ML19221A796
| ML19221A796 | |
| Person / Time | |
|---|---|
| Issue date: | 02/28/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-0555, NUREG-0555-05.4.3, NUREG-555, NUREG-555-5.4.3, SRP-05.04.03, SRP-5.04.03, NUDOCS 7907090145 | |
| Download: ML19221A796 (7) | |
Text
Section 5.4.3 February 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 from Routine Releases of Reactor Effluents for the Purpose of Evaluating 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 Objectives and Limiting Conditions for Operation to Meet the Criterion ' As Low As Practicable' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Ef fluents" 10 CFR 20.105, " Permissible Levels of Radiation in Unrestricted Areas" 40 CFR g 190, " Environmental Radiation Protection Standards for Nuclear Power 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: Costs 7
7 907 0 9D\\*5 5.4.3-1
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 comparison of the maximum individual dose commitments calculated by the reviewer for ES Section 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 population within 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 on the dose-commitment data calculated by the reviewer for ES Section 5.4.2 that 08 LJr 5.4.3-2
February 1979 have been evaluated by the reviewer for ES Section 3.5 and determined to be within the design objective guidelines of Appendix I to 10 CFR Part 50.
The reviewer will prepare a table that compares these dose commitments, on a per unit (indi-vidual reactor) basis, with the Appendix I guidelines, using the format shown i n Table 5. 4. 3-1.
The reviewer will also determine the 80-km population dose commitment (total body 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 eer will 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: aata that will be included as input to the environmental statement:
1.
The maximum individual dose commitment and the dose commitment to the population 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 reactor releases, 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 which the radioactive-waste-management system is operated.
Based on the 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. Table 5.4.3-1 compares the calculated maximum individual doses, based on radiological effluent source terms that reflect the potential system performance, with these design objectives. However, since plant radioactive waste system operation will be governed by operating license technical specifications based on these Appen-uix I dose design objectives (shown in Table 5.4.3-1), actual radiological inpacts of normal plant operation may result in doses close to the dose design objectives rather than those calculated as maximum individual body doses. Even if this situation exists, the individual doses will still be very small when compared to the individual natural background dose of
- mrem /yr or the total-body dose of 500 mrem /yr discussed in 10 CFR Part 20.105 as 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 the natural radiation background dose commitments of
- man-rem /yr to the 80-km pcpulation and 30,000,000 man-rem /yr to the U. S.
population.
As a result, the staff has concluded that there will be no observable health impact to man from normal operation of the proposed plant.
Ef fective December 1,1979, the licensee will be regulated accord-ing to the Environmental Protection Agency Standard, 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operations." This standard specifies that reactor operations shall 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 other organ of any member of the public as the result of exposures to planned discharges of radioactive materials, radon and its daughters excepted, 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 the following 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 dose commitments.
Based on an average individual dose commitment of 100 millirem /yr and a stabilized U.S. population of 300 million.
The reviewer will insert values appropriate to the environmental review.
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5.4.3-4
February 1979 Tha : eviewer will also ensure that the appropriate Safety Evaluation reviewer 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 the United States, ORP-SID 72-1, June 1972.
108 '2 n J<
5.4.3-5
February 1979 TABLE 5.4.3-1 COMPARISON OF MAXIMUM PER-UNIT INDIVIDUAL DOSE COMMITMENTS WIiH APPENDIX I DESIGN OBJECTIVES Per Unit Appendix I Dose Criterion Calculated Dose Design Objectives ( )
Noble Gas Releases Beta dose in air xxx 20 mrad /yr Gamma dose in a c xxx 10 mrad /yr Total-body dose xxx 5 mrem /yr Skin dose xxx 15 mrem /yr Liquid Releases Total-body dose xxx 3 mrem /yr Organ Dose xxx 1C mrem /yr Iodines and Particulate Releases (b)
Organ dose xxx 15 mrem /yr d.
Appendix I design objectives from Sections II.A, II.8, II.C of Appendix I, 10 CFR Part 50, maximum individual doses from a single reactor unit (as of January 1, 1977).
b.
Carbon-14 and tritium have been added to this category.
TPgh ~bdJ 5.4.3-6
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 background dose (
- mrem /yr), and year 2000 projected Dupulation of x
The reviewer will insert values appropriate to the environmental review.
108 239 S.4.3-7