ML20140C152

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Requests Mod to Certificate of Compliance 9853 to Enable Transport of R2 Matls Testing & Research Reactor Elements
ML20140C152
Person / Time
Site: 07109191, 07109853
Issue date: 03/22/1984
From: Regan N
BABCOCK & WILCOX CO.
To: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20140C149 List:
References
NUDOCS 8406190064
Download: ML20140C152 (12)
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~ Babcock.& Wilcox u...i uoci.., po i oi,i. ion t

a McDermott company P. O. Box 785 Lynchburg. Virginia 24505-0785 (804) 522-6000 March 22, 1984 30 C0

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USHRQ U. S. Nuclear Regulatory Commission Attn:

C. E. MacDonald, Chief 8;

APR 4 gg g p -2 Transportation Certification Branch NMM Division of Fuel Cycle & Material Safety, NMSS M[y RK d

Washington, D. C. 20555 f,

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Gentlemen:

U The Babcock and Wilcox Company, Naval Nuclear Fuel Division is requesting a modification to shipping container USA /9853/B( )F, Cer-tificate of Compliance Number 9853, per 10 CFR 71.31(b) and 71.13(b) to enable this package to be used for transporting R2 Materials Testing and Research Reactor elements.

The nuclear criticality safety of the R2 elements transported in the 9853 container is provided in the attached Babcock and Wilcox Company, Lynchburg Research Center letter from M. N. Baldwin to N. A.

Regan, dated March 20, 1984; " Nuclear Safety Analysis of the Unirradiated Fuel Shipping Container for Shipment of R2 Elements".

Pending approval, please make the following changes to Certificate of Compliance No. 9853, dated January 13, 1984:

5 (b) Contents (2) Maximum quantity of material per package ORNL - BNL Container Seven (7) fuel elements containing 3 0 grams U-235 per element with enrichment > 20 wt %

U-235;.orseven(7)uraniumsilicideUfSi/Al 2

fuel elements containing 500 grams U-235 per element with enrichment < 20 wt % U-235.

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- Babcock & VVilcox March 22, 1984 C. E. MacDonald U. S. Nuclear Regulatory Commission and References LRC letter: " Nuclear Safety Analysis of the Unirradiated Fuel Shipping Container for Shipment of R2 Elements", M. N. Baldwin, dated March 20, 1984.

Your expeditious review and approval will be greatly appreciated.

Sincerely, BABCOCK & WILCOX, NNFD I

A Re Nuclear Safety & Licensing Officer NAR:mh Attachment cc:

U. S. Department of Transportation Attn:

R. Rawl Materials Transportation Bureau Office of Hazardous Materials Regulation (OHMR)

Washington, D. C. 20590

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' Babcock GWilcrx Rese:rch and Devtpm:nt Division a McDermott company Lynchburg Rise rch Cint;.r Lynchburg, Virginia 24505 pg To RW Carson, NNFD-31; N. A. REGAN, Nhr 0-31 RA Cordani, NNFD-3, AJ Koudelka F rom RH Lewis M. N. BALDWIN, CHEMICAL & NUCLEAR ENGINEERING, LRC Cust.

File No.

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Subj.

NUCLEAR SAFETY ANALYSIS OF THE UNIRRADIATED FUEL SHIPPING oate CONTAINER FOR SHIPMENT OF R-2 ELEMENTS MARCH 20, 1984 The Analysis of the Unirradiated Fuel Shipping Container, designed by ORNL, is complete. The attached analysis shows that the container is suitable for shipping up to seven LEU, R-2 fuel elements with loadings not exceeding 500g U-235 per element. The attachment may be used as a basis for amending Certificate of Compliance #9853 to include the R-2 elements.

Q.A. Statement:

I have reviewed this work including comparison to earlier work at ORNL and detail checks of current computer runs with the U Si /Al R2 3 ?

fuel elements.

I agree with the reported results and with the reported conclusion that the shipping containers can be safely used for the R2 elements and meet the requirements of 10 CFR 71.57.

F. M. Alcorn

)r), 71. fjQg M. N. Baldwin l

l i

Babcock & Wilcox a McDermott company Page 2 M. N. Baldwin to N. A. Regan March 20,1984 1.

