ML20137F033
| ML20137F033 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/15/1985 |
| From: | Gerrald L SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | |
| Shared Package | |
| ML17195A921 | List: |
| References | |
| XN-NF-84-115, XN-NF-84-115-R01, XN-NF-84-115-R1, NUDOCS 8508260131 | |
| Download: ML20137F033 (27) | |
Text
- - - - - - - - - - - - - - - - - - - - - --- - ----- -- ------ ----- - -- -
l XN -NF- 84-115 REVISION 1 CRITICALITY SAFETY ANALYSIS DRESDEN 2,3 SPENT FUELS STORAGE POOL i WITH EXXON NUCLEAR COMPANY, INC.
9x9 RELOAD FUEL L_ANUARY 1985)
ANUARY 1985 RICHLAND,WA 99352 l ERON NUCLEAR COMPANY,INC.
t
(( 2g }{ ggO 7
XN-NF-84-115, Revision 1 Issue Date: 1/15/85 CRITICALITY SAFETY ANALYSIS DRESDEN 2/3 SPENT FUELS STORAGE POOL WITH EXXON NUCLEAR COMPANY, INC.
9x9 RELOAD FUEL (JANUARY 1985)
Prepared by V
)) -
f' ll/6/[
L. D. Gerrald, Senior Engineer Date Corporate Licensing
~
P.eviewed by: , '[ / -/o - Yr J.E.gieper, Engine 6r Date Corporate Licensing fM S T. L. Krysinsk}i, Manager
' ft/ kW Ddte BWR Neutronics Approved by: ' // ~ J R. Nilson, Manager Date Corporate Licensing rY ww H. E. Williamson, Manager l .hD I
' Date Neutronics and Fuel Management jrs
CUSTOMER DISCLAIMER IMPORTANT NOTICE REGARDING CONTENTS AND USE OF THIS DOCUMENT PLEASE READ CAREFULLY Exxon Nucteer Company's warrantas and representations concoming the subject matter of this document are those set forth in the Agreement between Exxon Nuclear Company, Inc. and the Customer pursuant to which this document is issued. Accordingly, except as otherwise expressly provided in such Agreement, neeths Exxon Nuclear Company, Inc. not any person actmg on its behalf makes any warranty or representation, expressed or implied, with respect to the accuracy, completeness, or usefulness of the information contained in this document, or that the use of any information, apparatus, method or process disclosed in this document will not infringe privetely owned rights; or assumes any liabilities with respect to the use of any information, apparatus, method or process disclosed in this document.
The information contamed herein is for the solo use of Customer.
In order to avoid impeirment of rights of Exxon Nuclear Company, Inc.
in patents or inventions which may be included in the information contamed in this document, the recipient, by its acceptance of this document ayees not to publish or make public use (in the patent use of the term) of such information until so authorized in wntmg by Exxon Nuclear Company, Inc.
or until after six (6) months following termination or expiretson of the aforsened Ayeoment and any extension thereof, unless otherwise expressly provided in the Agreement. No rights or licenses in or to any potents are implied by the furmehing of this document.
f zwer Foo.7ee L
8
Xft-f1F-84-115, Rev. 1 CRITICALITY SAFETY AtlALYSIS DRESDEll 2,3 SPEllT FUELS STORAGE POOL WITH EXX0ft flVCLEAR COMPAflY 9x9 RELOAD FUEL TABLE OF CONTENTS SECTI0ff Page 1.0 INTRODUCTI0fl 1 1.1 Summary 1 2.0 RACK DESCRIPTION 1 3.0 METHODS 2 3.1 Cross-Section Preparation 2 3.2 Geometry Model 2 4.0 KENO RESULTS 3 5.0 VERIFICATI0tl 5 5.1 Critical Experiment Benchmarks 5 5.2 Supplementary Data 7
6.0 REFERENCES
9 7.0 ATTACHMENTS FROM QUADREX 00CUMErlT 10 8.0 ATTACHMENTS FROM REFERENCE 3 14 4
XN-NF-84-115, Rev. 1 CRITICALITY SAFETY ANALYSIS DRESDEll 2,3 SPENT FUELS STORAGE POOL WITH EXX0fl NUCLEAR COMPANY
~9x9 RELOAD FUEL
~
LIST OF TABLES SECTI0ft Page Table 1 K-inf for 8x8 Fuel 8 Table 2 K-inf for 9x9 Fuel ,
8 Table 3 K-inf for 9x9 Fuel 8 g4 l
l l
h I
i
1 XN-NF-84-115, Rev. 1
1.0 INTRODUCTION
The spent fuel storage racks at Dresden units 2 and 3 were previously analysed for criticality safety assuming 7X7 or 8X8 assemblies in the rack. The assembly-average enrichments used in that analysis were 2.80% '(7X7) and 3.01%
(8X8). That analysis was performed by Nuclear Services Corp. and documented-as NSC-COM-0219-R 001. The reference for this analysis is Rev.5 to the original.
