ML20214W069
| ML20214W069 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/04/1987 |
| From: | Capstick R VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Rooney V NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation |
| References | |
| FVY-87-63, NUDOCS 8706150070 | |
| Download: ML20214W069 (9) | |
Text
$
VERMONT YANKEE NUCLEAR POWER CORPORATION RD 5. Box 169, Ferry Road, Brattleboro, VT 05301 y,go ENGINEERING OFFICE y
N 1671 WORCESTER ROAD v
FRAMINGHAM, M ASSACHUSETTS 01701 TELEPHONE 617-412-6100 June, 4 1987 FVY 87-63 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attention:
Office of Nuclear Reactor Regulation Mr. V. L. Rooney, Senior Project Manager Project Directorate No. I-3 Division of Reactor Projects - I/II
References:
(a) License No. DPR-28 (Docket No. 50-271)
(b)
R. T. Fernandez and H. C. da Silva, Vermont Yankee BWR Loss-of-Coolant Accident Licensing Analysis Method, YAEC-1547, YAEC, Framingham, Massachusetts, June 1986 (Docket No. 50-271).
(c) Letter, V. L. Rooney (NRC) to VYNPC, " July 29, 1986 Meeting with Vermont Yankee Nuclear Power Corporation to Discuss Review of the RELAP5YA Code," NVY 86-196, dated September 10, 1986 (Docket No. 50-271)
(d) Memo, R. T. Fernandez to S. P. Schultz, B. C. Slifer, R. W. Capstick, "Telecon from NRC and EG&G on Review of Vermont Yankee LOCA Licensing Analysis Method,"
LOCA 87-84, dated May 27, 1984 (e)
L. H. Steves et al., HUXY: A Generalized Multirod Heatup Code with 10CFR50, Appendix K Heatup Option: User's Manual, XN-CC-33(A), Revision 1 (Revision of XN-73-34, Revision 2), Exxon Nuclear Company, Inc., dated November 14, 1975 (f)
L. H. Steves, S. F. Gaines, and J. D. Kahn, HUXY: A Generalized Multirod Heatup Code, XN-73-34, Revision 2, Exxon Nuclear Company, October 1974 (g) Letter, W. ?. Johnson (YAEC) to R. A. Purple (NRC),
" Core XII 9.efueling," WYR 75-74, YAEC, dated July 14, 1975 (h) Yankee Nuclear Power Station Core XII Performance Analysis, (No Report Number), YAEC, dated July 9, 1975 (i) Letter, D. E. Vandenburg (YAEC) to USNRC, " Core XII LOCA Analysis," WYR 75-116, YAEC, dated October 10, 1975 (j) Letter with Enclosures, R. A. Purple (USNRC) to YAEC, dated December 4, 1975 (Docket 50-29) 8706150070 G70604 b\\
PDR ADOCK 05000271 O
p PM
United States Nuclear Regulatory Commission June 4, 1987 Attention:
Mr. V. L. Rooney Page 2
Subject:
HUXY Computer Code Information._for the Vermont Yankee BWR LOCA Licensing Analysis Method s s,
)
Dear Sir:
During recent discussions associated with the NRC staff review of the Vermont Yankee BWR LOCA Licensing Analysis Method (References (b), (c),
and (d)), additional information was requested concerning the HUXY code in the following areas:
1.
Yankee Atomic Electric Company's (YAEC's) use of the HUXY code in the Vermont Yankee BWR LOCA licensing analysis method; 2.
Brief summary of the HUXY code development history and NRC/NRR review for LOCA licensing analyses; and 3.
YAEC's use of the HUXY code in PWR LOCA licensing analyses for the Yankee Nuclear Power Station.
Accordingly, Vermont Yankee herein provides responses to the requested information.
1.
The HUXY code is only used to calculate individual fuel rod and chanac1 wall radiation view factors in the Vermont Yankee BWR LOCA licensing analysis method. This calculation corresponds to Step 1 in the description given on Page 55 of Reference (b). This step yields the planar view factors, F(I,J), where I represents the emitting surface (I = 1 to 11) and J represents the receiving surface (J = 1 to 11). The 11 surfaces are identified in Figure 3.1-2 of Reference (b). Surfaces identified as 1 through 10 represent fuel rods, and Surface 11 represents the inside channel wall. Enclosure 1 contains a copy of input and output data for a HUXY case identical to that used for obtaining the planar view factors for the Vermont Yankee LOCA sample problems. These values are subsequently used to obtain the Vermont Yankee hot channel view factors described in Step 2 on Page 55 of Reference (b).
