ML20206E384

Forwards Annual Radioactive Effluent Dose Repts for Listed Plants

ML20206E384
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	04/07/1987
From:	Rodgers R NORTHEAST UTILITIES
To:	Bottomley R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NE-87-RA-332, NUDOCS 8704130597
Download: ML20206E384 (1)

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April 07,1987 NE-87-RA-332 Mr. R. Bottomley Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission c/o Distribution Services Branch DDC, ADM Washington, D.C. 20555

Dear Mr. Bottomley:

Attached are your copies of the Annual Rr.dioactive Effluents Dose Report for Millstone Units #1, # 2 and #3 and Connecticut Yankee. These reports have been submitted to the Nuclear Regulatory Commission as per the Stations' Technical Specifications and the requirements of 10CFR50.36a.

Very truly yours, Reginald C. Rodgers, Ph.D., Manager Radiological Assessment Branch RCR/jha Attachments s

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ANNUAL RADI0 ACTIVE EFFLUENTS DOSE REPORT JANUARY-DECEMBER 1986 OPERATING LICENSE N0's. DPR-21, DPR-65, & NPF-49 DOCKET N0's. 50-245, 50-336, & 50-423

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(203) 665-5000 March 30,1987 Docket No. 50-245 50-336 50-423 B12471 Re: 10 CFR 50.36a U.S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.C. 20555

Reference:

(1)

E. 3. Mroczka letter to the U. S. Nuclear Regulatory Commission," Semiannual Radioactive Effluent Release Report," dated February 27,1987.

Gentlemen:

Millstone Nuclear Power Station, Unit Nos.1,2 and 3 Annual Radioactive Effluents Dose Report in accordance with the requirements of 10 CFR 50.36a and the Radiological Effluent Technical Specifications, 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 - December,1986. Copies of the report are being forwarded in accordance with the provisions of 10 CFR 50.4(b)(1).

Delayed sample analysis of Sr-89, Sr-90, Fe-55, and gross alpha for the last quarter of 1986, as noted in Reference (1), have been completed, and updated tables are included as Appendix A in this report.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 4.

W E. 3. Mroftik~a

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Senior Vice President e

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Dr. T. E. Murley, Region I Administrator J. 3. Shea, NRC Project Manager, Millstone Unit No.1 D. H. Jaf fe, NRC Project Manager, Millstone Unit No. 2 E. L. Doolittle, NRC Project Manager, Millstone Unit No. 3 T. Rebelowski, Resident inspector, Millstone Unit Nos. I and 2

3. T. Shediosky, Resident Inspector, Millstone Unit No. 3 o

TABLE OF CONTENTS SECTION PAGE

1.0 INTRODUCTION

i 2.0 0FFSITE DOSE INFORMATION 2-6 3.0 DISCUSSION OF RESULTS 3-10 FIGURE 1 50 MILE AREA MAP TABLE 1 0FFSITE DOSE C0fetITMENT (AIRBORNE)

TABLE 2 0FFSITE DOSE C0fetITMENT (LIQUID)

TABLE 3 WHOLE BODY DOSE COMPARISONS APPENDIX A UPDATED TABLES FOR THE SEMIANNUAL EFFLUENTS RELEASE REPORT: JULY - DECEMBER 1986 1

D

7

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 radiation doses resulting from the calendar ' year of airborne and j

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 1

individual doses with units of Person-Rem.

i 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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f-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.

Figure 1 illustrates this area.

r The radiation doses resulting from one calendar year of airborne and liquid effluents are integrated over a 50 year period, taking into account the radioactive decay and biological elimination of the radioactive meterials 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 specific data, and generic factors.

The radioactive source term (units of Curi es) is obtained from the Semiannual Radioactive Effluents Report.

The site specific data includes the meteorological data (wind speed, direction, stability, etc.)

to calculate the transport and dispersion of airborne radioactive effluents, dilution factors for liquid effluents, 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 fish.

The generic data includes the annual average consumption rates (inhalation of air and ingestion of fruits, vegetables, leafy vegetabl 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 effluents data into population and individual dose commitments..

r-

.a.

Airborne Radioactive Effluents 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 usir.g 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 ireplements the assumptions given in Section C of NRC Regulatory Guide 1.111,

" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Rcutine Releases from Light-Water-Cooled 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,

'l

r 4

4 to be elevated - 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.

m.

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,

radionuclide

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 l

Maximum individual and population doses due to the release of radioactive liquid effluente were calculated using the ccaputer code LADTAP(4).

The code impl ements the dose models and parameters given in Regulatory Guide 1.109 (October 1977),

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1

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 I 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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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 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.

}

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

doses observed.

-l l

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 of fsite location where'a potential for dose exists and multiplying by a factor of 0.7 to compensate for building shielding and o'ccupancy.

i i

i To determine compliance with 10CFR50 Appendix I,

the maximum I

individual whole body dose only includes the external-pathways 4

(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 population doses are presented in Tables 1.1 through 1.3.

v 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.

I Doses are calculated for the whole body, skin thyroid, GI-LLI, bone, liver, kidney and lungs.

Calculations are performed separately for adults, teenagers, and children.

Tables 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 levels.

The table also presents the i

legally allowed levels from 40CFR190.

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i FOOTNOTES (1)

GASPAR Dose Code, K. F. Eckerman, Radiological Assessment Branch, U.S.

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

A computer Code for Calculating Doses, (2)

AIREM Program Manual 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 Of fice 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 - U. S. Nuclear Regulatory Commission; Washington, D. C.

