ML20085G091

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Application for Amend to License DPR-4,requesting Interim Authority to Load Core III Fuel
ML20085G091
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 03/19/1969
From: Cindy Montgomery
SAXTON NUCLEAR EXPERIMENTAL CORP.
To: Skovholt D
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20083L048 List: ... further results
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FOIA-91-17 NUDOCS 9110240106
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- Telephonei Area 215 929 3601 P. O. Box 542, Reading, Po. 19603 P. O. Box 99, Saxton, Po. 16678 Area 814 635 2937

,/ m 1: arch 19,1969 j

Dochet No. 50-346 license DP?4

' ~ 1 3 Da, ,' *,0mphang lu , Dociald J. S!:ovholt-Accictant, Director for Reactor Operationc Divicion of Reactor Licencin; U.S. Atc:.:ic lhercy Ccc.uiccion Machireton, ').C. 20545

Dear lir. Shovholt:

Three cicned copics and 40 confonacd copics of a request for j interiu authority to load . Core III fuel into the Saxton reactor are enclosed.

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, Eccauco of t'ic ur;cnt need for the use of the Sa:d.on reactor for

! operr. tor training ccc=it:acnto, it is inportant that ue begin loading Coro III into the reactor cc coon us possible. He anticipate that_we vill be ready to begin Icadin; fuci on liarch 27 and are therefore requesting interin

ut.writy to c o co, uithout oucrating the reactor e p, "ing your final action on our Change Roquent 110. 32 in~uhich uc propoced the technical Specifications, for the new core.

Very truly yours,

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C. R. liontgcucry General Manager cc: G. G. Troubridge, Esquire

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9 Docket No. 50-146

  • DPR-4 Technical Specifications Amendment No. 2 to Change Request No. 32 Page 3 of 4 Pages
1. DESCRIPTION OF CHANGE Make the following change to the Saxton Technical Specifications.

Change Section F.1 through F.3.c to read as follows:

F. REACTOR CORE A teactor core having the following features shall be provided:

1. The main coolont shall be light water, and shall serve as the moderator and reflector. The designed effectivt reficctor thickness shall be 10 inches.

2 Mixed natural uranium and plbtonium dioxide enriched initially to a nominal 6.6 w/o Pu02 and previously irradiated in Saxton to a maximum of 33,500 MWD /Mn1 shall be in seven of the nine central fuel assemblies.

The remaining 2 central assemblies will be unirradiated enriched UO 2 fueled, having enrichments which vary from a nominal 5.7 w/o to a nominal 12.5 w/o U-235 Eleven of the enriched twelve peripheral assemblies, except for the test asseniblies described in F.3.f. will be irradiated UO2 assemblies (originally 5.7 w/o U-235 enriched) from Saxton Core 1. The twelfth peripheral assembly will be unitradiated ,

and contain 5.7 w/o U-235, Zircaloy-4 clad fuel.

3. The fuel assemblies shall be suppl'ied as follows:
a. General

Description:

Plutonium fuel assemblies Each main plutonium fueled assembly shall have a total overall length of 50.23 inches with a nominal fuel length of 36.6 inches and.shall approximate a 5.386_ inch square in. cross section.

The fuel rods shall be composed of Zircaloy-4 clad ceramic pellets or vibrationally compacted fuel. The rods shall be arranged in.a square lattice with an initial-0.580 inch center-to-center distance.

Every alternate rod will be a water filled tube so that the center-to-center distance of the fuel rods will be 0.820. The ceramic pellets shall have a diameter of 0.3374 inch (nominal) and a . length '

of 0.3660 inch (nominal).-

One end of each pellet shall be initially dished. The total pellet column tolerance shall be 0.183 inches. initially. The-maximum initit moisture content of the pellet column shall not exceed 30 ppm on a weight basis. The maximum initial nitrogen content of the pellet

___,___.___.,__mm_.. __

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Docket No. 50-146 DPR-4 , .

Technical Specifications Amendment No. 2 to Change Request No. 32

'Page 2 of 4 Pages

  • m F. REACTOR CORE (Continued) column shall not exceed 100 ppm on a weight basis.

The vibrationally compacted loose oxide anall have a total column tolerance of 0.188 inches initially. The maximum initial moisture content of the loose oxide fuel column is 100 ppm on a weight basis. The maximum initial nitrogen content of the loose oxide fuel column is 100 ppm on a weight basis.

The initial clad diameter shall be 0.3445 inches (nominal).

Theinitialdiametralc$earanceforthepelletiredfuelshallbe 0.0071 inches (nominal).

The cladding shall have a wall thickness initially of 0.0233 incines (nominal).

The gap between the pellet column and the internal plug end shall contain sintered aluminum oxide (A123 0 ) discs to provide a minimum end gaps initially of 0.609 inches.

