ML20207F998

Rev 0 to Final Rept Criticality Safety Analysis,Dc Cook New Fuel Storage Vault W/5.0% Enriched 17 X 17 Fuel

ML20207F998
Person / Time
Site:	Cook
Issue date:	07/31/1988
From:	Gerrald L SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:
Shared Package
ML17325A898	List: ML20207F998 ML20207G007 ML20207G022
References
ANF-88-057, ANF-88-057-R00, ANF-88-57, ANF-88-57-R, NUDOCS 8808230353
Download: ML20207F998 (21)

Text

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6 FIN AL REPORT E

d CRITIC ALITY S AFETY AN ALYSIS D.C. COOK NEW FUEL STOR AGE Ic

?

V AULT WITH 5.0 PERCENT ENRICHED 17 X ;17 F U E L

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E-JULY 1988 I

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ANF-88 057, Revision 0

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t FINAL REPORT CRITICALITY SAFETY ANALYSIS 0.C. COOK NEW FUEL STORAGE VAULT WITH 5.0 PERCENT E!! RICHE 017X17 FUEL t_

F Prepared By L. D. Gerrild Licensing Specialist-Criticality Safety irK SE

~~

a July 1988

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ANF-88 057, Revision 0

ssue Date:

7/14/88 x

FINAL REPORT CRITICALITY SAFETY ANALYSIS 0.C. COOK NEW FUEL STORAGE VAULT WITH 5.0 PERCENT ENRICHED 17X17 FUEL T

Prepared by:

h!

Gefrald, Criticality Safety Specialist Date Corporate Licensing Reviewed by:

b V) y -g- //

j J. E. Pieper, Criticalit/ Safety'3pecialist

' Date Corporate Licensing Approved by:

./, #

7- / 2 - f f a

C. W. Malody, Manager Date Corporate Licensir.g v-r

2 CUSTOMER OlSCLAIMER IMPORTANT %CTICS RE' ARDING CONT 11NTS AND USE CF mtS QQCUME:sf PLEASE RE.AD CAREFULLY Acvanced hear 8ueis Corocraten s *airartties anc ooresentatens :en-corneg me suotect matter of mw oocuraent are mose set 'orm n me Agreement between Acvancoc Nucear 8 eis Corcorsoon ano no C.stomer :ursuant to u

wesen me oocurnent.s sausc. Accorcegry, exceot as atnerwise ev.ortes4v :ro-need e sucn Agreemeret. seetner -ovancoc Nue: ear Nees Ccrocraten ao any person acong on as senast masse any eartmN or ooresentaten. encrossed or monoc, enn weet to me accuracy, :ornoretenosa. Or.seiu6 ness of me nfor.

manon contaaneo e me coeurnent. or mat the use of any.ntorn. aron accatarus.

metnod or procese sacosed :n mis document wui not ntnnge onvateiv : weed ngsts; or assumee arry asomtree man eeoect *o to ase of any ntormaten. ao-pararus. metnoc or procese esoosec in mis cocument.

The informanon contaced noroin S W me soie m of Catomer M orOer to avoso irnOesrment of rigftts of AcyanCec Nucear 8uees Corocraton e ostents or evermons wecn may es ceruced e me.ntormaten contaceo 'n mis coc",amerft. Se recpervt. Dv ts accoolance of mis coCument. agreet w *o

.mouen or make pucac use (in me catent use of me termi of suce inermaton untu so autnorued c enteg Dy Advancoe Nue: ear Fueis Corocraten or unte after sin (6) moretna tosevang terminaten or onceraten of t ie amresa4 Agreernent and any extenson moroof. un+ees otneronse excreasty provcea n me agreement. No ngnes or 'coneee in or o artw carents are >rnoised my +e 'urnisaq of mis cocu-ment.

ANF-P45 47ta

• 2 571

ANF-88-057, Revision 0 V

FINAL REPORT CRITICALITY SAFETY ANALYSIS 0.C. COOK NEW FUEL STORAGE VAULT WITH 5.0 PERLENT ENRICHED '7X17 FUEL 1

1.0 INTRODUCTION

j v

The critical ity safety of 5.0 percent enriched 17x17 fuel assemblies in the t

new fuel storage vault is conservatively demonstrate' in ac c o,'d a n c e with NUREG-0800 and ANSI /ANS-57.3-1983.

2.0

SUMMARY

The spent fuel storage rackr meet the applicable criticality safety criteria subject to the limits and controls iisted below.

