ML20210R007
| ML20210R007 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 05/01/1997 |
| From: | Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Quay T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19317C685 | List: |
| References | |
| AW-97-1105, NUDOCS 9709020245 | |
| Download: ML20210R007 (30) | |
Text
_.-
D J
_, Mi@ic Corporation
. Energy Systems gg,np,,,,,,,,,33233.n333 ouse Electr AW 971105 May 1,1997
' Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 f-ATTENTION:
T.R. QUAY APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
SUBJECT:
CLOSURE OF LEAK-BEFORE-BREAK OPEN ITEMS
Dear Mr. Quay:
The application for withholding is submitted by Westinghouse Electric Corporation (* Westinghouse")
4 pursuant to the provisions of paragraph (b)(1) of Section 2.790 of the Commission's regulations. It contains commercial strategic information proprietary to Westinghouse and customarily held in confidence, The proprietary material for which withholding is being requested is identified in the proprietary l
version of the subject report. In conformance with 10CFR Section 2.790, Affidavit AW-97 !!05 accompanies this application for withholding setting forth the basis on which the identified proprietary information may be withheld from public disclosure.
Accordingly, it is respectfully requested that the subject information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the Commission's regulations.
Correspondence with respect to this application for withholding or the accomp nying affidavit should reference AW-97-1105 and should be addressed to the undersigned.
f.
Very truly yours, A. !
Brian A. McIntyre, anager
- Advanced Plant Safety and Licensing
/jwh cc:
Kevin Bohrer NRC 12HS -
one.
9709020245 970501 PDR ADOCK 05200003 A
pop
m=
._..m._.
AW 971105 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
s:
COUNTY OF ALLEGHENY:
Before me, the undersigned authority, personally appeared Brian A. McIntyre, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Amdavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that the averments of fact set forth in this Amdavit are tme and correct to the best of his knowledge,information, and belief:
L YJ$
>3
/
Brian A. McIntyre, Manager Advanced Plant Safety and Licensing Sworn to and subscribed befo me this b
-. day i
$g of 1997 s
~
w g, Janet A Schwab, Hotary Publ!c Momoeym,e Boro, Megneny County My Commisson Expres May 22,2000 Womtm, rii=#wna Assouston of hotanei
~
Notary Public Sales
o.
AWo9701105 (1)
I am Manager, Advanced Plant Safety And Licensing,in the Advanced Technology Business Area, of the Westinghouse Electric Corporation and as such,I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing i.nd rulemaking proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Energy Systems Business Unit.
(2)
I am making this Amdavit in conformance with the provisions of 10CFR Section 2.790 of the 2
Ccmmission's regulations and in conjunction with the Westinghouse application for withholding accompanying this Affidavit.
(3)
I have personal knowledge of the criteria and procedures utilized by the Westinghouse Energy Systems Business Unit in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4)
Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
(i)
The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.
(ii)
The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types ofinformation in confidence. The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.
Under that system, information is held in confidence ifit falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:
onem
AW.971105 -
(a) na information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) wbwe prevention of !ts we by any of Wwtinghouu's competitors without license from Westinghoun constitutes a competitive economic advetage ovw othw companies.
(b)
It consists of supporting data, including test data, relative to a process (or compos,ent, structure, tool, method, etc.), the application of which data suures a competitive economic advantage, e.g., by optimization or improved marketability.
(c)-
las use by a competitor would reduce his expenditure of twources or improve his competitivs position in the daign, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d)
It reveals cost or price information, production capacities, budget levels, er commweial strategies of Wutinghouse,its customers or suppliers.
i (e)
It reveals aspects of past, present, or future West "'aouse or customer funded i
h smercial value to development plans and programs of potent Wutinghone.
W 1
(f)
It contains patentable ideas, for which patent protectior, may be desirable.
There are aound policy reasons behind the Watinghouse system which include the following:
(a)
The use of such information by Watinghouse gives Wutinghouse e competitive advantage over its competitors, it is, thwefore, withhela from disclosure to protwt the Watinghouw wapetitive position.
