ML20039A317

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Forwards Proprietary Revision 2 to SAR for HN-100 Series 3 Radwaste Shipping Cask. Withheld (Ref 10CFR2.790).Seven Oversize Drawings Encl.Aperture Cards Are Available in PDR
ML20039A317
Person / Time
Site: 07109151
Issue date: 11/27/1981
From: Mallory C
HITTMAN NUCLEAR & DEVELOPMENT CORP. (SUBS. OF HITTMAN
To: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML19268A565 List:
References
19966, HN-E556, NUDOCS 8112170215
Download: ML20039A317 (3)


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Subject:

llNDC IIN-100 Series 3

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Application for Certificate liance

Reference:

NRC Letter dated November 13, 1981 FCTC: RHO 71-9151

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Dear Mr. MacDonald:

Attached are eight (8) copies of the following documents which have been revised to include the information requested in the referenced NRC letter.

(1)

" Safety Analysis Report for the HN-100 Series 3 Radwaste Shipping Cask", Revision 2.

(2) liittman Nuclear & Development Corporation Drawings Fos. :

C001-5-9138, "rv. 2; C001-5-9139, Rev. 1; C001-5-9140, Rev. 1; C001-5-9141, Rev. 1; C001-5 oi43, Rev. 2; and C001-5-9144, Rev.

1.

Attachment A contains a listing of the changes that have been made in these documents in response to the ref erenced letter.

As previously requested, the Certificate of Compliance should be similar to Certificate No. 9079, with the changes noted in the attachment to our

.une 11, 1981 letter.

In addition, the certificate should specify that the cask will be constructed of A516 Grade 70 steel and the steel used in the outer shell shall have a minimum yield strength of 49,000 psi.

An early review of this revised application and issuance of a Certificate of Compliance will be appreciated.

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Attachments

fi ATTACHMENT A HNDC HN-100 Series 3 Packaging Docket No. 71-9151 Responses to Questions in Enclosure to NRC Letter Dated November 13, 1981 General The attached drawings C001-5-9138, Rev. 2; C001-5-9139, Rev. 1; C001-5-9140, Rev. 1; C001-5-9141, Rev. 1; C001-5-9143, Rev. 2; and C001-5-9144, Rev. 1, have been revised as follows.

1.

A note has been added to drawing C001-5-9139 to specify a minimum yield strength of 49,000 psi for the outer shell material.

The material is specified as ASTM A516 Grade 70 steel. The specification requires tensile testing to conform with ASTM specification A-20 and ASTM spec-ification A370.

2.

The material and dimensions of the stop to protect the lid gasket lave been included on drawing C001-5-9138.

3.

Drr, wing C001-5-9139 has been corrected to show the gasket on the inside of the guide pins (Item 9) with the stop on the outside. This will provide a seal between the inner cavity and the outside atmosphere including the guide pin holes.

4.

The type and sizes of welds on the lif t lugs and tiedown lugs on drawing C001-5-9143 have been shown using standard weld symbols of the American Welding Society.

5.

A note has been added to specify that the welding shall be done inaccordance with ASME Section IX.

6.

The items on drawings C001-5-9143 and C001-5-9144 have been cross referenced to the other drawings.

7.

The Certificate of Compliance should reference the following drawings:

"Hittman Nuclear & Development Corporation Drawing Nos: C001-5-9138, Rev. 2; C001-5-9139, Rev. 1; C001-5-9140, Rev. 2; C001-5-9141, Rev. 1; C001-5-9141, Rev. 1; C001-5-9142, Rev. 0; C001-5-9143, Rev. 2; and i

C001-5-9144, Rev. 1".

Structural 1.

An analysis has been x!ded (page 32) to show that the shackle connecting the tiedown cables to the lug will fail before the cask experiences any I

damage or loss of packaging effectiveness. The lug is designed for a j

tension over two times that of the shackle. If the cask arrangement experiences excessive loads the cask integrity will not be compromised.

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,j__ o e Attachment A Page 2 November 27, 1981 2.a. The analysis which assumes the tiedown lugs are used as lifting lugs has been redone (page 7).

The twisting momert equal to the lifting force times the offset distance f rom the shear center has been added to the bending moment and shear stresses. The resultant stress is 6013 psi with a Factor of Safety of 1.02.

b. In Section 3.1.4.2, the numbers "75.95" and "12.48" were typographical errors and have been changed to "69.8" and "12.0", respectively.

The correct numbers had been used in the calculation and the resulting cable tensions remain a s shown.

.. In Section 3.1.4.4, where the moment resistance of the welds was taken is more conservative than by computing it about the neutral axis. The moment arm is considered two inches which is twice the one inch to the neutral axis. The analysis has not been changed to maintain its present cons ervativeness.

3.

The one foot free drop was recalculated using finite element analysis, (pages 33 through 37).

Incremental velocities, impact times, and the resultant g forces due to decelleration were found. The maximum incremental g force calculated for a bottom corner drop at a 450 angle is 38.5 g's.

Based on this, the shear stresses for lower outer circum-ferential weld, as a result of the drop, were less than the minimum yield for their respective material. The stress in the outer shell due to the drop was found to be less than 2000 psi and buckling would not occur. This is not included in the analysis.

4.

In conjunction with Item 3 above, finite element analysis was applied to the cask falling on its lid for three orientations. They are based on impact on top one inch flat of the lid, (page 39), Unpact on top long flat of the lid, (page 44) and impact on the cask side on a ratchet binder with all energy being absorbed by the edge of the lid, (page 37).

The maximum g force on any of the orientations is 13.7 g's.

In all cases the ratchet binders were examined to ensure that they maintain the integrity of the cask and be able to absorb the decelleration of the contents. Although all eight were not accounted for, (six accounted for in the large flat, and seven for the short flat and edge drops), the remaining binders are capable of absorbing the decelleration forces and maintaining closure integrity.

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