Text

Semiannual Rept,Plant Radioactive Effluent Releases, Jan-June 1983.
	ML20080C993
Person / Time
Site:	Hatch
Issue date:	06/30/1983
From:	Nix H; GEORGIA POWER CO.
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	GM-83-850, NUDOCS 8308290422
	Download: ML20080C993 (46)
	v • d • e

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Georgia Power Company Aue One B:n 278 E8d ey Ga ;a 31513 9 ene ,= 412 367 7781 912 537 9444 A L O -

...,,.e.,,,,.,,,,,, . eop%u August 25, 1983 GM-83-849 PLANT E. I. HATCH Semi-Annual Radioactive Effluent Release Report Mr. James P. O'Reilly U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II, Suite 3100 101 Marietta Street Atlanta, Georgia 30303

Dear Mr. O'Reilly:

(]) Pursuant to Section 5.7.1.b in Appendix B, Environmental Technical Specifications, of the Plant Edwin I. Hatch Operating Licenses, please find enclosed the Semi-Annual Report for Plant Radioactive Effluent Releases, January 1, 1983 through June 30, 1983.

I H. C. Nix General Manager WHR/jak xc: G.F. Head (1)

J.T. Beckham (1)

T.V. Greene (1)

H.L. Sumner (1)

C.T. Jones (1)

R.W. Zavadoski (1)

W.H. Rogers (4)

T.E. Byerley (3)

W.H. Ollinger (1)

D.B. Cochran (1)

J. Setser, Ga. Dept. Nat. Resources (1)

File: M84-4

< 8308290422 830630 PDR ADOCK 05000321 R PDR

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GEORGIA POWER COMPANY PLANT E. I. HATCH UNITS NO. 1&2 SEMI-ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JANUARY 1, 1983 - JUNE 30, 1983 O

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PLANT E. I. HATCH i

' SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES TITLE PAGE SECTION

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LIOUID EFFLUENTS 1 1.

REGULATORY LIMITS 1 1.1 MAXIMUM PERMISSIBLE CONCENTRATIONS 2 1.2 4 1.3 MEASUREMENTS AND APPROXIMATIONS OF 4

TOTAL RADIOACTIVITY , ,

6 1.4 LIQUID EFFLUENT RELEASE DATA GASEOUS EFFLUENTS 24 2

REGULATORY LIMITS 24 2.1 2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 26 2.3 GASEOUS EFFLUENT RELEASE DATA 30 3 SOLID WASTE 30 3.1 REGULATORY SPECIFICATIONS 30

[]} 30

, 3.2 SOLID WASTE DATA i

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PLANT E. I. HATCH l SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES O FIGURE LIST OF FIGURES PAGE 7

l-1 METHODS OF MEETING TABLE II COLUMN 2 MPC LIMITS (10 CFR 20)

LIQUID RADWASTE ANALYSIS - UNIT I 8-12 1-2 LIQUID RAbWASTE ANALYSIS - UNIT II 13-16 1-3 17 1-4 LIQUID RADWASTE DISCHARGE PERMIT ,

18, 19 1-Sa, D LIQUID RADNASTE DATA COMPILATION LIST OF TABLES PAGE TABLE l-la, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 20, 21 1-2a, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-BATCH ONLY 22, 23 2-la-c EFFLUENT AND WASTE DISPOSAL SEMI-l

() ANNUAL REPORT, GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES 31-33 2-2a-c EFFLUENT AND WASTE DISPOSAL SEII-ANNUAL REPORT, GASEOUS EFFLUENIS-ELEVATED RELEASE ,

34-36 2-3a-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-GROUND LEVEL RELEASES . 37-39 3-la, b EFFLUENT AND WASTE DISPOSAL SEMI- >

ANNUAL REPORT, SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 40, 41 1

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PLANT RADIOACTIVE EFFLUENT RELEASES 1 LIOUIDEFFLUENTh 1.1. REGULATORY LIMITS O 1.

The concentration of radioactive materials released in liquid wastes from all reactors at the site shall not exceed the values specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for unrestricted area. .

materials in

2. The cumulative release of radioactive liquid wastes, excluding . tritium and dissolved gases, shall not exceed 10 Ci/ reactor / calendar quarter.

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release o'f radioactive materials in

3. The cumulati,ve liquid wastes, excluding tritium and dissolved gases, shall not exceed 20 Ci/ reactor in any 12 consecutive months. .

4. During release of radioactive wastes, the effluent control monitor shall be set to alarmdischarge and to initiate valve the automatic closure of the waste prior to exceeding the limits specified in 1. above.

5. The operability of the automatic isolation valve in the be liquid radioactive waste discharge line shall demonstrated quarterly.

6. The equipment installed in the liquid radioactive' waste system shall be maintained and shall be operated to Q process radioactive, liquid wastes prior to their discharge when the projected cumulative release rate .

could . exceed 1.25 Ci/ reactor /celendar quarter, exc'luding tritium and dissolve 3 gases.

7. The maximum radioactivity to be contained in any liquid radwaste tank that can be discharged directly to the environs shall not exceed 10 Ci, excluding tritium and dissolved gases.

8. If the cumulative release of radioactive materials dissolved in liquid effluents, excluding tritium and gases, exceeds 2.5 Ci/ reactor / calendar quarter, the licensee shall make an investigation to identify the causes of such releases, define and initiate a program action to reduce such releases to the design j

of objective levels and report these actions to the Commission within 30 days from the end of the quarter during which the release occurred.

unplanned uncontrolled offsite release of

9. An or radioactive materials in liquid effluents *in excess of 0.5 Ci excluding dissolved gases shall be reported.

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1.2. MAXIMUM PERMISSIBLE CONCENTRATIONS ,

The MFC values used in determining allowable liquid radwaste release concentrations are taken from 10 CFR Part 20, Appendix B, Table II, Column 2. Release rate and dilution ratio for each batch are determined by a mixed nuclide MPC calculation performed '

O' before the release of the batch. To facilitate the measurements and calculations, the nuclides of Column 2 which can be produced i in a fission reactor have been grouped according to MPC value and I

type of radiation as shown in Figure 1-1.

The concentration of each of the 29 gamma emitting' nuclides specifically noted in Figure 1-1 is measured individually because of interest in that nuclide or because of inadequate sensitivity for the nuclide from a gross activity measurement. For any of I the 29 nuclides not detected in the gamma scan, the MDA limit is computed from the measured data for that sample.

Only two pure beta emitters, Sr-89 'and St-90, have MPC values less than 9 X 10 -6 .uci/ml. Individual measurements are made on proportional composite liquid radwaste samples to determine the Sr-89 and Sr-90 concentration or MDA value to be applied to individual batch release calculations.

Although the MPC limit for tritium is greater than 9 X 10 -6, a separate measurement is made for tritium since the gross beta technique does not provide an acceptable tritium measurement. A

, distillation and liquid scintillation counting technique is used to measure tritium concentration.

(] The maximum activity of gamma and beta emitting nuclides with MPC 4 V values greater than 9 X 10 -6 uCi/ml, except for the 29 nuclides noted above, is determined by gross gamma and gross beta measurements. Measurement sensitivity limits of approximately ?

cpm /ml allou a null measurement to show that the sum (Ci/MPCi), is less than 0.1 for gamma and beta nuclides not measured directly. -

l The sum of the ratios, E (Ci/MPCi), for alpha emitters can be i shown to be less than 0.1 by a null measurement with a sensitivity limit of approximately 1 X 10 -2 cpm /ml'. Gas flow i

counting is used to achieve the required sensitivity of measurement.

Thus, except for radionuclides produced in negligible quantities in a fission reaction (eg. I-125, I-129 etc.), the methods outlined above provide a means to assign a quantitatively l measured or MDA value to all nuclides in Column 2. These measured and calculated concentration values for each batch are us'ed to calculate the dilution ratio, release rate, and dilution rate prior to release of each batch. Both the concentration and release data are stored on a computer disc file. The disc file data is used to assure that quarterly and annual release limits are not exceeded. Bases used for the data of Table 1-1 a': e as follows:

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r . , _ , , , . . . . _ . _ _ _ _ _ . , _ - . _ _ . . , . . _ .

.n , _ _ - . . _ , m

A. Fission and activation products -

The total release values (not including tritium, gases, alpha) are comprised of the sum of the individual radionuclide activities and include the LLD concentration of all isotopes that were not measured but did not meet the minimum sensitivity limit as set forrh in the Environmental Tech Specs. This sum is for each batch O reteesed to the river for the resgeceive suereer.

of applicable limit is determined from a. mixed nuclide MFC Percent calculation. The average concentration for' each nuclide summed over all batches is divided by the corresponding individual MPC value. The sum over all nuclides of the l C1/MPCi ratios times 100 is the percent of applicable limit for effluent releases during th,e quarter.

1 B. Tritium - The measured tritium concentration in a composite '

sample is used to calculate the total release and average diluted concentration during each period. Average diluted ,

concentration divided by the MPC limit, 3 X 10 -3 uCi/ml, is converted to percent to' give the percent of applicable limit.

