ML20211D464
| ML20211D464 | |
| Person / Time | |
|---|---|
| Site: | 07109145 |
| Issue date: | 09/17/1997 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20211D459 | List: |
| References | |
| NUDOCS 9709290142 | |
| Download: ML20211D464 (4) | |
Text
_ _.
fwwwwwwwww M M .
l NRC.FOcW 618 U.S. NUCt. EAR EEOut ATORY COMMISSION
. g! o* CERTIFICATE OF COMPLIANCE 4'l gl " C" " FOR RADIOACTIVE MATERIALS PACKAGES Nl g Is CLkTillCATE NUMitt R b REVislON NUMBLR s PACKAGE IDfWTif1CAtlON NUMBLR d PAGE NUMBER e TOT AL NUMBER PAGLS 9145 - 12 USA /9145/A 1 3 p 4 k i 2 PREAMati N a This ceruncate is wued io centfy that the packaging and contents descnhed in item 5 helow. meets the apphcable safety standards set forth in Title 10. U O
g Code oflederal Regulatons, Pan 71. *Pedaging and Transportation of Radioacuse Material? !
b This ceruncate da:s emt etheve the consigna frorn comphance with any tequirement of the regu.aimns of the U.S. Dcpaament of Transportation or other N hl apphcable regulatory agencies, including the governmem of any country through or into which the package will be transponed. N q,
t 3 TH1% CLRilflCATL 15 !55Uth0N Till BA%I5 W A SAITTY AN ALY51% Rf PORT OF THE PACKAGl: DESIGN OR APPLICATION a 155ULD TO(A.ame sad A4tresel b. TITLT AND IDENTIBCATION OF RLFORT OR APPLICATION. k NUPAC Services Division, Inc. application 8 g$ Molten Metal Technology, Inc.
g i 1009 Commerce Park Drive dated February 21, 1991. U N
Oak Ridge, TN 37830
'l$ c. DOCKl'T NUM8'.R 71-9145 N g
b 4 CONDITIONS g
$ This certificate is conditional upon fulfilhas the requirements of 10 CIR Part 71, as applicable, and the conditions specified below. g
- 8
- 5 '
i (a) Packaging N 8
% (1) Model Hos.: NUPAC 50-1.5L, NUPAC 50-2.5L, NUPAC 50-3.0L, and NUPAC 50-4.0L. E
% 5
% (2) Description N d
Wi
% A steel encased lead shielded cask for radioactive material. The casks are d q
9, rightcircularcylinderswitha48.5-inchinsidediameterby52.5-inchinsidela high cavity. The walls of the casks contain a lead thickness ranging from D 1.25 to 3.75 inches encased in 3/8-inch thick steel shells. The bottom and a
%j g l
top fromcovers 1.00 to 3.00 of the cask are made up of two steel plates ranging in thicknes inches. g
% A secondary cask lid is centered
% cask body by eight, 1-inch rachet binders. q ej in the primary lid and is secured to the primary lid with eight, 3/4-inch q W; studs and nuts. Each lid is provided with a Neoprene gasket seal. The cask g Bj is provided with four equally spaced lifting / tie down devices. Cask gross a t
weights range from 13,200 to 28,900 pounds. g f%- (3) Drawing 8
g i e The Model No. NUPAC 50 Series packagings are fabricated in accordance with g Nuclear Packaging, Inc. Drawing No. X-20-2010, Sheets 1 and 2, Revision C.
>l!
g E
N f
8 '
5 4
! W d
- B g i 8 E l N l $ N l $ d l $ W'
! p
. g l 4 g
~
U 9709290142 970917 k PDR ADOCK 07109145 d
% C PDR g bammmmmmmEEEmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmml4
,ww=ww._w._r_muEsm==wwmununx=Lwwwwwwwwwww=wwwwwwwwwwwwwww4' g NR FORM 814A memow umum.n.n U.S. NUCLEAR REGULATORY COMMISSION g g
i b l
- pf Page 2 - Certificate No. 9145 - Revision No.12 - Docket No. 71-9145 g g
g;
,l p
- 5. (b) Contents
- R p (1) Type and form of material y
- l p l Dewatered, solid or solidified waste, in secondary containers, or q
g e
activated solid components, and limited to the following: g h (i) Materials in which the radioactivity is essentially uniformly l distributed and in which the estimated average concentration per g gram of contents does not exceed: y N
I 0.0001 millicurie of radionuclides for which the A quantity in I Appendix A of 10 CFR Part 71 is not more than 0.05, curie; l 0.005 millicurie of radionuclides for which the A, quantity in U N
l Aspendix A of 10 CFR Part 71 is more than 0.05 curie, but not more t1an I curie; or l
$l 0.3 millicurie of radionuclides for which the A quantity in AppendixAof10CFRPart71ismorethanIcurke.
