ML20086P857

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Criticality Safety Analysis for Palisades New Fuel Storage Array
ML20086P857
Person / Time
Site: Palisades Entergy icon.png
Issue date: 12/09/1991
From:
SIEMENS CORP.
To:
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ML18057B434 List:
References
EMF-91-1421(NP), NUDOCS 9112270226
Download: ML20086P857 (25)
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~4 ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 EMF-91-1421(NP)

CRITICALITY SAFETY ANALYSIS FOR PALISADES NEW FUEL STORAGE ARRAY

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4 Siemens Nuclear Power Corporation EMF 91 1421(NP) tssue Date: 12/09/91 s

CRITICAL:Ff GAFETY ANALYSIS FOR THE PALISADES NEW FUEL STORAGE ARRAY.

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December 1991 9

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t CtJSTCMER CISCLAIMER IMPORTANT NOTICE REGARDING CONTENTS AND USE CF THIS QQQUMENT PLEASE RE.A0 CAREFULLY 5emtes Nucear 8 reert Corporanon s marranses and representatoes concoming me subsect maner of this cocument are rose set form m tre Agreement nerneen S.emens Nuoear #ower Corporaton and me Customer oursuant to *nien Sis occument is issuee Acconsngly, encoot as omerwise encrossly provced a swen Agreement, never Semons Nuaoat P?aer Corocracon eor any person acang on its nonest manes any warranty or represenmoon, espressee or ecueo. ae mscect a me aa:uracy, comoienness, or usefucess of to mformanon contamed n vis document, or mat to use of any informacon asparatus metnoo :r orecess disclosed m mis cocurrent wul not etnnge onvate+y oweed ngnts. or assumes any liacihtee um ru,=J to me use of any information. accarats metroc or crocesa discosed m mi. Occument.

The eformacon contaned heren is for ce scie use of 're Owstomer in orner to avoid imoairment 41 ngnts of S.emees Nue: ear 8t wer Corporat:en n cannes or evensons anicn may to cauced in re informacon contanec >n vis document, me teocent, ty its accontance of ns document, agrees not to puch sn or meme puanc use on me catent use of tne term) of sucn informanon unts se sueor:s oc e wnang by Semens Nuceat P*)wer Corporanon or unni af*er sta ,6) months icilouang termneson or escroson of me aforesa4 Agreement and any en:ension .

merced, unesa encrossty proveed e me Agreement. No ngmts of ticenses in of to any potents are epwd by me furrwaning of trus ccxument, 1

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. . 5 EMF 91 1421(NP)

Issue Date:

- CRmCAUTY SAFETY ANALYSIS ...

FOR THE PAUSADES NEW FUEL STORAGE ARRAY

[ .-

l-Prepared by: I C* A*4sif 2*-/**'

R. A. Jensen', Senior Research Engineer Date Approved by: N k. in S !za!9i S. W. Heaberlin,.Ranager Reactor / Ofte

-Systems Analysis Section:

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E M F.91 1421. N P)

Pagev TABLE OF CONTENTS d

Section ,

  1. sce Le 1.0 ~ INTRCCUC'1CN . . . 1 2.0

SUMMARY

. . 2 3.0 FUEL ASSEMBLY CESCRIPTICN 2 4.0 STORAGE ARRAY CESCRIPTICN 5 5.0 CALCULATIONAL METHCCCLOGY S 6.0 METHODS VAllCATION . . i 7.0 MAJOR CONSERVATISMS 1:

, 8.0 RESULTS s. . . . .. . . .

t*

9.0 ABNCRMAL CONDITIONS i4

10.0 CONCLUSION

S . . . . . , 15 11.0 PEFERENCES *i M

EMF 91 1421:NF)

Pagot UST OF TABLES Table Pace No 1 Cesign Base Pallsades Batch N Fuel Assembly Parameters 4 2 Critical Speriment Benchmark Aesults 9 3 Palisades New Fuel Storage Array,5 Reactivity (Kg)

Calculation Results for 4 25 w/o ', U Fuel 13 e

EMF 91 1121 AP)

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- UST OF AGUPES Eig.yLt =sce N 1 Peload N1 Assembly . . . . . . . . . . .. . . . . . . 3 2 Palisades New Fuel Sterage (Measurements of installed Pack) . . . . . . . 7 _

3 Palisades New Fuel Sterage Array (Werst Case Geometry) . . . . , ,, , , '2 b

m 4

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.- 4 .

