ML20085E686

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Change Request 18 to License DPR-4 Re Fuel & Cladding Development
ML20085E686
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 05/07/1965
From: Neidig R
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110210111
Download: ML20085E686 (7)
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SATI'ON h"JCLEAR EXPERIMENTAL CORNRATION DOCKli NO. 50 146 LICESE DPR-4 Change Request E18 l

1. Applicant hereby submits Change Request No. 18 in compliance with leragraph 3B of License DPR.4 for change of the Technical Specifications to be authorized by the Com:nission as provided in 10 CFR 50 59.

l SAXTON NUC1EAP EXPERIMEN1'AL CORPORATION  !

By /s/ R. E. Neidig President -

ATTEST:

~

,. .s

/s/ R. E. Sypher  ;. (

Secretary (S E A L)

Sworn and subscribed to before me this 7th day of May , 1965 (S E A L) /s/ Martin A. Kehr Notary Public Muhlenberg Township, Berks County PJ Commission Ecpires Feb. h,1966 9110210111 010424 FDR FOIA DD:0K91-17 PDR

i Ibeket No. 50 146 DPR 4 Technical Specification Change Request No. 18 Page 1 of 6 Twges l

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1) Description of Chance l

In Supplement No.1 to Technical 3pecifications, page 2, change Item F.2. '

to read:

Uranium oxide (Uo 2 ) enriched to 5 7%. of U-235 shall be used in the fuel ,

assemblies, except that the teet fuel assembl.ies listed below having '

, enrichments and other chameteristics as described any be inserted in the reactor. In test fuel assemb1Acc the fuel rode as described may be replaced with regular fuel rods, that is, enviched to nominal 5 7%,

U-235 and constructed as described in Technical Specification F.3.

Test Ascembly No. 1 one 61 rod assembly containing rods of the numbers and types listed in the following tables No. of Clad Pellet ibds Cladding Thickness (1) Diaceter Enrichment Peak Power kb) 304 SS 805 nils (U)- o.294 in. 071v/o 31kv/ft 4(5) 304 SS 80 5 o.294 o.29 v/o 2.2 3 304 SS 15 o.357 (2) 16 3 304 SS 15 0 357 (2) 16 3 304 SS 15 0 357 (2) 16 3 304 SS 15 o.357 (2) 16 3 16-20 SS 15 o .3 57 (2) 16 3 348 SS 15 o.357 (2) 16 -

3 304 SS(9) 15 o.357 5.69v/o 13 5 3 304 SS 15 0 357 569v/o(3) 13 5 3 Zr-4(6) 23 7 o.337 5.69 v/o 12.0 5 Zr-4(6) 23 7 o.337 6.1 v/o 13 5 3 Zr-2(6) 23 7 o.337- (2) 14 3 Zr-2(6) 23 7 o.337 (2) 14 (Ni Free) 3 Zr-4(6) 23 7 0 337- (2) 14-3 Zr-4(10) 23 7 0 337 (2) 14 3 Zr-4(8I 23 7 o.337 (2) 14 3 Zr-4(7) 23 7 o.337 (2) 14 3 Zr 4(6) 23 7 o.337 73v/o 16 l

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DPR-4 Technical Specificati Change Request No. 16 Page 2 of 1 Pages Notes for Table (1) 0 391 in. 0.D. nominal.

(2) All rods First 14 are pelletsfree standing 5 69 v /o Next 5 pellets 6.81 v/o Next 12 pellets 6.45v/o Next 5 pellets 6.81v/o Nex+ 13 pellets f.69v/o

3) Contains approximately 100 ppm boron as zirconium diboride
4) RCC element with perforated guide tube
5) Rc0 element with solid guide tube
6) Autoclave pre-oxide on 0.D.
7) Autoclave pre-oxide on 0.D. and I.D.
8) Furtmee pre-oxide on 0.D.
9) Compartmented rod, i sections O As pickled, no pre-)*1de treatment 1 RCC rod 0.D. is 0.461 in. nominal.

Test Assemblies 11 and 111 Test Puel Test Fuel

/.ssembly No. 11 Assembly No. iii 9-Rod 9-Rod Subassembly Subassembly First 14 penets 5.6% 5.69%

Next 2 pellets 9 19% .7 30%

Next 3 penets 8 57 % 6.81%

Next 12 penets 8.13% 6.46%

Next 3 pellets 8.57% 6.815 Next 2 penets 9 19% 7 30%

Next ik penets 5 69% 5.69%

NME: The 9-rod subassemMy S the first column shan not be used at reactor power levels greater than 20 MWt.