(b)
It is information which is marketable in many ways. The extent to which such information is available to competitors diminishn the Westinghone ability to sell products and services involving the use of the information.
h m.....-
.. _ _.,,u _..e.
,. _.. _ -. - - _ -. _ _. - -, ~ _.. -....,.. _.. -.. - _. -
l AW.971105 (c)
Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense, (d)
Each component of proprietary infonnation pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puule, thereby depriving r
Westinghouse of a competitive advantage.
(e)
Unrestricted disclosure would jeopardire the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.
(f)
The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.
(iii)
The information is being trusmitted to the Commission in confidence and, under the provisions of 10CFR Section 2.790,it is to be received in conndence by the Commission.
(iv)
The information sought to be protected is not available in public sources or available infonnation has not been previously employed in the same original manner or method to the best of our knowledge and belief.
(v)
Enclosed is Letter NSD NRC.97 5103, May 1,1997 being transmitted by Westinghouse Electric Corporation M) letter and Application for Withholding Proprietary Information from Public Disclosure, Brian A. McIntyre (yL), to Mr. T. R. Quay, Ofnce of NRR. The proprietary information as submitted for use by Westinghoui,e Electric Corporation is in response to questions concerning the AP600 plant and the associated design certification application and is expected to be applicable in other licensee submittals in response to certain NRC requirements for justincation oflicensing advanced nuclear power plant designs.
%is information is part of that which will enable Westinghouse to:
anem
\\
.. : w -- -
~
AW.97110$
l (a)
Demonstrate the dwign and safety of the AP600 Passive Safety Systems.
(b)
Establish applicable verification testing methods.
l (c)
Dwign Advancod Nuclear Poww Plants that meet NRC requirements.
(d)
Establish nochnical and licensing approaches for the AP600 that will ultimately
)
ruult in a certified duisa.
(e)
Assist customus in obtaining NRC hpproval for future plants.
Furthw this information has substantial commercial value as follows:
(a)
Westinghouse plans to sell the use of similar information to its customers for purposes of meeting NRC requirements for advanced plant licenses.
b (b)
Westinghouse can sell support and defense of the technology to its customers in the licensing process.
Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar advanced nuclear power designs and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would enable othws to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the infonnation.
h e
.,--r-
, -,N y
,n s.
v.,
--m.wn~,-
.s
AW.971105 The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Wutinghouse effort and the expenditure of a considerable sum of money.
In order for oorspetitors of Wutinghouw to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the twiultite talent and experience, would have to be expended for developing analytical methods and receiving NRC approval for those methods.
Further the deponent sayeth not.
e
4 4
e e
a ENCLOSURE 2 NSD.NRC.97.$ 103 e
A 4
e e
e e
e e
e t
4 9
9 0
4 0114H t
. to NYC NSD 99 5103 Summary of Screening Criteria foe Water Hammer Potentialin AP600 LBB Lines De piping in the AP600 that is evaluated for leak before break characteristics includes stainless steel safety related lines of six inch diameter and larger inside containment. To be included in the leak.
before break category the lines must not have a significant potential for a water hammer. To provide a means to gauge the potential for water bammer a screening criteria has been developed for the NRC staff. The criteria includes geometric characteristics such as slope and length of horizontal pipe and thermal. hydraulic cnteria such as the potential for stenin voids and the pressure at time of interest.
The enteria is documented in Section 5.29 of NURE0/CR 6519. " Screening Reactor Steam / Water Piping Systems for Water Hammer," November,1996.
Westinghouse has reviewed the LBB piping using the screening criteria. All of the LBB lines have been screened out of consideration by one or more of the criteria ne lines ac listed below with the criterion by which it is screened out. In addition to the lines noted below, the steam line inside containment is an LBB line. De steam line does not have a source of cold water and is not susceptible to water hammer.
