Text

Semiannual Radioactive Effluent & Waste Disposal Rept, Jan-June 1979
	ML19290A082
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	06/30/1979
From:	; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
References
	NUDOCS 7909100487
	Download: ML19290A082 (55)
	v • d • e

CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT t

4 HADDAM, CONNECTICUT

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SE'1IANNUAL RADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT FOR THE PERIOD OF JANUARY 1, 1979 TO JUNE 30, 1979 DOCKET No. 50-213 LICENSE DPR-61

? $ $ & Gi Q 'L 2043 187

~

7 000100 W7.1

TABLE OF CONTENTS PAGE Supplemental Information.

1-7 Gaseous Effluents - Summation of all Releases.

8 Gaseous Effleunts - Mi.;ed Mode Release (Partially Elevated and Partially Ground).

9 Liquid Effluents - Summation of All Releases.

10 Liquid Effluents.

11 Solid Waste.

12-13 Off-Site Dose Estimates.

14-21 Meteorological Data.

22-53 2043 iBB e

i

n.)

REGULATORY LIMITS y

Specifications for Gaseous Waste Effluents (1)., The release rate limit of noble gases from the site shall be:

1Qiy 94 Ety + 460 T1[

< 1 iwhere Qy 7 = release rate from all roof and unit vents in Ci/sec (ground release) i

= the 4th individual nuclide Tiy = the average gama energy per disintegration for nuclh'e i Tig = the average beta energy per disintegration for nuclide 1 (2)

The release rate limit of all radiciodines and radioactive materials in particulate form with half-lives greator than eight days, released to_the environs.as part of the gaseous wastes from the site shall,be:

1.2 X 106 gy < )

where Qv is defined above.

(4)

The average release rate of noble gases from the site during any calendar quarter shall be:

[ Tia 1450 Qi_v 1 1 3

and.

[ ty

590 Qi.v 1 1 3

(4)

The average release rate of noble gases from the site during any 12 consecutive months shall be:

{Eg 2900 Qiv 1 1 i

1 and.

{Ety 1180 Qiv 1 1 1

(5)

The average release rate of all iodines and radioactive materials in particulate form per site with half-lives greater than eight days during any calendar quarter shall be:

1.5 X 108 gy

)

2043 189 (6 )

The average release rate of all iodines and radioactive materials per site in particulate form with half-lives grcater than eight -

days during any period of 12 consecutive months.shall b,:

3.0 X 108 Qv i 1

~

The amount of iodine-131 rele'ased during any calendar quarter shall 0 ) i*not exceed 2 Ci/ reactor.

@)

The amount of iodine-131 released during any period of 12 consecutive months shall not exceed 4 Ci/ reactor.

Should any of the conditions of (1). (2) or (3) listed below exist, the licensee shall make an investigation to identify the causes of the release rates.

define and initiate a program of action to reduce the release rates to design objective levels listed in Env. Tech. Spec., Section 2.4 and report these actions to the Commission within 30 days from the end of the quarter during which the releases occurred.

(1)

If the average release rate of noble gases from the site during any calendar quarter is:

1

}Ts i

5800 Qty or,

[Ety 2400 Qijg 1

1 (2)

If the average release rate of all iodines and radioactive materials in particulate form per site with half-lives greater than eight days during any calendar quarter is':

5.9 X 108 gy > 1 (3)

If'the amount of iodine-131 released during any calendar quarter is greater than 0.5 Ci/ reactor.

2043 190 t

=

M*

9 Specifications for Liquid Waste Ef fluents The concentration of radioactive materials released in lid 64d waste effluents at the site shall not exceed the values specified in 10 CFR Part 20 Appendix B.

Table II, Column 2, for unrestricted areas.

The cumulative release of radioactive materials in liquid waste effluents, excluding trition and dissolved gases, shall not exceed 10 Ci/ calendar quarter.

The cumulative release of radioactive materials in liquid waste effluents, excluding tritium and dissolved gases, shall not exceed 20 Ci in any 12 consecutive months.

