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NUREG-1537, Part 2 - NRC

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CHAPTRS<br />

acceptable radiological dose consequence limits derived from the accident<br />

analyses. The radiological consequences from the contaminated coolant<br />

should be discussed in Chapter 11 and summarized in this section of the<br />

SAR. Necessary surveillance provisions should be included in the technical<br />

specifications.<br />

The applicant should identify operational limits, design parameters, and<br />

surveillances to be included in the technical specifications.<br />

Review Procedures<br />

The reviewer should compare the functional design and the operating<br />

characteristics of the primary coolant system with the bases for the design<br />

presented in this and other relevant chapters of the SARI The system design<br />

should meet the appropriate acceptance criteria presented above considering the<br />

specific facility design under review.<br />

Evaluation Findings<br />

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

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

evaluation report:<br />

* The primary coolant system is designed in accordance with the design<br />

bases derived from all relevant analyses in the SAR<br />

* Design features of the primary coolant system and components give<br />

reasonable assurance of fuel integrity under all possible reactor conditions.<br />

The system is designed to remove sufficient fission heat from the fuel to<br />

allow all licensed operations without exceeding the established limiting<br />

safety system settings that are included in the technical specifications.<br />

* Designs and locations of primary coolant system components have been<br />

specifically selected to avoid coolant loss that could lead to fuel failure,<br />

uncontrolled release of excessive radioactivity, or damage to safety systems<br />

or experiments. Heavy water systems are designed to quickly detect<br />

leakage and prevent the release of heavy water to the environment. (If an<br />

emergency core cooling system is required to prevent a loss offuel<br />

integrity, it is evaluated in connection with the review of the engineered<br />

safetyfeatures.)<br />

(For reactors licensed to operate withforced-convection coolant flow)<br />

The primary coolant system is designed to convert in a passive or fail-safe<br />

method, to natural-convection flow sufficient to avoid loss of fuel integrity.<br />

<strong>NUREG</strong>-<strong>1537</strong>,PART2 5-6 REV 0,2/96<br />

<strong>NUREG</strong>-<strong>1537</strong>, PART2 5-6 REV 0, 2/96<br />

-as-

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