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NUREG-1537, Part 2 - NRC

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APPENDIX 18.1<br />

Review Procedires )<br />

The reviewer should detennine if the scenarios and consequences of the MHA for<br />

the HEU-fueled reactor and the proposed LEU-fueled reactor are significantly<br />

different. If not different, the reviewer should follow the analysis by the licensee,<br />

with quantitative checks at key steps as the accident scenario evolves. The<br />

reviewer should compare the projected consequences of the MHA for the<br />

proposed LEU-fueled reactor with the consequences of all other postulated<br />

accidents to verify that those of the MHA exceed and envelope all others.<br />

If the scenarios differ significantly, the reviewer should verify that the evolution of<br />

the accident scenario is analyzed by applicable methods and should compare the<br />

projected consequences with acceptance criteria. The reviewer should verify that<br />

the projected consequences continue to comply with the acceptance criteria for<br />

MHAs at the specific non-power reactor facility.<br />

Evaluation Findngs<br />

This section of the SAAR should contain sufficient information to support the<br />

following types of conclusions, which will be included in the staff's safety<br />

evaluation report. The reviewer should choose a conclusion from IA, IB, or IC<br />

and conclusion 2:<br />

(lA) The licensee has discussed the changes in fuel parameters, operating<br />

characteristics, and procedures that result from conversion of the reactor<br />

from HEU to LEU fuel. The effects of these changes on the assumptions<br />

and analyses of the MHA postulated for the existing HEU-fueled reactor<br />

are small enough so that the same MHA scenario is applicable for the<br />

proposed LEU-fueled reactor.<br />

(IB) The information and analyses for the MHAs of the two reactors were<br />

compared. The steps and mechanisms for transport of fission products<br />

from fuel to the unrestricted area are not significantly different, and any<br />

change in the fission product inventory or other radioactive material<br />

between the two reactors has been included in the analyses.<br />

(IC) Changes to the reactor fuel, core, operating conditions anid procedures<br />

required by the fuel conversion were shown to be significant The effects<br />

on the previously postulated MHA for the HEU-fueled reactor were shown<br />

to be large enough that a different MHA scenario was required for the<br />

proposed LEU-fiueled reactor. The licensee adopted a different analytical<br />

procedure that was demonstrated to be applicable by verification with the<br />

HEU MHA (or with other acceptable analytical techniques and references).<br />

The MHA for the LEU-fueled reactor was analyzed and appropriate, and o<br />

<strong>NUREG</strong>-<strong>1537</strong>, PART 2 44 REV 0.2/96

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