ML17279A648

Draft Lead Test Assembly Program,Wpps 2.

ML17279A648
Person / Time
Site:	Columbia
Issue date:	05/01/1986
From:	Aeschliman L WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
References
TAC-60804, NUDOCS 8712070097
Download: ML17279A648 (17)

Text

87i2070097 PDR ADOCK P t&H1%TON PU3QC PEER SUPR Y QSTR teQEAR fVN'.2 P.Q.KN 9%Ah~~MMIB6AM@AY@IAMB, 88ltk~<tCR BXR 860001 05000397 PDR~~I QQ II~'CI R lI)'I,I.ji'I~(i"'r Bfp'l)I)I'~IlI fy I I g II t'I'".w (l I,/)I'l I W)'qd~4 AC;'86%4~)IX F8't-'I:'l

'lI'(563)3V 66fZ ZZR 609 WOUGH 6GTZ'6'Z 685 a<'ead Test Assembly Program MNP-2 JIEUL0Dli 0 II A IIII A IIY The purpose of the Lead Test Assembly Program is to provide performance information relative to variations fn the desfgn parameters noted below.This test program is part of Exxon Huc'lear's Advanced Fuel Development Program.This test p~ogram will involve fabrication of two fuel assembly types, shown in Figures I and 2.Each of the assemblies will incorporate segmented and full-length characterized fuel rod configurations.

The segmented rods shall be designed with the capability of being removed from the assemblies at different burnup levels and replaced with rods of appropriate enrichment.

The removed rod will subsequently be separated and stored for later ramp testing.The assemblies are identical in design with the XN-1 reload except for the differences noted below.In addition to characterization, various test fuel rod configurations will incorporate the following variations fn design parameters:

I)Variatfons fn pellet microstructure (grain size and pore size).2)Yarfatfons in pellet fabrication process (AOU conversion, Dry Conversion, duplex , and gadolinia pellets).3)Variations fn cladding (normal production and beta heat-treat).

4)A plenum spacer inse)t which will allow quantitative, non-destructive fission gas analysis with poolside gamma spectroscopy measurement.

This spacer insert will be fncorporated only in full-length test rods.*Diinl.er.

pn)le~~fncori~oraf e.,s, net.>>rigel.

uranium coze surrounded by a higher enriched uranium annulus, co-pressed h, ground to thc stan<'ard pellet configuration and producing a pellet with an average enrichment approximating that of'standard pellet.9S I68 10'Qe'98<'61K ZZR 6BQ Wolfe 0 1 I~

SUHHARY OF ROD~Y~S Assemblies will contain segmented and full-length characterized fuel'rods with type and location as specified in Figures l and 2.The remaining fuel rods required to complete an assembly array shall be of standard production design.A summary of the various characterized test rod types and quantities is given in Table l.HARACTER IZATIO U H Y Table 2 summarizes the measurements to be performed for characterization.

LICEHS NG CONSIDE T OHS Hechanical, thermal hydraulic, LOCA/ECCS, plant transient and neutronic design analyses were reviewed for the Lead Test Assemblies.

The results of this review indicated that the Lead Test Assembly design has comparable margin to limits as the standard XN-I Reload design.In no case are the test rods the limiting rods in the design analysis.9Q: 60$0;40'98 i--66$Z ZZR 60Q W083 I

Table 1 Summary of Required Characterized Rods and Segments Rod~Te Rod Segments Archive Cladding Rtt.~ll d~51~0 Pellet Oescri tion Pellet Enrichment Total 16 Rods N/A N/A N/A N/A H/A Production Production Production Production Production Production Beta Heat Treat Beta Heat Treat Beta Heat Treat Beta Heat Treat Beta Heat Treat Beta Heat Treat Beta Heat Treat Production Beta Heat Treat 10 Archive Samples Duplex Gadolinia Gadolinia Ory Conversion HL HL ADU-Large Pore ADV-Small Pore ADU-Large Grain ADU-Small Grain Duplex Ory Conversion ADU-Production Duplex AOU-Large Grain N ADU-Small Grain N AOU-Large Pore 0 J l I Jl

~o~~s I~~Table 2 Summary of Characterization Heasurements o PelIets Open/closed porosity Hensur ation, density, weight, volume Chemistry Ceramography (grain size)Resinter test Pore size Dish depth and volume o~C1 add I.D., O,D., wall thickness{ultrasonic 3-D)Standard gC mechanical test Texture measurements Contractile strain ratio (axial and circumferential)

Cladding I.D.surface roughness Grain size and hydride orientation Standard chemistry Rod length Plenum length Fuel column length Full length X-ray As-fabricated 0~D~MlasulLmcnl&SQ:6B$0'QB'98 s 661K ZZR 6BQ W083

.f l

~E~I~~t 4 4~~~o Se men ed uel ods Overall fuel rod length and segment length Plenum length Fuel column length Full length X-ray showing pellet/pellet interfaces As-fabricated O.D.measurements

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~e e\I o,l~~~~"FI e~~4 C r~Full-Length Rod Type F MI D E-Full-Length Rod Type E-Full-Length Rod Type L-Full-Length Rod Type d'I IVI)'IVI I//l I/I I I//II/'/l/I/I III g I//Full-Length Rod Type L Segmented Rod Type A~Segmented Rod Type B ull-Length Rod Type K Figure 1.Rod Hatr)x-Assembly 1 (see Table 1)6S:60'l0'00'98<

6615 ZLR 600 II08d O I~'I 1'I~

R~~Full-Length Rod Type H Full-Length Rod Type G Full-length Rod Type L Full-Length Rod Type 0 ,,I////g)i/)$/I I,I I I/)I///)/)//'////~I II/().',//II R~, I 1 II/il/I I))'l'//')I I I I/)I~I////I I R I I I g I ,I//I I in'I~'ull-Length Rod Type L~~~I..'.'"""~Ac~R~" Typ~C-Segmented Rod Type D Full-Length Rod Type K Figure 2.Rod Hatrlx-Assemb1y 2 (see Yab1e 1)00:Ol lO'QO'98 R OOQ WOUGH

~~, n'l April 30, 1985', I:STRIBUTION:M/0 Enclo'sJre ument Control,(50-397)

~¹2 Reading EHylton JBradfute DOCKET NO(S).50-397 Nr.G.C.Sorensen, f<anager Regulatory Programs Washington Public Power Supply System P.O.Box 968 3000 George ktashington May Qgig~, Nash)ngton 99352 HPPSS NUCLEAR PROJECT NO.2 The following documents concerning our review of the subject facility are transmitted for your information.

D Notice of Receipt of Application, dated D Draft/Final Environmental Statment, dated D Notice of Availability of Draft/Final Environmental Statement, dated D Safety Evaluation Report, or Supplement No., dated D Notice of Hearing on Application for Construction Permit, dated D Notice of Consideration of Issuance of Facility Operating License, dated g3 Monthly Notice;Applications and Amendments to Operating Licenses Involving no Significant Hazards Considerations, dated D Application and Safety Analysi's Report, Volume D Amendment No.to Application/SAR dated D Construction Permit No.CPPR-D Facility Operating License No., Amendment No., Amendment No.dated , dated , D Order Extending Construction Completion Date, dated D Other (Specify)

Enclosures:

As stated Office of Nuclear Reactor Regulation cc: See next page OFFECS+SURNAME+DATE+NRC FORM 318 (1/84)NRCM'0240 II 1