Fuel Design:

As specified in Section 3.0.

g h

Storage Rack Design:

As described in Section 4.0.

f Fuei Handling: Unless covered by a speci fic analysis, all n-trans1s oundles shall be maintained at least 12 inches edge-edge from all other bundl as.

3.0 F'JEL DES LG The nominal bundle design parameters assumed in this evaluation are listed in T1ble 1 s

2 ANF-88-057, Revision 0 1

TABLE 1 FUEL DESIGN PARAMETERS Parameter Desian Value Model Value I' < Y Enrichment (wt?. U-235) 5.0 (max.)

5.0 "A.

i Pellet Diameter (inch) 0.3030 0.3030 n*b @'; -

.. ir Pellet Density (P.TD) 94.0 : 1.5 95.0

,,' I j Pellet Disn (Volf.)

1.0 0

Pellet Stack length (inch) 144 144 (min.)

' lid Clad 10/00 (incn) 0.310/0.360 0.310/0.360 N

Inst. Guide Tube ID/0D (inch) 0.448/0.480 0.448/0.480(l)

Number of Inst. Guide Tubes 25 25(1) h 4 14 V.'-

Rod Pitch (inch) 0.496 0.496(1) 1

..a :t 1

The tabulated values were used in explicit models of the nominal design.

As described in Section 7.1, sensitivity studies were performed with generic bundle designs which had different values for the noted parameters.

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}s, The arrangement of the rod types in the bundle is shown in Figure 1.

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CIGURE 1

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R00 ARRANGEMENT WITHIN BUNDLE i;,

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F - FUEL R00: G - GUIDE TUBE; I - INSTRUMENT TUBE

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4 ANf-88-057 Revision 0 40 S1SHM._f1LQHETRY The racks were modeled using naminal dimensions.

The array descriptions celow, such as

~'MxN", imply M units in the east-west directico and 1 Jnit$

In

' he norti1-south di rect ic.1.

Sundles are stored in a 2x4 array of banks with a 9x2 array of bunales per aanK.

Since room is available for an additional lx4 array of Dara to the east of the 2xt. array, a 3x4 bank array was modeled for tnese calculations.

fhe bunales are on 21 inch centers within the banks.

The banks are on 234"x64.5" canters.

Concrete reflection was applied at the four wall s, the f'oor, and at 12 feet above the fl oo r.

The fuel length was 12 feet.

7 Uniformly interspersed water with a density in the range 0 to 1.0 gm/cc was within and between the bundles.

5.0 CALCULATION METHODS All computer codes and cross sections used in this evaluation are part o' the SCALE (I) system which has been extensivaly benchmarked against uota from critical exper'ments.

Sixteen groep cross sections were prepared using 80NAMI/NITAWL.

7 K

or k calculations were performed using KENO-Va or XSORNPli.

g7 inf M_tAggLVerificatiqn 5.1 f

The SCALE cooes anc cross sectlans nive oeen extensively cencnmar<ea against data from critical experiments.

m 5

ANF-88 057, Revision 0 5

Supplemental benchmarking was performed immediately before the calculations a

E reported here.

The (qperimr:nts selected are described in References 2 and 3.

The experiments were selected particularly to establish the calculational bias

[

for the poisoned spent fuel storag9 rack analysis but virtually identical results have been obtained in previous calculations for aon-poisoned

{

experiments.

The results are listed in Table 2.

It i

I TABLE 2 BENCHMARK CALCULATION RESVLTS FROM KENO-Va 16 GROUP CROSS SECTIONS k

Case No.

Calculated k

{

Reterence2'Excebents 2378 1.00395 0.00376 2384 1.00037 0.00306 2388 0.99886 0.00341

.y

[

2420 1.00038 0.00367

[

2396 0.99443 0.00360 2402 1.00694 0.00283 2411 1.01223 0.00286

[

2407 1.00647 2 0.00332 2414 1.00967 0.00327 Reference 3 Exoeriments 9

1.00092 1 0.00487 y

10 1.00181 ! 0.00412 11 0.99786 1 0.00413 12 0.99885 :

.00487 31 1.00442 0.00421 E

l The average and standard deviation are 1.00265 and 0.00490, respectively.

i m

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6 ANF 88 057, Revision 0 The 95 percent upper limit (UL) on t..a EN0 k,ff is calculated by pooling the KENO variance and the bias variance.

For example, the 95 percent UL k,ff for case 2378 is calculated below.

k,ff (95Y. UL) = 1.00395 - 0.00265 + 1.66

• SQRT(3.76E-3**2 + 4.90E-3**2)

=

1.00130 + 0.01025 - 1.01155.

