ML20206G768

Supplemental Matl for Third Quarter 1984 Dose Assessment Rept

ML20206G768
Person / Time
Site:	Three Mile Island
Issue date:	09/30/1984
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20206G594	List: ML20206G591 ML20206G746 ML20206G757 ML20206G768 ML20206G784 ML20206G799 ML20206G819 ML20206G839 ML20206G858
References
NUDOCS 8606250437
Download: ML20206G768 (2)

Text

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ATTACHMENT 4410-86-L-0100 ,

EFFLUENT

SUMMARY

Page 5 of 22 THREE MILE ISLAND UNIT 2 LIQUID AND GASEOUS EFFLUENTS (Sumary of All Releases)

JULY AUGUST SEPTEMBER 3rd QUARTER TYPE EFFLUENT I. Liquid Effluent:

A. Fission and activation products (not incibding H-3, gases & alpha) 2.37E-4 2.82E-6 1.01E-5 2.24E-4

1. Total Release (Ci) (Note 2) 7.21E-11 1.41E-11

2. Concentration (nCf/cc) 4.79E-13 1.95E-12 3

B. Tritium 1.30E-5 1.22E-5 2.52E-5

1. Total release (C1) <LLD 4.11E-12 3.96E-12 2.63E-12

2. Concentration (pci/cc) <LLD C. Dissolved and entrained gases <LLD

<LLD <LLD <tLD

1. Total release (C1) N/A N/A N/A

2. Concentration (pC1/cc) N/A , ,

D. Gross alpha radioactivity

1. Total release (C1) (Note 3) CID (UD (un ;ng E. Volume of waste released 9.70E4 1.45E5 priortodilution(liters)(Note 1) 1.45E4 3.33E4 mwo F. Volume of dilution water i Eo (flow to river in liters 3.36E9 3.16E9 3.08E9 9.60E9 i

$ from NPDES Report) wa 8 13 29 50 ES G. Number of batch releases:

SO OE - The concentration of radioactive material other than dissolved or entrained noble gases in liquid 88 effluent released to the unrestricted area shall not exceed the values specified in 10CFR 20, 1

885 Appendix B. Table II.

mn j - Present liquid effluent release limits are 10% of the concentration values specified in 10CFR 20 Appendix 8. Table II.

~

- Liquid effluent releases are also limited to 10CFR 50, Appendix I, not to exceed a dose of 3 mrem i

total body and 10 mrem to any organ per year.

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

I Note 2) Includes Industrial Waste and Sanitary Waste. t 1 Note 3) These activities were determined by cmposite sampling.

ATTACHMENT 4410-86-L-0100 9

1984 UNIT 2 LIQUID RADIDHUCLIDE' RELEASES BY ISOTOPE (C1)

JULY AUGUST SEPTENDER 3rd QUARTER RADIONUCLIDE Fission and activation products <LLD <LLD <LLD (not including alpha. H-3 & gases) <tLD

<tLD <LLD <LLD

<LLD Ag-110m

<LLD <LLD <LLD (LLD Ce-144

<LLD <LLD <LLD C:;-58 <LLD

<LLD <LLD <LLD

<LLD Co-60

<LLD <LLD 1.07E-6 1.07E-6 Cs-134 1.21E-6 4.84E-6 8.94E-5 9.55E-5 . .

Cs-137 ,

<LLD <LLD

<LLD ", <LLD 1-131 1.61E-6 5.23E-6 1.34E-4 1.41E-4 Sr-90

• 2.82E-6 1.01E-5 2.24E-4 2.37E-4 TOTAL (LLD 1.30E-5 1.22E-5 2.52E-5 H-3

. Thus, the i ' *Tne values reported include Sr-90 activity and any activity not specifically identified.

3, reported Sr-90 value represents a conservative estinate (i.e. overestimate) and contains activity fran other beta ganun emitters which were not positively identified during conduct of analytical procedures.

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