Introduction The Unirradiated Fuel Shipping Container, designed by Oak Ridge National 1

Laboratory and licensed by NRC for shipping specified types of unirradiated fuel elements, is examined herein from a NJClear Criticality Safety point of view for its suitability for shipping R-2 fuel elements.

The overall safety analysis of the container has been reported in reference 2.

The R-2 elescet is geometrically similar to an "MTR element" as is the HFBR elements assumed for the ORNL evacuations of the container, but incorporates U 3I /Al as the core material. The fuel is proliferation 3 2 resistant low enriched uranium (<20 wt% U-235), and each element may be loaded with up to 500g of U-235.3,4 The element is illustrated in Figure 1.

It is made up of 18 fuel plates, each loaded to 27.2 + 0.5g of U-235.

Total length including end adapters is 36-3/8 inch.

II. Method of Analysis Our analysis follows that used by Thomas,6 in proving the criticality 5

safety of HFBR element & ALRR converter element shipments:

1.e., the KEN 0 IV code and the Hansen-Roach cross-section sets were used, nine element positions are assumed per packages rather than the actual seven, the steel forming the inner basket was associated with each element in an identical manner, the nature of container damage was identical, and the geometric representation of the container was identical.

In addition, our analysis incorporated the reduced density phenolic foam described in the re-evaluation of the ORR Shipping Package by Thomas.7 The validity of using the KEN 0 IV code and Hansen-Roach cross-section set for LEU fuel (~20% enriched) was demonstrated by a calculation of the LEU

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Babcock & Wilcox a McDermott company Page 3 M. N. Baldwin to N. A. Regan March 20,1984 Critical Experiment which was conducted at the Ford Nuclear Reactor, University of Michigan in Decerrber,1981. This calculation explicitly modeled each fuel plate and water gap as has been done in the present safety evaluation. This benchmark calculation gave a result that exceeded the measured value by a AK of 0.027 + 0.007. Details of this calculation are 5_

reported in reference 8.

Thomas.eferences the work of D. W. Mugnuson for validation of the code and cross-section sets used with borated-phenolic foam.

Results of Calculations Results of the calculations are presented in Tables 1 and 2.

Note that an infinite array of packages under normal conditions gives a very low Keff of less than 0.3.

When the interior of the packages is flooded and no water is present between the packages to provide isolation, Keff reaches a maximum.

In this latter case, Keff reaches 0.96 when nine elements per package are assumed loaded and the package is assumed damaged. When the number of elements is reduced to seven, by filling two element positions with water, Keff of an infinite array of packages is well below 0.9 for all postulated conditions.

Conclusions Calculations show that up to seven LEU, R-2 fuel elements with loadings not exceeding 500g of U-235 per element, meet the requirements of a Fissile Class I package in transport, when loaded into the Unirradiated Fuel-Shipping Container No. USA /9853/B( )F.

Since a Fissile Class I package is more restrictive than a Fissile Class II or III (from a nuclear criticality safety -

viewpoint), the package evaluated is acceptable for all class shipments.

e Table 1 Computed Keff for the Undamaged Package Keff + o Number of l

Packages Condition 9 elem/pkg 7 elem/pkg Arrangement of 7 Elements Infinite array No water preset 0.249 + 0.003

+

Infinite array Packages flooded, and 0.833 + 0.008 water between packages Infinite array Packages flooded, and no 0.914 + 0.010 0.854 + 0.009 EEW water between packages EEE EEW Table 2 Computed Keff for the Damaged Package Keff + 0 Number of Packages Condition 9 elem/pkg 7 elem/pkg Arrangement of 7 Elements Infinite array Packages flooded, and 0.822 + 0.010 water between packages Infinite array Packages flooded, and no 0.961 + 0.009 0.844 + 0.009 EEW between packages EEE WEE

. Infinite array-~ between packages EEW Packages flooded, and no 0.854 + 0.010 EEE EEW D

N References 1.

Certificate of Compliance No. 9853 dated January 13, 1984.

2.

Safety Analysis Report for Packaging:

The Unirradiated Fuel Shipping Container ORNL/ENG/TM-15, September 1979.

3.

Statement of Work for Fabrication of LEU Silicide Fuel Elements To Be Irradiated In The R-? Reactor, ANL Document No. A0004-1024-SA, Rev. 00, January 25, 1984.

4.

Babcock & Wilcox NNFD Contract No. 31-109-38-6734 Supplemental Agreement No. 3.

5.

