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NUREG-1537, Part 2 - NRC

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- - ~DECOM SSOKMGPLANS<br />

facility. Such notations as "not detected" are not acceptable. Instead, the licensee<br />

should propose quantitative measurements and scientifically derived, valid limits of<br />

eror. The reviewer should 'aluate stafistical inferences to locations not directly<br />

measured and should compare them to accepted methods.<br />

At non-power reactors; radioactive material may exist in two forms. The material<br />

may be surface or absorbed contamination or neutron-irradiated material<br />

distributed within the body of a coinponent. In the DP, the licensee should address<br />

reducing both sources of radiation. Guidance for surface contaminaton levels can<br />

be found in Regulatory Guide'1.86, Table 1. Current <strong>NRC</strong> criteria for'release of<br />

non-power reactor facilities for unrestricted use are discussed in Section 17.1.4 of<br />

the format and content guide. Release criteria may change with time. The<br />

reviewer should verify that the guidance given in the format and content guide is<br />

current and that the licensee is using the most recent release criteria<br />

<strong>NRC</strong> regional stiff or an <strong>NRC</strong> contractor will conduct an onsite survey to measure<br />

and verify the radiation exposure and contamination levels. When the<br />

requirements for release have been'satisfied, <strong>NRC</strong> will issue an order that<br />

terminates the license and any further <strong>NRC</strong> urisdiction over the facility.<br />

5 TEC-H MCALSPECIFICATIONS.<br />

After the fuel is shipped off site under the facility operating license, most of the<br />

technical specifications for the operating license should no longer apply.<br />

Therefore, the licensee should have requested relief by applying either for a<br />

possession-only license amendment or for authorization to dismantle and<br />

decommission the facility. In either case, the licensee should propose a modified<br />

set of technical specifications that contains safety controls and limitations that<br />

ensure continuous protection of the health and safety of the puic and satisfy DP<br />

criteria. The format of the technical specifications f decommissioning o<br />

should<br />

conform to the appropriate sections of ANSTIANS .15.1-1990, as discussed in<br />

Chater 14, 'Technical Specificaitions," of the format and content guide,' and<br />

should include the following:<br />

a section imposing limiting decommissioning conditions at the facilihy<br />

comparable to the limiting conditions for operation for required equipment<br />

and operational conditions'<br />

'a section providing for surveillance of the equipment and conditions<br />

* a secion describing the residual defueled facility and site to which the<br />

deconumissioning order will apply<br />

-REV. 0, 296 I I<br />

STANDARD REVEW PLAN

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