ML20245H546
| ML20245H546 | |
| Person / Time | |
|---|---|
| Site: | 07000036 |
| Issue date: | 02/10/1989 |
| From: | ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML20235N211 | List: |
| References | |
| NUDOCS 8903010105 | |
| Download: ML20245H546 (14) | |
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ENCLOSURE I q
COMBUSTION ENGINEERING, INC. -
HEMATITE NUCLEAR FUEL MANUFACTURING FACILITY LICENSE AMENDMENT REQUEST l
-LIST OF ~ AFFECTED PAGES i
i FEBRUARY,1989 1
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HEMATITE NUCLEAR FUEL MANUFACTURING FACILITY v
LICENSE AMENDMENT ~
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-o Combustion Engineering requests that the license (SNM-33) for its Hematite Nuclear Fuel Manufacturing Facility be amended.to reflect changes which will-be made to the.UFg to UOg conversion line..In brief, this modification-involves the additi5n of a hew section to the upper end of the R-2 reactor.
' This new section is of a larger. diameter and' extends R-2 to,a height of eleven' feet four inches.. This' modification of R-2 will reduce carryover, minimize' recycle and reduce material handling..
The license pages affected by this amendment and their respective revision numbers are listed below. The proposed change pages are provided in Enclosure' II.
Deleted Page Added Page 3
Page No.
Rev.
Page No.
Itev.
I.4.5a 0.
II.9-1 1-II.9-1 2
II.9 2 II. 9-2 3
II.9-2a 0
II.9-2a 1
II.9.2b 0
II. 9-3 0
II. 9-3 1
i 11.9-4 1
11.9-4 2:
II.9-4a 0
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II.9-5a 2
II.9-5 3
II.9-Sa 2
II.9-5a 3
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LICENSE AMENDMENT REQUEST ki t
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W Docket No. 70 -
Lic:nse No. SNM-33:
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The R-2 steam'line will have' two (redundant)Ifail-safe shut-off valves, : each activated by two -independent: high' and. low temperture < alarms. setpoints on -the - R-2 reactor..
ascertained. at; The operability of this systemsi will-- be1 least once every.~ six months.-
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License No. SNM-33, Docket 70-36 Revision 0 Date:
02/09/89 Page:
I.4-Sa L di :.
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9.0 NUCLEAR SAFETY ANALYSIS OF UF; - U0g
~q CONVERSION-9.1 Reactor' Vessels and Furnaces a.
Description Vessel R-2 and it's furnace 'are shown in cross-section on j Figure 9-2.
For comparison, the upper end configuration ofi vessels R-1 and R-3 are shown in dotted lines. The a
elevation view of the UF -UO conversion reactor _ line.
6 2
3 is shown on Figure 9-1.
.The lower sections (10" diameter and 12" diameter) are the same for all three vessels.
Vessel R-2, however, has an additional 16" diameter section which increases the total height to 11'4".
All three vessels are fitted with electrically heatedi furnaces.
R-1 and R-3 have two independently controlled sections and R-2 has three independently controlled sections.
All three reactors have ' low temperature alarm set points and R-2 has a second (redundant) low temperature alarm setpoint.
In addition, the steam supply line to R-2 has two shut-off valves (one redundant) which are activated by the low temperature alarm setpoints from the-R-2 controllers.
b.
Nuclear Safety Assumptions:
- 1) Maximum enrichment 5.0%.
- 2) Under process design (normal) conditions, SNM is only in the 10" diameter lower section of the vessel.
- 3) Reflection as provided by furnace insulation; and vessel steel walls as shown in Figure 11.9-2.
Reactor vessels are supported 30, 20, and 10 feet above the ground level; infinite water reflection is, therefore not credible.
1 License No. SNM-33, Docket 70-36 Revision:
2 Date:
02/10/89 Page:
11.9-1 L
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Figure 11.9-3
,4' 1] --> Cas out to filter system -
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Electrical Heater \\%
' Secondary Disengaging Section a
(R2 only)
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and allows fines to drop back ri.:i:
into the bed. (R2 only)
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Primary Disengaging Section
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reduces gas velocity and allows powder to drop back into bed.
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Control Reactor Section where powder reacts with I
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' D]4-- Gas in from boiler and/or ammonia cracker ll Basic Reactor & Furnace Schematic License No. SNM-33, Docket 70-36 Revision: 0 Date: 02/10/89 (new figure)
Page; ll.9-4a l
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,4 9.1
'Re' actor Vessels and Furnaces (continued) l
- c. ' Conclusions (continued)
Nonetheless, a K,ff calculation has' been made for an l
isolated R-3 reactor as shown 'in II.9-2.
The K,7f 0.9510 i.0055.
(See page 11.9-29)
- 3) Criticality Safety Analysis The following conservative,
l assumptions were used in the calculational model of the conversion equipment analysis:
UF6.to U02 a) Reactors R-1 and R-2 were assumed to'be filled.in the 10" portion (i.e., no overfill) with dry U0 at 2.5 2
235 g/cc density of powder and 5.0 w/o U All struc-tures consisting of.375" steel wall, 7.75" of 37.5 3
lbs/ft firebrick, insulation and.25" steel casing -
were included in the model. The conservative reactor details shown in Figure 11.9-2 (page II.9-4) were used.
b) The R-3 reactor was assumed to be filled in both the 10" and 12"' portions (i.e., overfilled) with satur-235 ated UO at 2.5 g/cc powder density and 5.0 w/o U 2
All structures consisting of.375" steel wall, 7.75" firebrick insulation and
.25" steel casing were included in the model.
c) The cooler was assumed to contain UO with 5.0 w/o 2
water. The.125" steel walls were also modelled.
d) The silos were assumed to contain UO with 5.0 w/o 2
water. The.125" steel walls were also modelled.
e) The UO blenders contained U0 with 5.0 w/o water.
2 2
The.125" steel walls were also modelled.
f) The UF scrubber was assumed dry UO with no external 6
2 structures modelled.
g) The R-1 hopper was assumed to be filled with dry U02 and surrounded by 1" of water, h) An external mist of.001 g/cc was assumed.
License No. SNM-33, Docket 70-36 Revision: 3 Date:
02/10/89 Page:
11.9-5
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