ML20206G819

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Supplemental Matl for Second Quarter 1985 Dose Assessment Rept & Semiannual Radioactive Effluent Release Rept
ML20206G819
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 06/30/1985
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20206G594 List:
References
4410-86-L-0100, 4410-86-L-100, NUDOCS 8606250450
Download: ML20206G819 (4)
v • d • e


Text

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ATTACHMENT . .

EFFLUENT

SUMMARY

'L' THREE MILE ISLAND UNIT 2 LIQUID AND GASE0US EFFLUENTS Pa e or (Summary of All Releases)

APRIL MAY JUNE 2nd QUARTER 1985 TYPE EFFLUENT l 1. Liquid Effluent:

- A. Fission and activation products (not includir.g H-3, gases & alpha) 3.85E-5 4.96E-5 7.22E-6 3.85E-6

1. Total Release (C1) (Note 2) 9.84E-12 4.15E-12 Concentration (pC1/cc) 1.16E-12 1.04E-12 2.

B. Tritium <LLD <LLD 7.25E-5 7.25E-5

1. Total release (C1) 2.21E-11 7.69E-12
2. Concentration (pci/cc) N/A N/A C. Dissolved and entrained gases <LLD

<LLD <LLD <LLD

1. Total release (C1) N/A N/A
2. Concentration (pC1/cc) N/A N/A i

D. Gross alpha radioactivity l

1. Total release (C1) (tbte 3) (m (g (g E. Volume of waste released 1.18E5 1.44E5 prior to dilution (liters) (Note 1) 1.09E4 1.46E4 l mim F. Volume of dilution water E$ (flow to river in liters 2.96E9 3.19E9 3.28E9 9.43E9 from NPDES Report)

>u l ES G. Number of batch releases: 6 24 39 Sumps and sewage 9

) 28 Os - 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,

)g

, miu AppendixB. Tab leII.

l - Present liquid effluent release limits are 10% of the concentration values specified in 10CFR 20, 1 Appendix 8. Table II.

I - 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. ,

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

J Mote 2) Includes Industrial Waste and Sanitary Waste.

Note 3) These activities were determined by cmposite sampling.

.f 1

ATTACHMENT ^ '

4410-86-t-0100 - -

Page 14 of 22 1985 UNIT 2 LIQUID RADIONUCLIDE RELEASES BY ISOTOPE (Ci)

APRIL MAY JUNE 2nd QUARTER 1985 RADIDNUCLIDE Fission and activation products <LLD <tLD <LLD

<LLD (not including alpha, H-3 & gases)

<LLD <LLD <LLD

<LLD Ag-110m

<LLD <LLD <LLD

<LLD C -144

<LLD <LLD <LLD

<LLD Co-58

<LLD <LLD <LLD

<LLD Co-60

<LLD <LLD <LLD

<LLD Cs-134 2.72E-6 5.28E-7 1.11E-5 1.43E-5 Cs-137

<LLD <LLD <LLD

<LLD I-131 4.50E-6 3.32E-6 2.74E-5 3.52E-5 Sr-90

  • 7.22E-6 3.85E-6 3.85E-5 4.%E-5 TOTAL

<LLD <LLD 7.25E-5 7.25E-5 N-3

  • t e values reported include Sr-90 activity and any activity not specifically identified. % us, the reIrrted Sr-90 value represents a conservative estinate (i.e. overestimate) and contains activity from other beta-ganna ptters which were not positively identi,fied during conduct of analytical procedures.

ATTACHMENT l

4410-86-L-0100 Page 15 of 22 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFrLUENTS-SUMMATION OF ALL RELEASES Tech _. Spec. Limit = 10CFR20, Appendix B. Table II, Column 2 UNIT If8{ Iffh EST. TOTAL QUARTER QUARTER ERROR %

' 11 A. Fission and activation products

1. Total releases (not including 605, tritium, gases, alpha) Ci 3.99E-5 4.96E-5
2. Average calutec concentration -

durine eeriod pCi/mi 5.36E-12 a ice.2, Based on 2E-5

3. Percent of applicable limit  % 2.68E-5 2.08E-5 pCi /ml (Cs-137 )

B. Tritium

1. Total release ci 3.56E-5 7.25E-5 60%
2. Average calutec concentration durine eeriod UCi/ml 4.78E-12 7.69E-12 Based on 3E-3
3. Percent of applicable limit  %

1.59E-7 2.56E-7 pCi/ml (H-3)

C. Dissolved and entrained gases

1. Total release ci < LLD < LLD 60%
4. Average cilutec ccr. centration d urine eeriod uCi/ea N/A N/A
3. Percent of applicable limit  % N/A N/A D. Gross alpha radioactivity 1

j 1. Total release (Note 3) Ci (E (E 60's l i

l 4

a E. Voluse or waste releaseo j

(rrier to dilution) liters 5.67E4 1.44E5 25%

_F.)]lygeo{rdigutionwaterused liters 7.45E9 9.43E9 10%

  • Includes only those releases mentioned in Note (1) which were found to contain radio-isotope concentrations >LLD. .

f;0te:(1):There were no liquid releases from the radwaste system during the first half of 1985 since this system is flanged off from the discharge lines. However, low concentrations of radionuclides have been occasionally found in the industrial waste stream and sanitary waste and are appropriately included in Item A2.

N:te:(2): Refer to Table 5 for typical LLD values.

Note:(3):These values were determined by offsite vendor analysis of a composite sample.

STTACHMENT 4410-86-L-0100 Page 16 of 22 TABLE 2B EFFLLT.NT A'?D WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS (Note 1)

Continuous Mode Batch Mode Nuclides UNIT k knb Afff Ifbh QUARTER QUARTER QUARTER QUARTER Released II 5 ;t S EE strentium-89 Ci NDT : 2 NOT E2 < LLD < 11 D strentium-90 (Note 3) Ci 3.61-5 3.61E-6 3.52E-5

< LLD < LLD cesiu=-134 Ci eesium-137 Ci 3.76E-6 1.43E-5 iodine-131 c4 < LLD < LLD cebalt-58 Ci < LLD < LLD cobalt-60 Ci < LLD < LLD iron-59 Ci < LLD < LLD eine-65 Ci < LLD < LLD enn a ean e c e- 54 Ci < LLD < LLD chre=it=r51 Ci < LLD < LLD zirceniu -nicbium-95 Ci < LLD < LLD colybdenu=-99 Ci < LLD < LLD technetium-99m Ci < LLD < LLD b arium-lan thanu=-140 Ci < LLD < LLD cerium- 141 Ci < LLD < LLD Other (snecifv) Ci < LLD < LLD Ci Ci l

Ci Ci Ci cf Te sl for perfed C1 3.99E-5 4.96E-5 xenen-133 Ci ,

< LLD < LLD '

xenen-135 Ci < LLD < LLD btE

!!E

{l)gn;.e;escnijtnoSereleasesmentionedinHote(1)page6.

s-) ir.ere was no continuous release of effluent from Unit II duri.n

te (3) These values include Sr-90 and any activity not specifically 1g tipg sgcond half of 1985.

l

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