ML19290B883

From kanterella
Revision as of 15:23, 1 February 2020 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Effluent Waste Disposal & Potential Doses Semiannual Rept, Jul-Dec 1976.
ML19290B883
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 02/08/1976
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML17174B224 List:
References
FOIA-79-488 NUDOCS 7912140319
Download: ML19290B883 (17)
v • d • e


Text

, .

ll

,/J

'+

Q, ATTACmENT 1 'h

EFFLUENT, WASTE DISPOSAL, AND POTENTIAL DOSES SEMIANNUAL REPORT July - December 1976 Brunswick Steam Electric Plant February 8, 1977 791'140 2

3l914 as 1578 030 w-

      • - EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1976 Supplemental Information Facility Brunswick Steam Electric Plant License Carolina Power & Light Co.
1. Regulatory Limits
a. Fission & activation gases II {0.72 g Q, + 290 Qv) 1 1 quarterly average Ik{22Q,+200Q)11quarterlyaverage y

IEg {1.4 Q, + 580 Qy) 1 1 12 month average I%(45Qs+400Qy)1112monthaverage

b. Iodines 2 Curies per quarter 4 Curies per 12 months
c. Particulates, half-lives >8 days

{4.7 x 105)qs + {7.2 x 10 7)Q, 1 1 quarterly average (9.3 x 10 5)Q, + {1.5 x 10 )Qy 8

1 12 month average

d. Liquid effluents 10 Curies per quarter 20 ?uries per 12 months

". Maximum Permissible Concentrations

a. Fission & activation Cases iqs (4.0 I y+ 0.23 I ) g+ Q , {35% + 92 Ig) 1 1
b. Iodines ,

4

{3.7 x 10 )Q, + {5.8 x 106 }qv i i

c. Particulates, half-lives > 8 days

{3.7 x 104 )Qs + {5.8 x 106 )Qy11

d. Liquid Effluents values specified in 10CFR Part 20, Appendix B. Table II, Column 2 for unrestricted areas.
3. Average Energy Stack

% = 0.47 MEV Yg = 0.44 MEV 7 j

Average Energy Ground 57= 0.00 MEV I g= 0.17

4. Measurements and Approximations of Total Radioactivity
a. Fission and activation gases Analysis for specific radionuclides in representative grab samples by gamma spectroscopy.
b. Iodines Analysis for specific radionuclides collected on charcoal cartridges by gamma spectroscopy.
c. Particulates .. - -

Analysis for specific radionuclides collected on filter papers by gamma spectroscopy.

d. Liquid effluents Analysis for specific radionuclides by individual releases by gamma spectroscopy.

Relative variance for each measurement used in calcualting activity values were combined using the additive property of variance. The square root of the combined variance was extracted to obtain an estimate of the standard deviation of the multistep process. The standard deviation was used to evaluate the error in the calculated activities at the 95% confidence level.

5. Batch Releases
a. Liquid
1. Number of Batch releases: 504
2. Total time period for batch releases: 4.63 E04 minutes
3. Maximum time period for a batch release: 3033 minutes
4. Average time period for batch releases: 91.86 minutes
5. Minimum time period for a batch release: 1 minute
6. Average stream flow during periods of release of effluent into a flowing stream: not applicable
b. Gaseous
1. Number of batch releases: none .
2. Total time period for a batch release: not applicable
3. Maximum time period for a batch release: not applicable
4. Average time period for a batch release: not applicable
5. Minimum time period for a batch release: not applicable 1578 032

/

6. Abnormal Release
a. Liquid
1. Number of releases: none
2. Total activity released: none
b. Caseous
1. Number of releases: none
2. Total activity released: none 1578 033

~ .* . .. .

TABLE 1A EFFLUElir AND WASTE DISPOSAL SEMIANNUAL REPORT (1976)

CASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES

~

Unit Quarter Quarter Est. Tota Enor, %

, III IV l

A. Fission & activation gases 4.66E03 1.36E04 1.33E01

1. Total release Ci 1.71E03
2. AveraRe release rate for period UCi/ sec 5.86E02

~

3. Percent of Technical specification limit  %

B. Iodines

- ~

1. Total iodine-131 Ci
  • 1.33E01 4.53E-02
  • 0~
2. Average release rate for period __ UCi/sec
3. Percent of technical specification limit  % 3.16 EGO 4.54E-01 C. Particulates
1. Particulates with half-lives > 8 days Ci 3.54E-03 2.05-03 1.33E01
2. Average release rate for period UCi/sec 4.45E-04 2.61E-04
3. Percent of technical specification licit  % 2.78E-01 1.10E-01
4. Gross alpha radioactivity C1 3.09E-07 9.15E-06 b

i D. Tritium

1. Total release Ci 8.27E-01 2.48E-01 1.45E01
2. Average release rate for period uCi/see 1.04E-01 3.12E-02

{ ,

3. Percent of technical specification limit  % 5.5 1.65 I

I 1578 OM 4

=. TABLE IB

^

EFFLUENT AND WASTE DISPOSAL ShiIANNUAL REPORT (1976)

- - GASEOUS EFFLUEhTS-ELEVATED RELEASE Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission gases C1 < MDA 0 0

} k rypt on-85 <wna C1 2.17E02 1.08E03 0 0 krypton-85m 0 Ci 3.48E02 1.44E03 0

- _ _ krypton-87 0 0

_kryp ton-88 C1 9.78E01 1.32E03 C1 1.53E03 3.16E03 0 0 xenon-133 0 Ci 1.37E03 4.43E03 0 xenon-135 0 0 xenon-135m Ci 1.40E02 4.93E02 2.63E01 9.39E01 0 0 xenon-138 C1

Ci 6.22EOl 8.54E02 0 0 argon-41 1.4 5 E02 1.02E02 0 0 xenon-133m C1

{ C1 0

C1 0 unidentified 0 Total.for period C1 ,3.94E03 l1.33E04 0 i i

2. Iodines U

, iod in e-131 C1 3.18E-01 6.86E-02 0 iodine-133 C1- 1.s1E-uz. 3.21E-03 0 0 iod ine-135 Ci o ost-na 1 147-na o o Total for Period C1 3.36E-01 7.19E-02 0 0

~

3. Particulates strontium-89 C1 '

o.32E-05 7 97v-ns 0 0 strontium-90 Ci <MDA 9.?0E-05 0 0 Ci < MDA 1.29E-05 0 0 c3sium-134 0 casium-137 C1 1 93p_oS 5.15E-05 0 Ci < MDA 0 - ~70 barium-lanthanum-140 < MDA Ci 8.35E-06 1.21E-04 0 t cobalt-58 C1 6.69E-06 4.35E-05 0 0 cobalt-60 0 chro-in -51 C1 6.llE-06 ' 7.56E-05 0 C1 1.27E-06 2.71E-05 0 0 zine-65 0

< MDA 6.98E-06 0 iron-59 Ci 0

mancanese-54 Ci 7.50E-06 1.32E-04 0 Ci Ci Ci Ci Ci ci ,

Ci Ci unidentified ci

  • Total for period Ci 1.35E-04 6.02E-04 0 0 e

1578 0,33 t

TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1976)

CASEOUS EFFLUENTS- GROUND-LEVEL RELEASES 1

l Continuous Mode Batch Mode I

s Quarter

- Nuclides Released Unit Quarter quarter Quarter

1. Fission gases k ryp t on-85 Ci < MDA < MDA 'O O

. krypton-85m Ci < MDA < MDA n 0 krypton-87 Ci < MDA < MDA 0 0 kryp ton-88 C1 < MDA __ < MDA _ 0 0 xenon-133 Ci 5 76F02 2.49F02 0 0 xenon-135 C1 1.20E02 7.31E01 0 0 xenon-135m C1 < MDA < MDA 0 0 xenon-138 C1 < MDA _

< MDA 0 0 vennn-111, Ci 2.63E01 6.24E00 0 0 Ci Ci unidentified Ci 0 0 Total.for period Ci 7.22E02 3.24E02 0 l 0

2. Iodines iodine-131 C1 4.15E-02 5.79E-03 0 0 iodine-133 C1 2.01E-03 5.16E-05 0 0 iodine-135 C1 6.86E-05 < MDA 0 0 Total for Period C1 4.36E-02 5.84E-03 0 0
3. Particulates etrontium-89 C1 2.64E-03 2.17E-05 0 0 s t ront'ium-90 Ci <MDA 3.072-06 0 0 cesium-134 C1 2.48E-05 2.06E-05 0 0 cesium-137 C1 2.71E-04 6.43E-05 0 U barium-lanthanum-140 C1 < nua < MDA u u cobalt-58 C1 9.23E-05 1.83E-04 0 0 cobalt-60 C1 1.24E-04 2.32E-04 0 0