2.
The HUXY code, documented in Reference (e), was developed by Exxon Nuclear Company from the M0XY code. The following sections from Reference (e) contain relevant information requested by the NRC/NRR staff:
l a.
Section 1 summarizes the HUXY development history.
l b.
Section 2.1 summarizes the original M0XY code developed by Idaho Nuclear under AEC sponsorship.
c.
Section 2.3 describes the HUXY method for calculating the radiation view factors for a fuel bundle.
d.
Section 4 describes the HUXY input requirements.
O United States Nuclear Regulatory Commission June 4, 1987 Attention:
Mr. V. L. Rooney Page 3 e.
Appendix D contains the NRC/NRR Safety Evaluation Report for the Exxon Nuclear Company's ECCS nonjet pump BWR fuel heatup model. This report includes a review and approval of the HUXY code as part of this Exxon model.
YAEC obtained the HUXY code (Reference (f)) from the Exxon Nuclear Company in March 1975. Please note that Reference (e) is a revision of Reference (f) that includes the NRC/NRR SER. YAEC has made nine code modifications to convert this code from the Exxon Cyber Computer System to our Cyber Computer System and from Fortran 4 to Fortran 5.
These modifications and their verification and testing have been carried out under YAEC's software control procedures. The modifications do not change the basic physical models.
3.
YAEC performed its first LOCA-ECCS analysis in 1975 to support the Core XII reload for the Yankee Nuclear Power Station. Reference (g) requested an amendment to the Technical Specifications for the Core XII refueling and transmitted the Core XII Performance Analysis Report (Reference (h)). Reference (i) transmitted the appendix, titled " Loss of Coolant Accident Analysis for Core XII of the Yankee Nuclear Power Station," for Reference (h). This appendix described the YAEC LOCA-ECCS licensing analysis method and results for the Yankee plant. Page 65 of this appendix described how YAEC uses chi.
HUXY code as a check on the Exxon Nuclear Company's ENC-WREM hot rod radiation model to ensure the latter yields conservative results.
Figures 14 and 15 show schematic diagrams of the HUXY and ENC-WREM radiation models. Figure 16 shows a comparison of the HUXY and ENC-WREM (T00DEE 2-EM) results for the hot rod.
Reference (j) transmitted the NRC's Safety Evaluation for the Core XII Core Performance Analysis Report.
We trust that this submittal completes all the information needs associated with your review of the Vermont Yankee BWR LOCA Licensing Analysis Method. Should you have any questions or require additional information concerning this matter, please contact this office.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION Y
ff &
R. W. Capstick Licensing Engineer RWC/dib Enclosure
s ENCLOSURE 1 HUXY Input / Output Listing of Radiation 9-View Factor Calculation for Vermont Yankee LOCA Sample Problems i
n.
.m,
.,ac.
VM PREPARED IT/MICHEtt[D SY _hj JAC-427 PAGE AUG 7. 1966 CALCULAT!DN OF IA0!ATION VIEW FACTORS UTILIIING THE NuxY ConPUTER CODE b-
^<u
+ ALL ""
g3p+xexgjpt
-f f
N 4 6.lJs2ih,VL l&
I 1
l i
YANKEE ATOMIC ELECTRIC COMPANY ses.esansassanes.asessensenessasseessanssessasse.ssassess as SOFTWARE CONTROL LIBRARY en sesessenessassessnessisesessenessassessnessassessessenese i