Line Criteria ADS Stage 2 and 3 and Pressurizer Safety nermal hydraulic ADS Stage 4 (East)
Small llD Pressuriter Surge line Slope > 0.5 inch /ft.
Direct Vessel injection A and B Slope > 0.5 inch /ft.
Normal residual heat removal to IRWST T/H No steam Normal residusi heat removal from RCS hot les T/H Insufficient subcooling PRHR supply and ADS Stage 4 (West)
Small L/D PRHR retum T/ H No steam Balance line from RCS cold leg to CMT A Small l>D Balance line from RCS cold leg to CMT B Small L/D Primary loop piping Small IJD e
e e
E2 I l
i
-: = =
MEETING WITH 4
THE UNITED STATES NUCLEAR REGULATORY COMMISSION ON "AP600 LEAK-BEFORE-BREAK AND RELATED ISSUES" 4
PITTSSURGH
)
APR:L 16-18,1997 i.
i
<Wl W
t 4
t 1
i i
i
~~ SENSITIVITY STUDY "EFFECT OF RESTRAINT OF PRESSURE INDUCED BENDING ON LBB" I
1 i
1
,+
b e
9 4
e e
8:
I i
6" Diameter, Schedule 160 pipe Material : Stainless Steel SA312 Type 316LN
~
THROUGH WALL l-CRACK LENGTH
\\
i
=r 3.
/
f i
i M
t i
W 1
i
1 l
~
~
MODEL. DETAILS:
~
NUMBER OF NODES:
~
1708
~
NUMBER OF ELEMENTS:
266
^
NUMBER OF D. O. F.:
4800
~
TYPE OF ELEMENTS:
20-NODE 3D ISOPARAMETRIC BRICK a'
2 i
3 so
- $18 i
k 9
l N 13 g
/
N r
5 o,
12 7
2 ggi f
7d in
=,
I
~
4 g g, l
is 20 FINITE ELEMENT PROGRAM :
ADINA i
~
I l
j
- 6-
-.w.
e a
4 4
t o
\\
N
,l N
\\\\
w.
N,\\\\
.s s s
\\
v w $\\\\
N
( x Ny.,
Q
+
4 i
n e,
. ~,
'O'M**-h.9,
t e
t I
\\
e
.\\
\\
9
'e g,
i j
k.
Nh
\\
g
\\\\
\\'h e
N
\\
' \\\\
4 t
i i
I
-,-.-:.3
=.-e u,
~.4 i e.-
+.r.-5
--%-.e--w-
.x-4
_,.-=m.
da m
m.
2.
4..-
A 4
e 9
g
\\
/
e-
,/
]
.s'
's 4l.
~
/
eq e
6 e
/
e 1'
, l
.~..+.m
= ~ ~
6.
.-~G l>
l O
e O
4 i
, i, i
i a
n\\
\\.
i
\\,
\\
\\
J' 4
t
.\\ t
.\\,
i j
\\
y n
n t
\\.
L i
\\
2 A
\\'/ \\* a
\\" \\/l. '.
~
\\
\\
~
R R
R g
\\*
\\\\
\\,\\
k-
'i k
g C
E k
w k
\\
'. I
\\.
\\
g/.
4 g
1
,1 m=.
i y
\\
\\
t
?
E I
i a
a.
s..w m.
.----=.-...,n s
.-~-n-
4 s
I l
e
\\
\\
s i
\\
\\
\\
\\
\\
\\
\\
\\
'n i I I
I
\\
.\\
\\
\\
3
\\
g t
I,
\\
\\
t.
3
\\,
i
\\
n
\\
E I
M
'i ' I'$
g.i
( v i,i, \\
i ar
\\
~
\\
g
\\
\\
\\
l
/
\\
,\\
\\\\
\\
(
r 1\\
\\,
\\
1
\\
i i.
s-i 1
\\
\\
\\
\\.,!
