Text

Application for Amend to Certificate of Compliance 5450 to Permit Use of Carbon Steel Matl as Neutron Absorber Plates in RCC-4 Container.Revised Pages to 801217 License Renewal Application Encl
	ML20031E492
Person / Time
Site:	07105450
Issue date:	09/04/1981
From:	Mardi A; WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Macdonald C; NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
	19640, LA-81-193, NUDOCS 8110160005
	Download: ML20031E492 (32)
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Attention:

'!r. Charles E. fiacConald, Chief Trarsportaticn Certificatico Branch Gentlemen:

Subject:

Arendment to RCC Shipoing Package Certificate cf Ccmpliance No. 5450 Docket 71-5450 i

The Westinghcuse Electric Corp: ration hereby submits this reques: for an arend-ment to the RCC shi: ping package.

The curpose of this amendrent is to gernit the use of carbon steel ~aterial as the neutron absorber clates in th: RCC l container.

The amendment is in the form of revised pages' (marked Revisior.3 'io. 2) to cur license renewal application dated Decerber 17, 1980 as modified on January 21, 1981.

The porciens of each page which have been changed are indicated b; a bar in the margin of that page.

'?hile only a few pages in attachment =19 have been changed, the entire attacer.ent is included in t!is 2, r. d. =_ n *.. o d. - l i =.,v

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g inforFation.

Please also note that on pages 1 and 2, a aince correction has been mace to two drawing numbers which. vere inadvertently mi,<ed up an the criginal suMittal For acc; racy, a corresponding correction should be made to it=m 5(a)(3) of the r=_, : :lt. ~,... r_

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r A check in the amount of $350.C0 as payment of the minor amendment fee is b=ing transmitted under e arate correspcndence.

Your timely revier of this amendment apolication would be appreciated.

If you have any ouesticns regarding this natter please contact me at the above address cr telephone me at (112) 373 a552.

l-Applicant... 5 Q '* ' ' * * * *--

Very truly yors,

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RCC Container Renewal Application

1.1 INTRODUCTION

1.2 PACKAGE DESCRIPTION 1.2.1 PACKAGING 1.2.1.1 RCC Container Designation - RCC (Rod Cluster Control) Shipping Container Gross Weight - 6,300 pounds.

Fabrication - The design and fabrication details for the RCC Shipping Cc +ainer are given in Equipment Specification E-676200, dated 8/9/65, and-Westinghouse drawings 1596E24, 159,825 and 1553E30, which are attached as Appendices 15 and 12 respectively to our application, Coolants

- Not applicable 1.2.1.2 RCC-1 Container Designation - RCC-1 Shipping Container Gross Weight - 7,200 pounds Fabrication - The Cesign and fabrication details for the shipping containers in the RCC-1 series are given in Equipment Specification E-676498, and Westinghouse drawings 1596E24 and 1596E25, 1553E31, which are attached as Appendices 16 and 12 respectively to our application.

Coolants

- Not applicabla 1.2.1.3 RCC-2 Container Designation - RCC-2 Shipping Container Gross Weight-6,300 pounds Fabrication - The design and fabrication details for the shipping containers-in the RCC-2 series are given in Equipment Specification E-676200, and Westinghouse drawings 1596E24, 1596E25, and 1553E31, which are attached as Appendices 15 l2 and 12'of our application.

Coolants

- Not applicable Docket 71-5 4 5 @ ate: 8-29-8 0 Revision No. 2

'Date:

9-2-81 Page 1

1.~ 2.1. 4 RCC-3 Co:'tainer Designation'- RCC-3 Shipping Container Gross Weight-7,200 pounds Fabrication - The design and fabrication details for the shipping containers in the RCC-3 series are.

given in Equipment Specification E-676498, and Westinghouse drawings 1596E24 and 1596E25, 1553E30, which are attached as Appendixes 16_and l2 12 respectively to our application.

i Coolants

- Not applicable i

L.2.1.5 RCC-4' Container Designation - RCC-4 Shipping ',ontainer Gross Weight-8400 pound 9 Fabrication - The desig

.ad : fabrication details for shipping containers in the RCC-4 series are given in 1

Equipment Specification E-953511 and Westinghouse 4

{

drawings 1596E22, 1596E23,-and.1548E55, which are attached'as Appendices 17 and 12 respectively to our application.