as A8SDLUTE NAME HXYAV10 sa
(
sa HXYAV10 ATTACHED AS HUXY as se VERSION /M00 LEVEL 1/0 se s8 DESCt!PTION PROGRAN HUXT sa 1/M/96 8e as INSTALLED DATE
+
en WE-108 LEVEL 2
as as CODE COGNIZANT IMO: R. HARVEy se se TODAY'S DATE 0,8/06/96 es en TIME OF RUN 16.06.40 as sensassassssssssssssssssssssssssssssssenessassenesseneses
+
seassasassentassenestantissessassenessassessenessessansat v
1
'Y y,
,e,
PREPARED B7/M CHECrE0 af [
427 PAGE AUG
- 7. 1966 CALCULATION OF RADIATION VIEW FACTORS UTILIZING THE HUXY COMPUTER CODE sessassessasasssstetsseestnessenes e
e L
e s
YANKEE ATOMIC e 4
a a
PROGRAM MJXY9 s
e 8
VERSION AUG754 e
a a
a e
itstastasiltittttittstaBattlentita
,d h CALCULATION NUMBER V)f&,427 PREPARED SY
_[, j d_ _...,. _ A CALCULATION DATE B6/08/06 CHECKED SY
&)p THE FOLLOWING IS A CARD IMAGE LISTING CF THE INPUT CARD 0
1 2
3 4
5 6
7 8
NUMBER 12345678901234567890123456789012345678901234567890123456789012345678901234567890 1
VY HOT-CHANNEL RADIATION VIEW FACTOR CALCULATION a
2 11 8
1 1 15 0
0 2
2 0 10 3
3 0
1 1
0 1
1 0
0 0
0 0
4 0.0 0.01 70 0 0 100 5
0.1 100.0 0.10 100.0 7
4.910464 4.000000 18.000000 1.000000 1.000000 1.000000 8
1.000000 1.000000 1.000000 1.000000 1.000000 1.000090 1.000000 1 000000 9
1.000007 1.000000 10 023030 0.0 0550977 0.0001 0530985 6.48 0518555 11.43 II 0507979 16.48 0498781 21.48 0490619 26.48
.0483250 31.48 12 0476502 36.48 0470246 41.48 0464389 46.48 0458864 51.48
(
13 0453619 56.48 0448615 61.48 0443823 66.48 14 15 1000.0 1000.0 1000.0 1000.0 1000.0 1000.0 1000.0 1000.0 16 1000.0 1000.0 1000.0 17 0.64000 5.2780 0.080 0.1 1.0 0.0000324 1.5 0.0 18 1
1 1
1 1
1 1
1 1
1 19 3
20 1
1 3
21 2050000 004500 032 22 1000.0 1000.0 1000.0 1000.0 1000.0 1000.0 1000-0 1000.0 23 1000.0 1000.0 CARD 0
1 2
3 4
5 6
7 8
NUM9ER 12345678901234567890123456789012345678901234567890123456789012345678901234567890 24 000449 000449 000449 000449 000449 000449 000449 000449 25 000449 - 000449 26 1.0 27 2200.0 28 2200.0 29 1
1 1
1 1
1 1
g 3
g y
30 0.0 0.0 0.0 1000.0 31 255.0 0.0 255.0 1000.0 32 425.59 425.59 425.59 425 59 425 59 425.59 425.59 1232.92 33 1216.57 1249 14 34 1.0 1.0 5
O) NA 7hA W k.a*e4 % fe eM % 42$- 6,'<.u) fa d er.,. L., nJy Al-p A M. 4 p % d u d e t y,rA = A w ~ e n n yy 4. ~ cy s m y -
& / Wi% " 4 N % /*// Q (E M of 1 @,) W.
PfEPARED tY [CHECREDBT[.
427 PAGE AUG 7, 1986 CALCULATION OF RADIATION VIEW FACTORS UTILIZING THE HUIT CDMPUTER CODE
=
VY MOT-CHAnEL SADIATION VIEW FACTCR CALCULATION 8
HUXY,M00008:LHS 86/08/06 16.06 44.
')
1 DEFAULT CPTIONS EXERCISED CN PRECEDING INPUT ADJUSTED DATA LISTING 6
Y CARD 1 - tun TITLE VY WOT-CHANNEL RADIATION VIEW FACTCt CALCULATION e
0
+ CARD 2.1 - AttAf SIZES N NPOS NDTA NOPF M NAX NGC L LL NED NAFP 11 8
1 1 15 0
0 2
2 0
0 4 CARD 2.2 - SWITCH SETTINGS NSYM ICON IMut IMWil IEM8t 18LN ITDG NPRT NGN NRM N6F ICAN 3
0 1
1 0
1 1
0 0
0 0
0 0
CARD 3 1 - EVENT TIMES (SEC)
TMINTL TRAD TSPRAY TIMLMT 0000 01 70.00
.10 0
CARDS 3.2 - TIME INCREMENT (SEC) VS CHANGE TIME (SEC) NOTA PA!!S DT TIME DT TIME DT TIME DT TIME 10 100.00 0
CARDS 3.3 - OUTPUT TIME INTERVAL (SEC) VS CHANGE TIME (SEC), NGPF PAIRS OTOUT TIME DTOUT TIME DTOUT TIME DTOUT TIME 10 100.00 0
CARD 4.1 - POWER LEVEL PARAMETERS POWEt(MWT)
BNDLES L6H(IN) GAMMAS RPF APF 4.91 4.