C. Dissolved and entrained gases - Concentrations of dissolved and entrained gases in liquid effluents are measured on each batch by Ge(Li) spectroscopy on a one liter sample from each liquid radwaste batch. Dissolved and entrained gases for which . measured or MDA concentrations are determined include noble ' gases with half lives greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; Xe-135,

> Xe-133m, Xe-133, and Kr-85 Iodine radionuclides in any form are also determined during the isotopic analysis for each batch, therefore a separate analysis for possible

-s gaseous forms is not performed because it would not provide 4

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additional information.

A conservative release limit, the maximum sensitivity limit of 4 X 10-5 uCi/ml of each dissolved and entrained radionuclide as specified in Regulatory Guide 1.21, has been applied in determining the percent of applicable limit.

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1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY.

Details of the analytical procedures for liquid radwaste analysis are con'tained in operating procedure HNP-7601. The following measurements are performed as indicated:

MEASUREMENT FREQUENCY METHOD Ge (Li) spectrometry with

l. Gamma Isotopic Each Batch on-line computer.

2. Gross Gamma Each Batch 2 X 2 NaI well cryst'al counting

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3. Gross Beta Each Batch Gas flow proportional counting 4.. Sr-89 Quarterly Chemical separation and Composite gas flow proportional 2

counting

5. Sr-90 Quarterly Chemical separation and Composite gas flow proportional counting

6. Tritium Monthly Distillation and liquid Composite scintillation counting

7. Alpha Monthly Gas flow proportional Composite counting

} Ge (Li) spectrometry with

8. Dissolved Gases Each Batch on-line computer I

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If a liquid radwaste tank cannot be reprocessed, a sample for analysis is taken from the tank after the required recirculation.

time. The sample.is used for gamma-ray spectroscopy, gross gamma and gross beta counting, and for preparation of a composite

sample.

The Ge(Li) detector consist of a 10% and two 15% efficiency, 2.8 .

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FWHM resolution detectors in 4-inch thick lead shields. A one-liter radwastic liquid sample is poured in to a Marinelli beaker in preparation for a 2000-3000 second Ge(Li) count. A peak search of the resulting gamma ray spectrum is performed by the on-line computer system. Energy and net count data for all

- ' significant peaks are determined, and quantitative reduction or MDA calculations are performed for the nuclides listed in Figure 1-1. The quantitative calculations include corrections for counting time, decay . time, sample volume, sample geometry, detector efficiency, baseline counts, and branching ratio. MDA calculations, including the above corrections, are made based on the counts in two standard deviations of the baseline count at -

the location on the spectrum where a peak f~or that nuclide would be located if present.

, 'The calculated radionuclide concentrations or MDA values from the j gamma scan and from previously stored Sr-89 and Sr-90 values are used to calculate the dilution ratio E (Ci/MPCi) and allowable release parameters. A sample printout is shown in Figures 1-2 and 1-3.

The Liquid Radwaste Discharge Permit Printout is transferred item by item to the first portion of the release permit (Figure 1-4)

O by a laboratory technician. Although the computer could printout the release permit and will inform the technician if a batch cannot be discharged as desire'd, a manual transfer of calculated results to the release permit by the technician was implemented as more likely to catch abnormal conditions in the data.

The liquid radwaste monitor setting is calculated by the computer based on the gamma activity as measured in the sample used for laboratory analysis. A coefficient has been determined which relates laboratory gamma counts to the monitor count ~ rate. If the monitor count rate exceeds the calculated setting during discharge, then the liquid passing through the monitor is not representative of the sample which wa's analyzed in the lab. A monitor reading in excess of the calculated setpoint therefore results in an automatic termination of the liquid effluent discharge. Liquid effluent discharge is also automatically terminated if the dilution ~ flow rate falls below the flow rate used in the computer calculation.

When the release permit is returned from Radwaste Operations l following discharge, the discharge data is combined with the i

analysis results on the computer disc file. The disc file may be scanned to display trends in any recorded parameter, or may be i summed for reporting purposes as shown in Figure 1-Sa and b.

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All other radionuclide concentration measurements are performed as indicated in the table given previously in this section and as detailed in the procedure HNP-7601. The dissolved gases Q calculation is performed in the Ge(Li) spectrometry system with computer data reduction using the Liquid Radwaste Library which includes gases. !

l Several comments are indicative of the success of the HNP liquid radwaste program during this reporting period:

1. The total measured activity released in liquid effluent for j both Units was 3.81 E-1 curies for the third quarter and i 2.46 E-1 curies for the fourth quarter. These values were

a pproximately 1/35 for Unit 1 and 1/105 for Unit 2 for the turd quarter and 1/56 for Unit 1 and 1/150 for Unit 2 for the fourth quarter of the allowed 10 curies per quarter per reactor.

2. The radwaste release procedure strongly emphasized reprocessing rather than discharge of liquid radwaste.

During this report period 35.58% of the liquid radwaste reaching the sample tanks was discharged; 64.42% was recycled back into both of the reactor water systems.

3. A complete isotopic scan, gross beta, and gross gamma counts and computer analysis were performed prior to the release of each of the 1148 discharge batches for both Units.

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Regulatory Guide 1.21 Tables 2A and 2B are found in this report as Table 1-la, b and 1-2a, b. Data is presented on a quarterly basis as per Regulatory Guide 1.21.

Other data pertinent to batch releases of radioactive effluent from both units is as follows:

Number of batch releases: 1148 Total time period for releases: 149,023 minutes Maximum time period for a batch release: 412 minutes Average time period for batch release: 130 minutes Minimum time period for a batch release: 5 minutes Average stream flow during periods of release of effluent into a flowing stream: 20,342 CFS O

FIGURE l-1 METHODS OF MEETING, TABLE II, COLUMN 2 MPC LIMITS O ALPHA MPC RANGE GAM >lA-RAY BETA (U Ci/ml) EMITTERS EMITTERS EMITTERS 1-131,1-132, 1-133 St-89, St-90 l (Separation &

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I-135, Cs-134 Gas Flow 9 X 10-6 (Ge(Li) Gamma-Ray Counting)

Spectroscopy) ALL Tc-99m, Ce-141, Zn-69m, (Gas Flow W-187, Zr-97, Mn-56, Counting, Cs-138, Sb-125, Rb-88, Sensitivity Cs-136, Sb-124, Ru-103, 0.01 CPM /ml)

Nb-97, Br-82, Lu-174m, St-91 Ba-La-140, Na-24,Cu-64 Tritium CO-60, Fe-59, Zn-65 9 X 10-6 Ag-110m, Mn-54, CO-58 (Distillation &

Liquid Scintil-lation Counting)

Zr-Nb-95, Cs-Ba-137 As-76, F-18, Cr-51 All Others

() Np-239, Ce-141 Mo-Tc-99, Ce-Pr-144 (Gas Flow Count-(Ge(Li) Gamma-Ray ing Sensitivity Spectroscopy) 2 CPM /ml All others (Gross Gamma-Well -

Counter; Sensitivity 5 CPM /ml)

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FIGURE 1-2 .

PROCEDURE: HHP-7601 DATA SHEET S l *,-***,***+- m u ,***u **** u **************u **

E. I. Hatch Huclear Plant *

Liquid Radwaste Analysis

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Re ac t or # 1 Batch # 544 T a.nk : CWSTB1 Rectre time: 65 minutes Comment: HIGH COND., TE, FS j 4

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t Run date: 6/20/33 0848 Count start date: 6/20/83 0035 Saaple volume: 1000.00 m1 Clock time: 3001 secs

. Cect..e t ry code: 1LHB-0 Live time: 3001 secs 6; Detector # 2 MCAN 2

Library: LRNLE2 Operator: EHU t

Energy (kev)= .07 + 1.001*Ch# + 0.000E+00*Ch#^2 + 0.000E+00*Ch#^3: 06/20/63*0010 Eff =

1/C5.130E-01

Ea(-1.6267E+00) + 300.561

Ea(9.2021E-01>3 : 06/04/83 0110 l uhere E = Energy in MeV.