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MILLSTONE PLANT O

50-MILE

TABLE 1.1 0FFSITE DOSE C0petITMENTS (AIRBORNE)

Millstone Unit 1 - 1986 AIRBORNE EFFLUENTS Ist Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

1.

Maximum Individual Dose (mrem) a.

Whole Body (External) 2.75E-3 @lmi ESE 2.10E-2 @.3mi NE 4.60E-2 @.3mi NE 1.50E-1 ?.3mi NE b.

Skin (External) 3 35E-3 @lmi ESE 2.10E-2 @.3mi NE 4.60E-2 @.3mi NE 1.50E-1 s.3mi NE c.

Thyroid (Internal) 5 98E-5 @lmi ESE 9.82E-3 @l.8miNNE 4.85E-2 @l.8miNNE 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-1 6.10E-1 3.

Average Dose (mrem)

(0-50 MIIes) j 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

+

TABLE 1.2 0FFSITE DOSE COMITNENTS (AIRBORNE) liillstone Unit 2 - 1986 AIRBORNE EFFLUENTS 1st Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

1.

Maximum Individual _D:se (mrem) a.

Whole Body (External) 2.03E-3 @.4mi NE 1.90E-3 @.4ml NE 5.46E-3 @.4mi HE 1.14E-4 91mi E b.

Skin (External) 4.82E-3 @.4mi NE 3.91E-3 @.4mi NE 1.24E-2 @.4mi NE 1.66E-4 @lmi E c.

Thyroid (Internal) 2 32E-3 @.4mi NE 5.82E-2 @.4mi NE 6.81E-1 @.4ml NE 1.44E-2 @2mi ENE (teen)

(child)

(child)

(infant)

2. - Population Dose (Person-Rem)

(0-50 Miles) a.

Whole Body 1.19E-2 2.72E-2 1.07E-1 5.73E-3 b.

Skin 2.14E-2 3.59E-2 1.32E-1 5.72E-3 c.

Thyroid 1.28E-2 8.17E-2 5.95E-1 3 14E-2 3.

Average Dose (mrem)

(0-50 Miles) a.

Whole Body 4.13E-6 9.46E-6 3 72E-5 1.99E-6 b.

Skin 7.44E-6 1.25E-5 4.59E-5 1.99E-6 c.

Thyroid 4.43E-6 2.84E-5.

2.07E-4 1.09E-5

TABLE 1.3 0FFSITE DOSE C0pMITMENTS (AIRBORNE) i Millstone Unit 3 - 1986 AIRBORNE EFFLUENTS 1st Otr.

2nd Otr.

3rd Qtr.

4th Qtr.

s 1.

Maximum Individual Dose (mrem) a.

Whole Body (External) 3 71E-5 @.4mISSW 5.94E-5 @.4mi NW 3.42E-4 @.5mi NE 8.29E-5 @.4mi SSE b.

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

Thyroid (Internal) 1.59E-3 e.4miSSW 2.33E-1 @.5miENE 3.95E-2 @.5mi NE 6.61E-3 @.4mi SSE (teen)

(child)

(infant)

(teen) i 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 M11es) 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 0FFSITE DOSE C0fetITNENTS (LIQUID)

MILLSTONE UNIT 1 - 1986 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 een 1.46E-4 t

child c.

Thyroid 6.64E-5 8.30E-4chiId 1.44E-3 1.24E-5 1

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 (mrem)

(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 - Gl(LLI); 2nd and 3rd Qtr - Liver; 4th Qtr - Bone

TABLE 2.2 0FFSITE DOSE COMITMENTS (LIQllID)

MILLSTONE UNIT 2 - 1986 LIQUID EFFLUENTS 1st Otr.

2nd Otr.

3rd Otr.

4th Otr.

1.

Maximum Individual Dose (mrem) a.

Whole Body 4.24E-3 3.99E-3 1.11E-2 1.09E-2 teen b.

Maximum Organ Gl(LLI) 1.48E-2 6.56E-3 4.08E-2 1.09E-1 c.

Thyroid 1.80E-3 3.21E-3 1.05E-2 4.65E-3 teen 2.

Population Dose (Person-Rem)

(0-50 miles) a.

Whole Body 2.08E-2 1.64E-2 6.56E-2 5.67E-2 b.

Maximum Organ G1 ( LLI) 5.86E-2 2.23E-2 1.24E-1 2.33E-1 c.

Thyroid 1.64E-2 1.41E-2 5.88E-2 4.13E-2 3.

Average Dose (mrem)

(0-50 mi1es) a.

Whole Body 7.23E-6 5.70E-6 2.28E-5 1.97E-5 b.

Maximum Organ Gl ( LLI) 2.04E-5 7.75E-6 4.31E-5 8.10E-5 c.

Thyroid 5.70E-6 4.90E-6 2.04E-5 1.44E-5

TABLE 2.3 i

0FFSITE DOSE C0petITMENTS (LIQUID)

MILLSTONE UNIT 3 - 1986 LIQUID EFFLUENTS 1st Qtr.

2nd Qtr.

3rd Qtr.

4th Otr.

1.

Maximum, Individual Dose (mrem) a.

Whole Body 9.07E-6 2.50E-4 1.27E-3 een 2.67E-4 t

b.

Maximum Organ Gl(LLI) 4.57E-5 3.06E-3 2.15E-2 1.20E-2 c.

Thyroid 3.93E-Schild 9.63E-4 child 2.14E-3 child 2.71E-4 2.

Population Dose (Person-Rem)

(0-50 miles) a.

Whole Body 3.38E-5 8.23E-4 4.04E-3 8.30E-4 b.

