ML20207G007

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Rev 1 to Criticality Safety Analysis,Dc Cook Spent Fuel Storage Racks W/15 X 15 & 17 X 17 Fuel Enrichments Up to 5.0%
ML20207G007
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 08/31/1988
From: Gerrald L
SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:
Shared Package
ML17325A898 List:
References
ANF-88-112, ANF-88-112-R01, ANF-88-112-R1, NUDOCS 8808230355
Download: ML20207G007 (26)
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ANF-88-112 REVISION 1 k3' P

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n ADVANCEDNUCLEAR FUELSCORPORATION 3

CRITICALITY SAFETY ANALYSIS D.C. COOK SPENT FUEL STORAGE RACKS WITH 15X15 AND 17X17 FUEL ENRICHMENTS UP TO 5.0 PERCENT AUGUST 1988 f00 SOSEE 8!88$$3I PR. ;

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CRITICALITY SAFETY ANALYSIS D. C. COOK SPENT FUEL STORAGE RACKS i WITH 15X15 AND 17X17 FUEL ENRIC MENTS UP TO 5.0 PERCENT

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ANF-88-112 IssueDatk':hkD8b CRITICALITY SAFETY ANALYSIS D. C. COOK SPENT FUEL STORAGE RACKS WITH 15X15 AND 17X17 FUEL ENRICHMENTS UP TO 5.0 PERCENT

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Prepared by:

L. D. Gerrald, Criticality Safety Specialist Date Reviewed by:

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~ M ieper, Secondfarty Reviewer I)/#/ff

/ Date Approved by: M/ F//o/PP C.W.Malody, Manage ~r,Corporatepensing / Dare J

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NUCLEAR REQUI ATORY COMMISSION REPORf OlSCLAIMER IMPOhTANT NOTICE REGARDING CONTENTS AND USE OF THIS DOCUMSNT LEASE READ CAREFULLY This technical report was dortved through research and development pro-grams sponsored by Advanced Nuclear Fuels Corporation. It le being submit-ted by Advanced Nuclear Fuels Corporation to the U.S. Nuclear Regulatory Commission as part of a technical contribution to facilitate safety analyses by licensees of the U.S. Nuclear F4egulatory Commisalon which utilize Ad-Yuced Nuclear Fuels Corporation feoricated reload fuel or other technical services prov6ded by A?enced Nuclear Fuels Corporation for light water power reactors and it is true and correct to the best of Advanced Nuclear Fuele Corporation's knowled0s, informat6on, and belief. The informat6on con-tained herein may be used by the U.S. Nuclear Regulatory Comtnission in its review of this report, and under the terms of the respectfva agreements, by ticonoces of applicants before the U.S. Nuclear Regulatory Commission which are customers of Advanced Nuclear Fuels Corporatlon in their demonstration of cornpliance with the U.S. Nuclear Regulatory Commission's regulations.

Advanced Nuclear Fuels Corporation's warrantles and reprsuntations con-coming the subject matter of this document are those set forth in the agree-ment between Advanced Nuclear Fuels Corporation and the customer to which this document is Isoued. Accordingly, except as otherwise expressly provided in such agreement, neither Aovenced Nuclear Fuele Corporetnon nor any person acting on its behalt:

A. Makes any warranty, or representation, express or im.

plied, with respect to the accuracy, completeness, or usefulness of the information contained in this docu-ment, of that the use of any information, apparatus, method, or process disclosed in this docurnent will not intnnge prtvately owned nghts, et B. Assumes any llaoilities with respect to the use of, or for damages resulting from the use of, any informatlon,30-paratus, method. or process d!scbsed in this document.

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ANF 88-ll2 Revision 1 Page 1 CRITICALITY SAFETY ANALYSIS D. C. COOK SPENT FUEL STORAGE RACKS WITH 15X15 AND 17X17 FUEL ENRICHMENTS UP TO 5.0 PERCENT

1.0 INTRODUCTION

Criticality safety of new fuel assemblies for Units 1 and 2 (15x15 and 17x17) in the spent fuel storage racks is conservatively demonstrated in accordance with NUREG-0800 and ANSI /ANS-57.2-1983.

2.0

SUMMARY

The subject racks meet the applicable criticality safety criteria subject to the limits and controls listed below.

. Fuel Design: 15x15 and 17x17 fuel designs with nominal parameters listed in Table 1.

. Storage Rack Design: As described in Section 4.0.

. Storage Rack Loading:

For new fuel enrichments up to 4.23 percent, the racks may be fully loaded with new or exposed assemblies.