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FIGURE 1-2 j (CONTINUED) j *:~~^~~ ~ 11: GY COHCENTRATION ERROP. MPC C/NPC l 1 0 4Y) (uCi/ml) (uCi/al) (uC1/ml> :

j ....-..........................................................................!

l Cs-144 133.50 <2.950E-07 1E-05 <2.95E-02 I

T:-??. 140.50 , <3.336E-03 3E-03 <1.11E-05 l l Ci-141 145.40 <6.693E-03 9E-05 <7.44E-04 I j

Mp-23? 277.90 <2.694E-07 1E-04 <2.69E-03 Cr-51 320.10 <3.745E-07 2E-03 (1.87E-04 1 1-131 364.38 4.264E-06 8.486E-08 3E-07 1.42E+01 l 2n-69a 438.70 <2.785E-OS 6E-05 (4.64E-04 i H-187 479.50 (1.206E-07 6E-05 <2.01E-03 j F-18 511.31 . <5.233E-09 5E-04 < 1. 0 5E'-0 5

I-133 52?.50 <3.190E-03 1E-06 <3.19E-02

) Ea-140 537.40 <1.51SE-07 2E-05 <7.5?E-03 i As-76 559.30 <7.098E-03 2E-05 <3.55E-03 Cs-134 605.02 3.835E-06 9.376E-08 9E-06 4.26E-01

.1 C2-137 661.83 6.569E-06 1.277E-07 2E-05 3.23E-01 l l Ne-99 739.70 <1.699E-07 4E-05 <4.25E,03 2r-97 743.50 <2.041E-OS [

} 2E-05 <1.02E-03 2r-95 756.90 <3.360E-08 6E-05 <5.60E-04 j Hb-95 765.80 <2.731E-03 1E-04 <2.73E-04 ;

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1-132 772.60 <3.747E-09 BE-06 (4.63E-04 '

Co-53 810.60 <2.637E-OS 9E-05 <2.93E-04 -

t:n-!J 634.80 <2.966E-08 1E-04 <2.97E-04 i

A;-110m 834.70 <3.502E-OS 3E-05 <1.17E-03 2n-65 ,1115.3? 9.187E-07 8.369E-03 1E-04 9.1?E-03 1-135 1260.50 <2.732E-03 4E-06 <6.S3E-03 1291.60 Fe-53 <4.136E-08 6E-05 <6.S9E-04

()

7 Co-60 1330.05 3.164E-07 3.S79E-OS 3E-05 1.05E-02 Cu-64 1345.90 7

<1.94SE-06 2E-04 <?.74E-03 -

Hi-24 1363.55 <1.969E-03 3E-05 <6.56E-04 La-140 1596.60 <1.881E-03 2E-05 <9.41E-04 1

Mn-56 LS11.00 <3.827E-09 . 1E-04 <3.83E-05 i Sr-89 (EETA) 4.040E-07 0.000E+00 3E-OS 1.35E+01 Sr-90 (BETA) <1.000E-03 1E-03 <1.00E+00 H-3 (EETA) 1.020E-03 1.000E-06 3E-03 3.40E-01 Fe-55 (LETA) <1.000E-06 BE-04 <1.25E-03 ;

P-32 ( EC ) <3.000E-07 2E-05 <1.50E-02 i

_________________ __________ , O________ _____ _________

M4 asured totals 1.036E-03 1.021E-06 2.8SE+01 LLD totsis <5.162E-06 <1.12E+00 Totals 1.041E-03 2.99E+01 DISSOLVED CASES I

M4-133 81.20 4.161E-07 4.977E-03 4E-05 1.04E-02 Kr-SS 196.10 <1.493E-08 4E-05 <3.73E-04 Xe-133n 233.13 <3.260E-07 4E-05 <S.15E-03 X4-135 24?.60 <2.165E-08 4E-05 <5.41E-04 t

_g.

1 FIGURE 1-2 (CONTINUED)

Kr-S59 305.00 <S.050E-08 4E-05 <2.01E-03 Kr-37 402.70 <1.286E-09 4E-05 <3.22E-05 Me-133 434.50 <2.125E-17 4E-05 -<5.31E-13 Me asured gas tot als 4.161E-07 4.977E-08 1.04E-02 G) LLD g as tot als (4.444E-07 <1.11E-02 2.15E-02 Tot al g as 8.604E-07 l GPOSS ACTIVITY Counter Gross B ac k ground Time Vol Het Error l Counts Counts (Min) ml Activity (cpm /ml) 1 Sigma I Hell Crystal 2245 1090 20.0 2 2.89E+01 1.44E+00 orocortional 568 160 10.0 2 2.04E+01 1.35E+00

)

ESTIMATED HASTE TAHK VOLUME = 6063.00 g al l ons ESTIrtATED ACTIVITY THIS EATCH EXCLUDING GASES: 2.38E-02 Curies ( 2.38E+04 Microcuries)

EXCLUDIllG H-3 AHD GASES: 3.74E-04 Curies ( 3.74E+02 Microcuries)

THE ACTIVITY OF THIS BATCH (EXCLUDING H-3 AND CASES) IS 374.22 uCi -

THE NAXIMUH TAHK RELEASE LIMIT IS 300 uCi LAI SUPERVISON APPROVAL HEEDED FOR THIS RELEASE RELEASE APPROVED EY: VAM

, O Licuid Raduaste Releast Summaru 1)fle as. conc., excluding H-3 and dissolved gases (uC1/ml): 1.63E-05 +- 2.07E-07

' Meas. conc., including H-3, excluding gases : 1.04E-03 +- 1.02E-06 t

4 2) Calculated LLD concentration, excluding dissolved gases .<uci/ml): 5.16E-06

3) Calculated HPC ratio (C/MPC of meas. , including gases): 2.8SE+01

4) Minimum dilution flou rate (gpm): 10000

5) Maximum tank discharge flou rate (gpm): 360 6)Specified tank flou rate (gpm): 75 7)Raduaste monitor trip setting: 2139 A = 1.63E-05 ,uct/ml B = 1800 , Monitor EG CPS C = 6481000.00 ,Monttor CPS per uCi/ml F = 2 ,Conserv. Factor 1

A includes measured ' selected','other' nuclides and gues but excludes:

Sr-89, Sr-90, H-3, Fe-55, P-32

8) Estimated conc. of mens, nuclides at point of release (uCi/ml): 7.714E-06

9) Monitor maximum to ensure 10CFR20 limits are not exceeded: 493

-- -- _ . - _ . - - - - - - -. =_ _ --- - - . . _ .

FICURE 1-2 (COMTINUED)

ESTIMATED DOSES THIS EATCH, HPEN IJorope 11.Pody Eone Live- Thyroid Kidney Lung GI-LLI Mi-133 0.00E+00 0.00E+00 0.00E+00' O.00E+00 0.00E+00 0.00E+00 0.00E*00 Ce-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E,00 0.00'+00 Tc-??u 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Kr-33 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Me-1?3m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Me-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j Hp-239 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-35m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E,00 Cr-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E 00 i I-131 1.3?E-06 1.63E-06 2.40E-06 7.68E-04 4.13E-06 0.00E+00 6.34E-07 Kr-37 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

, Xe-139 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 i Zn-69m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E*00 W-197 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 As-76 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C2-134 6.J6E-04 3.32E-04 7.89E-04 0.00E+00 2.56E-04 8.49E-05 1.3GE-05 Cs-137 6.52E-04 7.31E-04 9.96E-04 0.00E+00 3.39E-04 1.13E-04 1.93E-05 l Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 Zr-97 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E,00 I 2r-95 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E*00 Hb-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00

, I-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00

Co-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j Hn-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

) A g - 110 ra 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 i

Zn-65 4.4TE-06 3.09E-06 9.04E-06 0.00E+00 6.5SE-06 0.00E-00 6.19E-06 I-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00

Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-i0 6.09E-07 0.00E+00 2.76E-07 0.00E+00 0.00E+00 0.00E+00 5.20E-06 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E,00 l

Hi-24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E,00 L a- 14 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-39 3.21E-03 1.12E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-07

Sr-?0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 2.31E-07 0.00E+00 2.31E-07 2.31E-07 2.31E-07 2.31E-07 2.31E-07 Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4 To t al 1.31E-03 1.07E-03 1.80E-03 7 SSE-04 6.06E-04 1.98E-04 4.56E-05 Cumulative dose this YEAR (includes estiraate for this batch):

Mhole body 7.02E-01 mrem Percent of Tech Spec Liraft: 2.34E+01

'Eone 5.85E-01 mee ra Percent of Tech Spec Limit: 5.S5E+00 Lier 9.71E-01 rar e m Percent of Tech Spec Limit: 9.71E+00

! Thyroid 8.23E-02 rarem Percent of Tech Spec Limit: 8.23E-01 J Kidney 3.30E-01 mnem Percent of Tech Spec Limit: 3.32E+00 Lung 1.04E-01 meem Percent of Tech Spec Lisit: 1.04E+00

, G1-LLI 6.04E-02 meem Percent of Tech Spec Lirait: 6.04E-01 Curaul at i ve doze thiJ OV ARTER (i nc lude s est i rante f or thiJ batch):

lihole body 2.59E-01 meem Percent of Tech Spec Liait: 1.72E*01 Lone 2.2?E-01 mrem Percent of Tech Spec Lirait: 4.5SE+00 Liver 3.50E-01 mrem Percent of Tech Spec Limit: 7.16E+00 Thyroid 7. 59E-02 rarem Percent of Tech Spec Lirait: 1.52E+00

, Kidney 1.01E-01 meem Percent of Tech Spec Limit: 2.43E+00

FIGURE 1-2 ,

i Lung 3.35E-02 mrern(CONTINUED)

Percent of Tech Spec Lirait: 7.76E-01 i GI-LLI 1.70E-02 mrem Percent of Tech Spec Limit: 3.40E-01 )

i Pr oj e c t e d curaul it ive doz e this OVARTEP (inc ludes es t i mate for this b at c h) : I Uhole body 2.94E-01 mrem l q Pone 2.61E-01 mrem

(,j Liuer 4.0TE-01 na r e m Thyroid 3.64E-02 mrera Kidney 1.1SE-01 mrem Lung 4.41E-02 mrem GI-LLI 1.93E-02 mreni Cur. ul at i ve n e asured ac t i vi ty thi s YE AR (i nc l udes est i m at e for this batch):

4.913E-01 Curies, exc luding H-3 and di ssolved g ases LRil tre at ment system should be OPERABLE due to projected dose for Uhole Eody LRU treatment system has been demonstrated OPERRELE, confirnied by: BHU ERTCH4 544 DATA SUCCESSFULLY STORED SPECTRUM STORED AS: LRU2 n

( I

i.

