l
ll l.Page 4 - Certificate No. 6003 - Revision No. 15 - Docket No. 71-6003 h
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- 5. (b) (2) Contents (cont'd) 1 l i I
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I (viii) 4 fuel cells as described in 5(b)(1)(xi); or l
2 fuel cells as described in 5(b)(1)(xi) and ll 2 fuel cells as described in 5(b)(1)(xii).
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l (ix) 6 fuel assemblies as described in 5(b)(1)(xiii).
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(x) 8 fuel cells as described in 5(b)(1)(xiv).
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l (xi) 4 fuel cells as described in 5(b)(1)(xv) plus h
q 2 corner fuel cells or 1 RFA fuel cell.
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(xii) 4 fuel modules as. described lin 3(b)(1)(xvi).
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(xiii) 10 fuel modules,is described in 5(b)(1)(Wii).
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(xiv) For contents > described in 5(b)(1)(xviii), 6 fuel modules, or I
I 8 fuel modules, as described in supplement dated March 30, 1992.
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(3)
Shipments shall be further limited by thermal; requirements as follows:
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(i) Shipment of contentst specified-in 5(b)(1)'(iv) and 5(b)(1)(v) and limited ll '
q in 5(b)(2)(iii) shall/ b'e made' no earl.ier than 75 days:
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I after shutdown and shall have a ' decay heat load not-to exceed 1
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I 33,500, Btu /hr perishipment.~~
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(ii) Shipme$t of ' contents'spedified.in!5(ti)(1)'(si):and 5(b)(1)(vii) and I I I
limited,in 5(b)(2)(iv) _shal.libe made in a : stainless. steel M-130 g
container and shall have a decay; heat load not to exceed 18,960 Btu /hr I
I per shipment.
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(iii) Shipment'ofecontentsspecifiedin5(b)(1)(viii)}'5(b)(1)(ix)and l.!
5(b)(1)(x) and limited in 5(b)(2)(v), 5(b)(2)(vi) and 5(b)(2)(vii) shall.
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l be made at a' time after shutdown as determined from Bettis Atomic Power i
I Laboratory repoFt WAPD-0P(PP)S-4401 dated June 29, 1979 and shall have a l
I decay heat load not'to exceed?2B,620 Btu /hr for the shipboard core and I
j 30,000 Btu /hr for the prototype core.
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(iv)
Shipment of contents specified in 5(b)(1)(i), 5(b)(1)(ii) l l :
shall be made no earlier than 72 days after shutdown and shall l '.
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have a decay heat load not to exceed 33,500 Btu /hr per shipment.
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'(v)
Shipment of' contents specified in 5(b)(1)(xi) or 5(b)(1)(xii) l l
as limited by 5(b)(2)(vii) shall have a fully loaded. container g,,
heat load not to exceed 15,400 Btu /hr per shipment.
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(vi)
Shipment of contents specified in 5(b)(1)(xiii) and limited in I
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5(b)(2)(ix) shall have a heat load not to exceed 23,800 I
Btu /hr and shall be made no earlier than 92 days after shutdown.
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Page 5 - Certificate No. 6003 - Revision No. 15 - Docket No. 71-6003 h ;
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- 5. (b) (3) Contents (cont'd) ilj i
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1 (vii) Shipment of contents specified in 5(b)(1)(xiv) and limited in l l l l
5(b)(2)(x) shall have a heat load not to exceed 22,400 Btu /hr
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l and shall be made no earlier than 122 days after shutdown.
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i (viii) Shipment of contents specified in 5(b)(1)(xv) and limited in I !
E 5(b)(2)(xi) shall have a heat load not to exceed 19,100 Btu /hr I
and shall be made no earlier than 420 days after shutdown.
l (ix) Shipment of contents specified in 5(b)(1)(xvi) and limited in h l 5(b)(2)(xii) shall have a heat load not to exceed 6,000 Btu /hr k
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and shall be made no earlier than 50 days after shutdown.
