NUREG-1537, Part 2 - NRC

DEco wIssioNDJGPLA
controls to comply with 10 CFR Part 20. Any gaseous or airborne radioactivity.
should be confined, filtered, and diluted for controlled release under 10 CFR Part
20. The licensee should discuss the use of controls,'such as hoods, tents, face:
miasks or self-contained airpacks. Control of radioactivity during demolition,
segmeation, and com'pacting'of solid radioactive wastes should be ensured.
dturig processing for disposal. '
3.2.3 Radioactive Waste Disposal..
The licensee should account for all of the radioactivity discussed in Section 2.2.2
of the DP. The licensee should state the regulations that are applicable to the
various radiation sources. It should give details for the disposal site, types and
quantities of radioactivity expected, methods of verifying and certfying the
radioactive content, formal agreements required for ansport and release of the
radioactive waste to a designated licensee, and methods of transport. The DP,
should state that the licensee is responsible for properly packaging and labeling all
radioactive waste for transport. 'The licensee shall include a commitment to
complywith all applicable regulations (10 CFRParts 20 and 71 .and 49 CFR) and
should list specific references.'
The licensee should describe in detail, and with quantitative criteria, how material
to be disposed of in unrestricted sites will be monitored, selected, and controlled.
The only criterion acceptable to NRC at present is that no measurable radioactivity
above background levels should be disposed of in unrestricted locations (NRC IE
Circular 8 1-07 and NRC E InformationNotices 83-05 and 85-92). The licensee
should give acceptable criteria for measuring 'and iurisng that condidon, with
limits defining sensitivity of sr en io'
3.2.4 General Industrial Safety'Program
Although NRC does not directly regulate or license nonradiological activities
except as they would affect radiological health and safety, an agreement exists
between the Occupational Safety and Health Administration (OSHA) and NRC
concerning nonadiologcal activies. The DP should show that the licensee is
aware of and responsible for controlling any nonradiological hazards or releases
that ensue from decommissioning acativites so that radiological work activities can
be safely accomplished in accordance with the DP.
3.3 Radiological Accident Analyses
Fuel is not usually present on site when decommissioning begins. If this is the
case, radiological accident scenarios need only address the residual radioactive
material. The licensee should address potential accidental exposures during'the
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