ML20211D445
| ML20211D445 | |
| Person / Time | |
|---|---|
| Site: | 07109079 |
| Issue date: | 09/18/1997 |
| From: | Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20211D441 | List: |
| References | |
| NUDOCS 9709290134 | |
| Download: ML20211D445 (5) | |
Text
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>l N CERTIFICATE OF COMPl. LANCE
<t 11)R RADIDACllVE MA1LRI AIS PACKAGl3 gl 1.s CI FTU IC ATI NUMitl N gl b R) YlilON NUMh! k s PACA AGI IDI NTH IC AilON NUMht k d l'Abt NUMbi k e TOT AL Nt'Mbi k FAGLS e
9079 17 USA /9079/A 1-4 g
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kl a 11us tertifwale h hsped to certif) that Ow packaging and stmtents described in hem $ lelon, snects Ow applashle safety standards set forth in Title 10.
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Code of f ederal Regulatums. Pan 71. *Pm Laging and Tramportatum of Raboacthe Material
- i b Than terurnale does put reheve the consigna frorn contharne with an) requirenent td the regulatnes of de U.S Ikpartrnent of Tranipatnike e e other N
applwat4r regulalor) agernees,irxtuding tfw genernment of ari) country through or into whwh the package mill be transprird Il i 3 THit 01 k1If1C AT111l',5UtD ON THI B A$ts OF A &AltTY AN AM515 kl.R)RT Of 11tl PACK AGE DLilGN OR APPtICATION N
a 151U1D10( Ana.e mad 4#esu b TITtt ANDIDLNTif1CA110N Of RLM>RT OR APft.lCATION hlMoltenMetalTechnology,Inc.
Nuclear Packaging Inc. application l
g 1009 Commerce Park Drive dated March 30, 1988, as supplemented.
, Oak Ridge, TN 37830 y
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Thn certifu sie is 6teditumal umm fulfilhng the requirernents of 10 CIR Part 71 as sppluable,and the t mJsilons erecified leton.
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(a)
Packaging l
(1) Modc1 No.: NUPAC 14D-2.0 (2) Description U
Steel encased, lead shielded cask for radioactive material. The cask is a d
right circular cylinder 81-1/2 inches high by 81-3/4 inches in diameter.
the d
I cask cavity is 73-3/8 inches high by 75-1/2 inches in diameter. The cask side 4
wall consists of a 3/8-inch thick inner steel shell, a 1-3/4-inch lead shell, N
and a 7/8-inch thick outer steel shell.
Each base is comprised of two, 2-inch 4
thick steel plates welded together to form a 4-inch thick base which is d
intergerally welded to the inner and outer steel shells of trie side wall. A d
steel flange is welded to the inner and outer steel shells of the side wall at G
the top. The lid is comarised of two, 2-inch thick steel plates, which are d
stepped and welded togetier to mate with the steel flange.
The cask closures d
are sealed by a Neoprene gasket located between the lid and steel flange, 4
positive closure of the lid is accomplished by eight rachet binders.
The lid I
contains a centrally located shield plug comprised of two, 2-inch thick steel u
plates and one,1-inch thick steel plate stepped and welded. The shield plug q
is sealed by a Neoprene gasket, and eight, 3/4-inch studs and nut are used to a
provide positive closure, q
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Tie-down is accomplished by four tie-down lugs welded to the cask body.
There ql are four cask lifting lugs, three lid lifting lugs, and one shield plug lifting a
lug. The package gross weight is approximately 48,000 poufids, a
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(3) Drawings q
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The Model No. NUPAC 14D-2.0 packaging is fabricated in accordance with Nuclear g
Packaging, incorporated Drawing No. X-20-2150, Revision C.
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(b) Contents a
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ip (1) Type and form of material u
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Process solids, either dewatered, solid or solidified, in secondary a
e, containers, and limited to the following:
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p, (1) Materials in which the radioactivity is essentially uniformly e
distributed and in which the estimated average concentration per gram 8l p
of contents does not exceed:
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O.0001 millicurie of radionuclides for which the A quantity in g
pl' Appendix A of 10 CFR Part 71 is not more than 0.05, curie; p
y 0.005 millicurie of radionuclides for which the A,ie, but not more l
quantity in A)pendix A of 10 CFR Part 71 is more than 0.05 cur g
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lp t1an 1 curie; or g
0.3 millicurie of radionuclides for which the A, quantity in Appendix U
l A of 10 CFR Part 71 is more than I curie.
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'l (ii) Objects of nonradioactive material externally contaminated with 8
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radioactive matuial, provided that the radioactive material is not l
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readily dispersible and the surface contamination, when averaged over p
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an area of I square meter, does not exceed 0.0001 mi.111 curie g
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(220,000 disintegrations )er minute) per square centimeter of g
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radionuclides for which tie A, quantity in Appendix A of p
10 CFR Part 71 is not more than 0.05 curie, or 0.001 mil 11 curie I
(2,200,000 disintegrations per minute) per square centimeter for E
other radionuclides.
