Text

Amend 1 to Supplemental Info for Purposes of Evaluation of 10CFR50,App I
	ML20235B064
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	08/31/1976
From:	; VERMONT YANKEE NUCLEAR POWER CORP.
To:	;
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ML20235A662	List: ML20235A659; ML20235B051; ML20235B060; ML20235B064;
References
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Amendment 1 August 31, 1976 o.

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Amendment 1 to O\\

V Supplement Information For the Purposes of Evaluation of 10 CFR Part 50, Appendix I for VEIBIONT YANKEE NUCLEAR POWER STATION 4

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B709230523 870921 PDR ADOCK 05000271 P

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Amendment 1 August 31, 1976 i

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VERMONT YANKEE FUCLEd,R POWER CORPORATION 3

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License No. DPR-28 1

. Docket No. 50-271 i

Instructions For Entering Amendment I to the report entitled " Supplemental Information For the Purposes of Evaluation of 10 CFR Part 50, Appendix I".

Remove Add New Table of Contents Tabic of Contents Page 1-2 Page I-2 Page 11-1 Page 11-1 Table QI.2-1 Tabic QI.2-1

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Tabic QI.2-2 Tabic QI.2-2 Table QII.3-1 Table QII.3-1 Table QlT.3-2 Table QII.3-2 Table QII.3-3 Table QII.3-4 Section IV l

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6 Amendment 1

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August 31,.1976

. Contents Introduction Page I.

Response to NRC's letter of I-1 February 18, 1976 11.

Meteorology II-1 III. Technical Specifications for Radioactive Effluents III-1 IV.

Radiological Dose Assessment TV-1 Appendix A.

Nuclear Regulatory Commission's letter A-1 to Vermont Yankee dated February 18, 1976 Appendix B.

Data Needed For Radioactive Source Term B-1 Calculations for Boiling Water Reactors (Appendix D of Regulatory Guide 1.CC)

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y Amendment 1

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August 31, 1976

.y Response: The primary release point for rad,ioactivity in gaseous effluents at (3/

Vermont Yankee is from a 94 meter stack. The stack qualifies as an

-+,

elevated release point as defined in draft Regulatory Guide 1.DD.

Table Q1.2-1' list the distances from thecstack:to.important landLuse e

characteristics in the vicinity of the plant. The turbine building roof vents are considered a ground Icvel release point and are located approximately 900 feet south of the stack.

Table-QI.2-2 list.the dis--

tances,to the important-land.uses from the turbine building.

In addi-tion to these users, there are numerous individual residences through this area.

Ilowever, the three mile radius surrounding the plant is primarily farm or undeveloped land. The actual distribution of individual residences, as well as farms, follows the main roadways in the area.

As a result, the distribution of farms and residences in the land use Tables represents those areas where additional residences are located., Figure

~O

~

V

-Q1~,.8.-1 shows,thesC1c' cations..whereindividua11resideneesTcan be found y

within;three miles.

Question 3.

Based on considerations in Draft Regulatory Guide 1.DD, provide estimates of relative concentration (X/Q) and deposition (D/Q) at locations specified in rerponse to item 2 above for each release point specified in response to item 1 above.

Response

See Section 11 for meteorological information concerning estimates of X/Q and D/Q values at points of interest.

Question 4.

Provide a detailed description of the meteorological data, models and parameters used to determine the X/Q and D/Q values.

Include information concerning the validity and accuracy of the models and assumptions for your site and the representativeness of the meteorological data used.

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Amendment 1

Augtist 31, 1976 6

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TAllLE.QI.2-1 VERMONT YANKEE

, Distance To Important Land Use Ch a ra c t e ri s t i e s From;Tijd. P.l a n ttS t a c k

_a hearest Resident 4 (1)

Nearest Site (1)

Sector Milk Cows III Milk Coats III Meat Animals II)

Vegetable Garden (2)

Boundary (Miles)

(Miles)

