ML19281B213
| ML19281B213 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 04/04/1979 |
| From: | Dipiazza R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| WRD-LS&S-702, NUDOCS 7905020187 | |
| Download: ML19281B213 (2) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS WASHINGTON, D.C. 20555 ORDER TO SHOW CAUSE (IMMEDIATELY EFFECTIVE)
During a meeting on March 29, 1979, and by letter dated April 2, 1979, the Nuclear Assurance Corporation informed the NRC staff that a cask designated as the Model No NFS-4 (NAC-1, Serial A) was not fabricated in accordance with the design approved by NRC Certificate of Compliance No. 6698.
Cask Model No. NFS-4 is used for transportation of spent reactor fuel and is authorized to carry one PWR element or two BWR elements.
Eighteen owner / users and the Department of Energy are currently authorized to use this model cask.
The deviations were characterized as a difference in the dimensions of the steel shells identified as Part Numbers 67 and 69 as shown in NFS Drawing No. E10080, Revision 16.
In addition, copper plates were welded to the outside of Part 69. The information provided by Nuclear Assurance Corporation in the March 29 meeting indicates that one or more of the shells is warped or bowed, but the exact cause or extent of the warp or bow is not known at this time.
Also, the NRC staff was informed that the cask manufacturer added increased shielding material in an area of reduced shielding thickness by welding copper plates to the outer shell of the cask.
The full safety implications of these reported deviations are not known at this time but they could represent a substantial reduction in the effectiveness of the package such that it would not meet the requirements of 10 CFR Part 71 for normal and accident conditions.
It is possible that other casks fabricated to this design contain similar deviations. There are six casks fabricated to the design and one under construction at the present time.
II In view of the foregoing and in the interest of public health and safety all casks of this design should be withdrawn from use until a determination can be made of the exact nature of any deviations from the approved design and an assessment can be made of the safety significaace of such deviations.
70050201%'7
. Accordingly, pursuant to the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR Parts 2 and 71, IT IS HERESY ORDERED THAT:
1)
Effective immediately, the general license to use casks designated as Model No. NFS-4 is suspended pending further order of the Commission.
- 2) Each owner / user shall show cause in the manner hereinafter provided why the general license to use cask Model No. NFS-4 should not remain suspended until such time as:
The owner / user demonstrates to the Commission that each cask was fabricated in accordance with the design approved by the Commission in Certificate of Compliance No. 6693. This demonstration shall include review of the quality assurance records required by Condition 17 to Certificate of Compliance No. 6698 and actual physical measurements of existing packages.
III In view of the facts set forth in Part I, above, and the importance to public health and safety of proper fabrication of the casks, the Director of the Office of Nuclear Material Safety and Safeguards has determined pursuant to 10 CFR 2.202(f) that the suspension of the general license to use cask Model No. NFS-4 shall be immediately effective.
An owner / user to whom this Order applies may, within 20 days from the receipt of this Order, file a written answer to this Order under oath or af firma tion. Within the same time, an owner / user may request a hearing.
Any answer or request for hearing shall be filed with Mr. Richard E. Cunningham, Director, Division of Fuel Cycle and Material Safety, U. S. Nuclear Regulatory Commission, Washington, D.C. 20555.
Any request for a hearing shall not stay the immediate effectiveness of this Order.
If a hearing is requested, the Commission will issue an Order designating the tine and place for hearing.
. I'!
In the event a hearing is requested, the issues to be considered at such a hearing shall be:
- 1) Whether the owner / user's casks designated Model No. NFS-4 were fabricated in accordance with design approved by NRC Certificate of Compliance No. 6698, and
- 2) Whether this ORDER should be sustained.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION A
Vb William J. Dircks, Director Office of Nuclear Material Safety and Safeguards Dated at Bethesda, Maryland thisf* day of April,1979.