To enable storage of new fuel enrichments in the range 4.24 to ,

5.0 percent, exposed bundles (10 GWD/MTU minimum) must first be >

loadeo ints the racks in the "black squares" of a checkerboard arrangement. New or exposed fuel assemblies with enrichments up to 5,0 percent may then be loaded into the "red squares".

. Dissolved Boron: At least 1000 ppm dissolved boron shall be assured I during fuel handling.

ANF-88-112 Revision 1 Page 2 r

3.0 FUEL DESIGN Bundles for Units 1 and 2 were analyzed for safety within the racks. The 15x15 and 17x17 fuel design parameters modeled are listed in Table 1. Fuel designs of Advanced Nuclear Fuels Corporation (ANF) and Westinghouse (W) are included.

TABLE 1 FUEL DESIGN PARAMETERS Pellet Guide Tube Rod Diameter Clad 10/00 10/00 Pitch Desian (inch) (inch) (incht. , (inch)

ANF 17x17 0.303 0.310/0,360 0.448/0.480 0.496 W 17x17 0.3225 0.329/0.374 0.450/0.482 0.496 sNF 15x15 0.3565 0.364/0.424 0.511/0.544 0.563 i W 15x15 0.3659 0.3734/0.422 0.515/0.545 0.563 M 15x15 (OFA) 0.3659 0.3734/0.422 0.512/0.546 0.563 The 15x15 bundle has 21 "water rods" (guide tubes). Th9 17x17 bundle has 25 water rods. The arrangement of the guide tubes is shown in the attached i listings of typical CASMO inputs.

4.0 SYSTEM GEOMETRY The spent fuel racks were modeled as an infinite x infinite array of infinite length cells filled with infinite length assemblies.

Each cell contain; the regions described below.

. Fuel assembly: 8.432 inch square (17x17) or 8.445 inch square ,

(15x15)

. Water to inner surface of cell wall at 8.969 inch square

. Cell wall to 9.361 inch square

. Water to 10.5 inch square (cell boundary)

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1 ANF-88 112 Revision 1 Page 3 The cell wall is 0.196 inch thick with the following regions, starting at the inner surface.

. 0.075 inch thick stainless steel

. 0.010 inch thick aluminum clad for Boral

. 0.071 inch thick Boral

. 0.010 inch thick aluminum clad for Boral

. 0.030 inch thick stainless steel l

The Boral was conservatively modeled at 0.020 gm B-10 per square cm.

Average and standard deviation values for 175 suples of the Boral used in the racks are 0.0234 and 0.0010 gm B-10 per square cm.

The system was flooded with water (zero voids, zero dissolved boron) at 20'C.

5.0 CALCULAT10H liETH00S Most calculations, including rack k-inf, in core k-inf, and fuel depletion were performed using CASMO 3 with 40-group cross sections. CASMO has been extensively benchmarked.

Additional and replicate calculations were performed using KENO-Va with 16-group cross sections from the SCALE (1) system. Sixteen group cross sections were prepared using BONAMI/NITAWL.

5.1 Methods Verification The SCALE codes and cross sections have been extensively benchmarked against data from critical experiments.

ANF 88-ll2 Revision 1 Page 4 Supplemental benchmarking was performed immediately before the calculations reported here. The experiments selected are described in References 2 and 3. The experiments were selected particularly to establish the calculational bias for the poisoned spent fuel storage rack analysis.

The results are listed in Table 2.

TABLE 2 BENCHMARK CALCULATION RESULTS FROM KENO-Va 16 GROUP CROSS SECTIONS Calculated Case No. k-eff _

Reference 2 Experiments 2378 1.00395 t 0.00376 2384 1.00037 1 0.00306 2388 0.99886 i 0.00341 2420 1.00038 1 0.00367 2396 0.99443 1 0.00360 2402 1.00694 1 3.00283 2411 1.01223 t 0.00286 2407 1.00647 1 0.00332 2414 1.00967 1 0.00327 Reference 3 Experiments 9 1.00092 1 0.00487 10 1.00181 1 0.00412 11 0.99786 i 0.00413 12 0.99885 1 0.00487 31 1.00442 1 0.00421 The average and standard deviation are 1.00265 and 0.00490, respectively.

The 95 percent upper limit (UL) on the KEN 0 k-eff is calculated by pooling the KENO variance and the bias variance.