N

>5.0 3.6

>5.0 0.95 0.25 NNE

>S.0

>5.0

+5.0 0.93 0.22 NE

>5.0 2.6

$5.0 1.4 0.22 ENE

>5.0

>5.0 0.63 0.23 E

1. 4 - ~

>5.0 1.4 0.65 0.31 ESE cl.8(3) -

>5. 0 1.8 1.8 0.43 lh s

SE 2.3 2.6 1.6 1.3 0.45 2.3 SSE 3.5

>5. 0 3.5 1.3 0.54 S

1.6-5.0 1.6 0.33 0.24 SSW e 1,4 -

4.0 1.4 0.30 0.18 4h SW

> 5.0

>5.0

>5.0 0.25 0.16 ESW

> 5.0

>5.0 25.0 0.27 0.16 W

0.65

>5.0 0.35<

- Di2d 0,28 0.26 0.64 0.65 0.14 WNW 1 8' I

>S.J 0.n5 0.68 0.35 Z.9 2.9 NW

>5.0

>5.0 1.4 0.34 NNW

>$.0

>5.0 35.0 1.3 0.34 (1) First location indicates &tance of nenett land use within 5 miles. Additional distances Indicate loc a t ion o f a_I _1 teser.* wi t h e n. ca 1 +. *_.

(2) Nearest veget.cre garden is assuncJ to be located at t he nearett resident.

(3) Two separate locations at approximately same distance, 1

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Amendment 1 '

August 31, 1976 TAnl.F. QI.2-2

' VERMONT YANKEE Distance To Important Land Use Characteristics From The Turbine Buil' ding"' Vent.

Nearest Resident 6 (1)

Nearest Site (1) l Sector Milk Cows (1)

Milk Goats (1)

Meat Animals (1)

Vegetable Carden (2)

Soundary (Miles)

(Miles)

(stiles)

(Miles)

N

>5.0 3.7

>$.0 1.1 0.30 NNE

>5.0 25.0

>5.0 1.0 0.28 NE 75.0 2.6 55.0 0.65.

0.28 ENE 1.4

>5.0 1.4 0,55 ~:l~

0.30 E

I.6

>5.0 1.6 0.75 0.31

T lid ESE

$5.0

>5.0 1.6 0.30 A

SE 2.0 2.4 2.0 1.0 0 33 h (TX H SSE 3,3

>5.0 3,

1.2 0.37 5

>$ 0

>5.0

>5.0 1.2 n.37 SSW 1.2

$5.0 1.2 0.25 0.20 1.4 1.4 SW

$5.0

>5.0

$5.0 o,g4 0.17 m

WSW

>5.0 55.0

$5.0 0.25 0.17 W

0.75

$5.0

}-

0.75 0.28 0.19 e

'#% O 0,39.

WNw 7;

>5.0 bh -

d 0.39 0.23 y

'V_ i _ l.2 NW 3.0 25.0 3.0 1.6 0.51 NNW

>5.0

>5.0 1.4 0.42 (1) First location indicaten distance of nes-est land use =lthin 5. miles. Additional distances indicate location of all users within 3 miles.

(2) Nearest vegetable garden is assumed to be at the nearest resident.

[

t

m Amendment'l August 31, 1976 1

Sectioq II i

Meteorology Dataco11cetedfromtheVermontYankee_on-site]meteorologicalsystemwas analyzed for the period April.1,1975 through !hrch. 31,3976. The annual and monthly joint frequency distributions of wind speed and direction by atmospheric stability class in Tabic QII.6-1 provide a detailed description of the meteorological data. A 96.6 percent data recoverability was achieved for the period of record.

The Straight-Line Airflow Model, with appropriate source configuration con-siderations as described in NRC Regulatory Guide 1.111, the Source-Depiction

_ Fbdel as described in Meteorology and Atomic Enerny (1968) and deposit _ ion velocitips_as_given by Pelletier and Zimbrich (1970bere used to determine the X/Q x==-

and D/Q values for specific receptors as provided in Table QII.3-1 through

(~')

QII.3-4.

Site specific recirculation correction factors, for a river valley

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site, are in the process of being developed with the use of appropriate mesoscale diffusion models.

The following site specific parameters assumptions were used in the calculation of X/Q and D/Q values.

A.

Stack release:

1.

Elevated release 2.

Physical height of the release point above ground:

94 meters 3.

Inside diameter of stack:

2.13 meters l

4.

Vertical exit velocity of plume:

19.4 meters /second x

l 5.

Maximum adjacent building height:.'D_me(crs N

6.

Depth of mixing layer:

1,000 meters

()

7.

Average ambient air temperature:

281*K 8.

