ML20009H139
| ML20009H139 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 07/14/1981 |
| From: | Lichtenberger H ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 19407, NUDOCS 8108060132 | |
| Download: ML20009H139 (4) | |
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4 C-E Power Systems Tel. 203/688-1911 Combustion Engineering, Inc.
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July 14, 1981 License Stif1-1067 co 7c7g3 je Docket 70-1100 USNRC P []?g%
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U. S. fluclear Regulatory Commission j
Washington, DC 20555 NYSS
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DOCKET CLERK I
2 Attention:
Mr. W. T. Crow, Section L Uranium Process Licensing S 6
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($ y g Uranium Fuel Licensing Branch M
3 Division of Fuel Cycle & Material Safety (f.,-
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Reference:
Amendment Application from H. V. Lichtenberger to W. T. Ce dated flay 11, 1981
Dear fir. Crow:
In discussing the referenced license amendment with Mr. N. Ketzlach of your staff on 6/30/81, several wording changes in the text were requested to pro-vide further clarification of the proposed fuel storage in the Building #2 vault. These changes have been made and are hereby submitted as revised license pages. Accordingly, it is requested that the revised pages in our original application be withdrawn in their entirety and that the following page changes to License SNft-1067 be made effective:
l Delete Pages Add Panes VIII-3, Rev. 3, dated 2/22/74 VIII-3, Rev. 4, dated 7/14/81 XIII-1, Rev. 5, dated 12/21/79 XIII-1, Rev. 6, dated 7/14/81 XIX-1, Rev. O, dated 3/22/79 XIX-1, Rev. 1, dated 7/14/81 Very truly yours, H. V. Lichtenberger Vice President-Nuclear Fuel Nuclear Power Systems-Manufacturing HVL/GJB/ssb FEE HEMPT
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Written health and safety restrictions for all operations on radioactive materials are provided by the Radiological Safety Officer, and appropriate operational limits are posted near the appropriate work station.
Each operation on fissile naterial 235 235 is limited to 350 gm U for uranium enriched to more than 5% U
, and to 740 gms 235 235 U
for uranium enriched to 5% or less U
, and must be separated from any other l
0 fissile material by 12 feet. Sealed rods containing sintered UO2 pellets enriched 235 to a maximum of 4.1% U may be stored in the Building #2 vault. Storage of mat-erial in this vault is limited to a single slab less than 3.7 inches thick. No other i
fissile materials shall be used or stored in this vault.
A continuous log is main-tained for each work station to assure that the limit is maintained and that the en-richment of all material is recorded. No other criticality controls are required l
for the laboratories. No material of enrichment exceeding 4.1% may be transferred from the laboratories to NFM-W.
l In addition to providing the above safety restrictions, the Radiological Safety Off-icer is resoonsible for the surveillance of all Nuclear Laboratory activities in which radioactivity is invol'ted to ensure that the health and safety standards set j
forth in the license application are met.
He has the necessary authority to halt any operation which falls outside those limits, and he is responsible for indicating what remedial action is necessary to bring the operation within acceptable limits.
As shown in Figure 8.1, he reports directly to the Vice President of the Development O
Department.
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License No. SNM-1067, Docket 70-1100 Revision:
4 Date:
7/la/81 Page:
VIII-3
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13.0 NUCLEAR LABORATORIES i
I This license is intended to authorize the Nuclear Power Systems Division to l
l receive, store, use and transfer in all laboratory facilities for research and development and manufacturing, source material in any chemical or physical 235 form, and special nuclear material enriched to more than 5% in the isotope U 235 l
is limited to 350 gms U For uranium enriched to 5% or less V
, a limit of 740 gms U app 1'es.
All mass limits will be separated by at least 12 ft.
235 235 Sealed rods containing sintered UO2 pellets enriched to a maximum of 4.1% U may be stored in the Building #2 vault. Storage of material in the vault is limited to a single slab less than 3.7 inches thick. flo other fissile materials shall be used or stored in this vault. Total quantities of source and SNM will be described in Section 4 of this license.
The Nuclear Laboratories are therefore authorized to receive, store, use and return special nuclear and source material from the manufacturing facility in accordance with the provisions therein.
It should be noted that work under these transfers will be of an analytical nature and that the material will ultimately be returned to the fluclear Manufacturing Facility - Building #17.
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l These transfers will not require the issuance of the applicable transfer docu-ments to the NRC since the material must be transferred in accordance with the l
provisions of the license, and will be handled as a departmental transfer and controlled by the Nuclear Material Management Procedures described elsewhere in this license.
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I License No. SNM-1067. Docket 70-1100 Revision:
6 Date:
7/14/81 j
Page:
XIII-1
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19.0 HUCLEAR CRITICALITY SAFETY LIMITS l
This section provides the limits which may be applied to the Nuclear Labora-tories, and to the UO perations carried out by Nuclear Fuel fianufacturing-2 Windsor.
35 All laboratory operations are limited to 350 gm U for uranium enriched to 235 235 235 more than 5% U
, and to 740 gm U for uranium enriched to 5% U or less.
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Each such limited operation nust be separated from any other limit by at least 12 feet. Sealed rods containing sintered UO2 pellets enriched to a maximum of 235 4.1% U may be stored in the Building #2 vault.
Storage of material in the j
vault is limited to a single slab less than 3.7 inches thick. No other fissile l
materials shall be used or stored in this vault.
l Criticality safety of the 1s;s complex manufacturing operations is based on the use of limiting parameters which are applied to simple geometries.
Safe In-dividual Units (SIU) are selected on the basis of optimum moderation, and full reflection using published nuclear criticality safety data. These are spaced using the surface density method.
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The remaining manufacturing operations are evaluated using two dimensional transport and/or three dimensional ftonte Carlo Codes. The sixteen group Han-sen Roach cross section liorary is used for homogeneous systems, while the CEPAK Code is used to generate four group cross sections for heterogeneous systems.
A detailed validation cf these calculational codes and cross sections is pro-vided in Exhibit D.
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l License No. SNM-1067, Docket 70-1100 Revision:
1 Date:
7/14/81 19407 Page:
XIX-1
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