The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process radioactive liquid wastes prior to their discharge when the projected cumulative release could exceed 1.25 Ci/ calendar quarter, excluding tritium and dissolved gases.

The maximum radioactivity to be contained in any liquid radwaste tank that can be discharged directly to the environs shall not exceed 10 C1, excluding tritium and dissolved gases.

7.f the cumulative release of radioactive materials in liquid effluents, excluding tritium and dissolved gases, exceeds 2.5 Ci/ calendar quarter, the licensee shall make an investigation to identify the causes for such releases, define and

' initiate a program of action to reduce such releases to the design objective levels listed in Section 2.4, and report these actions to the Commission within 30 days from the end of the quarter during which the release occurred.

s m

=

M*

O 6

/

3_

2) Maximum Permissible Concentrations (Micro curies /ml) a.

Fission and Activation Gases Ns Kr - 85 3.0 E-07 Kr - 85m-1.0 E-07 Kr - 87 2.0 E-08 Kr - 88 2.0 E-08 Xe - 133 3.0 E-07 Xe - 135 1.0 E-07 Xe - 135m 1.0 E-06 Xe - 138 1.0 E-06 Ar - 37 1.0 E-04 b.

Iodines I - 131 1.0 E-10 1 - 133 4.0 E-10 I - 135 1.0 E-09 c.

Particulates, Half-Lives > 8 Days Sr,89 3.0 E-10 Sr - 90 3.0 E-ll Cs - 134 4.0 E-10' Cs - 137 5.0 E-10 Ba - 140 1.0 E-09 La - 140 4.0 E-09

\\

d.

Liquid Effluents Sr - 89 3.0 E-06

~

Sr - 90 3.0 E-07 Cs - 134 4.0 E-05 Cs - 137 2.0 E-05 I - 131 3.0 E-07 2043 192 Liquid Effluents (Cant.)

~

Co - 58 9.0 E-05 Co -_60 3.0 E-05 Fe - 59 5.0 E-05 2n - 65 1.0 E-04 Mn - 54 1.0 E-04 Cr - 51 2.0 E-03 2r - 95 6.0 E-05 Hb - 95 1.0 E-04 Ho - 99 4.0 E-05 Tc - 99m 3.0 E-03 Da - 140 2.0 E-05 La - 140 2.0 E-05 '

Ce - 141 9.0 E-05 Eu - 154 2.0 E-05 Be - 7 2.0 E-03 Ru - 106 1.0 E-05 Ag - 11,0m 3.0 E-05 Sb - 124 2.0 E-05 Sb - 125 1.0 E-04 Co - 57 4.0 E-04 Xe - 133 3.0 E-06 Xe - 135 3.0 E-06 Ar - 37 3.0 E-06 s

Kr - 85 3.0 E-06

-2043 i93

.s.

2nd Quarter;

1st Quarter E Seta E Gamma E Seta E' Gamma

3). Average. Energy (E)

'O.193 Mev 0:056 Mev 0.2'69 Mev

' O'.1'24' Mev,.

i

.r-For Fission and

\\

Activation Cases Heasurements-and 17proximation of Total Radioactivity

4) a.

Fission and Activation Gases: An in-line G. M. detector monfl ot s stack effluent. Gas samples are collected on the stack and ala sent to a off site lab for low level fission and activation gas analyses.

b.

Todines: Continuous in line charcoal filter on main stack effluent. Charcoal

. filters are then analyzed for iodines.

c.

Particulates: Continuous in line particulate filter on main stack effluent.

Particulate samples are then counted for Gross B-2 Ueekly samples

~~

anesent to a off site lab for analysesof Low level gamma emitters.

A montL'y composite is made from these weekly samples. The monthly composite is checked for gross alpha and 89Sr 9USr.

d.

Liquid Effluents:

In line-scintillation detector monitors waste liquid being released. Prior to discharge a sample is tak.cn. Principal gamme emitters, gross 8-y and tritium analysis are performed. Weekly composites are prepared and sent to a off site labortory. Principal gamma emitters are determined. A monthly composite is made from the weekly samples.

Gross Alpha, 89Sr and 90Sr are determined. One batch samole per month is sent out for determinatior. of dissolvedand entrained gases.

d i

D@(D t

2043 194

4 0

'.s.

f

5) Batch Releases a.

Liquid

1) Number of batch releases:

1.05E+02

2) Total time period for batch releases: 1.29E+03 Hours

3) Maximum time period for a batch release:5.36E+01 Hours

4) Average time period for batch releases: 1.13E+01 Hours

5) Minimum time period for a batch release:1.33E+0QP.ours i

6) Average stream flow during periods of 1.58E+04 Cubic feet release of effluent into a flowing per second stream:

b.

Caseous l'

1) Number of batch releases: 3.30E+01

2) Total time period for batch releases: 1.80E+02 Hours

3) Maximum time period for a batch release:7.80E+01 Hours

4) Average time period for batch releases: 1.80E+91 Hours

5) Minimum time period for a batch release: 6.67E-01 Hours

6 Abnormal Releases None a

2045 19r:)

s b

L e

9 7-

i, I

/

EFFLtftNT AND WASTE OISPOSAL SEMI-ANNUAL REPORT

- 1979

]

GME0US EFFLUENTS-SUMMATION OF ALL RELEASES

I_

UNIT QUARTER QUARTER E57. TOTAL I ',

1 1st 2nd ERROR %

i

+

((~ \\d. F 3SION & ACTIVATI0ft GASES s - n3 Ci 4.08E+03 4.97E+01 1.40E+01 T. Total release l

~

2. Average rehm rate for period uCi/sec 5.24E+02 6.32E+00 x

3. Percent of 7echnica? Specifica-1.46E+01 2.51E-01 s

.N.

tion Ifmit B.

10 DINES

?.

1. Total iodine - 131 l

Ci '

4.31E 02

<1.00E-12 1.32E+01

\\)

3.54E-03

< 2.4 5E-05 1

2. Average release rate for period uCi/sec_

)

3. Percent of Technical Specific.a-s 2.16E+0C 0.00E+00 tion limit g

1 A.'

C.

PARTICULATES I

.s 1'

.i

1. Particulates.<i';h nulf-lives s

1.95E-04 1.68E-04 1.46E+01 i

> 8 days

' Ci r

2. h:trage release' rate for period uCi/sec 2.50E-05 2.14E-05

%.1

3. Percent of Te:hnical Spectfica-3.75E-01 3.21E-01 tio_n

4. Gross alpha ra9'ioactivity C5 4.42E-08 6.79E-07 z

J D.

TRITIUM '

C 3.00E+01 9.92E+01 7.80E+00

1. Total release Ci 3.86E+00 1.26E+01

2. Avsale release rate for period uCi/sec R

3. Percent of Technical Specifica-7.85E-2 2.57E-1 I.

l ti:,n lir..it l

e

(

l 2043 196 3

4, 1

2 8-

.i

,i

EFFLUENTANDWASTEDISPOSdt$r$le-ANNUAL REPORT s.u...

r... i s.o i

1979.

GASEOUS EFFLUENTS MIXED MODE RELEASE CONTINU0US MODE BATCH MODE NUCLIOES_ RELEASED UNIT Int QUARTER 2nd'- QUARTER ist QU_A_RTER 2nd QUARTER

1. FISSIO?; GASES e

Krykon-85 Ci 7.43E+01 9.02E+00 4.33E&01 1.74F-02 _

Kryp, ton-85m Ci

<1.00E-04

<1.00E-04 2.14E-01 2.26E-01 Krypton-8/

Ci

<1.00E-04

<1.00E-04 4.31E-01 5.22E-01 yyp_ ton, _88 Ci

<1.00E-04

<1.00E-04 4.73E-01 4.90E-J1 Xenon-133 Ci 2.19E+03 2.22E+01 1.64E+03 2.56E+00 lenon-)35 Ci 1.83E+01

<1.00E-04 1.69E+00 1.72E+00,

Xenon-135m Ci

<1.00E-04

<l.00E-04 1.76E-01 2.45E-01

. Xenon-138 Ci

<1.00E-04

<1.00E-04 7.51E-01 1.20E+00 Others sMcify Carbon-14 Ci 9.82E400 9.97E+00 4.83E-01 5.80E-02 3H.

