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NUREG-1537, Part 2 - NRC

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APPNmix 17.1<br />

radiaton fields, contamination, and airborne radiation hazards created during the<br />

decommissioning process.<br />

3.1.3 Dose Estimates<br />

For each maor task in which radiation is a factor, the licensee should estimate the<br />

total cumulative and individual maximum dose equivalents to both radiation<br />

workers and the public. These estimates should take into account both external<br />

and internal exposures. Potential pathways and any doses to the public should be<br />

analyzed according to current practices. Methods to ensure compliance with<br />

10 CFR <strong>Part</strong> 20 and the ALARA program should be explained. For each task<br />

identified by the licensee in Section 2.3.1 ofthe DP that involves radiation, a dose<br />

estimate should be given in this section of the DP. The reviewer should verify<br />

several representative dose determinations. The reviewer may gain insight into<br />

actual doses received during decommissioning activities by studying final reports<br />

from non-power reactors that have been decommissioned.<br />

3.2 Radioactive Waste Management<br />

3.2.1 Fuel Removal<br />

Licensees are expected to properly remove all fuel under the reactor operating<br />

license before decommissioning begins. In this secdton of the DP, th licensee<br />

should state whether or not the fuel has been removed. If fuel will be removed as<br />

a part of decommissioning, the DP should give information about the removal.<br />

This information should include the defueling schedule, the methods of removing<br />

the fuel from the facility, the method of shipment, and the recipient of the fuel. If<br />

any fuel is still on site at the beginning of other dismantlement activities, the DP<br />

should containia discussion of the license status and the way fuel integrity, physical<br />

protection, and emerge planning will be maintained. Note that<br />

decommissoning with fuel on site may require the analyses of new accidents or<br />

changes to previously analyzed accidents. The licensee should explicitly commit to<br />

compliance with all applicable regulations and guides, including 10 CFR <strong>Part</strong>s 20,<br />

50, 71, and 73 and 49 CFR <strong>Part</strong>s 170 through 189.<br />

3.2.2 Radioactive Waste Processing<br />

The licensee should demonstrate that it has considered all of the radioactive<br />

sources discussed in Section 2.2.2 of the DP and has a plan for monitoring,<br />

sorting, packaging, and processing the wastes. If there are liquid radioactive<br />

wastes, methods for controlling and processing them, such as solidifying waste for<br />

shipment, should be discussed. If diluting waste for disposal into a sanitary waste<br />

system is proposed, the licensee shall discuss in detail assessment methods and ><br />

<strong>NUREG</strong>-1S37,PMr2 S REv. 0,2/96<br />

<strong>NUREG</strong>-<strong>1537</strong>,PART2 8 REV. 0, 2/96

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