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(x) Shipment of contents'specified in5(b)(1)(xvii) and limited in t
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5(b)(2)(xiii)7shall have a heat load not to exceed 27,400 Btu /hr and shall be made no earlier than 195 days'after shutdown.
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Shipment of contents specified in 5(b)(1)(xviii) and limited in l l g
(xi) 7 5(b)(2)(xiv) shall have a heat load not to exceed 43,800 BTU /hr and I :
shall be7made no earlier than 400 days after shutdown.
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l (c) Fissile Class [,
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g Maximum number"b..f packages;per; shipment:
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Except for the' contents' described in3
. _ i-One (1) l l I !!
N 5(b)(1)(viii) and limited in 5(b)(2)(v);
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Forthecontents#describeddin5(b)(1)(kiii)[
- Two (2)
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and limited in 5(b)(2)(v)
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1 6.
For shipments involving the contents specified in!5(b)(1)(ii) or 5(b)(1)(iii)
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the Model No. M-130 ' package shall be' inspected to verify that boron poison l
plates are in the module" holders.
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For shipments involving the content's specified irf 5(b)(1)(viii), 5(b)(1)(ix) or
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5(b)(1)(x) the thermocouples and thermocouple ~ cases if included or the vacant module holder shall be located in the mid-position of either cage and module
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holder assembly.
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Page 6 - Certificate No. 6003 - Revision No. 15 - Docket No. 71-6003 t.
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8.
Shipments shall be made in the dry condition, except for residual water as jl : i i
limited in 5(b)(1), 5(b)(3)(v), and 5(b)(3)(vii).
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l 9.
Container number three (M-130-3) has been modified by adding two 4-inch thick by 8-inch wide steel plates welded between fins 25 and 50 and between fins 110 t.
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and 135 at approximately 14.75 inches from the bottom of the container. The La a
cooling fins in this localized area are removed to permit attachment of
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the plate directly to the outer shell of the container.
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- 10. Container number four (M-130-4) has been modified by adding a 2-inch thick 3
by 4-inch wide steel plate welded between fins 32 and 49 at approximately
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1 18.4 inches from the bottom of the container. The cooling fins in this E:
J localized area removed to permit attachment of the plate directly to the I-1 outer shell of the container. >
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i II. ContainersM-130-3,MI30-4,M-130-6,andM-130-7maybeusedforthecontents ff f
3 specified in 5(b)(1)(viii) and 5(b)(1)(x) only. Containers M-130-10 and M-130-15 L.
1 may be used for thejcontents specified in 5(b)(1)(viii), 5(b)(1)(x) and r-1 5(b)(1)(xviii) only.
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- 12. Container M-13041i may be 'used for NR-1 shipmentsfonly.
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3 13.
For shipments involving the contents specified in 5(b)(1)(xvii)' which do not
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1 contain a fullucomplement of(fuel modulesi(i.el one position is occupied by
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1 either two flux thimbles or-a vacant fuel ~ module holder with pocket shield
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1 plug), that position shall be located in.the middle module holder of either h};
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half of the cage cassembly.-
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Expiration date:EDecember 31, 1997._,
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CONDfTIONS (contmuect)
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l Page 7 - Certificate No. 6003 - Revision No. 15 - Docket No. 71-6003 E-q t
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REFERENCES lE
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l Safety analysis report for M-130 shipping container, MAO-E8-703 dated December 30, g
t-1968.