) chromium-51 Ci 2.64E-04 4.65E-04 0 0 zirconium-niobium-95 C1 4.56E-05 1.19E-05 0 0 l zine-65 Ci 5.39E-05 1.35E-04 0 0 iron C1 2.34E-05 5.74E-05 0 0 l -anennen,-54 cf 1_11v-na- 9 17v-na n n

-nl i.h a a m.,_ o q Ci 1.719-04 < MDA n n technetiun-99m Ci 1_7AF-rs < MDA n n Ci Ci Ci Ci Ci unidentified Ci l "otal for Period Ci 3 R1F-n1 1.45E-03 0

1578 036 i

I Notes:

1) Minimum detectable concentrations for radionuclides not detected (uci/cc):

isotope uci/cc .

Kr-85 5.40E-06 Sr-90 1.00E-15 Cs-134 1.74E-14 Fe-59 1.74E-14 Kr-85m 1.68E-08 Kr-87 2.84E-08 Kr-88 6.05E-08 Xe-135m 2.87E-08 Xe-138 1.85E-08 I-135 3.50E-14 Ba-La-140 2.93E-14 Mo-99 4.96E-14 Tc-99m 4.78E-15 Cs-137 1.29E-14 O

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1976)

LIQUID EFFLUENTS-SUMMATION OF AIf RELEASES

. Unit Quarter Quarter Est. Total Error, %

III IV A. Fias! r.md acti'. cion products t 1. To* ' release (not including Ci ~

.ME00 I ..tum, gases, alpha) 7'. 2'5E41 ' 1.15E01

2. Average diluted concentration uCi/mi during period 2.05E-08 1. 23 E-O'8"

% 1.41E01 l7 25E'00

3. Percent of applicable limit B. Tritium Ci 2.45E00 1.32E00 1.33E01
1. Total release
2. 3.56E-08 2.24E-08

. Average diluted concentration uCi/ml i during period I

3. Percent of applicable limit Z 1.19E-03 7.47E-04~

a C. Dissolved and entrained gases 6.65E-01 3.58E-02 1.15E01

1. Total release Ci

, 2. Average diluted concentration uCi/ml 9.66E-09 6.08E-10 during veriod I

i 3. Percent of ' applicable limit  % 3.22E-01 2.02E-02 D. Cross alpha radioactivity J

1. Total release Ci }+3. 72E-08 M8.44E-09 1.22E01 E. Volume of waste released (prior to liters 5'.66E00 dilution) 1.84E07 1.28E07 F. Volume of dilution water used liters during eeriod 5.88E10 5.89E10 1.10E01 1578 033

TABLE 2B EFFLUENI AND WASTE DISPOSAL SEMIANNUAL REPORT, (1976)

LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclide', Released . Unit Quarter Quarter Quarter Quarter coba?c-57 Ci 0 0 7.92E-05 9.85E-07 arrenic-76 Ci 0 0 2.94E-03 <MDA

. gallium-72 Ci 0 0 9.19E-04 <MDA e nvi um-14 4 Ci 'O O 2.97E-02 3.14E-03 ein-111 Ci o n 1.15E-05 <MDA in44n--111 Ci 0 0 1.76E-05 <Mna '

cin-117, Ci 0 0 7.24E-04 <MDA minkin--97 C1 0 0 6.79E < wn a eevnneinm-R9 C1 0 0 5.15E-05 <MDA mernneine-87m C1 0 0 6.52E-03 <MDA brn-ine-82 C1 0 0 1.65E-04 <MDA ce=iun-13 6 C1 0 0 1.01E-03 3.05E-04 nnei-ony-122 C1 0 0 2.03E-04 4.20E-04 barfu--130 C1 0 0 3.68E-03 9.18E-05 ceriu--139 C1 0 0 7.59E-04 2.11E-05

-ndin--22 C1 0 0 1 1.47E-05 <MDA rubidium-88 C1 0 0 1.49E-03 <MDA iodine-132 C1 0 0 <MDA 1.57E-04 xenon-131m C1 0 0 4.95E-02 9.54E-03 venon-133m C1 0 0 1.22E-02 1.84E-04 arcon-41 C1 0 0 1.46E-03 2.90E-04 krvnton-85 C1 0 0 1.28E-02 (MDA krvoton-85m Ci 0 0 5.56E-04 0.17E-Oo krvDton-87 l Ci l 0 0 l 3.26E-04 (MDA

. krvnenn-88 i Gi 0 0 4.92E-U4 <MDA stroncin--92 i C1 n n <MDA 8.13E-07 0 0 <MDA 1.21E-04 tunesten-187 Ci 9

1578 n39 TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1976)

I LIQUID EFFLUENTS f

Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter Ci 0 0 8.52E-04 1.43E-04 strontium-89 .

l strontium-90 Ci 0 0 9.58E-05 8.43E-05 .

