ML20235W603
| ML20235W603 | |
| Person / Time | |
|---|---|
| Site: | 07109191 |
| Issue date: | 09/24/1987 |
| From: | Christopher Boyd BABCOCK & WILCOX CO. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 28658, 87-165, NUDOCS 8710160329 | |
| Download: ML20235W603 (9) | |
Text
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7PWW Babcock '& Wilcox :
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U. S. Nuclear Regulatery Cannission September 24, 1987
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. Attn:. C. E. MacDonala, Chief.87-165
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Transportation Certification Branch 7
Division of Fuel Cycle and Material Safety, NMSS Washington DC 20555 i
G'entlemen:
j
~ 1he Babccck & Wilcox Canpany, Naval Nuclear Fuel Division is requesting a
-1
- modification to. Shipping Container USA /9191/AF, Certificate of Canpliance
.Nunber 9191 in accordance with 10 CFR 71.31(b). The imdifications will enable 1
this package to be used for transporting low enriched silicide/aluninum Petten Fuel elements (with loadings not exceeding 626 grams U-235 per element) as a Fissile Class I, 'II, or III shipnent.
The nuclear criticality safety analysis of the Petten fuel element transported i
l in the 9191 Container is provided in the attached document fran the NNFD Research Laboratory to C. C. Boyd, dated September 2,1987 titled, " Nuclear Safety Analysis of the Unirradiated Fuel Shipping Container for Shipnent of Petten Elements".
y Pending approval, please make the following changes to Certificate of Canpliance Number 9191 dated April 23, 1984:
l
'5 (b). Contents (1) Type & form of material'
{
Unirradiated uranium fuel element enriched in the U-235 isotope composed of aluminun plates.
)
(2) Maximum quantity of material per package ORNL-BNL Container
]
Seven (7) uranubn silicide (U Si A1) fuel elements containing a maximum q
of 626 grams U-235 per fuel eIem nt with a U-235 enrichment of :20 weight t
)
A check for $150.00 is attached to cover the initial amendment fee. @
- s. -
DocmED NNFD requests a priority review by your office so that the necess usnRc 7.
endorsements may be obtained for an international shipment.
(
L OCT 71987~)
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Sincerely, tms 1
MAIL SU3M m
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/3 Char le C. Boyd Jr.
N Nuclear Safety & Licensing Officer l 7-i CCB/s1h /*k 7-p
.Atbchments M U %. -
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ox UNCLASSIFIED 5
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f B710160329 870924-
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>4 References 1.
Certificate of Cmpliance No. 9191 dated April 23, 1984.
q 2.
Safety Analysis Report for Packaging: h e Unirradiated Fuel Shipping Container ORNI/ENG/TM-15, September 1979.
3.
Babcock & Wilcox Application dated April 5, 1984.
l
- 4.
Nuclear Criticality Safety Assessment of ORR, NBS, and HFBR Fuel El ment Shipping Package, J. T. Thmas, OfEL/CSD/TM-77, January 1979.
5.
Union Carbide Letter dated March 21, 1979 frm J. T. hmas to R. W. Knight.
6.
Union Carbide Ietter dated September 10, 1979 trm J. T. % mas to J. H. Evans.
7.
Babcock & Wilcox Memo dated March 20, 1984 frm M. N. Baldwin to N. R. Regan.
8.
Babcock and Wilcox Memo dated September 2,1987 frm M. N. Baldwin to C. C. Boyd.
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To RL Bennett 1
RE Carson-NNTD/42 C. C. BOYD, W FD-42 M Welka From RE Taylor-NNFD/42 LK Trent-NNTD/31 M. N. BALDRIN,' NUCLEAR CRITICALITY SAFETY, NNFD-RL
- Cast, File No.
"' MNB87-24 I
subj.