18.00 1.0000 1.0000 1.0000 0
CARDS 4.2 - LOCAL POWER DISTRIBUTION, (N-1) VALUES
-4 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000 10M(
1.0000 1.0000 1.0000 f
0 CARDS 4.3 - NCRMALIZED POWER VS TIME (SEC). M POINTS 2
POWEt TIME POWER TIME POWEt TIME POWER TIME 0230 00 0551 00 0531 6.49 0519 11.48 0508 16.48 0499 21.49 0491 26.48 04B3 31.48 0477 36.48 0470 41.48 0464 46.48 0459 51.48 0654 56.48 0449 61.4B 0444 66.4S 0
CARD 5.1 - QUENCH PARAMETERS FRDOWN HF(RODS)
0 1.000 0.
" O CARDS 5.2 - GUENCH TIMES (SEC). N VALUES (ZERD = QUENCH CALCULATED INTERNALLY) 1000.0 1000.0 1000.0 1000.0 1000.0 1000 0 1000.0 1000.0 1000.0 1000.0 1000.0 0
4 CARD 6 - MISCELLANEDUS PARAMETERS (INCHES,F)
ROD PITCH CAN WIDTH, THICKNESS TEP XMWR CXTC ALPHA OXSTRN 6400 5.2780 0800 1000 1.0000 0000324 1.500 0000 0
t CARDS 7.1 - 200 TYPE ASSIGNMENTS, (N-1) VALUES 1
1 1
1 1
1 l'
1 1
1 0
CARD 7.2 - R00 TYPE INDICES (1=ZR 200, 2=2R TUIE, 3=2R CLAD t.RANIA, 4=ZE CLAD It 800, 11=SS 800,12=SS TUBE.13=SS CLAD URAh!A,14=SS CLAD 22 fr3), 1 VALUES I
O f CARDS 7.3 - ROD TYPE NUMBER OF RADIAL N0 DES, 1 CARDS REG 1 REG 2 REG 3 1
1 3
0
_g CARDS 7.4 - 200 TYPE IEGION RADIAL SIZES (INCHES), 1 CARDS RE61 REG 2 RE63 20500 00450
.03200 0
CARDS 7.7 - GAP COEFFICIENTS (ITU/NR-FT2-F), (N-1) VALUES 1000.0 1000.0 1000.0 1000.0 1CH.0 1000.0 10H.0 1000 0 1000.0 10H.0
(
0
.( CARDS 7.8 - INITIAL HOT SAP (IN.), (N-1) VALUES 00045 00045 00045 00045 00045 00045 00045 00045 00045 00045 0
CARDS 7.9 - R00 TYPE FUEL FRACTIONAL THEDIETICAL DENSITIES, 1 VALUES 1.00000 0
CARDS 7.10 - ROD TYPE FAllutE TEMPERATURE, 1 WLUES (DE6 F) 2200.00 0
CARDS 7.11 - 200 TYPE SALL00NING TEMPERATUIE, 1 VALUES (DEG F) 2200.H 0
CARDS 8.1 - HEAT TRANSFEt SROUP ASSIGNMENT 3, N VALUES 1
1 1
1 1
1 1
1 1
1 1
0 CARDS B 2 - HEAT TRANSFER COEFFICIENT (ITU/HR-FT2-F) VS TIME (SEC).1 SETS DF L POINTS EACH HTC TIME HTC TIME HTC TIME HTC TIME GROUP 1 C
00
.00 00, 1000.00 0
CsWS 9.1 - FLUID TEMPERATutE (F) V3 TIME (SEC), LL POINTS TEMP TIME TEMP TIME TEMP TIME TEMP TIME 255.00 00 255.00 1000.H 0
CAfDS 9.2 - INITIAL CLAD SURFACE TEMPERATURE. (1-1) VALUES 425.59 425.59 425.51 425.59 425.59 425.59 425.59 1232.12 1236.57 1249.94 y&
WA Y
= ($$L &s* 5 h W) a u.
PREPA7ED l'/MCHittED B7 [.O 427 PCGE AUG 7, 1986 CALCULATION OF RADIATION VIEW FACTORS UTILI8ING VHE HUXY COMPUTER CODE Vf NOT-CHAMEL RADIATION VIEW FACTOR CALCULATION 8
HUXY, MOD 00StLHS 86/08/06 16.06.44.