FIGURE 1-3

} FROCEDURE: HHP-7601 DATA SHEET 8 f ** m --*** m ***,n****** m m m m m ********

i

E. I. Hatch Huclear Plant *

Liquid Radukste Analysis *

, Reactor # 2 Batch # 443 Tank: FDST2 Rectre time: 105 minutes i

j Comment: HIGH COND.,FS,TURB.

t Run date: 6/03/83 2250 Count start date: 6/03/83 2150 Sample volume: 1000.00 al Clock time: 3001 secs Geometry code: 1LHB-0 Live time: 3000 secs i Detector # 2 MCR4 2 Library: LRHLE2 Operator: EMR/F0 i

Energy (kev)= .17 + 1.000+Ch# + 0.000E+00*Ch#^2 + 0.000E+00*Ch#^3 : 06/03/83 1252 t

i Eff = 1/t1.570E-01

Ea(-2.0900E+00) + 302.816

E^<8.9041E-01)] : 06/03/S3 1252 uhere E = Energy in fleV.

l ,

ISOTOPE ENERGY C0bCENTRATION ERROR HPC C/t1FC (kev) (uCi/ml) (uCi/ml) (uCi/ml)

========================================================== =========

Ce-144 133.50 <1.641E-07 1E-05 <1.64E-02 Tc-99m 140.50 <2.026E-OS 3E-03 <6.75E-06 i Ce-141 145.40 <3.763E-08 9E-05 <4.18E-04 i Hp-239 277.90 <1.462E-07 1E-04 <2.46E-03 i Cr-51 320.10 <1.783E-07 2E-03 <8.91E-05 1-131 364.50 <2.482E-08 3E-07 <8.27E-02 2n-69m 438.70 (1.696E-08 6E-05 <2.83E-04

}

i i

l

[

, O

( U)

W-137 479.50 (6.231E-OS 6E-05 <i.05E-03 F-13 511.00 <1.937E-08 SE-04 <3.97E-05 1-133 529.50 <1.619E-09 1E-06 <1.62E-02 En-140 537.40 <6.105E-03 2E-05 <3.05E-03 As-76 559.30 <4.294E-OS 2E-05 <2.15E-03 Cs-134 604.70 6.733E-08 1.711E-03 9E-06 7.48E-03 CA-137 662.53 1.333E-07 3.431E-03 2E-05 6.94E-03 Mo-99 739.70 <1.296E-07 4E-05 <3.24E-03 Zr-97 743.50 <2.241E-OS 2E-05 <1.12E-03 Zr-95 756.90 <3.506E-OS 6E-05 <5.84E-04 Hb-95 765.30 '<1.896E-03 1E-04 <1.90E-04 1-132 772.60 <2.211E-08 8E-06 <2.76E-03 Co-58 810.60 <2.515E-OS 9E-05 <2.79E-04 Mn-54 834.80 <2.524E-08 1E-04 <2.52E-04 Ag-110m 884.70 <3.083E-08 3E-05 <1.03E-03 2n-65 1115.37 7.404E-07 9.142E-03 1E-04 7.40E-03 1-135 1260.50 (6.048E-08 4E-06 <1.51E-02 Fe-59 1291.60 <4.710E-03 6E-05 (7.85E-04 Co-60 1332.43 2.652E-07 3.460E-03 3E-05 8.84E-03 Cu-64 -

1345.90 <3.233E-06 2E-04 <1.62E-02 Ha-24 1368.55 <1.001E-OS 3E-05 <3.34E-04 La-140 1596.60 <1.728E-08 2E-05 (8.64E-04 Mn-56 1811.00 <2.653E-08 1E-04 <2.65E-04 Sr-39 (BETA) E.910E-OS 4.090E-03 3E-08 2.97E+00 Sr-90 (EETA) <1.000E-OS 1E-08 <1.00E+00 H-3 (EETA) 6.870E-04 1.000E-06 3E-03 2.29E-01 Fe-55 (EETA) <1.000E-06 8E-04 <1.25E-03 P-32 ( EC ) <2.000E-07 2E-05 <1.00E-02 Measured t ot al s 6.883E-04 1.006E-06 3.23E+00 LLD totals <!.705E-06 <1.18E+00 Tot al s 6.940E-04 4.41E+00 V DI??OLVED GASES Xe-133 80.99 <4.835E-08 4E-05 <1.21E-03 Kr-88 196.10 <4.03SE-08 4E-05 <1.01E-03 Xe-133m 233.13 <2.057E-07 4E-05 <5.14E-03 Xe-135 249.60 <1.986E-08 4E-05 <4.97E-04 Kr-55m 305.00 <1.203E-07 4E-05 <3.01E-03 Kr-37 402.70 <2.850E-08 4E-05 <7.13E-04 Xe-138 434.50 <1.321E-08 4E-05 <3.30E-04 Measured gas totals e.000E+00 0.000E+00 0.00E+00 LLD gas totals (4.763E-07 <1.19E-02 Total gas 4.763E-07 1.19E-02 GROSS ACTIVITY Counter Gross Ea.ckground Time vol Het Error Counts Counts (Min) m1 Ac t i vi t y(c pruml ) 1 Sigma Well Crys t al 1397 1159 20.0 2 5.95E+00 1.26E+00 Pecportional 194 166 10.0 2 1.40E+00 9.49E-01 ESTIMATED WASTE TAHK VOLUME = 9135.00 g al l ons

/3 ESTIMATED ACTIVITY THIS EATCH EXCLUDIHC GASES: 2.38E-02 Curies ( 2.3SE+04 Microcurnes)

EMCLUDIHC H-3 AND GASES: 4.50E-05 Curies < 4.50E+01 Microcuries)

FIGURE 1-3 (CONTINUED)

Licoid Paduute Release Summaru 1)De as . conc., excluding H-3 and dissolved gases (uct/ml): 1.30E-06 +- 1.13E-07 Ma ts. conc., including H-3, excluding gases : 6.SSE-04 +- 1.01E-06 2)C alcul kt <d LLD concentrat ion, excluding dissolved gases (uCi/n1): 5.71E-06 3)Calcul ated MPC r atio (C/MPC of me ss. , including gases): 3.23E+00

4) Minimum dilution flou rate (gpm): 10000 5', Maximum tank discharge flou rate (qpm): 4485 6)Specified tank flow ra.te (gpm): 75 7)Raduaste monitor trip setting: 416 A = 1.21E-06 ,uCi/mi B = 350 , Monitor BG CPS C = 3880000.00 ,Moniter CPS per uCi/ml F = 2 ,Conserv. Factor A includes measured ' selected','other' nuclides and gases but excludes:

Sr-89, Sr-90, H-3, Fe-55, P-32 8)Est imat ed conc. of me ts . nuclides at point of release (uCi/ml): 5.124E-06

9) Monitor m ax i mum to ensure 10CFR20 limits are not exceeded: 196 O ESTIMATED DOSES THIS BRTCH, MREM Isotope W. Body Bore Liver Thyroid Kidney Lung GI-LLI Xe-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Ce-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E*00 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Kr-33 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 4

Xe-133m 'O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 'O.00E-00 0.00E+00 Xe-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Hp-239 0.00E&OO 0.00E&OO 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Kr-85m 0.00E+00 0.00E+00 0.00E'00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Cr-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 1-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Xe-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Zn-69m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 H-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 F-13. -0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 1-130 0.00E+00 0.00E+00 0.00F.+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Ba-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 As-76 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Cs-134 1.71E-05 8.79E-06 2.09E-05 0.00E+00 6.78E-06 2.25E-06 3.66E-07 Cs-137 2.0SE-05 2.33E-05 3.17E-05 0.00E+00 1.03E-05 3.59E-06 6.16E-07 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 gs Zr-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00

(,) tib-9 5 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 I-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Co-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 l Mn-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00

Ag-110m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 l

Zn-65 5.40E-06 3.75E-06 1.19E-05 0.00E+00 7.99E-06 0.00E-00 7.52E-06 l

FIGURE 1-3 (CONTINUED) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E*00 I-135 0.00E+00 Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 Co-60 7.69E-07 0.00E+00 3.49E-07 0.00E+00 0.00E+00 0.00E-00 6.56E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 Cu-64 0.00E+00 0.00E+00 T' Hi-24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 La-140 0.00E+00

!!n-56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 1.07E-03 3.72E-07 0.00E+00 0.00E+00 0.00E+00 0.00E-00 5.93E-OS Sr-39 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 2.35E-07 0.00E+00 2.35E-07 2.35E-07 2.35E-07 2.35E-07 2.35E-07 H-3 0.00E-00 0.00E+00 Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 P-22 -_-__--- _----_-_ -_-__ _- -_-----_