This revision was issued by Quadrex Corp. as document QUAD-1-79-234 in January 1981 This analysis will supplement the referenced document for 9X9 assemblies at average enrichments up to 3.50%.
The previous analysis examined the effect of several parameters on the pool reactivity. These parameters include temperature, eccentric bundle positioning within the rack tubes, an extra bundle at the side of the rack, presence or absence of the channel in the model, and inter-rack spacing. The most reactive condition was to place all racks in contact rather than have the normal 1.75-3.88" of water between the racks.
This analysis focuses on the normal and most reactive conditions as previously determined. Also, data on the effect of missing poison plates within the rack ji are presented.
1.1
SUMMARY
The 9X9 fuel design at 3. 50". average enrichment is demonstrated to meet criticality safety criteria in the spent fuel storage pool.
The primary controls for criticality safety are:
- 1) The fuel shall be a 9x9 design as described in Table I.
- 2) The bundle-average U-235 enrichment (excluding axial blankets) shall not exceed 3.5 wt.%.
- 3) The bundle design shall include 7 (minimum) rods with UO2-Gd203 pellets.
At beginning of life, these pellets shall be 2.0 wt.% (minimum) Gd203.
- 4) Rack characteristics such as dimensions and poison content shall conform to those in the rack description (Section 2.0).
Any 9X9 fuel assembly which meets the limits defined above may be stored l l
l appropriately in the storage pool.
2.0 RACK DESCRIPTION ,
The fuel storage pool arrangement is shown in Figure 3.1-2 (attached) from the Quadrex document. There are 18 racks of the 9x11 type and 15 racks of the 9X13 type. The racks were constructed using stainless steel tubes shown in Figure 3.2-1 (attached) from the Quadrex document. The walls of these tubes contain aluminum-clad Boral . These poisoned tubes were spaced 6.3" apart by welded unpqisoned stainless steel sheets. Thus, an additional tube was formed between
2 XN-NF-84-115, Rev. 1 the poisoned tubes. The racks are a checkerboard array of poisoned and unpoisoned tubes. However, the internal unpoisoned tubes are surrounded by poisoned tubes which ef fectively makes all tubes poisoned. Only the edges of the rack have the potential for interacting with adjacent bundles (in adjacent racks) without intermediate poison. The edge-edge spacing between racks is typically 1.75-3.88". -
3.0 METH00S The effective multiplication factor (k-eff) for the storage pool was calculated using KENO-IV. All computer codes except XFYRE (2) are as described in the SCALE (1) package. The methods involved in this analysis include cruss section preparation, geometry modeling, and verification of the computer codes and cross sections employed. These methods are detailed below.
3.1 CROSS SECTION PREPARATION The codes employed include XFYRE, NITAWL, and XSDRNPM.
The Dancoff factor and the sigma-m (eff) values (for input to NITAWL) were calculated using the algorithms in section F1 of the SCALE package. Sauer's approximation for the Dancoff Correction in a square lattice was used.
XFYRE, an ENC code to calculate the microscopic depletion of BWR assemblies, was used to calculate the peak reactivity condition and the atom densities at that condition.
NITAWL was used to fetch the needed cross section sets from the XSDRN library and to make resonance corrections to sets such as U-238. The output was a 123 energy-group library.
XSDRNPM was used to collapse the 123 group sets to 41 groups. This was a straight 3/1 collapse. Cell weighting was used in the XSDRNPM run to prcduce bundle-average cross sections to be used in KENO.
3.2 GEOMETRY MODEL A single 9x11 rack was the model for this analysis. An infinite pool of 9x11 racks will be more reactive than a pool of 9x13 racks because the 9x11 rack has a higher fraction of unpoisoned tubes at the edges of the rack. The 9x11 rack has 18 unpoisoned edge tubes per 99 total tubes compared to 20 per 117 for the 9x13 rack. Therefore, the 9x11 system will have more unpoisoned inter-rack interactions than the 9x13 system. Spectral reflection was applied at all six faces of the model. This model represents an infinite array of infinite length I racks. This is a conservative model of the spent fuel storage pool.
