ML17254A910

Discusses Encl Results of Analysis of Reactor Vessel Surveillance Capsule T,Supporting 821208 Application for Amend to License DPR-18.Fluence Data & Analysis Presented in WCAP-10086 Verified

ML17254A910
Person / Time
Site:	Ginna
Issue date:	08/08/1984
From:	Kober R ROCHESTER GAS & ELECTRIC CORP.
To:	Paulson W Office of Nuclear Reactor Regulation
References
NUDOCS 8408150108
Download: ML17254A910 (23)

Text

REGULATORY INFORMATION DISTRIBUTION SYS H (RIDS)

ACCESSION NBR'800815(108 DOC DATE! 84/08/08 NOTARIZED: NO DOCKET. 0

~

FACIL:50-240 Robert)Emmet Ginna Nuclea'r Planti Unit li Rochester G 05000240 AUTH'BYNAME AUTHOR AFFILIATION ROBERtRel4e Rochester Gas 5 Electric Carp.

'EC IP, NAME RECIPIENT AFFILIATION PAULSONiWeA ~ Operating Reactors Branch 5.

SUBJECT:

Discusses encl, results of analysis or Reactor Vessel Surveillance Capsule T~supporting 821208 application to License DPR-18.Fluence data 8 analysis presented in for'mend YCAP 10086 verified, DISTRIBUTION CODE: A001S COPIES RECEIVED:LTR ENCL / SIZE:

TITLE: OR Submittal: General Distr ibution NOTES:NRR/DL/SEP 1cy, 05000244 OL+ 09/19/69 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR ORB5 BC 01 7 7 INTERNALS ADH LFMB 0 ELD/HOSP 0 NRR/DE/MTEB 1 NRR/DL DIR 1 NRR/DL/ORAB 1- 0 N HETB 1 NRR/DSI/RAB 1 EG F E 04 l.

RGN1 1 1 EXTERNALS ACRS 6 LPDR 03 NRC PDR 02 1 NSIC 05 NOTES'9 NTIS 1 1

1 1

TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 24

II' o; l C

t

'II IIIIIIIIIg ROGER W. KOBER VICE PRESIDENT III" XWn'P::::

ZZZZZS ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 TELEPHONE 1am< Owl ~

• ELECTRIC & STEAM PRODUCTION AREA CODE Tld 546-2700 August 8, 1984 Director of Nuclear Reactor Regulation Attention: Mr. Walter A. Paulson, Acting Chief Operating Reactors Branch No. 5 U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Reactor Vessel Surveillance Capsule T R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Paulson:

On December 8, 1982 an Application for Amendment to Operating License was submitted to the NRC incorporating the results of the analysis of reactor vessel surveillance capsule T. This analysis was performed by Westinghouse and published as WCAP-10086.

The results of the neutron transport calculations presented in WCAP-10086 were obtained using a statistically based generic 2-loop core power distribution and cross-sections employing a Pl expansion of the scattering matrix. In spite of the good agreement between measurements and calculations at the surveillance capsule locations, both of these assumptions were questioned by the NRC staff in their review of WCAP-10086. In particular, the consideration of plant specific core power distributions and the use of a P expansion of the neutron scattering cross-sections were requested.

In order to address these two issues, neutron transport cal-culations in R II geometry were carried out using the Dl@Idiscrete ordinates code and the SAILOR cross-section library . The SAILOR library is a 47 group, ENDF-BIV based data set produced specifically for light water reactor applications. Anisotropic neutron scattering is treated with a P 3 expansion of the cross-sections.

Two sets of transport calculations were carried out to provide the appropriate data to address the issues at hand. The first, a single computation in the forward mode, utilized the P cross-sections in conjunction with the generic 2-loop power distribution to provide a direct P3/Pl comparison. The second set of calculations consisted of a serxes of seven adjoint analyses relating power distributions within the core to the fast neutron flux at four locations on the pressure vessel as well as at the 8408150108 g QQoP 05000244, 840808'DR ADOCK P PDR

e ROCHESTER GAS AND ELECTRIC CORP. SHEET NO.

DATE August 8 1984 g

Mr. Walter A. Paulson center of each surveillance capsule. These adjoint importance functions were then used along with actual core burnup information to generate plant specific fluence levels on a cycle by cycle basis for the R. E. Ginna reactor. A P3 scattering cross-section expansion was used for all of the adjoint analyses.

