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Question 384: Nuclear power plant licensees are required
to meet the criteria in 10 CFR 50 Appendix I and 40 CFR 190
with regards to maintaining doses to individual members of
the public ALARA. Related Regulatory Guides (e.g., 1.21,
1.109, and 4.1) describe programs which are acceptable to
the NRC staff to demonstrate compliance with 10 CFR 50
Appendix I and 40 CFR 190 criteria. Specific requirements
for monitoring, sampling, dose calculation and reporting
are included in each plant's Technical Specifications and
related Offsite Dose Calculation Manual. Does compliance
with plant Technical Specifications, applicable Regulatory
Guides, and the radiation standards in 40 CFR 190 fully
meet the requirements of 20.1301? The purpose in asking
this question is to obtain clarification that, although the
revised 10 CFR 20 introduces new dose limits for individual
members of the public and new effluent concentration values
in 10 CFR 20 Appendix B, the scope of monitoring, sampling,
dose calculation and reporting are not changed for nuclear
power plants by the revised 10 CFR 20 from the previously
applicable requirements and guidance.
Answer: Not necessarily. See the questions and answers
in sections 10 CFR 20.1301 and 10 CFR 20.1302. Generally,
for nuclear power plants, no major changes are needed in
"the scope of monitoring, sampling, dose calculation, and
reporting" that has been adequate for compliance with plant
Technical Specifications and 40 CFR 190, and for
conformance with applicable regulatory guides. However,
some relatively minor changes may be needed. For example,
at some plants, changes may be needed for demonstrating
compliance with the requirements of 10 CFR 20.1301 as they
apply in members of the public in controlled areas. (See
the answer to Question 104.) (References: 10 CFR 20.1301,
10 CFR 20.1302).