The effect of missing poison plates was examined by placing unpoisoned tubes in model locations where poisoned tubes should have been placed. Thus, missing poison plate cases were conservative in that all poison plates of a tube were removed rather than randomly removing single plates from non-contiguous rack locations.
l The " normal" rack spacing was taken as 1.75" of water in the horizontal directions (X,Y). This was modeled by placing 0.875" of water at the edges of
3 XN-NF-84-115, Rev. 1 the rack model and then applying spectral reflection at the outer bound of the water layer. The 1.75" value is a conservative " normal" condition spacing. The actual pool reactivity would be lower than that modeled because of the isolating effect of the larger actual spacings between many of the racks.
The temperature of the pool was 40F, the most reactive temperature per the Quadrex document. The racks were flooded with full density water.
The detailed dimensions of the tubes in a rack were taken from Figure 3.3-1 (attached) of the Quadrex document. This figure shows part of a typical 2x2 array of rack tubes with bundles. One quadrant from each of the four tubes is depicted. According to Figure 3.3-1, the Boral poison does not extend to the corners of the poisoned tubes.
In the attached copy of Figure 3.3-1, the poisoned regions are darkened. This was modeled by reducing the density of Boral used in the poison regions and then allowing the poison to extend to the corners of the tubes. The total Boral content was conserved.
The Boron content of the poison plate is certified at 0.111 gm B per sq.cm.
(minimum). Use of the minimum certified B content yields conservative results in the KENO model.
Other fuel bundle parameters are listed in the table below.
TABLE I Reference Fuel Bundle Parameters Peak Reactivity ( 6 GWD/MTM)
Parameter Nominal Value KENO Model Clad outer diameter (inch) 0.424 0.424 Clad thickness (inch) 0.030 0.030 Pellet Diameter (inch) 0.3565 0.3565 Rod Pitch (inch) 0.572 0.572 Fuel Density (% TD) 94.5 95.0 Fuel Length (inch) 145.52 (max) infinite Water Rods 2 0 4.0 KENO RESULTS The peak reactivity (exposure-dependent) condition for the 9X9 fuel at 3.50% BOL bundle-average enrichment was calculated using XF YRE. All referenced XF YRE l results are for an in-core bundle (reactor lattice k-inf). The peak tundle reactivity occurs at 6 GWD/MTM exposure. The average U-235 content was depleted to about 2.84% and about 0.27 wt. % Pu has been generated. The model is conservative in neglecting the poisoning effects of fission / decay products and of any residual Gd.
Table I contains other bundle parameters employed in the model.
The k-inf for the bundle at peak reactivity is 1.336 (per XFYRE).
The k-inf for the bundle at zero exposure is 1.166 (per XFYRE).
The results presented below are based on the peak reactivity bundle.
4 XN-NF-84-115, Rev. 1 The conditions analysed include:
- 1) " Normal" conditions. The rack-rack spacing was 1.75" and there were no missing poison plates.
- 2) All racks in contact ( 0 rack-rack spacing ) with no missing poison plates. This is the most reactive condition per section 3.3.5 of the ll Quadrex document.
- 3) All racks in contact with four missing poison plates. The missing plates were the four plates in tube (5,5) of the 9x11 tube array. Tube (5,5) is normally poisoned. In this case, five unpoisoned tubes are together in the middle of the rack.
- 4) All racks in contact with eight missing poison plates. The eight missing poison plates were those of tubes (5,5) and (5,7). In this case, 10 unpoisoned tubes are together in the middle of the rack.
The KEN 0 results for these four cases are listed below. The standard deviations l of the Monte-Carlo k-eff's are also listed. d 9X9 BUNDLES IN RACK 6 GWD/MIM EXPOSURE (PEAK REACTIVITY) 3.50% ENRICHED AT BOL Rack-Rack Spacing Missing plates k-eff (inches) 1.75 0 0.807 +- 0.005 0 0 0.923 +- 0.005 0 4 0.929 +- 0.005 0 8 0.942 +- 0.004 The results indicate that k-ef f meets the 0.95 limit (95% confidence) when all racks are in contact and eight poison plates are missing. The eight missing plates (8/200) is equivalent to one missing per 25 total. The limit in the original analysis was 1 missing per 32 total. These results for missing poison '
plates are presented for information. There is no requirement that the system I l meet a 0.95 limit on k-eff with a specified percentage of missing plates.
These results demonstrate that the 9x9 fuel design meet the applicable criticality safety criteria.
l l -
t 1
5 XN-NF-84-115, Rev. 1 5.0 VERIFICATION 5.1 CRITICAL EXPERIMENT BENCHMARKS Supplementary benchmarking of the methods employed was done using the data in Reference 3 . -
The reference contains critical experiment data for a 3X3 array of bundles.
