Text

Semiannual Radioactive Effluent & Waste Disposal Rept, Jan-June 1980
	ML19331D944
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	06/30/1980
From:	; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
References
	NUDOCS 8009040380
	Download: ML19331D944 (55)
	v • d • e

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THl3 DOCUMENT CONTAINS POOR QUAllTY PAGES,

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TABLE OF CONTENTS PACE Supplemental Information.

1-7 Caseous Effluents - Sure.ation of all Releases 8

Caseous Effluents - Mixed >bde Release (Partially Elevated ar.d Partially Ground) 9 Liquid Effluents - Su: mation of All Raleases 10 Liquid Effluents.

11 Solid Waste 12-13 off-Site Dose Estimates 14-21 Meteorological Data 22-53 i

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1.)

REGULATORY LIMITS _

g Syecifications for Gaseous Waste Effluents (1)

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

1 Qty

[94Ely+460Tg

,,1 i

iwhe're Qy = release rate from all roof and unit vents in t.

Ci/sec (ground release) 1

= the ith individual nuclide Yiy = the average garna energy per disintegration for nuclide i fig = the average beta energy per disintegration for nuclide 1 (2)

The release rate limit of al'l radiciodines and radioactiis materials in particulate forn with half-itves greater than eight days, released to_f.ha environs.as part of the gaseous wastes from the site shall,be:

1.7 X 106 gy < 1 where Qv is defined above.

(1)

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

[ Eig 1450 Qiv

.1,1 1

and.

[ Iiy

590 Qi_v

,1,1 (4)

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

[ Tj's 2900 Qi[

,,__1 1

and, g

{Tiy 1180 Qiy

, _1 3

(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 100 Q y,<_, 1 G

f.

3

(5 )

The average release rate of all icdtnes and radioactive materials per site in particulate form with half-lives gr:ater than eight -

days during any period of 12 consecutive months.shall be:

3.0 X 108 Qv < 1

0), The amount of iodine-131 rele'ased during any calendar quarter sh'all

?not exceed 2 Ci/ reactor.

Qi)

The amount of iodine-131 released during any period of 12 consecutive months shall not exceed 4 C1/ reactor.

Should any of the conditions of (1), (2) or (3) listed below exist, the ifcensee 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 fro:n the site during any calendar quarter is:

1 iB 5800 Qi

}I or, h400 Qi[

1

[Ity 1

(2)

If the average release rate of all iodines and radioactive mate' rials in particulate form per site with half-lives greater than eight days during ahy 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.

s m,

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

T4bic II, Column 2, for unrestricted areas.

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

The cumulative release of radioactive materials in liquid waste effluencs, 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 oojective 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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W2) Maximum Permissible Concentrations (Micro curies /ml) a.

Fission and Activation Gases 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 3.0 E-08 Xe - 138 3.0 E-08 Ar - 37 1.0 E-04 b.

Iodines I - 131 1.0 E-10 I - 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-11 Cs - 134 4.0 E-10 Cs - 137 5.0 E-10 Ba - 140 1.0 E-09 La - 140 4.0 E-09 i

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

Liquid Ef fluents (Cont.)

Co - 58 9.0 E-05 Co - 60 3.0 E-05 Te - 59 5.0 E-05 2n - 65 1.0 E-04 Hn - 54 1.0 E-04 Cr - 51 2.0 E-03 Zr - 95 6.0 E-05 Nb - 95 1.0 E-04 Ho - 99 4.0 E-05 Tc - 99m 3.0 E-03 Ba - 140 2.0 E-05 La - 140 2.0 E-05' Co - 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 Kr - 85 3.0 E-06

1st Qumrter 2nd Quarter E Seta E Ganna E Seta E Gamma

3) Average Energy (E)

MeV Mev Mev Mev 2.12E-01 3.65E-02 For Fission and 2.03E-01 5.41E-02 Activation Gases Measurements and Approximation of Tatal Radioactivity Fission and Activation Gases _: An in-line G. M. detector monitors

4) a.

stack effluent. Gas samples are collected on the stack and are sent to a off site lab for low levei fission and.ctiva, tion gas analyses, b.

Iodines: 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 d-1 Ileakly samples anesent to a off site lab for analysesof Low level gamma emitters.

1 The monthly A monthly composite is made from these weekly sam 2 es.

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 taken. Principal ganr.a emitters, gross a-7 and tritium analysis are performed. Weekly ccmposites 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, 895r and 90Sr are determined. One batch sample per month is rent out for determination of dissolvedand entrained gases.

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5) Batch Releases a.

Liquid

1) Number of batch releases:

1.14E+02

2) Total time period for batch releases:.

1.32E+03 hours 9

3) Maximum time period for a batch release: 3.47E+01 hours

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

5) Minimum. time period for a batch release: 2.17E 00 hours0 days 0 hours 0 weeks 0 months

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

b.

Gaseous

1) Number of batch releases:

2.40E+01

2) Total time period for batch releas'es:

3.67E+02 hours

3) Maximum time period for a batch release:1.17E+02 hours

4) Average time period for batch releases: 1.53E+01 hours

5) Minimum time period for a batch release: 5.58E 00 hours0 days 0 hours 0 weeks 0 months

6 Abnormal Releases Ion Exchange Slurry Vent Gas Releases (2)

1 5-4-80 0755-0759 Curies Released Metorological Data Xe-133 2.54E00 Wind speed 1.20E+01 mph Xe-135 9.07E-01

. Vertical Temp Dif f. -8.00E-01 F

Xe-133M 6.57E-02 Wind Direction 3.00E+02 Xe-135M 4.01E-03 W1..d Direction Variance 6.00E+01 0 K 8.5 M 2.10E-02

2 5-4-80 0900-0904 Xe-133 4.24E00 Wind Speed 1.50E+01 mph Xe-135 1.52E00 Vertical Tamp Diff. -1.20E00 F Xe-133M 1.06E-01 Wind Direction 3.00E+02 0 Xe-135M 6.67E-03 Wind Direction Variance 6.00E+01

.Kr-85M' 3.50E-02 l

Waste Gas Surge Tank Relief 5-28-80 0034-0036 Xe-133 1.62E00 Wind Speed 3.00E+00 mph Vertical Temp. Diff. 1.60E00 F Wind Direction 3.60E+02 Wind Direction Variance 4.00E+0lo EFFLUEilT AND WASTE DISPOSAL SEMI-AriflUAL REPORT

- 19 80

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GASECUS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT QUARTER QUARTER EST. TOTAL 1

1st 2nd ERROR %

A.

FISSION & ACTIVATION GASES l2.08E+03

1. Total release Ci 5.38E+02 1.40E+01

2. Average release rate for oeriod uCi/sec 6.92E+01 2.67E+02

3. Percent of Technical Specifica-2.09E+00 8.09E+00 tion limit 8.

10 DINES

1. Total iodine - 131 Ci 1.93E-04 1.93E-03 1.30E+01

2. Average release rate for oeriod uCi/sec 2.48E-05 2.48E-04

3. Percent of Technical Specifica-tion 1imit

3. 73E-01 3.73E+00 C.

PARTICULATES

1. Particulates with half-lives 2.86E-03 1.78E-03 1.40E+01

> 8 days Ci

2. Averace release' rate for period uCi/sec 3.68E-04 2.28E-04

3. Percent of Technical Specifica-tion 5.47E+00 3.40E+00 1.19E-06 9.00E-07

4. Gross alpha radioactivity Ci D.

TRITIUM

1. Total release Ci 1.73E+01 1.78E+03 8.00E+00

2. Averace release rate for period uCi/sec 2.20E+00 2.29E+02

3. Percent 'of Technical Specifica-4.48E-02 4.67E+00 tion limit

EFFLUENT AND WAdit utsrusst atna-nanunu

.m a un.

