ML20009E285
| ML20009E285 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 05/11/1981 |
| From: | Lichtenberger ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 19102, NUDOCS 8107280003 | |
| Download: ML20009E285 (5) | |
Text
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C-E P wer Systems Tel 203/688-1911 UM h
_ffA Cornbustion Engineenng, Inc.
Telex 9-9297 F.
II v 1000 Prospect Hill Road
.E-J(JIJ 10 jgg;,.g Windsor, Connecticut 06095 DOCKET CLERK N
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3.Q 39t-s3 May 11, 1981 r,
License SNM-1057 Docket 70-1100 i
U. S. Nuclear Regulatory Commission 3
_ Applicant...b. bg"aa'"
Washington, DC 20555 Check No.. (
- 3* *? *.ff Attention:
Mr. W. T. Crow, Section Leader Amouat/ Fee Category.
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Uranium Process Licensing Section f
ca.a Gwk Rec'd ' < *#
Uranium Fuel Licensing Branch necesd E' - %Qj;jj _'* J ' M Division of Fuel Cycle & Material Safety l
Dear Mr. Crow:
It is requested that License SNM-1067 be amended to allow storage of sealed fuel rods in a 3.7 inch slab arrangement in the Development Department's Building #2 vault at our Windsor site.
Non-coplanar storage will not be permitted and no other SNM will be stored in this vault.
The criticality alarm system has been extended to this vault and includes dual detectors and a remote indicator in the central guard house.
Building
- 2 is secured and included in the Windsor Site Plan which has been reviewed and approved by the Commission in the same manner ar all other secured lab-oratory areas.
Before fuel is first introduced to this vault, the area will be posted in accordance with 10 CFR 20. As all fuel rods will be sealed and decantam-inated to our unrestricted release limits, no further health physics consid-eration will be addressed. Accordingly, it is requested that the following page changes to License SNM-1067 be made effective:
Delete Pages Add Page_s_
VIII-3, Rev. 3, dated 2/22/74 VIII-3, Rev. 4, dated 5/11/81 XIII-1, Rev. 4, dated 3/15 4 XIII-1, Rev. 5, dated 5/11/81 XIX-1, Rev. O, dated 3/22/79 XIX-1, Rev. 1, dated 5/11/81 This amendment request is considered a minor health and safety amendment and the fee of $1400 required by 10 CFR 170.31 is beinq forwarded directly to the License Fee Management Branch under separate cover.
If you have any questions regarding this amendment application, please contact Mr. G. A. Johnstone of my staff, or Mr. P. R. Rosenthal.
Very truly,your,
b.t tdf H. V. Lichtenberger Vice President-Nuclear Fuel Nuclear Power Systems-Manufacturing 19102 HVL/bJB/ssb 8107280003 810511 PDR ADOCK 07001100 C
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' Writt:n health and safety restrictions for all operatio is on radioactive materials are provided by the Radiological Safety Officer,'and appropriate operational limits are posted near the appropriate work station.
Each operation en fissile material 235 235 is limited to 350 gm U for uranium enriched to more than 5% U
, and to 740 gms 25 235 U
for arar'"-
I to 5% cr less U
, and must be separated from any other o
fissile matet 17.eet.
Rods containing sintered UO2 pellets enriched to a maximum of 4.1% U'*" are stored in the Building #2 vault. Storage of material in this /ault is limited to a single slab less than 3.7 inches thick. No other fissile materials are to be used or stored in this area. A continuous 109 is maintaineu for each work station to a:sure that the limit is maintained and that the ei.richment of all material is recorded. No other criticality controls are required for the labor-atories. No material of enrichment axceeding 4.1% may be transferred from the lab-oratories to NFM-W.
In addition to providir.g the above safety restrictions, the Radiological Safety Officer is responsible for the surveillance of all Nuclear Laboratory activities in which radioactivity is involved to ensure that the health and safety standards set forth in the license application are met. He has the necessary authority to halt any oper-ation which falls outside those limits, and he is responsible for indicating what re-medial action is necessary to bring the operation within acceptable limits. As shown
.in Figure 8.1, he reports directly to the Director of the Nuclear Laboratories.
License No. SNM-1067. Docket 70-1100 Revision:
4 Date: 5/11/81 Page: VIII-3.
s
' 13.d NUCLEAR LABORATORIES This license is intended to authorize the Nuclear Power Systems Division to 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 235 235 is limited to 350 gms U For uranium enriched to 5% or less U
, a limit 235 of 740 gms U applies. All mass limits will be separated by at least 12 ft.
235 Rods containing sintered UO2 pellets enriched to a maximum of 4.1% U are stored in the Building #2 vault.
Storage of material in the vault is limited to a single slab less than 3.7 inches thick.
No other fissile materials are to be used or stored in this area. 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 Nuclear Manufacturing Facility - Building #17.
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 provisions of the license, and will be handled as a departmental transfer and controlled by the Nuclear Material fianagement Procedures described elsewhere in this license.
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License No. SNM-1067, Docket 70-1100 Revision:
5 Date: 5/11/81
-Page: XIII-l m
J
19.0 NUCLEAR CRITICALITY SAFETY LIMITS This section provides the limits which may be applied to the Nuclear Labora-tories, and to the U0 perations carried out by Nuclear Fuel Manufacturing-2 Windsor.
235 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.
Each such limited operation must be separated from any otner limit by St least 12 feet. Rods containing sintered U0 pellets enriched to a maximum of 4.1%
2 235 U
are stored in the Building #2 'ault.
Storage of material in the vault is limited to a single slab less than 3.7 inches thick.
No other fissile materials are to be used or stored in this area.
Criticality safety of the less complex manufacturing operations is based on the use of limiting parametcrs which are applied to ';imple 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.
The remaining manufacturing operations are evaluated using two dimensional trans-port and/or three dimensional Monte Carlo Codes. The sixteen group Hansen-Roach cross section library is used for homogeneous systems, while the CEPAK Code is used to generate four group cross sectiom for heterogeneous systems.
A detailed validation of these calculational codes and cross sections is pro-vided in Exhibit D.
4 License No. SNM-1067, Docket 70-1100 Revision:
1 Date: 5/11/81
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" LICENSE' AMENDMENTS" l
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Docket Ne. 2 O - I't O
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-to William O. Miller, License Fee Management Branch, ADM MATERIALS LICENSE AMENDMENT CLASSIFICATION Applicant:
C f Psw de Pr e 7
License No:
So +1 - / o 67 Fee Category:
r4 Application Dated:
c//r ///
Received: J/fl///
Applicant's Classification:
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The above application for amendment has been reviewed by NMSS in accordance with 8170.31 of Part 170, and is classified as follows:
1.
Safety arid Environmental Amendments to Licenses in Fee Catecortes 1A throuch 1H,'2A, 2B, 2C, and 4A (a)
Major safety and environmental (b)
V inor safety and environmental M
(c)
Safety and environmental (Categories ID through 1G only)
(d)
Administrative' 2
Justification for reclassification:
3.
The application was filed (a) cursuant to written NRC request and the ame1dment is being issued for the convenience 4
of the Commission, or (b)
Other (State reason):
7 Signature h 44]
Division of Fuel Cycle & Material Safety Date N
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