Experimental sariables include the bundle-bundle spacing and boron poisoning in -
the core water and in rods or sheets between the bundles. The cases selected (
for benchmarking were 2317, 2321, 2378, 2396, and 2420. These cases were selected as the most severe test of the methods. The other cases contained relatively minor changes in the water temperature or the boron content of the water.
Tables 6 and 7 and Figures 19,20,22,23, and 24 from Ref.3 are attached for E reference.
BENCHMARK RESULTS DATA 0F REF.3 Case k-eff k-eff k-eff
- (measured) (calculated) (final result) {
2321 1.0030 +/- 0.0009 0.997 +/- 0.005 1.007 2317 1.0083 +/- 0.0012 1.004 +/- 0.004 1.012 2378 1.0000 +/- 0.0010 1.009 4/- 0.005 1.019 2396 1.0001 +/- 0.0019 1.004 +/- 0.004 1.012 2420 0.9997 +/- 0.0015 1.002 +/- 0.004 1.010 The average of the measured k-ef f's is 1.0022. The average of the average ENC results is 1.0032. These results indicate that the ENC methods produce an average k-eff value slightly higher than actual.
l l The average value of k-ef f f rom a KENO run is not the value used to determine acceptability. Rather, it is the 957. confidence upper limit for the average l
k-eff. This limit is typically taken as the average value plus two standard l deviations. This upper limit is listed as the " final result" in the table above. It is seen that this final result value exceeds the measured value in j every case.
The average and stndard deviation of the individual biases (calc. minus l l measured k-ef f) in the table are 0.00098 and 0.0062 respectively. If the acceptablity limit for k-eff is to be defined per ANS 57.3 (rather than a fixed 0.95 limit ), this limit would be 0.942. The limit is composed of the following terms:
A: The mean calculated k-eff for the benchmark calculations. Since the
) criticals here are not exactly 1.000, the assigned value will be 1.0 plus I the average bias or 1.00098.
B: An allowance for uncertainty in the above parameter. This is taken as the square root of twice the sum of the experimental variance and the bias variance. This allowance is consistent with that in the Quadrex document.
6 XN-NF-84-115, Rev. 1 The assigned value is 0.0089.
C: An allowance for the uncertainty in the calculation of the k-eff to be evaluated. This will be included in the final result for the k-eff value.
This is twice the standard deviation of the average KENO k-ef f. Since this allowance is included in the final result, the acceptability limit will not be adjusted; i.e., the assigned value is zero.
c D: An arbitrary margin to ensure subcriticality. The assigned value is h.
0.05. Therefore, if bias and uncertainties were zero, the limit for k-eff would be 0.95. I The acceptablity limit is composed of the terms above:
Limit =A-B-C-0=1.00098 - 0.0089 0.05 = 0.942 Y
If the results in Section 4.0 are compared with a 0.942 limit (rather than the
~
l 0.95 limit), the normal and worst conditions remain acceptable. The number of missing poison plates required to exceed this limit would be about 5 per 200 total.
Therefore, the system is acceptable even with a conservative allowance for bias uncertainty.
s' l
7 XN-NF-84-115, Rev.1 5.2 SUPPLEMENTARY DATA The KENO results were also compared with those from XFYRE. Themodelhereisanll in-core bundle.
Three cases were modeled for comparison: -
Bundle Enrichment Gad. Rods Exposure Type (%) (#/%) GWD/MTU 8x8 3.01 0/0 0 9x9 3.5 7/2 0 9x9 3.5 7/2 6 The results are presented in Tables 1-3. Variable parameters in these cases were:
- 1) Code
- 2) Cross Section Set / Number of Groups
- 3) System Temperature
- 4) Rod enrichment distribution (explicit or average)
These comparisons are interpreted as follows:
- 1) The average enrichment model is conservative compared to the explicit (5 enrichment) model. The KENO model used for the spent fuel pool analysis used the average enrichment model.
- 2) The peak reactivity of .the 9x9 bundle is less than that of the 8x8 bundle of the original (Quadrex) analysis.