Tot al 4.43E-05 3.62E-05 6.51E-05 2.35E-07 2.58E-05 6.07E-06 1.54E-05 Cumu1 st i ve dose this YEFR (includes estimate for this batch):

Percent of Tech Spec Limit: 5.65E+00 Whole body 1.70E-21 mrem Bone 1.37E-01 mrem Percent of Tech Spec Limit: 1.37E+00 Liver 2.34E-El mrem Percent of Tech Spec Limit: 2.34E+00 Thyroid -1.25E-01 mrem

Percent of Tech Spec Limit: 1.25E+00 Kidney 8.00E-E2 mrem Percent of Tech spec Limit: 8.00E-01 2.54E-E2 mrem Percent of Tech Spec Limit: 2.54E-01 Lung GI-LLI 1.11E-E2 mrem Percent of Tech Spec Limit: 1.11E-01 Cut.ulative dose this QUFRTER (includes estimate for this batch):

Percent of Tech Spec Limit: 5.75E+00 Llhole body 8.63E-E2 mrem Bone- 6.83E-E2 mrem Percent of Tech Spec Limit: 2.07E-00 Liver 1.19E-El mrem Percent of Tech Spec Limit: 2.36E+00 Thyroid 5.00E-E2 mrem Percent of Tech spec Limit: 2.00E+00 Kidney - 4.03E-E2 mrem Percent of Tech Spec Limit: 8.05E-01

() Lung GI-LLI 1.29E-C2 mrem 4.92E-C3 mrem Percent Percent of of Tech Tech Spec Spec Limit:

Limit:

2.57E-01 9.85E-02 Projected cumulative dose this OUARTER (includes estimate for th;s batch):

Whole body 1.25E-01 mrem Bone 9.87E-E2 mrem Liver 1.71E-21 mrem Thyroid 7.22E-E2 mrem Kidney 5.82E-E2 mrem Lung 1.86E-02 mrem GI-LLI 7.11E-03 mrem Cumul at ive measured ac t ivity this YEAR (inc ludes est imate for th: s batch):

1.182E-01 Curies, excluding H-3 and dissolved gases t

l BATCH 2 448 DATA SUCCESEFULLY STORED l SPECTRUM STORED AS: LRW2 l

l l

[\

V x

. s l

. FIGURE'1-4 DATCH NO.______ -

! El^f.!!_Cziz_U/.*l.QU L10UID Rt.DWAS,T,C_OJ,0Ctif/JEC PCRM_ll UNIT # ._______

Tate < TO DE RELEAOCD _________ . _ _ _____

DATE _

i O HEACOtt FCG ICCCSO!1Y CF DISCHARCE RECIRC. STA9T TI?C _ S.*N LE TIRE HECIRC. DURATION __ MIt#JTES I. LA904ATORY ANALYSIS (I) MEASt. TIED RADICitJCLIDE CONCENTRATICt1 .E + .E UCi/ne!

(2) CALCULATED LLO LIMIT CONCENTRATIOras ,,___ uC i / n.1 (3) CALCULATED MFC RATIO: 2 (Ci/IPCi) -

. (4) MIt4IMt.m1 DILUTIOtJ FLOW RATE CPR1 (5) MAX. CALCULATED TANL( DISCHARGE RATE: J, GEE SEC F.5 3)__,_ __ CPM (G) SPECIFIED TAN'( DISCHARGE RATE: 6(5)/2 CPM

CPG -

(7) RADtMSTE MONITOR TRIP SETTINC*

A = Ce(Li)(1) uCi/ml B = MONITOR BG _ CPS j C = MONITCR CPS F = CONSERVATIVE PER Ce(Li) uCi/ml _

FACTOR g iD4ITOR ALARM SETPDINT (CPS) = (C X A Y. F) t'B + 3 h DATC l COMPLETED BY CO.POSITE LITER STORED (INITIALS) LAS FORE

At4 AoFf:GvED -

(B) RADWASlE IC11TCR MAX. CPS TO BE WITHIN 10 CFR EO LIMITS:

CXAX (6)+(4)

II. CPERATIC?f3 (6) (3) eps

' ~

O INIT.

(9) LIGUID RADWASTE MONITCR TRIP SET AT: CPS (10) CCNFIRMED DILUTIC:4 FLOW RATE _

CPM l' _ _ _ _

(11) VALVE LItEUP CIECKED AS PER HNP-TANK DIS. INTEGRATOR DIS. RATE DIL. TOTAL RIVER EL. MONITOR

_ ,_D AT_q,,, ,T,,J R I.EWL -T _ RONG. CPM CAL FT. CPS 1

GTART __

QO .__-- .__.__.__..__.~._.. _ _ _ . . .

COMPLETED BY '~ DATE MIN. CAL.

OtflATION TOTAL .

RELEASE ,

e 10 MIN AFTER START ,

- AFTER FLtGHING a

III.L/GORATCRY (IC) TOTAL TeMC VOLUME DISCHMRCED (CAL. X 3,7851 ml 3 (13) TOTAL ACTIVITY DISCHeRCED !(1) X'(12 . uCi (14) RIVER FLCN RATE (FRCM FSAR 2.4-6) CFS O CCMPLETED DY DATE 4

                                                                                    's 7.__     _.._ .. _ .__ __... __.                            q
                                                                -17 __ _

Ltquid FtS tJt4 Dit a n for Feg. Guide 1.21 Report E. 1. Hat ch Huc l e nr Pl snt Ull! T 1 Total Activity (Curies) Qutrt<r 1, 1993 Quarter 2, 1983 li*chts 1 thru 349 Estches 350 thru 580 O. H in t Mtisor4d Error High LLDs Tots 1 Meksured Error High LLD1 Total Ci-144 5.87E-04 7.S?E-05 0.00E+00 5.87E-04 2.1SE-04 5.34E-05 1.09E-05 2.29E-04 T c -9 ? r. 1.01E-04 2.??I-06

1.01E-04 3.69E-04 5.00E-06
3.69E-04 Ct-141 5.20E-0$ 1.07E-06 0.00E+00 5.20E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00

                   .Np-239           4.2$E-05 S.44E-06

4.2SE-05 0.00E+00 0.00E+00
0.00E+00 Cr-51 6.?0E-04 4.42E-05
6.80E-04 5.19E-04 2.91E-05
5.19E-04 1-131 9.'55E-04 1.26E-05 0.00E+00 9.55E-04 1.71E-02 3.59E-05 0.00E+00 1.71E-02 2n-6?n O'00E+00

                                        .         0.00E+00

0.00E+00 0.00E+00 0.00E+00
0.00E+00 W-187 0.00E+00 0.00E+00
0.00E+00 0.00E+00 0.00E+00 * .0.00E+00 F-13 6.33E-04 9.05E-06
6.33E-04 1.32E-03 1.3SE-05
1.32E-03 ,

a I-133 9.76E-04 4.35E-05

9.76E-04 2.60E-03 1.67E-05
2.60E-03 F1-140 2.76E-05 7.14E-06
2.76E-05 0.00E+00 0.00Ev00
0.00E+00

;                     Rs-7i           0.00E+00    0.00E+00            +         0.00E+00 1.16E-04 9.21E-06

1.16E-04 CJ-134 4.2?E-02 6.24E-05 0.00E+00 4.27E-02 3.26E-02 4.70E-05 0.00E+00 3.26E-02 Cs-117 6.78E-02 S.04E-05 0.00E+00 6.78E-02 5.54E-02 6.42E-05 0.00E+00 5.54E-02 Mc-i? 2.40E-04 5.10E-05 0.00E+00 2.40E-04 2.25E-04 2.33E-05 0.00E+00 2.25E-04

. ~r-97 0.20E+00 0.00Et00

0.00E+00 0.00Ev00 0.00E+00
0.00E+00

Zr-95 1202E-03 2.75E-05

1.02E-03 1.76E-04 9.19E-06
1.76E*04 Hb-35 3.2iE-03 2.81E-05
3.26E-03 3.37E-04 7.32E-06
3.37E-04

             -         I-120-         Z.?0E-06 6.79E-07

2.90E-06 2.05E-06 3.60E-07
2.05E-06 Co-!? '1'.5:-E-03 2.iOE-05 0.00E+00 1.89E-03 4.73E-04 8.52E-06 0.00E+00 4.70E-04 Mn-54 1.2SE-02 4.83E-05 0.00E+00 1.2SE-02 2.03E-03 1.77E-05 0.00E+00 2.03E-03 Eg-110a 9.'4E-05 7.42E-06
9.74E-05 7.26E-06 1.17E-06
7.26E-06

                    '2n-65             6.7BE-02 1.45E-04 0.00E+00 6.73E-02 2.37E-02 7.34E-05 0.00E+00 2.37E-02 1-13!           1.62E-04 S.262-06

