ML20198G639

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Forwards Request for Addl Info Re 860228 & 0508 Applications for Amend to Certificate of Compliance 5942 for Model 700. Response Should Include Drawing of Fuel Basket Developed Under NRC QA Program Which Addresses Fabrication
ML20198G639
Person / Time
Site: 07105942
Issue date: 05/20/1986
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Cunningham G
GENERAL ELECTRIC CO.
References
NUDOCS 8605290716
Download: ML20198G639 (2)


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RETURNTO A Mch?n 396-SS -

FCTC: RHO W20W 71-5942 General Electric. Company ATTN: Mr. G. E. Cunningham Vallecitos Nuclear Center j Pleasanton, CA 94566 Gentlemen:

This refers to your application dated February 28, 1986, as supplemented j flay 8,1986, requesting an amendment to the Model No. 700 package.

In connection with our review, we need the information identified in the

! enclosure to this letter.

Please advise us within 30 days from the date of this letter when this information will be provided. The additional information requested by i

this letter should be submitted in the form of revised pages. If you have any questions'regarding this matter, we would be pleased to meet

with you and your staff.

i Sincerely, Original Signed by WRE E9 E. FACDOEMS Charles E. MacDonald, Chief

Transportation Certification Branch i

Division of Fuel Cycle and Material Safety, MSS

Enclosure:

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DRAUING Drawing No. E-04-045

1. Provide a drawing of the fuel basket that has been developed under an NRC approved quality assurance progran which addresses design and fabrication.
2. Drawing notes should cite the code or standard by which the welder and welding procedures will be qualified.
3. The drawing should identify the weld joints to be nondestructively exanined, the nethod to be used, and the code or standard for the examination procedure and acceptance criteria.

, STRUCTURAL The criticality safety analysis is based on the configuration of the cask divider-loaded with fuel elements and spacers. Consequently, if there are weld failures resulting in significant change of the geocetry of the divider, criticality safety cannot be easily evaluated. Thus, perfom an analysis to demonstrate that nassive weld failure will not occur and that the cask divider configuration will not change significantly due to 30-foot drop of the package.

OPERATING PROCEDURE Chapter XVIII, Section R, Loading / Unloading Procedure for GE flodel No. 700 cask with extension.

1. Steps 8.kk. and 9.e. should include reference to 10 CFR $$71.47 and 71.87.
2. Step 9.c. should state torque requirecent.

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GSRC FORM 318 (10 80) NRCM O240 OFFICIAL RECORD COPY