ML20236R059

Forwards Request for Addl Info Re 830512 Request for Approval of Model A1W-3 Core Barrel & Thermal Shield Disposal Container.Nrc Should Be Advised within 30 Days from Ltr Date When Info Will Be Provided

ML20236R059
Person / Time
Site:	07109789
Issue date:	11/19/1987
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Engel W ENERGY, DEPT. OF
References
NUDOCS 8711230058
Download: ML20236R059 (3)

Text

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. DISTRIBUTION:w/enci 71-9789 Docket File 'NRC fDR3fn -

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Department of Energy CRMarotta CRChappel.1-ATTN:

Mr. W. P. Engel Region I NMSS'r/f Division of Naval Reactors SGTB r/f.

Washington, DC 20545 Gentlemen:

This refers to your application dated May 12, 1983 requesting approval of the Model No. A1W-3 Core Barrel and Thermal Shield Disposal Container.

In ccnnection 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 paget.

If you have any questions regarding this matter, we would be pleased to meet with you and your staff.

Sincerely,-

Original Signed by 1

CEARLESX. E CDOR ED Charles E. MacDorald, 2hief

. Transportation Branch Division of Safeguards and Transportation, NMSS.

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Enclosure:

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B711230058 871119 ADOCK 071*

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0FFICIAL R'ECORD COPY i

'I U. S. Department of Energy Division of Naval Reactors Model No. A1W-3 Core Barrel and Thermal Shiold Dis)osal Container i

Doc <et lio. 71-9789 Enc 1 to ltr dtd: NOV 191987 Structural 1.

The allowable stress criteria in the application should be based directly on material yield stress and ultimate stress rather than upon " yield bending modulus" and " modulus of rupture." (Pgs. 2.1.2.3-2,1.2.5).

2.

The requirements of 10 CFR 671-71(c)(3) for reduced external pressure should be addressed.

3.

The requirements of 10 CFR 971.71(c)(4) for increased external pressure should be addressed.

i 4.

Clarify the discrepancy between the room temperature static yield i

strength for ASTM A737 steel which was used in the IMPACT 2 Model to i

derive " Stress Max" and the room temperature static yield strength for ASTM A737 steel shown in Figure 2.3.1.

5.

It is noted that, under 30-foot flat bottom drop condition, the primary i

membrane plus bending stress at the cylinder to top plate and cylinder to bottom plate welds have exceed the ultimate strength (Su) of the base material.

Naval Reactors could Provide an adequate technical basis to justify that the dynamic a.

i strain rate effects are applicable to the above mentioned welds.

In addition, discuss the validity of the "1.57" dynamic factor used to account for the strain rate of the A1W-3 cask material. Since the "1.57" dynamic factor represents the total difference between the scale model test and IMPACT 2 analysis of a different cask with different material, it is not clear how much of the "1.57" dynamic factor was contributed by the strain rate of the material.

Furthermore, it is also not clear that the "1.57" dynamic factor is applicable to A1W-3.

b.

Assume failure of the above mentioned welas and assess the radiological consequences resulting from the failure.

c.

Re-examine the stress classification for bending at the above mentioned welds.

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I 6.-

The requirements _of 10 CFR 571/.73(c)(5) for ininersion of all packages should be addressed.

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Containment j

Revise Section 4.3 and Table 4.1 to show'that the package does not. release radioactive material exceeding an A accident conditions (10 CFR 71.73) 2 quantity in one week for hypothetical-

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