ML20140C145
| ML20140C145 | |
| Person / Time | |
|---|---|
| Site: | 07109191, 07109853 |
| Issue date: | 04/05/1984 |
| From: | Regan N BABCOCK & WILCOX CO. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20140C149 | List: |
| References | |
| 23513, NUDOCS 8406190062 | |
| Download: ML20140C145 (12) | |
Text
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Babcock & Wilcox n...i nuci..r ru.i oivision a McDermott company
' Cx5 P. O. Box 785 A Lynchburg, Virginia 24505N
(,804) 522 6000 Ap g -5,>1984 Docket No. 71-91 O
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U. S. Nuclear Regulatory Commission mj JUN 6 1984
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Attn:
C. E. MacDonald, Chief Transportation Certification Branch 6-tm
/j Division of Fuel Cycle & Material Safety, NMSS
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Washington, D. C. 20555 A.
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.7 Gentlemen:
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The Babcock and Wilcox Company, Naval Nuclear Fuel Division requested a modification to shipping container USA /9853/B( )F, Certificate of Compliance Number 9853, in a letter from N. A. Regan of B&W to C. E.
MacDonald of the NRC and dated March 22, 1984. This letter replaces the above referenced letter in its entirety.
B&W, NNFD is now requesting a different modification to the USA /9853/
B( )F shipping container which will involve the issuance of a new certificate of compliance and package identification number. Because this modification involves the use of this container for shipments of Type A quantities of material per 10 ryR Part 71, B&W is requesting the container be redesignated AF for low enriched fuel shipments. Per a telephone discussion with R. H. Odegarrden of your office, the new Certificate of Compliance No. would be USA /9191/AF and the new model No. would be 9191.
This redesignation would enable this container to be used more expeditiously for international air shipments. B&W intends to use the ORNL or BNL redesignated container for transporting R2 Materials Testing and Research Reactor elements to European customers.
The nuclear criticality safety of the R2 eleuants transported in the 9853 type 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 for the Unirradiated Fuel Shipping Container for Shipment of R2 Elements".
Upon approval, the following will be the only changes necessary to Certificate of Compliance USA /9853/B( )F for redesignation as Certificate of Compliance USA /9191/AF:
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y babcock & VVilCOX April 5, 1984 5(b) Contents (2) Maximum quantity of material per package ORNL-BNL Seven (7) uranium silicide U3Si2/A1 fuel elements containing no more than 500 grams U-235 per element with enrichment 20 wt % U-235.
References Safety Analysis Report for Packaging: The Unirradiated Fuel Shipping ORNL/ENG/TM-15, September 1979.
Nuclear Criticality Safety Assessment of ORR, NBS, HFBR FUEL Element Shipping Package, J. T. Thomas, ORNL/CDS/
TM-77.
Union Carbide letter September 10, 1979.
ORNL letter dated September 18, 1979.
Department of Energy letter dated November 1, 1979.
LRCletterdatedMareb 20, 1984.
i B&W has classified this request as an administrative amendment and a check for the applicable fee is enclosed.
We request a priority review by your office so that the necessacy endorsements may be obtained for international shipment.
Sincerely, BABCOCK & WILCOX, NNFD N. A. Regan Nuclear Sa ety & Licensing Officer NAR:mh I
Attachment cc:
U. S. Department of Transportation Attn:
R. Rawl Materials Transportation Bureau Office of Hazardous Materials Regulation (OHMR)
Washington, D. C. 20590 l
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'"TRANSPORTATIO!!APPRoyALSa DoEket No.71 - 9 t 91 l
William O. Miller License Fee Management Branch Office of Administration MATERIALS TRANSPORTATION APPROVAL CLASSIFICATION Applicant:
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'3Y Approval No: O/ 9 /
Fee Category
/ /.D Application Dated:
ApM l F,19% 9-Received: t//JA/T[LF/>d Applicant's Classification:
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The abo.ve application for amendment has been reviewed by the NMSS Transportation Branch, in accordance with Section 170.31, and is classified as follows:
- 1. ' Amendments to Acoravals in Fee Catecortes'11A throuch 11E e,
(a)
Major ftt Al 8 b O M " # " #
(b) y Minor
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Justificatio for clasificatUn:
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The application was filed (a) pursuant to written HRC request and the amendment is being issued for the convenience of the Corcnission, or (b)
Other (State reason):'
J Sigr.ature: khh Transportation Branch,'I :SS Date: 4/l9f9-f 6
Babc3ck &Wilczx Ruurd and Du&pment Di ision l
a McDermott company Lynchburg R:se:rch Center Lynchburg, Virginia 24505 l
pg l
To RW Carson, NNFD-3 RA Cordani, NNF N. A. REGAN, NNFD-31 q
AJ Koudelka l
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RH Lewis l
'M.
N. BALOWIN, CHEMICAL & NUCLEAR ENGINEERING, LRC l
C:st.
File No.
l or Ref.
Subi.
NUCLEAR SAFETY ANALYSIS OF THE UNIRRADIATED FUEL SHIPPING o te 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 suitaale 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 amerding Certificate of Compliance #9853 to include the R-2 elements.
Q.A. Statement:
I have reviewed thi.; work including comparison to earlier work at ORNL and detail checks of current computer runs with the U Si /A1 R2 3 p 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.
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F. M. Alcorn k, n. AR M. N. Baldwin o
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Babcock &Wilcox a McDermott company Page 2
-M. N. Baldwin to N. A. Regan March 20, 1984 I.