Recirculation correction factors:

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I' Amendment 1 August 31, 1976 SECTION IV Radiological Dose Assessment O.

O

e' Amendment 1 August 31. 1976 l

'I SECTION IV d

RADIOLOGICAL DOSE ASSESSMENT Paragraph (c) of 10 CFR Part 20.1, states that a licensee to operate a light-water reactor, should in addition to complying with the limits set. forth in that Part of the regulation on the amount of radioactivity that can be discharged in effluents to unrestricted areas, make every reasonable effort to maintain releases of radioactive materials to un-restricted areas as far below the limits specified as is reasonably achievable.

Appendix I to 10 CFR Part 50 provides guidance on the icvels of exposure of the general public resulting from effluents releases 7-that may be considered to be as low as is reasonably achievable.

This section indicates the calculational dose models and assumptions which were used in determining Vermont Yankee's compliance with the Appendix I dose guideline criteria on "as low as reasonably achievabic." The resultant individual radiation doses are based where possibic on realistic assessments of radioactive source terms, hydrologic and meteorologic dis-persion parameters, and physically applicable dose pathways in the site environment.

h'here site specific data is uncertain, conservative assumptions were made. The calculated doses due to normal plant operation, including anticipated operational occurrences, are presented in this section and summarized in Tables Q IV.1-1 through Q IV.1-3.

Radiation Doses From Liquid Effluent Pathways l

Vermont Yankee is a single reactor unit located on the Connecticut River approximately one-half mile above the Vernon Dam in Vernon, Vermont.

1

Amendment i August 31, 1976 Liquid offluents are dischar,ged from the plant via a shoreline surface

/~T discharge structure. The plant cooling water system is designed with both

- Q:

mechanical. draft cooling towers and a s pond which allows the plant flexibility in the way cocling water can be supplied to the main condensers and auxiliary equipment. The cooling system can operate on a total open-cycle or once-through basis, with all of the cooling water from the condensers by-passing the cooling towers and flowing directly to the discharge structure in Vernon Pond.

The phnt can also be operated on a hybrid-cycle basis, with an adjustabic portion of cooling water from the condensers diverted to the, cooling towers and subsequently mixed with the remainder of the water before discharge to Vernon Pond. A third mode of operation b}l -

is completely closed-cycle with all of the water from the condensers diverted to the cooling towers and subsequently returned to the intake structure for recirculation to the condensers. The choice among the three operating modes vary with the season of the year, the cooling towers being used as necessary to assure that biological impact of the heated discharge to the Connecticut River is minimized. The annual allowable frequency of use of each mode of operation is still being studied as part of a test program to evaluate potential thermal impacts on river biota.

Therefore, the annual discharge volume of cooling water which can be expected to be discharged from the plant is uncertain at this time.

Based on _ operating data from 1975 and 1976, the cooling system experienced a_n annual average dischargc ra_tc of about 117,000 ggm During this year period, approximately one-half of the time the plant was on full open

,a cycle, and one-half on hybrid <or, closed cycle.

The liquid radwaste system

~.,

is designed with dilution pumps which will supply 20,000 gpm of dilution j

water during periods of radioactive liquid waste discharge, irregardless

/

of the mode of operation of the cooling water system, Table Q B.5-3 of 2

m

Amemdmet.1 August 31, 1976 h',

Appendix B of this report. lists the isotopic breakdown of the liquid source term, as generated by th'e GALE computer code, which might be

. expected to be discharged annually to the plant's discharge system.

Appendix B describes the plant's effluent control systems and operating parameters which were used to analyze this potential liquid source term.

The description of the GALE computer code and its assumptions can be found in the Nuclear Regulatory Commission Report NUREG-0016{l)

As discussed in. Appendix B, the liquid waste discharge volume is assumed to be 1*6 of the total volume of water precessed each year.

From actual operating experience, the plant has been abic to holdup, process, and reuse waste water to a degree which has not necessitated the routine release ofJny_radiqa. ctiv11guid._ Waste.

Because of this ficxibility of i

1 operation, it is expected that any plant radioactive waste liquid discharge would be held until suitable conditions of river flow or circulation

_ ate _r_ discharge flow are present, to insure that potential doses through w

liquid pathways are kept to a minimum.

The liquid pathways which have been evaluated are those which now exist or could be expected to exist at some time during the plant life, and which could contribute a significant fraction of the total individual dose from water related exposures. The liquid pathways determined to be significant at this time include the ingestion of fish, and direct expusure due to sedimentation of radioactivity along the shore where individuals engaged in shoreline activities can be exposed.

Included in the dose analysis is the potential exposure to individuals through the irrigat on pathway. At the present, there is ngnown_pse of _the Connecticut River for irrigation in the area near the plant.

Ilowever, O

3

- - v Amendment 1 i

August 31, 1976 cultivated ficids do exist which border on the banks of the River just (q

below Vernon Dam, It has therefore been assumed that at sometime in the

. future irrigation water maybe taken from the River for these cultivated ficids.

Studies of the Connecticut River indicate that there are no existing municipal water systems which make use of the River for drinking water below Vermont Yankee. At this time, there are no known n.ians t> make use c

of the River as a source of _drinkinc water in the future, with the exception of a(13roposaDto divert water from the Connecticut River _to_ recharge the

. Quabbin Res.cIvoir.- In comparison to potential doses to individuals from fish caught along the shoreline near the plant, the potential drinking water dose from water drawn from the Quabbin Reservoir are considered insignificant because of the added dilution volu.no of the Reservoir, and p

long transit and holdup times which allow for decay and sedimentation O

4 w ahpwf V Mp.4

/

A 40[

C of radioactivity.

The point at which the_ dose analysis was performed was just below Vemon s/

d' '

Dam, 0.5 miles down stream from Vermont Yankee.

At this location, it was assumed that fishing from the shoreline took place, and that water was also withdrawn for the irrigation of nearby ficids. Crops grown on irrigated fields were assumed to be used both directly in the farmers home and as feed for milk and meat animals.

No direct use of river water for drinking by either individual or cattle is assumed since farming practices in this area make use of ground water from private wells to supply the drinking water requirements. The aqua _t_ic..inver1chrate pathway has also not been assumed since this source of food is not significant in these reaches of the Connecticut River, a

l

Amendment 1 August 31, 1976

'The fishing 1_ocation was chosen at' a point below the Dam since_ fishing

- [^\\

inVernonf{ondisconsideredpoor. This is due in part to bottom profile q) of the pond which provides littic food or cover for fish.

In addition, the adjacent shoreline between Vermont Yankee and Vernon Dam is either part of the plant's site boundary or is owned by the New England Power Company who operates the hydrocicctric station at the Dam. As a result, there is no direct access to the river shoreline between the plant and l

the Dam.

Littic boating has been observed in the Vernon Pond which could significantly contribute to any dose pathway.

Based on a 28 year period of record, the average flow rate of the River at Vt:rnon Dam is 10,170 cfs. The monthly average flow varies greatly from a high of about 32,000 cfs in April, to a low of 3400 cfs in August.

l In addition, the weekly and daily flow rates are greatly influenced by p

the operation of Vernon hydroelectric station.

Ilowever, when Vermont d'

Yankee became operational, a minimum flow rate of 1200 cfs was guaranteed

,to be maintained by the Dam.

As a result, the dose assessment conservatively assumed that the minimum flow of 1200 cfs of river dilution was available

, uring periods of liquid discharge, and that the on1.y_ flow from__the-plant d

was due to the 20,000 gpm,li_ quid.radwaste dilutjon_ pumps. llydrologic analysis indicates the turbulent action of flow through the Vernon Dam results in complete mixing of plant effluents with river flow below the Dam. There fore, the dilut_ ion factor assumed between plant discharge and point of exposure is approximately 26 to 1._

Actual dilution is expceted to be much greater than this since the plant has the ficxibility to hold waste for long time periods, and since the minimum guaranteed river flow would be expected to occur on an infrequent bases.

O 5

l-

w Amendment 1 August 31, 1976 L

The calculational metbc& use'd in dssessing the radiation dose to nQ.

individuals have been trian from Regulatory Guide 1.109(2) for liquid exposures through aquatic food, shoreline deposition, and milk - meat animal pathways. The human consumption or psage factors which were used in the dose calculations for ingestion of fish were taken from Regulatory Guide 1.129.

For fish ingestion, the consumption rates are 21 Kg per s

year, 16 Kg per year, and 6.9 Kg per year for adults, teenagers, and children,.respectively.

For internal doses due to ingestion of fish, an average transit time of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months has been used to allow for radionuclides decay during movement through the food chain, as well as during food preparation.

It has also been assumed that the fish which are caten had reached equilibrium with the water concentration of radioactivity. This assumption leads to conservatism in the calculation since fish tend to be very mobile and are not expected to remain for long periods near the

[

\\

outfall of the Dam.

Shoreline activities have been evaluated using the model listed in Regulatory Guide 1.109 with the shore-width factor of 0.2 used as this pathway is assumed to exir.t at the fisherman's location.

Usage factors of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per year, 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months per year, and 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months per year for adults, teenagers, and children, respectively, were used in the dose evaluations.

In addition, a fifteen year time period was assumed for the sediment to be exposed to activity in the water. This time period represents the approximate mid-point of plant operating lifetime, and thus allows for the buildup of radioactivity such that a plant lifetime average sediment concentration can be est imated.

No credit was taken for plume depiction during the transit of activity between the discharge point and the exposure location.

Usage or consumption factors for milk and meat ingestion are those of 6

l'

=4 ra Amendment 1 August 31, 1976

[

Regulatory Guide 1.109, that'is; $10 liters per year, 400 liters per G

,Q year, and 330 liters for adult's, teenager's, and children's milk

-ingestion and 110 kilogram per year, 65 kilograms per year, and 41 kilograms per year for adult's, teenager's, and children's meat ingestion, respectively.

For the milk ingestion pathway, infant s have also l

been assumed to drink 330 liters per year for the effected sources.

l Transit or holdup times of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and 20 days were used formilk and i

meat products, respectively. The irrigai;_ ion rate which was assumed l

to be applied to crops grown for both human consumption and cattle feed was 0.153 liters per_ meter squared per hour. The iin{fal human consumption of Icafy and stored vegetables are respectively 64 and I

520 kilograms per year for adults, 42 and 630 kilograms per year for teenagers, and 26 and 520 kilograms per year for children.

L O

The maximum external dose from shoreline activites as evaluated at the fishing location is 9.8 x 10-5 millirem per year to the whole body and 1.2 x 10-4 millirem per year to the skin of a teenager spending 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months per year at this location. The external exposures from shoreline activities for all age groups are given in Tahic Q IV.1-1.

The total internal exposures to organs of individuals from the meat, milk, fish, and vegetabic pathways are also summari:cd in this table. The maximum calculated total whole body dose from internal and external exposures is 2.2 x 10-2 millirem per year to an adult who had consumed food products produced with irrigated water from below the Dam and has caten fish taken from the same river location. This whole body dose is about 0.7 percent of the Appendix I design objective of 3 ;rrem per year per unit for whole body doses fro' liquid effluents. The critical organ dose due to plant liquid effluents represents 3 percent of the Appendix 1 design criteria dose of 10 mrem per year per unit to any organ. The 7

J

6c. '

Amendment 1 August 31, 1976 critical organ (bone of an adult) 'is calculated to receive 3.0 x 10-1 n = e =--

. (,)

mrem per year and is due primarily to the ingestion of fish. Table Q IV.1-1 summarizes all liquid doses due to plant discharges.

Radiation Doses From Gaseous Effluent Pathways Gaseous effluent source terms have been calculated using the NRC GALE computer code for boiling water reactors (BWR's). Table Q B 7-2 of l

Appendix B lists the quantities of noble gases, iodines, and particulate which might be generated as annual gaseous releases based on the system description and aperating parameters presented in Appendix B.

These source terms are based on measurements made at operating BWR's, and the primary coolant isotopic distribution as recommended by the ANS 18.1 Source Term Specification Working Subcommittee.

In addition to those nuclides listcJ in Tabic Q B.7-2, 9.5 curies per year of Carbon-14 and

()

25 curies per year of Argon-41 have been added to the gaseous effluents for radiaton dose assessments based on the information in the Nuclear Regulatory Commission's NUREG-0016.

The main release point for gases discharged from the plant is via the 94 meter tall stack which is located in the northern part of the site, about 250 meters from the closest edge of the reactor building.

