ML19290B884

Semiannual Environ & Effluent Release Rept for Jan-June 1977

ML19290B884
Person / Time
Site:	Brunswick
Issue date:	08/31/1977
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML17174B224	List: ML17174B223 ML19290B881 ML19290B882 ML19290B883 ML19290B884 ML19290B885 ML19290B886 ML19290B887 ML19290B888 ML19290B889 ML19290B890 ML19290B891 ML19290B892 ML19290B893 ML19290B895 ML19290B898 ML19290B901 ML19290B903 ML19290B904 ML19290B905 ML19290B909 ML19290B913 ML19290B915 ML19290B916 ML19290B917 ML19290B918 ML19290B919 ML19290B920 ML19290B921 ML19290B922 ML19290B923 ML19290B924 ML19290B925 ML19290B926 ML19290B929 ML19290B930 ML19290B932 ML19290B933 ML19290B934
References
FOIA-79-488 NUDOCS 7912140322
Download: ML19290B884 (20)

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ATTACHMENT 1 EFFLUENT, WASTE DISPOSAL, AND POTENTIAL DOSES SEMLWNUAL REPORT January - June 1977 Brunswick Steam Electric Plant August 9, 1977 1578 048

• -3.. n 50- 319'

.-' -..:172s20tSo i - g/3. /].7Z__t ; ". =. '.tr.?:

......s....: a

. i ll*

, 4./

2

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1977 Supplemental Information g

Facility Brunswick Steam Electric Plant License Carolina Pcuer & Light Co.

1.

Regulatory Limits -

a.

Fission & activation gases IiS

{0.72 Q + 29L Q ) < 1 quarterly average s

v -

Iiy {22 Q, + 200 Q } 1 1 quarterly average y

IiS {1.4 Q, + 580 g} 1 1 12 month average Iiy {45 Q, + 400 Q ) $ 1 12 month average y

b.

Iodine-131 via gaseous releases 4 Curies per quarter 8 Curies per 12 months c.

Particulates, half-lives >8 days

{4.7 x 10 }Q, + {7.2 x 10 }Q 1 1 quarterly average y

5 8

{9.3 x 10 )Q, + {1.5 x 10 }Q 1 1 12 month average d.

Liquid effluents 20 Curies per quarter 40 Curies per 12 months 2.

Maximum Permissible Concentrations a.

Fission & activation Gases IQ, {4.0 Ey + 0.23 IS) + Q {355y + 92 IS'} 1 1 y

b.

Iodines and Particulates with half lives greater than eight days.

6

{3.7 x 13 ) Q,

+ {5.8 x 10 ) q 1

c.

Liquid Effluents Values specified in 10CFR Part 20, Appendix B, Table II, Column 2 for unrestricted area.

3.

Average Energy Stack iv

= 0.56 is 0.42 MEV

=

Average Ene gy Ground Ey

= 0.15 MEV is 0.23

=

1578 049 1

=

L.

Measurements and Approximations of Total Radioactivity a.

Fission and activation gases g

Analysis for specific radionuclides in representative grab samples by v

gam =a spectroscopy.

b.

Iodines Analysis for specific radionuclides collect 2d on charcoal cartridges by gamma spectroscopy.

c.

Particulates Analysis for specific radionuclides collected on filter napers by gamma spectroscopy.

d.

Liquid effluents Analysis for specific radionuclides by individual releases by gamma spec-troscopy.

Relative variance for each measurement used in calculating activity values were combined using the additive property of variance. The square root of the com-bined 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. Nu=ber of Batch releases: 370

2. Total time period for batch releases: 5.15E04 minutes

3. Maximum time period for a batch release:

3940 minutes

4. Average time period for batch releases:

139.2 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 050

_2_

=

6.

Abnormal Release a.

Liquid 1.

Numbt:r of releases:

None 2.

Total activity released:

None b.

Gaseous 1.

Number of relew.ses:

None 2.

Total activity released:

None e

1578 051 O

s 3

TAP,LE lA EFFLUE:.T N;D L'ASTE DISPOSAL SCIINGUAL REPORT (YEAR)1977 CASEQUS EFFLUENTS-SUDfATIO: OF ALL RELEASES

^

Unit Quarter Quarter Est. Tota Error,%

77 7

7g A.

