ML20215G149

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Errata to Semiannual Radioactive Effluent Release Rept for Jul-Dec 1986, Correcting Direct Radiation Results from Sectors at the Site Boundaries
ML20215G149
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 12/31/1986
From:
ALABAMA POWER CO.
To:
Shared Package
ML20215G121 List:
References
NUDOCS 8706230138
Download: ML20215G149 (1)


Text

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  • MAXIMUM
  • OFF-SITE DOSES AND DOSE COMMITMENTS TO MEMBERS OF'THE PUBLIC Dose, M1111 rems Source 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year **

Note: l

+

Organ BONE LIV LIV .GI GI Liquid Effluents (1) 4.4E-02 2.7E-021.0E-02 9.9E-02,.144E-01 Airborne Effluents s Sector SW W SW 'SW SW Iodines & 4.3E-03 1.6E-03 2.5E-03 1.3E-02 2.1E-02 Particulates (2)

Sector WFW S W WSW WSW Noble gases (3) 4.5E-03 3.0E-03 3.9E-03 1.4E-02 2.4E-02 Sector NE E E NE NE Direct Radiation (4) 2.7E 01 2.8E 01 2.5E 01 2.7E 01 9.0E 01

  • " Maximum" means the largest fraction of the corresponding 10CFR50 Appendix I dose design objective.
    • " Maximum" dose for the year may not equal the sum of the quarterly maximum doses because the doses may be to different organs or may occur at different places.

Notes l

1. The liquid effluent total body and organ doses are determined primarily by the fish pathway. These are calculated using the bioaccumulation factors , dose conversion factors and assumptions of Regulatory guide 1.109 (March 1976).
2. Airborne effluent iodine and particulate doses are determined through the inhalation pathway using reported isotopic con- ,

centrations, atmospheric dispersion assumptions of Regulatory i

guide 1.111 (March 1976) and inhalation dose factors of j Regulatory guide 1.109. Once calculated these doses are multiplied by a constant (230) to convert them to the grass / cow /

milk pathway equivalents in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

3. The noble gas doses are determined using the measured isotopic concentrations, the atmospheric dispersion assumptions of Regulatory guide 1.111 and submersion dose factors from Reg-ulatory guide 1.109.
4. Direct radiation was assessed using thermal luminescent dos-imetry. Two dosimeters containing three LiF TLD chips each were placed at selected locations within each of 16 sectors around the plant. These chips were collected and read quarterly and annually.

i 0706230138 8706 PDR ADOCK 05000 48 PDR Miended May 8, 1987 R

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