ML20247G703

Annual Radioactive Effluents Dose Rept 1988

ML20247G703
Person / Time
Site:	Millstone
Issue date:	12/31/1988
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
References
NUDOCS 8904040299
Download: ML20247G703 (21)

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ANNUAL RADIOACTIVE EFFLUENTS l DOSE REPORT 1

JANUARY-DECEMBER 1988

, OPERATING LICENSE NO's. DPR-21, DPR-65, & NPF-49 i DOCKET NO's. 50-245, 50-336. & 50-423 8904040299 PDR 881231 R ADOCK 05000245 PDC //I /

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l ANNUAL RADIOACTIVE EFFLUENTS DOSE REPORT JANUARY-DECEMBER 1988

, OPERATING LICENSE NO's. DPR-21, DPR-65, & NPF-49

. DOCKET NO's. 50-245, 50-336. & 50-423 8904040299 881231 PDR ADOCK 05000245 //

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_.. N UTHJTIES o.nor i Ottices . seio.n street, seriin. Conn.ciicut 1 EsrYS v'rsIrEcU=~ P.O. BOX 270

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HARTFORD, CONNECTICUT 06141-0270

. L L J C,[ ,CE,,7,"co,", (203) 665-5000 March 29, 1989 Docket Nos. 50-245 50-336 50-423 B13173 Re: 10CFR50.36a U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Millstone Nuclear Power Station Unit Nos. 1, 2, and 3 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, NORTHEAST NUCLEAR ENERGY COMPANY Yf E. Ty difoczka //

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Senior Vice President cc: W. T. Russell, Region I Administrator M. L. Boyle, NRC Project Manager, Millstone Unit No. 1 G. S. Vissing, NRC Project Manager, Millstone Unit No.2 D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2, and 3

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TABLE OF CONTENTS SECTION PAGE I.0 INTRODUCTION 1 2.0 0FFSITE DOSE INFORMATION 2-6 3.0 DISCUSSION OF RESULTS 7-10 TABLE I 0FFSITE DOSE C0mITMENT (AIRBORNE)

TABLE 2 0FFSITE DOSE COMITMENT (LIQUID)

TABLE 3 WHOLE BODY DOSE COMPARISONS

1.0 INTRODUCTION

This annual report presents a summary of the estimated offsite 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 radiction 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, l

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2 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 Millstone have been calculated.

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

The dose estimates generally tend to be conservative due to the use of conservative assumptions in the calculational models. More realistic estimates of the offsite dose are obtained 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 Population dose commitment is defined as the total radiation dose 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 nuclear. site out to a 50 mile outer radius.

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The radiation doses resulting from one calendar year of airborne and liquid. effluents are integrated over a 50 year period, taking into A

account the radioactive decay and biological elimination of the radioactive materials contributing to the dose. The population dose I commitment' (units of person-rem) is the sum of the calculated individual doses.

l 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 Effluents Report. The site specific data includes the meteorological data (wind speed, direction, stability, l etc.) to calculate the transport and dispersion of airborne radioactive effluents, dilution factors for liquid ef fl uents , the

- population distribution and demographic profile surrounding 6he site divided into 16 compass sectors. Other site specific data include the 1

annual average production of milk, meat, vegetation, fish and.

shell fi s h. The generic data includes the annual average consumption rates (inhalation of air and ingestion of fruits, vegeta bl es , l ea fy vegeta bl es , grains, milk, poultry, mea t , fish and shell fi sh), 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 ef fl uents data into population and individual dose commitments.

a. Airborne Radioactive Effluents Maximum individual doses and population doses due to the release of noble gases, radiodines and particulate were calculated using the computer code GASPAR(1), with the exception of Unit 1 noble gas doses. The maximum individual dose due to direct exposure from the Unit I noble gas plume was calculated using the computer code AIREM(2),

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 Transport 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 storage. This data includes, wind speed, direction and atmospheric stability and joint frequency distributions.