Fission & activation cases Ci 1.18E+05 8.30Et04 1.33E+0 1.

Total release Ci/sec. 1.63E-02 1.06E-02 2.

Averace release rate for ceriod 6.70E+01 4.70E+01 3.

Percent of Technical specification limit B.

Iodines C1 1.06E-01 4.11E- 01 1.33E+0 1.

Total iodine-131 C1/sec. 1. 35E-08

5. 22E-08 2.

Averace release rate for ocriod 2.65 E00

1. 02 E+01 3.

Percent of technical seccification limit C.

Particulat es C1

1. 06E.02 4.41r- 02 1.11r*

1.

Particulates with half-lives > S davs c4fe,c. 1 34r_00 5.647-00

2. _ Average release rate for oeriod 2.01 E00

.3.06E01 3.

Percent of technicci soecification limit Ci 8.85E-05 7.74E-05 l 4.

Cross alpha radioactivity D.

Tritiuti c4 s 17v on 4 457 nn 1 asr+

1.

Total release c4 / e -

6. 58E-07 5.66E-07

~

"2.

Averace reiease rate for period 1.41E01 1.25E01 of technical specification limit 3.

Percent 1578 052

. +.....

8 *-.

em.

TAELE 1B EFFLUE2;T AND k'ASTE DISPOSAL SEMIAWUAL REPORT (YEAR)1977 GASEOUS EFFLUE2;TS-ET.EVATED RELF1.SE Continuous Mode Batch Mode f

II lst 2nd l

Tuclides Released Uni.t Quarter Quarter Quarter Quarter

1. Fission gases a

krypton-85 Ici I:<tCF-

< +nA krypton-85m Ci 8.37E+03 4.15E+03 krvoton-87

' Ci 1.25E+04 8.48E+03 krvuton-88 Ci 1.34E+04 6 snr+nt Ji 1.38E+04 1.50E+04 C

xenon-133 xenon-135 Ici 3.50E+34 2.61E+04 xenon-135m "Ci 8.21E+03 5.27E+03 xenon-138 C1-

'I 8.28E+03 6.10E+03 Argon-41

Ci l 3.16E+02 1.08E+03 Xenon-133M Ci 7.04E+02 6.97E+01 1

lCi l

unidentified lCi'

'11 1.17E+04 8.29E403 l

Total for period Ci l1.15E+05 8.11E404

,2.

Iodines iodine-131 lCi l 9.78E-02 1 siv-n1 fodime-133 ICi

'l 2.62E-02 1.98E-01 iodine-135

-l C1 1.49E-02 6.2Ar-n?

Total for period

' l C1 1.39E-01 6.14E-m

3. Particulates strontium-89 lCi l 1.30F-03 6.nor-n?

strontium-90

' 1 Ci I 3.71E-05 5'.73E-02 cesium-134 lCi

! 6.84E-05 1.54E-06 cesium-137 Ici i 1.99E-04 1.38E-04 barium-lanthanum-140 Ci

& 5.48E-03 4.02E-03 Cobalt-58 Ci i 1.52E-05 1.62E-05 Mancanese-54 lci I 6.36E-ns a 11r nm cerium-139 (Ci i 1.15E-04 1 n6F-n1 unidentified lCi i See Table ] B-1 cn=nene of el"a-tr-Elevated Mase Total for oeriod ICi

See Talbe IB-x Casecne dffinae c r'a..ond eric ge 1578 053

T TABLE 1B-1 EFFLUENT AND WAST DISPOSAL SEMIANNUAL REPORT (YEAR) 1977 GASEOUS EFFLUENTS - ELEVATED RELEASE Particulates (rnneiniiadi Ci 1_ air ns A 93r_nm Cobalt-60 Ci l A 7,r_nm 1.67r-04 chvn e,,, 51 i

Ci l, y ~~

1 n1r_nm Zirconitt -Mi nh 4i 0.,

Ci l

s 91r n;

'1 17v_nm l

14,- As Iron-59 l

C1 2.49E-05 l 1 74r-ns l

l 1

C1 7.45E-06

<Mna l

Ce s i n--116 I

C1 7_197_n;

