ML20210L717

Certificate of Compliance 6568,rev 11,for Model LL-60-150 Package

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: ML20210L706 ML20210L717
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 iW W g 3 (

I g NRC FORM 618 U.S. NUCLEAR REIULATORY COMM:CSION i nw g.

NI S C"'" CERTIFICATE OF COMPLIANCE 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 6568 11 USA /6568/A nl 1 4 m h2PREAMBLia N kl N

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-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

pl Chem-Nuclear Systems, Inc. Tennessee Valley Authority application 4 g

"Q 140 Stoneridge Drive dated August 16, 1976, as supplemented, g l Columbia, SC 29210 p! g p e DoCAETuUuBE, 71-6568 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 Ag 5 (

sj E f (a) Packaging I (1) Model No.: LL-60-150 l

(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 8

inner and outer steel shells that are welded to a laminated steel base E 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

1. j steel cylinder with a capacity of 150 cu ft. The total weight, when E Bj loaded, is approximately 73,000 pounds. E S

j E s Drawings i (3) E

% E

1. 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, t l E

1. { 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

1. l 6

1. j E h} E bj E B, a

% W

1. i E

% 4

% Ei

% E

% 4

% W D 9708210285 970814 g gI PDR ADOCK 07106568 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

gwaw 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 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 q

Bf B; 5. (b) Contents u Dj E b; (1) Type and form of material ,

e

1. j d W Process solids, either dewatered, solid, or solidified waste, in g B sealed containers, and limited to the following: q

1. 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

1. 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

1. . 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 d

>l p 0.3 millicurie of radionuclides f$r:which the A quantity in g

, AppendixAof10CFRPart71ismorethan1 curie. g h (ii) Objects of- nonradioactive material externally contaminated l g! with rr.dioactive matarial, provided that the radioactive gi material.is not readily dispersible and the surface N I

gl contamination, when averaged over an area of I square meter, l does not exceed 0.0001 millicurie (220,000 disintegrations U g

1 per minute) per square centimeter'of radionuclides for which I 9 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 hl '2,200,000 disintegrations per minute) per square centimeter E

? other radionuclides. 8 g

(2) h a )ity cf material per package U

Grea > ' ype A quantity of radioactive material with the 4 l}l weight ta .a package contents and secondary containers not E exceeding 12,500 pounds.

ll

!! E

'i# a 6 E E

!)

'l N

'j u bl u D N 9j E

• 6\ n Ej W Bj E B e i

i M l-  % i 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

CONDmo% tomsawe U.S. NUCLEAR RE2VLATORY COMMISSION gl p*

gl NRC FORM 818A Wl Page 3 .- Certificate No. 6568 - Revision No. 11 - Docket No. 71-6568 h'

f.

8 8

6. (a) For any package containing water and/or organic substances which could radiolytically generate combustible gases, determination must be made by f n;

1. 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 # l B E (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 Dj concentration greater than 5%. E 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 the package is prepared (sealed) and must be completed within twice the 5 3,

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 l 8 e 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 g gl 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

10. d p 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 Dj d

E mmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm$

,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 E

• l b

Bj Page 4,- Certificate No. 6568 - Revision No. 11 - Docket No. 71-6568 p' E-

1. {

D 11. Expiration date: April 1, 1999. This certificate is not renewable, E

g

,, E D E p REFERENCES g

.l E

1. ,j E 4, Tennessee Valley Authority application dated August 16, 1976. g 4

p!' Su)plements dated: October 8, 1976; Octob.ar 5, 1979; October 23, 1980; E g

pl 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 FOR THE U.S. NUCLEAR REGULATORY COMMISSION l

!{ E h E h Cass R. Chappell, Chief 8 9

1 Package Certification Section E gi Spent Fuel Project Office E

~I Office of Nuclear Material I Safety and Safeguards I Date: August 14, 1997 E E

1. ,i E

!I E 5; E S

E i E 5; E B

i E

!i S

E i E

!i E

• i E

!I 5

E B, E i E E

E

!j E

• {

i E 5

E b{i E si E 1 4 B

i E Bj E B

t E Bl E 9

E s!i E

1. 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 E ! ,,, ,m

7t:y

& UNITED STATES

[f j

t NUCLEAR HEGULATORY COMMISSION 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

- - _ - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ .