Text

Semiannual Radioactive Effluent & Waste Disposal Rept, Jul-Dec 1979
	ML20126B075
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/31/1979
From:	; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
References
	NUDOCS 8003040203
	Download: ML20126B075 (58)
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SEMIANNUAL RADIOACTIVE EFFLUENT'AND WASTE DISPOSAL' REPORT

.FOR'THE PERIOD OF

-JULY 1, 1979 TO DECEMBER 31, 1979-

. . 1

. .. DOCKET No. 50-213' LICENSE'DPR-61 o

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3003040. 203 m k- . __f

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CONNECTICUT YANKEE ATOMIC POWER COMPANY llADDAM NECK PLANT llADDAM, CONNECTICUT I

1 SEMIANNUAL RADI0 ACTIVE EFFLUENT AND WASTE DISPOSAL REPORT l

FOR Tile PERIOD OF JULY 1, 1979 TO DECEMBER 31, 1979 DOCKET No. 50-213 o

LICENSE DPR-61.

t

TABLE OF CONTENTS 4

PAGE Supplemental Information . . . . . . . . . . . . . . . . . .

Gaseous Effluents - Summation of all Releases . . . . . . .

Gaseous Effluents - Mixed Mode Release (Partially Elevated and Partially Ground). . . . . . . . . . . . . . . . . .

Liquid Effluents - Summation of All Releases . . . . . . . .

Liquid Effluents . . . . . . . . . . . . . . . . . . . . . .

Solid Waste . . . . . . . . . . . . . . . . . . . . . . . .

1 Off-Site Dose Estimates . . . . . . . . . . . . . . . . . .

Meteorological Data . . . . . . . . . . . . . . . . . . . .

1 a l

1-) REGULATORY LIMITS

. Specifications for Gaseous Waste Effluents '

(1)

- The release rate limit of noble gases from the site shall be:

o- '

{Qiv [94fjy+460 fig 31 i

where Qv a release rate from all roof and unit vents in Ci/sec(groundrelease)

. i = the ith individual nuclide fiy = the average gamma energy per disintegration for nuclide i Yip = the average beta energy per disintegration for nuclide 1 (2) The release rate limit of all radioiodines and radioactive

- materials in particulate form with half-lives greater than eight days, released to_the environs as part of the gaseous wastes from the site shall be: '

1.2 X 106 gy < j .

where Qv is defined above.

(1)

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

~

{ fig 450 'Qi[ 11 and.

[ fiy

590 Qiv .

11 .

1 (4) The average release rate of noble gases from the site during any 12 consecutive months shall be: ,

)Es i .[900 Qi[ 11 and, 11 180 Qi

{ EiY (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:

4 1.5 X 108 gy 1 )

Y e, ,-e- r- ,-er ,r .,-m -, - - - - ,wc- c w w-r , w - r c- w

(6)

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

days during any period of 12 consecutive months shall be:

3.0 X 108 gy;g,j (7)

The amount of iodine-131 rele'ased during any calendar quarter shall

.o.

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 releaso rates, define and initiate a program of action to reduce the release ra':es 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 q;<arter during which the releases occurred.

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

Qiy >

~

fi6 5800 1 or,

~

iy 2400 Qig > 1

{E (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) 1.f the amount of iodine-131 released during any calendar quarter is greater than 0.5 Ci/ reactor.

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ggcifications for Liquid Waste Ef fluents The concentration of radioactive materials released in liquid waste effluents at the site shall not exceed the values specified in 10 CFR Part 20, Appendix B,

. Tabic II, Column 2, for unrestricted areas.

The cumulative release of radioactive materials in liquid waste effluents, excluding tritium 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.

If 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.

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S 2- 1_ -- . . . _.

