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NUREG-1537, Part 2 - NRC

NUREG-1537, Part 2 - NRC

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CHvArEI<br />

requirements changed or the applicant made changes to the facility or utilization<br />

program that resulted in these conservative results being unacceptable. At that<br />

point, the applicant had to perform an analysis with assumptions and calculational<br />

methods that were more realistic in order to demonstrate compliance with<br />

regulatory requirements, and also had to explain the conservatism in the original<br />

analysis.<br />

In this chapter of the SAR, the applicant should discuss the capabilities of the<br />

reactor facility to control, collect, handle, process, store for short or long periods,<br />

and dispose of liquid, gaseous, and solid radioactive wastes related to reactor<br />

operations and utilization in a manner planned to protect the public, the<br />

environment, and facility staff. The instrumentation and methods used to monitor<br />

radiation exposures to personnel and the release of radioactive materials, including<br />

sampling methods, should be discussed by the applicant.<br />

11.1 Radiation Protection<br />

The provisions for radiation protection should be described completely in the<br />

sections that follow.<br />

11.1.1 Radiation Sources<br />

Areas of Review<br />

To develop a comprehensive radiation protection program, it is important to<br />

understand all sources of radiation exposure at the faclity Therefore, the<br />

applicant should provide complete listings and discussion of all expected radiation<br />

and radioactive sources. The reviewer should evaluate information requested of<br />

the applicant in the corresponding section of the format and content guide. As<br />

indicated there, airborne, liquid, and solid sources, including radioactive wastes,<br />

should be discussed.<br />

Acceptance Criteria<br />

The acceptance criteria for information concerning sources of radiation include the<br />

following:<br />

* All sources of radiation should be discussed by the applicant. This<br />

discussion should include the physical and chemical form, type (e.g.,<br />

neutron, gamma), curie strength or exposure rates, energy level,<br />

encapsulation (sealed or unsealed), use, storage conditions and locations,<br />

and planned program for disposal of all radioactive material subject to the<br />

reactor license.<br />

<strong>NUREG</strong>-I 537, PART 2 31-2 FRE. 0,2/96

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