The transport methodology, both forward and adjoint, using the SAILOR cross-~potion library has been benchmarked against the ORNL PCA facility as well as against the Westinghouse power reactor surveillance capsule data base. The results of these benchmarking studies will be available in a report to be issued by Westinghouse by the end of 1984. However, as indicated in our letter of October 10, 1983, the benchmarking studies indicate that the use of SAILOR cross-sections and generic design basis power distributions produces flux levels that tend to be conservative by about 7-22%. This conservatism is to be expected since the generic power distributions include a 2o statistical uncertainty based on plant-to-plant and cycle-to-cycle variations in peripheral power. It is unlikely that a single reactor would have a power distribution at the nominal +2o level for a large number of fuel cycles.

When plant specific power distributions are used with the adjoint importance functions, the benchmarking studies show that

.fluence predictions are within +15% of'easured values at sur-veillance capsule locations. Further, these predictions also tend to be in good agreement with the P calculations based on the generic power distribution. That ls, the 2o uncertainty added to the peripheral power tends to offset deficiencies in the P 1 analy-sis relative to the P3 approach.

Results of Anal sis Results of the plant specific fluence evaluations for the R. E. Ginna reactor are 0 summarized jn Tables 1 0 through 7. Data are presented for the 0 < 14.5 , 30 , and 44.5 azimuthal locations at the pressure vessel inner radius in Tables 1 through 4, respectively. Corresponding data applicable to tge center of surveillance capsules positioned at 13 , 23 , and 33 are given in Tables 5 through 7. In all cases, plant specific fast neutron flux and fluence levels for each operating cycle are listed along with predictions using a constant flux level based on P and P

1 cross-sections and the generic design basis core power dis(ri-butions.

In regard to the data contained in Tables 1 through 7, the plant specific core power distributions used for cycles lA through 13 were derived from actual burnup data. The cycle 14 power distribution was taken from the nuclear design data given in WCAP-10505. As with the power distribution data, the full power irradiation times for cycles lA through 13 were obtained from the cycle specific burnup data. The irradiation time for cycle 14 was computed from the design burnup of 8800 MWD/MTU specified in WCAP-10505. Cycle 14 began in Spring 1984.

I ROCHESTER GAS AND ELECTRIC CORP. SHEET NO. 3 DATE August 8, 1984 Mr. Walter A. Paulson Where appropriate, measured fluence values from surveillance capsules V, R, and T have been compared with calculated values.

These analytical/experimental comparisons are shown in Tables 5 and 6. It should be noted that the measured values represent the average fluence derived from all neutron sensors contained in each surveillance capsule. Further, in keeping with the NRC request, the fluence levels are based on spectrum average cross-sections obtained from the SAILOR P3 analysis. Therefore, measured fluence values listed in Tables' and 6 differ slightly (from 1% to 8%)

from the corresponding values given in Table 6-12 of WCAP-10086.

These variations in the experimental values are well within the uncertainty in the measurements themselves.

The following conclusions can be drawn from an examination of Tables 1 through 7.

l. Over the long term the plant specific SAILOR P3 analysis is in excellent agreement with the GAMBIT P analysis.

At the projected end of cycle 14 the P3/Pl luence ratios are as follows:

SAILOR P3/GAMBIT Pl 0

0 vessel 0.98 0 vessel 14.5 1. 01 30 vessel 1.04 44.5 vessel 1.14 13 0 capsule 0.92 23 capsule 0.95 33 0 capsule 0.92

2. For surveillance capsules, V, R, and T the fluence predictions based on plant specific SAILOR P3 analysis are in excellent agreement with dosimetry data.

Analytical/experimental comparisons are as follows:

SAILOR P3/MEASUREMENT Capsule V 0.99 Capsule R 0.95 Capsule T 0.92

3. Analysis using SAILOR P 3 cross-sections and the generic design basis core power distribution produces con-servative results relative to the other two analytical approaches as well as to the surveillance capsule measurements.

