B12846, Annual Radioactive Effluents Dose Rept for 1987

Annual Radioactive Effluents Dose Rept for 1987

ML20148G584
Person / Time
Site:	Millstone
Issue date:	12/31/1987
From:	Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
References
B12846, NUDOCS 8803290183
Download: ML20148G584 (26)

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4 NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATION UNITS NO.1,2 & 3

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ANNUAL RADIOACTIVE EFFLUENTS DOSE REPORT 1

JANUARY-DECEMBER 1987 OPERATING LICENSE NO's. DPR-21, DPR-65, & NPF-49 , \

DOCKET NO's. 50-245, 50-336. & 50-423 G

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0 TABLE OF CONTENTS SECTION PAGE

1.0 INTRODUCTION

1 2.0 0FFSITE DOSE INFORMATION 2-6 3.0 DISCUSSION OF RESULTS 7 -10 FIGURE 1 50 MILE AREA MAP TABLE 1 0FFSITE DOSE COMITMENT ( AIRBORNE)

TABLE 2 0FFSITE DOSE COM ITMENT (LIQUID)

TABLE 3 WHOLE BODY DOSE COMPARISONS APPENDIX A UPDATED TABLES I

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1.0 INTRODUCTION

1 This annual report presents a summary of the estimated offsite radiation doses from routine rel eases 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 commi tment 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 consnitments from natural background and other sources to provide perspective.

.s 2.0 0FFSITE DOSE INFORMATION In accordance with the requirements of the Technical Specifications 1.21, the offsite dose to humans from the

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and Regulatory Guide airborne and liquid radioactive effluents of Millstone have been calculated.

These estimations are performed using measured radioactive ef fluent data, measured meteorological data, and calculational models developed by the U.S. Nucl ear Regulatory Commission (NRC) and Environmental Protectior. 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 Connitment Population dose corami tmen t 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 anr.ular area surrounding the nuclear site out to a 50 mile outer radius. Figure 1 illustrates this area.

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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 Effluents Report. The site specific data includes the meteorological data (wind speed, di rection , stability, etc.) to calculate the transport and dispersion of airborne radioactive ef fl uents , dilution factors for liquid ef fl uents , 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 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, mil k , 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 effluents data into population and individual dose commitments.

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a. Airborne Radioactive Effluents l Maximum individual doses and population doses due to the release of noble gases, radiodines and particulates 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 1 noble gas plume was calculated using the computer code AIREM(2),

The GASPAR code uses the seci-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 Gt. SPAR 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 availabl e from computer storage. This data

includes, wind speed, direction and atmospheric stability aM joint frequency distributions.

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

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. i to be el eva t ed at all times. 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 ven'ts), MP2 batch releases through the MP1 stack (waste gas tanks), and MP2 batch releases through the MP2 vent (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 MP3 vent from building ventilation, MP3 batch rel eases from containment purges and drawdowns. The resulting doses were then

> summed to determine the total Unit 3 dose.

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The Unit I relea ses are from a 375-foot elevated stack and since the use of the G ASPAR 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 d eternine the maximum individual exposure from an overhead finite sanna cloud.

The AIREM code is an EPA code and uses a sector averaged Gaussian diffu si on model . It includes ground and inversion lid refl ections , ra dionu clide decay, first daughter in-growth, ground depositio n and cloud depletion, and contributions to dose from radionuclid es in clouds at all azimuths. The finite cloud model used is a nodified version of R. E. Cooper's EGAD code (3),

, b. Liquid Radioacti_ve_EfM Maximum individual and population doses due to the release of radioactive li qtaid effluents were calculated, using the computer code LADTAP(4). ,

The code i:npl ements the dose models and parameters given in Regulatory Guide 1.109 (October 1977).

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.a 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 1

thus, the dose to all other organs was less than that shown for l the thyroid.

For the dose to the maximum individual, the GASPAR program l

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.