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g Supplements: Naval Reactors letters Ah2256 dated February 24, 1969 and G#1931 dated i
R March 3,1969; General Electric Company letter ONP-74520-526 dated April 3, 1972;
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N Naval Reactors letter G#3207 dated April 27, 1972; General Electric Company letter f
ONP-74520-528 dated April 28, 1972; Naval Reactors letter G#3250 dated June 6, 1972; f
l g
General Electric Company letters ONP-74570-635 dated October 25, 1972; ONP-74570-654 t
g dated December 4, 1972; ONP-14570-666 dated December 12, 1972; ONP-74570-682 dated t.
g January 12, 1973; ONP-74570-698 dated January.31,1973: ONP-74570-687 dated February 6, L'
i 1973; ONP-74390-65 dated March 26, 1973; DLGN-85570-854 dated September 24, 1973; i(( -
i[,
R DLGN-85570-901 dated January 10,(1974; Naval Reactors,let.ter G#4061 dated Janaury 29, N
1974; General Electric Company']etters DLGN-85570-924 dated February 15, 1974; DLGN-i l
85570-923 dated March 6, 1974; DLGN-85570-969 dated May 24,#1974; Naval Reactors s
letter G#4991 dated November 25, 1975; General Electric Company letters ONP-74340-JTT-73 lt t;
i dated December 17, 1975;-CGN-85570-Il45 dated September 9, 1976; CGN-85570-ll46 dated it
(
September 10,1976; CGN-85570-Il48 dated September 14, 1976; Bettis Atomic Power
- L l
Laboratory letter WAPD-R(K)-1378 dated August 30, 1976; WAPD-0P(PP)S-4401 dated June 29, f
1979; Naval Reactors letters G#6197 dated July 13,fl979; G#7136 dated March 17, 1982; f
ggl Naval Reactors letter G#7022 dated July 14, 1981 and WAPD-LD-(CES)SE-181 dated it.
g September,1981; WAPD-LP(CES)SE-96 dated February) 1982,' WAPD-LP-(CES)SE-170 dated July L;
g 1981; Naval Reactors letter G#7160 dated May 18, 1982; Naval Reactors letter G#7582 L
i dated September 7,1983; Naval Reactorsletter GfC87-5692 dated September 2,1987; Naval F
I-R Reactors letter G#C87-5689 dated September 23,71987; and Naval Reactors letters G#C87-hl 1
l Naval Reactors letter G#C89-2863 8008 dated January 19, G#C88-5931 dated May-12, and G#C88-5961 dated July 25, 1988.
dated August ill,'1989; Naval Reactor letter G#C89-2825 g
g g
dated March 29,1989; Naval Reactors letter lG#C92-03392 dated March 30, 1992; and Naval L;
g Reactors letter G#92-03729 dated October 20, 1992; L.
5 L
8 FOR THE<U.S. NUCLEAR REGULATORY COMMISSION
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' Charles E.-MacDonald, Chief I
i Tran'sportation Branch I
E Division of Industrial and Medical Nuclear Safety, NMSS f,
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V AR 9 1993 t-R Date:
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o UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 f
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APPROVAL RECORD Model No.
M-130 Certificate of Compliance No. 6003 Revision No. 15 By application dated October 20, 1992, the Department of Energy, Naval Reactors requested an amendment to Certificate of Compliance No. 6003 for the Model No. M-130 package.
The applicant requested that up to two packages be permitted per shipment for the 53G-3 fuel modules. The certificate currently permits one package per shipment for all contents.
The application includes a criticality analysis for a Fissile Class 111 package.
For normal conditions, the applicant evaluated an infinite number of undamaged packages in a hexagonal, close-packed array. The interior of the packages were flooded except for the central region which was assumed to be air. This represents the most reactive " normal" condition of the package, and would occur during fuel loading.
For accident conditions, the applicant evaluated two damaged packages. The damaged packages were subjected to optimum internal and interspersed moderation and full water reflection.
In both the normal and accident calculations, the applicant assumed that the packages were fully loaded with the most reactive, partially depleted, unrodded (i.e., without the control rods) S3G-3 fuel modules.
The final k, values, which include the estimated bias and statistical g
uncertainty, show that the package remains subtritical under normal and accident conditions.
The applicant's analysis shows that the change does not affect the ability of the package to meet the requirements of 10 CFR Part 71.
M tv Cfiarles E. MacDonald, Chief Transportation Branch Division of Industrial and Medical Nuclear Safety, HMSS
-Dat e :
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