EMF 91 1421(NP)

Page1 1.0 INTAODUCTION In July 1975 a criticality safety analysisW was performed for the Palisades New Fuel Storage Array to allow storage (checkerccard arrangement) of fuel assemclies enrienec to 3 2 ,

wt.% 2MU. This analysis included a parametric searen to define the maximum array rea:: ivy

._ (kg) as a function of uniform interspersed moderation within the array. The maximum k, was shown to occur when the array is fully flooded with water. Subsequent to this esalua:cr.

another criticality safety analysis A was performed in 1979, whien demonstrated the stcrage array to be adequately subentical at a maxin%m average fuel assemcly ennenment cf 3 31

2 wt.% "U.

It is the intent of this report to demonstrate that Palisades fuel (us6ng Saten N fuel  ;

assembly parameters) enriched to 4.20 wt.% 2M U can be stored in the new fuel stcrage array and continue to meet the reactivity limit criterion (kg s 0.95) stipulated for the stcrage cf new fuel by the Technical Specifications for the Palisades Nuclear Power Station. ,

This enticality analysis was performed in accordance with NUP.EG 0800 and ANS!/ANS 57.31983 (including Section 6.2.4 and all applicable subsections).

,p p. -y.. = ww.-'*"' -fry +:r4

EMF 91 142* iNP)

Page 2 2.0

SUMMARY

The following criticality safety analysis of the new fuel storage array, containing steel box beams in alternate storage locations of the 3 x 24 array, cemenstrates the array to ce adequately . ;ritical for Batch N type fuel having a maximum average fuel assembly enrienment of 4.2 weight % # U The analysis demonstrates the storage array to nave an effective multiplication facter of <0.95 for assumed worst credible array concitions of tot assemcly spacing and uniformly interspersed moderation.

The sucject storage array meets the applicable enticality safety criteria (NUPEG CSCC arid ANSI 57,31983) subject to the fcilewing limitations:

1. Fuel Decign: As specified in Section 3.0. Any significant ceviation from this may require accitional analysis.
2. Array Design: As /,. ascribed in Section 4.0, 3 if fuel assemblies are stored with plastic wrapping, the bottcm of wrapping snail ce open to assure drainage.

3.0 FUEL ASSEMBLY CESCRIPTION The fuel assembly design (Saten N) assumed for the analysia is Jecicted in Figure 1.1 As-indicated, the 15 x 15 lattice arrangement includes a

'1 Figure 1 actually depicts a Palisades Batch N1 assembly whicn is the most reactae fuel assembly design of baten N'. All other assemoly designs of this caten nave :cwer average planar enr:cnments than the N1 cesign and incluce vancus !cacings cf gedclinia bearing fuel pins. .

EMF 91 1421(NP)

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I LL = 2.40 L = 2.58 wie U 235 Fuel M = 3.10 w<o U 235 Fuei H 3.30 w/o U 235 Fuet

, G Gwce Bat i Insrument TuOe O' !centfiers: WG = Wice Interauem0iy Gas NG = Narr0w Inttrauec0y Water Gac toteace* *

!GURE L. ;elcac H Assenoly

EMF 31 142' J#

Page4 single zirconium instrument guide tube located in the center of the assembly and eight zirconium guide bars positioned on the exterior of the assembly. The remain,ing pes.tiens within the assembly are occupied by 216 UO2 fuel reds.