3
'NPUT DATA LISTING
( -O f CARD 1 - RUN TITLE VY HOT-CHANNEL RADIATION VIEW FACTCt CALCULATION 0
W CARD 2.1 - ARRAY SIZES N NPOS NDTA NOPF M NAX NGC L LL NFO NAFP 11 8
1 1 15 0
0 2
2 0 10 0
V CARD 2.2 - SWITCH SETTINGS NSYM ICON IMWt IMWel IEM82 ISLN ITDG N'RT NON NIM NSF ICAN 3
0 1
1 0
1 1
0 0
0 0
0 0
CARD 3.1 - EVENT TIMES (SEC)
TMINTL TRAD TSPEAY TIMLMT 0000 01 70.00
.10 0
CAfDS 3.2 - TIME INCtEENT (SEC) VS CHANGE TIME (SEC), NDTA PAIRS DT TIME DT TIME DT TIME DT TIME
.10 100 00 0
CARDS 3 3 - OUTPUT TIME INTERVAL (SEC) VS CHANGE TIME (SEC), NOPF PAlts DTOUT TIME DIOUT TIME DTOUT TIME DTOUT TIME
.10 100.00 0
CARD 4.1 - POWER LEVEL PARAMETERS POWEt(MWT)
BNDLES LGH(IN) GAMMAS RPF APF 4.91 4,
18.00 1.0000 1.0000 1.0000 0
CARDS 4.2 - LOCAL POWER DISTRIBUTION, (N-1) VALUES 1.0000 1.0000 1.0000 1.0000 1 0000 1.0000 1.0000 1.0000 1.0000 1.0000 0
CARDS 4 1 - NORMALIZED POWER US TIME (SEC), M POINTS POWER TIME POWER TIME POWER TIME POWER TIME 0230 00 0551 00
.0531 6.48 0519 11.4B 0508 16.4B 0499 21.48 0491 26 48 0483 31.48 0477 36 49 0470 41.48 0464 46.48 0459 51.48 0454 56.4B
.0449 61.48
~.0444 66.49 0
CARD 5.1 - GUENCH PARAMETERS FIDOWN HF(2003)
.000 0
0 000 0
O CARDS 5.2 - 00ENCH TIMES (SEC), N VALUES (ZE20 = GUENCH CALCULATED INTERNALLY) 1000.0 1000.0 1000.0 1000.0 1000.0 1000.0 1000.0 1000.0 1000.0 1000.0 1000.0 0
$ CARD 6 - MISCELLANEDUS PARAMETERS (INCHES.F)
ROC PITCH CAN WIDTH, THICKNESS. TEP XMWt CXTK ALPHA OXSTEN 6400 5.27J0
.0000
.1000 1.0000 0000324 1.500 0000 0
iE CARDS 7.1 - ROD iTPE ASSIGNMENTS, (N-D VALUES 1
1 1
1 1
1 1
1 1
1 0
CARD 7 2 - 200 TYPE INDIMS (1=ZR 200, 2=ZR TutE, 3:ZR CLAD URANIA, 4:28 CLAD It ROD, 11=SS E00. 12*SS TUDE, 13=SS CLAD USANIA, 14=SS CLAD Zt 200), 1 VALUES 3
0
'd CARDS 7.3 - t00 TYPE NUMBER OF RADIAL NODES, 1 CARDS REG 1 REG 2 REG 3 1
1 3
0 it CARDS 7.4 - 200 TYPE REGION RADIAL SIZES (INCHES), 1 CARDS REG 1 REG 2 REG 3 20500 00450 03200 0
CARDS 7.7 - GAP COEFFICIENTS (BTU /HR-FT2-F), (N-1) VALUES 1000.0 1000.0 1000.0 1000.0 1000.0
'1000.0 1000.0 1000.0 1000.0 1000.0 o
$ CARDS 7.8 - INITIAL HOT GAP (IN.), (N-1) VALUES 00045 00045 00045 00045
.00045 00045 00045 00045 00045 00045 0
CARDS 7.9 - ROD TYPE FUEL FRACTIONAL THEORETICAL DENSITIES, 1 VALUES 1.00000 0
CARDS 7.10 - R00 TYPE FAILUBE TEMPERATURE, 1 VALUCS (DEG F) 2200.00 0
CARDS 7.11 - 800 TYPE BALLOONING TEMPERATURE, 1 VALUES (DEG F) 2200 00 0
CARDS 8.1 - HEAT TRANSFER Gt0UP ASSIGNMENTS, N VALUES 1
1 1
1 1
1 1
1 1
1 1
0 CARDS 8 2 - HEAT TRANSFER C0 EFFICIENT (BTU /Ht-FT2-F) US TIME (SEC),1 SETS OF L POINTS EACH HTC TIME HTC TIME HTC TIME HTC TIME 6t0UP 1 00 00 00 1000.00 0
CARDS 9.1 - FLUID TEMPERATURE (F) VS TIME (SEC), LL POINTS C
TEMP TIME TEMP TIME TEMP TIME TEMP TIME 255.00 00 255.00 1000.00 0
CARDS 9 INITIAL CLAD SURFACE TEMPERATutE (N-D VALUES 425.51 425 59 425.59 425.59 425 59 425.59 425.59 1232.92 1236.57 1249.94 NM M a n yta cudu!# V, e&ilu SWWg/4//de/o
+
(+)
MS &
s &,1,rt w g. 1 % o M e u d a - Q ow. wh,ho /=w 4 ep[< h.t.