In addition to the plant stack, the turbine hall roof ventilators have been considered in this analysis as a potential release point. Ilnder normal conditions, the turbine hall ventilation syst em is designed to exhaust air taken from lower levels of the building to the plant stack.

Ilowever, plant surveys have shown that when the turbine hall roof ventilators are in operation to exhaust excess heat from the operating floor of the turbine building, a portion of the ventilation air from i

l the lower elevations may be drawn to the operating floor and exhausted l

to the roof fans.

Plant measurements indicate that under these conditions 8

l

Amendment 1 e;

August 31, 1976 c

8 J

/

about 20 percent of-the exhaust air from the lower floors could be--

i exhausted to the operating _ floor. Since the primary sources of. potential Icakages are pumps and equipment which are in the lower elevations of the turbine building, the gaseous source terms generated by the GALE code for the turbine building ventilation system have been assumed released to the environment partly _(20 percent) through the turbine 7

roof ventil ators..and.. partly..(80_ percent ) throughJhe_phmt_stacku In evaluating both release points, the turbine hall exhaust has been assumed to be a ground level source. The plant stack has been treated as an elevated release point as defined in Regulatory Guide 1.111(3),

Meteorological dispersion of effluents was estimated by a straight-line airflow model applied to an inland valley site.

X/Q and D/Q values were I

determined in each sector for the nearest site boundary, nearest resident and vegetabic garden, and nearest cow, goat, and meat animal out to a distance of 5 miles from the reactor plus all cow, goat, and meat animal inventoried within 3 miles.

All resident are considered tojmye agenernble entdes large enough to produce enough food to meet a significant fraction of the assumed usage factors for the age groups given in Regulatory Guide 1.109, Table A-2.

This includes the annual intake of fruits and vegetables of 520 Kg per year, 630 Kg per year, and 520 Kg per year for children, teenagers, and adults, respectively, and of leafy vegetables of 26 Kg per year, 42 Kg per year, and 64 Kg per year for the same respective age groups.

For igafA x.tgetables, a factor of applied to the annual consumption which assumerthat lie. garden of_in_terest f

.is able to produce duri.n_g_ _the six mont_h growing seasons #hak,bf the annual

~

O l

9 L

Amendment i I

August 31, 1976 For fruits and vegetables, a factor of(0.76 is assumed.

i total consumed.

\\

r's X/Q and D/Q values were calculated from onsite meteorological data for LJ both anannual period and six-month growing season. Tables Q 11.3-1 j

through Q II.3-4 of Section II list the X/Q and D/Q values which have been calculated for each receptor point with respect to both the plant stack and turbine building. The stack and turbine building are located on the site approximately 250 meters apart from each ther.

[4cC(MC N

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W.

Gamma and Beta Doses Both gamma and beta air doses were calculated for the receptor point of highest offsite exposure. The methodology applied to the dose calculations was consistent with that of Regulatory Guide 1.109 for an i

elevated release point.

Dose conversion factors for noble gases and daughters were taken from Table B-1 of this Regulatory Guide.

For the beta air doses, a semi-infinite cloud model was used. The_ gamma air

,y

~

doses were calculated by considering the passage of theQnfinitl radio-active cloud _by the_ point _of _ interest. No credit was assumed for decy of gaseous activity in transit.to point of exposure. Terrain elevations of the surrounding area were factored into calculation of X/Q values at all receptor locations. As a result, the point of highest offsite exposure was determined to be at the southwestern;sitrhoundary from the turbine building ({$outh site boundary with respect to the plant syck).

The p mma and beta air dose calculated at this location arc 1.7 millirad per year and 1.9 mil _lirad per year, respectively, and are thus below the Appendix I guideline gamina and beta air dose values of 10 millirad and 20 millirad per year, respectively. The gamma and beta air doses consider both the contribution from the plant stack and turbine building. The 10

m

[

'c l-

c *

t I

+

g.

gamma air dose is primarily due to radiation from the overhead plume from

. I,h V

the plant stack. The beta air dose is mainly from the turbine building contribution where the passing plume is essentially at ground level. All 1

points beyond the site boundary experienced lower air doses than the site boundary because of the dispersion of the stack plume by the time.it reached ground IcVel, and because of the lessening contribution from the turbine building effluents with increased distance.

In addition to the air doses, the whole body and skincbses to the-most restrictive existing offsite individual were calculated. These doses assumed an occupancy factor of 100 percent and an attenuation factor of 0.7 for gamma rays to account for the dose reduction due to shielding provided by residential structures. The dose analyses indicates that the maximum whole l odyAsc to the worst real resident is 0.81 millirem per year for l

.Q m

Q the resident's located 0.33 miles (south / of thcEack (0.24 miles southwest w

of turbino buildings). The, skin dostat this point is calculated to be 1.9 millirem per year. These doses are also below the guideline values of the "as low as reasonably echievable" criteria of Appendix I which are set at 5 mrem per year per unit for whole body dose, and 15 mrem per year unit for skin dose,

~7 1

l The maximum calculated gamma and beta s occur at the site boundary which abuts the property _of the_yor.st existing residence with respect to whole body and skin doses. There fore, it can be assumed that any point beyond this existine icsidence which could at some time in the future he occupied, will also be below the guideline values of AppenJix 1 for l

l beta and gamma air doses as well as whole body and skin doses.

Tabic Q IV.1-2 summa 11:es the annual air, whole body and skin doses.

11 h

(s.

i s.

i

)

Doses From Radiciodine and Particulate

('$

)

Radiation doses from both radiciodine and particulate (including t

j' tritium and carbon-14) which were calculated to be part of the annual gaseous effluents from the plant were determined for the following pathways:

1) external irradiation from activity deposited onto the ground surface,. 2) inhalation, and 3) ingestion of vegetabic, meat, and milk. The dose models and standard input parameters for crop yicid, exposure and holdup times that were utilized in the dose assessment are those found in Regulatory Guide 1.109.

Doses were calculated for gor pathways which were d.eLennined by field surveys to actually exist. The resultant organ cbses were determined after adding the contribution from all pathways at each location. Tables Q I.2-1 and Q I.2-2 of Section I indicates the location of the nearest resident, cow, goat, and meat animal, plus all milk and meat animals within three miles for each of the sixteen compass sectors centered about both the plant stack and turbine building.

, Dose pathways which involve grazing of muk or meat animals, or the growing season for vegetables, were analyzed using the six-month meteor.ologicaLdata_tden during the growing season. fi_round surface exposure, as well as inhalation doses were analyzed using annual meteorological data.

Meat animals were assumed to receive their entire daily dietary intake from open pasture grass during the nth grazinp scason.

Milk cows

( r( /;

j and gcats/vore assumed to receive 80%;of their intake from pasture during g

this season. This is a conservative assumption since,most dairy operations use supplemgntaLfgeding_of animal when on pasture which would normally n

make up about 50% of their daily intake, or actually restrict animals to full-time silage feeding throughout the year.

All calculated doses considered both the contribution from the turbine building releases as 12

.s.

>4 e

7g well as_the plant stack. The turbine building was treated as r

j _ %J a ground-level source while the plant stack is considered as an elevated l

l-release point.

The highest._offsite dose was determined to be for an infant livin<,J.6' miles nh_oLthe_ plan ck The critical organ dose (3.8 mrom per year) was to the thyroid and was primarily due to exposure through the 4ngestion of goats milks The principle nuclide contributing to this thyroid dose is iodine-131.

The maximum calculated organ dose represents about 25 percent of the 15 mrem per year dose criteria of Appendix I for gaseous iodine and particulate, including tritium and carbon-14. Tabic Q IV.1-3 indicates the' total organ doses from all gaseous pathways for locations of maximum dose.

/

Conclusion The radiological assessment of the principal exposure pathways in the Vermont Yankee environment indicate that the dose criteria of Appendix I to 10 CFR 50 is not likely to be exceeded during normal operation of the plant. Vermont Yankee as analyzed, does meet the "as low as reasonably achievable" criteria for the radioactive effluents and is in compliance with Federal Radiation Regulations, o

l v

13 l

+ > '

Amendment 1 August 31, 1976 C

/"

i f

~

REFERENCES SECTION IV 1.

" Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (BWR-GALE Code)", NilREG-0016 tl. S. Nuclear Regulatory Commission.

2.

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Regulatory Guide 1.109, U.S. Nuclear Regulatory Commission, March, 1976.

3.

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

Regulatory Guide 1.111, ll.S. Nuclear Regulatory Commission, March 1976.

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