ML19274F840
| ML19274F840 | |
| Person / Time | |
|---|---|
| Site: | 07109132 |
| Issue date: | 07/25/1979 |
| From: | Mcdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Simchuk J NUCLEAR PACKAGING, INC. |
| References | |
| NUDOCS 7908150732 | |
| Download: ML19274F840 (3) | |
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NUCLEAR REGULATORY COMMISSION y
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WASHINGTON, D. C. 20555
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p JUL 2 51979 FCTR: RHO 71-9132 Nuclear Packaging, Inc.
ATTN: Mr. John D. Simchuk 1733 South Fawcett Tacoma, WN 98402 Gentlemen:
This refers to your application dated October 20, 1978, as amended, requesting approval to deliver the Model No. T-3 packaging to a carrier for transport.
In connection with our review, we need the information identified in the enclosure to this letter.
Please advise us within thirty (30) days from the date of this letter when this information will be provided. The additional information requested by this letter should be submitted in the form of revised pages to the original Safety Analysis Report in order to preserve the continuity of your application.
If you have any questions regarding this matter, we will be pleased to meet with you and your staff.
Sincerely, h
Charles E. PacDonald, Chiet Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS
Enclosure:
As stated 7008150 N ~
JUL 2 51979 Enc 1. ltr dtd:
Nuclear Packaging, Inc.
Model No. T-3 Packaging Structural 1.
The evaluation of the one-foot free-drop test (Section 1.6.6) should be revised to consider the following items:
Show that containment vessel stresses due to impact, when combined a.
with those caused by temperature and pressure, are within the limits specified in Section 1.1.2.
b.
Evaluate the containment vessel stresses for a side impact that does not occur onto the trunnions. Revise the analysis of corner impact to include the effects of both the axial and the lateral load components.
Show that the impact limiters would remain attached to the cask c.
under corner and oblique impact orientations and for side impact onto the trunnions.
d.
Revise the ar.alysis of end and corner impact to consider the containment vessel stresses caused by lateral pressure from the lead shielding. Revise the analysis of side impact onto the trunniens to consider the pressure (if any) that would be exerted on the containment vessel by the lead which backs the trunnions.
2.
The evaluation of the 30-foot free-drop test (Section 1.7.1) should be revised to consider items a, b, c, and d in Question 1, above.
Note that the evaluation of the 40-inch puncture test is predicated upon the impact limiters being in place (i.e., item lc).
3.
The evaluation of the closure plate under 30-foot side drop cor litions (Section 1.7.1.2.2, page 1-92) does not adequatcly show that the plate would remain attached. Note the closure plate was considered to be in place during the subsequent puncture test. The evaluation should be revised to consider the following items:
a.
The calculation to estimate the maximum impact force on the closure plate (p 1-93) did not consider strain-hardening of the material.
b.
The analysis did not justify the appropriateness of using the full 181 in.2 area of the lid step to calculate shear stress.
Also, the analysis did not evaluate the stresses in the step at the end of the cask, which provides a reaction force for the closure plate.
2_
The analysis did not evaluate bearing stresses between the lid c.
step and the step at the end of the cask.
d.
The analysis did not show that sufficient clearance was provided to prevent the bolts from being loaded by lateral displacement of the closure plate.
4.
Evaluate the stresses that would occur in the containment vessel shell under 40-inch puncture test conditions. Show that these stresses, when combined with those caused by temperature and pressure, are within the limits specified in Section 1.1.2.
5.
Show that the containment vessel shell would not buckle under the normal and accident tests specified in 10 CFR Part 71 or during fabrication (e.g., lead pour). Revise the containment vessel drawings to include the tolerances that will be used to assure the containment vessel, after fabrication, is the intended size and form (e.g., diameter, roundness, straightness, or cylindricity).
6.
The fatigue analysis of the bolts should be revised. Note that the fatigue life taken from Table I-9.4 of the ASME code appears to be incorrect for tho end closure bolts (pg 1-66), the containment closure bolts (pg 1-6d), and the push rod (pg.1-6e).
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