, ear nz lodine-131*

1.265-03 l

vervi,i a q i

C1

<m.

l C1

-~

l 1

1.27E-02 l

Ci 7,ggp_nt Unfann*4f4.A

,1.38E-01

(

l C1 l A 9?r n, yne 1 r e,- p e,. 4_ g I

C:-

1 l

C1 l

C1

{

l Ci I

.I ll C1 l

t l

l C1 i

i i

C1 1

l i

C1 l

l l

Ci l

l l

C1 l

l C1 l

l I

C1 I

n l

l C1 l

l l

t Ci l

I Ci I

Ci

• Iodine found on the particulate filter preceding the charcoal absorber 1578 054~

E TABLE IC EFFLUENT A'!D k'ASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1977 GASEOUS EFFLUENTS-CROUND-LEVEL RELEASES O

Continuous Mode Batch Mode 11 1st 2nd j

{

Quarter Uuelides Released Unit Ouarter Quarter

! Quarter l

1. Fission gases krvoton-85 i Ci i 0.00 0.00 krvoton-85m i Ci 1 0.00 0.00

'krvaton-87 Ci 8 0.00 0.00 krvoton-88 l Ci I 0.00 0.00 xenon-133 i Ci

't 1.45E+03 6.59E+02 xenon-135 i Ci i 1.15E+03 1.05E+03 xenon-135m I ci I 0.00 0.00 xenen-138 i Ci i 0.00 0.00 Ae-133m i Ci I 4.51E+01 1.58E+01 l' Ci i

i Ci i

unidentified I Ci I 3.00E+02 1.96r+n?

~~

Total for period i Ci l_2.95E+03 1.9?E+03

2. Iodines I

iodine-131 l Ci l'&.62E-03 5.76E-02 iodine-133 i ci l_1.97E-03 2.92E-02 iodine-135 i Ci I 8.77E-05 7.32E-04 g, Total for oeriod I Ci l 1.07E-02 8.75E-02

3. Farticulates strontiun-89 i Ci I 7 1nr.ns 2.31E-04 strontium-90 1 Ci l, 7sr_ns 1.02E-05 cesium-134 i Ci

, qqv_ns

't tor n1 '

cesium-137' 1 'Ci I 6.7'F-ns 1 1Av_n1 barium-lanthanum-140t Ci t0.00 t sne_ns Cobalt-58 i Ci' i 1.30r-04 R 47F-na Cobalt-60 i Ci

!1.43E-04 1 ?Ar n1 Chromiun-51 i Ci I9.65E-04 7.7Rr n1 Zirconium-Niobium-95i Ci i2.25E-06 6.41F-ns Zine-65 l ci i6.13E-05 4.29E-04 Iron-59 i ci

,9.09E-05 1.16E-03 Mancanese-54 I ci

!1.93E-04 5.69E-03 C1 Molybdenum-99 Technetium-99 i Ci Ci i

Zirconium-97

' Ci a

Niobiu=-97m Ci ieg, T,k1, 3 r_,

v,.

c.,,,, a v m.m3 om,,,,,,

unidentifed Total for period Ci ISee Table IC-1;For Ground Ldvel Reieases 0

i578 055

TABLE IC-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1977 GASEOUS EFELUENTS - GROUND LEVEL RELEASES dontinuous Mode Batch. Mode Particu1 stem (enneinnadi Ci 1.26E-06 1.24E-05 Cerium -139 Ci l 3.43E-04 '

1.03E-02 l T od i n e-191

• CL I

<MDA 4.04r-05 l

I i

Yttrium-88 C1 (MDA 1.07E-04 Yttrium-91 C1 l <MDA 2.97E-04 l l

Cerium-144 C1 1

<MnA 1 9%F-05 Cesium-136 C1

<FnA 3.26E-04 Cadmium-109 i

C1 L

1 L1 l

3.37E-03 Ci 2.16E-04 Unidentified Total for Period L

C1 2.3)E-03 3.67E-02 l

l C1 l

C1 C1 C1

.l l

Ci I

i 1

l l

l 1

G1 l

C1 l

l C1 I

I i

I C1 l

l t

Ci l

l L

C1 l

C1 l

l Ci l

l l

l C1 t

C1 Ci

• Iodine found on the articulate filter preceding the charcoal absorber.

