ML20085F567

From kanterella
Jump to navigation Jump to search
Change Request 30 to License DPR-4 Re Test Fuel Assemblies
ML20085F567
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 02/02/1968
From: Neidig R
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110220221
Download: ML20085F567 (4)
v • d • e


Text

_ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ .

1

/ *

,. n SAXTON NUCLEAR EXPIRIMENTAL CORPORATICN DCCKET NJ. 50-lh6 LICENSE DIH-b CHAN3E REQ'JIST NO. 30

--- ~_--

1. Applicant hereby submits Change Request No. 30 in compliance with paragraph 3B of License Dl%-b for change of the Technical Specifica.

tions to be authorized by the Commission as provided in 10 cFR 50 59.

SAXTON NUCLEAR EXPERIMENTAL CORPORATION by /s/ R. E. Neidig President >

J i-6 0110220221 910424 PDR FOIA DEKOK91-17 PDR S.g

1 ,. ,

, ed " ,

4 Docket No. 50-146 DPR-4 Technical Specifications Change Request No. 30 Page 1 of 3 *

1) Purpose of Change In a previous test of Zircaloy-4 clad fuel rods
  • internally pressurized to produce tensile stresses of approximately 22,000 psi, unexpected local diameter changes of 2% occurred after 4700 EFPH operation. The purpose of this change is, then, to provide more inpile creep data on Zircaloy-4 claddirg over the preesure range which will yield tensile stresses up to 22,000 psi and peak mean clad temperatures up *.o 721 F.
2) Safety Considerations Although the previous inpile creep test reds experienced greater local strains than expected, the safety of the reactor and the public was not jeopardized. In order to further reduce the chance of execssive strains producing failures, these test rods will be periodiculty (avery 2,000 EFPH or less) measured for strain with the use of a remote pro-filometer which is accurate to 1 0.0002 inch.
3) llealth and Safety It is our opinion that the health and safety of the public will not be endangered by this change.
4) Description of Change in Supplement No. 1 to Technical Specifications, add the following Test Fuel Assemblies to Ite;F.2.

Test Fuel Assembly XX One 9 rod subassembly of standard pitch and array shall contain the following: ,

a. Two burnable poison test rods containing borosilicate (Pyrex) glass tubing (o.388 nom. 0.D. x 0.251 nom. I.D.) sealed in type 304 stain-less steel clad (0.4315 nom. 0.D. x 0.019 nom. wall thickness) will be suspended in a type 304 stainless steel RCC thimble guide tube
  • 'IVo Zircaloyd clad rods, containing UO 2 Pellets enriched to 17 4 U-235, approved under change no. 22.

_ ________________________________J

\ ,o

  • Docket No. 50-146 DPR-4 Technical Specifications Change Request No. 30 Page 2 of 3 (0.519 nom. 0.D. x 0.4959 nom. 1.D.). The boros111cate glass is annular in cross section and is supported on the inner side by a type 304 stainless steel tube (o.245 nom. 0.D. x 0.007 nom. wall thickness). These rods may contain a 0.02 inch diameter Al-Co alloy tracer wire scaled in a 0.35 inch diameter titanium tube sus-pended in the central void from an attachnent to the inner surface of the top end plug.
b. The four corner positions and the center position of the subassembly contain dummy fuel rods of the same size and configuration as standard Saxton fuel rods, but contain no fuel. The five dummy rods are ori-ficed at the top and bottom end plugs to permit filling of the rod internal volume with primary coolant.
c. The remaining two rods will be internally pressurized Zircaloy-4 clad ends with nominal thickness of 23.5 mils containing enriched U02 fuel pellets (8.54% maximum U-235 enrichment) operating with tensile strenses of up to approximately 22,000 pai.

The test subassembly may be located in eicher of two peripheral core positiona, N-3 or N-5, and may operate at powe- densitias up to 19.1 kw/ft.

Test Fuel Assembly XXI One 9 rod subassembly of standard pitch and array shall contain the followings

a. The certet ivu ec.J ' ces.v; :0d* cled with type 304 stainless steel Sr.ing a t.ominal thickness of 15 mils containing uranium dioxide (UO2) uniformly enriched to 5.7 w/o U-235.
b. The remaining four rods will be internally pressurized "ircaloy-4 clad rods with nominal thickness of 23.5 mils containing enriched U02 fuel pellets (8.54% maximum U-235 enrichment) operating with tensile stresses of up to approximately 22,000 psi.

s

i

  • sv e a jo Docket No. 50-146 DpR-4 Technical Specifications Change Request No. 30 Page 3 of 3 The test subassembly may be located in either of two peripheral core positions, N-3 or N-5, and may operate at power densities up to 19.1 kv/f+.

Test Fuel Assembly XXII One 9 rod subassembly of standard pitch and array shall contain the followings

a. The four corner rods and the center rod clad with type 304 stain-less steel having a nominal thickness of 15 mils and containing uranium dioxide (UO 2 ) pellets uniformly enriched to 5.7% U-235.

These five rods ere identical to standard fuel rods with the ex-ception that the end closure velds are substandard for test pur-poses.

b. The remaining four rods will be any combination of the following:
1) Internally pressurized Zircaloy-4 clad rods with nominal thick-ness of 23.5 mils containing enriched 002 fuel pellets (8.54%

naximum enrichment) operating with tensile stresses of up to approximately 22,000 psi.

2) Fuel rods clad with type 304 stainless steel having a nominal thickness of 15 mils and shall contain uranium dioxide (UO2) pellets uniformly er.riched to 5.7% U-235. These rods are ider.tical to standard fuel rods with the exception that they .are internally pressurized to produce maximum tensile stresses of approxiuately 36,000 psi during reactor operation.

The test subassembly ray be located in either of two peripheral core positions, N-3 or N-5, and may operate at power densities up to 19.1 kw/ft.

-. . . - . -. . - . .

Retrieved from "https://kanterella.com/w/index.php?title=ML20085F567&oldid=2739733"