ML20032A606
| ML20032A606 | |
| Person / Time | |
|---|---|
| Site: | 07109151 |
| Issue date: | 10/20/1981 |
| From: | Mallory C HITTMAN NUCLEAR & DEVELOPMENT CORP. (SUBS. OF HITTMAN |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20032A607 | List: |
| References | |
| 19820, HN-E548, NUDOCS 8110300464 | |
| Download: ML20032A606 (4) | |
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Refer to:
2 Colurabia. Maryland 2C45 HN-E548 t\\ -
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6 Mr. Charles MacDonald, Chief Transportation Branch 4
U.S. Nuclear Regulatory Commission
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Subiect:
UNDC HN-100 Series 3 V
4 Radioactive Materials Package g
g Application for CertJficate of Compliance
Reference:
NRC Letter dated September 22, 1981 FCTC: RHO 71-9151
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 1.
(2) Hittman Nuclear & Development Corporation Drawings Nos.
C001-5-9138, Rev. 1: C001-5-3140, Rev. 1; and C001-5-9143, Rev. 1.
Attachment A cont ains a listing of the changes that have been made in these documents.
As previously requested, the Certificate of Compliance should be similar to Ccrtificate No. 9079, with the changes noted in the attachment to our June 11, 1981 letter.
In addition, the certif teste 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 will be appreciated. If you have any questions, or require additional information, please contact me.
Very truly yours, 4'
C arles U. F ory f*
Vice Presid
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ATTACHMENT A HNDC HN-100 Series 3 Packaging docket No. 71-9151 Responses to Questions in Enclosure to Letter Dated September 22, 1981 Drawings The attached drawings: C001-5-9138, Rev. 1; C001-5-9140,-Rev. 1 and C001-5-9143, Rev. 1, have been revised to _ include closure and seal dimensions, tolerances, bolts, nuts, thread engagements, _ ratchet binders, and materials of construction. The other drawings have not been revised. The Certificate of Compliance should reference the following drawings:
"Hittman Nuclear & Development Corporation Drawings Nos. :. C001-5-913E, Rev. 1; C001-5-9139, Rev. 0; C001-5-9140, Rev. 1; C001-5-9141, Rev. 0; C001-5-9142, Rev. 0; C001-5-9143, Rev.1; and C001-5-9144, Rev. 0."
Structural 1.
The tiedown lug weld has been increased to one inch,.(see drawing C001-5-9143). In the weld. stress evaluation, (see page 19), only the weld on the tiedown lug has been considered. No credit is.taken for the weld on the attached lift lug.
The allowable shear stress has been reduced to 22,800 psi or 60 percent of the minimum tensile yield strength. The saf ety factors have' been recalculated on this basis.
2.
The righting moment due to the weight of the cask has been removed from the calculation of the tension' in the tiedown cables, (see pages 15 and 16), to make the analysis more' conservative. The offset
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distance of 2.75 inches used in the prior analysis did not include the thickness of the reinforcing plate. The correct value of 4.25 inches is used in the revised report, (see page 21). This results in a maximum stress in the shell of the cask of 46,200 psi. The yield strength of the three casks now being built ranges from 49,800 to 51,700 psi, (see Attachment B).
On future casks in this series, A516 Grade 70 steel with a minimum yield strength of 49,000 psi will be specified which will exceed the stress in the shell under the 10, _5 and 2 g condition. The certificate of compliance should include the minimum yield value for the shell of 49,000 psi.
3.
A side drop on a ratchet binder has now been included in the one foot drop evaluation, (see pages 37 and 38). The binder will-be damaged but the remaining seven binders will be adequate. An analysis of the forces on the ratchet bi.nder due to decelleration during a top corner drop has been included.
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. ATTACHMENT A 71-9151 Thermal Evaluation The' thermal heat generated by che maEimum allowable contents with either Cobalt 60 or Cesium 137 is negligible, (see page 39).
Containment The analysis shows that the elongation of the ratchet binder due to an internal pressure of 7.5 psig will be much less than the initial deformation of the gaskets, (see pages 40 through 42).
Acceptance Tests The tests and other requirements for acceptance of the casks' have been included,- (see page 44).
Maintenance Program The operations -and maintenance program including periodic inspections has been included, (see pages 43. and 44).
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TEST CERTIFICATE P. O.
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Refer to:
HN-E518
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@ Of e, l9 $N Mr. Dick Odegaarden Transportation Branch
)C7ig U.S.-Nuclaar Regulatory Commission Washington, D. C.
20555 "Subj ect :
HNDC HN-100_Sfrie, s _3 Radioactive Materials Package Application for Certificate of Compliance
Dear Mr. Odegaarden:
Reference is made to your June 17, 1981 inquiry relative to the " Proprietary Data" marking on the drawings and safety analysis report submitted with our June 16, 1981 application for a certificate of compliance. The proprietary marking is to advise other parties that the use of this information is restricted as described in the " Notice." HITTMAN has no objective to the filing of this information in the public document room provided that the " Notice" is included.
Very truly yours, j
Vice Presidg t, Engineering
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