~

cesium-134 C1 0 0 5.78E-03 2.35E-02 cesium-137 Ci 0 0 1.77E-02 6.36E-02 iodine-131 C1 -

0 0 4.14E-01 1.70E-01 cobalt-58 Ci 0 0 1.26E-01 6.41E-02 cobalt-60 Ci 0 0 1.48E-01 6.69E-02 iron-59 Ci 0 0 3.54E-02 1.41E-02 zine-65 Ci 0 0 7.95E-02 2.79E-02 manganese-54 C1 0 0 1.64E-01 7. 7 7E -02

__ chromium-51 C1 0 0 1.67E-01 1.01E-01 zirconium-niobium-95 Ci 0 0 2.37E-02 3.05E-03 molybdenum-99 C1 0 0 1.22E-02 2.66E-03 technetium-99m Ci 0 0 1.31E-02 2.84E-03 barium-lanthanu=-140 Ci 0 0 4 MDA < MDA cerium-141 C1 0 0 1.16E-03 1.13E-04 fluorine-18 C1 0 0 6.45E-02 2.77E-02 cooper-64 C1 0 0 5.62E-02 6.04B-02 andium-24 Ci 0 G 9.44E-03 < MDA

-anennese-56 C1 3.26E-03 Ci n 0 6.32E-03 '

iodine-133 n o ?_ASE-02 9.15E-03 antfrony-124 C1 n n 9.86E-04 1.60E-04 unidentified C1

[_ Total for period (above) l C1 0 v (1.41 7.25E-01 xenon-133 i C1 0 0 5.46E-01 1.67E-02 xenon-135 i C1 0 0 4.21E-02 8.97E-03 Total for period Ci 0 0 6.65E-01 3. 58E-02 1578 040

Notes:

Minimum detectable concentrations for radionuclides not detected (uci/cc):

isotope uci/cc Ba-La-140 9.65E-08 Na-24 1.49E-08 As-76 4.27E-08 Gs-72 5.10E-08 Sn-113 1.88E-08 In-113m 1.88E-08 Sn-117m 1.70E-08 Nb-97 1.93E-08 Sr-85 1.89E-08 Sr-87m 2.06E-08 Br-82 2.35E-08 Na-22 2.73E-08 Ru-88 1.24E-07 I-132 2.11E-08 Kr-85 4.68E-06 Kr-87 3.53E-08 Kr-88 4.27E-08 Sr-92 1.71E-08 W-187 7.03E-08 1578 041 s

.- . .. , /* .

TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)

SOLID WAGTE ANO IRRADIATED FUEL SHIPMENTS . . , :c o, : . ,9

- . . .r...

A. SOLIO WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NotIrradiated fuel)

- Seonth Est. Toad

1. Type of waste , . .urde Error,%

Period

  • a. Spent resins. filter sludges, evaporator d 9 4 04E02 79E02 1.50E01 bottoms, etc. C1
b. Dry compressible waste, contaminated m' l.g6E02 -

equip. etc. C1 2,o8E00 2,00E01 m' O. 00E00

c. Irradiated components, control 0.00E00 0,00E00 rods, etc. Ci m' u,vuEUU

- d. Other (describe) U 0 00E00 0 00E00

2. Estimate of major nuclide composition (by type of waste)

Krypton - 85 cr, 2.60E-01

. a.+ b. 7.30E-Cl Xenon - 133  %

Chromium - 51  % 2,45E01 Manganese - 54 cr, 2.31EU1 Cobalt - 60  % 1.3/EU1 Cobalt -58  % 10 EUA Iron - 59  % 3.26E0C'

' Zine- 65 4 6 77Enn

, Cesium - 134  % 2 41EOC e Leslum - 1.s/ 4 4./DEUL Cerium - 134 ar, 1.66E00 *

c. + d. None  % U.UUEUU e' -
3. Solid Waste Disposition Number of Shipments Mode ofTransportation Destination 74 Sole use Vehicle Chem-Nuclear Sy* stems, Inc.

Barnwell, SC ,

B. IRRADIATED FUEL SHIPMENTS (Disposition) -

Number of Shipments Mode of Transportation Destination None .. .. . .- .....t.:. .

. ~ . ., ... .,. ...

1578 042 v

1.2!.19 12* -

  • e .

WORST CASE SITE BOUNDARY DOSES RELATED TO AIRBORNE IODINE RELEASES (Hypothetical Cow and Leafy Vegetables at Site Boundary)

Thyroid Dose due to inhalation, mrem /6 Months 1 year old 1.39E-01 4 years old 1.34E-01 14 years old 8.92E-02

~

Adult 1.19E-01 Thyroid Lose due to Milk Pathway mrem /6 Months 1 year old 2.09 +01 4 years old 8. 64 +00 14 years old 2.98 +00 Adult 2.33 +00 Thyroid Dose due to Eating Green Leafy Vegetables, mrem /6 Months 1 year old 0.00 +00 4 years old 1.43 +00 14 years old 8.35 -01 Adult 8.83E-01 i

I 1578 043

SUMMARY

OF DOSES DUE TO LIQUID RE! EASES Dose Due to Eating Fish Caught in Discharge Canal Whole Body 6.82E-05 mrem /6 months G. I. Tract 3.34E-04 mrem /6 months Thyroid 3.81E-04 mrem /6 months Bone 4.00E-05 mrem /6 months Shoreline Sediment Dose Along Discharge Canal 3.15E-05 mrem /6 months Ocean Swimming Dose 2.86E-07 mrem /6 mcntha Radiological Impact on Man from direct radiation from the facility is negligible based on the results from environmental TLD's.

O 1578 044 AIR SUBMERSION WHOLE BODY DOSE, mrem /6 Hontha BRUNSWICK STEAM ELECTRIC PLANT . .

July to December 31, 1976 -

SECTOR

.5 1.5 2.5 3.5 4.5 7.5 15 25 35 45 S 1.399E-01 6.563E-02 5.227E-02 4.167E-02 3.411E-02 2.151E-02 1.069E-02 6.213E-03 4.297E-03 3.250E-03 SSW 5.566E-02 4.448E-02 4.203E-02 3.570E-02 3.000E-02 1.920E-02 9.2942-03 5.235E-03 3.549E-03 2.649E-03 SW 1.513E-02 4.148E-02 3.957E-02 3.363E-02 2.830E-02 1.825E-02 8.989E-03 5.131E-03 3.507E-03 2.630E-03 WSW 2.478E-02 2.951E-02 2.536E-02 2.104E-02 1.751E-02 1.117E-02 5.434E-03 3.094E-03 2.1198-03 1.596E-03 W 4.503E-02 2.709E-02 2.250E-02 1.871E-02 1.569E-02 1.019E-02 5.036E-03 2.873E-03 1.958E-03 1.464E003 WNW 5.293E-02 2.624E-02 2.208E-02 1.867-02 1.584E-02 1.061E-02 5.441E-03 3.164E-03 2.185E-03 1.651E-03 NW 4.770E-02 2.635E-02 2.G98-02 1.718E-02 1.427E-02 9.241E-03 4.615E-03 2.702E-03 1.894E-03 1.454E-03

. NNW 5.419E-02 3.248E-02 2.643E-02 2.170E-02 1.386E-02 1.210E-02 6.400E-03 3.844E-03 2.704E-03 2.067E-03 C'

