Table 2.1. Evaluation guidelines for public protection from radiation

DOE-STD-6003-96

For comparison with the evaluation guidelines, only plume passage dose is evaluated.

Plume passage dose includes the following pathways: (1) direct cloudshine and (2) 50-yr CED

from inhalation for the duration of plume passage. These pathways are considered an immedi-

ate threat. Other slow-developing pathways are not included because they are a measure of the

effectiveness of public health measures (e.g., interdiction) rather than the severity of the acci-

dent itself. If dose is evaluated on public access roads that are not controllable by the licensee,

the time of exposure to the plume should be based on realistic vehicle passage time estimates.

2.2.1 Evaluation Guidelines for Exposures to the Public

The following goals and requirements have been established in DOE-STD-6002-96 for

exposures to the general public during normal and anticipated operational occurrences and for

off-normal conditions and accidents. The origin of each of the limits follows Table 2.1.

Evaluation guidelines for public exposures to nonradiological materials should be in

accordance with federal, state, and local regulatory and permit requirements.

TABLE 2.1. Evaluation guidelines for public protection from radiation

Fusion radiological

Regulatory limit

release requirement

(evaluation guidelines)

Normal and anticipated

100 Sv/yr

1 mSv/yr

[10 mrem/yr]a

[100 mrem/yr]b

operational occurrences

Off-normal conditions (per

10 mSv

250 mSv

[1 rem]c

[25 rem]d

event)

(no public evacuation)

aThis

value, which is a limit for the MEI, is consistent with the limit on the emissions of radionuclides to

the ambient air for DOE facilities as stated in 40 CFR 61.92. In meeting this limit, a facility would be well

below the exposure limit mandated by the Nuclear Regulatory Commission (NRC) safety goals for

nuclear facilities (51 FR 30028) and the DOE safety goals. Both of these goals, which consider the

average exposure to the population within 10 miles of a facility, state that the risk to the population

resulting from nuclear operations should not exceed 0.1% of the sum of all cancer fatality risks resulting

from all other causes. The radiological cancer risk coefficient is about 0.4%/0.1 Sv for long-term

exposures (BEIR-V, p. 6), and the annual cancer fatality risk due to all causes is about 200/100,000

people. If we conservatively assume that the site-boundary to average exposure ratio is 2, then the

routine exposure limit should be

(0.1%) (200 per year/100,000 people) (0.1 Sv/0.4%) (2) = 0.1 mSv/yr = 10 mrem/yr.

bThis

value is based on the 10 CFR 20.1301 dose limits on individual members of the public.

cThis requirement is based on the limit in the Protective Action Guideline (PAG) (EPA 1991) at which

public sheltering and evacuation should be undertaken.

dThis is the required limit for exposure due to an accident. This value is based on the design basis

acceptance criteria for nuclear reactor siting in 10 CFR 100.