ML20062E364

Forwards Request for Addl Info Needed for Review of 771102 Applications for Approval of Model 44

ML20062E364
Person / Time
Site:	07105097
Issue date:	07/23/1982
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Prichard R ENERGY, DEPT. OF
References
NUDOCS 8208090331
Download: ML20062E364 (2)

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{ggL NM FCTC:RH3 CRMarotta 71-5097 NMSS R/F FCTC R/F U.S. Departnent of Energy ATTil: ifr. Reuben P. Prichard l'S E-201 Washington, DC 20545 Centlenen:

This refers to your application dated f*ovember 2,1977, requesting approval of the l'odel No. I'.odel 44 packaging.

In connection with our review, we need the infomation identified in the enclosure to this letter.

Please advise us when this inforrc.ation will be provided. The additional information requested by this letter should be submitted in the forn of revised pages. If you have any questions regarding this tratter, we would be pleased to neet with you and your staff.

Sincerely, Original Signod by CHARLES E. MACD0:lALD.

Charles E. I:acDonald, Chief Transportation Certification Branch Division of Fuel Cycle and l'aterial Safety,ImSS

Enclosure:

As stated cc v/ encl:

U.S. Departnent of Energy ATTil:

l'.r. R. J. Hart, ranager Oak Ridge Operations Office P.O. Box E Oak Ridge,-Tli 37830 8208090331 spo723 PDR ADOCK 07105097 C

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_OF_FICI AL___ RECORD COPY

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U.S. Department of Ensrgy fiodel 11o. Ilodel 44 Packacing Docket No. 71-5097 JUL 2 31982 Enc 1 to ltr dtd:

STRUCTURAL l.

The package skids should be shown to neet the requirements of 10 CFR 571.31(d)(2).

2.

Drawing of the inner containment vessel should clearly show all safety features (i.e., welds (including seam)). !!aterial properties (specifications) for the foamglass filler tested should be included on the drawing. Drawing and revision numbers should be shown on the drawing.

3.

For a 30-foot side drop onto the drua, show that the 9-inch diameter hole in the center of the package (cut-out in drums) will not cut or pierce the 12-gauge inner containment vessel.

4.

For the puncture test, show that a drop between the skids directly i

onto the center weld of the package (location of cut-vent) that

" beam like" failure of the package will not occur and the containment vessel will not be cut or pierced.

CRITICALITY The fifth paragraph on page 6 of the SAR states that the aluminum tubing is not required for nuclear criticality safety reason.

Independent calculations indicate the containment vessel would be critical (10 CFR $71.33(a)(2))

without the aluminum tubes. Also consideration should be given to effects on nuclear criticality safety of shipments containing less than t

44 fuel rods and increased moderation between rods.

OPERATING PROCEDURES. TESTS AND ffAlf(TENANCE

!!uclear criticality safety for the array is based on the containment vessel remaining leak tight during normal and accident conditions of transport. The drawing of the package (Figure 2) states that:

(1) At the time of fabrication, the inner vessel will be bubble leak tested for 10 psi over a one (1) hour period.

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(2) A new gasket will be used for each shipment.

Item 3 on page 17 indicates the welds on the inner vessel will be tested by pulling. The procedures should be revised to require a leak test following this operation. Also, the inspection form on page 21 should i

be revised to include:

(1) A new gasket gasket for each shipment.

i (2) Torquing of the closure bolts (specified value).

(3) Annual leak testing of the inner vessel.

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OFFICIAL RECORD COPY j