Maximum Organ Gl(LLI) 1.05E-4 5.65E-3 3 30E-2 1.22E-2 c.

Thyroid 4.43E-5 1.28E-3 3.42E-3 6.44E-4 3.

Average Dose (mrem)

(0-50 miles) a.

Whole Body 1.18E-8 2.86E-7 1.41E-6 2.8'E-7 b.

Maximum Organ GI (LLl) 3.65E-8 1.96E-6 1.15E-5 4.24E-6 c.

Thyroid 1.54E-8 4.45E-7 1.19E-6 2.24E-7

i TABLE 3 COMPARISON OF WHOLE BODY DOSES I.

Doses from Station Effluents - 1986 mrem A.

Maximum Individual - Unit 1 Liquids 7.60E-3 8.

Maximum Individual - Unit 1 Airborne 2.20E-1 C.

Maximum Individual - Unit 2 Liquids 3.02E-2 0.

Maximum Individual - Unit 2 Airborne 9.97E-3 E.

Maximum Individual - Unit 3 Liquids 1.80E-3 F.

Maximum Individual - Unit 3 Airborne 5.21E-4 G.

Maximum Individual - Millstone Station Liquids 3.96E-2 H.

Maximum Individual - Millstone Station Airborne 2.30E-1 I.

Average Individual - (0-50 Miles) - Station Airborne 1.17E-3

~

J.

Average Individual - (0-50 Miles) - Station Liquids 6.7 E-5 II. Limits from Nuclear Power Plants A.

Maximum Individual 25 III. Doses from Other Sources A.

Natural Background in Connecticut - Cosmic, Terrestrial and Food Products 125 B.

Radioactivity from Building Materials (varies from Wood to Stone House) 12-34 C.

Medical X Ray 30-70 0.

Air Travel (Round Trip - Cross Country) 4

/

/

r

APPENDIX A UPDATED TABLES FOR THE SEMIANNUAL E[RUENT RELEASE REPORT:

JULY - DECEMBER 1986 W

The following tables with the required data (Sr-89, Sr-90 and gross A) are included to update your copy of the Semiannual Effluent Release Report for the period July - December 1986.

'l o

4 9

4 a

e

,r

I Ttble 2.2-1 l

MILL 510NE NUCLEAR F0WER STATION UNIT #2 l

LIQUID EFFLUENT - SUte(ATION OF ALL SELEASES l

' QUARTERLY I UNITS October November December TgrALg TEAR 1986 A. Fission and Activation Products C1 8.01E-41 5 71E-01 8.06E-01 2.18E+00

1. TOTAL ACTIVIIT RELEASED

2. AVERACE DILUIED UC1/m1 2.85E-07 2.43E-07 1.63E-08 4.00E-08 ACTIVIIT DURING PERIOD

5. Tritium

1. TOIAL ACIIVITY Ci 4.38E+00 3.10E+00 3.381+00 1.29E+01 RE1. EASED

2. AVERACE DILUIED UC1/mi 1 56E-06 1.32E-06 1.09E-0/

2.37E-07 ACTIVITY DURING PERIOD I

C. Dissolved and Entrained Cases

1. TOTAL ACTIVITY 1.15E-04 3.11E-03 C1 2.99E-03 agLgAggy 4

2. AVERAGE D1 LUTED VC1/a1 1.06E-09 2 33E-12 5.71E-Il ACTIVIIT DURING PERIOD l

B. Gross Alpha

1. TOTAL ACTIVITY Ci 7,ggg_o$

6 9.39E-05 61.53E-03 61.53E-03 MED l

E. Volume I

1.10LUME OF WASTE LITERS 1.33E+06 9.391+05 2.79EM7 3.02E+07 RELEA5ED l

2. TOLUME OF DILUTION L TERS 1.13E+10 7.02E+09 1.185+10 3.01E+10 DURINC RELEASES LITERS 2.81E+09 2.35EM9 4.93E+10 5.45E+10 10D includes Unit 1 dilution for periods of releases while shutdown (for MPC calculation'

\\

l

\\

l

Table 2.2-z i

MILL 8 TONE NUCi2AR 70WER STATION UNIT #2 Year _

1986 LIQUID EFFLUENTS - 00NT1WU008 - 8/0

$I7 Nuclides Esleased Unit October November December Ci Ci j

Co-58 C1 6.65E-03 6.65E-03 1.79E-02 1.79E-02 Co-60 Ci 1

1-133 Ci 3 04E-03 3.04E-03 Ci

~

~

7.46E-03 7.46E-03_

Co-134 Ci 4

C1 et M

7 u

c1 c1 21 c1 ei

_ Ci C1 i

Fe-55 gg 3.06E-02

_3.06E-02 66.361-04 l

87-89 eg i

ar-en c1 41.91E-04 6.57E-02 6 57E-02 1

Total Activity ei j

s.2n.<a

8. 2n-o2 u-3 Es-133 m

i l

l In-111 21 Ia-1SSM gg 61 53E-Oi i

crema A1.hm ti l!,

ci

~

Ci

Table 2.2-3 MILLSTONE NUCLEAR POWER STATION UNIT #2 Year 1986 LMJID ErrTErrs. iwr m. Auwr/c Mr /TK10-11 Nuclides Released Unit October November December 1.24E-04 1.32E-04 Cel144 Ci 7.943-06 Cr-51 Ci 4.48E-02 1.36E-02 3.62E-02 9.46E-02 Ma-54 Ci 4.6_4E-03 1.17E-02 5.22E-03 2.16E-02 La-140 Ci 2.41E-03 1.42E-03 5.80E 04 4.41E-03 Co-58 Ci 3.58E-01 2.38E-01 2.89E-01 8.85E-0_1_.