O 1578 056

TABLE 2A EFFLUENT AND UASTE DISPOSAL SEMI /GNUAL REPORT (YEAR)1977 UQUID EFFLUC'TS-SU:ttATION OF ALL PILEASES Unit Quarter Quarter Est. Total Error, %

ist 2nd Fission md activation products A.

1.

Total release (not includinS Ci --

4.19E-01 1.86E-00 1.15E+01 tritium, cases, alohn) 2.

Average diluted concentration uCi/ml 1.13E-08 2.43E-08 during period 2.10E00 9.3E00 3.

Percent of applicable licit B.

Tritiu:2 1.

Total release ci 1.62E00 2.08Em

1. 33Em1 2.

Average diluted concentration uCi/ml 4.36E-08 2.7 2E-08 during ceriod 3.

Percent of apolicable limit

1. 46E-03 9.07E-04 C.

Dissolved and entrained cases Ci 1.19E.42 9. 3 8E-02 1.7SE+n, 1.

Total release Average diluted concentration uCi/ml 2.

3.21E-10 1.23E- 09 during period 3.

Percent of acolicable limit 1.07E-02 4.10E-02 D.

Gross alpha radioactivity ci m-7.11r_05 0'2.52E-05 1.22Em1 1.

Total release Volume of vaste released (prior to liters 5309314

,11245492 5.66E00 E.

dilution) liters F.

Volume of dilution uater used 3.71E+10 7.65E+10 1.10E+01 during period 1578 057

g TABLE 2B EFFLUENT AND k'ASTE DISPOSAL SEMIANNUAL REPORT (YEAR)1977 LIQUID EFFLUENTS Wi t-Ouarter ovinrte-onarrer oiinvrer Nuclid,es Releas'd Ci 3.03E-04 1.82E-03 strontium-8 L _

C1 l

1 ?ar ns 1 64F n1 strontium-90 7.41r-01 6.41r-02 C1 l

cesium-134 1 2.74E-01 Ci 1.ggE-02 cesium-137 4.12E-01 Cl-l I 3.86E-02 1

__ iod in e-131 l.01E-02 6.69E-02 I

Ci 1

cobalt-58 cooalt-60 C1 1 lic n?

A snr n?

iron-59 i

C1 L

I 2.05E-03 6.06E-02 I

'l I

1 AAF n1 9 asr_no zine-65 l

Ci l

3_7gv_n?

1 Asr n1

.,., y,,,,, s t I

1 9 977 n>

'9 mor_ni chromin~-51

(

C1 l

7.11r no s R1r nq zircon 4n -ninhin -os 1.35E-03 5.55E-03 I

'l

_molvbdenum oo

'5.94E-03 i

C1 1 lor n, technetium-99m l

C1 l

<m

- I s ?qv-na ba rium-I nn eh a nn--160 l

Ci l

j l < MDA Io.697-OR

__ cerium-14_1 I

6.?nt n? I 8.05E-04 C1 g

9.56E-02 l1.70E-03 f

1. 1on*f,p-1R C1 l

i 6.65E-02 lo A4F n9 cooper-64 Cl I

Ci l

l g_qq7_n1 l1 1 >r_n >

enafu -24 arsenic-76 l< m Ci I

A oce_nr iodine-132 Cl l

I 6 1Re nq I? 01F 0?

iodine-133 See tablei23-1 Ci i

J unid entified l See tablei2B-1 l

C1 l

Total for ne*4n,a (akr.. 3 l-I 7.6 At nq ' R nsv-n?

1 ci venor-133

! 2.31E-03

'8.50E-01 1

i C1 xenon-135

<MDA l1 1RF na Ci

'krVoton See Table ;ZE-1 Ci Total for period 1578 058 O

TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)1977 LIQUID EFFLUENTS Nuclides Released (

nn'ei Unie Ouarter Ouarter ounreer ni,,re,y U1 1 799-01 1.71E-03

-,c,noe.