ROCHESTER GAS AND ELECTRIC CORP. SHEET NO. 4 D4TE August 8, 1984 Mr.,Walter A. Paulson Based on these conclusions, the fluence data and analysis presented by WCAP-10086 is verified and supports our application of December 8, 1982.

er truly yours,

~ul Roger W. Kober

ROCHESTER GAS AND ELECTRIC CORP. SHEET NO. 5 AUgUst 8 g 1 984 Mr. Walter A. Paulson

References:

Soltesz, R. G., R. K. Disney, J. Jedruch, and S. L. Zeigler, "Nuclear Rocket Shielding Methods, Modification, Updating and Input Data Preparation Volume 5 Two-Dimensional Discrete Ordinates Transport Technique", WANL-PR-(LL)-034, Vol. 5, August 1970.

2. SAILOR RSIC DATA LIBRARY COLLECTION DLC-76, "Coupled, Self-shielded, 47 Neutron, 20 Gamma-ray, P3, Cross-section Library for Light Water Reactors".

3. McElroy, W. N., "LWR Pressure Vessel Surveillance Dosimetry Improvement Program: PCA Experiments and Blind Test",

NUREG/CR-1861, June 1981.

4 ~ Letter J. E. Maier to D. M. Crutchfield, October 10, 1983.

SD-RSA-84/2153 Table 1 FAST NEUTRON E > 1.0 MeV EXPOSURE. AT THE PRESSURE VESSEL INNER RADIUS 'O'ZIMUTHAL ANGLE CUMULATIVE FLUENCE (n/cm2)

Irradiation Cycle Avg.

Cycl e Time Fj,ux Plant Specific Generic, Generic No. (EFPS) (n/cm~-sec) P3 P3 1A 2.09 x 10 3.88 x 10 8.10 x 10 8.26 x 10 1.01 x 10 18 2.38 x 10 4.16 x 10 1.80 1p18 1.77 x 10 2.15 x 10 2 0.71 x 10 4.22 x 10 2.10 x 1018 2,05 x 10 2.50 x 10 3 2.88 x 10 3.62 x 10 3.14 x 10 3.18 x 10 3.88 x 10 2.17 x 10 3.60 x 10 3.93 x 1018 4.04 x 10 4.93 x 10 5 1.84 x 10 4.63 x 10 4.78 x 10 4.77 x 10 5.82 x 10 6 2.42 x 10 3.93 x 10 5.73 x 1018 5.72 x 10 6.98 x 10 7 2.35 x 10 3.74 x 10 6.61 x 1018 6.65 x 10 8.12 x 10 8 2.20 x 10 4.40 x 10 7.58 x 1P18 7.52 x 10 9.18 x 10 9 2,62 x 10 4.13 x 10 8.66 x 1018 8.55 x 10 1.04 x 10 19 10 2.51 x 10 3.97 x 10 9.65 x 1018 9.55 x 10 1.16 x 10 19 11 1.83 x 10 3.86 x 10 1.04 x 10" 1.03 x 10 1.25 x 10 19 12 2.30 x 10 4.53 x 10 1.14 x 10 1.12 x 10 1.37 x 10 13 2.32 x 10 3.11 x 10 1.21 x 10 1.21 x 10 1.48 x 10 1p19 19 14 2.27 x 10 3.05 x 10 1.28 1.30 x 10 1.59 x 10 P

10 2 Notes: 1 9 avg = 3.95 x 10 n/cm -sec.

1p

= 4.82 x 10 n/cm -sec.

'0 n

p1

SD-RSA-84/2153 Table 2 FAST NEUTRON E > 1.0 MeV . EXPOSURE AT THE PRESSURE VESSEL INNER RADIUS - 14.5'ZIMUTHAL ANGLE CUMULATIVE FLUENCE (n/cm2)