The 1.66 multiplier is the one-sided Student t (5Y.) with about 80 degrees of freedom.

The KENO results are for 83 or 103 generations of neutrons.

Thus, the 1.66 multiplier is conservative.

For reference, the bias-corrected results are reported in Table 3.

TABLE 3 BIAS-CORRECTED 8ENCHMARK RESULTS K

Case No.

K,ff (959,fbli 2378 1.00130 0.00376 1.01155 2394 0.997716 0.00306 1.00731 2388 0.936206 0.00341 1.00612 2120 0.997726 0.00367 1.00789 2396 0.991776 0.00360

'1.00187 2402 1.00429 0.00283 1.01368 2411 1.00958 0.00286 1.01900 2407 1.09382 0.00332 1.01364 2414 1.00702 0.00327 1.01680 9

0.998266 1 0.00487 1.00973 10 0.999156,0.00412 1.00978 11 0.995206 0.00413 1.00584 12 0.996196 1 0.00487 1.00766 31 1.00177 0.00421 1.01249

___________.__m_

7 ANF-88-05/, Revision 0 The 95 percent upper limit (UL) which is the parameter used in judging acceptability excaeds 1.0 in every case after bias correction.

The average 95% UL is 1.0102. Therefore, the results remain conservatively.

All k,ff results in this report have a21 been bias-corrected, unless otherwise stated.

Therefore, these results would tend to be conservative by about 0.0027.

I p.

6.0 CALCULATION RESULIS 3

4 The racks were conservatively modeled with uniform interspersed moderation and with concrete reflection.

The 11put for a typical KEN 0 run is attached for reference.

The KENO-Va results are listed in Table 4.

TABLE 4 NEW FUEL RACES 3X4 BAliX ARRAY 5.0% ENRICHED FUEL INTERSPERSED M0QERATION EFFECTS KENO-Va RESULTS Interspersed Water Density (Vol%)

k,ff 2.5 0.8771 0.0045 5

"0.8794 0.0045 1.5 0.8530 0.0048 10 3.8316 t 0.0043 100 0.9359 : 0.0039

8 ANF-88-057, Revision 0 The fully flooded result is actually that for a single bundle surrounded oy 30

=

cm of water.

As will be shown in Section 7.2, flooded bundles on 21-inch centers are effectively isolated; i.e.,

the bundle-bundle interactions are negligible.

P F

The k for an infinite array of infinite length fuel rods with zero inf interspersed moderation is 0.8340 using XSORNPM.

The finite system reactivity I

would be less than this value.

b The peak reactivity occurs at full flooding.

If all cells had oeen on 21-inch centers without banking and spacing between banks, the peak reactivity woula have been higher at it would occur with low density interspersed moderation.

r h

If the iron / steel structural members of the rack had been modeled, the k 77 would have been lower than reported here.

E The one-sided 95 percent upper limit on the blas-corrected peak ke#f ' S

=

h keff (95*. UL) 0.9359 - 0.00265 + 1.66

• SQRT(0.0039"*2 + 0.0040**?) - 0.9333

+ 1.66

• 0.0063 - 0.9437.

-=

7.0 SENSITIVITY STUDIES

==

=

b lhe key parameters controlling reactivity are:

m 1.

Fuel Enrichment - The enrichment is fixed at tne maximum credible value

( 5. 0*.).

m 2.

Moderation - Data on interspersec moderation effects within the new fuel storage vault are in Section 6.0.

Other moderation eff ects are covered in Section 7.1.

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Bundle-Bundle Soacina - Spacing effects due to dimensional tolerances.

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eccentric positioning, etc. and those due to bundle handling accidents

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are coverad in Section 7.2.

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b 7.1 Moderation Effects (Full Floodinal

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h. a i qs'j The nominal bunctie design (264 fuel rods and 25 Instrument / guide tubes) is

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iN composed as follows:

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TABLE 5 4.gl V-FUEL ZONE COMPOSITION

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NOMINAL DESIGN VALUES 9;y

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f. j

.i, A Material Volume %

,j p}, i

.%. g :...,:

sd, V,

...M. -

U02 26.77 r

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?., p aB Pellet Clad Gap-1.25 l(i

y. ~

C1ad (Zr) 10.59

[2;

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Moderation (water) 61.38

f. l:,

t

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{f}['

Total 99.99

n. ; n

. h..

{ 't,

-y }

The average water / fuel volume ratio (Vw/Vf) is 2.29.

If the entire 17x17 U.._

array was fuel rods, the Vw/Vf would be 2.00.