The fuel assembly specifications anc lattice cell parameters assumed in this evatat,09 are given in Table 1. The parameters suen as peitet size, pellet density, c!ac thickness, et:

have been set to conservative values within the expected manufacturing tclerances TABLE 1 Cesign Base Palisades Batch N Fuel Assembly Parameters!5)

Parameter Neminal Vedel Lattice Pitch, in. 0.550 Clad 00, in. 0.417 Ctad Material Zircalcy 4 Ctad Thickness, in. 0.0295 Pellet 00, in. -0.3510 Pellet Density, % TO 94.5 Dish Volume, % .

Active Fuel Length, in. 131.800 Fuel Rod Array 15 x 15 Fuel Rods 216

'3uide Bars S Instrument Tubes 1

x EMF 91 1421(NP)

Page 5 Note that since the mcnufacturing enrichment uncertainty / tolerance is 0.05 wt% 235 U 235 the analysis was performed using 4.25 w/o U fuel so that the rack could be qualified to store 4.20 wie 235y gy,;,W 4.0 STORAGE AAAAY DESCAlpTtCN The Palisades new fuel storage rack has been measured to determine actual *as built

  • dimensions. Figure 2 is an arrangement crawing giving those measured dimenstens. Ths information was supplied by Consumers Power Company.M Subsequent informationA established that the dimensions indicated are actually measured center to-center distances between adjacent top bands. Such dimensions, therefore, represent nominal center to-center spacings between adjacent storage locatiers. It should be noted that the nominal center to-center separation between assemolies was designed to be 9.5 inches. Measurements cf tre installed rack, however, show that a maximum negative tolerance of 1/8 inches exists on tne design value. (Therefore, minimum nominal center to center separation of 9 3!8 incnes was assumed for this analysis.)

Concrete walls are adjacent to three sides of the storage array and are separatec from the fuel by 0.5 to 1.5 inches. For_the purpose of this analysis, a 16 inch thick concrete reflector was assumed to be touching three sides and bottom of the storage rack. The founn side and top of the array was assumed to be reflected by 6 inches of water, wnich is effectively an infinitely thick water reflector.

EMF 91 1421lNP)

Page 6 The 3 x 24 array contains 36 fuel assemblies with alternato positions occupied by 8 x 3 inch structural steel box beams having a nominal wall thickness of 5/16 inch.(2) A minimum

- wall thickness of 0.25 inches was established fer this analysis.(8) e S

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EMF 91-1421(NP)

PageB 5.0 CALCULAT10NAL METHODOLOGY The KENO Va Monte earlo computer code (10) was used to mockup the Palisades New Fuel Storage Array. The pin cell composed of fuel rod, gap, clad and moderator regions was explic:tly modelled. The Palisaces N1 assembly with 8 guide bars and a single instrument tube was also explicitly modelled with the exception of using a constant average planar enrichment for the 216 fuel pins within the assembly (this is a conservative assumction, see below).

In conjunction with KENO-Va, the SCALE 27 Group Library l ") was used. Both the : sy 238 U cress sections were corrected for the effects of resonance self shieleing using the and NITAW1. code.02) NITAWL uses the Nordheim Integral Treatment to compute a neutren spectrum which is used to cbtain effective

  • resonance cross sections. Dancert :ctreet.cn 1

factors are used to account for snielding effects due to the close proximity of lattice p:ns.

To demonstrate that assigning fuel pins an average planar ennchment througn cut tre assembly, rather than using :ened enrienments, is conservative the 2 0 transport code.

CASMO-2EU3) was used. CASMO calculations indicate that the actual":oned" N1 assemoty design is approximately 9 mK less reactive than the corresponding constant enrichment assembly.

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6.0 METHODS VAUDATION The calculational methodology used in this analysis was cenchmarked against s:x critical experiments.04.1s) This set of enticals simulated conditions associated with ligrt o

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EMF-91 1421(N P)

Page 9 water fuel stcrage pools and were conducted at both the Battelle Critical Mass Laboratory and the Babcock and Wilcox CX-10 cntical facility.

