ML20197F732
| ML20197F732 | |
| Person / Time | |
|---|---|
| Site: | 07109168 |
| Issue date: | 05/12/1986 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20197F714 | List: |
| References | |
| NUDOCS 8605150657 | |
| Download: ML20197F732 (4) | |
Text
e
- ----a,_-g I
k Nac Pones sis U.S. NUCLEAR REOULATO;Y COMMISSION I
- au Il CERTIFICATE OF COMPLIANCE E
l FOR RADIOACTIVE MATERIALS PACKAGES E
io CFR n l
1.a. CERTIFICATE NUMBER b REVGION NUMBER
- c. PACKAGE iDENTIFiCAT60N NUMBER d PAGE NUMBER e TOTAL NUMBER PAGES Iq 9168 3
USA /9168/R(U) 1 3
R:
l 2 PREAMBLE El ll a This certificate is issued to certify that the packaging and contents described in item 5 Delow, meets tne apphcacie safety st.ndards set forth m Title 10. Coce I) g of Federal Regulations. Part 71,' Packaging and Transportation of Radioactive Matenal?
jl
(
l
- n. This certificate does not reheve the consignor from comphance witn any requirement of the regulations of the U S. Geoartmant of Transportation or other Il ll apphcaole regulatory agencies. including the government of any country througn or into which the pacmage wiH be transported
'EI l
l l
l 3 THiS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANAL llE I
- n a ISSUE 0 70 rName maaf Aderm b TITLE AND IDENTIFICATION OF REPORT OR APPLICATION
?
I in i
Chem-fluclear Systens, Inc.
Chen-fluclear Systems, Inc. application dated
- E I
220 Stoneridge Drive June 19, 1984, as supplene'nted.
!b I
Columbia, SC 29210
)5 l
l l
- c. DOCMET NUMBER a CONOITIONS l
This certificate is conditional upon fulfdhng the requirements of 10 CFR Part 71, as apphcable. and the conditions specified below l I lE I s iE j
(a)
Packaging I
lE y
(1) Podel No.:
CNS 8-120B 1
I' N N
I (2) Description l'N
- I E
l The packaging is a carbon steel-encased, lead shielded 74-inch OD by 88-inch high cask for radioactive waste materials.
The cask is a
,y ly lg right circular cylinder with a 62-inch ID by 75-inch high cavity.
The p
walls of the cask contain a lead thickness of 3.35 inches encased in N
' ll 0.75-inch thick inner steel shell and 1-1/2-inch thick outer steel f
I s hel l.
The exoosed sides of the package are provided with a thernal j
l barrier consisting of a 5/32-inch diameter wire wrap on 12-inch centers 1
g and covered with 3/16-inch thick steel jacket. The botton weldment is
!9 g
g made of two, 3-1/4-inch thick carbon steel plates. The primary lid is N
l sealed with a double silicone 0-ring and 20 equally spaced 2-inch H
I diameter bolts. The 29-inch diameter centered secondary lid is sealed
,h I
with a double silicone 0-ring and twelve equally spaced 2-inch diameter f
l bol ts. The optional drain line is sealed with a 3/4-inch diameter cap
!b screw and a silicone 0-ring. The lid sealing surfaces are stainless g
steel and the space between the double 0-ring seals is provided with a lp h
I test port for leak testing.
lN I
- N
!j I
The top and bottom of the cask is provided with steel encased, rigid l
polyurethane foan inpact limiters. The inpact limiters are secured to y
y each other about the cask with eight 1-inch dianeter ratchet binders.
p p
The impact limiters are 102 inches in diameter and the overall height E
of the package with the impact limiters attached is 132 inches.
E I:
l-I The package is provided with four tie-down and two renovable lifting l
Il devices.
Each lid is provided with three lifting lugs. The gross y
weight of the packaging and contents is approximately 74,000 pounds.
I I
3 11
!I
&7 660512 l
- N C
l, l
PDR l
4l>
==mamm ammammum umm - - - -mmm.mmmm - - - - - - = mmmmmmmwr-
.= =.ac.naurum um CONolTloNS (contsnued)
Page 2 - Certificate No. 9168 - Revision No. 3 - Docket No. 71-9168 l
9 1
I (a)
(3) Drawing The packaging is constructed in accordance with Chem-Nuclear Systems, Inc. Drawing No. C-110-E-0007, Sheets I and 2, Revision D.
j (b) Contents l
(1) Type form of material i
(i) Byproduct material in the fom of dewatered resins, solids, or solidified waste contained within secondary container (s); or N
l 7
(ii) Radioactive material in the fom of activated reactor components.
(2) Maximun quantity of naterial per package l
Type B quantity of radioactive material, not to exceed 2,000 times a Type A quantity,100 thermal watts, and 14,680 pounds including weight of the contents,_ secondary container (s) and shoring. The contents may i
l include fissile materials provided the mass limits of 10 CFR 971.53 are not exceeded.
l l
6.
Except for close fitting contents, wood shoring must be placed between the secondary container (s) (or activated components) and the cask cavity to prevent movement during accident conditions of transport.
i 7.
The cask primary lid rust be secured by twenty and the secondary lid by twelve, I
2"-8UNC-2A x 4" long hex cap screws with flat washer torqued to 500 ft-lbs +50 i
f t-Ibs (lubricated).
- p 3
8.
Prior to each shipment (except for the contents neeting the requirements for low lE packaging must be leak tested in accordance with Section 8.2.2.2 of t specific activity naterial which is transported by exclusive use vehicle), the g
y l
9.
In addition to the reouirements of Subpart G.of 10 CFR Part 71:
I l
(i) Each package nust meet the acceptance tests and be maintained in accordance j
with the Acceptance Tests and Maintenance progran of Section 8.0 of the application, and
)g 4
l 5
I (ii) The seals must be replaced with new seals if inspection shows any defects
- B I
or every 12 nonths, whichever occurs first. The test ports and optional lE
]
drain line must be appropriately plugged and sealed prior to transport.
g p
g 10.
(a) For any package containing water and/or organic substances which could
- p il radiolytically generate conbustible gases, determination must be made by y
I tests and neasurements or by analysis of a representative package such that f
I the following criteria are net over a neriod of time that is twice the
]
expected shipment time:
j (i) The hydrogen generated must be limited to'a molar quantity that would I
be no more than 5% by volune (or equivalent limits for other inflamnable if
'N I
gases) of the secondary cogtainer gas void if present at STP (i.e., no
]
more than 0.063 g-noles/ft at 14.7 osia and 70"F); or i
!I
r
- p -- ----m -----mm mm ---mm mm mmmmm mm----uanam m m m m awnuom - - m m mm mmq lRl lll CONDITIONS (continued) lf Page 3 - Certificate No. 9168 - Revision No. 3 - Docket No.
\\l[
il I
nll
!II 10.
(continued)
I lI!
(ii) The secondary container and cask cavity nust be inerted with a diluent f;
to assure that oxygen must be limited to 5% by. volume in those portions g
ll of the package which could have hydrogen greater than 5%.
't I
E:
[4 For any package delivered to a carrier for transport, the secondary container j,{
must be prepared for shipment in the same nanner in which determination for lgi gas generation is made.
Shionent period begins when the package is prepared g
jgj (sealed) and must be conoleted within twice the expected shipment time.
p l#
- 5!
15 (b) For any package containing naterials with radioactivity concentration not
!E exceeding that for low specific activity material, and shipped within 10
}l days of preparation, or within 10 days af ter venting of druns or other p
l secondary containers, the determination in (a) above need not be made, and gi l !
the time restriction in (a) above does not apply.
5:
l !
t' i I
- 11. The package authorized by this certificate is hereby approved for use under the Ej general license provisions of 10 CFR 571.12.
- 12. Expiration date: fiarch 31, 1990.
g I
in REFERENCES
- Pj lil Chem-Nuclear Systems, Inc., application dated June 19, 1984.
l Supplements dated:
December 7,1984; March 15 and December 9,1985; and April 30, jij 1986.
E lI!
E II
- Ej
]
FOR THE U.S. NUCLEAR REGULATORY C0fitilSSION ll
.I
' I
.El ld, Chie 4
Transportation Certification Branch 8
j Division of Fuel Cycle ard
- j
}f is!
Material Safety, fliSS I
Date: MAY l 2 W j}
I N
i l
N i
ll
.i Il
!I I
lB I
E g
- L8 I
II lI I
l l is it l
IE i
.5 g
- B
.r --
l~
v# "**%*
j UNITED STATES
~'
NUCLEAR REGULATORY COMMISSION j,,
Y'I.
j WASHINGTON, D. C. 20555 e
?,g %.
8
,o Transoortation Certification Branch Approval Pecord l'odel No. CNS C-120B Package Docket No. 71-9168 By application dated Aoril 30, 1986, Chem-Nuclear, Inc. requested revised 0-ring gasket sizes to the Model No. CNS 8-1208 package design.
The lid 0-ring diameters have been increased in size fron 0.250" to 0.275" with a 70 + 10 -10 durometer rating. The increased diameter should provide a more positive seal to the cask lids.
The revised package design meets the requirements of 10 CFR Part 71.
. /]
Char es
. P*aceonaid,~ Chief Transportation Certification Branch Division of Fuel Cycle and fiaterial Safety, HMSS Date: MAY 121996
.