Coolants

- Not applicable l.2.2 Operational Features Not Applicable 1.2.3 Contents of Packaainc

1. 2. 3.1 RCC Packaging Contents Descriotion Radioactivity - Not appliccole Identification and Enrichment of SNM - The SNM will be 35 unirradiated uranium enriched 5 w/o in the isotope U.

Form of SNM

- The SNM will be in the form of clad fuel assemblies.

Specific data on-maximum assembly parameters are included in Appendix 18 to this application.

The reactivity values listedLin Appendix 18 equal the computed reactivity adjusted by a factor to provide for-the-probable error in the calculations.

s Docket 71-5450 Dofe: 8-29-80 Revision No. 2 Dole:

9-2-81_

'Poge 2

The contents will be loaded in such a fasaion that if the package were to be flooded and subsequently drained, any. water'which may.have penetrated the contents would drain simultaneously.

In~the clad form, the assemblies will not disruptively react 'or decompose at the - Accident Thermal condition.

No chips, oowders or solutions will be offered for transport in this packaging.

Neutron Absorbers, etc. - Neutron absorber plates, consisting of 0.19" thick, boronated stainless steel containing 1.3 w/o natural. boron or consisting of 0.19" thick, oxygen-free, high conductivity (OFHC) copper, will be mounted in the packaging, when required.

As shown.in Westinghouse drawing 1596E24, these plates are restrained by the massive vertical structure-separating the fuel assemblies, by a heavy end plate at one end, and by a clamp plate secured by two 1/2 inch bolts at the other.

The installation is such that the presence of the. neutron absorber plates may be readily detected by visual 1 examination.

Specific data on assembly parameters which will require the.

use of neutron absorber plates will be included in Appendix 18 to this application.

Maximum Weight of Fissile Content-Listed in AppendixL18.

Maximum Net Weight of Contents - Listed in Appendix.

18 Maximum Decay Heat - Not applicabla, s

Dockef71-5450 Date: 8-29-80 Revision No.

'Date:

Page 3 I

1.2.3.2 RCC-1 Container Contents Description The description and discussions given in Section 1.2. 3.1 will be directly applicable in all respects.

1.2.3.3 RCC-2 Container Contents Description The description and discussions given in Section 1.2.3.1 will be directly applicable in all respects.

1.2.3.4 RCC-3 Container Contents Descriction The description and discussions given in Section 1.2.3.1 will be directly applicable in all respects.

1.2.3.5 RFC-4 Container Contents Descriotion The description and discussions given in Section 1.2.3.1 will be directly applicable in all respects except that the neutron 2

absorber plate may consist of 0.19" thick carbon steel as an alternate.

2.0 Structural Evaluation 2.1 Structural Design 2.1.1 Discussion The design of the RCC series of fresh fuel shipping containers is basically the same for all models.

The fundamental differences between models are length and weight.

All containers are comprised of the container shell (base and cover) and the internals assembly.

Positive closure of the j

shell base and cover is acecmplished by means of high strength bolts or fasteners.

The number of fasteners is prueartional to the length of the container thus maintaining the loading per fastener at a r._arly constant value which is well below the fastener ultimate strength.

Both the shell design and

.' 2-81 E 9' 4 Docket 71-54 50 Date: 8-29-80 Revision No. 2 Date:

l

s ATTACHMENT 18 e

e Docket 71-54 50 Dofe: 8-29-80 Revssion No. -

Date:

9-2-81 Page 18-1 _,

ATTACllMENT ' 18 f

Authorized Package Contents b

L (i)

Type and form of material.