2) Maximum Permissible Concentrations ' (Micro curies /ml)

. a. Fission and Activation Gases 9 L 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 l

b. Iodines i I

I - 131 1.0 E-10 4

I - 133 4.0 E-10 1 - 135 1.0 E-09 )

c. Particulates, Half-Lives > 8 Days ,

l l

Sr - 89 3.0 E-10 l

)

Sr - 90 3.0 E-11 Cs - 134 4.0 E-10 )

l Cs - 137 5.0 E-10 ,

Ba - 140 1.0 E-09 La - 140 4.0 E-09 -

l

d. Liquid Effluents s -

Sr - 89 3.0 E-06

.- a

- - Sr - 90 3.0 E-07 Cs - 134 4.0 E-05 Cs - 137- 2.0 E-05 1 :131 3.0 E-07

l. ,

I

I

+ _ ,. _

Liquid Effluents (Cont.) ,

Co - 58 9.0 E-05 ,

Co - 60 3.0 E-05 re - 59 5.0 E-05 In - 65 1.0 E-04 Mn - 54 1.0 E-04 Cr - 51 2.0 E-03 .

Zr - 95 6.0 E-05 Nb - 95 ,

1.0 E-04 , .

Mo - 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 ,

De - 7 2.0 E-03 l

Ru - 106 1.0 E-05 .

A9 - 110m 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

-- Kr - 85 3.0 E-06 b

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1 6

9

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3rd Quarter 4th Quarter E

- E seta E Gamma -Eseta Ganma 0.214 Mev 0.058Mev 0.243 Mev 0.02 MeV

3) Average Energy (E)

For Fission and'

'. Activation Cases 4

Measurements and Approximation of Total Radioactivity

4) a. Fission and Activation Gases: An in-line G. M. detector monitoru stack effluent. Gas samples are collected on'the stack and are sent to a

- off site lab for low level fission and activation gas analyses,

b. lodines: 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 Grass 8-1 Weekly samples anesent to a off site lab for analysesof Low level ganna emitters.

A monthly composite is made from these weekly samples. The monthly composite is checked for gross alpha and 895r , 90Sr.

d. Liquid Effluer.ts: In line-scintillation detector monitors waste liquid being released!~ Prior to discharge a sample is taken. principal gamma ,

emitters, grcss 8- 7 and tritium analysis are performed. Weekly composites i are prepared and sent to a off site labortory. Principal gamma emitters :

are determined. A monthly composite is made from the weekly samples. ,

l Gross Alpha, 895r and 90Sr are determined. One batch sample per month is sent out for determination of dissolvedand entrained gases.

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-. -.- -- - - - - - . - _ . - - . . . - . ~~-- . - . . .-. - --- - - . _ _ _ _

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5) Batch Relcanen

a. Liquid _

1) Number of batch relcanen 6.906401

. 2) Total time period for batch relenses 7.82E+02 Houra

3) Maximum time period for a batch relcano:2J9840111ours

4) Averngu time period for batch relcance:1.14E401 Hourn ,

5) Hin'imum time period for a batch rolonne:4.67E+09tourn

6) Average stream flow during periodo of 15,800 cubic feet.

relcane of effluent into a flowingg ,,.8E60ger nec nd 3

streams i

b. Cnacoun l l

1

1) Humber of batch relcanes: 3. 20E401

2) Total time period for batch relensen: 9.391R01 llouro

3) Maximum time period for a batch relenne:L97EMllours i

4) Average time period for batch relenson:1.01E40111oura l

5) Hinimum time period for a batch relcane:1.70E-(Mourn

6 Abnormal Relennen

1) Degonifier Rupture Dinphragm Dntc 12-16-79 Timei, 054fl t o 0558 Curlon of Radianctive Metorologicn1 Data During Mnterin1-Helenned The Time of Italonne Xc-133 7.43E+00 Wind Speed 4.00E-01 mph Xc-135 4. file t 00 Vertient Temp Difference 6.00E-01 0F Xe-133H .1.60E-01 Wind Direction 3.7E+0! o Kr-85H 6.09E-01 Wind Direction Variance 1.41E+02 o K r-fl7 1.45E+00

., Kr-811 1.35E400 '

Ar-41 3.11E-02 1-131 . 6. fl6E-05

, 1-133 7.91E-04 Co-5tl 1.47E-05 Cc-144 3.91E-05

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EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1979 ,

'GASE0US EFFLUENTS-SUMMATION OF ALL RELEASES

EST. TOTAL UNIT QUARTER QUARTER 1 3rd 4th ERROR %

A. FISSION & ACTIVATION GASES

^

2.24E+02 1.18E+03 1. 40E+01

i. Total release C1

$.'Averagereleaserateforperiod pCi/sec 2.82E+01 1.48E+02

3. Percent of Technical Specifica- 5.14E+00

% 7.45E-01 tion limit B. IODINES 2.02E-05 2.29E-03 1.32E+01 x

1. Total iodine - 131 Ci ~

2. Average release rate for period pCi/sec 2.54E-06 2.76E-04

3. Percent of Technical Specifica-4.04E-03 4. 39 E-01 tion limit %

C. PARTICULATES

1. Particulates with half-lives 1.44E-03 4.60E-04 1.46E+01

> 8 days ' Ci pCi/sec 1.81E-04 5.79E-05

2. Average release rate for period

3. Percent of Technical Specifica- 2.72E+00 8.68E-01 tion %

2.60E-07 3.00E-07

4. Gross alpha radioactivity C1 D. TRITIUM 3.76E+01 6.53E+00 7.80E+00 *

1. Total release C1 4.73EMO 8.21E-01

2. Average release rate for period pC1/sec

3. Percent of Technical Specifica- 9. 64E-02 1.67E-02 tion limit %

4

1 1

i

- 1979 l EFFLUENT AND WASTE DISPOSAli. SEMI-ANNUAL 'RER0 fit 1

GASEOUS EFFLUENTS-ELEVATED RELEASE I CONTINU0US MODE BATCH MODE 3rd QUARTER 4tfi QUARTER 3rd QUARTkR 4th 00ARTER NUCLIDES RELEASED UNIT

1. FISSION GASES 9.49E+02 1.08E+01 3.16E+00 j

5.46E+00 Krypton-85 Ci 8.46E-01 f

<1.00E-04 <1.00E-04 1.43E-01 Krypton-85m Ci '

<1.00E-04 3.62FdU 2.08E+00 Krypton-87 Ci <1.00E-04 1.88E+00

<1.00E-04 <1.00E-04 3.19E-OL Krypton-88 Ci 1.56E+02 1.15E+02 3.31E+01 4.16E+0! <

Xenon-133 C1 6.60E+00

<1.00E-04 <1.00E-04 1.77E+00 Xenon-135 Ci 2.50E-01 6.55E-02 Ci <1.00E-04 <1.00E-04 Xenon-135m <1.00E-04 1.18E+00 2.96E-01 Ci <1.00E-04 Xenon-138 1.80E+01 2.48E+00 4.64E-01 Others (specify) Carbon-14 Ci 3.91E+00 3.70E+01 6.44E+00 6.11E-01 9.26E-02 3H Ci 2.99E-01 1.27E+00 . 1.18E+00 4.27E-01 C1 Ar00n 37 <1.00E-04 3.87E-01 4.30E-02 Argon 41 Ci <1.00E-04

<1.00E-04 3.03E-01 6.16E-01 Xenon 131M. C1 <1.00E-04

<1.00E-04 3.97E-02 9.49E-01 Xenon 133M Ci <1.00E-04

<1.00E-04 1.24E+00 1.71E-01

~

c,1 <1.00E-04 fedon'137 1.uzt+04 1.01E+03 6.15E+0L J.74EiO2

.. Total. Ear Pe r i <ui

2. 10 DINES *

Ci 2.02E-05 2.19E-03 Iodine-131 Ci <1.00E-10 1.02E-04 lodine-133 Ci <1.00E-10 <1.00E-10 fodine-135 2.29E-03 Total for period 2.02E-05

3. PARTICULATES Chromium-51 C1 <1.00E-13 1.52E-05 Ci 2.39E-07 1.60E-06 Strontium-89 S tron tium-90 Ci 3.41E-06 3.50E-06 Cesium-T34 Ci 5.12E-04 1.19E-04 Cesium-137 Ci 6.66E-04 6.20E-05

~ ~~ Barium-lanthanum-140 Ci <2,00E-13 <6.00E-14 Cerfum-144 C1 1.24E-04 1.29E-04 ~

Cl 1.89E-05 2.94E-06 Cobalt-60 3.44E-06 Ci 3.34E-06 F13_nnnnefe-54 4.38E-07 8.74E-06 Ci c.ohnit -58 -

Ci 6.43E-05 1.76E-06 _ . _

Cerium.141's 4.00E-06 Riithenium 1D3 Ci '4.11E-07 f 2.irconium/ Niobium 95 - Ci 2.04E-05 2.75E-05 Ruthenium 106 Ci 2.76E-05 8.15E-05 Total for Period. 1.44E-03 4.60E-04

Reported Under Continuous Mode e

p 4 . e

. 4

___a

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1979 LIQUID EFFLUENTS-SUMMATION OF A!.L RELEASES UNIT QUARTER QUARTER EST. TOTAL 1 3rd 4th ERROR %

A. FISSION AND ACTIVATION PRODUCTS

1. Total release (not including 3.58E-02 8.70E-02 1.15E+01 tritium, gases, alpha) Ci

2. Average diluted concentration 1.86E-10 4.52E-10 during period pCi/ml 3.58E-01 8.70E-01 .

3. Percent of applicable limit %

B. TRITIUM Ci 8.51E+02 8.66E+02 3.55E+00

1. Total release

2. Average diluted concentration 4.50E-06 during period pCi/ml 4.43E-06

3. Percent of applicable limit % 1.48E-01 1.50E-01 C. DISSOLVED AND ENTRAINED GASES 1.04E-04 5.65E-03 1.89E+01

1. Total release C1

2. Average diluted concentration 5.41E-1] 2.94E-11 during period pCi/ml 1.80E-05 9.80E-04 l

3. Percent of applicable limit %

0.' GROSS ALPHA RADI0 ACTIVITY 8.84E-05 8.00E-04 8.00E+00

1. Total release Ci E. Vol me of waste released (prior 1.09E+0) 1.91 E+07 3.00E+00 Liters i '1 F. Volume of dilution water used 1.88E+11 1.78E+11 2.60E+00 ;

during period Liters l j

+

4 T .

ol l

4 l , - -

i . - 1979

. EFFLUENT AND WASTE D SPOSAL SEMI-ANNUAL REPORT LIQUID EFFLUENTS i

CONTINUOUS MODE BATCH MODE UNIT '

U Q'ARTER QUARTER QUARTER QUARTER NCULIDES RELEASED. 3rd j 4th 3rd 4th _

a

<5.00E-08 1.10E-04 4.45E-05 5.00E-04 Strontium-89 C1 2.97E-05 2.10E-04 6.13E-05 6.00E-04 St ronti um-90 C1 4.45E-03 <7.00E-08 8.81E-04 7.87E-03 ,

Cesium-134 C1 6.27E-03 <3.00E-08 2.48E-03 9.80E-03 Cesium-137 Ci <2.00E-07

<7.00E-07 <5.00E-07 1.19E-05 lodine-131 C1

<3.00E-08 1.84E-05 1.75E-03 Cobalt-58 Ci 7.71E-04

<3.00E-08 5.86E-03 1.64E-02 Cobalt-60 Ci 4.35E-03 <5.00E-07

<5.00E-07 <5.00E-07 <5.00E-07 fron-59 Ci <5.00E-07

<5.00E-07 <5.00E-07 <5.00E-07 Zinc-65 Ci 2.49E-04

<2.00E-08 <2.00E-08 <2.00E-08 Manganese-54 Ci 1.89E-03

<5.00E-07 <5.00E-07 <5.00E-07 Chromium-51 Ci 4.46E-03 Ci <3.00E-08 <3.00E-08 2.16E-03 Zirconium-niobium-95 <5.00E-07 <5.00E-07 <5.00E-07 Molybdenum-99 Ci <5.00E-07

<5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 Technetium-99m C1

<2.00E-07 <1.00E-07 <2.00E-07 < 1. 00E-07 Barium-lanthanum-140 Ci

<7.00E-08 <8.00E-08 1.12E-03 1.42E-04 Cerium-141 Ci

<5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 Europium-154 Ci j

<3.00E-07 <5.00E-07 <3.00E-07 <5.00E-07 Be ryllium-7 Ci J Ci <1.00E-07 <2.00E-07 6.27E-03 Z.94E-uZ Cerium-144 1.28E-02 Ci <2.00E-07 <2.00E-07 9.86E-04 Ruthenium-106 <5.00E-07 Ci <5.00E-07 <5.00E-07 4.94E-05

_ Silver-110m Ci <1.00E-08 <4.00E-08 1.21E-04 8.23E-04 Ruthenium - 103 <5.00E-07 !

Antimony-125 C1 <5.00E-07 <5.00E-97 <5.00E-07 Ci <5.00E-07 <5.00E-07 <5.00E-07 <5.00E-07 f Cobalt-57 <5.00E-07 <5.00E-07 <5.00E-07 Todine-13 r> Ci <5.00E-07 Ci 1.58E-02 3.20E-04 1.99E-02 8.67E-02 r Total for Period (above)

Ci <1.00E-05 <1.00E-05 2.81E-02 4.77E-03 Xenon-133 7.09E-04 l Ci <1.00E-05 <1.00E-05 7.37E-03

- Xenon-135 < 2. 30E-09 <3.00E-09

' Argon-37 Ci <2.00E-09 <2.00E-09 1.03E-04 1.50E-04 2.02E-06 2.00E-05 Krypton-85 C1 '

Tritium C1 4 3.01E-01 6.47E-01 8.51E+02 8.65E+02 l 4

4 T

4 4

l Sol.TD UASTE AND 1RRADIATED FUEi, SilIPMENTS A. S!)l.ID WASTE SillPPED OFFSITE FOR liURI AI, OR DISPOSAL (NOT 1Rl!ADI ATED FUEL). )

, 6-HONTil EST. TOTAL

1. TYPE OF WASTE UNIT PERIOD ERROR %

a. Spent resins, filter m3 5.1882EM1 sludges, evaporator i 1.0 U+01 bottom, etc. C1 1.6883E+01

b. Dry compressible m3 5.779E+02 Waste, Contarainated i 1.0 E+01 erguip. , e tc. C1 3.205E+00

c. Irradiated components N/A N/A N/A

2. ESTIMATE _OF MAJOR NUCf.IDE COMPOSITION (BT TYPE OF WASTE)

a. CE-144 % 3.0E+01 CS-134 % 1.7E+01 CS-137 % 1.6E+01 NB-95 % 1.0EMI ZR-95 % 9.7E+00 RU-103 % 5.4E+00 CO'58 % 3.4E+00 Co-60 % 2. 5EMO

'~

b. CE-144 % 4.2E+01

CO-60 % 2.0E+01 CS-137 % 1.2E+01 CS-134 % 1.0E+01 CO-58 %- 6.0E+00 '

NB-95 % 5.0E+00 ,

ZR-95 % 3.0E+00 MN-54 % 2.0E+00 o

1 5

l 3. S0 LID WASTE DISPOSITION NUMBER OF SIIIPMENTS MODE OF TRANSPORTATION DESTINATION 26 Tmk Ba m ell, S.C.

B. IRRADIATED FUEL SIIIPMENTS (DISPOSITION) - None e

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OFFSITE 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. ,

i The dose estimates generally tend to be conservative due to the use of conservative assumptions in the calculational models. More realistic 1

estimates of the off-site dose are obtained by analysis of the environ-mental monitoring data. A 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.

I

1. Dose Models l

l

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

The code uses the semi-infinite cloud model to implement the dose models of U.S.N.R.C. Regulatory 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 o

using a meteorological computer code which implements the assumttions given in Section C of NRC Regulatory Guide 1.111. " Methods for Estimating Atmospheric 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 icvels of the meteorological tower.