Irradiation Cycle Avg.  :- 1 Cycl e Time Fj,ux Plant Specific Generic , Generic No. (EFPS) (n/cm~-sec) P3 P1 P3 1A 2.09 x 10 2.34 x 10 4.89 x 10 4.97 x 10 6.11 x 10, 1B 2.38 x 10 2.48 x 10 1.08 x 10 1.06 x 10 1.31 x 10 2 0.71 x 10 2.57 x 10 1.26 x 1018 1.23 x 10 1.52 x 10 3 2.88 x 10 2.22 x 10 1.90 x 10 1.92 x 10 2.37 x 10 4 2.17 x 10 2.38 x 10 2.42 x 10 2.44 x 10 3.01 x 10 5 1.84 x 10 2.81 x 10 2.94 x 10 2.87 x 10 3.55 x 10 6 2.42 x 10 2.47 x 10 3.53 x 10 3.45 x 10 4.27 x 10 7 2.35 x 10 2.48 x 10 4.12 x 10 4 01 x 10 4.96 x 10 8 2.20 x 10 2.67 x 10 4.70 x 10 4.53 x 10 5.61 x 10 9 2.62 x 10 2.59 x 10 5.38 x 10 5.16 x 10 6.38 x 10 10 2.51 x 10 2.46 x 10 6.00 x 10 5.75 x 10 7.12 x 10 11 1.83 x 10 2.39 x 1010 6.44 x 10 6.19 x 10 7.66 x 10 12 2 '0 x 10 2.61 x 10 7.04 x 10 6.74 x 10 8.34 x 10 13 2.32 x 10 1.93 x 10 7.49 x 10 7.29 x 10 9.03 x 10 14 2.27 x 10 1.97 x 10 7.94 x 10 7.83 x 10 9.70 x 10

- 10 2 Notes: 1 5 = 2 38 x 10 n/cm -sec.

10 2

= 2.95 x 10 n/cm -sec.

~l SD-RSA-84/2153 Table 3 FAST NEUTRON E > 1.0 MeV EXPOSURE AT THE PRESSURE VESSEL INNER RADIUS - 30 AZIMUTHAL ANGLE CUMULATIVE FLUENCE (n/cm2)

Irradiation Cycle Avg.

Cycle Time F/ux 'Plant Specific Generic , Generic

'No. (EFPS) (n/cm -sec) P3 Pl -

P3 lA 2.09 x 10 '.50 x 10 3.14 x 10 3.24 x 10 .-

4.12 x 10 .

1B 2.38 x 10 1.53 x 10 6.78 x,10 6.93 x 10 8.81 x 10 2 0.71 x 10 1.75 x 10 . 8.02 x 10 8.03 x 10 1.02 x 10 3 2.88 x 10 1.46 x 10 1.22 x 10 1.,25 x 10 1.59 x 10 4 2.17 x 10 1.80 x 10 1.61 x 10 1.59 x 10 2.02 x 10 5 1.84 x 10 1.71 x 10 1.93 x 10 1.87 x 10 2.38 x 10 6 2;42 x 10 1.62 x 10 2.32 x 10 2.25 x 10 2.85 x 10 7 2.35 x 10 1.71 x 10 2.72 x 10 2.61 x 10 3.32 x 10 8 2.20 x 10 1.76 x 10 3.11 x 10 . 2.95 x 10 3.75 x 10 9 2.62 x 10 1.84 x 10 3.59 x 10 3.36 x 10 4.27 x 10 10 2.51 x 10 1.78 x 10 4.04 x 10 3.75 x 10 4.76 x 10 ll l.83 x 10 1 ~ 48 x 10 4.31 x 10 4 03 x 10 5.12 x 10 12 2.30 x 10 1.43 x 10 '4.63 x 10 4.39 x 10 5.58 x 10 13 2.32 x 10 1.27 x 10 4.92 x 10 4.74 x 10 6 03 x 10 14 2.27 x 10 1.54 x 10 5.27 x 10 5.09 x 10 6.48 x 10 Notes: 1 - 5 ayg = 1.55 x 10 10 n/cm 2 -sec.

10 Pay= 1 .97x1 0n/cm-sec P

ill

4

SD-RSA-84/2153 Table 4 FAST NEUTRON E > 1.0 MeV EXPOSURE AT THE PRESSURE VESSEL INNER RADIUS - 44.5'ZIHUTHAL'ANGLE CUMULATIVE'FLUENCE (n/cm2)

Irradiation Cycle Avg.

