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NUREG-1537, Part 2 - NRC

NUREG-1537, Part 2 - NRC

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HEU TO LEU CONVERSION<br />

should be discussed and justified here and referenced to the technical specifications<br />

discussion.<br />

Operating parameters that verify proper core configuration and behavior and can<br />

be accurately measured, should be verified by measurements in the startup test<br />

program. A range of expected values with acceptance criteria and bases should be<br />

provided in this discussion and referenced to the startup test program discussion.<br />

Acceptance Criteria (Sections 4.5.1-4.5.4)<br />

Acceptance criteria for the dynamic'design should be based on the following<br />

considerations: The comparison of the parameters for the existing HEU and.<br />

proposed LEU cores that are significant factors in the stability and dynamic<br />

behavior of the reactor during steady-state or pulsed operation should not<br />

significantly change. The temperatuire coefficients and void coefficient of<br />

reactivity of the LEU-fueled reactor should rem'ain sufficiently negative over the<br />

allowed ranges of operation that credible reactivity additions are compensated to<br />

prevent violation of facility design and safety limits. If the coefficients are not<br />

negative, the licensee should justify the values and discuss compensating safety<br />

features. If there are no major differences"in the magnitudes or funictions of<br />

individual parameters between the IEU and LEU c'ores, the reviewer should<br />

accept the licensees use of the same analytical and computational methods to<br />

compare the performances of the two'reactors. The analyses should confirm that<br />

the analytic results for the BEU core have been qualified by reasonable agreement<br />

with the experimentally determined parameters of that core and other test cores,<br />

such as those tested at the Special Power Excursion Reactor Test (SPERT) project<br />

(Nyer et al., 1956). The safety significance of any differences between calculated<br />

and measured reactor performances should be discussed and analyzed by the<br />

licensee to demonstrate that reactor safety is ensured. The proposed conversion<br />

should be acceptable if the analyses of the HEU and LEU cores confirm (a) no<br />

significant decrease in safety margin for the ful range of operational conditions<br />

and (b) no loss of fuel integrity. The proposed startup test program plan should<br />

include verification of reactor core parameters as outlined in Section 12 that<br />

includes comparison to the predictions in this section. 'Postulated accident<br />

conditions should be evaluated in Section 13 ofthe SAR. -<br />

Review Procedures (Sections 4.5.1-4.5.4)<br />

The reviewer should evaluate all reactor parameters that affect reactor operation,<br />

determine fuel integrity, and affect oveiall reactor safety. The'reviewer should<br />

evaluate the methods and assumptions used by the licensee to analyze the<br />

operations of the REU-fueled reactor. These analyses should be qualified by<br />

comparison with experimentally determined values for the HEU core. 'The<br />

reviewer should evaluate the licensee's analyses of the LEU core and compare<br />

REv 0, 2/96 17 STANDARD REVIEWPLAN

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