ANF-88 ll2 Revision 1 Page 5 For example, the 95 percent UL k eff for case 2378 is calculated below. l k-eff (95% 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 (5%) with about 80 degrees of freedom. (The KENO results had at least 80 degrees of freedom.)

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

TABLE 3 BIAS CORRECTED BENCHMARK RESULTS k-eff Case No. k-eff (95% UL) 2378 2384 1.00130 1 0.00376 0.997716 1 0.00306 1.01155 1.00731 l>

2388 0.996206 1 0.00341 1.00612 2420 0.997726 1 0.00367 1.00789 2396 0.991776 1 0.00360 1.00187 2402 1.00429 1 0.00283 1.01368 2411 1.00958 1 0.00286 1.01900 2407 1.00382 1 0.00332 1.01364 '

2414 1.00702 1 0.00327 1.01680 '

9 0.998266 1 0.00487 1.00973 10 0.999156 1 0.00412 1.00978 11 0.995206 1 0.00413 1.00584 12 0.996196 i 0.00487 1.00766 31 1.00177 1 0.00421 1.01249 The 95 percent UL which is the parameter used in judging acceptability exceeds 1.0 in every case after bias correction. The average 95 percent VI. is y 1.0102. Therefore, the results remain conservative.

All reported results in this report have H21 been bias-corrected, unless otherwise stated. Therefore, these results would tend to be conservative by about 0.00265.

ANF 88 ll2 Revision 1 Page 6 6.0 RESULTS 6.1 CASMO Model of Soent Fuel Storace Racks The spent fuel racks were modeled as filled with new fuel with ,

enrichments in the range 2.5 to 5.0 percent. The CASMO results for four fuel designs are listed in Table 4.

TABLE 4 CASMO RESULTS '

SPENT FUEL RACKS WITH FRESH FUEL ENRICHMENT - BUNDLE-TYPE EFFECTS Enrichment ANF 17x17 ANF 15x15 W 17x17 W 15x15(0FA)

(wt% U 235) k:)"? k-inf k-inf k-inf 2.5 0.82961 0.82403 0.83049 0.83296 3.0 0.87037 0.86360 0.86926 0.87204 3.5 0.90270 0.89471 0.89970 0.90271 4.0 0.92887 0.92028 0.92464 0.92791  ;

4.5 0.95105 0.94154 0.94514 0.94869 5.0 0.96947 0.95938 0.96277 0.96643 The Table 4 results indicate that all designs will be suberitical by substantial margin at all enrichments up to 5.0 percent. However, the 0.95 limit on k-eff will be exceeded at enrichments somewhat less than 4.5 percent.

The Table 4 results also indicate that the in-rack k-inf values for the four bundle types differ little and that, for the higher enrichments of main interest, all results are bounded by the ANF 17x17 values.

6.2 KENO-Va Models of Soent Fuel Storaae Racks Since the rack k-inf exceeds 0.95 when fully loaded with new 5.0 percent enriched fuel, partial loading of the racks was evaluated. A checkerboard loading of new 5.0 percent enriched bundles (red squares) with bundles of lower reactivity (black squares) is the selected partial loading arrangement.

o ANF 88-112 Revision 1 Page 7 i

The KENO Va results from checkerboard loadings of new ANF 17x17 fuel bundles' are in Table 5. Appropriate CASMO results from Table 4 are included for comparison.

T.%BLE 5 CHECKERBOARD LOADINGS OF SPENT FUEL RACKS FRESH ANF 17X17 8UNDLES OF TWO ENRICHMENTS KENO-Va RESULTS WITH 16 GROUP CROSS SECTIONS Low Enrichment High Enrichment KENO-Va CASMO (wt% U-2351__ (wt% U 235) __

k-inf k-inf 2.5 2.5 0.8307 1 0.0033 0.8296 3.0 3.0 0.8730 1 0.0039 0.8704 '

3.5 3.5 0.9077 1 0.0037 0.9027 4.0 4.0 0.9342 1 0.0036 0.9289 4.5 4.5 0.9512 1 0.0035 0.9511 5.0 5.0 0.9721 1 0.0038 0.9695 ,

3.0 4.0 0.9063 t 0.0033 3.0 5.0 0.9253 t 0.0034 4.0 5.0 0.9509 1 0.0035 Results below have empty (water-filled) low enriched cells (Empty 3.0 0.7323 1 0.0031 (Empty 4.0 0.7820 1 0.0038 (Empty 5.0 0.8101 t 0.0040 The KENO results from Table 5 are very close to the CASMO results from Table 4.

