ML20085D070
| ML20085D070 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 01/18/1963 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 11397, NUDOCS 9110150223 | |
| Download: ML20085D070 (2) | |
Text
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' Q SAXTON NUCLFAR EXPEIGMElfrAL CORPORATION DOCTI NO. 50-146 4
LICENSE NO. DPRk lb q omsgce P
V Proposed Revision of Supplement No.1 to the Saxton Technical Specifications It is proposed that Supplement No.1 to the Technical SIecifications incorporating changes applicable to conduct of Phase 1 of the Saxton five-year resenreh and develoinent program be revised as follows in order to provide for changes and additions to the phase 1 experimental program as described in Supple-ment No.1 to the safeguards Report for the Phase 1 experimental program.
Page 3 - Change item 6(b) to read as followst Uranium oxide (UO ) enriched to 5 7% U-235 vill be used in the p
fuel assemblies, eateept that the '.'ollowin6 test fuel assemblies having special enrichments as atiseribed may be inserted in the renetor:
63-Rod
- 9. Rod 9-Rod No11ov Sub-Sub-Assembly and Assembly or Assembly First 14 pellets 5 69%
5 69%
5.69%
Next 2 pellets 7 30%
9 19%
7 30%
Next 3 pellets 6.81%
8 57%
6.81%
Next 12 pellets 6.46%
8.13%
6.46%
Next 3 pellets 6.81%
8 57%
6.81%
Next
? Iellets 7 30%
9 19%
7 30%
Next 14 pellets 5 69%
5 69%
5 69%
The 9-rod subassembly in the second column shall not be used at power levels greater than 20 Mdt.
one 9-rod subassembly vill have four corner rods clad with Zircaloy-4 and vill contain uranium oxide (UO ) enriched to 6.1%
2 stainless steel and vill contain uranium oxide (UO ) ype 304 U-235 The other five rods vill de clad with thin, T enriched to 2
5 7% U-235 u a V'
One 9-rod fuel subassembly vill be the same as the above 9 rod L
subassembly, except that the uranium oxide in the stainless steel o.
clad rods vill have the same enrichment as the 63-rod sIecially enriched hollow assembly listed above.
n s N37 cc-One 4-rod subassembly vill have Type 304 stainless steel clad e
M rods with uranium oxide (UO ) fuel pellets uniformly curiched to 2
3d 8 3% U-235
-ow Uranium oxide..ttgedensitybeingusedhasameltingpointof Ql l }W QJ i
3 approximate 1L 5000 F.
.. g.
e page 5 - Change item 6(k) to read as f 011ovs:
Under steady-state conditions at 23 5 MWt and thermal characteristics ofgthe core ar,e as follows:the principal temperature Maximum egiculated heat flux in spiked region, Btu /hr ft 533,000 Maximum egiculated heat flux in unspiked region, B?u/hr ft h70,000 Average heat flux, Btu /hr ft2 161,000 Minimum eteady-etate burnout safety factor in spiked region (W-2 correlation) 2.27 Minimum eteady-state burnout safely factor in unspiked region (V-2 correlation) 2.84 Maximum calculated fuel clad temperature, OF 642 Maximum fuel heat generation in 63-rod spiked hollow assembly and 9-rod spiked subannembly, kv/ft 16.0 Maximum fuel heat generation in 4-rod spiked subassembly, kv/ft 20.0 Maximum fuel heat generation in unspiked region, kv/ft i
14.1 Average power density, kv/ liter of core 63 5 Page 5 - Change item 6(1) to read as folluvat Under credible accident conditions as described in Saxton' Report for Phase 1 the minimum calculated bur s Safeguards or in any be less than 135 (W-2 correlation).
temperature is not expected to exceed 1500VF. subassemb o
cladding t
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