A Ci l

l 8.15E-04 6.39E-03

,,24-m-,

199 C1 l

i 4.7 3E-01

'1.08E-03 antimony -124 Ci l

l 1 9'F-04

! ? 879-04

,'< nki n 0 7 l

Cl I 1.67E-05 3.95E-04 cee4"- -116 5.16E-04

< MDA C1 rhodium-106 i

C1 4.53E-05 1.04E-04 vetrium-91m strontium-91 i

C1 l

3.44E-05 l< MDA l 4.11E-04 l < MDA cesium-138 i

L1 I 3.32E-06 l< MDA Ci te11urium-132 barium-139 i

C1 j

1.31E-04 1.57E-04 1 00r-05 H 6.23E-05 l

C.

cerium-139 Cl l

I 7.44E-06 i 3. 57E-03 cerium-144 cobalt-57 l

C1

< MD A 7.18E-06 sodium-22 l

Ci

< MDA 47.55E-05 zinc-69m l

C1

).< MDA l4.66E-07

( < MD A I1.51F-05 Ci i

tin-117m l < MDA l3.06E-07 o

Ci I

nickel-65 C1 l

l l < MDA l5.68E-05 mercury-203 C1 l

1. < M DA i1.43E-05 strentium 02 Ci l

}

l C1 I

i 3.15E-02 11.71E-01 C1 l

l Unidentified Total for period l

C1 l

l l 4,19p-01 j1.867 00 l

Ci l1 Elv nA 0.76E-04 l

Arton-41

! 1.19E-02 7.1RE-02 I

C1 Tn *3,1 fn* n-winA ci 1578 059

Minimum det'ectable activity in pCi/ml for 2500 sec. count time for radionuclides not detected.

h Liquid Release Cesium -138

7. 23E- 08 Cobalt -57

6. 44E- 08 Mercury -203

6. 93E- 08 Nickel -65

1. 94E-07 Rhodium -106 5.12E-07 Sodium -22 6.43E-08 Strontium -91 1.45E-07 Strontium -92 1.71E-08 Tellurium -132 1.87E-07 Tin -113 1.88E-08 Zinc -69m 5.59E-08 dissolved and entrained gases xenon -131m 3.04E-06 Krypton -85m 6.72E-08 II.

Gaseous Release (uCi/cc)

(a) Nobles Krypton -85 5.40E-06 Krypton -85m 1.68E-08 Krypton -88 6.05E-08 Xenon -135m 2.87E-08 Xenon -138

1. 85E-08 1578 000 O

(b) Particulates Yttrium -88 1.54E-14 Zirconium-Niobium-97 3.49E-14 Cadmium -109 2.47E-13 Cesium -136 2.15E-14 Cerium -139 1.26E-14 Cerium -144 1.05E-13 Barium-Lathanum -140 6.79E-14 Molybdenum -99 4.96E-14 III 1578 061

. ~

TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)1977 SOLID WASTE AND IRRADIATED FUEL SHIPMEh*IS A.

Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel) 1.

Type of Waste Unit 6-month Est. Total period Error, %

a.

Spent resins, filter sludges, evaporated m

1.08E03 bottoms, etc.

Ci 5.55E02 1.50E01 b.

Dry compressible vaste, contaminated mJ 2.54E02 eouip., etc.

Ci 4.91E00 2.00E01 c.

Irradiated components, control mJ 1.10E01 rods, etc.

Ci 6.20E02 1.50E01 m3 d.

Other (describe)

Ci 0.00E00 0.00E00 2.

Estimate of major nuclide composition (by type of waste)

A+B Chromium - 51 3.50E01 Manganese - 54 1.98E01 Cobalt - 58 9.04E00 Cobalt - 60 1.39E01 Iron - 59 2.96E00 Zine - 65 4.91E00 Todine - 131 2.13E00 cesium - 134 3.31E00 Cesium - 137 9.00E00 i

C Zirconium - 95 3.04E01 l

Niobium - 95 3.04E01 Mancanese - 54 7.84E00 Colbalt - 58 2.08E00 Colbalt - 00 1.78E01 41nc - os 8.53E00 -

Indium 113M 3.03E00 l

D None l

3.

Solid Waste Disposition Number of Shioments Mode of Transoortation Destination 99 Sole Use Vehicle Chem-Nuclear Systems, Inc'.

Barnwell, S. C.