Ci 2.99E+01 9.92E+01 7.76E-02 2.50E-02 Ci 5.71E+01

<1.00E-08 5.29E-01 8.77E-02 Argon _37 r

Arron 41

_Ci

<l.00h-04

<l.00E-04 2.41E-03 1.36E-02

_Ci

/. m +00

<l.00E-06 3.00E+01 8.40E-01 Xenon 131M_

1.78E+00

<1.00E-06 5.13E+00 4.30E-02 Xenon 133M Ci Ci i

<1.uJt-u*

<l.00E-04 3.01E-01 8.62E-01

~

Xenon,1,37 2.39E+03 1.40E+02 1.72E+03 8.41p+00

_ _.Jlo tal.Ep r _ P.s r i mi lodine-131 Ci 4.31E-02

<1.00E-12 10 dine-133 Ci 2.41E-03

<1.00E-10 lodine-135 Ci 3.74E-03

<1.00E-10 T otal'Toi' per_iod Ci 4.93E-02

3. PARTICULATES Strontium-89 Ci 1.64E-06 1.39E-06 Strontium-90 I

Ci 6.43E-0/

6.09E-07 Cesium-134 Ci 3.20E-05 3.70E-05 Cesium-137 Ci 2.90E-OS 4.03E-05 Bari um-l ant ha nuin-140 Ci

<1.00E-13

<5.00E-14 Cerfum-144 Ci 3.02E-05 3.53E-05 1.44E-05 Cobalt-60 C:

2.23E-05

'<5.00E-14 M d nese-54 Ci _ <1.00E-14 CI 2.23E-06 1.31E-06 Qbh-g_

Cerium ]41 Ci 6.86E-06 2.40E-06 R_6thenium lh3 C1 2.04E-05 8.21E-06 i

/.irconium/ 4 oht um 'h ri 2.02E-05 2.32E-05 Ruthenium 106 Ci 2.04E-05 3.49E-06

Reported under continuous mode W

6

EFFLUENT AftD WASTE DISPOSAL SEMI-AliNUAL REPORT

- 1979-Ll_ quit) EFFLUENTS-SUMMATION OF ALL RELEASES UN!!

QUARTER

. QUARTER EST. TOTAL 1

1st

}nd ERROR ".

A. FISSION AND ACTIVATION PRODUCTS 1.Totalreiease(notincinding tr_itium a ases, alpha)

Ci 6.06E-01 1.38E-01 1.15E+01

2. Average, diluted c~oncentratien 4.73E-09 7.15E-10 during period pCi/m1_

3. Percent of appliceble limit 6.06E+00 1.38Et00 B. TRITIUM 1.70E+03 1.29E*02 3.55E+00

1. Total release Ci

2. Average diluted concentration 1.32E-05 6.68E-07 during period pCi/ml

3. Percent of apolicable limit 4.42E-01 2.23E-02 i

C. DISSOLVED AND ENTRAINED GASES

1. Total release Ci 3.35E-01 6.75E-04 1.89E+01

2. Average diluted concentration 2.62E-09 3.50E-12 during period pCi/ml

3. Percent of applicable limit 8.72E-02 1.17E-04 D. GROSS ALPHA RADI0 ACTIVITY

1. Total release Ci

__8.44E-03

. 30E-03 8.00E+00 E. \\'olume of waste released (prior to dilution)

Liters 3.24E+06 1.41E+07 3.00E+00

\\

F. Volume of dilution water used during period Liters 1.28E+11 1.93E+11

?.60E+00 g

043 198 CONNECTICUT YANKEE EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT ' - 19h LIQUID EFFLUENTS