...m GASEOUS EFFLUENTS ELEVATED RELEASE j

-c CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT ist OUARTER 2nd QUARTER lst OUARTER 2ndOUARTER 4

1. FISSION GASES Kr -ton-85 Cf 1.37E+01 5.66E+02 1.06E+01 9.41E+00 1, Kr_; ton-85m Ci 2.84E-03

<1.00E-04 3.11E-01 4.28E-01 Krypton-87 Ci 5.74E-03

<l.00E-04 7.04E-01 3.6bE-01 Kryoton-88 Ci 5.61E-03

<1.00E-04 6.70E-01 3.99E-01 Xenon-133 Cj 3.43E+02 4.20E+02 7.74E+01 1.02E+03 Xenon-135 Ci 2.14E-02 d.89E-03 2.60E+00 2.07E+01 Xenon-135m Ci 4.08E-03

<1.00E-04 5.08E-01 2.71E-01 Xenon-138 Ci 1.59E-02

<1.00E-04 1.74E+00 7.30E-01 Others (specify) Carbon-14 Ci 8.39E+01 8.31E+00 5.58E-01 8.62E-01 3H Ci 1.72E+01 1.78E+01 1.07E-01 7.07E-02 Arqon 37 Ci

<7.00E-09 2.39E+01 5.56E-01 5.60E-01 Ci

<1.00E-04

<l.00E-04 3.17E-03

8. 27 E-0 }

Argon 41 Xenon 131M Ci 1.07E-02

<1.00E-04 1.07E+00 4.87E-01 6.76E-04 1.72E+00 7.38E-02 3.48E+00 Xenon 133M Ci 9.36E-01

_3.66E-01 Xenon 137 Ci 1.40E-02

<l.00E-04 i

~

4.40E+02 1.02E+03 9.77E+01 1.06E+03 Torni Fnr onri na l

t Iodine-131 Ci 5.86E-05 1.93E-03 i

lodine-133 Ci 1.34E-04

<1.00E-10 l

i Iodine-135 u

Ci

< l. 00E-LO

<l.00E-10 l

l Total for period Ci

1. 9 3E-04 1.93E-03

3. PARTICULATES Strontium-89 Ci 2.14E-06 6.00E-06 Strontium-90 Ci 1.02E-06 8.00E-07 Cesium-134 Ci 3.87E-06 8.27E-05 Cesium-137 6.31E-06 1.18E-04 Barium-lan,thanum-140

[i

<1.00E-11

<1.00E-11 Cerium-144 Ci 3.57E-04 3.04E-04 Ci 2.96E-04 3.35E-04 u

Cobalt-60 Maneanese-54 i

Ci 9.23E-05 6.78E-05 Ci 1.35E-03 2.78E-04 r,ch. i t -59 Cerius.141 Ci 2.17 E-05 1.34E-05 suchentun 1h3 Ci 6.15E-05 5.21E-05 l

Zircon 4uat.2iculum 95 Ci +

6.72E-05 5.clE-05

, 9,r_nx i_ ir_ns Ru t hen tt23-J 06 _

r. i _

_'i 4.16E-04 1.16E n4 Chronium-51 l

Reported Under Continuous Mode 9

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EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT

- 1980, I

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES UNIT QUARTER QUARTER EST. TOTAL 1

1st 2nd ERROR %

A. FISSION AND ACTIVATION PRODUCTS i

1. Total release (not including 4.42E-02 8.00E-02 1.10E+01 tritium, cases, aloba)

Ci

2. Average diluted concentration 2.34E-10 1.27E-09

- during period uCi/ml 4.42E-01 8.00E-01

3. Percent of aoplicable limit 4

B. TRITIUM C1 1.81E+03 1.10E+03 3.50E+00

1. Total release

2. Average diluted concentration durino ceriod uCi/ml 9.62E-06 1.08E-05 l

3. Percent of acclicable limit 3.20E-01 3.60E-01 C. DISSOLVED AND ENTRAINED GASES Ci 6.16E-03 3.94E-02 1.90E+01

1. Total release

2. Average' diluted concentration durinc ceriod uCi/ml 3.27E-11 2.09E-10 j

3. Percent of acclicable limit l'.90E-03 6.98E-03 l

i D. GROSS ALPHA RADI0 ACTIVITY 1

1. Total release Ci 8.10E-04 7.20E-04 8.00E+00 1

E. Volume of waste released (prior 2.24E+07 3.37E+07 3.00E+00 to dilution)

Liters F. Volume of dilution water used 1.90E+11 1.02E+11 2.5E+09 during period Liters O

