ML20236F412
| ML20236F412 | |
| Person / Time | |
|---|---|
| Site: | 07109781 |
| Issue date: | 07/29/1987 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20236F406 | List: |
| References | |
| NUDOCS 8708030330 | |
| Download: ML20236F412 (4) | |
Text
g-mm,-- sarrszerenacram.iiacTemmzerrssa:rrzrexTEErmersrEEri N NF.C FORM 61: U.S. NUCLEAR REGULATORY COMMISSION 4 N e CERTIFICATE OF COMPLIANCE #
, io crA 7' FOR RADIOACTIVE MATERIALS PACKAGES Y i a ctRiiricATE NUMeER b REVi$lON NUMBER C PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES g
g 9781 4 JSA/9781/B()F 1 3 I:g 4, 2 PREAMBLE i a Tnis ceriihces is ,ssuee to certif, inaiIne pac *ag,ng ano conients eescrib o in item s beiow. meets tne sopi.caoie safety staneares set fortn m Titie to, cooe 1 ,
of reeero neguiations. part 7i. Pac = aging ana Transportation of nacioactive uater ai-f( O Thes certificate does not rehevc the consignor from comphance with any requiremen' of tne regulations of the U S Department of Transportation or other
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h' applicaDie regulatcly agencies including the government of any Country tnrough or into which the package will be transported h{ I 4; ,
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"'%"E ANo"o'EET$A t oN ENEPoE"NAPY"c4 Tion i 4
n!d U.S. Department of Energy Safety Analysis Report for M-160 Shipping ;
8: Division of Naval Reactors Container dated October 18, 1968, as i l
5 Washingtort, DC 20585 supplemented. j l Nl i-(
c oocxETNuueER 71-9781 ;
o CONDif10NS hj This certthcale is conditional upon fulhlhng tne requirements of 10 CFR part if as apphcable. and the conditions specified below i' 5
Nj ,
(a) Packaging l g tg- l (1) Model No.: H-160 pi l
- l (2) Description i i The packaging is a right circular cylinder, 79 inches in diameter i j t by 199 inches overall height. The packaging outer shell consists i
of 84 evenly spaced vertical fins 151-1/2 inches long, attached to a 1-1/2-inch thick wall (fabricated from carbon steel and clad , l
! with stainless steel on the outer surface). The inner shell, the E l containment vessel, is 1-inch thick (having a 1/8-inch thich fl E
l rollbonded stainless steel cladding) whose base is 7 inches thick. l
- The 9-7/16-inch annulus between the outer and inner shells is !
ql filled with lead. The top of the container is covered with a '
i rotatable closure head fabricated of stainless steel 15 inches :
%g; thick which is bolted to the container and seals the containment ,
l N; vessel. An oblong access plug in the cover allows for individual i 4
( spent fuel cell loading or unloading. 1 l
4 gl The containment vessel has an inside diameter of 55 inches. The '
u t
central region contains a secondary heat exchanger which is ll supported by the closure head. (This heat exchanger is not used i lll during shipment.) An inner backup cylinder, 21 inches in diameter, i I! occupies the central region of the containment vessel. The annulus i f between the backup cylinder and of the containment vessel shell lj 8l N
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l 8708030330 G70729 PDR ADOCK 0710 1 g
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CONofTIONs (continu:d) i l Page 2 - Certificate No. 9781 - Revision No, 4 - Docket No. 71-9781 1
I I 5. (a) Packaging (continued) l (2) Description (continued) l l provides a space 17 inches wide by 160 inches high for spent fuel.
l The spent fuel is contained in the annulus by aluminum module i holders designed for the particular spent fuel to be shipped.
I I The packaging has external penetrations to the containment vessel l for a steam and water vent line, which is capped during shipment.
i Shipments are by rail. The packaging is cradled in a support which i permits the packaging to be nearly horizontal during shipment. The i maximum loaded shipping weight is 237,000 pounds.
I ,
j (3) Drawings /
l The packaging is constructed in accordance with the description and i Drawing Nos. contained in the Bettts Atomic Power Laboratory Safety i Analysis Reports (WAPD-0P(R)C-243, WAPD-0P(R)C-558 and WAPD-0P(R)C-621 4 dated May 1973, October 1, 1976 and March 1977.
(b) Contents l l (1) Type and form of material e
j Irradiated fuel assemblies and blanket nodules of the following type:
l h (i PWR Core 2 Seed 1 Fuel Assembly.
j (11 PWR Core 2 Seed 2 Fuel Assembly.
y (iii PWR Core 2 Blanket Fuel Assembly.
g (iv SSG Fuel Module, rodded or unrodded.