l l
4
8 XN-NF-84-115, Rev. 1 TABLE 1 K-INF FOR 8X8 fuel 3.01% AVERAGE ENRICHMENT ZERO GA00LINIA ZERO EXPOSURE CODE UNIT # ENRICH TEMP GROUPS k-inf -
CELL IN MODEL (F)
XF YRE BUNDLE 5 546 4 1.339 KEN 0 BUNULE 1 546 41 1.371 +/- 0.003 KENO BUNDLE 1 40 41 1.377 +/- 0.003 TABLE 2 K-INF FOR 9X9 FUEL 3.50% AVERAGE ENRICHMENT 7 RODS WITH 2 WT.% GAD 0LINIA ZERO EXPOSURE CODE UNIT # ENRICH TEMP GROUPS k-inf CELL IN MODEL (F)
XFYRE BUNDLE 5 546 4 1.166 KENO BUNDLE 1 546 41 1.190 +/- 0.003 TABLE 3 K-INF FOR 9X9 FUEL j
3.50% AVERAGE ENRICHMENT (AT BOL) l ZERO GADOLINIA (AT THIS EXPOSURE) 6 GWD/MT EXPOSURE CODE UNIT # ENRICH TEMP GROUPS k-inf CELL IN MODEL (F)
XF YRE BUNDLE 5 546 4 1.336 KENO BUNDLE 1 40 41 1.3 76 +/- 0.004 i
9 XN-NF-84-115, Rev. 1
6.0 REFERENCES
- 1) SCALE: "A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation",0RNL/NUREG/CCC-450
- 2) J.M. Sierra ,et al ., "XFYRE: A Multigroup Two Dimensional Theory Code For The Microscopic Depletion of Boiling Water Reactor Assemblies",
XN-CC-37, Exxon Nuclear Co., April 1980.
- 3) M.N. Baldwin, et.al., " Critical Experiments Supporting Close Proximity (
Water Storage of Power Reactor Fuel", BAW-1484-7, July 1979.
l l
10 XN-NF-84-115, Rev. 1 7.0 ATTACHMENTS FROM QUADREX DOCUMENT l
I i
Use, reproduction, transmittal or disclosure of the above information is subject to the restriction on the first or title page of this document.
11 XN-NF-84-115, Rev. 1 NI Od 32I:l" . . _ . . -
I a
t.
'l . ~ ,
1 i ~-
Il % ; g g _
e is j
g p W %. I a ,'
> lt I = % e n r d- r - =m 5 2 W h
- 6. ; i
- e
- 3
- l
['
- t.
. - 5 .
> ., r-. l - ., a-t*
-6,.
s l e > 8 e
+ ,a ,a l N
l r .4 . .-3 l i I -
m
~
~
- t. . . .-.
_. D. 3, q
- ; c-.-- * , , ,_
9 >
- a. ...J ,
O f P E.P at. .e s , a l
D. . . i. .. . . .
i > j .. i.-, > b i
- j 6- m. < r.
l ; I
. O. - i : .
i e * -
4 e
! H' - -,
~ ', s~ a. r . s% ~ ~
i . . i . . i
'5w
- r *.
- j :-
?
, r.1 !,* .
u ._ - a i e t e- i i 3.r ..
I
,i.- ,_
, . . i i s ! t t W I m$
. rm =* g g =-
j u I u ".:
ae eI m
w z g
% , a w i =y
- hg *eg
, 't
=uc
.d %
fi l
g
- d. W ,q w, I L. _ L. *
- l I
c l
m, W u:
I li :. ,_
i e !
l -
, . 5:
4 j i _ p. i , __ _
. , , 1, ..
~
~ ,
~
~
s t e- -
s.
.. . .a
~
~
~ n 'tn A i ? O ; i: 0 4 S- ,.;
, t,. .= s t. ,
i .
- b , *.
I W
-- g:c Ll ww .a e p
b e i s c 6- --
t.
t.
% l .
.. = . 6 1 . p .
%- e e ar-i, ,- e t -
,..u-_ - q,
.t l . l
- t. .- .
c ri.
. ~ . . ..
. . . -i . . , ; .
> % % 6.w. > % .i a m s.
^
- as --
[k IQ
- Y
$ ~_ )
4 m : O [~i j t : 1 1 -
% g - = i; *
- I =
i .,
A : * .L'_ :,; -, -
I$
1 -
- s eo g )
I , ... ,
$ D
- ji g a r 4 e j . . _
, - & Li -- : ,
i l -
- ----; ; g I 1 .. .
l t t l %' ' ~.
' ]
o l ,i & A & t a
i t *= ,
v .
f C Y d* *' Y ' =~
3-5
.O.
- t
.--- ,j,. _ , ,,
e 12 XN-NF-84-115, Rev. 1 M
t n"
.25 CI A. METER HO'. E k FOR PJ'E5 inROLH INNERLIHEROh;Yg IN'TER LINER WELD b I
"'[
,,. %-ENDOFBORALd
\, g' '
\
~~
SEE SECTION A-A
-_ .217 _
.076 - -
.105
{ .C3I BDEN.
