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NUREG-1537, Part 2 - NRC

NUREG-1537, Part 2 - NRC

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11.1 Radiation Protection Program<br />

Areas of Review<br />

HEU TO LEU CONVESION<br />

No significant changes in the radiation protection program are expected to result<br />

from changes in reactor systems, operating conditions, or procedures that were<br />

required by the conversion from HEU to LEU fuel.'<br />

The reviewer should evaluate<br />

the potential sources of radiation at a research reactor (including if<br />

appropriate criticality monitors to comply with 10 CER 70.24 requirements<br />

for fuel storage)<br />

* the provisions made by the licensee to detect and measure all potential<br />

reactor-related sources<br />

* the provisions made to assess potential exposures and doses to the facility<br />

staff and the public<br />

* measures being taken to limit doses to within applicable regulations<br />

* commitment to an ALARA program for potential exposures<br />

* ongoing assessment of the effectiveness of the radiation protection<br />

programs .<br />

If the conversion of the reactor from HEU to LEU fuel requires modifications to<br />

the facility or changes to operating conditions, limits, or procedures, the reviewer<br />

should confirm that the licensee has addressed the effects of these changes on the<br />

radiation protection program at the facility.<br />

Acceptance Crteria<br />

Acceptance criteria should be based on the following considerations: Any<br />

proposed changes to the radiation protection program or its implementation should<br />

be related to the conversion of the reactor from HEU to LEU fuel. Any changes<br />

to the radiation protection program'should not significantly decrease the level of<br />

protection provided to the public, the facility staff or the environment. The<br />

licensee's analytical methods and assumptions should be applicable to non-power<br />

reactors, conmmensurate with the types and magnitudes of radiological risks at the<br />

facility, and consistent with the existing prograim for the HEU-fueled reactor. The<br />

program shall continue to comply with the requirements of 10 CFR <strong>Part</strong> 20 and the<br />

facility-specific ALARA program.<br />

REV. 0. 2/96<br />

33<br />

REV. 0, 2M 33

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