B13174, Annual Radioactive Effluents Dose Rept 1988

Annual Radioactive Effluents Dose Rept 1988

ML20247G692
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/31/1988
From:	Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B13174, NUDOCS 8904040296
Download: ML20247G692 (15)

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ANNUAL RADIOACTIVE EFFLUENTS DOSE REPORT l

JANUARY-DECEMBER 1988 i g

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DOCKET NO. 50-213 .

( LICENSE DPR-61 -

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TABLE OF CONTENTS 4

SECTION PAGE 1

1.0 INTRODUCTION

2.0 0FFSITE DOSE INFORMATION 2-5 3.0 DISCUSSION OF RESULTS 6 -8 TABLE 1 0FFSITE DOSE C0f941TMENT (AIRBORNE)

TABLE 2 0FFSITE DOSE COMMITMENT (LIQUID)

TABLE 3 WHOLE BODY DOSE COMPARISONS

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1.0 INTRODUCTION

, This annual report presents a summary of the. estimated o'f fsi te '

radiation doses from routine releases of radioactive materials- in airborne and liquid effluents for each unit. These include the annual population dose commitments (Person-Rem) for the annular region out to 50 miles from the site, the annual average dose commitment (mrem) to the population and the annual maximum dose commitment (mrem) to any real member of the public.

The radiation doses resulting from the calendar year of airborne and liquid effluents are integrated over a 50 year time span, taking into account _ the effective decay and removal of the radioactive materials contributing to the dose for each individual in the population. The population dose commitment is the summation of the calculated individual doses with units of Person-Rem.

The doses are compared with the regulatory limits and with the annual average population dose commitments from natural background and other sources to provide perspective.

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2.0 0FFSITE DOSE INFORMATION In accordance with the requirements of the Technical Specifications and Regulatory Guide 1.21, the offsite dose to humans from the airborne and liquid radioactive effluents of Haddam Neck have been calculated.

These estimations are performed using measured radioactive effluent data, measured meteorological data, and calculational models developed by the U.S. Nuclear Regulatory Commission (NRC) and Envi ronmental Protection Agency (EPA).

The dose estimates generally tend to be conservative due to the use of i

conservative assumptions in the calculational models. More realistic estimates of the offsite dose are obtaine'd by analysis of the environmental monitoring data. A comparison of the doses estimated by each of the above methods will be presented in the Annual Radiological Environmental Monitoring Report.

Calculation of Population & Maximum Individual Dose Commitment Po pul a tion dose commitment is defined as the total radiation dose 1

received by the specified population during a specified period of time from an identified source of radiation. For purposes of this report, the population is taken to be within the annular area surrounding the i l

nuclear site out to a 50 mile outer radius.

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l The radiation doses resulting from one calendar year of airborne and liquid ef fluents are integrated over a 50 year period, taking into account the radioactive decay and biological elimination of the radioactive materials contributing to the dose. - The population dose commitment (units of person-rem) is the sum of the calculated individual doses.

The dose calculations involved the input of three types; radioactive source term data, site speci fic data, and generic factors. The radioactive source term (units of Curies) is obtained from the Semiannual Radioactive Ef fluents Report. The site specific data includes the meteorological data (wind speed, direction, stability, etc.) to calculate the transport and dispersion of airborne radioactive ef fl uents , dilutio1 factors for liquid ef fluen ts , the population distribution and demographic profile surrounding the site divided into 16 compass sectors. Other site specific data include the annual average production of milk, meat, vegetation, fish and shellfish. The generic data includes the annual ' average consumption rates (inhalation of air and ingestion of fruits, ve geta bl es , leafy ve ge ta bl es , grains, milk, poultry, meat, fi s h , and shellfish), and occupancy factors (air submersion and ground irradiation, shoreline activity, swimming, boating, etc) for determination of dose to the individual who would receive the maximum dose (maximum individual).

All these factors are input into the appropriate dose model for converting radioactive airborne and liquid e f fluents data into population and individual dose commitments.

1 a '. Airborne Radioactive Effluents Maximum individual doses and population doses due. to the release l

of noble gases, radiodines and particulate 'were calculated

- using the computer code GASPAR(1).

The GASPAR 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 assumptions given in Section C of NRC Regulatory Guide.

1.111 " Methods for Estimating Atmospheric Trans port and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cool ed Reactors."

The annual summary of hourly meteorological (15 minute increments) data collected for the year is not included in this report but is available from computer s tora ge. This data includes, wind speed, direction and atmospheric stability and joint f'equency r distributions.

Releases from the 175-foot vent stack were considered as a mixed mode release (partially eleva ted and partially ground). The Pasquill stabil,ity classes were determined using the temperature i

4 gradient between the 33-foot and the 196-foot levels of the-meteorological tower.

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The GASPAR code was run for continuous releases through the vent (building ventilation) and batch releases ' through the vent (waste gas tanks, vent header, volume control tanks, and containment. purge). The resulting doses were t hen - . summed to determine the total dose.

b. Liquid Radioactive Effluents Maximum individual and population doses due to the release of radioactive liquid effluents were calculated using the computer code LADTAP(4). The code impl ements ' the dose models and parameters given in Regulatory Guide 1.109 (October 1977).