/ W' \
E h X>:
w
" , / ~
) / g STAINLE55 STEEL
,,e - ' STAIN ESS STEELg/
) . #" / BORAL
) b h / N
\
~
E IN5IDE
/ OUTSIDE r
SECTION A-A y
ALL LIME;iSIONS IN IN HES
, n ;l lN 4-s' l
INNER LINER o b WELDED EXCEPT.5" GAP AT FOUR CORHERS FIGURE 3.2-1. STAIN.iis STEEL TLTI k VITK 50RAL CORE FOR DRESDEh FUEL STOUSE
l..
13 XN-NF-84-115. Rev. 1 t
e
.O.
.e e.
, "- .iu s o~ 6 h w -
t =
- i l
o, a~
= ore
. t '-
a.et,,Me, B -
a.
8
~ :
w s M E w aC I w
m s a u a a g 8
5 d- 8y*g E. == -
e g
giu~ - m x--< gg_ = =
-e== M E E E ad d E e,*** O g' "
o e cn - -
2 e 11 I
r i
. 2*
e.
' r
= - - . i,t .._._
, !+___ a ;_ ,
~
g
.e .e ac m
8 I
.j _
e
,m m I
w D A_ *
--.- ._ _ _ -. - -. s.,
'- 2 ~ '.l " 3 i
. t________________
e . ._ 1, , i sE N, ,,.
m .m -
55 J
n" k aa 6 1 u J V
h p---____--____
,. I
..___..p ,,
l l
_ 6_-,- . - - - - - - , .
F_--__...-.
, n e g m
- i l "
s 1
- 8
' I t
, , l l l 5
3 I i ll E,3 8 I
E I I I E E i
w w w = w w w .E.,
g h -
N M O " g ~. ?O 0 E
- ". . .1 P,
. E o !o o o e o o d
.I, s
et e's E E g Ew o cw w wo
'N wgC5 5 o o .
- ** c mes s v o o. O c.
i 14 XN-NF-84-115, Rev. I l
8.0 ATTACHMENTS FROM REFERENCE 3 O
, ,-w- - - - - - " " - " _ _ - _ _ -
e 15 XN-NF-84-ll5, Reve 1 I
a.
%_ um e - e e meC e esome == e e ce e ., ce e e e e e%
4 e. - e. ** en
- e e o -e e. o e es e e e
- e.
ax **
e< O. . . e. e. e. e. ac. e. e. e. e. **
O C C O WI O. o o o o
.oCC O c oo.
) . l
- e. . e. e. e. e. e. ce . -
e t e ** . a. o. e. o. e.
- e. e ee Oe.** ce.
- e es ce O .e o - em er e B2* G,I t
e e emeeseememes se ee se me en se e o e .e, es me ** e
.e.e se os se e me se me e4 em *e =e e C es m.
eJ T e ce ee e ao e =e C en ce O **
gec e.s 3 e. e. e. e. e. ew I es me =e es ** m . e. e. ce. e. es. e. en. se. m.
=e e == se e .= m e e M **
. ^f e
w.e C.l ew
.e eC. C C. se e. e=e.ce O ** e es em em - C e ce O
- e. E. *=.e..
=;*..
f 1
- m. ee em .e ce m en en m een.ce. me. eee. ce. ee e, ew ce.
es. e.
ce n O e ce o
.e e ,o a e e- e . . . *
- e. g e. *. o. e, e b es. e. o. e.
e ,
e e e em O_ ~ . en *e e es .e e eDe. e.
- e me C.
- C
- e. e. E.
me e C e M en. o.
me me C4 o . .
b _s e e-4
- e. p e. e. o. e. o. e. e .
pq m
- p ep B ee e ce em M
- o. e. e. ,e.
e% e e e e . e . c j _e . .e o e e e e es er. an e .O se e e.e .e e. en em emseo e e'5 g ef e EneI
$U' a.
m t
eme ' S e.n .e.E ew ** W C O e f
.b _ _
we . . .t.o eu
.e e e e.
ee C en e W ** e
.C 8 e. E. E. E. eD. C.
Sh e
3 _m.
. - e e C e e' es em E.
ee. e. C. E. e=. em. E. P*
"U. a. m
,s .e en .e' e .e e=
- = c . P ee e e e* == .
- e. == e= e. == .e ee - == ,o. e e.t.
. m e e
%. . & E i e. - c.e e *e e e. .
.C E.
- w. ** g 6
d e
4' . _ f e. , T ee. - <er ac- ew ,e C. we u .I n.
e ew er es e. e ce e e e* e u . s. . n. e. c. e. e. - e W.
e w.
b
_64e. d C..mee
,e
, -m.eea4 E.
m.
e
_e C.,
e.
e' en'e. C C Q ee we se.
e=
e e C e
- me<* ee.cee. <e. **
s=
o.
e.
ew **
W l' . en u == - es.
e e. .* ee **
1 E.
M . t
,,c.e 4' e6
.c. e s.
