ML20210L717
| ML20210L717 | |
| Person / Time | |
|---|---|
| Site: | 07106568 |
| Issue date: | 08/14/1997 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20210L710 | List: |
| References | |
| NUDOCS 9708210285 | |
| Download: ML20210L717 (5) | |
Text
i
.J A W E W W W W W,313rW W w W W W W W W W W W W W W W W W W W W W W W W W u<W W W W g 3 (
i Ig NRC FORM 618 U.S. NUCLEAR REIULATORY COMM:CSION g.
i nw N S C"'"
CERTIFICATE OF COMPLIANCE i
I l'OR RADIOACTIVI: M ATI:RI ALS PACKAGl3 k
i i a Cl'RTillCATh NUMBLR b kEvlslON NUMBf k e PACAAGEIDENTillCATION NUMhtR d PAOL NUMhER e TUTAL NUMBLR PAGES nl 6568 11 USA /6568/A 1
4 m
h2PREAMBLia N
kl
- a. This cemficate is issued to certify that the packaging and contents descnbed in item $ below, rnects the applicable safety standards set forth in Title 10, N-N Code of Federal Regulations, Part 71.
- Packaging and Transportation of Radioactise Material."
d'
%g b This ccmficate does not reheve the consignor from comphance with an) requirement of the regulations of the U.$ Department of Transportation or other h
apphenble regulatory agencies, including the gesernment of any country through or into w hich the package aill be transported.
E 3 TH15 CL RTil1CATE 15 ISSULD ON THE B Asis Of A 5 AfITY AN ALY$15 RINRT OF THE PACK AOL DL$lGN OR APPLIC ATION a ISSULD TO f %me sinJ AJJersu b TITLE AND IDENT1f1 CATION OF Rf PORT OR APPLICATIOk N
4, E
W l
4 p
Chem-Nuclear Systems, Inc.
Tennessee Valley Authority application g
"Q 140 Stoneridge Drive dated August 16, 1976, as supplemented, l
Columbia, SC 29210 g
p!
71-6568 g
p e DoCAETuUuBE, y
$ 4 CONDITION 5 g
g This cemficate is conditional upon fulfilhng the requirements of 10 Cf1 Part 71, as appikable, and the conditions specified below.
g A 5 g
(
sj E
f (a)
Packaging I
l (1)
Model No.:
LL-60-150 (2)
Description l
Ni The cask is cylindrical in shape 93 inches long and 82.5 inches in E
1 diameter.
Lead shieldir:g, 3-1/2 inches thick, is encased within the E
!I inner and outer steel shells that are welded to a laminated steel base E
8 plate assembly. The cover is a steel plate assembly secured to the top E
flange by 36 steel bolts.
Encircling the top of the cask is a partial E
sj length steel shell of 1/2-inch thickness. Silicone 0-rings provide seals E
si at the top cover and at-all plugs.
The inner container is right circular E
- j steel cylinder with a capacity of 150 cu ft. The total weight, when E
Bj loaded, is approximately 73,000 pounds.
E Sj E
s (3)
Drawings E
i E
The packaging is constructed in accordance with the following ATCOR Inc.
E s
Drawing Nos.: 0568-B-0005, Rev. H; 0568-C-0008, Rev. E; 0568-B-0010, l
E t
- {
Rev. E; 0568-B-0016, Rev. D; 0568-B-0018, Rev. A; 0568-B-0025; and E
0568-R-0001, Rev. J.
E Sj E
- l 6
- j E
h}
E bj E
B, a
W
- i E
4 E i E
4 W
D 9708210285 970814 I
5
!= = m um m m m m m m m m m m m m m m m. m m m m m m_m m m s m m m m m, u. m m m m, J
waw w w w w w w w w w w w w w w w w w w w w w =usur = = = w w w w w w w w w w w w w w w w w g g
g NRC FORM 618A CONDmoNs inmunu.es U.S. NUCLEAR REoVLATORY COMMIS$10N g
ei a
Bj Page 2.- Certificate No. 65f>8 - Revision No. 11 - Docket No. 71-6568 q
B e
Bf q
B; 5.
(b)
Contents u
Dj E
b; (1)
Type and form of material e
- j d
W Process solids, either dewatered, solid, or solidified waste, in g
B sealed containers, and limited to the following:
q
- j N
Bj (i)
Materials in which.the radioactivity is essentially uniformly a
W; distributed and in which the estimated average concentration a
4; per gram of contents does not exceed:
q
- i d
p 0.0001 millicurie of radionuclides for which the A, quantity g
e in Appendix A of 10 CFR Part 71 is not more than 0.05 curie; g
r a
p 0.005 millicurie of radionuclides for which the A, quantity in y
p Appendix A of 10 CFR Part 71 is more than 0.05 curie, but not g
4 more than 1 curie; or g
>l 0.3 millicurie of radionuclides f$r:which the A quantity in d
p AppendixAof10CFRPart71ismorethan1 curie.
g g
h (ii) Objects of-nonradioactive material externally contaminated l
g!
with rr.dioactive matarial, provided that the radioactive N
g material.is not readily dispersible and the surface i
l I
g contamination, when averaged over an area of I square meter, l
U g
does not exceed 0.0001 millicurie (220,000 disintegrations 1
I 9
per minute) per square centimeter'of radionuclides for which U
y!
the A, quantity in Appendix A of 10 CFR Part 71 is not more J
than 0.05 curie, or 0.001 millicurie I
E h
'2,200,000 disintegrations per minute) per square centimeter l
? other radionuclides.