N 5.256E-02 3.271E-02 2.965E-02 2.529E-02 2.150E-02 1.432E-02 7.418E-03 4.385E-03 3.063E-03 2.283E-03 NNE 5.272E-02 5.844E-02 5.638E-02 4.812E-02 4.053E-02 2.613E-02 1.268E-02 7.694E-03 4.773E-03 3.535E-03 NE 1.279E-01 9.524E-02 8.091E-02 6.565E-02 5.373E-02 3.307E-02 1.535E-02 8.435E-03 5.621E-03 4.136E-03 ENE 8.943E-02 6.824E-02 7.050E-02 6.308E-02 5.492E-02 3.7323E-02 1.923E-02 1.114E-02 7.654E-03 5.750E-03 E 1.031E-01 4. 645E-02 4.276E-02 3.714E-02 3.196E-02 2.154E-02 1.116E-02 6.543E-03 4.538E-03 3.436E-03 ESE 9.546E-02 4.008E-02 3.299E-02 2.726E-02 2.285E-02 1.495E-02 7.659E-03 4.531E-03 3.178E-03 2.435E-03 SE 9.701E-02 4.506E-02 3.643E-02 2.977E-02 2.424E-02 1.579E-02 7.710E-03 4.368E-O3 2.967E-03 2.214E-03 SSE 1.573E-01 5.811E-02 4.771E-02 3.909E-02 3.247E-02 2.069E-02 1.008E-02 5.690E-03 3.855E-03 2.870E-03 LD N HAXIMUM OFFSITE WHOLE BODY DOSE MREM /6 Honths 1.573E-01 CO CD

.?:=

LJ1 -

AIR SULMERSION SKIN DOSE, mrem /6 Months ., ,

BRUNSWICK STEAM ELECTRIC PLANT

.Tuly to December 31, 1976 SECTOR 25 35 45

.5 1.5 2.5 3.5 4.5 7.5 15 N 3.257E-01 1.318E-01 1.00hE-01 7.908E-02 6.425E-02 4.011E-02 1.979E-02 1.146E-02 7.911E-03 5.97/E-03 NNE 1.296E-01 8.538E-02 7.794E-02 6.555E-02 5.484E-02 3.491E-02 1.684E-02 9.471E-03 6.417E-03 4.787E-03 6.300E-03 4.724E-03 NE 8.654E-02 7.727E-02 7.21SE-02 6.098E-02 5.195E-02 3.299E-02 1.617E-02 9.220E-03 3.827E-03 2.880E-03 ENE 1.035E-01 5.582E-02 4.680E-02 3.851E-02 3.194E-02 2.028E-02 9.S33E-03 5.592E-03 E 9.049E-02 5.029E-02 4.109E-02 3.397E-02 2.840E-02 1.839E-02 9.06E-02 5.166E-03 3.520E-03 2.631E-03 ESE 1.072E-01 4.931-02 4.061E-02 3.407E-02 2.880E-02 1.920E-02 9.813E-03 5.698E-03 3.932E-03 2.971E-03 SE 1.219E-01 4.900E-02 3.838E-02 3.124E-02 2.587E-02 1.668E-02 8.310E-03 4.859E-03 3.403E-03 2.612E-03 l-.

7 SSE 1.113E-01 6.091E-02 4.859E-02 3.960E-02 3.304E-02 2.189E-02 1.154E-02 6.919E-03 4.863E-03 3.715E-03 S 1.197E-01 6.362E-02 5.547E-02 4.672E-02 3.950-02 2.611E-02 1.346E-02 7.936E-03 5.537E-03 4.216E-03 SSW 1.151E-01 1.085E-01 1.026E-01 8.710E-02 7.328E-02 4.705E-02 2.279E-02 1.274E-02 8.568E-03 6.344E-02 SW 2.791E-01 1.800E-01 1.492E-01 1.202E-01 9.801E-02 6.005E-02 2.782E-02 1.526E-02 1.016E-02 7.477E-03 WSW 2.155E-01 '1.329E-01 1.313E-01 1.160E-01 1.005E-01 6.784E-02 3.480E-02 2.013E-02 1.382E-02 5.257E-02 W 2.484E-01 9.528E-02 8.258E-02 7.031E-02 5.994E-02 3.993E-02 2.053E-02 1.200E-02 8. 311E-03 6.287E-03 2.262E-01 8.209E-02 6.429E-02 5.213E-02 4.330E-02 2.799E-02 1.430E-02 8.374E-03 5. 862E-03 4.485E-03 WNW LJ7 NW 2.280E-01 9.077E-02 7.035E-02 5.659E-02 4.666E-02 2.949E-02 1.431E-02 8.084E-03 5.625E-03 4.092E-03 N

C33 NNW 3.720E-01 1.206E-01 9.395E-02 7.550E-02 6.211E-02 3.908E-02 1.891E-02 1.065E-02 7.207E-03 5.364E-03 CD 4

CB MAXIMUM OFFSITE SKIN DOSE MREM /6 Months 3.720E-01

Retrieved from "https://kanterella.com/w/index.php?title=ML19290B883&oldid=2376542"