ML20211H002
| ML20211H002 | |
| Person / Time | |
|---|---|
| Site: | 07109181 |
| Issue date: | 06/02/1986 |
| From: | Temus C NUCLEAR PACKAGING, INC. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 27057, BBB5960, NUDOCS 8606200417 | |
| Download: ML20211H002 (19) | |
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'06 J"N -5 A10:49 June 2, 1986 File:
PAS-2 Ref: BBB5960 Mr. Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. MacDonald:
Enclosed please find eight copies of the revised pages to convert Revision 4 of the NuPac Safety Analysis Report to Revision 5.
These revised pages are merely Revision. E of drawing X-20-220D.
Also enclosed is a check for $150 to cover the cost of a minor amendment to the certificate of Compliance.
The proposed change is very minor.
The drawings controlling the
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configuration of the cask have been revised slightly to remove ambiguous dimensions and to clarify the controlling requirements.
None of the proposed changes to the drawing are significant to the ability of the cask to meet the requirements of 10 CFR 71.
To facilitate your review, I have enclosed a copy of our Document Change Notice governing the rev'isions to the drawing.
The pro-posed changes are given item numbers in the DCN.
Item number 1 changes the offset of the shield penetrations from.58 inches to 0.47 min./ 0.5 8 max.,
thereby defining the tolerance for this dimension.
Item 2 changes the way that the shi' ld penetrations e
are dimensioned to avoid undesirable dimensional problems in conjunction with the tolerance defined in Item 1.
Item 3 relaxes an implied tolerance on the diameter of the shield.
The change shown in Item 4 clarifies that the 4.00 dimension refers to the thickness of the bottom of the foam in the inner overpack.
Item 5 allows a chamfer in the foam of the inner overpack to allow easier installation of the closure bolts in the secondary con-tainment vessel.
Item 6 allows the removal of an unnecessary recess in the end of the lower shield plug, improving the ALARA shielding performance of the packaging.
None of those changes aff ny of the analyses or text in the Safety Analysis Report.
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h@Yr; June 2, 1986 Mr. Charles E. MacDonald NRC Page 2 While we acknowledge that these changes are very minor, we wish to avoid any possible future problems arising f rom the ambigui-ties in our previous drawing revision.
If you have any questions, please do not hesitate to call either myself or Stephen Goetsch.
Thank you very much.
Very truly yours, NUCLEAR PACKAGING, INC.
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Charles J. Temus Technical Director CJT/sdg Enclosures
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1010 South 336th Street Federal-Way, Washington 98003 June 3,.1986 O
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