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NUREG-1537, Part 2 - NRC

NUREG-1537, Part 2 - NRC

NUREG-1537, Part 2 - NRC

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RADIAnON PRoTEcnoN PROGRAM AND WASTE MANAGEmEr<br />

* The applicant should present the best estimates of the maximum annual<br />

dose and the collective doses for major radiological activities during the full<br />

range of normal operations for facility staff and members of the public.<br />

The doses shall be shown to be within the applicable limits of 10 CFR<br />

<strong>Part</strong> 20.<br />

* Airborne radioactive material sources should be described in sufficient<br />

detail to provide the bases for the design and assessment of structures,<br />

systems, and components, and of personnel protective measures and dose<br />

commitments. -<br />

* Conservative best estimates of the predicted concentrations, locations, and<br />

quantities of airborne radionuclides during the full range of normal<br />

operation in areas occupied by personnel should be discussed.<br />

* Conservative best estimates of the predicted locations and magnitude of<br />

external radiation fields during the full range of normal operation in areas<br />

occupied by or accessible to personnel should be discussed.<br />

* The applicant should identify models and assumptions that are used for<br />

predicting and calculating the dose rates and accumulative doses from such<br />

radionuclides as &rgonAl (Ar-41), nitrogen-16 (N-16), and vapors,<br />

aerosols, and airborne radioactive particulates in both restricted, controlled<br />

(if present), and unrestricted areas. The applicant should identify<br />

(1) locations of specific sources (e.g., coolant water, beam tubes, and gasor<br />

air-driven rabbit systems), (2) expected production rates, release rates,<br />

and concentration distributions in occupied areas and resultant personnel<br />

doses or dose rates, and (3) release points from the control of the reactor -<br />

facility, dilution air (quantities and sources), quantities and concentrations<br />

expected to be released, dispersion and diffusion, concentration at point of<br />

interest, applicable average atmospheric conditions, plume spread,expected<br />

concentration distnibutions in unrestricted areas, and applicable<br />

radiation dose rates, including gamma-ray shine from elevated plumes and<br />

inhaled or ingested dose commitments. The analysis should contain<br />

conservative best estimates of the predicted annual total doses to at least<br />

the following in the unrestricted areas: (1) the ma=im exposed<br />

;indiidual, (2) the nearest permanent residence, and (3) any location of<br />

special interest, such as a classroom or campus dormitory. The discussion<br />

and calculations should show that the sums of internal and external doses<br />

to thefacility. staffand the public are within the limits of IO CFR <strong>Part</strong>20 -<br />

and that ALARA principles are applied. -<br />

* Liquid effluent volumes and radionuclide concentrations should be shown<br />

to be within the requirements of 10 CFR <strong>Part</strong> 20. The discussion should<br />

-REV. 0,2196 - - 11-3 - STANDARD REVIEW PLAN<br />

--REV. 0, Z% .-- . - 11-3- STANDARD REviEwPN

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