The benenmark results are given in Table 2. The corresponding bias (mean difference) and benchmark' uncertainty (difference standard deviation) of these ::enenmarks are O C0755 and 0.00414, respectively, i TABLE 2. Cntical Expenment Benchmark Results Calculated Measured Citference Bench No. K E4ective. C K Effective M WC 4 0.99552 +/ 0.00308 1.00000 0.CC448 7 0.99109 +/ 0.003C6 1.0C000 0.CCS91 29 0.99870 +/ 0.00379 1.00000 0C0130 2245 - 0.98983 +/ 0.00255 1.00000 0.01017 2266 0.99244 +/ 0.00267 1.00000 0.00756 2321 0.98710 +/- 0.00300 1.00000 0.01290 Mean Difference = 0.00755 (Bias)

Standard Ceviation = 0.00414 (Benchmark Uncertainty)

A Kolmogorov Smirnov test was conducted and indicated that the accve difference distnbution agrees well with a theoretical normal distribution.

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EMF 91-1421(NP)

Page 10 7.0 MAJOA CONSERVATISMS The major conservatisms of this analysis were:

  • An average planar enrichment was used for all pin locations, rather than us:ng ':ener' -

enrichments.

  • The most reactive Batch N fuel assembly cesign (i.e., hignest enrichmt.nt sue caten with no burnable poisons) was used in determining storage array reactivity (k eff).
  • Fuel design parameters such as pellet size, pellet censity, clad thickness. etc., Aere ccilectively set to conservative values within the expected manufacturing tolerances.
  • The system was meceled as fleeded with pure water (:ere soluble icisens).

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39e 'l 8.0 PESULTS 22 U fuel this analys s in determining the maximum array reactivity (Kg) for 4 25 w/o evaluated the effects of varying moderater density and 'uel assembly scacing etnin the ra:(-

All rack ccncitions were found to have an acceptable reactivity of Kg <0 35 a'ter acccur*rg fer all uncertaintles and bias. The maximum K-et'ective at the 95% ccnficer.ce teve! e as 0.945.2 The hignest calculated reactivity occurs when the array is fully ficodec Min na'er I

and the fuel assemblies are located in the rack as cepicted in Figt re 3. A summary Of e resu!ts is given in Table 3.

2 95 ucper limit Kg = Calc. Kg + Bias + K95 (Benchmark Vanance - KENC Var:ar:a 2

= 0.92682 + 0.C0755 + 2.015 (0.004142 + 0.00348

= 0.945 Where 4,95 = 2.015 is Oased en a cre siced ncrmal Students t Cistricution at the 0.05 significance level for 5 cegrees of freecem.

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EMF 91 1421tNP)

I Page 12 1

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h Ficure 3. Palisades New Fuel Storage Array (worst case geometry)

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EMF 911421(NP)

Page 13 TABLE 3. Palisades New Fuel Storage Array Reactivity (Kg) Calculation Pesults for 4.25 w/o "U Fuel)

Array Rack Moderator Calculated geometry Veid Fractien K.effectivo Nominal 0.0 0.91399 -/- 0.00343 Adverse 0.0 0 92682 +/ 0 00348 Adverse 0.05 0.91123 +/ 0.00310 Adverse 0.10 0.89581 +/ 0.C0309 Adverse 0.30 0.85648 +/ 0.00288 Adverse 0.50 0 81299 +/ 0.00329 Adverse 0.70 0.80100 -/ 0 00323 Adverse 0.75 0.79879 +/ 0.003C5 Adverse 0.80 0.79041 +/ 0 CO303 Adverse 0.90 171333 +/ 0.00283 Adverse 0.95 0.63454 +/ 0.00275

  • Adverse Rack Geometry is depicted in Figure 3. Three sides and bottom reflected by 16 in. of concrete; open side and top reflected by 6 in, of water at full density.
  • Fuel / moderator temperature was 20*C.
  • Other than the steel box teams no rack structual components were modelled.