1.62E-04 4.02E-04 1.18E-05 + 4.02E-04 a

F1-59 2.2?E-03 3.46E-05 0.00E*00 2.29E-03 1.45E-04 6.23E-06 0.00E+00 1.45E-04 Co-60 3.43E-02 7.42E-05 0.00E+00 3.43E-02 9.03E-03 3.30E-05 0.00E+00 9.03E-03 Cu-64 9.22E-04 2.00E-04

9.22E-04 5.23E-03 3.93E-04
5.23E-03 Ha-24 2.4fE-03 1.67E-05
2.46E-03 9.3SE-04 1.03E-05
9.3SE-04 4

Ls-140 7.44E-05 3.43E-06

7.44E-05 1.96E-04 5.27E-06
1.96E-04

, Mn-56 0.00E+00 0.00E+00

0.00E+0'O 0.00E+00 0.00E+00 ,
0.00E+00

i. Cz-13S 2.35E-04 5.64E-06

P.35E-04 7.46E-06 S.37E-07
7.46E-06 Sb-125 6.78E-04 2.10E-05
6.70E-04 1.07E-04 7.32E-06
1.07E-04 Rb-S3 1.SiE-04 1.25E-05
1.s E-04 3.71E-06 7.61E-07
3.71E-06 C4-136 1.SSE-05 3.47E-06
1.SSE-05 1.07E-03 1.30E-05
1.07E-03 Sb-124 1.SSE-04 1.55E-05
1.SSE-04 0.00E+00 0.00E+00
0.00E+00 RU-103 2.31E-04 S.S?E-06
2.31E-04 0.00E+00 0.00E+00 + 0.00E+00 Hb-?7 4.23E-07 6.4SE-07
4.23E-07 0.00E+00 0.00E+00
0.00E+00 Er-32 3.1?E-05 2.03E-06
3.19E-05 0.00E+00 0.00E+00
0.00E+00 LU- 174 ra 0.00E+00 0.00E+00
0.00E+00 5.63E-05 1.17E-05
5.63E-05 Sr-91 0.00E+00 0.00E+00
0.00E+00 3.13E-05 4.64E-06
3.13E-05 Sr-S? 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.44E-04 6.44E-04 Sr-?O 1.54E-04 S.99E-05 0.00E+00 1.54E-04 4.94E-04 4.12E-04 0.00E+00 4.94E-04 F4-55 4.20E-02'6.00E-03 0.00E+09 4.20E-02 2.39E-02 4.18E-03 0.00E+00 2.39E-02 P-32' 6.00E-04 2.10E-04 0.00E+00 6.00E-04 0.00E+00 0.00E+00 4.3SE-03 4.38E-03 To t T !'2 2.36E-01 6.01E-03 0.00E+00 2.86E-01 1.7?E-01 4.22E-03 5.03E-03 1.84E-01 Me-123 2.40E-03 2.55E-05 0.00E+00 2.49E-03 4.5SE-03 1.27E-04 0.00E+00 4.53E-03 Kr-il 0.00E+00.0.00E+00 0.00E+00 0.0CE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M4-1?in 0.00E+00 0.00E+00,0,00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M4-125 3.22E-03 1.6?E-05 0.00E+00 3.22E-03 2.40E-03 1.31E-05 0.00E+00 2.40E-03 Kr-SSM 1.15E-05 5.43E-06 0.00E+00 1.1_5E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mc-S' O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-111 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1

                   . Tet d s          !.i:E-Oi 3.10E-05 0.00E+00 5.63E-0? 6.??E-02 1.27E-04 0.00E+00 6.98E-03 l                    a       Mc '_L*. e 4 u i re ra nt i r. T4:h :pic-

_ , - ,5 _ _ _ _ _ , _ , ,__

       -g                          L er : 7:3 . > .i t < 7 ,t a            ion for Re ;. Guide 1.21 Report.

E. I. Hit.:h !!u:li te Plant UtlIT 2 Tot al Retivity (Curies) O u p" < r 1, 1953 . Quarter 2, 1983 nch42 1 thru 274 Bat c hes 275 thru 568 ti .t P : u uri d Er'ce r Ht;h LLD5 Totsi tieazured Error High LLDs Total Cs-144 . 03E-04 3.10E-05 0.00E+00 2.03E-04 7.15E-05 3.42E-05 0.00E+00 7.15E-05 T:-9?e 3.35E-04 4.87E-06

3.35E-04 2.62E-04 5.15E-06
2.62E-04 Cs-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.43E-06 2.12E-06 0.00E+00 6.40E-06 Hp-2?? 0.00E*00 0.00E+00
0.00E+00 0.00E+00 0.00E+00
0.00E+00 Cr-51 6.60E-04 2.96E-05
6.60E-04 1.1?E-04.1.42E-05
1.1SE-04 I-131 -1.12E-02 2.41E-05 0.00E+00 1.12E-02 8.15E-03'2.17E-05 0.00E+00 S.15E-03 2n-69m 1.78E-06 4.84E-07
1.78E-06 0.00E+00 0.00E+00 : 0.00E+00 W-187 0.00E+00 0.00E+00
0.00E+00 0.00E+00 0.00E+00 *
0.00E+00 F-13 1.14E-03 1.09E-05
1.14E-03 2.07E-05 2.33E-06
2.07E-05 I-133 3.53E-03 1.47E-05
3.53E-03 5.66E-05 2.84E-06
5.66E-05 Ba-140 0.00E+00 0.00E+00
0.00E+00 0.00E+00 0.00E+00
0.00E+00 3 AI-76 9.55E-06 1.44E-06
9.55E-06 0.00E400 0.00E+00
0.00E+00 '

          ,     C2 *24         6.74E-03 2.27E-05 0.00E+00 6.74E-03 1.39E-02 2.82E-05 0.00E+00 1.39E-02 C2-117         1.21E-02 3.04E-05 0.00E+00 1.21E-02 2.07E-02 3.66E-05 0.00E+00 2.07E-02 le-? ?        4.36E-05 9.23E-06 0.00E+00 4.36E-05 1. 67E- 0 4 1.94E-05 0.00E+00 1.67E-04
                '/-97          2.52E-06 6.83E-07

2.52E-06 0.00E+00 0.00E+00
0.00E+00 Zr - :- 5 1r32E-05 2.95E-06
1.33E-05 1.27E-05 3.02E-06
1.27E-05 lib -95 5932E-05 3.34E-06
5.322-05 6.56E-05 3.30E-06
6.56E-05 l-131 3.70E-05 2.39E-06
8.70E-05 0.00E+00 0.00E+00
0.00E+00 Co-!! 1.0~E-04 3.91E-06 0.00E+00 1.07E-04 4.24E-04 6.96E-06 0.00E+00 4.14E-04 Mn-54 7.67E-04 1.12E-05 0.00E+00 7.67E-04 1.05E-03 1.07E-05 0.00E+00 1.05E-03 A ;- 110:.. 9.,4 4 E -0 6 1.50E-06
9.44E-06 1.04E-04 5.06E-06
1.04E-04'

              .Zn-55           6.66E-03 4.26E-05 0.00E+00 6.66E-03 1.10E-02 4.86E-05 0.00E+00 1.10E-02 4.77E-04 1.05E-05

()- I-!?!

4.77E-04 2.51E-06 7.19E-07
2.51E-06 F4-59 4.95E-06 1.02E-06 0.00E+00 4.95E-06 4.692-05 3.86E-06 0.00E+00 4.69E-05 Cc-60 3.47E-03 2.22E-05 0.00E+00 3.47E-03 4.13E-03 2.07E-05 0.00E+00 4.13E-03 Cu-64 3.77E-03 3.2SE-04
3.77E-03 7.6SE-04 1.32E-04
7.6SE-04, Ha-24 1.25E-03 9.93E-06
1.25E-03 1.97E-06 7.57E-07
1.97E-06 La-140 7.98E-07 2.54E-07
7.98E-(7 4.15E-05 2.59E-06
4.15E-05 Mn-56 0.00E+00 0.00E+00
0.00E+n0 0.00E+00 0.00E+00 + 0.00E+00 Cs-138 1.54E-04 3.55E-06
1.54E-04 1.47E-05 1.60E-06
1.47E-05 Rb-SS 9.7CE-05 3.64E-06
9.70E- 35 4. 98E-06 9. 07E-07
4.98E-06 Cs-136 2.15E-04 4.96E-06
2.15E-04 6.15E-04 8.31E-06
6.15E-04 l Sb-125 2.00E-05 2.33E-06'
2.00E-05 0.00E+00 0.00E+00
0.00E+00 Sr-?2 0.00E+00 0.00E+00
0.00E+00 2.02E-03 5.7SE-09
2.02E-06 Eu-155 0.00E+00 0.00E+00
0.00E+00 1.12E-05 2.36E-06
1.12E-05 Ag-112 0.00E+00 0.00E+00
0.00E+00 5.47E-06 3.76E-07
5.47E-06.