Cc-60 C1 1.79E-01 1.25E-01 2.64E-01_

5.68E-01 9.12E-05 1-131 Ci 9.12E-05 1.19E-04

1. 74 E-02 1-133 C1 1.73E-02 Zr-95 C1 2.70E-03 2.87Z-04 1.97E-03 4.96E-03 Co-134 Ci 6.30E-05 1.97E-03 2.80E-03 4.83E-03 Cs-137 Ci

_4.65E-03 1.20E-0_2_

_2.05E-02 3.72E-02 Ru-103 et 3.23E-04 2.94E-04 2.63E__04 8.80E-04 _

Co-57 ci 1.04E-03

__6.69E-44 8.37E-04_

2.55E-03 Ag-110m ci

_5.04E-03 4.74E-03_

3.95E-03 1.37E-02_

4 sr-92 ci 1.93E-03 1.70E-03 1.40E-03 5.03E-03 Fe-59 ci 1.25E 3.65E-05 3.28E-04 1.61E-03 6.87E-03 1.64E-02__

Kb-95 ci 6.34E-03 3_.19E-03_

Eb-9

ci 7.76E-03_

8.59E-03 6.48E-03 2.28E-02 Sb-124 C1 1.67E-02 2.38E-02 1.57E-02 5.62E-02 Sb-125 ci 2.34E-02 7.24E-02 3.11E-02 1.27E-01 Ka-24 ci 3.40E-04_

5.38E-04 1.85E-04 1.06E-03 Fe-55 ci __

1.20E-01 5_.07E-02 4.74F-07 7.21F-01 Br-89 ci 2.13E-04 4.32E-04 1.81F-Oh 8 ?RF AL 8.83E-05 3.81E-05 1.49E-04 ar so ci 2.26E-45_

8.01E-Cl 5.71E-01 7.40E-01 2.11E+00 Total Activity ci H-3 Ci 4.38E+00 3.10E+00 5_ _. 38E+00 1.29E+01 2.961-05 3.02E-03_

I'~I33 c1 2.99E-03 4.59E-051 4_.59E-05 Ma-lia ci 3.95E-05 3.95E-05 Ar-41 c1 i

Gross Aloha ci 17.98E-05 59.39E-05 41.90F-Oh

Table 2.2-4 NILLSfollE NUCLEAR POWER STATION WIT #2 GASEOUS EFTLUENTS - SUMMATION OF ALL RELEASES T

a QUARTI 2LY October November December TOTALS YEAR 1986 A. Fission and Activation Geses Ci 2.20E-01 2.05E-02 2.41E-01

2. AVERAGE RELEASE RATE UC1/sec 8.21E-02 7.65E-03 3.03E-02 FOR THE PERIOD L

I

3. Iedines

1. TOTAL I-131 ACTIVITT C1 2.34E-04 3.70E-06 2.3BE-04 REEASED 1

-2. AVERAGE RELEASE RATE UCi/sec 9.32E-05 1.53E-06 2.99E-05 FOR THE PERIOD l

L C. Particulates

1. TOTAL FARTICULATE i

5.21E-06 1.12E-05 7.94E-06 2.44E-05 ACTIVITY RELEASED

~

2. AVERACE RELEASE RATE Uci/sec 2.08E-06 4.63E-06 2.631-06 3.07E-06 FOR THE FERIOD

3. TOTAL GROSS ALPHA C1 ACTIVITY RELEASED 12.14E-07 61.73E-07 62.19E-07 62.19E-07 i

s i

D. Tritium _

1. TOTAL ACTIVITT A

3 24E+00 2.84E+00 3.46E+00 9.54E+00 RELEASED

?

2. AVERACE RELEASE RATE UCi/sec FOR THE PERIOD 1.29E+00 1.17E+00 1.15E+00 1.20E+00 i.

. -.. - -.....l

Table 2.2-5 j

MILLSTONE NUCLEAR POWER STATION - UNIT #2 SABE005 EFF15ENTS - MIXED RELIASE - CONTINUOUS MtEE Tear 1986

[ tac 11 des heleased l Snit l06tober l November December ta

1. Ffssion genes

~

z les Cf En.er _

C1 8948 C1 Es ass C1 3e-135 C1 Mn C1 E>-se C1 him Cf Es 1h C1 Ep.Sh CT Re.11m et Es.1 h 14 E>-SS tt Ar-77 ft Total Ptpr parted tt

3. ledines

_ tedine-12.

C1 2.34E-04 3.70E-06 2.38E-04 tedine.133 C1 1.99E-05 5.90E-06 2.58E_-05

3. perttem1stes Ru-103 C1 1.49E-06 1.49E-06 m.u C1 Fe-59 et Co-58

__ C1 _

2.71E-06 3.60E-06 6.31E-06 l

Co-60 C1

_~

4_.871-06 4.34E-06 9.21I-06_

Es-65 m

l I-131 et Co-134 21 Co-137 C1

1. 0_1 E'-06~

6.34E-06 7.35E-06 ma-140 C1 Co-141

$1 Co-144 cs 4

j l

Gross Alpha C1

.52.14E-07 41.7hE-07_42.19E-07

.51.43E-07_ 62.03E-07 62.63E-07 Sr-89 31 Br-to C1

.s2.14E-08 4 4.16_E-08

+3.50_E-08 Es C1 3.24FA00 2 84E+00 3 46E+00 9.54E+00 21

/

Table 2.3-1 MILLSTONE 1RIIT Wo. 3 smenTION OF LIQUID EFFLUENT EELEASES I

I i

y UNITS October November December TOTA 1.5

' TEAR 1986 A. Fission and Activation Products Ci 3.984E-02 3.71E-02 3.08E-02 1.08E-01 g