For the first six cases in Table 5, the bias-corrected 95 percent UL k-inf (rounded to nearest 0.0001) is well estimated by the regression line:

k-inf (95% UL) = 0.33236 + 0.32918 ENR - 0.061743 ENR**2 + 0.0043556 ENR**3, l I

i y _

ANF-88-ll2 Revision 1 Page 8 Based on the 7.7257E-6 sum of squares of residuals for six values, the l average residual is 0.00113. For an enrichment of 4.23 percent, the calculated k-inf value is 0.9497.

Repeating the regression after deleting the points at enrichments 2.5 and 3.0, the regression equation is:

k-inf (95% UL) = -0.69.480 + 1.0739 ENR - 0.2398 ENR**2 + 0.01840 ENR**3.

The above equation with four fitted coefficients is an exact fit to the four data points in the enrichment range 3.5 to 5.0 percent. For an enrichment of 4.23 percent, the calculated k-inf value is 0.9497.

Using the results from Tables 4 and 5, and the data from Section 5.1, the average and standard deviation of the KENO CASMO bias (KENO result minus CASMO result) are:

. 0.002810.0021 (based on nominal KENO value)

. 0.0002 1 0.0021 (based on bias-corrected KENO value)

. 0.0103 1 0.0021 (based on bias corrected 95% UL from KEN 0)

There is no significant effect of enrichment on this bias. Again, the KENO-CASMO results agree very well and the 95 percent UL on KENO is very conservative.

6.3 CASMO Models for In-core k-inf The previous section contains correlations between the enrichment in the racks and the resulting k inf. Good KENO CASMO agreement was also demonstrated.

l

ANF-88 ll2 Revision 1 Page 9 1 l

l The more generic correlation desired is between the reactivities of the bundles in the rack and the rack k-inf. A convenient index of bundle reactivity ic the in-core k-inf. This index will be based on a 8.466 inch bundle pitch, 20'C temperature, zero dissolved boron, and zero Xe-131/135.

The k-inf for new bundles with enrichments in the range 2.5 to 5.0 percent were calculated using CASMO. The results-are in Table 6.

TABLE 6 CASMO RESULTS NEW FUEL BUNOLE ON 8.466 INCH CENTERS, ZERO 80RON, TEMP-20'C ENRICHMENT - BUNDLE-TYPE EFFECTS l

Enrichment ANF 17x17 ANF 15x15 W 17x17 W 15x15(0FA)

(wt% U-235) k-inf k-inf k-inf k inf 2.5 1.34557 1.34688 1.34611 1.35002 3.0 1.39596 1.39528 1.39312 1.39743 3.5 1.43427 1.43200 1.42870 1.43335 4.0 1.46434 1.46082 1.45658 1.46152 4.5 1.48858 1.48403 1.47898 1.4841S 5.0 1.50852 1.50310 1.49740 1.50281 6.4 Co'. relation of in-Rack k-inf vs. In core k-inf A regression of the spent fuel rack k-inf (95% UL) value (checkerboard '

luading. Table 5) versus the in core k-inf values of the bundles (Table 6, ANF ,

17x17) in the racks yielded the equation below with a standard error of l 0.0016.

k-inf (95% UL) = 0.31517 + 0.40406 k inf(low) + 0.45206 k-inf(high) '

l The goodness-of-fit of the regression is demonstrated in Table 7. i m

ANF 88-112 Revision 1 Page 10 ,

TABLE 7' REGRESSION RESULTS IN RACK K INF (95% UL) VS. IN CORE K-INF k-inf k-inf k-inf k inf (In-core) (In core) (In Rack) (In Rack) flow) ,,

(Hich) (KENO) (Recression) 1.34557 1.34557 0.83618 0.83680 1.39596 1.39596 0.87947 0.87994 1.43427 1.43427 0.91384 0.91274 1.46434 1.46434 0.94018 0.93848 1.48858 1.48858 0.95701 0.95923 1.50852 1.50852 0.97751 0.97630 1.39596 1.46434 0.91178 0.91085 1.39596 1.50852 0.93094 0.93082 '

1.46434 1.50852 0.95671 0.95845 Using the regression equation with an assumed k inf (high) of 1.50852

_(5.0. percent enriched) and with a rack k-inf of 0.95, the maximum acceptable value fer k-inf (low) is 1.44342. This k-inf (low) value corresponds to a new ANF 17x17 bundle with an enrichment slightly greater than 3.5 percent (Table 4). This means that a checkerboard loading of new bundles with enrichments 3.5 and 5.0 percent would meet the 0.95 limit on rack k eff.  ;

i 6.5 In-core k-inf vs. Burnuo t All previous calculations were for new fuel assemblies. The reduced reactivity bundles are now assumed to be exposed ANF 17x17 bundles with an initial (BOL) enrichment of 5.0 percent. The minimum burnup to produce an in-core k-inf less than 1.44342 was determined. This minimum burnup will be

' conservative for all BOL enrichments less than 5.0 percent.