B.

Irradiated Fuel Shipments (Disposition).

Number of Shioments Mode of Transnortation Destination 4

1578 '062-

WORST CASE SITE DOSES RELATED TO AIRBORNE ICDINE RELEASES Thyroid Dose Due to Inhalation, mrem /6 Months at Site Boundary

~

1 Year Old 1.06 E-01 4 Years Old 1.03 E-01 14 Years Old 6.83 E-02 Adult 1.01 E-01 Thyroid Dose Due to Milk Pathway mrem /6 Months at Nearest Cow 1 Year Old 1.65 E+01 4 Years Old 6.80 E+00 14 Years Old 2.36 E+00 Adult 1.92 E+00 Thyroid Dose Due to Eating Green Leafy Vegetables, mrem /6 Months at Worst Garden 1 Year Old 0.00 +00 4 Years Old 3.71 E-01 14 Years Old 2.16 E-01 Adult 4.41 E-01 1578 063

SUMMARY

OF DOSES DUE TO LIQUID RELEASES Dose Due to Eating Fish Caught in Discharge Canal b' hole Body 2.60E-05 mrem /6 Months G. I. Tract 1.46E-04 mrem /6 Months Thyroid 1.96E-04 mrem /6 Months Bone 1.72E-05 mrem /6 Months Shoreline Sediment Dose Along Discharge Canal 2.37E-05 mrem /6 Months Ocean Swimming Dose 2.13E-07 mrem /6 Months Radiological Impact on Man from direct radiation from the facility is negligible based on the results from evnironmental TLD's.

O 1573 064

SKIN DOSE, mrem /6 lionths AIR SUBMERSION i BRUNSWICK STEAL' -.ECTRIC PLANT h

January to ay 30, 1977 SECTOR

.5 1.5 2.5 3.5 4.5 7.5 15 25 35 45 S

1.588E+00 6.651E-01 5.497E-01 4.480E-01 3.715E-01 2.382E-01 1.190E-01 6.826E-02 4.647E-02 3.455E-02 SSW 9.302E-01 6.277E-01 5.785E-01 4.872E-01 4.089E-01 2.629E-01 1.295E-01 7.346E-02 4.987E-02 3.711E-02

-SW 8.552E-01 6.522E-01 5.524E-01 4.491E-01 3.711E-01 2.374E-01 1.196E-01 6.955E-02 4.771E-02 3.565E-02 WSW 8.149E-01 9.181E-01 9.127E-01 7.824E-01 6.609E-01 4.267E-01 2.083E-01 1.165E-01 7.796E-02 5.725E-02 W

6.458E-01 9.145E-01 9.175E-01 7.887E-01 6.651E-01 4.255E-01 2.042E-01 1.131E-01 7.523E-02 5.506E-02 WNW 5.3))E-01 5.163E-01 4.924E-01 4.232E-01 3.607E-01 2.398E-01 1.229E-01 7.101E-02 4.832E-02 3.578E-02 NW 5.908E-01 5.849E-01 5.407E-01 4.523E-01 3.769E-01 2.386E-01 1.144E-01 6.350E-02 4.235E-02 3.103E-02 NNW 4.912 E-01 5.071E-01 4.978E-01 4.296E-01 3.656E-01 2.405E-01 1.213E-01 6.971E-02 4.761E-02 3.550E-02 N

4.950E-01 5.184E-01 5.482E-01 4.824E-01 4.127E-01 2.703E-01 1.328E-01 7.423E-02 4.962E-02 3.641E-02 NNE 1.086E+00 1.077E+00 1.059E+00 8.955E-01 7.458E-01 4.647E-01 2.151E-01 1.161E-01 7.636E-02 5.550E-02 NE 1.790E+00 1.915E+00 1.791E+00 1.486E+00 1.225E+00 7.518E-01 3.429E-01 1.837E-01 1.200E-01 8.680E-02 ENE 1.648E+00