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For the plume and inhalation pathways, the maximum individual l

(ose is calculated at the offsite location of highest decayed l

X/Q where a potential for dose exists. l l

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.a For the 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.

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 e

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 code 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 exists and multiplying by a factor of 0.7 to compensate for building shielding and

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occupancy.

To determine compliance with 10CFR50 Appendix 1, 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. Population doses include all applicable pathways.

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Maximum individual and populatien doses are presented in Tables 1.1 through 1.3.  ;

b. Liquid Effluents-The LADTAP code performs calculations for the following pathways: fish, shell fish, algae, 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-LL1, bone, liver, 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.

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'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 l evel s . The table also presents the legally allowed levels- from 40CFR190.

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

Nuclear Regulatory Cominission, 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 0.C., May,1974 (3) Cooper, R. E., EGAD - A Computer Program to Compute Dose Integrals from External Gamma Emitters, DF-1304. Nachematics and Computers (TID-4500, VC32), Savannah River Laboratory, Aiken, S.C. , September ,

1972.

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

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Table 1.1 ,

OFFSITE DOSE COMMITMENTS (AIRBORNE)

Millstone Unit 1 - 1987 Airborne Effluents 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter

1. Maximum Individual Dose (mrem)

a. Whole Body (External) 3.70E-2 @.3mi NE 4.30E-2 @ .3mi NE 2.17E-3 @1mi N 9.69E-4 @1mi ESE 4.10E-2 @1.6mi E 4.30E-2 @ .3mi NE 2.77E-3 @tmi N 1.42E-3 @lmi ESE

b. Skin (External)

c. Thyroid (Internal) 6.SCE-4 @1.6mi E 6.06E-2 @2 ENE 2.29E-3 @1.8mi NNE 6.63E-3 @2mi ENE (child) (infant) (infant) (infant) l l

2. Population Dose (Person-Rem)

(0-50 Miles)

a. Whole Body 1.26E+0 1.90E+0 8.66E-2 1.46E-2 l 2.86E+0 4.29E+0 1.52 E-1 4.99E-2

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1.29E+0 2.22E+0 8.97E-2 3.11 E-2 l c. Thyroid

3. Average Dose (mrem)

(0-50 Miles) 3.01 E-5 5.08E-6 4.38E-4 6.61 E-4

a. Whole Body 1.74E-5 9.94E-4 1.49E-3 5.29E-5

b. Skin 1.08E-5 4.49 E-4 7.72 E-4 3.12E-5

c. Thyroid

Table 1.2 i

OFFSITE DOSE COMMITMENTS (AIRBORNE)

I Millstone Unit 2 - 1987 i

Airborne Effluents 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 1 1. Maximum Individual Dose (mrem)

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a. Whole Body (External) 1.83E-3 @.4mi NE 3.11 E-3 @.4mi NE 5.32E-3 @.4mi NE 2.86E-3 @.4 NE

b. Skin (External) 5.08E-3 @.4mi NE 8.42E-3 @.4mi NE 1.48E 2 @.4mi NE 7.81 E-3 @1mi E

c. Thyroid (Internal) 3.39E-3 @.4mi NE 1.14E-1 @.4mi NE 2.02E-1 @.4mi NE 1.36E-1 @2mi ENE (teen) (child) (child) (infant)

- 2. Population Dose (Person-Rem) l (0-50 Miles) i j a. Whole Body 1.77 E-2 1.98E-2 9.10E-2 2.18E-2

b. Shin 3.44E-2 2.73 E-2 1.30E-1 3.96E-2 i c. Thyroid 2.41 E-2 1.24E-1 2.62E-1 2.55E-1 l

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3. Average Dose (mrem)

(0-50 Miles)

! a. Whole Body 6.15E-6 6.88E-6 3.16E-5 7.58E-6

' %in 1.20E-5 9.49E-6 4.52 E-5 1.38E-5 u yroid 8.38E-6 4.31 E-5 9.11 E-5 8.88E-5

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'l Table 1.3 OFFSITE DOSE COMMITMENTS (AIRBORNE)  ;