3 i

(i)

Uranium dioxide as zircaloy or stainless steel clad unirradiated fuel elements.

l' Two (2) neutron absorber plates consisting of 0.19" thick, full strength sttinless y

steel containing

1. 3% minimuni boron or 0.19" thick OPilC copper are req ui red between fuel elements of the foilowing sper.fications:

O 3.

=

14x14 15x15 14x14 15x15 17x17 16x16 14x14 o

Zr Zr STT STT Zr Zr Zr Type Clad Clad Clad Clad Clad Clad Clad 1

n Pe lle t_ diameter (nom), i n 0.344-0.367 0.367 0.384 0.384 0.308-0.322 0.322 0.3805 Rod diameter (nom), in 0.400-0.422 0.422 0.422 0.422 0.360-0.374 0.374 0.44 Maximum fuel length, in 144 144 120 120 168 144 144 Maximum rods / element 180 204 180 204 264 235 176

o e

Maximum cross section, (nom), in sq 7.8 8.4 7.8 8.4 8.4 7.8 7.98

{

Maximum U-235/ element, 17.7 18.3 18,5 18.7 16.95 (144"L) 16.6 19.0 kgs 19.8 (168"L)

[

Maximum U-235 enrich-ment, w/o 4.0 3.65 4.0 3.65 3.65 4.0 3.85 w

U (ii) Uranium dioxide as ziicaloy or stainless stell clad unirradiated fuel elements.

k Two (2) neutron absorber plates consistiny of 0.19" thicl carbon steel are required between fuel elemente of the following specifications.

e 17 x 17 sh DS Z]i11jid, co H

Pellet diameter (n>.d in.

0.308 - 0.322 Rod diameter (nom), in.

0.360 - 0.374 2

Maximun fuel length, in.

168 Maxinun ro.is/elenent 264 Maximum cross section, (non), in. sq.

8.4 o

Itaxinum U-235/ element, kgs.

19.3 9

?taximum l'- 2 35 enrichment, w/o 3.55

o h.

(iii) Uranium dioxide as zircaloy or stainluss steel clad unirradiated 2

g fuel rods of the follouing specifications:

"e TYPE SST Clad ZR Clad ZR Clad 4

i t

m

! u Pellet diameter (nom), in 0.384 0.367 0.322 Rod diameter (nom), in 0.422 0.422 0.374

) D Fuel length (max), in 144 144 168 l-Maximum U-235 enrichment, w/o 4.0 4.0 3.65 m

l rh (2)

Maximum quantity of material per package e

Im (i)

For the contents described in (1) (i) or.(1) (ii):

Two fuel elements.

=

c.j.

(ii)

For the contents described l'n (1) (iii):

G' 3

Two inner containers containing not more than 80 kilograms U-235.

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ATTACHMENT 19 Revisi n No. 2 Date: 9-2-81 Page 19-1 Dockef71-54 50 Date: 8-29-80

W SHIPPING CONTAINER CRITICALITY ANALYSIS INTRODUCTION In light of the improvements in the state of the art of criticality calculations in the last several years, a change in the W criticality design methodology has taken place. Criticality calculations are now done using the AMPX-I. modules NITAWL and XSDRNFM for cross section generation and KENO-IV for eigenvalue calculations.

These methode have been benchmarked to various critical experiments and are now used exclusively for fuel assembly criticality calculations.

The W design criteria for the criticality of shipping containers is that Keff < 0.95 on a best estimate basis with minimal additional uncertainties for the maximum credible accident (MCA).

The MCA for an RCC container is two ficoded containers crushed together such t'.lat i

the asse:nblies are separated by four inches of water.

DESIGD METHODS As mentioned previously, the current W criticality design methods employ the two AMPXII) modules NITAW_ nd XSDRNPM along wig. the Monte Carlo code KENO-IV(2)

The NITAWL code is used to add esolved resonance parameters to the 218 joup master library ( ).