Introduction The Unirradiated Fuel Shipping Container, designed by Oak Ridge National I
Laboratory and licensed by NRC for shipping specified types of unirradiated fuel elements, is examined herein from a Nuclear 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 element is geometrically similar to an "MTR element" as is the HFBR elements assumed for the ORNL evacuations of the container, but incorporates U SI /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 5
Our analysis follows that used by Thomas,6 in proving the criticality 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 l
element positions are assumed per packages. rather than the actual seven, l
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 b
5
- s Babcock &WHcom 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 December,1981. This calculation explicitly modeled each fuel plate and water gap as has been done in the present safety evaluati on. 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 references the work of D. W. Mugnuson for validation of the code and cross-section sets used with borated-phenolic foam.
Results of Calculations Results.'f 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.
I Conclusions Calculations show that up to seven LEU, R-2 fuel elements with loadings not exceeding 500g of U-23,5 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.
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SECTTON THROUGH R2 IS-PLATE FUEL ELEMENT l
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FIGURE 1
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Table 1 Computed Keff for the Undamaged Package Keff + o Number of 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 Packaget 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 + a 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 Packages flooded, and no 0.854 + 0.010 between packages EEW EEE EEW
References
.4 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-2 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 from J. T. Thomas to R. W.
Knight.
7.
Union Carbide letter dated September 10, 1979 from J. T. Thomas to J. H.
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Evans.
8.
Babcock & Wilcox memo dated March 20, 1984 from M. N. Baldwin to F. M.
Alcorn.
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l Appendix A Data Input e
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MIXTURES AND NUMBER DENSITIES i(r 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
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10 200 1.00000+00 STAINLESS STEEL 11 100 1.00000+00
--- CARBON STEEL 13 6100 1.10880-03 1101 1.39150-03 l(-13 13 8100 7.78390-04 13 5100 8.88440-05 13 14100 3.77890-05 BORATED PHENOLIC FOAM 13 11100 4.11060-06 --
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 14
---11100
- 6.50780-06
- AND WOOD -
14 17100 9.25890-06 14 13100 3.57820-06 l
14 12100 3.93130-06 14-20100
- 2,40870-05 15 6100 1.50995-03 15-5100 7.79750-05 l
15 14100 3.31750-05 15 11100 3.60750-06 CHARRED BORATED PHENOLIC FOAM l(
15 13100 1.98350-06 15 12100 2.17930-06 15 20100 1.33530-05
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l(r BOX..TYP,ES BOX TYPE 1
l CUBDID 1
0.32639+1
-0.32639+1 0.38000-1
-0.38000-1 O.29845+2
-0.29845+2 16*0.5 CUDDID 2
O.33422+1
-0.33422+1 0.76000-1
-0.76000-1 0.31278+2
-0.31278+2 16*0.5 CUBDID 5
O.33422+1
-0. 33422+1 - O. 22250+O
-0.22250+O - - -
O.31278+2
-0.31278+2 16*0.5 CUBDID 2
O.37922+1
-0.37922+1-O.22250+0
-0.22250+0 O.31278+2
-0.31278+2 16*0.5 CUDDID 7
O.37922+1
-0.37922+1 O.22250+0
-0.22250+0 O.46196+2
-0.46196+2 16*0.5 CUBDID 5
O.39827+1
-0.39827+1 -O.22250+0
-0. 22250+0 --
0.88027+2
-0.88027+2 16*0.5~
--CUBDID 10 O.40587+1
-0.40587+1 0.22250+O
-0. 222 50+O - -- - -
O.88344+2
-0.88344+2 16*0.5 BOX TYPE 2
CUBDID 1
0.32639+1
-0.32639+1 0.38000-1
-0.38000-1
. O.29845+2
-0.29845+2 16*0.5 CUBDID 2
0.33422+1
-0.33422+1 0.95000-1
-0.95000-1
-O.34449+2 --
-0.34449+2 16*0.5 CUBDID 5
0.33422+1
-0.33422+1 0.38200+0
-0.24150+0 0.34449+2
- -0. 34449+2
- 16 *0. 5 ----
CUBDID 2
O.37922+1
-0.37922+1 O.38200+0
-0.24150+0 l
O.34449+2
-0.34449+2 16*0.5 CUBDID 7
0.37922+1
-0.37922+1 0.382000+0 -0.24150+O O.46196+2
.-0.46196+2 16*0.5 - - - - - - -
CUBDID 5
0.39827+1
-0.39927+1 0.57250+0
-0.24150+0 O.88027+2
-0.88027+2 1 6
- O. 5 - -- - -- - -- - -
CUBDID 10 0.40587+1
-0.40587+1 0.64870+0
-0.24150+0 O.88344+2 -
-0.88344+2 16*0.5 CUBDID 1
O.32639+1
-O. 32639+1 - O. 38000-1
-0.38000-1
- O.29845+2
-0.29845+2 16*0.5 l
CUBDID 2
O.33422+1
-0.33422+1 O.95000-1 --0.95000-1 l
0.34449+2
-0.34449+2 16*0.5 CUBDID 5
O.33422+1
-0.33422+1 0.24150+O
-0. 38200+O - - -
0.34449+2
-0.344
- 2 16*0.5
-- CUBDID 2
0.37922+1
-0.37922+1 0.24150+0
-0. 38200+0 - --- -- ---
0.34449+2
-0.34449+2 16*0.5 l
CUBDID 7
0.37922+1
-0.37922+1 0.241500+0 -0.38200+0 O.46196+2
-0.46196+2 16*0.5 g
CUBDID.
5 O.39827+1
-0.39827+1 - O. 241500+0
-0. 57250+0 ' -
( O.88027+2
-0.88027+2 16*0.5 CUBDID 10 0.40587+1
-0.40587+1 O.241500+0 -0.64870+0 0.08344+2
,-0.88344+2 16*0.5
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