Releases from the Millstone 375-foot Unit I stack are considered

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to be elevated at all tim es . The Pasquill stability classes were determined using the temperature gradient between the 33-foot and 447-foot levels of the meteorological tower.

Releases from the 145-foot Unit 2 vent 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 the 142-foot levels of the meteorological tower.

Releases from the 133-foot Unit 3 vent were considered as mixed mode. The Pasquill stability classes were determined using the temperature gradient between the 33-foot and the 142-foot levels of the meteorological tower.

The GASPAR code was run for continuous releases through the MP2 vent (building ventilation) and steam generator blowdown tank flashed gases, MP2 batch rel eases through the MP1 stack (containment v en'ts ) , MP2 batch rel eases through the MP1 stack (waste gas tanks), and MP2 batch releases through the MP2 vent l

(containment purges). The resulting doses were then summed to determine the total Unit 2 dose.

The GASPAR code was run for MP3 continuous releases through the {

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MP3 vent from building ventilation, MP3 batch rel eases from l

containment purges and drawdowns. The resulting doses were then '

summed to determine the total Unit 3 dose. .

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The Unit I releases are from a 375-foot elevated stack and since the use of the GASPAR semi-infinite cloud model would lead to an under-estimate of the dose due to direct exposure from the plume at distances within 2 - miles of the stack, the AIREM code was implemented to determine the maximum individual exposure from an overhead finite gamma cloud.

The AIREM code is an EPA code and uses a sector averaged-Gaussian diffusion model. It includes ground and inversion lid refl ections , radionuclides decay, first daughter in-growth, ground deposition and cloud depletion, and contributions to dose from radionuclides -in clouds at all azimuths. The ' finite cloud model used is a modified version of R. E. Cooper's _ EGAD code (3),

, 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

, a. _ Airborne Effluents 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 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 (except for Unit 1 finite cloud doses), 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 potential for dose exists.

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L For '"e: ground deposition, the maximum individual dose is calculated at the offsite maximum land location of highest:

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

l For the vegetation pathway, the maximum individual dose is calculated at the vegetable - garden of highest 0/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.

The doses. presented in Tables 1.1 through 1.3, are the maximum doses observed.

The AIREM c'.de calculates the individual, whole body and skin dose for each . sector-segment. The maximum individual dose is obtained by taking the maximum AIREM result at the offsite location where'a potential for dose 41sts and multiplying by a factor of 0.7 to compensate for building shi elding and occu'ancy.

p To determine compliance with 10CFR50 Appendix 1, the maximum individual whole body dose only includes the external pathways (plume and ground exposure) while the maxime- le vidual organ dose only includes the internal pathways. Population doses include all applicable pathways.

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Maximum- individual .and population doses are ' presented in Tabl es 1.1 through- 1.3.

b. Liquid Effluents The LADTAP code performs calculations for the following pathways: fish, s hell fish, al gae, drinking water, irrigated food, shoreline activity,. swimming and boating. At Millstone, the algae, drinking water and irrigated food pathways do not exist, and thus, only the other pathways are included in the totals.

Doses are calculated for the whole body, skin thyroid, GI-LLI, bone, live 6, kidney and lungs. Calculations are performed  ;

separately for adults, teenagers, and children.

Tabl es 2.1 through 2.3 present the doses to the whole body,  !

thyroid, and the maximum organ dose. Unless otherwise noted in the table, the doses given are adult doses.

c. , Analysis of Results The doses are well below permissible levels and small in comparison to the dose from natural background radiation. The statistical expectation of health effects from the calculated radiation dose due to plant operations is insignificant, e

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for perspective, Table 3 presents a comparison between the doses due I i

to plant operation and doses received from other sources such as the naturally occurring background l evel s . The table also presents the I I) legally allowed levels from 40CFR190. The 3 year trend is shown below.

MP RAD'CACTIVE ErFLUECS DCSE (WB) 1 Maximum Of f s:te Individal c.?S l

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

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

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, l (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), Savanrial River Laboratory, Ai ken , S.C., September, 1972.

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

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