ML20085C633

Proposed Tech Specs Re 5-yr R&D Program

ML20085C633
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	01/05/1962
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 NUDOCS 9110040095
Download: ML20085C633 (2)

Text

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SAXTON NUCLEAR EXPER! MEN ~AL CORPORATION DOCKET NO. 50-lh6 LICENSE NO. DPR-b

% 4E 0/ co%hanc, Proposed Changes in Techni:al Specifications Applicable to Conduct of Phase 1 of the Saxton Five-Year Research and Development Program Page 1, item 2 - Change "20 Kdt" to "23.5 int."

Page 2 - Chan;e (c) in second paragraph to rear'. "Maxinum mixed core exit c

tenperature at 20 K4t borated with 161:w/f t spiked subassembly -

5h60F maximun mixed ccre exit temperature at 23.51Nt bort - .a with 16 kw/ft spiked subassembly - 5500F."

Page 2, (b) " Power operation" - Change " Boric Acid" from "Less than 3.0 ppm as boron" to "A maximum of 2500 ppm as boron," and change

" Lithium (Li 7)* 3 ppm as required to maintain pH between 9.5 to 10.5 15 as measured at 25oC" to " Potassium - A maximum of 3.8 ppm potassium (KOH) or the chemical equivalent of lithiun (LiOH)." Delete footnote marked with an "*", which pertained to " Lithium (Li7)."

Also delete last sentence on page 2.

Page 3, item 6(b) - Change to read " Uranium Oxide (UO2 ) enriched to s.7% U-235 will be used in 20 of the 21 fuel assemblies. The remaining fuel tssembly will have enrichments as follows:

"63 rods (and) 9 central rods (or) 9 central rods "First lh pellets 5.69% 5.69% 5.69%

Next 2 "

7.30% 9.19% 7 30%

a 3

6.81% 8.57% 6.81%

12 "

6.h6% 8.13% 6.h6%

3 6.81% 8.57% 6.815

" 2 "

7.30% 9.19% 7.30%

Last lh "

5.69% 5.69% 5.69%

" Uranium oxide at the density being used has a melting point of approximately 50000 F."

Page h, item 6(c) - Add following sentence, "One 9-rod subassembly using 5.7%

enriched fuel will have cladding of Zircaloy b which has a melting point of approximately 30h50F."

Page b, item 6(e) - Change to read " Maximum total weight of fuel in the core is approximately 2250 lbs of UO2 enriched as shown in (b) above."

Page h, item 6(i) - Add following sentence, "The moderator tempera ure coefficient during the chemical shim tests will vary from -5.3 x 10- k/0F to

-1.6 x 10-b k/ F."

Page h, item 6(j), fourth paragraph - Change "200 ppm" to "2500 ppm" in first sentence. Ihlete last sentence.

9110040095 o10424 PDR FOIA DEKOK91-17 PDP F om C0 W4S- 33{

IP-Pace $, iten 6(k) - Change to read as follows: "Under steady-state conditions at 23.5 MWt. the principal temperature and thernal characteristics of the spiked fuel assembly are as follows:

" Maximum calculated heat flux Btu /hr-ft22 h70,000' Average heat flux Btu /hr-ft 161,000 Minimum burnout safety factor (WAPD Correlation ) 1.6h Maximum calculated fuel clad tenperature, OF 6h2 Maximum fuel heat generation, kw/f t 16 Average power density, kw/ liter - core 63.5-Page 5, item 6(1) - Change "less than 1.85" to "less than 1.16."

Page 6, item 7(g) - Change "High Power Level at Power (Maximum)" from "2h MW" to "27 MW."

Page 6, item 7(g) - Change "High Main Coolant Temperature (Hot Leg) (Maximum)"

from "6000F" te "$$h0F."

Page 17, iten 19(e) - Add item (8) to read as follews: "During the chemical shim control tests periodic measurements of the core reactivity shall be made. The total unexplained reactivity loss, including measure-ment and calculation uncertaintics, shall be limited to value such I that its release in the manner postulated in Section V-B-5 of Phase 1 of the Safeguards Repert does not exceed the accident criteria set in Section V-A-2. In performing the computations to determine this reactivity value, the experimentally determined core charact:ristics will be used. If the unaccounted for reactivity reaches the above limit, the experiment shall be discontinued and an evaluation instituted to determine if the reactivity change was due to poison deposition on the core."

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