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3.0 DISCUSSION OF RESULTS i

a. Airborne Effluents l

l For population doses. the GASPAR code calculates the dose to the whole body, GI-tract, bone, l i ver ,. kidney, thyroid, lung and skin from each of the following pathways: direct exposure from 1

the pl ume and from ground depositon, inhalation, vegetation, cow's milk and meat.

The values presented are a total from all pathways, however, only the whole body, skin and maximum organ dose are presented.

The maximum organ dose in all cases was to the thyroid, and thus, the dose to all other organs was less than that shown for the thyroid.

For the dose to the maximum individual, the GASPAR program calculates the dose to the same organs listed above for the following pathways: direct exposure to the plume, exposure from ground deposition, inhalation, and ingestion of vegetation, meat, cow's milk and goat's milk. The doses are calculated for adults, teenagers, children and infants separately.

For the plume and inhalation pathways, the maximum individual  ;

dose is calculated at the offsite location of highest decayed X/Q where a poten'tial for dose exists.

For the ground deposition, the maximum individual dose is calculated at the offsite maximum land location of highest 1

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decayed X/Q and highest D/Q where a potential for dose exists.

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For the vegetation pathway, the' maximum individual dose is-l calcul'ated . at the vegetable garden of highest D/Q. For the meat, cow's milk and goat's milk pathways, the calculated ~ dose.

is included for 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.

1 The doses presented in Table 1 are the maximum doses observed.

To demonstrate compliance with 10CFR50 Appendix I, the maximum individual whole body dose only includes the external pathways (plume and ground exposure) while the maximum individual organ dose only includes the internal pathways. Popul ation doses include all applicable pathways.

Maximum individual and population doses are presented in Table 1. i

b. Liquid Effluents The LADTAP code per forms calculations for the following pathways: fish, shell fish, algae, drinking water, irrigated food, shoreline activity, swimming and boating. In the vicinity 1

of Connecticut Yankee, the shellfish, algae, drinking water and irrigated food pathway.s do not exist. Therefore, the maximum individual doses do not consider these pathways. The population doses considers all applicable pathways within 50 miles.

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• I Doses are calculated for the whole body, skin, thyroid, GI-LLI, bone, j i

, liver, kidney and lungs. Calculations are performed separately for adults, teenagers, and children.

Table 2 presents the doses to the whole body, thyroid, and the maximum organ dose. Unless otherwise noted in the table, the doses given are adult doses.

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c. Analysis of Results The doses are well below permissible levels and small in comparison to the dose from natural tackground radiation. The statistical expectation of health effects from the calculated radiation dose due to pl ant operations is insignificant. For perspective, Table 3 presents a comparison between the doses due to plant operation and doses received from other sources such as the naturally occurring background levels. The table also presents the legally allowed levels from 40CFR190. The 3 year trend is shown below.

CY RADIOACTIVE EFFLUENTS DOSE (WB)

MaximJm Offsite individual mrem /yr 06:

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1936 1987 1933 Year m_m._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

FOOTNOTES-(1) 'GASPAR Dose Code, K. F. Eckerman, Radiological Assessment Branch, U.S.

Nuclear Regulatory Commission, Washington, D.C., - Revised 2/20/76.

(2) AIREM Program Manual - A computer Code for Calculating Doses, Population Doses; and Ground Depositions due to Atmospheric Emissions of Radionuclides, J. A. Marlin, Jr., C. B. Nelson and P. A. Cuny, U.S.

EPA Office of Radiation Programs, Washington, D.C., May,1974 (3) Cooper, R. E., EGAD - A Computer Program to Compute Dose Integrals from External Gamma Emitters, DF-1304. Mathematics and Computers (TID-4500, VC32), Savannah River Laboratory, Aiken, S.C., September, 1972.

(4) LADTAP - V. S. Nuclear Regulatory Commission; Washington, D. C.

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HARTFORD CONNECTICUT 06141-0270 k ' J w m e auca aaw w cou.- (203) 665-5000 March 29, 1989 Docket Nos. 50-213 813174 Re: 10CFR50.36a U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Haddam Neck Plant Annual Radioactive Effluents Dose Report In accordance with the requirements of 10CFR50.36a and the Technical Specifi-cations, a copy of the Annual Radioactive Effluents Dose Report is herewith submitted.

This report includes a summary of the assessment of maximum individual and population dose resulting from routine radioactive airborne and liquid effluents for the period of January through December 1988. Copies of the report are being forwarded in accordance with the provisions of 10CFR50.4(b)(1).

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY

$6'f fW E. J'ytoczka 4

Senior Vice President cc: W. T. Russell, Region I Administrator i A. B. Wang, NRC Project Manager, Haddam Neck Plant J. T. Shedlosky, Senior Resident Inspector, Haddam Neck Plant e

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