2. AVERAGE DILUT D pggg 1.266E-09 5.54E-09 4.55E-09 1.14E-08 ACTIVITY DURINC FERIOD

3. Tritiva

1. TOT ACTI M Ci 85.0 47.13 37.22 169.35 g

2.. AVERAGE DILLTED UC1/ml 6.1 E-06 7.03E-06 5.48E-06 6.2 E-06 ACTIVITY DURING FERIOD C. Dissolved and Estrained Gases

1. TOTAL ACTIVITY C1 2.63E-02 2.61E-03 2.89E-03 3.18E-02 RELEASE i

2. AVERAGE DILUTED UCi/81 1.89E-09 3.89E-10 4.25E-10 9.10E-10 ACTIVITY DURINC PERIOD D. Cross Alphe Ci

<1.57E-04 II.36E-04 11.53E-04 61.49E-04

1. TOTAL ACTIVITT i

RELEASED 4

i E. Volume

[

I*

LITERS 3.146E+06 1.51E+06

1. 53E+06 6.19EK)6 2.

M MW LITERS 1.393E+10 6.W E+09 6.79E+09 2.74E+10 3

lI LITERS 1.479E+11 1.528E+11 1.59E+11 4.597E+11 PER 0D I

l

l Table 2.3-3 i

I WILL8 TONE UNIT No. 3 Year 1986 LIQUID RAD WASTE IFFLUElffS - BATCR - LWS 1

i Nuclides Released Unit October November December 9"*" * *1Y

=

l Cr-51 Ci 4.46E-0",

2.22E-03 9.59E-04 7.64E-03 j

h-54 C1 2.57E-03 2.96E-03 2.83E-03

. 8.36E-03 Tc-99M C1 2.903E-05 2.99E-05 5.893E-05 Co-38 C1 1.85E-02 1.36E-02 1.25E-02 4.46E-02 Co-60 C1 1.17E-03 1.31E-03 1_. 25 E-03 3.73E-03 1-131 C1 4.68E-04 5.62E-04 6.12E-04 1.642E-03' I-133 C1 9.65E-04 5.82E-OL 7.77E-04 2.324E-03 1-135 C1 3.05E-04 3 05E-04 Co-134 C1 Co-137 Ci Mo-99 cf t

Co-141 c,

Ca-1LL ci l

En-65 c1 Fe-59 1

c1 5.5 E-04 4.12E-04 1.97E-04 1.159E-03 Na-24 c1 7.52E-03 1.1 E-02 8.54E-03 _

2.706E-02 Zr-95 ci 1.25E-03 1.63E-03 1.0_2E-03 3.90E-03 l

Nb-95 ci 1.93E-03 2.84E-03 1.74E-03 _

6.51E-03 j

Co-57 ci 1.15E-05 1.49E-05 2.64E-05 Total C1 3.972E-02 3.713I-02 3.047E-02 1.073E-0_1 ci 13.146E_-03 11.51r-01 61.53E-b3 n2.06E-03 Fe-55 If*89 c1 1.195E-04 fr.01r-ns 2.75E-04 3.95E-04_

K.01E-05_ 61.53E-05 62.35E-05 l

Er-en ci 12,52E-05 3

.984E-02 Total Activity c1 3.71E-02 3.07E-02 1.08E-01 Xe-133M 4.82E-05 4.82E-05 X8"I33 ci 2.47E-02

__1. 38 E-03 1.67E-03 2.775E-02 re-lis c1 1.5 E-03 1.23E-03 1.22E-03 3.95E-03 I**13SM c1 7.44E-05 7.44E-05 ci cen.. At,A.

c1 11.'i7E-nt II.36E-04 61.53E-04 61.49E-04 i*

R-3 c1

_85.0 47.13 37.22 169.35 i

/

Table 2.3-5 MILLSTONE UNIT No. 3

$UMMATION OF GASEOUS EFFLUENT RELEAS18 i'

i a

WE QUARTERLY October November December TOTALE TEAR 1986 A. Fission _ and Act_1vation Gases

1. TOTAL ACTIVITY Ci RELEASED 6.08E+00 7.34E-02 1.34E-02 6.17E+00

2. AVERAGE RELIASE RATE Uci/ set FOR THE PERIOD 2.27E+00 2.83E-02 5.74E-03

.8118 J

I B. Iodines j

1. TOTAL I-131 ACTIVITY C1 8.95E-06 5.21E-06 6.03E-06 2.019E-05 RELEASED 1

2. AVERAGE RELEASE RATE' UCi/888 3.34E-06 2.012E-06 2 59E-06 2.65E-06 FOR THE PERIOD C. Particuistes

1. TOTAL FARTICULATE UA 5.63E-07 41.32E-06 fl.11E-06

{

ACTIVITY RELEASE 11.46E-06 5

E RAM 1.17E-07 6 5.67E-07 64.43E-07 UC1/sec 15.45E-07 2

pgg l

=

j

3. TOTAL GROSS ALPHA Ci 9.25E-09 5 8.14E-07 3.28E-07 9 25E-09 ACTIVITY RELEASED 1

!i D. Tritium _

C1 16.86 2.55 60.7 80.11 g

3. AVERAGE RELEASE RATE UCi/888 6.29 984 26.05 11.1 i

FOR THE PERIOD

Table 2.3-6 MILLSTONE UNIT No. 3 - GASEOUS EFFLUENT - CONTINUOU$

NORMAL VENTILATION Year 1986

[ abc1tdes teleased j Unit october l November December IF

1. Finsten gases an.nu _

Ct a

t2 C1 C1 EMS E>88m C1 amus C1

-_ _Es-123 C1 6.0BE+00 6.caren tr.09 C1

%11r C1

._ e him C1 te.33s C1 3a.1 h tt w a_m s

eq A>27 ft total Per period tt 6.08E+00

_~

6.08E+00 E. ledines tod{ne.131 Ci 8_.95E-06 5.211-06 6.03E-06 2.02r-os tedine.133 Ci_

1.212E-os 1.new nt A.oir-nA 2.00r At

3. Partssulates Cr-51

?