The effect of burnup on bundle k-inf was calculated for the ANF 17xl?

bundle at various combinations of temperature and dissolved boron concentration. The objective is to assure that the burnup effect is

e ANF 88-ll2 Revision 1 Page 11 c;nservative regardless of operating parameters and also to assure that axial temperature effects are addressed. The ANF 17x17 bundle was selected because it has the highest in-core k inf values in Table 6.

Fuel depletion runs (0 to 60 GWD/MTV) were made at the temperature at the top and bottom of the bundle and with a constant 500 or 1000 ppm dissolved boron concentration. The modeled fuel / moderator temperatures were 986.8/555.9 K (bottom) and 1023/592.1 K (top).

After the depletion run, the bundle cold (20*C), clean (zero Xe-131/135) k-inf was calculated with zero dissolved boron. Tha results are in Table 8.

TABLE 8 BUNDLE K INF VS. BURNUP (ANF 17X17 BUNDLE)

CASMO RESULTS FOR 5.0 PERCENT ENRICHED FUEL AT BOL BUNDLES ON 8.466 INCH CENTERS (INFINITE LATTICE)

ZERO DISSOLVED BORON, ZERO Xe-131/135 TEMPERATURE - 20*C FUEL DEPLETION RUNS AT T0P/ BOTTOM TEMPERATURE AND AT 500/1000 PPM BORON Burnup Top /500 Bottom /500 Top /1000 Bottom /1000 (GWD/MTV) k-inf k-inf k-inf k-inf 5 1.45971 1.46028 1.45958 1.46014 10 1.41219 1.41308 1.41208 1.41295

15 1.36139 1.36210 1.36150 1.36220 20 1.30853 1.30849 1.30910 1.30906 25 1.25366 1.25225 1.25494 1.25358 30 1.19725 1.19373 1.19959 1.19624 35 1.13903 1.13258 1.14282 1.13673 40 1.07910 1.0G884 1.08478 1.07518 45 1.01774 1.00289 1.02581 1.01200 50 0.95561 0.93557 0.96652 0.94804 55 0.89379 0.86841 0.90791 0.88464 60 0.83394 0.80384 0.85137 0.82183 The indications are:

ANF 88 ll2 Revision 1 Page 12 ,

. A 10 GWD/MTU minimum burnup will be more than adequate to lower the in-core k-inf value below the 1.44342 reference value.

. Temperature / boron effects become significant only at higher burnups, 6.6 Axial Effect1 All models in previous sections assumed an infinite fuel length with uniform properties. The actual fuel length is finite and the burnup is lower at the two ends than in the central region.

1 Additional calculations were performed to demonstrate that the infinite l

length model with the bundle average burnup includes adequate margin for axial burnup effects.

The bases for these additional calculations were:

. The enriched fuel length is 12 feet.

. The enriched fuel has three regions: a central eight foot region with a constant burnup B and two end regions. The burnup in the two foot long end regions varies linearly from 0.58 (at end) to B. '

These values were taken from ANF neutronics calculations.

. The average burnup for this model is 0.91678 (11B/12).

. Since the average burnup modeled is 10 GWD/MTV, the value B is 10.91.

. Only half (six feet) of the symmetric fuel region was iuodeled.

Specular refle>:tiun was applied at the plane of symmetry. ,

. The two foot long region was modeled as four 6-inch long zones with f burnups 10.23, 8.86, 7.50 and C.14 GWD/MTU (progressing toward the  :

end of the enriched zone). Expressed as fractions of the vclue B, ,

the average burnups of the four end regions are 0.93758, 0.81258,  !

0.6875B and 0.56258, respectively.

. The calculations were performed using XSDRNPM (1 0 discrete-ordinates transport code) with 16 group cross sections.

u

L ANF 88 ll2 Revision 1 Page 13

. All fueled regions contained new fue!. The reduced reactivity due to burnup was matched by adjusting the enrichment. The reactivities for low burnup ANF 17x17 fuels used for interpolation are listed below.