\\
I I
s I63 a g
~
B~
~
a I
~
i
\\
\\
k g
i i
~
\\
t I
k e
I I
i'l i
1
wI
. =.+= r.
e MATERIAL TOUGHNESS :
Y Jf(
.in-kips /in 2
y-(dJ/da)aw =
J si k
T
=r 9^>
- clearty, ij (dJ/da), < (dJ/da).
i T,<T.
.6 Therefore the postulated (
linches long crack is stable e
e i
j o
i
_t l'
e j;
_ LOADS :
15 ksi NORMAL STRESS i
37 ksi MAXIMUM STRESS i
RESULIS :
~
,..b
~
_ GPM WAS CALCULATED FROM A CRACK (A) [ LEA)l[ AGE OF LjibCHES LONG.
1 THUS, THE MARGIN OF A FACTOR OF 10 ON LEAKRATES IS MET.
(
l (B) CRACK STABILITY ANALYSIS AS PERFORMED FOR A
{
THROUGH-WALL CRACK [ ]l ES LONG:
l
( > 2 TIMES THE LEAKAGE SIZE CRACK) i THE CRACK WAS SHOWN STABLE AS FOLLOWS :
o ll J, was > J,c
,.. b pl (dJ/da), = g
.ksi l
L f.6 r
h applied (
j ll j
n, u
W l
W L
~
~
q l
))
-(
w.m.w.., :_,
i CONCLUSION :
~
~
1 NRC RECOMMENDED LBB MARG!NS WERE DEMONSTRATED FOR THE 6" STAINLESS STEEL PIPE WITH POSTULATED THROUGH-WALL CRACK INCLUDING THE EFFECT OF RESTRAINT.
?
1 I
i
~
t e
~
p.
~
_,-._w
.a--
. - _ +.
w,_
__...~.. _
4
.2 l
0 I
e ENCLOSURE 3 NSD NRC.97.$103 e
e e
4 4
9 e.
4 4
0 0116H s
l l.
- to NSD.NRC 97 5103 l*
Smaller Diameter Leak.Before. Break Sensitivity Study NUREO/CR 6443 identified a potential effect due to restraint of pressure induced bending on the leak.
before break evaluation for some 4 inch diameter piping. Although the application of leak befo,w break criteria to 4 inch diameter piping has been foregone in AP600 design certification, the NRC staff had a uncertainty about the effect on 6 and 8 inch diameter pipes, in order to resolve this concem a sensitivity analysis was conducted using a representative 6-inch pipe to show that the leak before break margins are maintained.
De study was done on a 6 inch pipe conservatively modeled as being restrained by a conn:ction to a nozzle. De stresses used were 15 ksi normal stress and 37 ksi maximum stress. His combination represents the normal stress calculated for a representative AP600 6 inch line and the maximum suess
- at 15 ksi normal stress from the appropriate bounding analysis curve. Bis combination of stresses was determined by the NRC staff and consultants as the point where effects would be the most significant. De staff agreed that the sensitivity analysis could demonstrate that for tne AP600 the leak before break criteria is not significantly effected by bending restraint and that a successful outcome would resolve the issue, he initial results of the analysis were presented to the staff on April 18,1997 and shoud that the.
recommended margins are maintained. De following summarizes the methods used and the conclusions of the study. This information is provided to document the results of the study.
Analysis Aasumptions Pipe Dimensions: 6' nominal diameter, Schedule 160 Pipe Material: SA312 Type 316LN stainless steel Pipe Geometry:
THROUGH Wall.
CRACK LFNGTH I
b i
t).
i f
M Finite Element Models A number of finite element models were built for analyses. Figures I and 2 are two views of a typical model representative of all models used. Details in the vicinity of the crack tip region are shown in Figures 3 and 4.
De norrie is included in the models to provide the constraints intended for the investigation. The crack is through wall oriented in the circumferential direction of the pipe. De crack is located at a distance equal to one diameter of the pipe from the transition point of the nozzle to pipe. Due to symmetry, the model covers 180 degrees of the pipe circumference.