1. 345E+00 1.426E+00 1.271E+00 1.098E400 7.292E-01 3.610E-01 2.020E-01 1.350E-01 9.896E-02 E

2.021E+00 8.075E-01 7.094E-01 6.037E-01 5.146E-01 3.439E-01 1.775E-01 1.030E-01 7.055E-02 5.266E-02 ESE 2.152E+00 9.972E-01 8.367E-01 6.844E-01 5.659E-01 3.569E-01 1.718E-01 9.593E-02 6.429E-02 4.736E-02 SE 1,997E+00 9.551E-01 7.552E-01 6.102E-01 5.038E-01 3.195E-01 1.557E-01 8.818E-02 5.968E-02 4.431E-02 SSE 1.874E+00 1.084 E+00 8.955E-01 7.178E-01 5.843E-01 3.570E-01 1.654E-01 9.942E-02 5.989E-02 4.376E-02 MAXIMUM.0FFSITE AIR SUBMERSION SKIN DOSE, mrem /6 Months 2.15 E00

~

CO CD LJ1

AIR SUBMERSION Wil0LE I?ODY D0SE, mrem /6 Months BRUNSWICK STEAM 'ECTRIC PLANT h

January to

_.y 30, 1977 SECTOR

~

.5 1.5 2.5 3.5 4.5 7.5 15 25 35 45 S

6.775E-01 3.350E-01 2.908E-01 2.408E-01 2.013E-01 1.304E-01 4.432E-02 3.790E-02 2.587E-02 1.927E-02 SSW 3.989E-01 3.307E-01 3.159E-01 2.688E-01 2.266E-01 1.466E-01 7.249E-02 4.123E-02 2.803E-02 2.087E-02 SW 3.955E-01 3.528E-01 3.053E-01 2.499E-01 2.071E-01 1.331E-01 6.727E-02 3.918E-02 2.691E-02 2.011E-02 WSW 3.733E-01 5.038E-01 5.100E-01 4.392E-01 3.717E-01 2.406E-01' 1.177E-01 6.585E-02 4-409E-02 3.239E-02 W

2.952E-01 5.054E-01 5.144E-01 4.438E-01 3.748E-01 2.402E-01 1.154E-01 6.397E-02 4.257E-02 3.117E-02 WNW 2.374E-01 2.805E-01 2.736-E01 2.366E-01 2.022E-01 1.350E-01 6.934E-02 4.010E-02 2.730E-02 2.023E-02 NW 2.886E-01 3.232E-01 3.028E-01 2.543E-01 2.165E-01 1.347E-01 6.463E-02 3.591E-02 2.396E-02 1.756E-02 NNW 2.185E-01 2.760E-01 2.770E-01 2.404E-01 2.052E-01 1.354E-01 6.842E-02 3.938E-02 2.691E-02 2.007E-02 N

2.119E-01 2.808E-01 3.048E-01 2.700E-01 2.316E-01 1.522E-01 7.493E-02 4.191E-02 2.803E-02 2.057E-02 NNE 4.756E-01 5.848E-01 5.883E-01 5.005E-01 4.178E-01 2.611E-01 1.211E-01 6.547E-02 4.307E-02 3.132E-02 NE 8.131E-01 1.048E-00 9.983E-01 8.322E-01 6.875E-01 4.229E-01 1.932E-01 1.036E-01 6.768E-02 4.897E-02 ENE 7.029E-01 7.195E-01 7.879E-01 7.080E-01 6.137E-01 4.092E-01 2.031E-01 1.138E-01 7.611E-02 5.583E-02 E

8.581E-01 4.032E-01 3.750E-01 3.251E-01 2.796E-01 1.891E-01 9.841E-02 5.738E-02 3.939E-02 2.945E-02 ESE 9.631E-01 5.181E-01 4.507E-01 3.730E-01 3.102E-01 1.971E-01 9.540E-02 5.344E-02 3.588E-02 2.547E-02 SE 9.355E-01 5.051E-01 4.102E-01 3.347E-01 2.776E-01 1.772E-01 8.682E-02 4.933E-02 3.595E-02 2.486E-02 SSE 8.475E-01 5.748E-01 4.881E-01 3.946E-01 3.225E-01 1.981E-01 9.220E-02 5.052E-02 3.351E-02 2.451E-02 Ln

~sj MAXIMUM OFFSITE AIR SUBMERSION U110LE BODY DOSE, mrem /6 Months 1.04'8 E00 CO CD C7s C3%