The XSDRNPM code then takes the revised 5,. cup library and performs a cell calcu-lation. The solution for this cell calcul: tion is then used to u11 apse the 218 group cross sections into a 19 group library (the group structure recommended by ORNL).

This library is then used as input to KENO-IV.

Cross sections for a shipping container are obtained from a cell calculation.

The cross sections for the structural material and the Docket 71-5450 Date: 8-29-80 Revision No. 2 Date:

9-2-81 Page 19-2

absorber are obtained by introducing trace amounts into the moderator in the cell.

As far as has been determined, this procedure does not produce any bias in the results due to the fineness of the group structure.

The geometric capabilities of KEti0-IV are used to provide an essentially exact two-dimensional representation of the problem.

The problem is con-sidered to extend infinitely along the length of the fuel assemblies, conservatively ignoring the benefits of axial leakage.

tach cell (or box type) is modelled explicitly as a fuel pellet, cladding and ;ssociated moderator.

Thimble cells are also modelled explicitly, i'o credit is taken for the cresence of U-234 or U-236; neither is credit taken for any structural mate.*ial (grids, clamping frames, etc.) that does not extend the full length of the assembly.

A representation of the lCA problem is given in rigure 1.

The boundary conditions on the top and right are zero current, while those on the

~

botton and left are zero flux.

The minimum spacing permitted by the tolerances and the minimum material condition is employed.

The W criticality method has been benchmarked to a set of 30 critical experiments from three sources. Two sets of the experimants were per-formed at Battelle's Pacific fiorthwest Laboratories (4,5); the third was performed at ORtiL(6)

The PiiL experiments were performed with LWR type fuel in LWR type geometries; the ORtil experiments were performed with dry highly enriched uranium metal cylinders.

Table 1 provides general information about the critical experiments.

Table 2 provides statistical information about the Pfil analyses, the ORf4L analyses and the combined set.

As is evident, there is very little difference between the Ptil analyses and the combinea set, indicating the wide range of applicability of the method.

The results of the benchmark calculations show that there is essentially no bias to the experiments, with a 95/95 uncertainty of

.013.

No critical experiment was eliminated on the basis of an anomalous result.

Docket 71-5450 Date:

8-29-80 Revision No. 2 Date: 9-2-81 Page 19-3

\\

CONTAINFR ANALYSIS The RCC container was analyzed for three different W optimized fuel assemblies (0FA) - the 14x14 0FA, the 15x15 0FA and the 17x17 0FA.

These assemblies were designed to maxnnize reactivity by optimizing the H/U ratio.

A separate calculations was done for the 16x16 fuel type.

All of the analyses were done using the fuel with lircaloy-4 cladding, which is more limiting than stainless steel cladding.

Figure 2 shows LEOPARD (7) calculations of Keff versus H/U far the 14x14 and 17xi? lattices (the 15x15 assemblies is already optimized, and no changes have been made to the H/U ratio between standard 15x15 and 15x15 0FA).

In both cases, the OFA is more reactive than the standard assemblys indicating that the OFA is limiting from a criti-cality st2ndpoint. An an.alysis has also been performed for a 17x17 standard fudl assembly in a container in which the copper absorber 2

plate has been replaced by a carbon steel plate of the same dimensions.

Each of the five limiting fuel types was analyzed in the RCC container in KEN 0.

A sammary of the results is given in Table 4, the KEN 0 input listings are in Tables 5, 6, 7, and S, and the nuclide/nuclide number correspondence is given in Table 9 In each case, the best estimate Keff 5 0.95 while the final Keff with uncertainties is less than 0.965.

The 14x14 and 16x16 assemblies, therefore, exhibit no criticality safety problems at enrichments less than or equal to 4 w/o while the 15x15 and 17x1 ' assemblies behave similarly at enrichments less than l

or equal to 3.65 w/o.