Date NUCLEAR SAFETY ANALYSIS OF THE UNIRRADIATED FUEL i
SHIPPING CONTAINER FOR SHIPMENT OF PETTEN ELEMENTS September 2, 1987 i
This letter to cover one customgr and one subject only, The analysis of the unirradiated fuel shipping container, designed by ORNL is complete. The attached analysis shows that the container is suitable for shippi'ng up to seven LEU, Petten fuel elements with loadings not exceeding 626 grams U-235 per element. he attachment may be used as a basis for amending Certificate of Compliance #9191 to include the Petten elements.
- h. M. AK, M. N. Baldwia bp Q. A. Statement:
I have reviewed the work reported in this memo.
I have checked the input and output of five computer cases and compared this work to the previous work of Reference 3.
I concur with the methodology, the computer model, the results and conclusions.
?N F. M. Alcorn UNCLASSIFIED ND11/
5'bVl?7
,s.
/
Date Ctssifier f
C. C. Boyd 9/2/87 Page 2 Introduction The unirradiated fuel shipping container, designed by Oak Ridge National Laboratory and licensed by NRC (see Reference 1) for shipping R-2 fuel elements, is herein examined from a nuclear criticality safety point of view for its suitability for shipping Petten fuel elements. The overall safety analysis of the container has been reported in Reference 2 and the nuclear criticality safety analysis for R-2 fuel elements wac detailed in Reference 3.
The Petten element is similar in geometry and composition to the R-2 element for which the container is already licensed.
Both are "MTF. Type Elements". Both contain proliferation resistant low enriched uranium (less than 20 wtt U-235), and both incorporate U Si /A1 as the core material.
3 Each Fetten element is made up of 20 fuel plales, and each plate is loaded with up to-31.3 grams U-235 (i.e., 626 grams for the entire element).
The fueled section of the element is illustrated in Figure 1.
Total length of the Petten fuel elements including end adapters is 35.748 inches.
Method of Analysis This criticality safety analysis, showing that the Petten fuel is acceptable in the shipping cask, is identical to that used in Reference 3 to show the acceptability of the R-2 elements.
The only difference in the two analyses is the substitution of Petten elements for R-2 elements.
Both analyses follow that used by Thomas (Ref s. 4, 5, and 6),
i.e., the KENO IV code and the Hansen-Roach cross section sets were used, nine element pocitions were assumed per cask rather than the actual seven, the steel forming the inner basket was associated with each element in an identical manner, the nature of the container was identical, the geometric represen-tation ot the container was identical, and a reduced density phenolic fcam was assumed.
The validity of using the KENO IV code and Hansen-Roach cross-section set for LEU fuel (approximately 20% enriched) was demonstrated by a calculation of the LEU critical experiment which was condacted at the Ford Nuclear Reactor, University of Michigan, in Decenber,1c81.
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 6K of 0.027 0.007.
Details of this calculation are reported in Reference 7.
Thomas (Ref. 4) references the work of D. W.
Mugnuson for validation of the code and cross-section sets used with j
borate-phenolic foam.
Results of Calculations Results of the calculations for casks containing Petten elements (each element loaded to 626 grams U-235 in a fuel matrix of U si,,/A1) are presented in 3
3 4
1 l
l 1
l
- .Q C. C. Boyd.
9/2/87
.Page 3 Tables l'and 2.
Note that an infinite array of packages under normal conditions gives a very low K-eff of less than 0.3.
When the interiors of the casks are flooded and no water is present between the casks to provide:
isolation,. K-eff reaches a maximum. In this latter cace, K-eff reaches 0.95 when.nine elements'per cask'are assumed loaded and the cask is assumed damaged.. When the number of elements is reduced to seven, by filling two element positions with water (designated by the letter "W" on.the arrangement diagram in Tables 1 and 2), K-eff of the infinite array of packages is well below 0.9 for all postulated conditions.
These~ results are almost identical to these calculated for the R-2 elements, for which the cask was licensed in 1984. Th!s is explained by.a comparison of the K-eff for single, fully flooded and reflected Petten and R-2 elements. ns shown in Table 3, their K-eff values-are virtually identical.