Since reactivity may be changed

.w y j Q,:

if fuel rods are removed from the bundle, generic bundle designs with Vw/Vf lll.l ij{

ratios in the rangs 2.0 - 4.0 were evaluated.

The generic bundles were

};

I' k modeled with the nominal pellet and gap dimensions but with clad 00 and pitch 4.i.' ;

. [

values to yield the designed Vw/Vf and the bundle-average clad volume.

The

{[.

' ' '.. ~

calculation sequence was as follows.

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Q,

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1.

Self-shielded 16 group cross sections were generated using BONAMI/NITAWL.

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10 ANF-88 057, Revision 0 2.

Cell weighted cross sections were generated using an XSDRNPM model of an infinite rod array.

3.

These cell-weighted cross sections were used to simulate a

8.432"x8.432"xinfinite bundle in KENO-Va or XSDRNPM models of bund'st in s

an infinite array or a single bundle with full water reflection.

Generic bundle characteristics are listed in Table 6.

TABLE 6 GENERIC BUNDLE CHARACTERISTICS Clad 00 Pitch Total Removed l

y,yLY,f (cm)

(cm)

Fuel Rods Fuel Rods 2.0 0.92376 1.26516 278.3

-14.3 (14.3 rods in guide tubes) 2.29 0.92426 1.31814 264.0 0.0 (nominal) 2.50 0.92462 1.35443 254.7 9.3 3.0 0.92548 1.43816 234.9 29.1 3.5 0.92634 1.51729 217.9 46.1 4.0 0.92720 1.59249 203.2 60.8 Listed in Table 7 are XSDRNPM results ror generic rods / bundles.

The results include the k for an infinite rod lattice (cell-weighting run) and the k,77 inf for a single bundle with full water reflection (FWR).

The bundle was modeled as a 12.0834 cm radius cylinder (infinite length) surrounded oy 30 cm of water.

V c

11 ANF-88 057, Revision 0 TABLE 7 FUEL R00 REMOVAL EFFECTS (GENERIC RODS /8UNOLES) 15Q&NPM RESULTS (INFINITE LENGTH RODS / BUNDLES)

Rod FWR Bundle Vv/Vf

_ti n f-eff 2.0 1.5038 0.9256 2.29 1.5163 0.9373 2.5 1,5231 0.9438 3.0 1.5311 0.9528 3.5 1.5305 0.9553 4.0 1.5251 0.9536 The Tablo 7 results indicate a peak k,ff near 0.955 assuming that fuel rods are withdrawn in the optimum sequence.

Give the conservative model useJ in these calculations, the fact that about 10-20 optimally removed rods are r,9' tired to achieve a 0.95 k and the

eff, subcriticality with any ' number of removed rods, safety of a single bundle is assured with any credible number of fuel rods removed (or added).

The KEN 0 result for an explicit model of a -single bundle (264 fuel

rods, 25 instrument / guide tubes,12 feet long) flooded and reflected with full density water is 0.9359 t 0.0039.

A single flooded bundle was also modeled using the homogeneous (cell-weighted) cross sections.

The KENO-Va results from a cylindrical model (as in XSORNPM) and from a cuboidal model are 0.9388 0.0039 and 0.9305 0.0036, respec.tively.

Therefore, the cross sections (heterogeneous-homogeneous) and the codes (KENO-XSDRNPM) agree very well.

12 ANF-88 057, Revision 0 w-7.2 Bundle Soacina Effect1 An infinite array of generic' bundles with the nominal Vw/Vf (2.29) were modeled with XSORNPM.

The system modeled was fully flooded.

The infinite length bundles were spaced as indicated in Table 8.

7ABLE 8 PUNDLE SPACING EFFECTS INFINITE X JNFINITE BUNDLE ARRAY

+

FULLY FLOODED XSDRNPM RESULTS n

Center-Center Spacing Edge-Edge Spacing finch) finch)

_h inf-12 3.568 1.0931 14 5.568 0.9839 16 7.568 0.9517 18 9.568 0.9420 20 11.568 0.9388 21 12.508 0.9382 An infinite array of, bundles is acceptable with all center-center spacings greater than about 16-18 inches.

The storage cell guides form a 9.0"x9.0"

(

square.

If four bundlas were brought together at the near edges of their contiguous guides, these bundles would be on 20.432 inch centers.

