ML20128B581

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Forwards Response to 850517 Request for Addl Info Re Application for Certificate of Compliance 9192 for Model AP-300.Rev 5 to SAR Encl
ML20128B581
Person / Time
Site: 07109192
Issue date: 06/12/1985
From: Jerome Murphy
ANEFCO, INC.
To: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20128B585 List:
References
25372, NUDOCS 8507030292
Download: ML20128B581 (6)


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ANEFCO INC. ZNJ!soo. ce877 203 42 m asa

'85 JUN 14 A10:39 fN June 12, 1985 h

WO 4 39as US Nuclear Regulatory Commission Transportation Certification Branch Division of Fuel Cycle and Material Supply Washington, D.C.

20555 Attention: Charles E. MacDonald, Mail Stop 396 SS

Subject:

Model AP-300 Type A Package Docket No. 71-9192

Dear Mr. MacDonald:

This in in response to questions in your letter, dated Fby 17, 1985, in which you requested additional information on our '. application for Certificate of Compliance for our Model AP-300 Shipping Container. We have responded to your questions and have made the appropriate revisions in the text of our Saftey Analysis Report.

Enclosed are the ANEFC0 responses to the questions related to the structural aspects of the report, the shielding requirements and the Acceptance Tests, Section 8.

Also enclosed are eight (8) copies of the complete SAR, Revision 5.

We have added a segmented toroidal ring to absorb the energy of an assumed one foot drop. Consequently, we have revised both the text and 6e appropriate drawings.

We appreciate your comments and hope our responses meet with your approval, so that we may be granted a Certificate of Compliance at your earliest convenience.

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e ANSWERS Revision 5 Page 1 STRUCTURAL 1.

On Drawing No. 133-1, Rev. 3, the required number of parts B-8 (lifting pad) should be four rather than one as shown.

Part B-8, lifting pad, has been deleted from the ANEFC0 Cask AP-300 in this revisionof the SAR.

Part 10, formerly used as a tie-down pad, is now utilized as the combination lifting and tie-down device and is analyzed in revisions to Section 2.4.3.1, pp. 2.4-2 through 2.4-5.

Part B-8 is now assigned to the segmented toroidal ring which is discussed in the response to question 3, below.

2.

Section 2.4.4 - Tie-Down Devices a.

Since the tie-down cables can resist tensile force only, the analysis should not assume the resultant force is equally distributed to all four tie-down lug.s.

The maximum tie-down force acting on one lug should be derived on equilibrium condition considering the angles between the tie-down cable with the vertical and the direction cf travel and also the reaction force of the chocking ring at the base of the cask.

The analysis has been revised and assumes that the resultant force is distributed to two of four tie-down lugs. The analysis in Section 2.4.4.5.2, pp. 2.4-12 and 2.4-14, shows that the tie-down pad design provides capacities in excess of allowable values.

b.

For fillet welds, the effective throet area should be used (see p2.4-12).

The calculation on page 2.4-12 has been revised. An effective throat depth of 0.53 inches has been used for the 0.75 inch fillet welds, Page 2.4-14 states that the tie-down lugs are welded to the cask body c.

using full penetration weld all around. Drawing No. 138-1, Rev. 4, however, shows 5/8" fillet weld all around. Please clarify the size and type of welds for the tie-down lugs.

The text on page 2.4-14 has been revised and states that a 3/4" fillet weld all around will be used to weld the tie-down lugs to the cask body. Drawing No. 138-1, rev. 5 shows a 3/4" fillet weld all around.

3.

The evaluations of the top end drop'is not adequate.

Since the cask lifting lugs are stronger than the welds attaching the lugs to the cask, the lugs would be sheared off rather than cru.shed. Therefore, the analysis should show that the lid closure bolts can sustain an impact force large enough to shear off the lugs without damage.

For simplicity, the analyses may use a dynamic load factor of two against the static value of the lifting lug weld capacity to simulate an impact condition. After the cask lifting lugs are sheared off, the cask will then impact on the lid lifting lugs (See Drawing No. 133-1, rev. 3).

It would be necessary then to show that the lid would not deform significantly under this secondary impact condition and that the cask would remain scaled.

The ANEFC0 AP-300 cask will be lifted by four combination lift / tie-down lugs that are analyzed in Section 2.4.3.1 for their lifting capabilities and in Section2.4.4.5 for their tie-down capabilities. The cask lifting lugs and lid lifting lugs have been deleted f rom 6e cask. The revision of the cask lifting system is described in

ANSWERS Revision 5 Page 2

3. Continued Section 2.4.3.2.

Four l\\" diameter threaded eye bolts will be used to lift the cask lid.

These will be threaded into the cask lid before the lid is moved.

Four ik" diameter threaded hexagonal head bolts will occupy the spaces provided for the eye bolts, when the latter are not in use.

The evaluation forithe top end drop have been revised in Section 2.6.7 page 2.6-13 The energy arising from a one foot drop will be absorbed by a segmented toroidal ring, 2\\" 0.D. x \\" thick, which will be welded to the top of the outside shell of the cask.

As shown on page 2.6-13, the one foot drop will cause a 0.72" deformation in the ring, and result in a "g" load of 16.7.

The capacity of the lid bolts to withstand the "g" load for the corner drop and vertical drop are shown in Sections 2.6.8.1.1 and 2.6.8.1.2.