I Millstone Unit 3 - 1987 f i

Airborne Effluents 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter

1. Maximum Individual Dose (mrem) f l

a. Whole Body (External) 6.29E-4 @.4mi ENE 2.33E-3 @.4mi ENE 1.42E-6 @.4mi ENE 1.44E-2 @.4mi ENE j

b. Skin (External) 8.67E-4 @.4mi ENE 6.44E-3 @.4mi ENE 2.20E-6 @.4mi ENE 1.81 E-2 @.4mi ENE

c. Thyroid (Internal) 1.13E-3 @.4mi ENE 4.43E-2 @.5mi ENE 2.94E-3 @.5mi ENE 8.71E-2 @2mi ENE (teen) (child) (child) (infant) l

2. Population Dose (Person-Rem) i I

(0-50 Miles) l

a. Whole Body  ;

5.09E-3 4.34E-2 4.33 E-3 1.28E-2 l

b. Skin  !

5.76E-3 5.54E-2 4.33 E-3 1.86E-2 i

c. Thyroid i 5.67E-3 6.30 E-2 6.11 E-3 1.57E-1

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3. Average Dose (mrem) {

[0-50 Milet.)  :

a. Wnole Body 1.74 E-6 1.51 E-5 1.51 E-6 4.45E-6

b. Skin 2.00E-6 1.93 E-5 1.51 E-6 6.47E-6

c. Thyroid 1.97E-6 2.19 E-5 2.12E-6 5.47E-5

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Table 2.1 '.

OFFSITE DOSE COMMITMENTS (LIQUID)

Millstone Unit 1 - 1987 Liguid Effluents 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter

1. Maximum Individual Dose (mrem)

a. Whole Body 1.05E-4 1.15 E-3 3.60E-3 5.56E-3

b. Maximum Organ 1.61E-4 BONE 3.02E-3 GILLI 8.13E-3 GILLI 1.98E-2 GILLI (child)

c. Thyroid 3.54E-5 5.47 E-4 1.43 E-3 - 3.31 E-3

2. Population Dose (Person-Rem)

(0-50 Miles)

a. Whole Body 4.41 E-4 6.22 E-3 1.75E-2 3.60E-2

b. Maximum Organ 5.58E-4 9.97E-3 2.61 E-2 6.40E-2

c. Thyroid 3.22 E-4 4.98E-3 1.31 E-2 3.06E-2

3. Average Dose (mrem)

(0-50 Miles) 1.53E-7 2.16E-6 6.08E-6 1.25 E-5

a. Whole Body 1.94E-7 3.47E-6 9.08E-6 2.22 E-5

b. Maximum Organ 1.1 E-7 1.73 E-6 4.55E-6 1.06E-5

c. Thyroid

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. i OFFSITE DOSE COMMITMENTS (LIQUID) -

Millstone Unit 2 - 1987  ;

i Liquid Effluents 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter j

1. Maximum Individual Dose (mrem)

a. Whole Body 4.09 E-3 5.70E-3 7.40 E-4 9.82E-3

b. Maximum Organ 2.94 E-2 2.09E-2 3.76E-3 5.43 E-2

c. Thyroid 1.20 E-2 2.72E-3 9.58E-4 7.12 E-3 I

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2. Population Dose (Person-Rem) I (0-50 Miles)

a. Whole Body 2.28E-2 3.10E-2 4.24E-3 4.81 E-2 .

b. Maximum Organ 7.24E-2 6.02E-2 1.02 E-2 1.38E-1 i

c. Thyroid 3.02 E-2 2.37E-2 4.26E-3 3.86E-2 1

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3. Average Dose (mrem)

(0-50 Miles) i

a. Whole Body 7.92 E-6 1.08E-5 1.47E-6 1.67E-5

b. Maximum Organ 2.52E-5 2.09 E-5 3.56E-6 4.80E-5

c. Thyroid 1.05E-5 8.23E-6 1.48E-6 1.34E-5

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C Table 2.3 .

