[ RadSafe ] Question on 10CFR 20
wlipton at sbcglobal.net
Fri May 30 15:01:40 CDT 2008
The key phrase is, "each licensee shall conduct operations so that..." Hence, this standard thus applies to the effluents and direct radiation from a single licensee.
However, EPA regulations, in 40 CFR 190 (copied below) set stricter standards that apply to the dose from all nuclear fuel cycle installations. In addition, 10 CFR 50, Appendix I, "Numerical Guides for Design Objectives and Limiting Conditions for Operation To Meet the Criterion 'As Low as is Reasonably Achievable'' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents," sets even stricter "guidelines" for effluents.
It's not about dose, it's about trust.
Title 40: Protection of Environment
Subpart B—Environmental Standards for the Uranium Fuel Cycle
§ 190.10 Standards for normal operations.
Operations covered by this subpart shall be conducted in such a manner as to provide reasonable assurance that:
(a) The annual dose equivalent does not exceed 25 millirems to the whole body, 75 millirems to the thyroid, and 25 millirems 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 operations and to radiation from these operations.
(b) The total quantity of radioactive materials entering the general environment from the entire uranium fuel cycle, per gigawatt-year of electrical energy produced by the fuel cycle, contains less than 50,000 curies of krypton-85, 5 millicuries of iodine-129, and 0.5 millicuries combined of plutonium-239 and other alpha-emitting transuranic radionuclides with half-lives greater than one year.
----- Original Message ----
From: Sandra Matzkin <matzkin at invap.com.ar>
To: radsafe at radlab.nl
Sent: Friday, May 30, 2008 2:11:13 PM
Subject: [ RadSafe ] Question on 10CFR 20
I have a question regarding 10CFR Part 20 - Standards for Protection
Against Radiation. Specifically the section dealing with dose limits
for members of the public. I'm quoting part of it:
" 20.1301 Dose limits for individual members of the public.
a) Each licensee shall conduct operations so that --
(1) The total effective dose equivalent to individual members of the
public from the licensed operation does not exceed 0.1 rem (1 mSv) in
a year... "(SNIP)
My question is: is this a limit to be complied with by each nuclear
installation (i.e. reactor, plant, etc) independently? or else, in
case there is more than one facility in a given area, should the 1
mSv/year limit be the summation of the contributions from all of
them? FWIW, the latter case is the regulatory concept applicable in Argentina.
I'll appreciate any insights on this subject.
Nuclear Engineering Department
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PART 190—ENVIRONMENTAL RADIATION PROTECTION STANDARDS FOR NUCLEAR POWER OPERATIONS
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