ML19274E635
| ML19274E635 | |
| Person / Time | |
|---|---|
| Site: | 07000025 |
| Issue date: | 02/01/1979 |
| From: | Remley M ROCKWELL INTERNATIONAL CORP. |
| To: | Mccorkle G NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 79ESG-1071, NUDOCS 7904090381 | |
| Download: ML19274E635 (3) | |
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f, Actkn Compi,2, February 1, 1979 In reply refer to 79ESG-1071 Ap plica nt........,. k,,,,,,,,,,
t, fir. George W. McCorkle, Chief Sheck No. a7/Off[./
Woan:/Fce Categor J J.ep..),1 Physical Security Licensing Branch i,:e of Fee... ww.
Division of Safeguards 0.:.e Check Rec'd.. M.6/,
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Dear Mr. McCorkle:
Subject:
Physical Security of Special Nuclear Material, Docket No. 70-25 The Energy Systems Group of Rockwell International is currently conducting fuel fabrication activities at the Group Headquarters Facility at 8900 De Soto Avenue, Canoga Park, California, under Special Nuclear Material License SNM-21 with physical security for the special nuclear materials provided as described in Al-74-5, Revision A, and in accord with Part A of Section 9.0 of Materials and Plant Protection Amendment MPP-1 to License No. SNM-21.
One of the steps in the fuel fabrication process requires the examination of rolled fuel plates with an X-ray fluoroscope to locate accurately the position of tne fuel-bearing material inside the aluminum cladding.
This examination is currently corducted on the fuel plates for the University of Missouri Reactor with an X-ray fluoro-scope located in Roon 119-33D, as shown in Figure 2.1 of AI-74-5, Revision A.
As discussed in my recent telephone conversations with Messrs. Russell Rentschler and Jerry Ennis of your staff, the X-ray fluoroscope presently installed inside the fuel fabrication area is not providing the necessary locatic 1 accuracy for the fuel in the University of Missouri fuel plates.
This is resulting in a major interruption of our fabrication activities with a consequent failure to meet our production schedules.
However, we have a second X-ray fluoroscope presently located in our maintenance shop in Building 102, located just east of our headquarters manufacturing building, inside the industrial complex, on De Soto Avenue.
Preliminary measurements indicate that this fluoroscope can be used to examine the University of Missouri fuel plates.
However, to avoid further delay in our production schedules, it is necessary to use the equipment in its present location outside the material access area to work off the current bacHog of fuel plates requiring inspection.
While that activity is being conducted in Building 102, the unacceptable fluoroscope inside the material access area will be disassembled and removed and the room prepared for acceptance of the fluoroscope presently ' located in Building 102. Therefore, please consider this letter a formal application to ab 11 noroso38(
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79ESG-1071 February 1,1979 Page 2 conduct the Missouri University plate inspection operation with the X-ray fluoroscope in Building 102 on an interim basis, under the security and safeguard conditions described below.
The fuel plates have been fabricated through Step 8, as described in Section 4.3.5 of AI-74-12, Supplement 1, "Special Nuclear Materials Control Program for Uranium-Aluminum Fabrication Operations." They are in the form of flat plates which are approximately 26 in. long and vary in width from about 2 in. to 4-1/2 in.
The special nuclear material content varies from 19.2 to 45.3 gm of U235, and each plate is identified with a serial number.
In this interim examination operation, Step 9 in Section 4.3.5 of AI-74-12, Supplement 1, the Core Location Operation, the plates will be handled in lots to limit the amount of contained U235 to less than 350 gm; e.g. a maximum of 7 number 24 plates, each of which contains 45.3 gm, or a maximum of 18 number 1 plates, each of which contains 19.2 gm.
A lot of plates will be placed on a safe cart, moved through Doors 43 and 2, shown on Figure 2.1 of AI-74-5, Revision A, and south on Aisle llD of Building 001.
They will then be moved east on the east-west aisle near the center of Building 001, out a door on the east side of the building, and across to Building 102, which is shown on Figure 1.1 of AI-74-5, Revision A.
The lot will be examined with the fluoroscope, replaced on the cart, and immediately returned to the material access area in a manner the reverse of that described above.
Accountability of the plates will be continuously maintained by item control and identification of the serially-numbered plates.
At all times, when the plates are transferred through the doors either
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to or from the material access area, the doors will be unlocked by an armed security guard who has radio contact with the primary alarm station and who will maintain continuous serveillence of the area while the doors are open.
The guard will check the plates by serial number both when they are removed from the material access area and again when they are returned after being examined in Building 102.
All operating personnel, either leaving or entering the area with the fuel plates, will be searched as described in the approved security plan in AI-74-5.
At all times while outside the protected area, the fuel plates will be under the continuous surveillance of two of the Energy Systems Group personnel who are authorized unescorted access to the material access area and who will be conducting the examination of the plates with the fluoroscope.
79ESG-1071 February 1, 1979 Page 3 It should be emphasized that the fuel plates will always remain inside the Energy Systems Group industrial site perimeter barrier, as described in Section 1 of AI-74-5.
In addition, all ingress and egress through the site perimeter barrier are controlled as described in Section 2 of AI-74-5.
Thus, any personnel in the area will be badged and will have been admitted only after they have identified, and their affiliation and purpose for entry have been established as described in Section 3 of AI-74-5.
With the operation described above, the maximum amount of special nuclear material outside the protected area at any one time will be 350 gm of U235, the amount permitted in laboratory activities outside of material access areas by Section 73.6 of 10 CFR 73.
The maximum time that any one lot of plates will be outside the protected area will be 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
As indicated above, this is to be an interin operation until we have recovered the lost time in our production schedule and are prepared to install the second X-ray fluoroscope inside the material access area.
Therefore, we request your approval of the operation for a period of 90 days.
Because of the urgency of the University of Missouri production schedule, we solicit your review and approval of this interim operation as soon as possible.
If you have questions or desire further information, please call me at (213) 341-1000, Extension 2238.
As required in Section 170.31(1A) of 10 CFR 170, we have determined that this application is for a Minor Safeguards Amendment to our Special Nuclear Material License and thus is subject to a fee of $3,500.
There-fore, we are enclosing our check for $3,500 in payment of the required fee.
Sincerely yo
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M. E. Rem y,
irec r Health, Safety & Radiktion Services Energy Systems Group add:4/1-3 Enclosure
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