~

CONTINUOUS MODE BATCH MODE QUARTER QUARTER QUARTER QUARTER NCUI.lDES RELEASED UNIT 1st 2nd 1st l

2nd

. _St rontium-89 Ci

<4.00E-08

<3.00E-08 5.41E-03 6.05E-04 Strontium-90 Ci

<1.00E-08

<7.00E-09 2.37E-03 3.65E-04

-'eTium-134 Ci 8.03E-04 3.83E-03 1.98E-02 2.97E-03 C

Cesiym-137 Ci 9.98E-04 6.27E-03 2.00E-02 3.17E-03 lodine-131 Ci 6.23E-04

<2.uoE-07 6.46E-02 1.84E-03 CobaIt-58 Ci

<1.00E-08

<2.00E-08 1.04E-02 1.35E-03 Cobalt-60 Ci

<1.00E-08

<2.00E-08 5.15E-02 1.78E-02

_ Iron-59 Ci

<5.00E-07

<5.00E-07 Zinc-65 Ci

<5.00E-07

<5.00E-07 Mangane_se-54 Ci

<1.00E-08

<5.00E-07 2.13E-03 8.60E-05 Chromium-51 Ci

<5.00E-07

<5.00E-07 6.56E-03

<5.00E-07 Zi rconi tra-niobium-95 Ci 2.26E-04

<2.00E-08 1.12E-01 2.58E-02 Molybdenum-99 Ci

<5.00E-07

<5.00E-07 Technetium-99m Ci

<5.00E-07

<5.00E-07 Bari um-l a nthanum-140 Ci

<5.00E-07

<l.00E-07 4.61E-04

<3.00E-07 Cerium-141 Ci

<l.70E-08 l

<3.00E-08 4.90E-02 3.24E-03 Europium-154 Ci

<5.00E-07

<5.00E-07 Ocryllium-7 Ci

<1.00E-07

<2.00E-07

<1.00E-07

<5.00E-07

~

ium-144 Ci

<4.00E-08

<7.00E-08 1.85E-01 5.69E-02 Cer Ruthenium-106 Ci

<1.00E-07

<1.00E-07 1.84E-02 5.30E-03 Silver-110m Ci

<5.00E-07

<5.00E-07 Ruthenium - 103 Ci

<1.00E-08

<2.00E-08 5.5bE-02 8.42E-03

~ Antimony-125 Ci

<5.00E-07

<5.00E-07 1

Cobalt-57 Ci

<5.00E-07

~

Igini-T~ig Ci

<5.00E-07

__Tr*al for Period (above)

Ci 2.65E-03 1.01E-02 6.03E-01 1.28E-01 XenoE133 Ci

<1.00F-os

<1.00E-05 q _ up_n1 6.72E-04 Xenon-135 Ci

<1.00F-os

<1.00E-05 g nv_nc

<1.00E-05 Argon-37 Ci

<1.00E-09

<1.00E-08

<1.00E-09

<1.00E-08 Krypton-85 Ci 1.21E-05

<1.00E-09 2.67E-05 3.06E-06 Tritium Ct 1.69E-01 2.07E-01 l 1.70E+03 1.29E+02 Il j

i

=

A DQ{D 2041 199

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-MONTH EST. TOTAL 1.

TYPE OF WASTE UNIT PERIOD ERROR %

a.

Spent resins, filter m3 1.06E+02 sludges, evaporator bottom, etc.

C1 1.94E+02

-+ 1.0 E+01 4

b.

Dry compressible m3 5.58E+02 Waste, Contaminated

+ 1.0 E+01 equip., etc.

Ci 9.06E+01 c.

Irradiated components N/A N/A N/A 2.

ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BT TYPE OF WASTE) a.

Cs-137 3.50E+01 Cs-134 3.20E+01 Ce-144 1.50E+01 Ce-141

5. 00E+00 Nb-95 5.00E+00 Zr-95 4.00E+00 Co-60 2.00E+00 Co-58

2. 00E+00 b.

Ce-144 3.00E+01 Cc-14]

2.00E+01 Nb-95 1.00E+01 Zr-95 1.00E+01 Co-60 5.00E+00 Cs-134 5.00E+00 Cs-137 5.00E+00 Ru-103 5.00E+00 La-140 5.00E+00

>00 m047 c

Ba-140 5.00E+00

'h l

.I WW J-.d..