Cycl e Time Fiux Plant Specific Generic Generic No. (EFPS) (n/cm~-sec) P3 Pl P3 1A 2.09 x 10 1.29 x 10 2.70 x 10 , 2.65 x ] 017 3.64 x 10 1B 2.38 x 10 1.31 x 10 5.81 x .10 5.68 x 1017 7.78 x 1017 2 0.71 x 10 1.60 x 10 6.95 x 10 '.58 x 10" 9. Ol x 10 3 2.88 x 10 1.30 x 10 1.'07 x 10 1.02 x 1018 1.40 x 1018 4 2.17 x 10 1 ~ 62 x 10 1.42 x 10 1.30 x 1018 1.78 x 10" 5 1.84 x 10 1.36 x.l0- 1.67 x 10 1.53 x 018 2.10 x 10 6 2.42 x 10 1.30 x 10 1.99' 10 1.84 x 1'0" 2.52 x 1018 7 2.35 x 10 1.38 x 10 2.31 x 10 2.14 x 10 2.93 x 1018 8 2.20 x 10 1.58 x 10 2.66 x 10 2.42 x 1018 3.31 x 1018 9 2.62 x 10 1.68 x 10 3.10 x 10 2.75 x 1018 3. 77 x 1018 8

10 2.51 x 10 1.63 x 10 3.51 x 10 3.07 x 10 4. 21 x 1018 11 1'.83 x 10 1.45'x 10 3.77 x 10 3.30 x 1018 4.52 x 10" 2.30 x 10 1.39 x 10 4.09 x 10 3.59 x 018 4.92 x 1018 12 .

13 2.32 x 10 1.05 x 10 4.34 x 10 3.84 x 1018 , 5.33 x 10 2.27 x 10 1.54 x 10 4.69 x 10 4.13 x 1018 5.72 1018 14

- 10 2 Notes: 1 9 = 1.27 x 10 n/cm -sec.

10 2 2 - p = 1.74 x 10 n/cm -sec.

FSD-RSA-84/2153 Table 5 FAST NEUTRON E > 1.0 MeY EXPOSURE AT THE 13'URVEILLANCE CAPSULE .CENTER CUMULATIVE FLUENCE (n/cm )

Irradiation Cycle Avg.

Cycl e Time Pjux '1ant 'Specific'n/cm Capsule Generic Pl Generic P3 No. (EFPS) -sec.) P Measurement 1A 2.09 x 10 1.19 x 10 2.49 x 10 2.'78 x'1018 3.07 x 10 7 18 5. 95 x 1018 6.57 x 10 1B 2 38 x 10 1.27 x 10 5.51 x 10 1.30 x 10 6.44 x 10 6.53 x 10 6. 89 1018 7.61 x 10 2 0.71 x 10 3 2.88 x 10 1.13 x 10 9.69 x 10 . 1.02 x 10 1.07 x 10 1.18 x 10 1.22 x 10 1.36 1019 1.50 x 10 4 2.17 x 10 1.17 x 10 19 5 1.84 x 10 1 ~ 43 x 10 1.49 x 10 1.61 x 10 1.77 x 10 6 2.42 x 10 1.24 x 10 1.79 x 10 1.93 x 10" 2.13 x 10 19 7 2.35 x 10 1.23 x 10 2.08 x 10 2.24 x 10 2.48 x 10 2.37 2.53 1019 2.80 x 10 8 2.20 x 10 1.36 x 10 x 10 9 2.62 x 10 1.29 x 10 2.71 x 10 2.88 x 10 3.18 x 10 10 2.51 x 10 1.23 x 10 3.02 x 10 3. x 10 3.55 x 10 2-1'.46 3.24 x 10 1019 3.82 x 10 11 1.83 x 10 ~

1.22 x 10 3.56 3.76 1019 4.16 x 10 12 2 30 x 10 1.36 x 10 x 10 13 2.32 x 10 9.43 x 10 3.78 x 10 4.07 x 10 4.50 x 10 19 4.37 x 10 4.83 x 10 14 227 x10 9.49 x 10 4.00 x 10 10 2 Notes: 1 - P

= 1.33 x 10 n/cm -sec.

11 2 2 - 5 = 1.47 x 10 n/cm -sec.

'V

'l e

~ II

~ ~ p C II

~f'

FSD-RSA-84/2153 Table 6 FAST NEUTRON E ) 1.0 MeV EXPOSURE AT THE 23'URVEILLANCE CAPSULE CENTER CUMULATIVE FLUENCE (n/cm )

Cycl e Irradiation Time Cyc1e Ayg. ~:

Generic 1 ~

beneric 2

, F)ux P1ant Specific No. (EFPS)'n/cm -sec.) P3 Capsu1e Pl P3 Measurement lA 2.09 x 10 6.86 x 10 1.43 x 10 1.60 x 10 1.86 x 1018.