The fuel rods shall be initially hermetically scaled with end plugs welded to the tubing. The end plugs shall be Zircaloy.

The top nozzle of these assemblies is removable,

b. General

Description:

Uranium fuel assemblies from Core I.

Each Core 1 uranium fueled assembly shall have a total overall length of 50.25 inches with a nominal fuel length of 36.6 inches-and shall approximate a 5.386 inch-square in cross section.

The fuel rods shall be composed of stainless steel tubes which contain uranium dioxide fuel in the form of cylindrical ceramic-pellets. The rods shall be arranged in a square' lattice with an initial 0.580 inch center-to-center distance. The pellets shall have the following initial dimensions:

Diameter-(nominal) 0.357 inches Length (nominal) 0.732 inches.

The ends of each pellet shall be dished initially. The total pellet column tolerance shall be 0.366 inches initially..

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Decket !1o.50-14b DTR- 4 Technical Specifications  :

Amendment No. 2 to Change Request No. 32 Page 3 of 4 Pages ,

T. Ri>C10R CORE (Continuedd The initial clad inside diatt.eter sh 12 be 0.361 inches. The I diametral clearance between clad 1.D. and pellet 0.D. chall bc initi ,

ally 0.004 inches.

2 The gap between pellet stack and internal plus end shall contain sintered aluminum ontde (A1 2 03) circular hollov disca, to provide a minimum of 0.374 inch end gap, The initial moisture content of the pel)ct stack shall not e ed 75 ppm on a i weight basis. The fuel rod ends shall be initial.y hermetically F sealed with end plugs welded to the tubing. Those fuci rods which-

, require no further walding shall be clad with 0.015 inch wall of Type 304 welded'stainicss steel 10% cold-worked with a 400 ppm maxi-mum cobalt content. The end plugs shall be Type 304 L or 308-stainless steel. Those fuci rods which require subsequent braging shall be composed of 0.028 inch wall of Type 348 modified carbon, ,

annealed rtainless steci vith a 500 ppm maximum cobalt content.

Th" cnd plugs shall be Tfpc 304 or 304 L stainless steel.-

c. Cencral

Description:

Unitradiated Uranium Fuel Assemblies I

Two of the centrel nine assemb' lies will be unirradiated uranium l fueled and shall have a total overall length of 50.23 inches with a nominal fuel length of 36.6 inches and shall approximate a 5.386 inch square in cross section.

The fuel rods shall be composed of ceramic pelleta clad in Zircaloy-and. stainless steel and the rods shall be arranged in a square lat-tice with an initial 0.580 inch center-to-center distance. The dimensions of the ceramic pe13 cts are given in the addendum.(1)

The top nozzle of these assemblies is removable and held in place with three tie rods, Two of the tie rode in tlie UO2 fueled assem-blies will be fillou with inconel and one of the tie rods will be filled with stainless steel.

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~(1) WCAP-7219 Addendum to Saxton Core 111 Licensing Application (Westinghouse. Con-fidential) Jaly 1968 t

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Dochet !;o. 50-346 l DPg-4 '

Technical Spe'cific$tions i I

Amenhent lio. 2 to  ;

Change Request No. 32 Page 4 of 4 Pages

. F. REACTOR C0!tt (Cont _1 g f

One of twelve peripheral assembif es will contain unitradiated 5.7 w/o U-235 enriened Zircaloy-4 clad uranium fuel. - This assem-i bly has a tejnforced assembly can and rhall 1. ave a total overall i

length of $0.23 inches with a nominal . .1 length of 36.0 inches  !

j and shall approximr te a 5.386 inch % w i in cross section. ,

The fuel rods shall be conposed of Zircalvy-4 tubes which contain ' (

' uranium dio x foe fuci in the form of cylindrical ceramic pellets.

l The rods shall be arransed in a square lattice with an initial  ;

0.580 inch center to-center distance. The pellets shall have the follow.tr.g initial dimens. tons 01ameter (nominal) 0.338 inches Length (nominal)

  • O.000 inches The ends of cach pellet shall be ivitially dished. The total pellet coltano tolerance shall be 0.6$6 inches initially. The 1 initial c19d inside diarneter shall be 0.3345 inches. The dia-metral cle4rance cetween clad I.D. and pellet 0.b. shall be initia11

( 0.0065 inches.

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  • The gap bet;wcen pellet stack and internal plug end shall contain sintered aluminium oxide (A103) 2 circular hollow discs, to provide a minimum of 1.473 inch end nap. The initial moisture content of the pellet stack shall not exceed-30 ppm on a weight basis. The fuel rod ends shall be dnitially hermetically scaled with end plugs velded to the tubing. The end plugs shall be 2trealoy-4.

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