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(2) Maximum quantity of material per package N
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Greater than Type A quantity of radioactive material which may contain d
fissile material provided the fissile material does not exceed the limits W
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in 10 CFR 671.53.
The weight of the contents and secondary containers 4
i shall not exceed 14,000 pounds and the internal decay heat load shall not d
g exceed 7 watts.
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>;,Page 3 - Certificate No. 9079 - Revision No. 17 - Docket No.
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(a) for any package containing water and/or organic substances which could a
8 radiolytically generate combustible gases, determination must be made by test g
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and measurements or by analysis of a representative package such that the g
8 following criteria are met over a period of time that is twice the expected y
e, shipment time:
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W, (l') The hydrogen generated must be limited to a molar quantity that would be g-1 9
no more than 5% by volume (or equivalent limits for other inflammable g
gases) of the secondary coptainer gas void if present at STP (i.e., no g
p, more than 0.063 g-moles /ft at 14.7 psia and 70'); or g
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(2) The secondary container and cask cavity must be inerted with a diluent to y
el' assure that oxygen must be limited to 5% by volume in those portions of g
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the package which could have hydrogen greater than 5%.
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'f for any package delivered to a carrier for transport, the secondary container y
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must be prepared for shipment in the same manner in which determination for gas y
l generation is made. Shipment period begins when the package is prepared g
el (sealed) and must be completed within twice the expected shipment time, y
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f (b)
For any package shipped within 10 days of preparation, or within 10 days after 8
venting of drums or other secondary containers, the determination in (a) above need not be made, and the time restriction in (a) above does not apply.
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Except for close fitting contents shoring must be placed between secondary 8
,1 containers and the cask cavity to prevent movement during normal conditions of 4
transport.
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8 The lid and shield plug lifting lugs must not be used for lifting the cask, and 8
g shall be cuered in transit.
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In addition to the requirements of Subpart G of 10 CFR Part 71:
ll (a)
Prior to each shi> ment, the packaging lid seals, if opened (or if security seal E
1 is broken), must )e inspected.
The seals must be replaced with new seals if t'
4 inspection shows any defects or every twelve (12) months, whichever occurs W
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first.
Cavity drain line and optional vent / test connection must be sealed with 4
li tppropriate sealant applied to the pipe plug threads.
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- i (b)
Each cask must meet the Acceptance Tests and Maintenance Program of Section 8.0 E
E of the application, in addition, the cask must be leak tested at least once E
ll every twelve (12) months in accordance with Appendix 8.4 of the application.
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(c) The package shall be prepared for shipment and operated in accordance with the t
h operating procedures of Section 7.0 of the application, a
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The cask body and each cask lid must be marked in accordance with 10 CFR $71.85(c).
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The package authorized by this certificate must be transported on a motor vehicle, di
$li railroad car, aircraft, inland watercraft, or hold or deck of a seagoing Vessel 5
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assigned for the sole use of the licensee.
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D Page 4 - Certificate No. 9079 - Revision No. 17 - Docket No. 71-9079 I
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12.
The package authorized by this certificate is hereby approved for use under the I
general license provisions of 10 CFR 671.12.
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B Expiration date: April 1, 1999. This certificate is not renewable.'
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W EEFERENCES E
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Nuclear Packaging, Incorporated application dated March 30, 1988.
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- lSupplementdated:
4 April 26, 1988; February 23, 1993; and August 5,1997.-
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FOR THE U.S. NUCLEAR REGULATORY COMMISSION t
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Cass R. Chappell, Chief 8
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Ip Spent Fuel Project Office 8
lp Office of Nuclear Material Safety n
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8 l'Date:
Septafor 18, tw7 s
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UNITED STATES j
,j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, o.C. 306E-0001 4,...../
APPROVAL. RECORD Model No. NUPAC 14D-2.0 Certificate of Compliance No. 9079 Revision No. 17 By letter dated August 5, 1997, VECTRA Technologies, Inc., and Molten Metal Technology, Inc., requested that the certificate holder for Certificate of Compliance No. 9079 for the Model No. NUPAC 140-2.0 package 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 design, and the quality assurance records in accordance with 10 CFR 671.01(c). Molten Metal Technology, Inc., stated that the records required by 10 CFR 671.91(c) for the package design will be maintained at their document control center at 1556 Bear Creek Road, Oak Ridge, Tennessee. Molten Metal Technology, Inc., has been 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 Holten Metal Technology, Inc., as certificate holder.
These changes do not affect the ability of the package to meet the requirements of 10 CFR Part 71.
p Cass R. Chappell, Chief Package Certification Section Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Date:
w. 18. 1o97 l
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