Nuclear Criticality Safety Assessment of ORR, NBS, and HFBR Fuel Element Shipping Package, J. T. Thomas, ORNL/CSD/TM-77, January,1979.

6.

Union Carbide letter dated March 21, 1979 f rom J. T. Thc..as to R. W.

Knight.

7.

Union Carbide letter dated September 10, 1979 f rom J. T. Thomas to J. H.

Evans.

8.

Babcock & Wilcox memo dated March 20, 1984 from M. N. Baldwin to F. M.

Alcorn.

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.s Appendix A Data Input tb.

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MIXTURES AND NUMBER DENSITIES 1

-92504 2.39803-03 1

92803 9.50083-03 FUEL MEAT 1

14100 7.92159-03 1

13100 3.46789-02 2

13100 6.02726-02 ALUMINUM 5

502 1.00000+00 WATER 7

13100 1.13837-02 END FITTINGS

-7 502 0.8113O+00 10 200 1.00000+00 STAINLESS STEEL 11 100 1.00000+00 CARBON STEEL l

13 6100 1.10880-03 13 1101 1.39150-03

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13 8100 7.78390-04 13 5100 8.88440-05 13 14100 3.77890-05 BORATED PHENOLIC FOAM 13 11100 4.11060 - - - - - - -

13 17100 5.84920-06 13 13100 2.26010-06 13 12100 2.48320-06 13 20100 1.52160-05 14 6100 2.72390-03 14 1101 3.24120-03 14 8100 1.75120-03 14

- 5100 1.40660-04 14 14100 5.98470-05 BORATED PHENOLIC FOAM l

14

- - -11100

-6.50780-06

-AND WOOD -

l 14 17100 9.25890-06 14 13100 3.57820-06 14 12100 3.93130-06 14-20100 2.40870-05 15 6100 1 50995-03 15 5100 7.79750-05 15 14100 3.31750-05 15 11100 3.60750-06 CHARRED BORATED PHENOLIC FOAM

( 15 13100 1.98350-06 15 12100 2.17930-06

- ----~ --- - -----

l 15-20100 1.33530. -

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BOX TYPES

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BOX TYPE 1

CUBOID 1

O.32639+1

-0.32639+1 O.38000-1

--0.38000-1 0.29845+2

-0.29845+2 16*0.5 CUBOID 2

O.33422+1

-0.33422+1 -- O. 7 6 0 0 0 -0.76000-1 0.31278+2

-0.31278+2 16*0.5

-CUBOID 5

O.33422+1

-0.33422+1 -O.22250+0

-0.22250+0 - - - - - - - -

0.31278+2

-0.31278+2 16*0.5 CUBOID 2

0.37922+1

-0.37922+1 0.22250+0

-0.22250+0 0.31278+2

-0.31278+2 16*0.5 CUBOID 7

O.37922+1

-0.37922+1 -O.222"O+0

-0.22250+0 O.46196+2

-0.46196+2 16*0.5 CUBOID 5

O.39827+1

-0. 39827+1 - O. 22250+0

-0.22250+0 -

0.88027+2

-0.88027+2 16*0.5

- - CUBOID 10 O.40587+1

-0.40587+1 O.22250+0-

-0. 222 50+0 - - -

0.88344+2

-0.88344+2 16*0.5 BOX TYPE 2

CUBOID 1

O.32639+1

-0.32639+1 O.38000-1

-0.38000-1 O.29845+2

-0.29845+2 16*0.5 ~--

(-O.34449+2 CUBOID 2

0.33422+1

-0.33422+1 0.95000-1

-0.95000-1

-0.34449+2 16*0.5 CUBOID 5

0.33422+1

-0.33422+1 0.38200+0

-0.24150+0 0,34449+2

-0.34449+2

-- 16

  • 0. 5 --- - -

CUBOID 2

0.37922+1

-0.37922+1 0.38200+O

-0.24150+0 O.34449+2

-0.34449+2 16*0.5 CUBOID 7

0.37922+1

-0.37922+1 0.382000+0 -0.24150+0 0.46196+2

-0.46196+2 16*0.5 CUBOID 5

0.39827+1

-0.39827+1 0.57250+0

-0.24150+O O.88027+2

-0.88027+2

- 16

  • 0. 5 -- -- -- - -

CUBOID 10 0.40587+1

-0.40587+1 0.64870+0

-0.24150+0 O.88344+2

-0.88344+2 16*0.5' BOX TYPE 3

CUBOID

-1 O.32639+1

-0. 32639+1 - - 0. 38000 -O. 38000-1 ------ -

0.29845+2

-0.29845+2 16*0.5 CUBOID 2

O.33422+1

-0.33422+1 0.95000-1

-0.95000-1---

0.34449+2'