1B 2.38 x 10 7.14 x 10 3.13 x 10 3;42 x 10 , 3.98 x 1018 0.71 7.80 18'.

2 x 10 x 10 3.69 x 10 3.97 x 10 >4.61 x 10 3 2.88 x 10 6.61 x 10 5.59 x 10 6.18 x 10 7;18 1018 4 2.17 x 10 7.82 x 10 7.29 x 10 7.84 x 10 ,9.11 x 1018 5 1.84 x 10 8.14 x 10 8.79 x 10 9.25 x 10 1.08 x 10 2.42 7.50 19 10" 6 x 10 x 10 1.06 x 10 1.11 x 10 1.29 x 7 2.35 x 10 7.82 x 10 1.24 x 10 1.29 x 10 1.50 x 10 2.20 'x 7.95 8 10 x 10 1.42 x 10 1.46 x 10 1.70 x 10 9 2.62 x 10 8.07 x 10 1.63 x 10 1.78 x 10 1.66 x 10 1.93 1019 10 2.51 x 10 7.74 x 10 1.82 19 x 10 1.85 x 10 2.15 x 10 ll 1.83 x 10 7.18 x 10 1.96 x 10 1.99 x 10 2.32 x 10" 12 2.30 x 10 6.85 x 10 2.11 x 10 2.17 x- 10 '2.52 1019 13 2.32 x 10 5.95 x 10 2.25 x 10 2.35 x- 10 2.73 x 10" 14 2.27 x 10 6.55 x 10 2.40 x 10 2.52 x 10 2.93 x 10 Notes: - 10 2 1

Hay 7 66 x 10 n/cm sec.

2 pay=8.9 1x10n/ cm-sec 10

wc ll

~f ~

D-RSA-84/2153 Table 7 FAST NEUTRON E > 1.0 MeV EXPOSURE AT THE 33'URVEILLANCE CAPSULE CENTER CUMULATIVE FLUENCE (n/cm2)

Irradiation 'yc1e Avg.

Cyc1e Time Flux Plant Specific Generic Generic No. (EFPS) (n/cm~-sec) P3 Pl P3 18 1A '2.09 x 10 6.06 1010 1.27 x 10 1.48 x 10 1.68 x 10 7 18 1B 2.38 x 10 6.14 x 10 2.73 x 10 3.16 x 10 3.60 x 10 18 2 0.71 x 10 7.24 1010 3.24 x 10 3.66 x 10 4.18 x 10 3 2.88 x 10 5.95 x 10 4.96 x 10 5.69 x 10 6.50 x 10 4 2.17 x 10 7.40 x 10" 6,.56 x 10 7.22 x 10 8.25 x 10 5 1.84 x 10 6.75 x 1010 7.80 x 10 8.52 x 10 9.73 x 10 6 2.42 x 10 6.45 x 10" 9 37 x 10 1.02 x 10 1.I7 x 10 10 1.19 x 10 1.36 x 10 7 2.35 x 10 6.86 x 10 1.10 x 10 8 2.20 x 10 7.22 1010 1.26 x 10 1.34 x 10 1.53 x 10 9 2.62 x 10 7.61 x 10" 1.46 x 10 1.53 x 10 1.75 x 10 10 2.51 x 10 7.39 x 10 1.64 x 10 1.71 x 10 1.95 x 10 ll 1.83 x 10 6.03 x 10 1.75 x 10 1.84 x 10 19 2.10 x 10 12 2.30 x 10 5.78 1010 1.88 x 10 2.00 x 10 2.28 x 10 10 19 13 2.32 x 10 5.00 x 10 2.00 x 10 2.16 x 10 2.47 x 10, 19 14, 2.27 x 10 6.38 x 10 2.14 x 10 2.32 x 10 2.65 x 10 10 2 Notes: 1 9 = 7.08 x, 10 'n/cm -sec.

- 10 2 2 9 avg = 8.06 x 10 n/cm -sec.

0