ML19256E513

Proposed Changes to ETS 2.2 & 2.4 Re Calculation of Dose Rates

ML19256E513
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/31/1979
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19256E510	List: ML19256E509 ML19256E513
References
NUDOCS 7911070553
Download: ML19256E513 (7)

Text

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2.4 Radioactive Discharge Objective To define the limits and conditions for the controlled release of radioactive effluents to the environs to ensure that these releases are as low as practicable. These releases should not result in radiation exposures in unrestricted areas greater than a few per-cent of natural background exposure. The release rate for all effluent discharges should be within the limits specified in 10 CFR Part 20.

To assure that the release of radioactive material to unrestricted areas meet the as-low-as-practicable concept, the following objectives apply:

For Liquid Wastes:

a. The annual total quantity of radioactive materials in liquid waste, excluding tritium and dissolved gases, should not exceed 5 curies;

b. The annual average concentration of radioactive materials in liquid waste upon release from the Restricted Area, ex-cluding tritium and dissolved noble gases, shall not exceed 2 x 10-8 uCi/ml; and

c. The annual average concentration of dissolved gases in liquid waste, upon release from the Restricted Area, shall not exceed 2 x 10-6 uCi/ml.

For Caseous Wastes:

a. Averaged over a yearly interval, the released rate of noble gases and other radioactive isotopes, except I-131 and par-ticulate radioisotopes with half-lives greater than eight days, discharged from the plant should be limited as follows:

1.4 x 10-4 sec/m3 91 3 1 (MPC)1 Where Qi is the release rate in Ci/sec for isetope i and (MPC)1 is the maximum p'rmissible concentration of isotope i as defined in Appendix B, Table II, Column 1, 10 CFR Part 20.

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2-12 annual exposure from liquid wastes to the whole body or any organ of an individual will not exceed 5 mrem per year. At the same time, the Licensee is permitted the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a deper.dable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels, but still within the con-centration limits specified in 10 CFR 20. It is expected that using this operational ficxibility under unusual operating conditions, the Licensee shall exert every effort to keep levels of radioactive materials as low as oracticable, and that annual releases will not exceed a small f raction of the annual average concentration limits specified in 10 CFR 20.

2.4.2 Gaseous Discharge Specification

1. When the release rate of radioactive materials ia gaseous wastes averaged over a calendar quarter is such that the quantities of I noble gases and other radioactive isotopes, except I-131 and I particulate radioisotopes with half-lives greater than eight daya, exceeds twice the design objective, or exceeds 2% of 2.4.2.3.b, the Licensee shall notify the Commission within 30 days, identify-ing the causes of the excessive activity and describing the pro-posed program of action to reduce such relcases to design objective levels.

2. The maximum activity to be contained in one Waste Gas Decay tank shall be limited to 15,480 Ci.

3. a. The rate of release of radioactive materials and gaseous wastes from the plant (except I-131 and particulate ra ioisotopes with half-lives greater than eight days) cveraged over any one-hour period shall not exceed:

Qi _ <

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1 6.7 x 10" m>/sec (MPC)1 Where Qi is the release rate in Ci/sec for isotope i and (MPC)i is the maximum permissible concentration of isotope i as defined in Appendix B, Table II, Column 1, 10 CFR Part 20.

b. The release rate of I-131 and particulates with half-lives greater than eight days released to the environs as part of airborne effluents, shall not exceed 0.96 uCi/sec.

4. a. The release rate of gross gaseous activity averaged over a calendar quarter shall not be such that the quantities of noble gases and other radioactfie isotopes, except I-131 and particulate radioisotopes w-th half-lives greater than eight days, exceeds eight times the design objective.

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, The noble gas release rates stated in the objectives are based on a X/Q value from the annual meterological data. The dispersion factor used, 2.8 x 10-6 sec/m3, is corservative and the release rate is controlled to a small fraction of 10 CFR 20 requirements at the exclusion area boundary (.02 of 10 CFR 20 -

10 mrem per year). The dispersion factor is taken from annual meterological data taken at the ANO site (see ANO-2 FSAR Section 2.3.4.4, Page 2.3-30) and is based on the majority of the gaseous activity released from the site vill be released from the waste gas decay tanks and reactor building purges, within the time frame of 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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The annual average concentration of radioactive materials in liquid waste upon release from the Restricted Area, excluding tritium and dissolved noble gases, should not exceed 2 x 10-8 uCi/ml.