The 17xl7 standard fuel assemblies in the con-tainers with carbon steel absorber plates exhibit'no criticality safety 2

prcblems at enrichments less than or equal to 3.55 w/o.

The analysis for CE type fuel is given in Appendix 19B.

The same benchmarks and methods apply.

Figure ? shows the relationship (calcf:ated by LEOPARD) between Keff and rod pitch for all three rod types. The 16x16 rod is the same as Docket 71-5450 Date:

8-29-80 Revision No. 2 Date: 9-2-81 Page 19-4

the 17x17 standard rod.

In each case it is cbvioLs that the drier the lattice the less reactive it is.

A scuare tight-packed lattice o'f individual fuel reds is, therefore, less reactive than those same fuel rods in a fuel assembly.

The fuel assemoly is, therefore, the limiting case for fuel rod shipment,.

CONCLUSION A Monte Carlo criticality analysis of the RCC shipping container has demonstrated that, ;L enrichments of 4.0, 3.65 and 3.65 w/o, the 14x14, 15x15 and 17x17 fuel assemblies, respectively, can be safety shipped without risk of criticality.

If the ccpper absorber plate is replaced by one of carbon steel, the 17).17 standara fuel assemblies can be 2

safely shipped without risk of criticality at an enrichment of 3.55 w/o.

The analysis has also shown that, since loose fuel rods in a tight lattice are less reactive than fuel assembli-s, loose fuel rods of the above enrichments can also be safely shipped in the RCC container.

e e

Docket 71-5450 Dat.:

8-29-80 Revision No. 2 Date:

9-2-81 Pace 19-1

REFERENCES 1.

N. M. Greene, et al, "AMPX: A Moduler Code System for Generating Coucled Multigroup Neutron-Gamma Libraries from ENDF/B," ORNL/TM-3706 (March 1976).

2.

L. M. Petrie and N. F. Cross, " KENO IV - An Improved Monte Carlo Criticality Program," 0RNL-4938 (November 1975).

3.

W. E. Ford III, et al, "A 218-Group Neutron Cross-Section Library in the AMPX Master Interface Format for Criticality Safety Studies,"

CRNL/CSD/TM-4 (July 1976).

4.

S. R. Bierman, et al, " Critical Separation Between Subcritical Clusters of 2.35 wt r235U Enriched UO9 Rods in Water With Fixed Neutron Poisons," Battelle Pacific Northwest Laboratories PNL-2438 (October 1977).

5.

S. R. Bierman, et al, " Critical Separation Between Subcritical Clusters of 4.29 wt ;235U Enriched UO2 Rods in Water With Fixed Neutron Poisons," Battelle Pacific Northwest Laboratories PNL-2615 (March 1978).

6.

J. T. Thomas, " Critical Three-Dimensional Arrays of U (93.2)

Metal Cylinders," Nuclear Science and Engineering, Volume 52, pages 350 - 359 (1973).

7.

R. F. Barry, "The Revised LEOPARD Ccde - A Spectrum Dependent Non-Spatial Depletion Program," WCAP-2759 (March 1965).

Docket 71-5450 Date: 8-29-80 Revision No. 2 Date: 9-2-81 Pace 19-6

Table 1 9

Benchmark Critical Experiments Enperiment Experiment Enrichment Water-To-Fuel Separating Characterizing g

Type Number W/0 U-235 Volume Ratio Material Separation (cm).

eff PNL 015 2.35 2.92 Water 11.92 1.004 1.004 005 8.39 0.993 i.004 022 0.39 1.005 f.004 921 4.46 0.994 1.004 034 Stainless Steel 10.44 1.005 i.004 035 11.47 0.992 i.004 026 7.76 0.992

.004 027 7.42 1.004 t.004 020 Boral 6.34 1.005

.004 016 9.03 0.992 1.004 017 5.05 1.001 r.004 043 Copper 6 88 1.001 2.004 7.00 1.009