OFFSITE DOSE COMMITMENTS (LIQUID)

Millstone Unit 3 - 1987 Liquid Effluents 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter

1. Maximum Individual Dose (mrem)

a. Whole Body 3.33E-3 (child) 3.36E-3 1,36E-3 1.09E-2

b. Maximum Organ 3.66E-2 4.21 E-2 7.93 E-3 6.43 E-2

c. Thyroid 1.87E-3 1.43 E-3 6.63E 4 7.87E-3 l

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2. Population Dose (Person-Rem)

(0-50 Miles)

a. Whole Body 9.98 E-3 1.07 E-2 5.68E-3 6.02E-2

b. Maximum Organ 6.34E-2 6.98E-2 1.62 E-2 1.54E-1

c. Thyroid 5.45E-3 5.53 E-3 4.12 E-3 5.05E-2

3. Average Dose (mrem)

(0-50 Miles) ,

a. Whole Body 3.47E-6 3.72E-6 1.97E-6 2.09E-5

b. Maximum Organ 2.20E-5 2.42 E-5 5.63 E-6 5.35E-5

c. Thyroid 1.89E-6 1.92E-6 1.43 E-6 1.76E-5

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COMPARISON OF WHOLE BODY DOSES j Annual Radiation I. Doses from Station Effluents - 1987 year)

(mre A. Maximum Individual- Unit 1 Liquids 0.0104 B. Maximum Individual- Unit 1 Airborne 0.0831 C. Maximum Individual- Unit 2 Liquids 0.0204 D. Maximum Individual- Unit 2 Airborne 0.0131 E. Maximum Individual- Unit 3 Liquids 0.0190 F. Maximum Individual- Unit 3 Airborne 0.0174 ,

G. Maximum Individual - Station - Liquids 0.0498 ,i H. Maximum Individual- Station - Airborne 0.1136

l. Average Individual-(0-50 Miles)- Station - Liquids 0.000088 -

J. Average Individual - (0-50 Miles) - Station - Airborne 0.0012 f l

11. Limits from Nuclear Power Plants [-

I A. Maximum individual 25 ,

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Ill. Doses from Other Sources f A. Natural Radiation Sources in Connecticut - Cosmic, i' Terrestrial, Food Products, and Radon 270 [

l B. Radioactivity from Building Materials i (varies from Wood to Stone House) 12-34  :

C. Air Travel (Round Trip - Cross Country) 4  ;.

D. Smoking (1 pack / day) 2-20

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APPENDIX A UPDATED TABLES The following tables were updated with corrected data and are included to update your copy of the Annual Radioactive Ef fluents Dose Report for the period January - December 1986.

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TABLE 1.1 OFFSITE DOSE C0fetITMENTS (AIRBORNE)

Millstone Unit 1 - 1986 .

AIRBORNE EFFLUENTS 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

1. Maximum Individual Dose (mrem) ,

a. Whole Body (External) 2.75E-3 @lmi ENE 2.10E-2 @.3ml NE 4.60E-2 @.3ml NE 1.50E-1 s.3mi NE

b. Skin (External) 3.35E-3 @lmi ENE 2.10E-2 @.3mi NE 4.60E-2 @.3mi NE 1.50E-1 s.3mi NE

c. Thyroid (Internal) 5.98E-5 @l.6mi ENE 9.82E-3 @l.8miNNE 4.85E-2 @l.8mlNNE 9.75E-2 32mi ENE (child) (infant) (infant) (Infant)