Ho-166 0.00E+00 0.00E+00

0.00E+00 1.76E-04 5.40E-05
1.76E-04 tib-90 0.00Et00 0.00E+00
0.00E+00 6.62E-06 9.50E-07
6.62E-06 Sr-39 0.00E+00 0.00E+00 f.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 OiO0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-55 4.17E-02 5.21E-03 0.00E+00 4.17E-02 4.91E-03 1.97E-03 0.00E+00 4.91E-03 P-32 0.00E*00 0.00E600 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Tot al s 9.4SE-02-5.22E-03 0.00E+00 9.4SE-02 6.6SE-02 1.97E-03 0.00E+00 6.6SE-02 I

Me-!?3 1.1'E-02 5 4.93E-05 0.00E+00 1.15E-02 1.?2E-02 3.98E503 0.00E+00 1.92E-02 ( Kr-SS 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0,0E+00 0.00E+00O.00E+00 0.00E+00 < Ms-133:1 3.64E-06 6.39E-06 0.00E+00 3.64E-05 2.00E-04~1.95E-05 0.00E+00 2.00E-04 ! Me-135 1.07E-01 2.02E-05 0.00E400 1.07E-02 1.30E 204 3.22E-06 0. 00E+00 1.30E-04 Fr-15:1 3.57E-O'? 2.10E-06 0.00E+00 3.57E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 A) (, 1:r-87 5. 73E-O ' 1.52E-07 0.00E+00 5.730-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M4-1?S 0.00E+0J 0.00E+00 0.00E+00 0.00E+00 0.00E+00 e.00E+00 0.00E+00 0.00E+00 X+-135f t 3.13E-O' 4.6EE-08 0.00E+00 3.t3E-07 0.00E+00 0.00E+00 0.00E400 0.00E+00 MS- 21 . 0.00E-04 0.00E,+00 0.00E+00 0.00Et00 1.39E-03S.95E-050.00E+0g'1.89E-03 Totala 2.22E-02 5.37E20S 0.00E+00 2.22'E-02 2.14E-02 9.9*E-05=0.00E+00 0.14E-02 e 4 "t;e L*,7 . . q c d .-4 :.< n t i n s Te ch Spe c I /

i

               ~-                                                                                                   _

TABLE 1-la x E. 1. H at c h th.: 14 ar Plane UllI T 1 . } E.~Fi '.'E::T AllL 1: A1 TE L ' iF0NL SEI1! A*::tV AL F:EF CF.T 1953 L I'.~ U I D EFFLUE!lTS-$UilP. AT I 0tt OF ALL F E L Ei> 5 E ? Unit Outrter Quarter. Est TorEl *

                                            ,                                                                                              1             2       E r'r o r   .

6. Ft22 ion

Ac.ivition products

1. To* si retta24 (not including H3, c u a s . sl ob s)

Ci 2.86E-01 1.79E-01 4.76E+01

2. A *4 r 19 4 diluted concentrition .

                              > c_ oeried                                              uC i / nil                                       1.12E-07     9.94E-00 5       Fi      en- o v' sc e l t e tt.1 + l i rri t t              l 5.93E-01) 3.80E+00l
             .    ,: r i , i u::.

I 1. ~; 1. 't !i u s i Ci 2.34E-011 2.55E+01' 3.21E-011

2. A - t r :r; < dilut<< concentration c .. ' tt v: ciried uC i / n.1 9.14E-06 1.42E-05 i ?. ;<rc+nt of toolic1514 1 i t.i i t l % 3.05E-01 i 4.73E-01

 ^          C. Dissolvid And entrhined gazes Iv)

1. Tot il r414ase Ci 5.63E-03) 6.9SE-03 1.0!E-021

2. Aut r age dilutid conce ntrat ion du'-ino niriod uCi/ml 2.20E-09 3.8?E-09

3. P4 ' c + n *. or neolicable l i rii t i % l 5.50E-03i : 9.71E-03 l D. Gr:.22 alpha radioactivitaj l 1. T 3

11 r + 14 aI + l Ci 1 5.OSE-046 6.80E-05l 1.20E+02l lE. vc l u n e o v' uute ( p r' i o r- to dilution >l l i t e r's l 1.2SE+071 7.49E+06l 1.00E*011 lF. Volune o r'. d t l u t i o n i.i it e r' used i 1iters l 2.55E+09l 1.79E+09l 1.60E*02)

O t,-) 1

i I TABLE 1-lb ;

O i 1 4

E. ! . H atch fluc 1 e ar Pl ant UllIT 2 i EFFLUE!!T Att011ASTE DISPOSAL SEftI6tiffURL REPORT 1933

, LI6UID E~FLUEtlTS-SUttt1ATI0li 0F ALL F.ELEASES i 1

                                                                                                   )         Unit       j         Ouarter                 Quarter            Est Tot al j

l 1 2 Error '4 f { Ft . F i 2 21 , n *., activstion products

I l 1. Tot si release (not including H3, 6.CSE-02 4.95E+01 j cszes. alpha) Ci 9.4SE-02

! 2. Averigt diluted concentratton during period uCi/mi 4.90E-03 3.05E-03 i 'I 2.20E*00 1.37E+00

3. Percent of acolicable Itmit l

S. Trittun l Ct I 7.19E+00l 1.03E+01' 3.21E+011 l l 1. Totsi release j 1 2. A'>erEge dilu'id concentration durice period uCi/mi 3.71E-06 4.69E-06 i

3. Fercent of anolichole limt?

i

                                                                                                                  %                   1.24E-01               1.56E-01l           .

C. Dissolved and entrained gases l i 1. Tot ti release Ci l 2.22E-02l 2.14E-021 1.00E+02!

2. nue r a';e di l ut e o conc e nt rat i on i e *f m etriod uCi/ml 1.15E-OS 9.75E-09

3. Parc4nt of acoltchole Iimit % l 2.87E-02 I 2.44E-02)

Gross al pha radioac t ivi ty D, ] l 1. Totti re14 E2 e ! Ci l 6.80E-05) 5.22E-0"l 1.20E+026 1 l i lE. Voluue of ukste (prior to dilution >l Itters l 7.62E+06l S.99E+06l 1.00E+011 j lF. Volor e of dilution water used i l i t e r s- l 1.93E+09l 2.1SE+09l 1.60E+02l l, . I l -- - - . _ - . . , _ . . _ , . . - ,, . _ , _ __

                                                                                              ,,-21 ,.                        _ _ , _

TABLE 1-2a E. 1. Hatch tiuct.:ir P1 ant UMIT 1 EFFLUIM7 6'ID ilALTE DI?PG36L SEMIAllHUAL REPORT 1983 LIQUID EFFLUEllTS CONTINUOUS fl0DE BATCH t:0D" Huc l i .:< j F.414 12 4 d Unit Guarter Qu ar t e r Quarter Quarter ' 1 2 1 2 C4-144 Ci Tc-95: Ci 5.87E-04 2.18E-04l CI-141 1.01E-04 3.69E-044 Ci - 5.20E-06 0.00E+001 Mp-239 Ci 4.28E-05 0.00E+00 Cc-51 Ci

                                 !-131 6.80E-041 5.19E-04 Ci                                            9.55E-041 1.71E-02) 2r.-694                                 Ci
                                .1 - 1 ? 7 0.00E+001 0.00E+00l Ct                    l                       0.00E+004 0.00E+001
                                ~-!?                                    Ci 1-133 l                       6.3?E-04l 1.?2E-031 Ci    l l                       9.76E-041 2.iOE-031 En-140                                 Ci AI-76                                                                                 2.76E-051 0.00E+001 Ci                                            0.00E+001 1.16E-041 l                      C J -1: .                               Ci l 4.27E-02l 3.26E-026 l

I C3-137 i Ci l l H 6.76E-02 5.54E-021 I Mc-hb I Ct l l 2.40E-04 2.25E-041 6 2r-97 2*-?5 i Ci l 0.00E+00r 0.00E+001 i Ci l '1.02E-03l 1.76E-04l iio-:5 i Ci l l 3.26E-031 3.37E-04l 1-112 Ct i

                              ' C :-5 5 l                                i                   1 2.90E-06l 2.05E-061 i         Ci    '

1.89E-031 4.73E-041 ik. - 5 4 i Ci 6:-1100 i 1.2SE-02l 2.03E-03l_ C1 9.74E-05! 7.26E-061 1 ~n-?5 Ci l 1-135 6.76E-02l 2.37E-021 Ci 1.62E-041 4.02E-041 1 F4-59 Ci Co-60 2.29E-031 1.45E-046 Ci 3.4?E-021 9.03E-03t Cu-64 Ci 9.22E-04 l 5.23E-031 Ha-24 Ci 2.46E-03 9.3SE-041 La-140 Ci 7.44E-05 1.96E-04l (In-56 Ci 0.00E+00 0.00E+001 Cs-133 Ci 2.35E-04 7.46E-061 1 56-125 Ci 6.78E-04 1.07E-041 Rb-SS C1 1.36E-04 3.71E-06i Cs-136 Ci 1.88E-05 1.07E-031 Sb-124 Ci 1.8SE-04 0.00E+001 RU-103 Ci n 2.31E-04 0.00E+001 No-97 C1 4.23E-07' O.00E+001 Fr-82 Ci 3.19E-05 0.00E+00f LU-174a Ci 0.00E+00 5.63E Sr-?1 Ci 0.00E+00 3.13E-05' i Sr-89 Ci 0.00E+00 0.00E+00 dr-90 l Ci 1.54E-04 4.94E-04