.007 044 6.62 1.006

.005 031 004 4.29 3.88 Water 10.64 0.999 2.005 007 Stainles, Steel 9.76 0.999 f.005 009 8.08 0.998 i.006 031 Boral 6.72 0.998 i.005 ORNL NA 93.2 flA Air 15.43 0.998 i.003 23.84 1.006 1.005 19.97 1.005 i.003 36.47 1.001

.004 13.74 1.005 i.003 23.48 1.005

.004 Plexiglas 15.74 1.010

.003 24.43 1.006 1.004 21.74 0.999

.003 27.94 0.994

.005 Steel 14.74 1.000 i.003 Plexiglas Steel 16.67 1.006

.003

7.-

4 Table 2 Benchmark Calculation Statistics DNL Criticals ORNL Criticals Both Sets Number of Experiments 18 12 30 Average Keff (K rr) 0.9998 1.0012 1.004 e

Standard Deviation (S )

0.0055 0.0062

'.0058 0

1 One Sided Tolerance Factor 2.453 2.74 2.22 for 95/95 (k)

Bias (1.0 - Refr) 0.0002

-0.0012

-0.0004 KS1 0.0136 0.0170 0.0128

Table 3 Fuel Type Applicability L_imiting Fuel Type Applicable Fuel Types _

14x14 0FA 14x14 0FA 14x14 Zr Clad All f.ene,ths 14x14 SST Clad 16x16 7.r Clad j

15x15 0FA 15x15 0FA 15x15 Zr Clad 1

All Lengths

~

15x15 SST Clad 17xl? 0FA 17x17 0FA 17x17 Zr Clad, All Lengthst

1 Table 4 Shippin9 Containar KEt10 Results Pin Pin 95/95 final Fuel Type Diameter (In)

Pitch (h)

Enrichment eff "KEtt0 I'e f f

~

14xl4 0FA

.3444

.556 4.00 0.9263

.dO83 0.9417 l

STD

.3659

.556 15x15 0FA

.3659

.563 3.65 0.9434

.0074 0.9583 l

STD

.3659

.563 1

17x17 0FA

.3088

.496 3.65 0.9431

.0047 0.9569 STD

.3225

.496 3.65 0.9413

.0052 0.9553 16x16 STD

.3225

.485 4.00 0.9148

.0098 0.9310 17x17*

STD

.3225

.496 3.55 0.9498

.0048 0.9637 l2

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TABLE 10 l2 ELEMENT IDEtiTIFICATION flUMBERS USED Ifl KEl0S ELEMErlT I.D.

ELEMEf4T 11261039 U-235

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Rod-To-Rod Separation (Inches)

Figure 3 K

Vs Red Separation For Loose Fuel Rods eff 1"SAO v

1

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"TRAtiSPORTATI0il APPROVALS" Docket flo.

'lI ' S William O. Miller License Fee Management Branch Office of Administration MATERIALS TRAtiSPORTATIO t APPRO'/AL CLASSIFICATI0!!

Applicant:

/ M / M,I, M A,, o Approval io:

fMS7)

Fee Category M///)

App'iication Dated: 9////,F/

Received: 9//ff//

Applicant's Classifica[ ion:

%uJW The above application for amen:! ment has been revie, zed by the m'SS Transportation Branch, in accordance with Section 170.31, and is classified av follows:

f 1.

A'rendments to Accrovals in Fee Catncories 11A throuch 11E (a)

Major (b) nor (c)

Administrative 2

Justification for reclassification:

L 3.

The application was filed (a) cursuant to written llRC request and the amendment is being issued for the convenience of the Comnission, or (b)

Other (State reason):

Signature:

bh*

Transportation Branch', f 'SS

'[f[6[3(

Date:

h a

ML20031E492

Text

Subject:

1.1 INTRODUCTION

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==

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