E31
.- to NSD.NRC 97 5103 Typically, the model contains about 1700 nodes and 260 elements. De element type is 20 node quadratic,isoperametnc. ADINA 3D brick elemen s.
ma==dg Conditions A. Prescribed displacemenu:
De boundary conditions are specified based on the coordinate system used in the finite element mooels, as wmmarized below:
U, = U = U = 0, on the a=0 plane, the model end on the noule side, to simulate fised end condition for,the noule.
y
.U, = 0, ' on the y=0 plane, the symmetric plane.
Whenf U,, U, and U, are di< placements in the x, y..and a directions respectively.
y B. Prescribe'd tractions:
e' The intemal 6"rface of the pipe is wbjected to pressure.
f De model and (pipe sids) is wbjected to bending and memterane stresses. De tractions are applied to the urface elen ents over the pipe end, in the form of tuess. De bending stress is superimposed to the memb.ane stress.
j Loads r
Two different load levels were considered in the analyses. This pair of loads was agreed to by Westinghouse and the NRC staff ar'd consultants, i
i Normal leading condition: intemal pressure p = 2283 psig. Membrane plus bending stress = 15 ksi. These lo=ds were used to determine the leakage crack slee.
Faulted loading condition: intemal prissure p = 2283 psig Membrane plus bending stress =
37ksi. nene loads were used to determine the structural stabili./.
i I
Method of at.al,nes.
incremental elastic plastic finite element analyses using computer pmgram ADINA were performed to i
determine crack opening area and the J. integral values.. De material was assumed to be isotropic hardenable, obeying the von Mises yielding criteria.
he J. values were calculated using the vinual crack extension method (VCE) which is available in i
ADINA.- De VCE method can effectively determine the potential energy penurbation corresponding -
7.-
. to nodal penurbations at the crack tip.- Thus the energy release rates or the J. values are computed.
De track opening displacements were obtained directly fiom the displacement solctions of the finite element calculations. The relative displacements of both sides of the crack planes, after ciack ope.1s, were evaluated to detennine the crack cpenhe, area._ All crack opening evaluations were performed
- under the fised load value of 15 ksi in:luding the intemal pressure of 2283 psig. De conesponding
- leak rate was then determined.
i E3 2 yy*v r-r
- Te< t t-
~f f-r' e
4 y,-
d-
+e*W-,,-e, a%-w---y_w--o-ge,-=v e-.-s,
,,a-,ea-,
wr-
+. mve3.-w-e
.-,s..,,
r sw ir ~-.e w e r
+s-+ew-o
- --e a-A"w+s-
- t) NSD NRC 97 5103 ne 6tructural stability evaluations were performed for the crack as indicated below.
Resuks A through wall crack (
la.b inches long provided a leakage of [
la,b OpM which is greater than 10 times the leak detection capability of 0.5 GPM.
A stability analysis was performed with a through wall crack sim [
la.b inches long which demonstrates a crack slu margin greater than 2.
J,ppi;g
=l Ja.b in kips /in2 (d1/da),pp ;g
=[
. ja b ksi j
T,ppi;g -
=[
la.b Material Toughness, A representative J.R curve was used to establish the material toughness, e 2
Jge=[
)* 8 in kips /in (dj/da) =[
)* 8 ksi T=l
]* 8 Clearly. (dj/da),ppij,4 < (dJ/da)matenal and Tapplied < Tmatsnal. Derefore the postulated crack is stable under the applied maximum stress condition.
Additional Evaluation Some of the input for the initial case were based on conservative estimates of intermediate results to facilitate completion of the analysis during the meeting with the NRC staff. Recognizing that the postulated crack sius in the above results predicted margins greater than the recommended margins, an additional sensitivity study case was performed by varying the postulated crack sins as tollows:
Al Ja.b inch long through wall crack provided a leak rate of about 10 times the leak detection capability.