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EMF 91 1421(NP)

Page 14 9.0 ABNORMAL CONDmONS in accordance with ANSI /ANS 57.31983 (6.2.4.1) this analysis evaluated the potential adverse effects of fuel handling accidents. Due to the fact that the Palisades New Fuel Array is a dry storage rack fuel handling accidents do not adversely impact nuclear safety. The infinite multiplication factor (K) for dry 5 w/o N U uranium oxide systems is less tnan 0.S.;*6)

Specific design features # of the rack which preclude flooding include:

1) All cells and spaces between cells have openings at the bottom to facilitate draining.
2) The rack is situated 3 ft above a ecurse steel grading floor. The floor below the grading is approximately another 12 ft.

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EMF 91 1421;NP)

Page 15 4

10.0 CONCt.USIONS This analysis conservatively demonstrates the reactivity of the Palisades new fuel storage array as described for a Batch N fuel assembly with an enrichment of 4 20 w!o 2M U to be less than 0.95 under the worst crecible stcrage array concitions.3 3

Although this analysis was performed using an average planar enrichment cf 4.25 uto:

22 U it is necessary to lower the allowacle ennenment by the manufacturing enrienme-t uncenaintyltelerance wnten is 0.05 wt%2 ny,W

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EMF 911421(NP)

Page 16 11.0 AEFERENCES (1) L E. Hansen," Palisades New Fuel Storage Array Criticality Safety Analysis *, XN NF 3C9.

Exxon Nuclear Co., (July 1975).

(2) C. O. Brown, Palisades New Fuel Storage Array Criticality Safety Reanalysis. XN NF-508, Exxon Nuclear Co., (February 1979),

(3) Advanced Nuclear Fuels Crawing," Fuel Assembly Lead Map Type N1,* ANF 307,3C9 Revision 0, l

(4)' " Palisades Characteristics of Reload N," ANF-CS 386, Revision 1.

(5) " Principal Reload Fuel Design Parameters Palisades Reload M,* ANF 89-063(P).

(6) Letter, W. J. Beckius (CPCO) to W. E. Niemuth (ENC), May 13,1975.

(7) W. J. Beckius, Personal Communication Consumers Power Company, June 10,1975.

(8) 8. Webb, Personal Communication, Consumers Power Company, June 10.1975.

(9) T. Hollowell, Personal Communication, Consumers Power Company, August 26,1991. -

(10) L M. Petrie and N. F. Landers," KENO V.A An improved Monte Carlo Criticality Program with Supergrouping.* NUREG/CR 0200, Cecember 1984.

(11) " SCALE: A Modular Code System for Performing Standarcized Computer Analyses for Ucensing Evaluation,* NUPEG/CR-0200.

(12) R. M. Westfall, "NITAWL S," ORNL/NUREG/CR-0200, October.1981.

(13) "CASMO 2E; A Fuel Assembly Burnup Prograra (Methodology),* Studsvik/NFA 86/S.

Studsvik Energitekmik AB, Nyk6 ping, Sweden.

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EMF 91 1421(NP)

Page 17 (14) M. N. Baldwin, et al.," Critical Experiments Supporting Close Proximity Water Storage of Power Reactor Fuel, "BAW 1484 7, July 1979.

(15) S, R. Bierman, B. M. Durst, anc E. D. Clayton, " Critical Separation between Sucentical Clusters of 4.29% Enrich 6d Vo2 Rods in Water with Fixed Neutron Poisons.* PNL 2615.

March 1978.

(16) S. R. Bierman and E. D. C!ayton," Gmelin Ha[1cbook of tnorganic Chemistry."

Supplement Volume A6,8th Edition,1983.

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EMF-91 1421 (NP)

Issue Date: 12/09,91 CRIT 1CAUTY SAFETY ANALYSIS FOR THE PAUSADES NEW FUEL STORAGE ARRAY OtSTAIBUTION Consumers Power (5)

J. W. Hulsman C. D. Manning T. C. Probasco Occument Control (5) e____ _____ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..

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