ML20085D070

Proposed Rev of Suppl 1 to Tech Specs Re Automatic Switching of 440 Volt Buses During Operation of Safety Injection Pump

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: ML20085C449 ML20085C452 ML20085C455 ML20085C458 ML20085C461 ML20085C464 ML20085C467 ML20085C472 ML20085C477 ML20085C480 ML20085C483 ML20085C490 ML20085C500 ML20085C501 ML20085C504 ML20085C508 ML20085C513 ML20085C517 ML20085C540 ML20085C543 ML20085C546 ML20085C583 ML20085C586 ML20085C590 ML20085C592 ML20085C602 ML20085C605 ML20085C616 ML20085C620 ML20085C622 ML20085C625 ML20085C628 ML20085C630 ML20085C633 ML20085C634 ML20085C637 ML20085C805 ML20085C809 ML20085C826 ML20085C835 ML20085C840 ML20085C844 ML20085C904 ML20085C913 ML20085C966 ML20085C973 ML20085D041 ML20085D048 ML20085D052 ML20085D059 ... further results
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

_. - - - _]