TABLE 9 ANF 17X17 IN-CORE K-INF VEASUS BURNUP (SAME BASES AS TABLE 8)

Burnun k-inf_.

6 1.50852 0.5 1.49724 1 1.49186 2 1.48417 3 1.47651 5 1.45957 7.5 1.43637 10 3.41209 12.5 .38706 The k inf values for burnups 10.91, 10.23, 8.86, 7.50 and 6.14 were estimated at 1.4030, 1.4098, 1.4231, 1.4364 and 1.4490. The k inf values for cell-weighted cross sections representing new fuel enrichments of 3,0, 3.1, 3.3, 3.5 and 3.7 percent are 1.4025, 1.4107, 1.4259, 1.4396 and 1.4520, respectively. The enrichments used to match the burnups (k infs) listed above are 3.006, 3.089, 3.263, 3.453 and 3.662 percent.

. The XSDRNPM model is an infinite slab with 30 cm of water reflection. The infinite slab has five regions (one at four feet plus four at six inches) as described earlier.

. The XSDRNPM result for the five region model witn 30 cm of water reficction is 1.4247. The value for the infinite length model at 10 GWD/MTU is 1.4121. An infinite length model with a burntp near 8.70 would yield the 1.4247 value from the finite length model. The 1.4247 vlaue is well below the 1.4434 limit established earlier.

r l

ANF 88 ll2 s

Revision 1 l Page 14 l

l l Therefore, 10 GWD/MTU minimum burnup value ir.cludes conservative

[ allowance for axial burnup effects. .

6.7 Fuel Handlina Accidents The worst credible accident is bringing two bundles together in the pool.

l Accidents such as placing a Dundle next to the storage racks are less reactive.

The k eff of two edge to edge bundles (new, 5.0 percent enriched, infinite length) with full water reflection is 1.0785 2 0.0052. This case has zero dissolved boron.

Repeating the above case with 1000 ppm dissolved boron in all water j reduced the k eff to 0.9075 1 0.0038.

i A minimum dissolved boron concentration of 1000 ppm is more than adequate to assure criticality safety during fuel handling.

7.0 COMPUTER INPUT LISTINGS 7.1 CASMO Model for Soent Fuel Rack The CASMO-3 input for the spent fuel racks containing the ANF 17x17 bundle is listed below. All rack cells contain the same enrichment.

DIM,17,2

, TIT TFU 293.15 TMO 293.15 BOR=0

  • DC COOK FUE 1 10.412/5.0 *95% TD, 5.0% ENR M!! 5 41/347-78.24 13000=16.58 5000 4.06 6000=1.13 MIXl IS SMEARED RACK CHANNEL i

PIN 1 0.38481 0.3937 0 4572/'FUE' ' AIR' 'CAN'//1 PIN 2 0.5690 0.6096/'C00' 'CAN'//l

  • Gul0E TUBE PWR,17.1.25984,22.76348,4*0,2 l
  • INNER SHROUD: 8.962 IN SQ (IN PWR)
  • METAL: 0.075 STL, 0.010 AL, 0.071 BORAL, 0.010 AL, 0.030 STL
  • OUTER WATER: 1.45542CM l

1

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I l

ANF 88-112 Revision 1 l Page 15 i

LP!

1

  • ROW l

, 1 1 ' ROW 2 1 1 1

  • ROW 3 1 1 1 2
  • ROW 4 1 1 ! 1 1
  • ROW 5 1 1 2 1 1 2
  • ROW 6 1 1 1 1 1 1 1
  • ROW 7 1 1 1 1 1 1 1 1
  • ROW 8 1 1 2 1 1 2 1 1 2
  • ROW 9 1 1 1 1 1 1 1 1 1 1
  • ROW 10 1 1 1 1 1 1 1 1 1 1 1
  • ROW 11 1 1 2 1 1 2 1 1 2 1 1 2
  • ROW 12 I 1 1 1 1 1 1-1 1 1 1 1 1 1
  • ROW 13 1 1 1 2 1 1 1 1 1 1 1 1 1 2
  • ROW 14 1 1 1 1 1 2 1 1 2 1 1 2 1 1 1
  • ROW 15 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
  • ROW 16 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
  • ROW 17 LFU 1
  • ROW 1 I 1
  • ROW 2 l 1 1 1
  • ROW 3 1 1 1 0
  • ROW 4 1 1 1 1 1
  • ROW 5 1 1 0 1 1 0
  • ROW 6 1 1 1 1 1 1 1
  • ROW 7 1 1 1 1 1 1 1 1
  • ROW 8 1 1 0 1 1 0 1 1 0
  • ROW 9 1 1 1 1 1 1 1 1 1 1
  • ROW 10 1 1 1 1 1 1 1 1 1 1 1
  • ROW 11 1 1 0 1 1 0 1 1 0 1 1 0
  • ROW 12 1 1 1 1 1 1 1 1 1 1 1 1 1
  • ROW 13 1 1 1 0 1 1 1 1 1 1 1 1 1 0
  • ROW 14