. ==. C
.,,,e
_ .C.
em ca 4 ew * * =* e.
e -
e ~- - - C C C C C C C C C Te
. ..- ~ ~ ~ ~ -~ ~~ e e.- 4 G
. - =
6
'4 C, . .
vi o c.
- e. e.
,u e. e. e.
e.
- e. e.
e.
ec '
- e. _ m.
e.
.~ _~ . _~ _~~ -~.- ~
e.
_ se~
I .
- c. I ,
.= . e c . u, _: *. C c : : C C c C
- s. .' z
- .e r
a e
-. ,o
. .e C *.
t 1 .. .
.e .
. ee e.._.
e
-e .
ao C _ _ _ _ _ - e. _ ,, e, - - - e .e ,
- s. e, _ .i .e. e .e ., ,
_e _. e. - -.e _ ,
.e . - . , ,
e.
. .c . m. - -
- _ . . .e.
e
~ ,.
e* #
, e,a 4 *. et
- C
- ~ ~
.e. ~ e e,.
e
.< -< ~. -~ ~== ~
- e. e=
. ~.~ ~.-~-- -_- - _- _- -
~ w e g
~ ~
~ ~ w e. ~ e. ~ ~ ~ ~
b .e _ _
e __. > ,_ _
__ 3 iabcock & Wilcox
1
.c .
1 f' XN-NF-84-115, Rev. 1
^
16 .
(
~ 1
, .- . ~ .
~ . . .
.~ ~~ - . .. ~ . . .s
.e..
~. ~. o. ~. 3. ~,. . ,
. . ~. ,
w.m.f' o o oe o o e. o . ~.o o~.o~.o . C o o o ~ea
. ~ . ~ . .~ .~.
e
. ... ~
. . . . ~. ~. ~ . . . i
- . . . . . o. . .
.~ ,
.~ ..
i -o . . ~
. .r .
~ .
~.
~ . . 8 ~. .~ o .
- e. ~. o. o. o. . o.
. ~ . -
. ~ - ~ ., ~ ~
.H wo
~
. .o e. ~ . .m
.e e e .
.. . ~. .c -
~. . .o. .. .
. - - ~
~. m ~..,. . .
=l .
~ i .o . . e , - - o o e ~
- o. .. . , o. ~. ~. .
- o. - ~. -. . .
., e - ~ ., . . .
E -
=,, .,
- e. .
.- s
~-...,,..o.
~
~. . - .,
~
. ~
,. .~. .
o .
~ . ~ .
o, .. .
C D
ci .~
.a, . .- ~. ,. . e
,,,, 6o . -
. ,,. c. ac. ~. . . . e, . ~e ,e
~ . . ..~ .
. e.- . ,. . -
,e 3 .,. - - -
e, .I
. ., e
~. .
. e
_ ,- e L
.c ;
H
... ~.- ~ ,
C. . o ! ~. . .,..
c.
~
~
.e, _. e.
,o
~ -
.e .,. -
k N w 8 E
i eo o .r ,. . ,g -,
o ., - - ., - ~ ~
g
. . ~- .
3 . g e. -
g3 9, . .- .- .e . .~.
. e
.~~.- - -
. .~.
C C, '
. No
, ,. .i . . < .
L u .e.
x ~ ~ ~ ~ ~. ,.
. <. ~- ~ ~. ~e -~ .
c' ->
. . ~ .... ~ . . ~ . _ 1 u:
.l s
. ,. , . , . .~
c.
. . ...l .
V
.- a l
- e. .t .V, .V, , .-
, 9 V 9 z_ , . , .- . . _ _ . . ._ - . . _. _ _,
.= ~. ~. ~.
w C . ~. ~ . ~. ~. ~. u
_ ~ _ _ _ - ~ _-_
,. , _.=_.:, .- ~ ~
- ~ ~ ~~ ~~ ~. ~ ~- ~~ ~~ ~ ~ - -
a
~ ~~~.~ ~ ~ ~ .
s
.i. - ,-, - , ,e _ ~ -
.e , _< ., = . - ., . . . -
. ~ ~ ~
._ _._ -- ~ ~ m .e e,, _ _. _e
.. ~ s ~ ~ ~ . ,. .. ~), ,, ., .
~ ~ ~ ~
i -
e w . -
2 c,_
~ . .
i '
t Babcock s. Wilcox -
17 XN-NF-84-115, Rev. 1 Figure 19. Core VIII Loading Diagra: - Nine Arrays Separated by Three Pin Pitches and 34 E uC Pins l
e .