A stability analysis was performed for a through wall crack two times the leakage crack sia (through wall crack = [
ja,b inches long)
J,ppi;g
=[
ja.b in kips /in2 (dj/da),gi;g
=l lab ksi Tapptwd "l-l Clearly, (dJ/da),ppi;g < (dj/da)matenal and Tappled < Tmaterial or this case. Derefore the f
postulated crack is stable under the applied maximum stress condition. Bis case more closely E3 3
Er. closure 3 to NSD.NRC 97.$103 85 Presents the AP600 conditions for Japplied and ' applied Concluelon The wnsitivity analysis demoristrates that for the application of leak.before break in the APbOO, recommended margins on leak rate and crack site are not adversely effected by restraint of the pressure induced bending on smaller diameter piping. The 6 inch diameter p!pe restrained at a nozzle connection represents a conservative bounding condition of the conditions in the AP600. Based on the agreement with the NRC staff, the issue concerning the uncertainty of the application of leak before.
break to smaller lire suggested in NUREO/CR 6443 has been resolved for AP600.
4 4
e d
4 4
4 8
4 4
E3 4 4
F o
Enclosum 3 to NSD NRC.97.$103 E
- t E
E P
d l
9 4
Y, e.
+
+
0 i
,N r
f s
4 4
4 6
1 h
T b
f h
t I
h s
e 4
e e
r s
e e
v
?
f i
i s-L r
t
(
- q,
- 'n'~
. Figm I E3 5 -
4
m------
i
?
i Enclowre 3 t) NSD>NRC 97 5103 i
1 t
i h
?
k l
t I
t 1
i o
6 e
e
/
/
4
{
/
/
A
/
4 i
l
/
l
~-
1 4
-' ' ' = ' ' ' ' *
)
b A
/
1 t
A f
4
+
i Figure 2 -
E3 6 r
S 4
-:ni<,--y
.,, ~, -,--
-.,N,,-
.+..,
- ~ - -,
e-no.-.--e.-
,,.w--w>.-
,,- ~, -
r,n<o-,,----,v-
+.. ~..... - -, - - +, -. -
e-
_... a. = = -- :- - :
- - - - - ' - - - - - - - - - - - = - -
i
, t) NSD NRC 97 5103 I
f 4
[
i
!i i
Ia 4
y
[p *.
'N 000 s, /.
syf j
",,W
'g
'. h gas /
\\
'N
/
f
\\
/
N
/
s,y
./.
x x
s j
,N)..
/
~
/
\\
./
.sb /se m
/
l
- V
/.
/
n er or i
\\,
[/'..'
/
"/
mi/
y!
'.,/ ^ ',/
,-l,,
/u,'
~
..,l./
,/
/
es
/
e
. h j'/
s
/ es j
l y/.
. / l.,
,/
=
/-
,/ -
?,
/,
m-,- s,y
.i-
/
,\\
e:
Figure 3 E3 7
--r
.-a.,.,...,.,..
e
,,_m.,
3_
. to NSD NRC 97 5103 i
t S
m,
~
s
...e W6
,seio Mt
/.2\\
f
< 84
/
'4#'
,eN
's 8
,nen
'A
'N
/
/
/ N "8
/N
/
/
s
,som N,,,
/, N dit
/.
\\
\\j
/
z /.. ' ' t.. /..
/
/
/
/
n
,/
l**..
/r '
./'w/
,A..
/
/'**/
s
/ /
'.g e
/
/
/ s n' /
l o
A Q
/
/
/
/
/
p to sim
/
,/ ' fee /
w
,/
/ yom/'"
/
,,u
/
y,
/
/\\
/
ist
,- [
, s,,,!',<,/j/
s
/
iin e,.,
7
/
, 948
/
j/ Ny*,,,
l eue /
eenn
/
,i
/
/
/
/
/
/
,/
p no
/
r
/
tim /
/
/
/
/
i,
/
,/
t'=,,;,'
,/
/ li-l j
,/'
4 Figure 4 E3 8
-