' 1 1 1 1 1 0 1 1 0 1 1 0 1 1 1

  • ROW 15 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
  • ROW 16 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
  • ROW 17 FST,4*0.49784/4*1.45542/8*'Mll'/8*'C00'/

STA l TIT TFU 293.15 TMO 293.15 BOR=0

  • DC COOK l FUE 1 10.412/4.5 *95% TD, 4.5% ENR STA TIT TFU 293.15 TM0=293.15 BOR=0 OC COOK FUE 1 10.412/4.0 *95% TD, 4.0% ENR STA TIT TFU 293.15 TM0-293.15 BOR=0
  • DC COOK FUE 1 10.412/3.5 *95% TD, 3.5% ENR l

l L

ANF 88 112 Revision 1 Page 16 STA TIT TFU 293.15 TM0=293.15 BOR=0

  • DC COOK FUE 1 10.412/3.0 *95% TD, 3.0% ENR STA TIT TFU 293.15 TM0 293.15 BOR=0
  • DC COOK FUE 1 10.412/2.5 *95% TD, 2.5% ENR STA END 7.2 KENO Ya Model for Checkerboard loadina The KENO model for the spent fuel racks with a checkerboard loading of 4.0 and 5.0 percent enrichments is listed below.

DC COOK, SPENT FUEL RACKS, 4.0% X 5.0% CHECKERS 0ARD LOADING READ PARAMETERS TME=60.0 GENul03 NPG=500 LIB 41 TBA=2.0 FLX YES FDN=YES XSl=YES NUB =YES PWT=YES PLT =NO END PARAMETERS READ MIXT SCT-1 MIX = 1 l

002 PELLET, 4.0% ENR, 95% TD

92235 9.406816E 04 92238 2.229106E 02 8016 4.646348E 02 MIX = 2

' U02 PELLET, 5.0% ENR, 95% TD 92235 1.175834E 03 92238 2.205852E 02 8016 4.646871E 02 MIX = 3 ZlRCALOY 40302 4.251812E 02 MIX = 4 WATER 8016 3.337967E 02 1001 6.675933E 02 MIX. 5 BORAL, 0.020 GM B 10/SQCM, 0.071" THK BORAL, B 10 = 0.020 GM/SQCM (95% MIN VALUE - 0.0232)

AT 0.071" THICK, B 10=1.1090E 1 GM/CC

= 0.1109/10.0129 G MOL/CC = 1.1076E 2 GMOL/CC (B 10 ONLY)

TOTAL BORON = 1.1076E 2/0.1976 G MOL/CC = 5.6052E 2 GMOL/CC

= 3.3761E 2 ATOM /(BARN CM) = 0.606 GM B/CC

ANF 88-ll2

[ Revision 1 Page 17

[

I a

r I

E 5000 3.3761-2 I '

6012 8.4402 3 p BORAL DENSITY IS 2.49 GM/CC

= 0.606 GM B/CC + 0.1683 GM C/CC + 1.7157 GM AL/CC 13027 3.8299-2 MIX = 6 >

a ALUMINUM i 13027 6.024185E-02

+ MIX = 7 F 304SS ..

J 24304 1.742958E 02 -

t 25055 1.736443E-03

26304 5.935923E 02 28304 7.718178E-03 o

. END MIXT READ GEOMETRY UNIT 1 COM " 4.0% ROD, BUNDLE 1 "

e CYL1 1 1 0.38481 2P100.0 i CYLI O 1 0.3937 2P100.0 t CYLI 3 1 0.4572 2P100.0 t

CUB 0 4 1 4PO.62992 2P100.0 UNIT 2 COM " 5.0% ROD, BUNDLE 2 "

CYLI 2 1 0.38481 2P100.0

CYLI 0 1 0.3937 2P100.0 I CYLI 3 1 0.4572 2P100.0 E

=

CUB 0 4 1 4PO.6299? 2P100.0 UNIT 3 i C0tt= " GUIDE TUBE "