Table 3 also shows that reasonable differences in the Si and Al content of the fuel meat of the Petten elements has essentially no effect on the resulting
'K-eff value.
As a part'of this evaluation effort, eight cases run in 1984 to show the R-2 elements acceptable in this cask were repeated. All re-run results were
=within two standard deviations of the previous results.
Conclusions Calculations show that up to seven LEU /silicide/ aluminum Petten fuel elements with loadings not exceeding 626 grams U-235 per element, meet the requirements of a fissile Class I package in transport, when loaded into an unirradiated fuel shipping container identical to the ones licensed under Certificate of Compliance 9191. Since a fissile Class I package is more restrictive than a fissile Class II or III (from a nuclear criticality safety
-viewpoint), the package evaluation is acceptable for all class shipments.
References i
i 1.
Certificate of Compliance No. 9191 dated April 23, 1984.
2.
Safety Analysis Report for Packaging: The Unirradiated Puel Shipping Container ORNL/ENG/ m -15, September 1979.
3.
Babcock & Wilcox Application dated April 5, 1984.
4.
Nuclear Criticality Safety Assessment of ORR, NBS, and HFBR Puel Element Shipping Package, J. T. Thomas, ORNL/CSD/TM-77, January 1979.
j 5.
Union Carbide Letter dated March 21, 1979, from J. T. Thomas to R. W. Knight.
f 6.
Union Carbide Letter dated September 10, 1979 from J. T. Thomas to J. H.
Evans.
7.
Babcock & Wilcox Memo dated March 20, 1984, from M. N. Baldwin to T. M.
Alcorn.
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Table'l.
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' COMPtffED K-eff VALUES FOR THE UNDAMAGED CASK
(
K-eff' 2e & Run Identifier h ri Arrangement-l~'
of-Casks
. Condition 9 Elem/ Cask 7 Elem/ Cask of 7 Elements-Infinite
.No water present.
0.286':
0.004 g[
JArray' (AUG87* PETA)
- f.,
Infiriite ~
' Casks flooded and 0.808 0.008 Array.
water.between (AUG87*PETB)
P
. casks II
. Infinite Casks flooded and
.0.911' O.006 0.842 +LO.008-EEN
' Array
.no' water between (AUG87*PETC)
(AUG87*PETF)
EEE'
^
casks EEW Table 2 COMPlJTED K-eff VALUES FOR THE DAMAGED CASK -
e,.
K-eff 2a & Run Identifier :
hr Arrangement of' Casks Condition 9 Elem/ Cask 7 Elem/ Cask of 7 Elements
-Infinite.
Casks flooded and 0.813-0.008' Array water between (AUG87*PETD) casks Infinite.
Casks flooded and' O.937 0.008 0.855 0.008-EEW
. Array no water between
-(AUG87*PETE)
. ( AUG87
- PE'IG )
EEE casks WEE
, Infinite ~-
Casks flooded and 0.859 0.008 EEN Array; no water between (AUG87*PETH)
EEE casks EEN i,.
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Table 3-
- COMPARISON'.0F SINGLE FULLY FLOODED AND WATER REFLECTED ELEMENTS OF SLIGHTLY DIFFERENT COMPOSITION-Element.
U-235 Composition of H
.. Geome t ry.'
. Loading'-
Fuel ~ Meat-
~.K-eff' 2e Input'ID 1
'Petten-626 gm U Si,3/Al'
' O.470
.0.006j4 AUG87*PETK 3
g
.Petten.
626 gm' 0 Si,f/Al +10% Si 0.467.
0.006 AUG87*PETL 3
3 Petten
'626.gm.
U Si,3/Al -10% Al-0.467 0.006
' AUG87*PEm 3
3 Petten-
'626 gm.
U Si /A1
- 0.463 0.006.
.AUG87*PETP 3
3 l
R2 500:gm U Si /Al 0.464 0.006 AUG87*R2A 3
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a 1.515 _,,
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PLAi ' % 20
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.087 MIN.
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Figure 1.
Section Through Petten 20-Plate Fuel Element.
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