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NUREG-1537, Part 2 - NRC

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APPENDvx 18.1<br />

I *<br />

Acceptance Criteria ,)<br />

Acceptance Criteria for the scenario and consequences of the postulated LOCA<br />

should be based on the following considerations: The initiating event and<br />

scenarios for the existing BIEU- and the proposed LEU-fueled reactor should be<br />

siilar, unless the conversion requires significant changes in facility design or<br />

operating characteristics. If the scenarios are similar, similar assu'mptions and<br />

methods-of analysis should be used. 'The analysis should show that the LEU-fueled<br />

reactor systems and fuel are designed to ensure that fuel integrity is not lost and<br />

that potential risk of damage to fuel or systems is not significantly increased by the<br />

conversion.<br />

If changes in reactor systems, fuel, or operating characteristics required by the<br />

conversion are significant, a new scenario may be required as well as a different<br />

analytical method. The licensee should validate any significant differences in these<br />

factors by comparison with the HEU-fueled reactor and any applicable analyses. If<br />

different analyses are required, they should show that the LEU-fueled reactor fuel<br />

and systemn designs are sufficient to show that'any consequences of the LOCA are<br />

within acceptance criteria for the HEU-fueled reactor. The information should<br />

include reference to applicable technical specifications that ensure operability and<br />

availability of any required ECCS for which credit is taken in the analyses.'<br />

Review Procedures ><br />

The reviewer'should compare the information provided to-determine if there are<br />

significant differences in the postulated LOCA events for the HEU- and LEUfueled<br />

reactors. The reviewer should find any differences and trace the scenarios<br />

and analyses from initiation of the event until conditions are stabiliied. The<br />

information should justify changes in reactor systems or operating characteristics<br />

designed to mitigate consequences to fuel, the reactor, and the public.<br />

The reviewer should compare the analyzed consequences for the HEU- and LEUfiueled<br />

reactors and should compare the LEU consequences with the acceptance<br />

critera<br />

Ewluation Findings<br />

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

following type of conclusions, which will be included in the staffs safety<br />

evaluation report:<br />

* The licensee assumed the same loss-of-coolant initiating event and scenario<br />

for the proposed LEU-fueled reactor as previously postulated for the<br />

licensed HEU core (e.g., the instantaneous, total loss of coolant). The<br />

<strong>NUREG</strong>.1S37,PAR~T2 50 REv. O, 2/96<br />

Ns

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