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NUREG-1537, Part 2 - NRC

NUREG-1537, Part 2 - NRC

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SnE CHARAcrmusncs<br />

* The demographic information is sufficient to allow accurate assessments of<br />

the potential radiological impact on the public resulting from the siting and<br />

operation of the proposed reactor.<br />

* There is reasonable assurance that no geographic or demographic features<br />

render the site unsuitable for operation of the proposed reactor.<br />

2.2 Nearby Industrial, Transportation, and Military<br />

Facilities<br />

Areas of Review<br />

The reviewer should evaluate the reactor site and its vicinity for location and<br />

separation distances from existing and planned industrial, military, and<br />

transportation facilities and routes. Such facilities and routes include air, ground,<br />

and water traffic, pipelines, and fixed rianuflcturing; processing, and storage<br />

facilities. The reviewer should focus on facilities, -activities, and materials that may<br />

reasonably be expected to be present during the projected lifetime of the nonpower<br />

reactor. The purpose of this review is to e%;aluate the information<br />

concerning the presence and magnitude of potential hazards to the reactor due to<br />

local manmade facilities.<br />

Acceptance Criteria<br />

The acceptance criteria for the information on nearby industrial,'transportation,<br />

and military facilities include the following: -<br />

* The information presents a complete and current overview of facilities,'<br />

activities, and materials located in the vicinity of the reactor site.<br />

* 'The information is complete enough to support evaluations of potential<br />

risks posed by these facilities to the safe operation and shutdown of the..<br />

reactor during its projected lifetime. - -<br />

* The analyses show that none of the expected manmade facilities could<br />

cause damage or cther hazards to the reactor sufficient to pose undue<br />

radiological risks to the operating staff the public, or the environment.<br />

Consequences of such eventsiare analyzed in or are shown to be bounded<br />

by accidents considered in Chapter 13 of the SAR.<br />

Reiew Procedures<br />

The reviewer should confirm that any hazards to the reactor facility posed by<br />

normal operation and potential malfunctions and accidents at the nearby manmade<br />

REV. 0. 2196 2-3 STANDMARD REVIEW PLAN

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