Cl C1 m.nA Fe-59_

_ C1 Co-58 gg Co-60 Ci En-65 en I-131 et Cs-134

__Cf Co-137 Ct sa-1_40 Ct Co-141_

__ $1 Co-144 Ci Sr-89 c1 11.2 E-06

_5A _ m t m n? 61_.61E 6

61. 09 E-06' sr-95 i

Ct

.12.4 E-07 s.05 1-og 6 3.21 E-07 62.14E-07 a

a Total C1 11.Lar-nx 55.63_E-07 6 1. 93 E-06 61.31E-06 C1 H-3 Ct 16.78 2143 60.sa 79.79 Crose Alpha ti f.a. 01 E-07_

Sa.0L_r 07 63.21E-07 66.42E-07_

Ci

Table 2.3-7 MILLSTOME UNIT No. 3 - GASEQUS EFFLUENT - CONTINUOUS Year 1986

[ helfdes blessed l Weit October l _ November December l$'[F j

1. Ffssion gases 2

-iu

_Cs C1 n

C1 M

+

E M an 81 amass C1 l

2n.in C1 7.34E-02 1.34E-02 8.68E-02 n.se C1 mmm C1

. p. t m gi a

up san 81 Is.itta El _

ns.in.

et I

Elr=89 2t

_ Ar.Sf et total For parted et 7.ur-o2

1. ur-o2 a.sar-o2 1

3. ledines j

testne.131 C1_

12.09E-07 11.53I-07 s1.74E-07 15.36r-07 sedine 133 C1 53 55E-07 12.48E-07 12.37E-07

<m.4 E-07 j

8. fertisslates i

i Cr-51 C1 j

h-t A C1 Fe-59 et Co-38 gg Co-60 c1 i

En-65 et 1-131 11 j

Co-134 -

C1 Cs-137 Cf Re-140 Cf

)

Co-141 Cf t

co-144 C1 Sr-89 et 11.ast-on 11.67r-09 62.20E-08_. $1.54E-08 n

$r-90'

$1

.17.4 E-09_ $1,igy-no 6.18E-09. 65.40r-09.

7 Total C9

.52.59E 08 $6.anr-on 6 2.94E-08_ $1.18F-OR 81 1.10r.01 1.2Ar-01 1.99r A*

,L H-3 Ci 7.AaW-02.

Cross Aloha C1 e. nt-on la An na 57.38E-09 9.25E-09_

i e

1

- =

x xv

- - - ~,. -:: -

=~w m

=,

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CONNECTICUT: YANKEE!ATOMICPOWERCOMPANY$

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HADDAM NECK PLANT:

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ANNUAL RADI0 ACTIVE EFFLUENTS DOSE REPORT.

n

.g i

JANUARY-DECEMBER 1986 i

DOCKET NO. 50-213 LICENSE DPR-61 s

{

• ---b d

~'

+

CONNECTICUT YANKEE ATOMIC POWER COMPANY B E R L I N, CONNECTICUT P o box 270 HARTFORD, CONNECTICUT 06141-0270 TELEPHONE 203-665-5000 March 30,1987 Docket No. 50-213 B12472 Re: 10 CFR 50.36a U.S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.C. 20555 References (1)

E. 3. Mroczka letter to the U. S. Nuclear Regulatory Commission, " Semiannual Radioactive Ef fluent Release Report," dated February 27,1987.

Gentlemen:

Haddam Neck Plant Annual Radioactive Effluents Dose Report in accordance with the requirements of 10 CFR 50.36a and the Radiological Effluent Technical Specifications, 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 - December,1986. Copies of the report are being forwarded in accordance with the provisions of 10 CFR 50.4(b)(1).

Delayed sample analysis of Sr-89, Sr-90, and gross alpha for the last quarter of 1986, as noted in Reference (1), have been completed, and updated tables are included as Appendix A in this report.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY M fW E. J.-Mpfczka 4'

Senior'Vice President cc:

Dr. T. E. Murley, Region I Administrator F. M. Akstulewicz, NRC Project Manager, Haddam Neck Plant P. D. Swetland, Resident inspector, Haddam Neck Plant

/

/

TABLE OF CONTENTS SECTION PAGE 1

1.0 INTRODUCTION

1 2.0 0FFSITE DOSE INFORMATION 2-5 i

3.0 DISCUSSION OF RESULTS 3-8 j

i FIGURE 1 50 MILE AREA MAP TABLE 1 0FFSITE DOSE COMITMENT (AIRBORNE)

TABLE 2 0FFSITE DOSE COMITMENT (LIQUID) i TABLE 3 WHOLE BODY DOSE COMPARISONS I

APPENDIX A UPDATED TABLES FOR THE SEMIANNUAL EFFLUENTS RELEASE REPORT: JULY - DECEMBER 1986 P

i I

i t

e

1.0 INTRODUCTION

This annual report presents a sumary o f-the estimated offsite 4

radiation doses from routine releases of radioactive materials in airborne and liquid effluents for each unit.