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Test Fuel Aesembly No. iv One 9-rod subassembly shall have four corner rods clad with Zircaloy k l

having a nominal thickness of 23 7 mils and shall contain umnium oxide (UO2 )

enriched to 6.1% U-235 The other five mda chall be clad with Type 304 stainless steel having a nominal thickness of 9 5 mils and shall contain umnium oxide (UO2 ) enriched to 5 7% U-235.

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- LPB-4 Technical Specificatici Chance Request tio. 18 Pace __3,of 6 Pagen Test Fuel Accembly 1;o. v One 9-rod subancembly chan have four corner rods clad with Zircalo,,

having a nominal thickness of 23 7 mils and shall contain uranium oxide (b enriched to 6.1% U-235 The other five rode chan be clad with TLv 304 stainless steel having a nominal thickness of 9 5 mile and shan contain uraniwn oxide (002 ) having the same enrichment as Test Fuel Assembly tio. iii.

Tect Fuel Assembly fio. vi One four-rod subassembly shall have rods clad with Type 3Dl. stainlesh steel having a nominal thickness of 23 5 mils and ahen contain uranium dioxide (U02 ) fuel g liets uniformly enriched to 8 3 v/o U-235 One of these rods may contain up oo 100 ppm boron initinny as zirconium diboride.

Test Fuel Assembly flo vii One 9-rod *ubassembly shall have four corner rods and the center rod ,

clad with Zircaloy-4 having a nominal thickness of 23 7 mile and chan contain unnium oxide (UO 2 ) uniformly enriched to 7 3%. Two of the other rods shan be clad with Type 304 stainless steel hav4ng a nominal thickness of 15 mile and shan contain umnium oxide (UOp ) uniformly enriched to 5 7%

U-235 One other rod shall be clad with Type 304 stainlesa steel having a nominal thickness of 16.1 mile, shan contain unnium oxide (UOp) having a content of 0.29% U-235, and shall be concentrically located witEl. a solid stainless steel guide tube. The remnining rod shall be clad vi ch Type 304 stainless steel having a nominal thickness of 16.1 m as, shall contain uranium oxide (UO 2

) having a content of 0 71% U-233 and chan be concen ,

trically located within a perforated stainless steel Guide tube. ,

r Test Fuel Ascenbly lio. viii

(

One 9-rod subassembly shall have three corner rods clad with Zircaloy-4 having a nominal thickness of 23.7 mile and chan contain vibrationally compacted uranium dioxide (UO enriched to 7 2% U-235 and compac.ted to 86 + 2% tneoretical density.T 2)he fourth corner rod and the central rod shall l be clad with Type 304 stainless have a nominal thicknese of 15 mils and l shan contain vibrationally com 2 l

U-235 and compacted to theoretical 85,+ 2% pacted density. uranium Three of the dioxide remaining (UO ) enric

! rods shan be clad with Zircaloy-4 and chan contain uranium dioxide (UO2) penets 0 337 inches in-diameter which are enriched to 6.1% U-235 One of these rods shan have a previous irradiation exposure of N 7500 megavatt days per metric ton (M4D/MP) and chan contain a 15 mil diameter hole machined through the clad. The second of these roda shall have a previous irradiation exposure of ~7500 MJD.MP. The third of these rods shan have a 15 mil diameter hole machined through the clad. The final rod shall be clad with sensitizedType304stainlesssteelandshallcontainuranivadiny.ide(UO) 2 penets enriched to 5.69% U-235 and the ten central penets shall have 20 mil chamfers on both ends.

, DPR-k Technical Specification Change Request No. 18 Page h of 6 Pages Folloving a period of irradiation, the two defected, Zirealoy 4 clad rods may be replaced by sirilsr, defected, unirradiated Zircaloy-4 clad rods.

Test Fuel Assembly No ix One 9 x 9 fuel assembly shall contain 51 rods clad with Type 30k stainless steel of 15 mils thickness and shall contain uranium dioxide (UO 2

) fuel pellets of 5.69% U-235 enrichment. This assembly is made by removing the central 21 rods from a normal 9 x 9 f uel assembly. The space left by removal of the central 21 rods shall be filled by a plug consisting of a stainless steel tube 0.125 inches thick and 2 75 inches in diameter velded to perforated stainless steel end plugs. The end plugs shan be designe.d so that flow througn the plug vin experience the same enthalpy rise that is experienced by flov through a norma' fuel assembly. The plug shall contain three concentrically mounted stainless steel pipes 0.125 in. thick and of 2.125,1 50 and 0 75 in, diameters, respectively. Horizontal restraint for the plug shall be provided by the grids of the fuel assembly. Vertical support for the plug shan be provided by a 15 in. diameter stainless steel pipe extension of the reactor head port flanEe. When ChanEe Request No. 16 has been approved by the Atomic Energy Commission, this plug may be removed and replaced by a fueled super-critical loop pressure tube assembly.