.. =
. . . . . . . o l 'l l , ,!
. . 1.
I r i i
_. . . ,,ii: ;>
0 Fuel Rod Positien E4 C Pin Babcock & Wilcox
, , , _ _ . .. _ --- - - - --------------- -- - -~--~- ~ ~~ . --
t * .
I 18 XN-NF-84-115, Rev. 1 i
Figure 20. Core IX Loading Diagram - Nine Arrays Separated by Four Pin Pitches { ;
t -
I
(
i 4
i 3 ' [ I I I
! . i 1_ l T l 1 I I
. i : I T i i ll I 8!
i: ', il
[
f : 1 L (g
O Fuel Rod Position -u i
i I.
l t
i b
Babcock & Wilcor
____-r
' t I
19 XN-NF-84-115, Rev. 1 I Figure 22. I Cores XI, XIII, XIV, IV, XVII, and XIX - i Nine Unit Assemblies Separated by One Pin Pitch and Metal Isolation Sheets {
1
. I i
~
W ' I l 8 1 r I I W l t ,
3 18 T Fi i ,I i i ! .
i I [ i
- i !1 If . !-
if I i , Tl
. lli ii- vi
- i m
. ;, a
(. t C Fuel Rod Position e !
Threaded Alucine . Rod "
Isolation Sheet I
i l
L i
l
(
i i
i Babcock & Wilcox
_ _ _ ,. - . . - - - .. w=~~~~~'"*~~~~~~~~' ' ~ "
,__ __ _ _ . - . - _ _ - - - - - - - - - - - - - - - - - - - ~ ~ ~ - ~ ~ - ~
20 XN-NF-84-115, Rev. 1 Figure 23.
Cores XII, XVI, ITIII, and XX - Nine Unit Assemblies Separated by Two Pin Pitches and Metal Isolatien Sheets 4,
lll+,l'.' <
1 i
' .; l .
I - 1
, .. i,
',a, l
l C Tuel Rod Positier IT.readed Alutint= Red Iselatien Sheet Babcock & Wilcox
9 e
f 21 XN-NF-84-115, Rev. 1 Figure 24 Core XXI - Nine Unit Asse=blies Separated by Three Pin Pitches and Metal Isolation Sheets (
1 . . , , - m, . .
l I
FI II l l T -f !
i r- ;, ;. .
.' + . ,i
,i cr ,
L ' ' '
.; ; i . .
r i , , 8 ! t i ! I-~
I ! 8 e j i ai
' I ! I 1
, i , W ,
I i
! ii ) lli, l , '
! i
" ' ' ' ! 'r* mi i i i .! ; 1 ; i e, ..' ,;,, ; ;,
I ' ,,'
l ' ' ' ,'
>+
l =, = ,
,i,.
rs ., ,, 1
> - r, ., - ' -
, , i , ,
i ; ,
- - i , ,
, i -
i , , ,
. . . , , 4 1 ., .
i i . ; I . ;g I i I: i I i ; i l; I ' f 6
g , , ;
i , , ,,
i I '
T
' i !
, " 11
. r
! t h
IIy
- 1
] , ,
l.
I f f i :
.i ,
,,_ , , , ' ! ; T' 1 . P, r i ! , I ; 1 r. ps ,
I E ! '! I I I I I r [ y ,
f,I f
.f - 3 3 iij
~
F 6
- l f ! y
' 1 1 i
,. _ r.
_.;i, , ,
e
' i i ,
- 3. : 1- i , , .
! I i . j1 1 ;
i -
1 i . i l ' I i i I I . t '
43 , , ..,.
f i , _
i I .
. 2' . . i ,i; g
L, _
.'. . .d'
'i =- h. ,l , ), j ,
!;'l, k-l 4
O Fuel red Pcsi:ien f
- u Threaded Alur.in.c Red Isolation shee i l.
(
L a
\
t l
Babcock & Wilcox -
XN-NF-84-115, Rev. 1 i
Issue Date: 1/15/85 CRITICALITY SAFETY ANALYSIS DRESDEN 2,3 SPENT FUELS STORAGE P0OL WITH EXXON NUCLEAR COMPANY 9x9 RELOAD FUEL DISTRIB_UTION
~
C0 Brown LD Gerrald TL Krysinski CW Malody JL Maryott JN Morgan (2)
R Nilson JE Pieper HE Williamson Commonwealth Edison /LC O'Malley (51)
Document Control (5)
- - - - - - - - - - - - . _ _ _ _ _ - . _ _ _ . _ _ _ . _ _ ___ _____ , , _ , _ _ , _ _ _ , , _ _ _ _ _ _ _ _ _ _ , _ _ _ _