_a 3.

SOLID WASTE DISPOSITION NUMBER OF S111PMENTS MODE OF TRANSPORTATION DESTINATION 36 Truck Barnwell, S.C.

B.

_ IRRADIATED FUEL SHIPMENTS (DISPOSITION) - None 2043 201 e

0 i

0FFSITE DOSE ESTIMATES In accordance with the requirements of Section 5.6.1.b of the Environ-mental Technical Specifications and Regulatory Guide 1.21, the off-site dose to humans from the gaseous and liquid radioactive effluents of Connecticut Yankee have been estimated.

These estimations are performed using measured effluent data, measured meteorological data, and calculational models developed by the U.S.

Nuclear Regulatory Commission.

The dose estimates generally tend to be conservative due to the use of conservative assumptions in the calculational models. More realistic estimates of the off-site dose are obtained by analysis of the environ-mental monitoring data.

t. comparis,on of the doses estimated by each of the above methods will be presented in the Annual Radiological Environ-mental Monitoring Report due to be published March 31, 1980.

1.

Dose Models a.

Airborne Effluents Maximum individual and population doses due to the release of noble gases, radioiodines and particulates were calculated using the computer code CASPAR( }.

2043 202 3. _.

The code uses the semi-infinite cloud model to implement the dose models of U.S.N.R.C. Regulatcry Guide 1.109 (October,1977).

The values of average relative effluent concentration (X/Q) and average relative deposition (D/Q) used in the CASPAR code were generated using a meteorological computer code which implements the assumttions given in Section C of NRC Regulatory Guide 1.111, " Methods for

~

Estimating Atnospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors".

Releases from the CY,175 foot stack were considered as a mixed mode release (partially elevated and partially ground). The Pasquill stability classes were determined using the temperature gradient between the 33 foot and 196 foot levels of the meteorological tower.

The CASPAR code was run separately for continuous releases (building ventilation) and batch releases (waste gas tanks).

The resulting doses were then summed to determine the total dose.

2043 203 o

b.

Liquid Effluents Maximum individual and population doses due to the release of radioactive liquid effluents were calculated using the computer code LADTAP( }.

The code implements the dose,models and parameters given in Regulatory Guide 1.109 (October 1977).

2.

Results a.

Airborne Effluents The calculated doses are presented in Table 5.1.

For population doses, the GASPAR code calculates the dose to the whole body, GI-tract, bone, liver, kidney, thyroid, lung and skin from each of the following pathways:

direct exposure from the plume, direct exposure from ground deposition, inhala-tion, vegetation, cow's milk and meat.

The values presented in the attached table are a total from all pathways, but only the whole body, skin and thyroid dose p} 20k are presented.

For the maximum individual, the GASPAR program calculates the dose to the same organs listed above for the following pathways:

direct exposure from the plume, direct exposure from ground deposition, inhalation, vegetation, meat, cow's milk and goat's milk. The doses are calculated for adults, teenagers, children and infants separately. Unless otherwise noted in the table the doses given are for adults.

For the pluta, ground deposition and inhalation pathways, the maximum individual dose is eplculated at the offsite location of maximum decayed X/Q where a potential for dose exists.

For the vegetation pathway the maximum individual dose is calculated at the vegetable garden of highest depleted X/Q.

For the meat, cow's milk and goat's milk pathuays, the calcu-lated dose is included as the maximum individuals dose only at locations and times where these pathways actually exist.

Doses were calculated at the cow farm and goat farm of maximum deposition. The doses presented in Table 5.1 are the maximum doses observed.

b.

Liquid Effluents The calculated doses are presented in Table 5.1.

20 0 205 _.-~.-.

The LADTAP code performs calculations for the following pathways:

fish, shellfish, algae, drinking water, irrigated food, shore-line activity, swimming and boating. At Connecticut Yankee, the algae, shellfish, drinking water and irrigated food pathways do not exist, and thus only the other pathways are included in the totals given in Table 5.1.

Doses are calculated for the whole body, skin, thyroid, GI-LLI, bone, liver, kidney, and lungs.