The GASPAR 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.

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/

9 4 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 ]

I

a. Airborne Effluents !

l i

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 l

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 1

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

1 1

For the vegetation pathway the maximum individual dose is 1

calculated at the vegetable garden of highest depleted X/Q. l For the meat, cow's milk and goat's milk pathways, the calcu-lated dose is included as the maximum individuals dose only at locations and times where these pathways actually exist.

Doses were calculated 6t the cow farm and goat farm of maximum deposition. The doses presented in Table 5.1 are the maximum doses observed.

b. Liquid Effluents e

The calculated doses are presented in Table 5.1.

l

-BF-

4 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 I

the maximum organ dose . The dose to all other organs was less !

l than those values presented for the liver.

Calculations are performed for adults, teenagers, children and

~

infants separately. Unless otherwise noted in the table the doses given are adult doses. l

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 radiation in the vicinity of Connecticut Yankee is about 40 millirem I3) for a six month period as opposed to the average individual dose within 50 miles of the site of 0.000065 millirem from gaseous I

effluents and 0.00024 millirem from liquid effluents during the report period. The maximum individual dose of 0.04 millirem from gases or 0.16 millirem from liquids are less than one percent of the background dose.

1 I

1 1

e C-REFERENCES

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

I.ADTAP - U.S. Nuclear Regulatory Conunission; Washington, D.C.

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

G G

l l

8 s

TABLE 5.1 4

Of f-Site Dose Estimates Connecticut Yankee 1979 A. Airborne Effluents Units July-Sept Oct-Dec

1. Maximum Individual Dose M1111 rem

a. Whole Body 2.2(-2)a,b 1.9(-2)d

b. Skin 6.9(-2) 7.4(-1)b

c. Thyroid 1.7(-1)c 2.4(-2)f ,

2. Population Dose 0-50 Miles Person-Rem

a. Whole Body 1.5(-1) 1.0(-1)

b. Skin 2.8(-1) 2.4(0)

c. Thyroid 1.5(-1) 3.0(-1)

3. Average Dose 0-50 Miles M1111 rem

a. Whole Body 3. 9 (-5) 2. 6(-5)

b. Skin' 7.3(-5) 6.3(-4)

c. Thyroid 3.9(-5) 7.8(-5) l l

l B.- Liquid' Effluents )

1. Maximum Individual Dose Millirem 1

. a. Whole Body 7.0(-2) 9.4(-2)

b. Max Organ (Liver) 9.8(-2)* 1.3(-1)*

c. Thyroid 2.2(-3) 2.3(-3) )

2. Population Dose 0-50 Miles Person-Rem 1 1

a. Whole Body 4.0(-1) 5.4(-1)

b. Max Organ (Liver) 6.8(-1) 8.8(-1)

c. Thyroid 1.4(-2) 1.5(-2)

3. Average Dose 0-50 Miles Millirem o

a. Whole Body 1.0(-4) 1.4(-4) a b. Max Organ (Liver) 1.8(-4) 2.3(-4)

c. Thyroid 3.7(-6) 3.9(-6) a .- 2.2(-2) = 2.2 x 10-2

b. At a location 0.3 miles NNW .

c. Child thyroid dose at critical goat and vegetable farm 1.3 miles NW l

d. At a location 0.4 miles NNE I

e. Teenager dose ~ - all other doses are adult doses

f. Child thyroid dose at. critical location - 0.3 miles NNW

.i l: 4 i

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ML20126B075

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e- a e .a 1- F} Em 3 J C C C 3 D *J '3 3 3 "J C 3 C's D J A . s .J t A Y %I 3 R EO 3 m Zj r Qs 3 .* e a 3

* J, >

e E 2 O a E A 3

= &.

> g 3. e

= e D he '*D #

52

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e- a e .a 1- F} Em 3 J C C C 3 D J '3 3 3 "J C 3 C's D J A . s .J t A Y %I 3 R EO 3 m Zj r Qs 3 . e a 3