8 I
$ (ii) Objects of nonradioactive material externally contaminated with
'l radioactive material, provided that the radioactive material is not 8 8
$ readily dispersible and the surface contamination, when averaged
$ over an area of 1' square meter, does not exceed.0.0001 millicurie 4 A
l (220,000 disintegrations )er minute) per square centimeter of N
- j radionuclides for which tie A, quantity in Appendix A of E
$ 10 CFR Part 71 is not more than 0.05 curie, or 0.001 millicurie E
% (2,200,000 disintegrations per minute) per square centimeter for ( ,
other radionuclides. ,
N
% (2) Haximum quantity of material per package E
- E J
i Greater than Type A quantity of radioactive material. 4 4
% g
% 6. (a) For any package containing water and/or organic substances which could
% radiolytically generate combustible gases, determination must be made by (
% tests and measurements or by analysis of a representative package such that E
% the following criteria are met over a period of time that is twice the a expected shipment time: g
- 8 1
% (1) The hydrogen generated must be limited to molar quantity that would be s p
- p no more than 5% by volume (or equivalent limits for other inflammable p gases) of the secondary container gas void if present at STP (i.e., no q more than 0.063 g-moles /ft3 at 14.7 psia and 70*F); or u E
(2) The secondary container and cask cavity must be inerted with a diluent g
% to assure that oxygen must be limi+ed to 5% by volume in'those portions a of the package which could have a hydrogen concentration greater than 5%. g 4
% For any package delivered to a carrier for transport, the secondary container a
% must be prepared for shipment in the same manner in which determination for p 5 gas generation is made. Shipment period begins when the package is prepared g b (sealed) and must be completed within twice the expected shipment time. g g
Bi
$ , N k*mmamm m, = = m m m = m m . m , m . m . . . . . mm . ,,,,,,, , ,,, #
' JF_JLW_JLEUELMLM.EUWJF._ BLE.W_WJE1EF W Wiy w mLgLatm'.jtp w y mjEyg f I (uwmoutrwn t> U.S. NUCLEAR RE!ULATORY COMMISSION g ,
g NMC FORM 616A '
, 0W Dj Page 6 - Certificate No. 9176 - Revision No. 14 - Docket No. 71-9176 , !
e 4
l r i s[
n e
r l E
REFERENCES l
- f D E t l DlNuclearPackaging,Inc.,applicationdatedFebruary D 29, 1988. t E
l Dl Supplements' dated:
D April 19,1988; March 1,1993; and August 5,1997. - l t
E D
DfPacificNuclearsupplementsdated: October 23 and December 2 and 21, 1992. I t
Systems, Inc., supplements dated: February 19 and April 21, 1988; el Chem-Nuclear D3 January 18, and April 29, 1993; and January 29, 1996 i
r l
E I
$ 4 t
NUS supplement dated: November 22, 1985. l Dj 1 D I l D February 16, 1988. I I 1
BllLNTechnologiesCorporationsupplementdated e Scientific Ecology Group, Inc., supplement dated: April 30, 1993.
t t
E D
I FOR THE U.S. NUCLEAR REGULATORY COMMISSION r 9l D
2 E D; E t !
- t i p! Cass R. Chappell, Chief g gi Package Certificatirn Section ,
,I Spent Fuel Project Office g g! Office of Nuclear Material Safety g and Safeguards g gl t
D, Date: Septador 17, 1997 ll t
Dl B
f,j t I
5; t
- j
- j r f
B; Bj r
D t i
t Dj D t i
t Dj D i i
Dj E
- E D t i
9; E
Bl D t a
Di 5 Dj 8 r
% a m n m a m m_ m a m m a m m' m ai m a m m at a at m ai nt a m m m mi ni mi m mi at a n m a m m< as a ni mE e
k
[ UNITED STATES NUCLEAR REGULATORY COMMISSION
, J-
- #j WASHINGTON, D.C. soseHooi
\...../
APPROVAL RECORD Model Nos. NUPAC 50-1.5L, NUPAC 50-2.5L, NUPAC 50-3.0L, and NVPAC 50-4.0L .
Certificate of Compliance No. 9145 Revision No. 12 By letter dated August 5,1997, VECTRA Technologies, Inc., and Molten Metal .
Technology, Inc., requested that the certificate holder for Certificate of Compliance No. 9145 for the Model No. NUPAC 50-1.5L, NUPAC 50-2.5L, NUPAC 50-3.0L, and NUPAC 50-4.0L packages be changed from VECTRA Technologies, Inc., to Molten Metal Technology, Inc. Molten Metal Technology, Inc., has accepted responsibility for the completeness and accuracy of the statements and representations of the previous certificate holder. Molten Metal Technology, Inc., will be responsible for maintenance of the certificate, the safety analysis report for the package designs, and the quality assurance records in accordance with 10 CFR 671.91(c). Molten Metal Technology, Inc., stated that the records required by 10 CFR 671.91(c) for the package designs will be maintained at their document control center at 1556 Bear Creek Road, Oak Ridge, Tennessee. Molten Metal Technology, Inc., has oeen issued Quality Assurance Program Approval for Radioactive Material Packages No. 0870, under Subpart H of 10 CFR Part 71.
The Certificate has been revised to show Molten Metal Technology, Inc., as certificate holder. These changes do not affect the ability of the packages to meet the requirements of 10 CFR Part 71.
M4 f Cass R. Chappell, Chief '
Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date: Sept. 17, 1997 e
o