8 g
(2) h a
)ity cf material per package U
l}l ype A quantity of radioactive material with the 4
Grea >
weight ta
.a package contents and secondary containers not E
ll exceeding 12,500 pounds.
E
'i a
E 6
!)
E
'l N
'j u
bl u
D N
9j E
- 6
\\
n Ej W
Bj E
B e
i i
M i
l-i 5
l N
m m m m m m m m m m m m m m m m m m_m_ m m m m m m m m m m m m m m m m m, m m
M A gr y _prw w w w w w w w w w w w w w w w w w[w w w w w w w w w w w w w w w w w w w w I
gl NRC FORM 818A Wl CONDmo% tomsawe U.S. NUCLEAR RE2VLATORY COMMISSION gl p*
h' f.
Page 3.- Certificate No. 6568 - Revision No. 11 - Docket No. 71-6568 8
6.
(a)
For any package containing water and/or organic substances which could f
8 radiolytically generate combustible gases, determination must be made by n;
- l tests and measurements or by analysis of a represeqtative package such
'l that the following criteria are met over a period of time that is twice i,
t the expected shipment time:
(1)
The hydrogen generated must be limited to a molar quantity that E
would be no more than 5%.by volume (or equivalent limits for other E
inflammable gases) of the secondary container gas void if present i
at STP (i.e., no more than 0.063 g-moles /ft3 at 14.7 psia and E
70*F); or B
E l
(2)
The secondary container and cask cavity must be inerted with a 6
diluent to assure that oxygen must be limited to 5% by volume in E
Bj those portions of the package which could have a hydrogen a
D concentration greater than 5%.
E j
D E
M; For any package delivered to a carrier for transport, the secondary 8
9, container must be prepared for shipment in the same manner in which determination for gas generation is made.
Shipment period begins when d
4 3,
the package is prepared (sealed) and must be completed within twice the 5
expected shipment time, d
s,i 4
5';
(b)
For any package shipped within 10 days of preparation, or within 10 days 4
4 after venting of drums or other secondary containers, the determination d
M in (a) above need not be made, and the time restriction in (a) above does a
p!
not apply, d
N d
p 7.
In addition to the requirements of Subpart G of 10 CFR Part 71:
5 9
d p!
(a)
Each package must be maintained in accordance with Reactor Cleanup Cask 8
le Maintenance Program in the supplement dated February 20, 1991.
g B
E p
(b)
The package must be prepared for shipment and operated in accordance with d
p.
the Reactor Cleanup Cask Operating Procedure in the supplement dated a
p February 20, 1991.
g d
p 8.
The package authorized by this certificate must be trans)orted on a motor l
g g
vehicle, railroad car, aircraft, inland water craft, or Told or deck of a g
pl seagoing vessel assigned for sole use of the licensee.
g B
E p
9.
Fabrication of additional packagings is not authorized, g
b d
p 10.
The package authorized for use by this certificate is hereby approved for use g
g under the general provisions of 10 CFR 571.12.
g B;
E D
E D
d 4
a d
d a
d D
d j
Emmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm$
-,w_.. w w ws w w w w_w w w w w w w w w w w w w. w w w w w w w w w w w w. w w w w. w w w g
FORM 618A CONDm0NS (nmimwds U.S. NUCLEAR REGULATORY COMMISSION
- l Page 4,- Certificate No. 6568 - Revision No. 11 - Docket No. 71-6568 p'
E b
Bj E-
- {
E D
11.
Expiration date: April 1, 1999. This certificate is not renewable, g
E D
E
.l p
REFERENCES g
E
- ,j E
4, Tennessee Valley Authority application dated August 16, 1976.
g 4p!'
Su)plements dated: October 8, 1976; Octob.ar 5, 1979; October 23, 1980; g
E l
p Fe)ruary 20, 1991; February 29, and September 30, 1996.
g E
g Chem-Nuclear Systems, Inc. supplement dated December 20, 1996.
g 3
i g
l FOR THE U.S. NUCLEAR REGULATORY COMMISSION
!{
E h
E h
Cass R. Chappell, Chief 8
1 Package Certification Section E
9i g
Spent Fuel Project Office E
~I Office of Nuclear Material I
Safety and Safeguards I
Date: August 14, 1997 E
E
- ,i E
!I E
5; E
E S
i E
5; E
B i
E
!i E
S i
E
!i E
- i E
!I E
5 B,
E i
E E
E
!j
- {
E i
E 5
b{
E i
E si E
1 4
B i
E Bj E
B t
E Bl E
9 s!
E i
E
- i E
E l
E
$m m m m m m m m m m m m m m m m m m un < = m m m m m m m m m m m m m m m m m m m m m m,,,,m E
7t:y UNITED STATES
[f j
NUCLEAR HEGULATORY COMMISSION t
WASHINGTON, D.C. *anas %
...../
APPROVAL RECORD Model No.
LL-60-150 Certificate of Compliance No. 6568 Revision No. 11 In Certificate of Compliance No. 6568 for the Model No. LL-60-150 package, Revision No.10, Condition No. 5(a)(3), there was a typographical error in the third drawing number referenced. The Certificate of Compliance has been amended to correct the typographical error.
$ >f-ed(
f Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Dato:
August 14, 1997
- - _ - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _.