United States Nuclear Regulatory Commission - Protecting People and the Environment

U.S. Nuclear Regulatory Commission

Guidance on Reporting Doses to Members of the Public from Normal Operations

HPPOS-140 PDR-9111210378

Title: Guidance on Reporting Doses to Members of the Public

from Normal Operations.

See the memorandum from D. R. Muller to T. M. Novak and G.

C. Lainas dated March 10, 1983. The memo summarizes dose

design objectives of 10 CFR 50, Appendix I, and

requirements of 40 CFR 190 regarding off-site doses from

normal operations. The memo also provides guidance on the

content of required annual reports.

To meet the dose design objectives of 10 CFR 50, Appendix

I, the following conditions must be satisfied.

1. The dose or dose commitment to a member of the

public from radioactive materials in liquid effluent from

each reactor does not exceed:

a. during any calendar quarter, 1.5 mrem to the total

body or 5 mrem to any organ, or

b. during any calendar year, 3 mrem to the total body

or 10 mrem to any organ.

2. The dose from noble gases in gaseous effluents from

each reactor does not exceed:

a. during any calendar quarter, 5 mrad from gamma

radiation or 10 mrad from beta radiation, or

b. during any calendar year, 10 mrad from gamma

radiation or 20 mrad from beta radiation.

3. The dose to a member of the public from

radioiodines and particulates in gaseous effluents from

each reactor does not exceed:

a. during any calendar quarter, 7.5 mrem to any organ,

or

b. during any calendar year, 15 mrem to any

organ.

The requirements of 40 CFR 190 are met if the dose or dose

commitment to any member of the public from uranium fuel

cycle source in a calendar years does not exceed:

1. 75 mrem to the thyroid, or

2. 25 mrem to any other organ or to the total body.

The 40 CFR 190 requirements differ in significant ways from

the Appendix I criteria. Specifically, for 40 CFR 190

purposes, consideration must include the following (as well

as doses from effluents):

1. Direct radiation doses, and

2. Doses from fuel cycle facilities, including other

reactors.

The term "members of the general public" includes all

persons who are not occupationally associated with the

plant. The term does not include employees of the utility,

its contractors, or vendors. Also excluded are people who

enter the site to inspect, service equipment, or make

deliveries. The term includes people who use portions of

the site for recreational, occupational, or other purposes

not associated with the nuclear plant. "Direct radiation"

is radiation which reaches unrestricted areas even though

its source is retained within the plant. Examples are

gamma rays from the decay of nitrogen-16 in BWR turbine

buildings and gamma rays from low level wastes stored on

site.

The purpose of an annual report is to summarize the

calculations performed during the year to show compliance

with Appendix I and with 49 CFR 190 Technical

Specifications. The information should be presented as

indicated in Table 1 of the enclosure to this memo. Where

doses exceed the Appendix I criteria, an explanation should

be provided. Compliance with the 40 CFR 190 dose limits

must be addressed explicitly. If the dose is below the 40

CFR 190 limits, all that needs to be added are statements

addressing doses from other fuel cycle facilities (uranium

mills, conversion plants, enrichment plants, fabrication

plants, power reactors, reprocessing plants, and waste

disposal sites). In most cases, the limits of 40 CFR 190

are satisfied by statements that there are no other fuel

cycle facilities within 8 km.

Regulatory references: 10 CFR 50, 40 CFR 190, Technical

Specifications

Subject codes: 2.2, 7.3, 12.8

Applicability: Reactors

Page Last Reviewed/Updated Thursday, March 29, 2012