These include the annual population dose comitments (Person-Rem) for the annular region out to 50 miles from the site, the annual average dose comitment (mrem) to the population and the annual maximum dose comitment (mrem) to any real member of the public, e

I The radiation doses resulting from the calendar year of airborne and I

j liquid effluents are integrated over a 50 year time span, taking into account the effective decay and removal of the radioactive materials j

contributing to the dose for each individual in the population.

The population dose commitment is the sumation of the calculated individual doses with units of Person-Rem, 4

1 1

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

i i

1 1

I l

i l

..=

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 f

~

airborne and liquid radioactive effluents of Haddam Neck have been calculated.

l These estimations are performed using measured radioactive effluent j

data, measured meteorological data, and calculational models developed i

by the U.S.

Nucl ear Regulatory Commission (NRC) and Environmental I

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 1

Envirormental Monitoring Report.

I Calculation of Population A Maximum Individual Dose Commitment i

l 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, l

the population is taken to be within the annular area surrounding the 1

nuclear site out to a 50 mile outer radius.

Figure 1 illustrates this i

area.

1 p

i,

9 i

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 l

commitment (units of person-rem) is the sum of the calculated individual doses.

l The dose calculations involved the input of three types; radioactive l

source term data, site specific data, and generic factors.

The radioactive source term (units of Curies) is obtained from the Semiannual Radioactive Effluents Report.

The site pecific data includes the meteorological data (wind speed, direction, stability, etc.)

to calculate the transport and dispersion of airborne radioactive ef fluents, 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 fish.

The generic data includes the annual average consumption rates (inhalation of air and ingestion of fruits, vegetables, leafy I

vegetables, grains, milk, poultry, meat, fish, 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 airborno and liquid ef fluents data into population and individual dose commitments.

l 1

I i

c a.

Airborne Radioactive Effluents Maximum individual doses and population doses due to the release of noble gases, radiodines and particulates were calculated usingthecomputercodeGASPAR(1),

t 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 Gaseouc Effluents in Routine Releases from Light-Water-Cooled Reactors."

l 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, i

Releases from the 175-foot vent stack were considered as a mixed mode release (partially elevated and partially ground).

The Pasquill stabil,ity classes were determined using the temperature 4

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

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 then summed to determine the total dose.

l 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 implements the dose models and parameters given in Regulatory Guide 1.109 (October 1977).

A e

5-

3.0 DISCUSSION OF RESULTS a.

Airborne Effluents i

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, l

cow's milk and meat.

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

4 The maximum organ dose in all cases was to the thyroid, and j

thus, the dose to all other organs was less than that shown for j

the thyroid.

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

I calculates the dose to the same organs listed above for the I

following pathways:

direct exposure to the plume, exposure from I

ground deposition, inhalation, and ingestion of vegetation, meat, cow's milk and goat's milk.

The doses are calculated for I

i adults, teenagers, children and infants separately, i

l Fur the plume and inhalation pathways, the maximum individual i

dose is calculated at the offsite location of highest decayed X/Q where a poterf tlal for dose exists.

l t

o for the ground deposi tion, the maximum individual dose is

{

calculated at the offsite maximum land location of highest I l t

f 4

i i

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 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 1

calculated at the cow farm and goat farm of maximum deposition.

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.

Population doses include all applicable pathways.

l Maximum individual and population dosas are presented in Table 1.

b.

Liquid Effluents The LADTAP code performs calculations for the following pathways:

fish, shellfish, algae, drinking water, irrigated i

food, shoreline activity, swimming and boating.

In the vicinity of Connecticut Yankee, the shellfish, algae, drinking water and irrigated food pathways do not exist.

Therefore, the maximum individual doses do not consider these pathways.

The population doses considers all applicable pathways within 50 miles.

4,

J l

Doses are calculated for the whole body, skin, thyroid, GI-LLI, bone, l

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 t

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 i

expectation of health effects from the calculated radiation dose due j

to plant operations is insignigicant.

For perspective. Table 3 I

presents a comparison between the doses due to plant operation and 1

doses received from other sources such as the naturally occurring l

i 4

background levels.

The table also presents the legally allowed levels 1

l from 40CFR190.

t 4

I 4

k I

)

1 I

l 1

f i

I i

=8*

)

j

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.

l EPA Of fice of Radiation Programs, Washington, D.C., May,1974.

t (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.

1 (4)

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

l l

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HADDAM NECK PLANT 60 MILE I

i t

I

l TABLE 1 0FFSITE DOSE ColetITNENTS (AIR 30RNE)

Eonnecticut Yankee - 1986 AIRSIME EFFLUENTS 1st Qtr.

2nd Qtr.

3rd Otr.

4th Otr.

1.

Maximum Individual Dose (aren) a.

Idhole Body (External) 2.53E-1 @.4mi NNE 1.23E-2 @.4mi NNE 8.40E-2 @.3mi NNV 4.34E-2 @.4mi NE b.

Skin (External) 7.44E-1 @.4mi NNE 3.41E-2 @.4mi NNE 2.28E-1 @.3mi NNV 8.36E-2 @.4mi NNE l

c.

Thyroid (Internal) 5.41E-2 @.3mi NNV 5.88E-3 @.9mi SE 9.01E-2 @l.5mi NV 3.30E-3 @.4mi NNE (teen)

(child)

(infant)

(teen) 1 2.

