ML19260E194
| ML19260E194 | |
| Person / Time | |
|---|---|
| Site: | 07109069 |
| Issue date: | 01/11/1980 |
| From: | Dipiazza R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 15194, NUDOCS 8002130655 | |
| Download: ML19260E194 (4) | |
Text
- 4 7/- 14 uno.wan Westinghouse Water Reactor Bcx 3S5 Electric Corporation Divisions Pitt,tu;;h Passy!vna 15230 January 11, 1980 11. S. IJuclear Regulatory Concr.icaj on Of fice of ' : clear fiatorial Sa f ety & Safeguards Divician of Puel Cycle & McLerial Safety wanhington, D.C.
20555 Attention:
'r.
C.P.
MacDonald, Chief Transportation Branch Gon tle:aen :
S al:j oc t :
Apolication for Jimenda-nt to Certificatu of Comolitnce No. 90G9, Dochet 7]-90G9 The tectinnhouse Cloctric Corporation horeby sub:aiPm -n nr pli ca ?'i on toc ament":nt of Certificate of Cor'pliance llo. 9069, ??oci:ct 7 3 -9 0C9 in accordance with the nttachno-t to thit, J et t.a c.
The cpecitic changes to the fuel parameters listed on Table 1 are requented.
1) 14xl ; Ac cer.;bly - Change the highest enrichment (Puo UU2) to read "For various plutoniun icotopen 2
the Pt.0 enrichnent is 6.0 v/o (710 finnile), 4.4 2
v/o (811 fiscile) and 3.03 (855 finrilc).
The U 2. b-
.5 enrichraent in the name for all canec at 0.71 w/o."
The j us t1. fica Liori for th3a change has been previously tccusmiLred to the IJnC by Uectinghouce letter WPD-LSrJ-191 dated February 11, 1977, and tbc changed pager or our app)ication 5-10 ami 5-27 which are ine]uiaa with this tranr,nitta).
__Lau
WRD-LA-034 Page 2, A check in the amount of $690.00 has been included with the submi.ttal as paynent of the AmendInont Fee in accordance with 10 CPR170.31 Paragraph lle.
Please send the license amendment to rne at the above address.
If you have any questions regarding this natter, please write me at the above address or telephone me at 412-373-4652.
Very truly yours, f)
'A G
Ronald P.
DiPiazza, Manage License Administration RPD/m Attach.
Revision 5 January 11,1980 TABLE I Plutonium Fuel Licensing Parameters 14x14 Assembly Loose Rods Pellet Parameters Material PuO S""U 2
Highest enrichment (Puo UO )
(S N te 1) 6,0 w/o (85% fissile),
2 2
.71 w/o Diameter (NOM) 0.3659" Same Rod Parameters Cladding matl.
Zirc -4 Same Clad O.D.
(NOM)
.422" Same Clad thickness (NOM) 0,243" Samn Fuel length 120" - 144" Same Ass'y Paramcters No.cf rods (max) 179 350/ box Pattern 14x14 NA Fuel rod lattice pitch (NOM)
.556" Touching square lattice []
Assembly envelope (NOM) 7.784" x 7.784" 8.072" x 8.072" Licensing Criteria Total fissile (max)
< 20 kg/ assembly 33 kg/ box K
(Max / ass'y)
<.90 Same ggg K
(Max /1 pkg)
<.94 Same ggg K
(Max /MCA)
<.98 Same ggg Poison Plates Required 2 horated stainless Not Required. Boxes per or OPHC copper W drawing C5650D55.
1.
For various plutonium isotopics the Puo, enrichment is 6.0 w/o (71% fissile:
4.4 w/o (81% fissile) and 3.03 w/o (85%~ fissile).
The U235 enrichment is the same for all cases at 0.71 w/o.
2.
Fuel rods shall be closely packed in the fuel rod container on no more than an equivalent metal-to-metal square lattice. Partially loaded fuel rod container shall be fitted with a minimum of three, equally spaced blocks, of which the noncombustible portion of the blocks and the method by which they are secured shall assure that the rods are maintained on no more than an equivalent metal-to-metal square lattice within the fuel rod containcr.
5-10
Revision 4 January 9, 1980 In addition, similar calculations were performed using 3.03 w/o pug fuel with 83.5% fissile content.
The results s;10wed that 3
K was 0.03 nK lower than the 6.0 w/o Pu (71% fissile) caso gg7 discussed above.
This 0.03 t,K margin means that assemblies with average PuO nrichments up to 3.03 w/o and fissile content up 2
to 85% can be shipped.
NRC criticality guidelines are met for a single flooded assembly and for two flooded assemblies with copper absorber plates.
When it is assumed that in the maximum credible accident the fuel assemblies, after crushing, are separated by greater than 4 inches from each other, then copper absorber plates will meet NRC requirements.
15194 5-27