2. Population Dose (Person-Rem)

(0-50 Miles)

a. Whole Body 2.75E-2 5.52E-1 1.42E+0 4.16E-1

b. Skin 5.18E-2 1.24E+0 _ 3.18E+0 1.00E+0

c. Thyroid 2.92E-2 6.25E-1 1.55E+0 6.10E-1

3. Average Dose (mrem)

(0-50 Miles)

a. Whole Body 9.56E-6 1.92E-4 4.94E-4 1.45E-4

b. Skin 1.80E-5 4.31E-4 1.11E-3 3.48E-4

c. Thyroid 1.01E-5 2.17E-4 5 39E-4 2.12E-4

~

~

a TABLE 1.3 ,

OFFSITE DOSE C0fMITMENTS (AIRBORNE)

Hillstone Unit 3 - 1986 AIRBORNE EFFLUENTS lst Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

s

1. Maximum Individual Dose (arem)

a. Whole Body (External) 3.71E-5 @.4miSSW 5.94E-5 @.4ml NW 3.42E-4 @.5mi NE 8.29E-5 @.4mi SSE

b. Skin (External) 8.66E-5 e.4miSSW 1.67E-4 @.4mi NW 7.11E-4 @.5ml NE 2.32E-4 @.4mi SSE

c. T.yroid (Internal) 6.11 E-3 @.4mISSW 2.33E-1 0.5miENE 3.95E-2 @.5mi NE 6.61E-3 @.4mi SSE (teen) (child) (infant) (teen)

2. Population Dose (Person-Rem) 0-50 Miles)

a. Whole Body 2.65E-2 6.60E-1 8.18E-2 3.48E-2

b. Skin 2.65E-2 6.60E-1 8.50E-2 3.53E-2

c. Thyroid 2.65E-2 6.63E-1 9.99E-2 3.67E-2

3. Average Dose (mrem)

D-50 Miles)

a. Whole Body 9.21E-6 2.29E-4 2.84E-5 1.21E-5

b. Skin 9.21E-6 2.29E-4 2.96E-5 1.23E-5

c. Thyroid 9.21E-6 2.31E-4 3.47E-5 1.28E-5

TABLE 2.1 .

• r OFFSITE DOSE COMITNENTS (LIQUID)

MILLSTONE UNIT 1 - 1986 j LIQUID EFFLUENTS 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

1. Maximum Individual Dose (mrem)

a. Whole Body 2.16E-4 5.15E-3 2.19E-3 4.00E-5

b. Maximum Organ

• 1.14E-3 7.19E-3 teen 3.03E-3 teen 1.46E-4 child 1.4 8E-3 l

c. Thyroid 6.64E-5 1.44E-3 1.24E-5

2. Population Dose (Person-Rem)

(0-50 miles)

a. Whole Body 9.05E-4 1.91E-2 8.36E-3 1.74E-4

b. Maximum Organ

• 2.36E-3 2.34E-2 1.01E-2 1.30E-3

c. Thyroid 6.11E-4 1.38E-2 7.12E-3 1.13E-4

3. Average Dose (arem)

(0-50 miles)

a. Whole Body 3.15E-7 6.64E-6 2 91E-6 6.05E-8

b. Maximum Organ

• 8.21E-7 8.14E-6 3. 51 E-6 4.52E-7

c. Thyroid 2.12E-7 4.80E-6 2.48E-6 3.93E-8

• 1st Qtr - CI(LL!); 2nd anJ 3rd Qtr - Liver; 4th Qtr - Bone

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NAST UTILITIES o.n.r.i Oii,c.. . s.io.n sir..i. Be riin. Conn.ciicui 9 ' 57[$$

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c'A~ P.O. 80X 270 HARTFORD. CONNECTICVT 061414270 L L J [.[Z,3C',[~, (203) 665-5000 March 25, 1988 Docket Nos. 50-245 50-336 50-423 B12846 Re: 10CFR50.36a U.S. Nuclear Regulatory Contnission Attn: Document Control Desk Washington, D.C. 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 commitment resulting from routine radioactive airborne and liquid effluents for the period of January through December 1987. Copies of the report are being forwarded in accordance with the provisions of 10CFR50.4(b)(1).

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY u

E y Mroczka/

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

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