Calculations on page 2.6-14 show that the lid can resist a "g" load of 333 for the bottom drop with a safety faucor in excess of 5.

4.

For the Heli Coil inserts, show explicitly how the bolt thread length, the overall bolt length, the insert length, and the full tapped depth are selected based on the strength of the base material and the bolts.

Section 2.6.8.1 describes the bolting design and Figure 2.6-3 shows the tensile strength of the heli coil assembly insert as furnished by the manufacturer. The selection of the bolt specifications is based on having the bolt yield before either the insert or ring material.

5.

The response to our question regarding the corner drop is not adequate.

Provide the following information:

a.

Since the cask is constructed by thin _ plates and shells filled with lead, it is not reasonable to assume thatE all cask deformation will be crushing of steel without any indenti6n or flexure. The applicant should show (by clastic analysis) that the cask indention or flexure deformation is insignificant when the cask is subjected to the impact force associated with the corner drop so that the lid will remain sealed.

As indicated in response to question 3, the energy associated with the one foot dro p of the ANEFC0 AP-300 cask will be absorbed by the segmented toroidal ring, welded to the top of the cask outside shell. As indicated in the Cask Designer's Guide ORNL-NSIC-68, page 66, the toroidal shell-type energy absorber operates properly, regardless of the angle at which the cask impacts on a horizontal surface.

b.

On page 2.6-17a, it appears that the equivalent "g" load has been resolved into vertical (parallel to cask axis) and horizontal (perpendicular to cask axis) components. Thus, there is no justification to further reduce the moment arm by mulitplying sin 40.28' to the cask radius.

It is also noted that the analysis has not combined the effects of tension and shear on the bolts. These factors should be considered in analysis.

The "g" load used in the revision to page 2.6-17a is not a resolved value.

ANSWERS R:. vision 5 Pag: 3 6.

The evaluation for the bottom drop condition is not adequate. Provide an analysis to show that the lid would not have significant deformation due to the large equivalent "g" load associated with the bottom end drop so that the cask would remain sealed.

The revision to page 2.6-14 shows that a "g" load of 333 will occur.under the 1 foot bottom drop condition.This force will be distributed over the 2.5 inch lip of the lid. The resulting stress is lower than the yield strength of the lid material by a factor of 5.87.

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Revision 5 o

a ANSWERS Page 4 Shielding Provide a shielding analysis demonstrating the package can transport 150 thermal watts of radioactive material.

The ANEFC0 AP-300 cask is to be licensed to carry 20,000 lbs of radioactive material,.not to exceed 20 curies of Cobalt-60. Co-60 emits two gammas, 1.33 and 1.17 Mev for each disintegration. Therefore, 20 curies of Co-60 generate heat at the following rate:

0

-1 20 Ci x 3.7 x 10 dis.

x 1.602 x 10 watt sec x 2.5 Mev

= 0.296 watt sec-Ci Mev dis The maximum heat that will be generated in a loaded AP-300 cask will be 0.296 watt.

The AP-300 cask has been analyzed to show that it can dissipate 150 thermal watts.

The following revisions have been made:

Section 1.2.2 states "The decay heat generated by 20 Ci of Co-60 is less than 1 watt and the heat dissipation capacity of the cask has been calculated to be in excess of 150 watts."

Section 1.2.3.1 states " Decay heat of contents will be less than 1 watt".

Acceptance Tests and Maintenance Program In Section 8.2.2, provide an acceptance criterion for the annual 1x10~ atm-cc/sec helium leak test.

The following has been added to section 8.2.2:

"If leakage in excess of 10 cc/hr is detected, the gasket will be replaced and the leak test will be repeated until acceptable results are obtained."

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REVISION 5 - 6/11/85 INSERT PAGES REMOVE PAGES rawings 33-1.1-1 y.2 2 1.2-2 1.2-4 Drawings No. 133-1 136-1 1.2-4 1.2-5 134-1 138-1 1.2-5 136-1 151-1 2.1-1 137-1 2.1-1 2.3-1 138-1 2.3-1 2.4-la 151-1 2.4-2 2.4-lb 2.4-2a 2.4-2 2.4-3 2.4-3 2.4-4 2.4-4 2.4-5 2.4-4a 2.4-6 2.4-5 2.4-7 2.4-6 2.4-9 2.4-7 2.4-11

' 2.4-7a 2.4-12 2.4-9 2.4-13 2.4-11 2.4-14 2.4-12 2.6-13 2.4-13 2.6-13a 2.4-14 2.6-13b 2.6-13 2.6-14 2.6-13a 2.6-15 2.6-14 2.6-16 2.6-15 2.6-17 2.6-16 2.6-17a 2.6-16a 2.6-17b 2.6-17 2.6-18 2.6-17a 2.6-19 2.6-17b 2.6-20

.2.6-18 2.6-22 2.6-19 3.1-1 2.6-20 7.1-2 2.6-21 7.1-3 2.6-22 7.1-4 3.1-1 7.1-5 7.1-2 7.1-6 7.1-3 7.2-2 7.1-4 7.2-3 7.1-5 7.3-2 7.1-6 7.3-3 7.1-7 7.3-4 7.2-2 7.4-7 7.2-3 7.4-8 7.3-2 7.3-3 8.2-1 7.3-4 7.4-7 7.4-8

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