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EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT

- 19B0 l

LIQUID EFFLUENTS l

CONTINUOUS MODE BATCH MODE 4

^

NULLIDFS Rf t t AM D

@fst n

st j

nd 6.00E-04 7.50E-04 l 1.10E-04 l

1.50E-04 Strontium-89 Ci Strontium-90 Ci 1.00E-03 7.60E-04 1.20E-04 i

1.80f-04 Cesium-134 Ci

<5.00E-07

<5.00E-07 7.34E-03 1

1.88E-02 l

Cesium-137 Ci

<5.00E-07 1

5.24E 04 1.03E-02 1

2.86E-02 l

Iodine-131 Ci

<1.00E-06

<1.00E-06 3.88E-03 Cobalt-58 Ci c5.00E-07

<5.00E-07

.33E-04, 2.52E-03 Coba12-60 Ci

.4.3/E-OJ 1.77E-04 1.01E-02 1.06E-02 fron-59 Ci

< a.v ur.- u /

<5.00E-07

<5.00E-07 I

4 Zinc-65 Ci

<5.00E-07

<5.00E-07 Mancanese-54 Ci

<5.00E-07

<5.00E-07 3.21E-04 l

Chromium-51 Ci

<5.00E-07

)

Zircenium-niobium-95 Ci

<3.UUE-01

<5.00E-07 4.14E-04

<5.00E-07

<5.00E-07 Molybdenum-99 Ci

<5.00E-07

<5.00E-07 i

Technetium-99m Ci

<5.00E-07

<5.00E-07 I

Barium-lantnanum-140 Ci'

<1 00E-06

<1 00E-05

<1 00E-06 i

<5 00E-07

{

Cerium-141 Ci

<6 00E-07

<5 M -T7

<5 00E-07 l

<1 00E-06 L

i Eurcoium-154 Ci

<5.00E-07

<5.00E-07 l

<5.00E-07 i

Beryilium-7 Ci

<5.00E-07

(

Ceriu :-144 Ci

<3.00E-0/

<3.00E-07 1.14E-oz 6.46E-03 Ruthenium-106 Ci

<5.00E-07

<5.00E-07 6.28E-03 t

Silver-llCm Ci

<5.00E-07

<5.00E-07 f

luthenium th 7 Ci

<5.00E-07

<5.00E-07 i

Antimony-125

~ ~

Ci -

<5.00E-07

<5.00E-07 Cobal:-57 Ci

<5.00E-07

< 5. 00 E-07

<5.00E-07

<5.00E-07 i

.Icdine-133' -

Ci

<5.00E-07

<5.00E-07 l

i i

-~~

Total for Period (above)

Ci 4.17E-03

2. 21E-03 4.00E-02 7.78E-02 Xenon-133 Ci

<1.00E-05

<1.00E-05 5.23E-03 3.75E-02 Aenon-135 Ci

<1.00E-05

<1.00E-05 4.38E-04 1.36E-03 Araon-37 Ci 4.00E-05 5.00E-05 4.20E-06 4.00E-06

~

krypton-85 Ci 4.10E-04 4.00E-04 4.20E-05 5.00E-05 Tratium l

Ci j 2.26E-01 l 5.09E-02 l 1.81E+03 !

1.10E+03 ll I

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SOLID WASTE AND IRRADIATED FUEL SHIP!ENTS January 1, 1980 - June 30, 1980 A.

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

Type of Waste Unit 6-month Period Est. Error %

a.

Spent resin, filter m

9.3011 E + 01 sludges, evaporator

+ 1.0 E + 01 bottoms, etc.

Ci 1.1872 E + 02 3

b.

Dry compressible waste, m

h.7019 E + O2 contaminated equip., etc.

Ci 7.h818

+ 1.0 E + 01 c.

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

Estimate of Ma,jor Nuclide Composition (By type of vaste) a.

Cs-137 h.07 E + 01 %

Cs-13h 3.35 E + 01 %

Ce-lkh 1.01 E + 01 %

1 Co-58 5 52 E 00 %

Co-60 4.53 E 00 %

Nb-95 8.15 E - 01 %

Zr-95 h.56 E - 01 %

Mn-5h 2.76 E 00 %

b.

