Section 5.4.3February 1979

ENVIRONMENTAL STANDARD REVIEW PLAN

FOR ES SECTION 5.4.3 RADIOLOGICAL IMPACTS OF NORMAL OPERATION: IMPACTS TO MAN

REVIEW INPUTS

Environmental Report Sections

None

Environmental Reviews

5.4.2 Radiological Impacts of Normal Operation: Dose Commitments

Standards and Guides

Regulatory Guide 1.109, " Calculation of Annual Doses to Man fromRoutine Releases of Reactor Effluents for the Purpose ofEvaluating Compliance with 10 CFR Part 50, Appendix I"

10 CFR Part 50, " Domestic Licensing of Production and Utilization Facilities,"Appendix I, " Numerical Guides for Design Objectivesand Limiting Conditions for Operation to Meet the Criterion ' As LowAs Practicable' for Radioactive Material in Light-Water-CooledNuclear Power Reactor Ef fluents"

10 CFR 20.105, " Permissible Levels of Radiation in Unrestricted Areas"

40 CFR g 190, " Environmental Radiation Protection Standards for NuclearPower Operations"

Other

n'one

REVIEW OUTPUTS

Environnental Stateiaent Sections

5.4.3 Radiological Impacts of Normal Operation: Impacts to Man

Other Environmental Reviews

10.4.2 3enefit-Cost Balance: Costs7 ,,

,

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February 1979

I. PURPOSE AND SCOPE

The purpose of this environmental standard review plan (ESRP) is to direct.he staf f's preparation and presentation of a summary analysis and evaluation(f the radiological impacts to man due to radioactive effluents released from

the proposed plant in the course of normal operation.

The scope of the review directed by this plan will include (1) a comparisonof the maximum individual dose commitments calculated by the reviewer for ESSection 5.4.2 with the design objectives of Appendix I to 10 CFR P rt 50 and(2) an analysis and evaluation of population dose commitments for the populationwithin 80 km of the plant and for the total U.S. population.

II. REQUIRED DATA AND INFORMATION

The following data and information will be required:

A. Dose commitment data (from the ESRP for ES Section 5.4.2)

1. Maximum individual dose commitments from liquid ef fluents

2. Maximum individual dose commitments from gaseous effluents

3. Dose commitments to the population within 80 km of the plant

4. Dose commitments to the U.S. population (including occupational

dose commitments)

B. Site-specific natural radiation c )se levels (f rom Ref. 1).

III. ANALYSIS PROCEDURE

The reviewer's analysis of radiological impacts to man wiil be based onthe dose-commitment data calculated by the reviewer for ES Section 5.4.2 that

08 LJr5.4.3-2

February 1979

have been evaluated by the reviewer for ES Section 3.5 and determined to be withinthe design objective guidelines of Appendix I to 10 CFR Part 50. The reviewerwill prepare a table that compares these dose commitments, on a per unit (indi-vidual reactor) basis, with the Appendix I guidelines, using the format showni n Table 5. 4. 3-1.

The reviewer will also determine the 80-km population dose commitment (totalbody and thyroid) per reactor unit for liquid effluents, noble gas effluents,

and radioiodines and particulates and compare these doses with the natural radia-tion background for this population. The format of Table 5.4.3-2 should be used.

IV. EVALUATION

In consultation with the reviewers f or ES Sections 3.5 and 5.4.2, the revie eerwill serify the accuracy and completene ,s of the summary table baseo on Table .4.3-1.The reviewer will verify the availability and accuracy of the followin: aatathat will be included as input to the environmental statement:

1. The maximum individual dose commitment and the dose commitment to thepopulation within 80 km of the plant, based on individual reactor releases.

2. The individual and total-natural-background radiation dose to the popu-lation within 80 km of the plant.

3. The total U.S. population dose commitment based on individual reactorreleases, including the estimated occupational cose commitment.

V. INPUT TO THE ENVIRONMENTAL STATEMENT

The following input to ES Section 5.4.3 will be used:

The radiological impact to man associated with normal opera-tion of the proposed plant will depend on the manner in whichthe radioactive-waste-management system is operated. Based onthe staff's evaluation of the potential performance of this system,it is concluded that the system as proposed is capable of meeting

5.4.3-3 7op m,,,

February 1979

the dose design objectives of Appendix I to 10 CFR Part 50. Table5.4.3-1 compares the calculated maximum individual doses, basedon radiological effluent source terms that reflect the potentialsystem performance, with these design objectives. However, sinceplant radioactive waste system operation will be governed byoperating license technical specifications based on these Appen-uix I dose design objectives (shown in Table 5.4.3-1), actualradiological inpacts of normal plant operation may result in dosesclose to the dose design objectives rather than those calculatedas maximum individual body doses. Even if this situation exists,the individual doses will still be very small when compared tothe individual natural background dose of * mrem /yr or thetotal-body dose of 500 mrem /yr discussed in 10 CFR Part 20.105as a permissible level of radiation in an unrestricted area.

The staff has also concluded that the total dose commitment of* man-rem /yr to the population within 80 km of the plant,

(Table 5.4.3-2) and the total U.S. population dose commitment of* man-rem /yr, including the annual estimated occupational

dose commitment, are not significant when compared with thenatural radiation background dose commitments of * man-rem /yr to the 80-km pcpulation and 30,000,000 man-rem /yr to theU. S. population. As a result, the staff has concluded thatthere will be no observable health impact to man from normaloperation of the proposed plant.

Ef fective December 1,1979, the licensee will be regulated accord-ing to the Environmental Protection Agency Standard, 40 CFR Part190, " Environmental Radiation Protection Standards for NuclearPower Operations." This standard specifies that reactor operationsshall be conducted in such a manner as to provide reasonable assur-ance that the annual dose equivalent does not exceed 25 mrems to

the whole body, 75 mrems to the thyroid, and 25 mrems to any otherorgan of any member of the public as the result of exposures toplanned discharges of radioactive materials, radon and its daughtersexcepted, to the general environment from uranium fuel cycle opera-tions and to radiation from these operations.

The reviewer will provide inputs or ensure that inpo's will be made to thefollowing ES section:

Section 10.4.2. The reviewer will provide the reviewer for E5 Section

10. 4. 2 with a summary of the maximum individual and total population dosecommitments.

Based on an average individual dose commitment of 100 millirem /yrand a stabilized U.S. population of 300 million.

The reviewer will insert values appropriate to the environmental review.

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February 1979

Tha : eviewer will also ensure that the appropriate Safety Evaluationreviewer is provided with the 80-km population and total U.S. population dose-commitment calculations.

VI. REFERENCES

1. U. S. Environmental Protection Agency, Natural Radiation Exposure in theUnited States, ORP-SID 72-1, June 1972.

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February 1979

@

TABLE 5.4.3-1

COMPARISON OF MAXIMUM PER-UNIT INDIVIDUAL DOSE COMMITMENTSWIiH APPENDIX I DESIGN OBJECTIVES

Per Unit Appendix IDose Criterion Calculated Dose Design Objectives ( )

Noble Gas Releases

Beta dose in air xxx 20 mrad /yrGamma dose in a c xxx 10 mrad /yrTotal-body dose xxx 5 mrem /yrSkin dose xxx 15 mrem /yr

Liquid Releases

Total-body dose xxx 3 mrem /yrOrgan Dose xxx 1C mrem /yr

Iodines and ParticulateReleases (b)

Organ dose xxx 15 mrem /yr

d. Appendix I design objectives from Sections II.A, II.8, II.Cof Appendix I, 10 CFR Part 50, maximum individual doses froma single reactor unit (as of January 1, 1977).

b. Carbon-14 and tritium have been added to this category.

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February 1979

TABLE 5.4.3-2

CALCULATED POPULATION DOSE COMMITMENT WITHIN 80 km

Total Body Thyroid

Annual Dose Per Reactor Unit

Natural Radiation Background xxx man-rem

Liquid Effluents xxx man-rem xxx man-rem

Noble Gas Effluents xxx man rem xxx man-rem

Radioiodines and Pa-ticulates xxx man-rem xxx man-rem

" Natural Radiation Exposure in the United States", U.S. Environmental Pro-tection Agency, ORP-SID-72-1 (June 1972); using the average state backgrounddose ( * mrem /yr), and year 2000 projected Dupulation of *

xThe reviewer will insert values appropriate to the environmental review.

108 239S.4.3-7