-0.34449+2 16*0.5 CUBOID 5

O.3342241-- -0.33422+1 0.24150+0

-0. 38200+L -

0.34449+2

-0.34449+2 16*0.5

- CUBOID -

2 O.37922+1

-0.37922+1 - O. 24150+0

-0. 38200+O -- --- -

O.34449+2

-0.34449+2 16*0.5 CUBOID 7

O.37922+1

-0.37922+1 O.241500+0 -0.38200+0 l

O.46196+2

-0.46196+2 16*0.5 CUBOID 5

O.39827+1

-0.39827+1 O.241500+0--0.57250+0-~

! (.

O.88027+2

-0.88027+2' 16*0.5 CUBOID 10 -0.40587+1

-0.40587+1 0.241500+0 -0.64870+0 l

0.88344+2

-0.88344+2 16*0.5 o

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.,. 7 7

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BOX TYPES (CONTINUED)

(

DOX TYPE 4

CUDOID 5

0.40587+1

-0.40587+1 0.22250+0

-0.22250+0 0.88344+2

-0.88344+2 16*0.5 BOX TYPE 5

CUBOID 5

O.40587+1

-0.40587+1 -O.64870+0

-0.24150+0 0.88344+2

-0.88344+2 16*0.5 BOX TYPE 6

CUDDID 5

0.40587+1

-0.40587+1 0.241500+0 -0.64870+0 0.88344+2

-0.88344+2 16*0.5 AN ELEMENT AND ITS ASSOCIATED MATRIX IS FORMED BY STACKING BOX TYPES ALONG THE Y DIRECTION IN THE ORDER 3,

SIXTEEN l'S,

2.

AN ELEMENT POSITION WITH THE ELEMENT MISSING IS FORMED BY STACKING BOX TYPES ALONG THE Y DIRECTION IN THE ORDER 6,

SIXTEEN 4'S, & 5.

REFLECTGR GEOMERY FOR UNDAMAGED PACKAGES WITH WATER BETWEEN - -

CORE DDY O 1.21761+1

-1.21761+1

-1.33506+1-- -1.33506+1 8.8344+01

-8.8344+01 16*0.5 CYLINDER 13 3.1000+01 8.8344+01

--Bc8344+01 16

  • 0. 5 --- -

CYLINDER 14 3.1000+01 1.03108+2

-1.02944+2 16*0.5

-CYLINDER 11 3.1320+01 1.0343+02

1. 035B+02 16*0.5 CUDOID 5

3.13B+01 -3.138+01 3.138+01 -3.138+01 1.138+02 -1.138+02 16*0.5

-~-

REFLECTOR GEOMETRY FOR DAMAGED PACKAGES WITH WATER BETWEEN CORE-BDY

.O 1.21761+1

-1.21761+1 1.33506+1

-1. 33506+1 --

8.8344+01

-B.8344+01 16*0.5 CYLINDER 13 2.3380+01 8.8344+01

-8.8344+01 16*0.5 k

CYLINDER 14 2.3380+01 Y.5400+01

-9.5400+01 16*0.5 CYLINDER.15 3.1000+01 1.0311+02

--1.0294+02

-16*0.5 CYLINDER 11 3.1320+01 1.0343+02

-1.0358+02 16*0.5 CUBOID 5

3.138+01 -3.138+01 3.138+01 -3.138+01 1.138+02 -1.138+02-16*0.5

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Appendix B Keno Run Identifiers Hash Code Date-Keff i a ACRAAXN 3-13 0.833 1 0.008 ACRAAXK 3-13-84 0.822 1-0.010 ACRAAYL 3-13-84 0.249 1 0.003 ACRABKV '-

3-13-84 0.844 1 0.009 ACRABKH 3-13-84 0.854 1 0.010

- ACRAAX0 3-13-84 0.914 1 0.010 ACRAEBP 3-12-84 0.961 + 0.009 4

l ACRAAXP 3-14-84 0.854 1_0.009 f

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