Test Puel Assembly No. x One 9-rod subassembly shall have eight rods clad with Zircaloy-k having $

a nominal thickness of 23.3 mils. The fuel shall be mixed natural uranium-plutonium dioxide enriched to 6.6 v/o PuO . Four of the rods shall contain vibration compacted fuel and the remainink four shall contain sintered cemmic pellet fuel. The ninth rod position vill be a flux thimble for use with in-core instrumentation.

Tes+ ' bel Assembly No. x1 One 9-rod subassembly shan have the center rod and the four corner rods clad with Type 304 stainless steel having a nominal thickness of 15 mils and shall contain uranium dioxide (UO2) uniformly enriched to 5 7% U-235 Two of the remaining rods shall be clad with Zircaloy-4 having a nomical thickness of 23 mils and shall contain unnium dioxide (UO2 ) unir rmly enriched to 6.45 v/o U-235 The third rod shall be clad with Zirealoy-4 having a nominal thickness of 23 mils and shall contain uranium dioxide (UO2 ) uniformly enriched to 6.1 v/o U-235 This rod shall have a previous irradiation exposure in excess of 13,0001&D/MrU. The last rod shall be clad with Zircaloy-4 having a nominal thickness of 2, mils and containing uranium dioxide (UO2 ) unit rmly enriched to 7 3% v/o U 235 and shall have a previous irradiation exposure in excess of 3000}&D/)EU.

N

DPR-4 Technical Specification Change Request No. 18 Page 5 cf 6 Pages Test Ceisules Test capsules containing non-fuel material may be inserted in any of , ,

eleven du=y fuel locations adjacent to the reactor core region or in any of the eight irradiation sample tubes on the periphery of the core provided that:

1) Prior to irradiation, the design of the test capsule has been evaluated by the SNEC Safety Comittee and found acceptable with regard to physical, thermal and hydraulic performance and effect on core reactivity, neutron flux and reactivity coefficier.s.
2) No foreseeable failure of a test capsule could result in damage to any core co=ponent or in any manner alter the ability of the control system to function.
2) Parpose of Change The purpose of this chan6e is to permit insertion of test fuel assembly xi into the reactor. The scope of this experiment involves modification of the improved grid design subassembly as outlined in Ctense Report No.12.

The subassembly will contain the five non-removable roda previously in the subassembly plus two new fuel rods and two previously irradiated fuel rods.

The objectives of this experiment are to provide information on irradi-ntion effects on various clad surface treatments and to extend the iradiation exposure of the previously irradiated rods.

3) Safety Considerations The design character 1.stics of the fuel in test assembly xi are given in Table 1. The operation of test fuel assemblies containing rods similar to those in test assembly xi in Saxton has been reviewed in the Addenda to the Phase I Safeguanis Report so that operation of this test assembly does not present any significant hazards considerations not described in the Saxton Final Safeguards Report 'tnd its Addenda.
4) Health and Safety It is our opinion that the health and safety of the public vill not be endangered by this change.

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Technical Specifiestion Change Request No. 18 DPR 4 Pnge ,6 o f 6 Pages TABLE 1 FUEL IOD IJJIGN PARAMETEIG FUR TtiE Mo9IFIED IMPROVED GRID DESIGN 3x3 TEST ArumBLY x 23 5 s t Estimated !&tximum l

Power Density - kv/ft Clad Fuel Pellet Fuel Rod No. Type Clad Material Thickness ( Diameter Enrichment Periphery Center l

753, 762 4.6 756, 755 Non-Removable (7) 304 SS o.015 in. o.357 in. 5 69 w/o 13 5 7 57 102(2) Removable Zr-4 (Ni Free) 0.023 in. o.337 in. 6.1 v/o 4.6 13 5 Zr 4 0.023 in. o.337 in. T.3 v/o 5 35 16.o 323(3) Removable zr 4 0.023 :i. o.337 in. 6.45v/o 4.75 14.0 702 Removable zr-4(5) 0.023 in. o.337 in. 6.45v/o 4 75 14.0 703 Removable I

(1) All mis are " free standing" with 0 391 in. o. D.

(2) Previously irradiated to approximately 13,000 WD/Mru.

(3) Previously irradiated to eppmximately 3,000 WD/MTU.

(4) Clad surface is burnished and autoclave tested.

(5) Clad surface is btrnished only.

(6) Enrichments are unifom thmaghout rod.

(7) Previously irradiated.

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