Cs-137 29 E + 01 %

Cs-13h 2.hl E + 01 %

Co-58 1.37 E + 01 %

Ru-106 1.29 E + 01 %

Ce-lkh 9 06 E 00 %

Co-60 5.82 E 00 %

Mn-5h 2.75 E 00 %

Nb-95 1.17 E 00 %

3.

Number of Shipments Mode of Transport Destinati1 29 Truck Barnwell, SC B.

Irradiated Fuel-Shipments (Dispo.aition)

Number of Shinments Mode of Transport Destination 3

Truck Battelle Columbus Facility West Jefferson, Ohio 1%

s 0FFSITE DOSE ESTIMATES InaccordancewithOherequirementsofSection5.6.1.boftheEnviron-mental Technical Specifications and Regulatory Guide 1.21, the -if-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. 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, 1981.

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 GASPAR(1).

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 GASPAR code were generated using a meteorological computer code which implements the assumptionc 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 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 done.

t 1

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f b.

Liquid Effluents Maximum individual and population doses due to the release of radioactive liquid effluents were c.culated using the computer code LADTAP(2),

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 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 egiculated at the offsite location of maximur, 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 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 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 l

The calculated doses are presented in Table 5.1.

I 1

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y

l 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.

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 belou 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 millires( }

l for a six month period as opposed to the average individual dose j

within 50 miles of the site of 0.00012 millirem from gaseous..

1 effluents and 0.00082 millirem from liquid effluents

~

during the report period. The maximum individual dose of 0.14 millirem from gases or 0.55 millirem from liquids are approximately one percent of the background dose.

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REFERENCES (1)

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

(2)

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

(3)

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

TABLE 5.1 Of f-Site Dose Estimates Connecticut Yankee 1980 A.

Airborne Effluents Units Jan-Mar Apr-June 1.

Maximum Individual Dose Millirem a,b a.

Whole Body 2.5(-2)b 1.l(-1)f b.

Skin 7.5(-2)

5. 6 (-1) f c.

Thyroid 6.3 (-3) c,d 2.7(-1)8 2.

Population Dose 0-50 Miles Person-Rem a.

Whole Body 7.7(-2) 3.7(-1) b.

Skin

2. 9 (-1)

2. 2 (0) c.

Thyroid

2. 5 (-2) 5.4(-1) 3.

Average Dose 0-50 Miles Millirem a.

Whole Body

2. 0 (-5) 9.7(-5) b.

Skin 7.6(-5) 5.7(-4) c.

Thyroid

6. 5 (-6)

1. 4 (-4)

B.

Liquid Effluents 1.

Maximum Individual Dose Millirem a.

Whole Body

9. 8 (-2) 4.5(-1)*

b.

Max Organ (Liver )

1. 3 (-1) *

6. 3 (-1) c.

Thyroid 4.9(-3) 1.1(-2) 2.

Population Dose 0-50 Miles Person-Rem a.

Whole Body 5.7(-1)

2. 6 (0) b.

Max Organ ( Liver)

9. 2 (-1)

4. 3 (0) c.

Thyroid

3. 2 (-2) 5.6(-2) 3.

Average Dose 0-50 Miles M1111 rem a.

Whole Body

1. 5 (-4) 6.7(-4) b.

Max Organ ( Liver )

2. 4 (-4) 1.1(-3) c.

Thyroid 8.3(-6)

1. 5 (-5)

a. 4.6(-2) = 4.6 x 10-2

b. At a location 1300 meters SE

c. Teenage thyroid dose at critical location 1300 meters SE

d. Teenage lung dose at critical location is 8.1(-3); however thyroid doses are limiting over the year

e. Teenager dose - all other doses are adult doses

f. At a location 550 meters NW

)

g. Infant thyroid dose at critical goat and vegetable farm 2100 meters NW HADDAM NECK METEOROLOGICAL JOINT FREQUENCY DATA FOR WASTE GAS TANK Bl" EASES

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COtEl Yate:EE l#UCLEAR F0WEP STATIC:4 / triIT 1 g

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ML19331D944

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8 M >= >

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8 M >= >

J M&4 b

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