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NUREG-1537, Part 2 - NRC

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13 ACCIDENT ANALYSES<br />

Other chapters of the SAR should contain discussions and analyses of the reactor<br />

facility as designed for normal operation. The discussions should include the<br />

considerations necessary to ensure safe operation and shutdown of the reactor to<br />

avoid undue risk to the health and safety of the public, the workers, and the<br />

environment. -The analyses should include limits for operating ranges and reactor<br />

parameters within which safety could be ensured. The bases for the technical<br />

specifications should be developed in those chapters.<br />

In this chapter the applicant should present a methodology for reviewing the<br />

systems and operating characteristics of the reactor facility that could affect its safe<br />

operation or shutdown. The methodology should be used to identify limiting<br />

accidents, analyze the evolution of the scenarios, and evaluate the consequences.<br />

The analyses should start with the assumed initiating event. The effects on<br />

designed barriers, protective systems, operator responses, and mitigating features<br />

should be examined. The endpoint should be a stable reactor., The potential<br />

radiological consequences to the public, the facility staff, and the environment<br />

should be analyzed. The information and analyses should show that facility system<br />

designs, safety limits, limiting safety system settings, and limiting conditions for.;<br />

operation'were selected to ensure thatfthe consequences of analyzed accidents do<br />

not exceed acceptable limits. -<br />

The applicant should also'discuss and analyze postulated accident scenario<br />

whose potential consequences are shown to exceed and bound all credible<br />

accidents. For non-power reactors, this accident is called the maximum<br />

hypothetical accident (MHA). Because the accident of greatest consequence at a<br />

non-power reactor would probably include the release of fission products, the<br />

MHA, in most cases, would be expected to contain such a scenario involving fuel<br />

or a fueled experiment and need not be entirely credible. The review and<br />

evaluation should concentrate on the evolution of the scenario and analyses of the<br />

consequences, rather than on the details of the assumed initiating event.<br />

Because"the consequences of the postulated MHA lhould exceed those of any.<br />

credible accident at the facility, the accident is not likely to occur during the life of<br />

the facility. The MHA is used to demonstrate that the maxinum consequences of<br />

operating'the reactor at a specific site are ithin acceptable limits. The applicant<br />

may choose to perform sensitivity analysis of the assumptions of the MHA. For<br />

example, reactor operating time before accident initiation mnay be examined to<br />

determine the change in MHA outcome if a more realistic assumption is made.<br />

Assumptions made in the accident analysis may form the basis for technical<br />

specification limits on the operation of the facility For example, if the accident<br />

analysis assumes that the reactor operates for 5 hours a day, 5 days a week, this<br />

may become a limiting condition for operation.<br />

REv 0,2196 13-I STANDARD REVIEW PLAN<br />

REV 0, 2/96 . . - . - 13-1 -"' STANDARDREviEwPLAN

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