ML20206G799

Supplemental Matl for First Quarter 1985 Dose Assessment Rept

ML20206G799
Person / Time
Site:	Three Mile Island
Issue date:	03/31/1985
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20206G594	List: ML20206G591 ML20206G746 ML20206G757 ML20206G768 ML20206G784 ML20206G799 ML20206G819 ML20206G839 ML20206G858
References
NUDOCS 8606250445
Download: ML20206G799 (2)

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THREE MILE ISLAND UNIT 2 LIQUID AND GASEOUS EFFLUENTS T (Sumary of All Releases) , ,0100'.

TYPE EFFLUENT JANUARY FEBRUARY MARCH 1st QUARTER 1985 Page 11 of 22 I. Liquid Effluent:

A. Fission and activation products (not including H-3 gases & alpha)

1. Total, Release (C1) (Note 2) 1.06E-5 2.29E-5 6.37E-6 3.99E-5

2. . Concentration (uc i/cc) 4.22E-12 1.15E-11 2.05E-12 5.36E-12 i B. Tritium

1. Total release (C1) 1.21E-5 1.23E-5 1.12E-5 3.56E-5 .-

2. Concentration (uC1/cc) 4.82E-12 6.18E-12 3.80E-12 4.78E-12 C. Dissolved and entrained gases

1. Total release (C1) <LLD <tLD <LLD <LLD

2. Concentration (uci/cc) N/A N/A N/A N/A D. Gross alpha radioactivity

1. Total release (C1) (Note 3) ( LLD (LW ( LLD (p E. Volume of waste released priortodilution(liters)(Note 1) 2.58E4 1.99E3 1.10E4 3.68E4 F. Volume of dilution water (flow to river in liters 2.51E9 1.99E9 2.95E9 7.45E9 fromNPDESReport) 10 9 8 27

"@@ G. Number of batch releases:

"Sn

$8 - The concentration of radioactive material other than dissolved or entrained noble gases in liquid ,

gt effluent released to the unrestricted area shall not exceed the values specified in 10CFR 20 m Appendix 8. Table II.

• om 88 - Present liquid effluent release limits are 10% of the concentration values specified in 10CFR 20, ygg Appendix 8. Table II.

ouw "ci - Liquid effluent releases are also limited to 10CFR 50, Appendix I, not to exceed a dose of 3 mrem total body and 10 mrem to any organ per year.

Note 1) Includes only those releases which were found to contain radioisotopic concentration >LLD.

Note 2) Includes Industrial Waste and Sanitary Waste.

Note 3) These activities were determmed by composite sampling

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ATTACHMENT k4I 1985 UNIT 2 LIQUID RADIONUCLIDE RELEASES BY ISOTOPE (C1) ge f RADIONUCLIDE JANUARY FEBRUARY HARCH 1st QUARTER 1985 Fission and activation products (not including alpha H-3 8 gases) <LLD <LLD <LLD <tLD Ag-110m ' <LLD <LLD <LLD <LLD Ce-144 <LLD <LLD <LLD <lLD

- Co-58 - <LLD <tLD <LLD <lLD

~

Co-60 <LLD <LLD <LLD <LLD Cs-134 <LLD <LLD <LLD <LLD Cs-137 1.09E-6 1.61E-6 1.06E-6 3.76E-6 I-131 ,

<tLD <LLD <tLD <LI.D Sr-90

• 9.49E-6 2.13E-5 5.31E-6 3.61E-S TOTAL 1.06E-5 2.29E-5 6.37E-6 3.99E-5 H-3 1.21E-5 1.23E-5 1.12E-5 3.56E-5

• The values reported include Sr-90 activity and any activity not specifically identified. Thus, the reported Sr-90 value represents a conservative estimate (i.e. overestimate) and contains activity fran other beta-garmn emitters which were not positively identified during conduct of analytical procedures.

90

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