.m a;
n.
ICattu p 81 h I
-42/ PA;E ntrAztu v g
AUG 7, 1986 CALCULATION 0F RADIATION VIEW FACT 0t$
Uill!!!NG THE HUXY E0MPUTER CODE INVERSE RA0!ATION M4ftlX GENERATED F08 OCTANT SYMMEf tf IN 8X 8 BUNDLE Af 00 SECONDS.
O PITCH CANSID 6400 5.2780 0
B00 OUTER O!AMETERS, N-1 VALUES
.4830
.4830
.4830
.4830
.4830
.4830
.4830
.4830
.4830
.4930 0
R00 AND CANISTER EMISSIVITIES, N VALLTS 6700 6700 6700 6700 6700 6700 6700 6700 6700 6700 0000 0
R00 NUMBEt MAP -
0 11 11 11 11 11 11 11 11 11 11 0
11 1 2 3 4 4 3 2 1 11 0
11 2 5 6 7 7 6 5 2 11 0
11 3 6 8 9 9 8 6 3 11 0
11 4 7 9 10 10 9 7 4 11 0
11 4 7 9 10 to 9 7 4 11 0
11 3 6 8 9 9 8 6 3 11 0
11 2 5 6 7 7 6 5 2 11 Ill 1 2 3 4 4 3 2 1 11 0
0 11 11 11 11 11 11 11 11 11 11 0 VIEW FACTOR MATRIX -
F( 1.J), Ja1.11 -
0-254312 0
O.
. C57631 E41. 314579E41. 473942E-020 0
O.
623728 Ft 2,J), Ja1.11 -
.127156 857631E-01.142885 262222E42.127156 857631E-01.183512E-01.157290E-01 262222E-020 391953 F( 3,J), J=1,11 -
0.
.142885 0.
.127156 857631E-01.145287 103894 0
.157290E-01 240232E-02 376884 F ( 4,J), J=1,11 -
0 254646E-02 127156 127156 182754E-01.101492 212919
.157290E41.182754E-01.254666E-02 373905 Fi 5,J), J=1,11 -
(
85763tE-01.2543f2 171526 370811E-010 254312 0
857631E-01.370011E-010 741623E-01 F( 6,J), Js t,11 -
157290E-01.857631E-01.145460
.101492
.127156 857631E41.145460
.129731 101492
.183045E-01
.436487E-01 F( 7.J), J=1,11 -
281160E-02.185406E-01.104304 212919 0
1456 %
.127156
.101492 231459
.185406E-01 370811E-01 F t 8,J), J81,11 -
0 314579E-010 314579E-01.85763tt-01.259255 202984 0
259255
.117221
.126058E-01 F( 9,J), Je t,11 -
0 263073E42 157290E-01.183597E-01.183597E-01.101492 231279
.129737 247000 228648 670837E-02 F ( 10,J), Je t,11 -
0.
O.
562319E-02 562319E420 370811E41.370811E-01.117221
.457296 340075 0
F(11 J1, J=1,11 -
.179318 225368 216703 214993 213212E-01.250974E41 213212E-01 362409E-02.385722E-020 884007E-01 M
i e
p., u a m
. s + + w w p w pz~ <p us-tL 6a - 4 sa w f w
~.
i
.g
- y f,
+
s
- g.
,