I W (v S5G Center Cell.
t !
3 All shipments shall be made dry and shall use one holddown device f per PWR module. Each PWR Core 2 Seed 1 or Seed 2 fuel assembly shall contain a poison rod or a control rod.
(2) Maximum quantity of material per package l
! (1) 12 fuel assemblies as described in 5(b)(1)(1) or 11 fuel l assemblies and one specific blanket fuel assembly, Serial j No. G2A-W01-67. Shipment shall not be made prior to 1,614 days
! after last power operation of the fuel and shall not exceed st 12,846 Btu /hr of decay heat per shipment.
i 3
(ii) 12 fuel assemblies as described in 5(b)(1)(ii) which shall not exceed 1,100 Btu /hr per fuel assembly of decay heat or 13,200 gl Btu /hr per shipment.
3 l e (iii) 12 blanket fuel assemblies as described in 5(b)(1)(iii) which N
N shall not exceed 21,300 Btu /hr of decay heat per shipment. 1 Shipment shall not be made prior to 1,123 days after last power f f operation of the fuel, t i
M l L--- - --- - - - - ,. - - ,. . . - - r; c,.u. . =n.a. - - - - ,. . . c - - ,- - - - ,- - - - k
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CoNo(Tl5NS (continutd) 3 Page 3 - Certificate
- e. '781 - Revision No. 4 - Docket No. 71-9781 l
1 I
l (b) Contents kontinued) l I (2) Maximum quantity of material per package (continued) l (iv) 8 fuel assemblies as described in 5(b)(1)(ii) and 4 specific l blanket fuel assemblies, Serial Numbers G2A-F01-26B, G2A-F01-02, i
i G2A-F01-10 and G2A W01-73, which shall not exceed 12,016 Btu /hr i of decay heat per shipment. Shipment shall not be made prior I to 1,487 days after last power operation of the fuel, with the I four blanket fuel assemblies located adjacent to each other in l a clockwise or counter-clockwise direction as specified by the i serial numbers previously stated.
l l (v) 4 fuel assemblies as described in 5(b)(1) (iv) or 3 fuel I assemblies and one'centerJcell f as described in 5(b)(1)(v).
I Shipment,shall not be made rp'iore to 168 days after last power l oper6 tion of the fuel rod and shall;not exceed 12,800 Btu /hr of g decay heat per shipment. ;y 1
i (c) Fissile Class 'III Maximum number of packages per shipment- One(1) l l 6. Expiration date: July 31, 1992.
i 9
1 REFERENCES E
N l Safety Analysis Report for M-160 Shipping Container: Core Independent Analyses,
.4 SRSD-106, dated October 18, 1968, as transmitted by Naval Reactors Letter G#2097, y dated June 3, 1969.
H 4 Supplements: Knolls Atomic Power Laboratory letter 0NP-74520-414, dated November 26, 8
1969; Naval Reactors letter G#3742, dated May 15, 1973; Bettis Atomic Power l LaboratorylettersWAPD-0P(R)C-284,datedAugust 23, 1973 andWAPD-0P(R)C-297, dated y October 8,1973; Naval Reactor letters G#5582, dated December 17, 1976; G#5671, dated g April 15, 1977; G#5702, dated May 23, 1977; G#5792, dated September 22, 1977; G#5793, e dated September 29,1977; G#5872, dated December 20, 1977; G#5897, dated
! January ll, 1978, and G#6658, dated April 14, 1980.
m l FOR THE U.S. NUCLEAR REGULATORY COMMISSION 4
)
E hY 7ts Charles E. MacDonald, Chief l Transportation Branch y Division Safeguards and ;
) Transportation, NMSS ,
4 I Date: JE A I I907 N
d i ,I 3
f L____________________ m __ m__________ _ w
'. %g UNITED STATES e
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20065
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Transportation Branch Aaproval Record Model 40. M-160 Packaging Docket No. 71-9781
' Revision No. 4 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. 9781. No cha'iges have been authorized to the package design since approval of latest supplement dated April 14, 1980.
Condition 5.(a)(2) of the certificate has been revised to clarify the packaging description.
The certificate of compliance has been renewed for a five year term which expires July 31, 1992.
8!
Charles E. MacDonald, Chief Transportation Branch ,
Division of Safeguards and !
Transportation, NMSS JUL 39 My Date:
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