L CYLI 4 1 0.56895 2P100.0 r CYLI 3 1 0.6093 2P100.0 6 CUB 0 4 1 4P0.62992 2P100.0 UNIT 4 COM " BUNDLE 1 ,

ARRAY 1 2*-10.70864 -100.0 -

REPLICATE 4 1 4RO.6731 2RO 0 1 REPLICATE 7 1 4RO.1905 2RO.0 1 REPLICATE 6 1 4RO.0254 2RO 0 1 REPLICATE 5 1 4RO.18034 2RO.0 1 REPLICATE 6 1 4RO.0254 2RO.0 1 7 REPLICATE 7 1 4RO.0762 2R0.0 1 REPLICATE 4 1 4RI.45542 2RO 0 1 UNIT 5 COM " BUNDLE 2 ARRAY 2 2* 10.70864 100.0 REPLICATE 4 1 4RO.6731 2RO.0 1 L

ANF-88-112 Revision 1 Page 18 REPLICATE 7 1 4RO.1905 1RO.0 1 REPLICATE 6 1 4RO.0254 2R0.0 1 REPLICATE 5 1 4RO.18034 2R0.0 1 REPLICATE 6 1 4R0.0254 2R0.0 1 REPLICATE 7 1 4RO.0762 2R0.0 1 REPLICATE 4 1 4RI.45542 2R0.0 1 GLOBAL UNIT 6 ARRAY 3 3R0.0 END GE0 METRY READ ARRAY ARA-1 NUX-17 NUY-17 NUZ-1 LOOP 1 1 17 1 1 17 1 111 3 6 12 3 3 15 12 111 3 4 14 10 4 14 10 111 3 3153 6 12 3 111 EhD LOOP ARA-2 NUX-17 NUY-17 NUZ-1 LOOP 2 1 17 1 1 17 1 111 '

3 6 12 3 3 15 12 111 3 4 14 10 4 14 10 111 3 3 15 3 6 12 3 111 END LOOP ARA-3 NUX-2 NUY-2 NUZ-1 FILL 4 E 5 4 END FILL END ARRAY READ START NST-1 i END START l READ B0UNDS XYF-PERIODIC ZFC-SPECULAR END B0UNOS END DATA 7.3 Fuel Deoletion Runs (CASM0)

The CASM0-3 input below performed the fuel depletion calculation up to 60 GWD/MTU and then, using the results from the depletion calculations, calculated the in-core k-inf values at 20'C temperature, zero dissolved boron, and zero Xe-131/135.

4 ANF-88-ll2 l Revision 1 Page 19 DIM,17,8 -

TIT TFU-1023.0 TM0-592.1 B0R-1000 IDE ' REST'

  • DC COOK, TOP 0F BUNDLE FUE 1 10.412/5.0 *95%TD, 5.0%ENR PIN 1 0.38481 0.3937 0.4572/'FUE' ' AIR' 'CAN'//l PIN 2 0.5690 0.6096/'C00' 'CAN'//1
  • GUIDE TUBE l PWR,17,1.25984,21.50364,4*0,8 LPI 2

11 111 ,

2112  !

11111 111112 2112111 11111111 111111111 LFU 0

11 111 0110 11111

! 111110 '

I O110111 l

11111111 111111111 DEP,-60 WRE,-60 STA TIT

  • COLD, ZERO BORON RES,' REST',5,10,15,20,25,30,35,40,45,50,55,60 TM0,293 TFU,293 80R,0

~

CNU,'FUE',54131,0 CNU,'FUE',54135,0 LIS - .

STA END b

L.. _ __ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ . _ _ _ _ . _ _ _ _ . . _ _ _ _ _

ANF-88-112 Revision 1 Page 20

8.0 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 Subcritical Clusters of 4.31% Enriched UO2 Rods in Water With Fixed Neutron Poisons,' NUREG/CR-0073, May 1978.

l

ANF-88-ll2 Revision 1 Page 21 Issue Date: 8/11/88 CRITICALITY SAFETY ANALYSIS D. C. COOK SPENT FUEL STORAGE RACKS WITH 15X15 AND 17X17 FUEL ENRICHMENTS UP TO 5.0 PERCENT DISTRIBUTION L. D. Gerrald J. D. Kahn C. W. Malody J. E. Pieper H. G. Shaw/AEP (16)

F. B. Skogen Document Control (5)

. . 6. L d..aa -

4 i

s Attachment 5 to AEP:NRC:1071 ANF 88-09, "Thermal-Hydraulic Analysis Of The D. C. Cook Spent Fuel Pool" t

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