ML20151A564
| ML20151A564 | |
| Person / Time | |
|---|---|
| Site: | 07109193 |
| Issue date: | 03/31/1988 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20151A559 | List: |
| References | |
| NUDOCS 8804070080 | |
| Download: ML20151A564 (4) | |
Text
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CERTIFICATE OF COMPLIANCE y
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Nuclear Energy Services, Inc.
Nuclear Energy Services, Inc. application dated l
Shelter Rock Road June'18, 1984, as supplemented.
p, Dant'ury, CT 06810 l
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71-9193 l
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(a) Packaging e7
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W (1) Model No.: 'NES-5 _
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p (2) Description T
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Steel encased lead shielded package (dask) for radioacti've waste.
The y
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l cask is a right circular t.ylinder with a 34-inch ID by 63-inch IH cavity.
The walls of the cask contain a lead thickness of 5.75 fnches g
g, encased in 0.5-inch thick irner steel.shell.and 1.0-inch thick outer i
IlI steel shell. The exposed' sides of. the package are provided with a i}
R thermal barrier censisting of a 16-gauge wire wrap on 6-inch centers E
and covered with 0.25-inch thick steel iacket.
The 0.5-inch thick
[i (inner) and 1.0-inch (outer) thick bottom steel plates encase 6.25-l g'
inch thick lead shielding. The stepped top shielding cover has 0.5-l' inch thick inside steel plate and'1.75-inch thick outside steel plate (l
I separated by 6.25-inch thick lead.
The cover is secured with twelve
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(j equally spaced 1-1/2-inch closure bolts and a solid silicone flat I
The cask is provided with sealed drain and vent lines.
The top and bottom'of the cask is hrovided with steel encased, rigid l
h polyurethane fcam impact limiters.
The irpact limiters are secured to j
tl each other about the cask with six,1-3/8-inch ratchet binders.
The g
ll impact limiters are 82.5 inches in diameter and the gross height of
,g the package with the impact limiters attached is 112-3/8 inches, gj The package is provided with four tie-down and four lifting devices.
1; The gross weight of the packaging and centents is approximately 51,000 g
pounds.
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(3) Drswings The packagire is constructed in accordance with Nuclear Energy Services, f,
i Inc., Drawirig Nos. 83E0337. Rev. 6; 83E0338, Rev. 6; and p
If 83E0339. Rev. 7.
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PDR ADOCK 07109193 xxxub ammr rv zwmm*YwiViF2525**Vi***"A
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l ll Page 2 - Certificate No. 9103 - Revision No. 5 - Docket No. 71-9193 l
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5.
(Continued) l l!
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(b) Contents l
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(1) Type and fonn of material i
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i (i) Process solids, either dewatered, solid or solidified contained i
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II within a sealed secondary container (s); or II I
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[.7 p (ii) Irradiated di1[d'veactor. ndompdndntscontainedwithinasecondary l
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contai(er(s).
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(2) MaximumquNt i
V ' y of material per package
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1 Greater than Type A quantity of radioactive materia.hwhich may contain h
I fissile,raterial provided the fissile material-dpes not exceed the a
limith in 10 CFR 671.53. The contents may not exceed 2,000 times Type l
l A cuantity, a decaf. heat generation of 300 watts, and 1.0.000 pounds I
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including weight of, the contentsp' secondary container hnd shoring.
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As needed, appropriate shoring must be use(d in the :ask cavity' to limit movem
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of the secondary container during-accident condition of transport, p
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t The cask. cover must be secured by twelve,1-1/2"-8 (JNC x 4-}f4" long bolts w t
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gl' flat washer torqued to 300 foot-lbs :t 10% (lubricated).
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8.
Prior to each shipac'nt, the I.eak Test Procedure described 'in Section 8.3 of the a
f application must be performed.
No package-isi o be delivered to a carrier for t
t transport with a detectable. leak usingxthe method of Section 8.3.
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9.
(a) For any package containing w'ater'and/or o'rganic sub' stances which could I
I radiolytically generate combustible gases, deternination must be made by
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I tests and measurements or by analysis of a representative package such that a
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the following criteria are met over a period of time that is twice the p
lg expected shipment time: /
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I (i) The hydrogen generated must be limited to a molar quantity that would l
N be no more than 5% by volume (or equivalent limits for other inflam-l mable gases) of the secondary contaiger gas void if present at STP g
(i.e., no more than 0.063 g-moles /ft at 14.7 psia and 70'F); or t
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(ii) The secondary container and cask cavity must be inerted with a diluent f
ll to assure that oxygen must be linited to 51 by volume in those portions [
[i of the package which could have hydrogen greater than 5%.
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Page 3 - Certificate No. 9193 - Revision No. 5 - Docket No. 71-9193 j
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0 9.(a)
(Continued) l lti For any package delivered to a carrier for transport, the secondary
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container must be prepared for shipment in the same manner in which i
determination for gas generation is made.
Shipment period begins when p
the package is prepared (sealed) and must be completed within twice the p
expected shipment time.
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(b)
For any package containingMa&riils with radioactivity concentration not exceeding thatforj-low spe'cific 'sctivity material, and shipped within l
10 days of preparation, or within 10 da s after venting of drums or other p
secondary contain~ers, the detennination in (a)/above need not be made, and a
the time res'triction in (a) above does not apply.'Q 8
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10.
In addition to the requirements of Subpart G of 10 CFR'Pprt,71:
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a (i)
Each package must~ meet the acceptance tests"and be main,tained in accordance a
with'the Maintenance Program of Sectiop)'8'of the application; and I
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8 The' flat lid gasket must be replacedfannually. The test 8;
(ii) line.sealsmustbereplacedbeforeeachloadedshipment.fortanddrain p__. aj,,'
- 11. The package authorized by this certificate'is hereby' approved for use under the L
l general license provisions of 10 CFR 571.12, '
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12.
Expiration =date: ~, Ja nua ry 31 -1990; } } l [:
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REFERENCES
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Nuclear Energy Services, Inc. applic~ation daMd' June 18,(1984.g i
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Supplerents dated: Aucust 24 and October 5, 1984; Janua'ry 4 and 25, and March 22, 1985; September 11, 19871 and January 11 and March 7, 1988.
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'[F,0R'THEV.S.NUCLEARREGULATORYCOMMISSION t-l t
44 4
I Charles E. MacDonald, I..I r
Transportation Branch I
l Division of Safeguards and i
Transportation, NMSS l-i
{
Date:
MAR 311968
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0, UNITED STATES l'
'4 NUCLE AR REGULATORY COMMISSION
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' Revision No. 5 l
I By application dated September 11, 1987, as supplemented January 11 and March i
- 7. 1988. Nuclear Energy Services. Inc. requested that the Certificate of Compliance No. 9193 be amended to incorporate the latest revision of the follo @ c packaging drawings:
Drawing Nos. 83E0337. Rev. 6; 83E0338. Rev. 6; and 83E0339, Rev. 7.
c The packaging drawings have been revised to provide for alternate construction l
details (e.g., velds) and some options on the materials of construction.
These t
changes are the result cf the experience gained during the fabrication of the first cask.
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The alternate construction details and optional material specifications have l
been reviewed and it is concluded that these options have no significant i
effect on the ability of the package to meet the recuirements of 10 CFR Part 71.
Y CharksE.MacDonald,rytef w
Vransportation Branch Division of Safeguards and Transportation. NMSS i
Date:
M 31 M J
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