Population Dose (Person-Rem)

(0-50 Miles) j a.

idhole Body 1.15E+0 4.02E-2 1.75E-1 8.05E-2

(

b.

Skin 3 93E+0 1.03E-1 6.14E-1 1.99E-1 c.

Thyroid 1.27E+0 4.00E-2 1.70E-1 8.02E-2 3.

Average Dose (ares)

(0-50 Miles) a.

idhole Body 2.45E-4 8.57E-6 3.73E-5 1 72E-5

{

b.

Skin 8.38E-4 2.20E-5 1.31E-4 4.24E-5 c.

Thyroid 2.71E-4 8.53E-6 3.62E-5 1.71E-5 i

TABLE 2 OFFSITE DOSE CSSIITE NTS (LIQUID)

CONNECTICUT YANKEE - 1986 LIW ID EFFLE NTS lst Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

1.

Maximum Individual Dose (aren) a.

Whole Body 7.46E-2 2.53E-1 5.54E-1 1.60E-1 b.

Maximus Organ (Liver) 1.04E-1 teen 3.55E-1 een 7.04E-I een 2.31E-1 t

t teen l

c.

Thyroid 4.58E-3 6.13 E-2 3.67E-2 4.15E-3 2.

Population Dose (Person-Rem)

(0-50 miles) a.

Whole Body 5.96E-2 2.01E-1 4.41E-1 1.28E-1 b.

Maximusi Organ (Liver) 9.74E-2 3.38E-1 6.61E-1 2.25E-1 c.

Thyroid 3.10E-3 3.26E-2 1.93E-2 3 20E-3 l

3.

Average Dose (aren) l (0-50 miles)

I a.

Whole Body 1.27E-5 4.28E-5 9.40E-5 2.73E-5 b.

Maximum Organ (Liver) 2.08E-5 7.21E-5 1.41E-4 4.80E-5 c.

Thyroid 6.61 E-7 6.95E-6 4.11E-6 6.82E-7 l

l l

l

TABLE 3 COMPARISON OF WHOLE BODY DOSES I.

Doses from Station Effluents - 1986 mrem A.

Maximum Individual - Liquids 1.04E+0 B.

Maximum Individual - Airborne 3.93E-1 C.

Average Individual - (0-50 miles) 3.1 E-4 D.

Average Individual - (0-50 miles) 1.8 E-4 I

II. Limits from Nuclear Power Plants 1

A.

Maximum Individual 25 III. Doses from Other Sources A.

Natural Background in Connecticut - Cosmic, Terrestrial and Food Products 125 B.

Radioactivity from Building Materials (varies from Wood to Stone House) 12-34 C.

Medical X Ray 30-70 1

D.

Air Travel (Round Trip - Cross Country) 4 6

9 i

e l

APPENDIX A UPDATED TABLES FOR THE SEMIANNUAL EFFLUENT RELEASE REPORT:

JULY - DECEMBER 1936 The following tables with the required data (Sr-89, Sr-90 and gross %) are included to update your copy of the Semiannual Effluent Release Report for the period July - December 1986.

4

\\

I i

L EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 19 86-Ij GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 1

hbbER b

UNIT ERROR A.

FISSION & ACTIVATION GASES

~

4 f

1.

Total release Ci 3.93E+02 1.50E+02 1.40E+01 2.

Average release rate for period pCi/sec 4.94E+01 1.89E+01 i

]

B.

10 DINES i

l l

j 1.

Total iodine - 131 Ci 8.09E-04 4 MDL 1.30E+01 1.02E 04

<MDL 2.

Average release rate for period pCi/sec 1

I t

i

}

C.

PARTICULATES l

1 i

1.

Particulates with half-lives C1

> 8 days 1.49E-04 8.'84E-04 1.40E+01 j

2.

Average release rate for period pCi/see

1. 87E-05 1.11E-04 1

i

• d. Cross alpha radioactivity Ci 1.59E-Da 3.43E-08 l

D.

TRITIUM 1.

Total release Ci 8.05E+00 6.79E+00 8.00E+00

~

2.

Average release rate for period pCi/see 1.01E+00 8.54E-01 t

I l

i 9-1 4

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rr-r-,rw-,

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.,.,my,- -.,. +c,m-y

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT

- 19 86 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES EST. TOTAL h

I UNIT ER R

ERROR %

A.

FISSION AND ACTIVATION PRODUCTS 1.

Total release (not including tritium. Rases, alpha)

Ci 1.01E-01 a a?r.n')

1 1nr+nt 2.

verage diluted concentration durina period DCi/a1 5.49 E-10 2.43E-10 i

i B.

TRITIUM i

i 1.

Total release Ci 5.09E+02 1.07E+03 3.50E+00 2.

Average diluted concentration during period pCi/ml 2.77E-06 5.86E-06 4

i C.

DISSOLVED AND ENTRAINED GASES a

f j

1.

Total release ci 8.81E-02 3.05E-02 1.90E+01 1

2.

Average diluted concentration durina period DCi/ml 4.79E-10 1.67E-10 D.

GROSS ALPHA RADIOACTIVITY J

1.

Total release C1 1.31E-04 1.97E-05 8.00E+00 I

E.

Volume of waste released (prior i

to dilution)

Liters 4.20E+07 4.57E+07 3.00E+00 i

i l

F.

Volume of dilution water used' j

during period Liters 1.839E+11 1.825E+11 2.50E+00 i

j G.

Volume of dilution water used i

during releases (batch)

Liters 2.94E+10 2.21E+10 2.50E+00 i.

l

__