Therefore,

+

no credible combination of dimension tolerances and eccentric positioning could result in spacings approaching 18 inches or less.

l l

i r

13 ANF-88 057, Revision 0 Criticality can result if two bunc'les are brought together in a flooded system.

Since a minimum spacing between bundles has been specified and since flooding of the vault is an independent and very unlikely occurrence, no single accident condition in the new fuel vault can result in criticality.

l 8.0 KENO INPUT LISTING The new fuel vault model, including compositions and geometry, is in the-listing below.

The water density was changed for other runs reported in Section 6.0 DC COOK, NEW FUEL RACKS, 5.07. ENR, 107. INTERSPERSED WATER READ PARAMETERS TME 290.0 GEN =103 NPG-500 LIB 41 TBA-3.0 FLX-YES FDN=YES XSI-YES NUB =YES PWT=YES I

END PARAMETERS READ MIXT SCT-1 MIX-1 l

FUEL PELLET 92235 1.175834E-03 92238 2.205852E-02 8016 4.646871E-02 MIX-2 CLAD 40302 4.251812E-02 MIX = 3 f

10 i

8016 3.337967E 03 1001 6.675933E 03 4

i l

14 ANF-88-057, Revision 0 MIX-4 REG CONCRETE 8016 4.607448E 02 1C01 1.374186E-02 26000 3.472435E-04 13027 1.745493E-03 20040 1.520656E-03 14028 1.662057E-02 11023 1.747307E 03 END MIXT READ GE0 METRY UNIT 1 COM="

FUEL R00 CYLI 1 1 0.38481 2P182.88 CYLI O 1 0.3937 2P182.88 CYLI 2 1 0.4572 2P182.88 CUB 0 3 1 4P0.62992 2P182.88 UNIT 2 COM="

GUIDE TUBE CYLI 3 1 0.56896 2P182.88 CYLI 2 1 0.6096 2P182.88 CUB 0 3 1 4PO.62992 2P182.88 UNIT 3 COM="

BUNDLE ON 21 INCHX21 INCH CENTERS ARRAY 1 2*-10.70864 -182.88.0 CUB 0 3 1 4P26.67 2P182.88 UNIT 4 COM=" THIS IS A 9X2 BANK OF BUNDLES ARRAY 2 -240.03 -53.34 -182.88

' BANK SPACINGS (BUNDLE C-C): X=66", Y=54"

' 31.92272CM 0F C-C SPACING IN UNIT 4

' ADD 67.85864CM AT +/- X, 52.61864CM AT +/- Y CUB 0 3 1 2P307.88864 2P105.95864 2P182.88 r

15 ANF 88 057, Revision 0 GLOBAL UNIT 6 L

ARRAY 3 3R0.0

+' ADO CONCRETE REFLECTOR AT ALL 6 FACES REPL 4'2 6R5.0 6 END GE0 METRY READ ARRAY ARA-1 NUX-17 NUY=17 NUZ 1 LOOP f

1 1 17 1 1 17 1 111 2 6 12 3 3 15 12 111 2 4 14 10. 4 14 10 111 2 3 15 3 6 12 3 111 END LOOP ARA-2 NUX=9 NUY 2 NUZ-1 FILL F3 END FILL ARA-3 NUX-3 NUY 4 NUZ-1 FILL F4 END FILL END ARRAY READ START NST 1 CONSERVATIVE START XSM-897.0 XSP=950.0 YSM-212.0 YSP=424.0 ZSM-180.0 ZSP-185.76 ENO START READ BOUNOS ALL= VACUUM END BOUNOS READ BIAS ID=301 2 7 ENO BIAS END DATA

16 ANF-68-057, Revision 0

9.0 REFERENCES

(1)

"SCALE:

A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation," NUREG/CR-0200.

(2)

M.N. Baldwin, et al, "Critical Experiments Supporting Close Proximity Water Storage of Power Reactor Fuel," BAW-1484-7, July 1979.

(3)

S.R. Bierman, B.M. Durst and E.D. Clayton, "Critical Separation Between Suberitical Clusters of 4.317. Enriched UO2 Rods in Water With Fixed-Neutron Poisons," NilREG/CR 0073, May 1978.

,6 O

I L

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[-

t ANF-88 057, Revision 0 Issue Date: 7/14/88 r

a p

FINAL REPORT CRITICALITY SAFETY ANALYSIS O.C. COOK NEW FUEL STORAGE VAULT WITH 5.0 PERCENT ENRICHED 17X17 FUEL

[

l QL",TRIBUTION L. D. Gerrald l

J. D. Kahn C. W. Malody J. E. Pieper i

H. G. Shaw (11)

F. B. Skogen Document Control (5) l l

r i