The annual average concentration of dissolved gases in liquid waste, upon release from the Restricted Area, should not exceed 2 x 10-6 uCi/ml. _

For Caseous Wastes: ,

a. Averaged over a yearly interval, the release rate of noble gases and other radioactive isotopes, except I-131 and particulate radioisotopes with half-lives greater than eight days, dis-charged from the station should be limited as follows:

zy , sec ,

1.4 x 10-4 T Qi f 1 (MPC)1 Where Qi is the release rate in Ci/sec for isotope i and (MPC)1 is the maximum permissible concentration of isotope i as defined s in Appendix B, Table II, Column 1, 10 CFR Part 20.

b. Averaged over a yearly interval, the release rate of I-131 and other particulate radioisotopes with half-lives longer than eight days discharged from the station, should result in a dose in the unrestricted area of less than 15 mrem to the thyroid of a child through the grass-cow-milk chain; and the total annual quantity of iodine-131 discharged from ANO-2 should not exceed 1 C1.

2.2.1 l* quid Discharge Specification

1. The rate of release of radioactive materials in liquid waste from the station shall be controlled such that

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,' to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentration limits specified in 10 CFR 20.

It is expected that using this operational flexi-bility under unusual operating conditions, the Licensee shall exert every effort to keep levels of radioactive material low as reasonably achieve-ablq and that annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR 20.

2.2.2 Caseous Discharge Specification

1. When the release rate of radioactive materials in gaseous wastes, averaged over a calendar quarter is such that the quantities of noble gases and other radioactive isotopes, except I-131 and par-ticulate radioisotopes with half-lives greater than eight days exceeds twice the design objective, or exceeds 2% of 2.2.2.3.b, the Licensee shall notify the Commission within 30 days, identifying the causes of the excessive activity, and describe the proposed program of action to reduce such releases to design objective levels.

2. The maximum activity to be contained in one Waste Gas Decay Tank shall be limited to 16, ISO C1.

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3. a. The rate of release of radioactive materials and gaseous wastes from the station (except I-131 and particulate radioisotopes with half-lives greater than eight days) averaged over any one-hour period shall not exceed:

01 4

~

1 6.7 x 104 m3 (MPC)1 sec Where Qi is the release rate in Ci/sec for isotope i and (MPC)1 is the maximum permissible concentration of isotope as defined in Appendix B, Table II, Column 1, 10 CFR Part 20.

b. The release rate of I-131 and particulates with half-lives greater than eight days released to the environs from the station, as part of airborne effluents shall not exceed 0.9f uCi/sec.

4. a. The release rate of gross gaseous activity averaged over a calendar quarter shall not be such that the quantities of noble gases and other radioactive isotopes, except I-131 and particulate radioisotopes with half-lives greater than eight days, exceeds eight times the design objective.

b. The release rate of I-131 and particulates with half-lives greater than eight days shall not exceed 87. of the values specified in 2.2.2.2.b when averaged over a calendar quarter.

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source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentration limits specified in 10 CFR 20. It is expected that using this operational flex-ibility under unusual operating conditions, the Licensee shall exert every effort to keep levels of radioactive materials and gaseous wastes as low as reasonably achievable and that annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR 20. These efforts shall include consideration of meteorological conditions during releases.

The noble gas release rates stated in the objectives are based on a X/Q value from the annual meteorological data. The dis-persion factor used, 2.8 x 10-6 sec/m3, is conservative and the release rate is controlled to a small fraction of 10 CFR 20 requirements at the exclusion area boundary (.02 of 10 CFR 20

- 10 mrem per year). The dispersion factor is taken from annual meteorological data taken at the ANO site (see ANO-2 FSAR Section 2.3.4.4, Page 2.3-30) and is based on the majority of the gaseous activity released from the site will be released from the waste gas decay tanks and reactor building purges, within the time frame of 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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