Table 5.1 presents the doses to the whole body, thyroid, and the maximum organ dose. The dose to all other organs was less than those values presented for the liver and gastro-intestinal tract.

Calculations are performed for adults, teenagers, children and infants separately. Unless otherwise noted in the table the doses given are adult doses.

3.

Analysis of Results The doses are well below permissable levels and are of no signifi-cance as far as effects on the general population. For perspective, the average whole body dose to an individual from natural background I3) radiation in the vicinity of Connecticut Yankee is about 40 millirem for a six month period as opposed to the average individual dose within 50 miles of the site of 0.00018 millirem from gaseous (j@

1 D

2043 206.. - - -

/

effluents and 0.00063 millirem from liquid ef fluents during the report period. The maximum individual dose of 0.3 millirem from gases or 0.41 millirem from liquids is approximately one percent of the background dose.

2043 207 O

REFERENCES (1)

GASPAR Dose Code, K. F. Eckerman, Radiological Assessment Branch, U.S. Nuclear Regulatory Commission, Wash. D.C. - Revised 2/20/76.

(2)

IADTAP - U.S. Nuclear Regulatory Commission; Washington, D.C.

(3)

Does not include an average additional dose of approximately 30 mrem due to internal radiation, fallout, etc.

2043 208

. m,.

e TABLE 5.1 Off-Site Dose Estimates Connecticut Yankee 1979 A.

Airborne Effluents Units Jan-Mar Apr-Jun 1.

Maximum Individual Dose M1111 rem a.

Whole Body 2.2(-1)a,b

7. 5 (-2) f b.

Skin

6. 6 (-1)b 1,9 (_1) f c.

Thyroid

1. 4 (-1) c 1.9 (-1) 8 2.

Population Dose 0-50 Miles Person-Rem a.

Whole Body

4. 5 (-1)

2. 2 (-1) b.

Skin 1.5(0) 2.7(-1) c.

Thyroid 7.6(-1)

2. 3 (-1) 3.

Average Dose 0-50 Miles Millirem a.

Whole Body 1.2(-4)

5. 7 (-5) b.

Skin 3.9 (-4)

7. 0 (-5 )

c.

Thyroid

2. 0 (-4)

6. 0 (-5)

B.

Liquid Effluents 1.

!!aximum Individual Dese M1111 rem a.

Whole Body 3.3(-1) 8.4(-2) b.

Max organ d 2.8(0)

1. 2 (-1)"

c.

Thyroid 7.6 (-2)

2. 2 (-3)

2.

Population Dose 0-50 Miles Person-Rem a.

Whole Body 1.9 (0)

4. 8 (-1) d b.

Max Organ 1.4 (1)

8. 0 (-1) c.

Thyroid 3.1(-1)

7. 9 (-3) 3.

Average Dose 0-50 Miles Millirem a.

Whole Body 5.0 (-4)

1. 3 (-4) d b.

Max organ

3. 7 (-3) 2.1 (-4) c.

Thyroid

8. 2 (-5) 2.1(-6)

2. 2 (-1) = 2. 2x10~ 1 a.

b.

At a location 0.8 miles SE c.

At the critical residence - 0.9 miles SE d.

!!aximum organ is the adult GI-LLI for the first quarter and the liver for the second quarter e.

Teenager dose - all other doses are adult doses.

f.

At a location 0.4 miles NNE g.

Child thyroid dose at the cri cical vegetable garden - 0.4 miles NNW

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WIND SPLLD/ WINO OlkELTION/ STABILITY JOINT FkEQUENCY DISTRIBUTION I NJ LEVEL =

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ML19290A082

Contents

Text

e.J l P

21 cts NO. UF VALIO NON-LA L M LL NLUF 6.t NT Wis/WS/DT = 2 t:92 f1Lt. LF MISSING WU/WS

a

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ML19290A082

Text

e.J l P

21 cts NO. UF VALIO NON-LA L M LL NLUF 6.t NT Wis/WS/DT = 2 t:92 f1Lt. LF MISSING WU/WS

a

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