                             *Fe-55                                     Ci                                            4.20E-02 2.39E-02    t P-32                                    Ci                                            6.00E-04 0.00E+00 l             Tot si for period (aboue)                          Ci l              l                 l                   l 2.86E-01l 1.79E-01l "4-133                                  Ci                                            2.40E-03   4.58E-031 Kr-SE                                   Ci                                            0.00E+00   0.00E+00!
     )                          X+-133M                                 Ci                                            0.00E+00   0.00E+001
    /                           "<-135                                  C1                                            3.22E-03   2.40E-034 Kr-85H                                  Ci                                            1.15E-05 Kr-87 0.00E+001 Ci                                            O.00E+00   0.00E+001 Xe-138                                  Ci                                            0.00E+00   0.00E+001
                                                                               - , - ,                                 - -        3 --9          y    y e   - , - .  #=,w+-m   r---                 .,p   -   w c-

E. 1. H at c h fluc l e ar P l ant UllIT 2 EFFLUEHT A;lD !!ASTE DISF03AL SEMIntitlVAL REPORT 1983 Y LIQUID EFFLUEtlTS C0tiTINUGU3 MOLE EATCH MODE liuc l i d a J Rele12ed Unit Quarter Quarter Quarter Quarter 1 2 1 2 Ce-144 Ci 2.03E-04 7.15E-05 T c - 9 9 r.. Ci 3.35E-04 2.62E-04 C4-141 Ci 0.00E+00 6.43E-06 No-239 Ci 0.00E+00 ' O.00E+00 Cc-51 Ci 6.60E-04 1.1SE-04 I-131 Ci , 1.12E-02 3.15E-03 2n-69a Ci 1.78E-06 0.00E+00 11-187 Ci 0.00E+00 0.00E+00 F-13 Ci 1.14E-03 2.07E-05 I-133 Ct 3.53E-03 5.66E-05 B1-140 Ci 0.00E+00 0.00E+00 As-76 Ci 9.55E-06 t,0._00E+00 1 Ci-134 l Ci l l 6.74E-03 1.39E-02 i CJ-137 i C1 1 1.21E-02 2.07E-02 , r10 - ? ? 6 Ci ) 4.36E-05 1.67E-041 2r-E7 1 Ci I l 2.52E-06: 0.00E+001 2r-95 l Ci l l 1.33E-051 1.27E-05 l f.e- 9 5 Ci i 1 5.32E-051 6.56E-05 I . I-13I i Ct i 8.70E-051 0.00E*00 i Cc-59 I ci I ' 1.07E-04' 4.14E-04 I iln-54 i Ct i 7.67E-04 1.05E-03 l ia-110n 1 Ci l 9.44E-061 1.04E-04 2n-65 i Ct i 6.66E-031 1.10E-02 I-135 i Ci l 4.77E-04' 2.51E-06 i F+-59 ' Ci i 4.95E-06 1 4.69E-05 Co-60 Ci 3.47E-031 4.1?E-03 Cu-64 Ci 3.77E-03 7.66E-04 ilt-24 C1 1.25E-03 1.97E-06 Li-140 Ci 7.95E-07 4.15E-05 Hn-56 i Ci 1 0.00E+00 0.00E+00 C3-133 Ci 1.54E-04 1.47E-05 Rb-33 Ci 9.70E-05 4.98E-06 Cs-136 Ci 2.15E-04 6.15E-04 Sb-125 Ci 2.00E-05 0.00E+00 Sr-92 Ci 0.00E+00 2.02E-0$l Eu-155 i Ci l 0.00E+00; 1.12E-05 Ac-112 i C1 1 0.00E+001 5.47E-06 Ho-166 I Ci 1 0.00E+001 1.76E-04 tic-90 1 Ci 0.00E+001 6.6.2E-06 Br-69 i Ci 0.00E+001 0.00E+00' Sr-?O I Ci 1 0.00E+001 0.00E+00 Fe-55 i Ci 4.17E-021 4.91E-03 . F-32 l Ci 0.00E+006 0.00E+00 1 l Tot Al for period (amooe) i Ci l l l 9.4SE-02l 6.6?E-02) M4-133 Ci l 1.15E-021 1.92E-02 Vr-83 Ct 0.00E+00 0.00E+00 M4-133tt Ci 3.64E-05 2.00E-04 Ne-135 Ci 1.07E-02 . 1.30E-04 Kr-85H I Ci 3.57E-06 0.00E+00 Kr-37 i Ci 5.73E-07 h 0.00E+00 Xe-138 Ci 0.00E+001 0.00E+00 Me-135M Ci 3.13E-07 0.00E+00 X e - 131 t.: 1 Ci 0.00E+00 1.89E-03 ll

2 GASEOUS EFFLUENTS . 2.1. REGULATORY LIMITS

a. (1) The release rate limit of ncble gases frcs the site

                     -                 shall be:                                                                             -

O - - - - - E Qis .l.9 E6+ 1.0 EB- +Qv i ,11 E6 + 44 EB - I1 i +n where Q 3 = Total release rate f rom main stack for both Units in Ci/sec (elevated release) Oy = Total release rate from vent in Ci/sec (ground release) i= The individual nuclide n = total nuclides E6 = The average gamma energy per disintegration 5 3= The average beta energy per disintegration (2) The release rate limit of all radiciodines and

                                    - radioactive materials in particulate form with half lives greater than eight days, released from the site to the environs as part of the gaseous wastes, shall be.

1.0 X 105 Ops + 1.5 X 10 6 gpy g 1 . Where Op s = Total release rate from the main stack elevated for both Units in Ci/sec (as release) O from vents for both Units Oyp

                                                   =        Total release rate in Ci/sec (ground releases)

b. (1) The average release rate of noble gases from the site during any calendar quarter shall be:

_ _7 I Qi3 12 E 6 + 3.0 EBj] + O iv - 66 E6 + 140 E B, I1 1 +n (2) The average release rate of noble gases du' ring any 12 consecutive months shall be:

                                         -                                                     F         _                 -
                                                        + 6.1    E       q I       Qis           _

24 E6 B! +Ov i 130 E 6+ 270 B I1 E ]J i +n 1 I average release rate of- all radio iodines and (3) The radioactive materials in particulate fofm from the site during any with half lives greater than eight days . calendar quarter shall be: 1.3 X 106 Ops + 1.9 X 10 7 Opv $ 1 - rate of all radio iodines and (4) The average release radioactive materials in particulate form from the site l C I e

with half lives greater than eight days during any period'of 12 consecutive months shall be: , l

                                                                                                 .                       I 2.6 X 106       Ops + 3.7 x 10 7               Opv <1 (5)        The amount of Iodine - 131 released during any calendar O                         quarter shall not exceed 2 Ci/ reactor.

(6) The amount of Iodine - 131 released during any period of 12 consecutive months shall not exceed 4 Ci/ reactor.

c. Should the conditions of 2.1.3c (1), (2), or (3) listed below occur, the licensee shall make an investigation to identify the causes of the release rates, define and initiate a program of action to reduce the release rates to design objective levels listed in subsection 2.1 of the HNP-ETS and report these actions to the Commission within 30 days from the end of the quarter during which the releases occurred in accordance with 'section 5.7.2.

(1) If the average release rate of noble gases during any calendar quarter is: I Qg ,4 7 E 6 + 12 Eg +Qv 60 E 6 + 540 EB, >1 i i i+n (2) If the average release rate from the site of all radio iodines and radioactive materials in particulate form with half lives greater than eight days during any calendar quarter is: 5.0 X 106 Ops + 7.2 X.,102 Opv >1 , (3) If the amount of Iodine - 131 released during any calendar quarter is greater than 0.5 Ci/ reactor.

d. The pos t-tr ea tment offgas monitors sfiall be operating and set to alarm and to initiate the automatic closure of the waste gas discharge valve prior to exceeding the limits specified in Section 2.1.3a above. The operability of the automatic isolation valve shall be demonstrated quarterly.

e. If the post-treatment offgas monitor s not operating, a shutdown shall be initiated so that - the reactor will be in the hot shutdown condition within 10 hours.

f. If the release rate 'of noble gases measured at the pretreatment monitor exceeds 260,000 uci/sec for a period greater than 48 hours, notify the Commission in writing within 10 days, identifying the causes of activi ty .and in accordance with section 5.7.2. ,

g. The reactor containment for each Unit shall be purged through the standby gas treatment system for that Unit.

O _

                                                       -2 5 -

h. (1) Potentially - explosive gas mixtures of hydrogen and oxygen contained in the offgas system downstream of the

                    . recombiners       shall be continuously monitored during                      l reactor     power operation for hydrogen concentration.                       j q                      The hydrogen gas monitoring system shall provide alarms                       '

U locally and in the control room at a set point of 4% hydrogen concentration ,by volume. At least one continuous gas monitoring system and its associated : alarm system shall be operable during reactor power operation. If both of the hydrogen gas monitors or both of the associated alarm systems are inoperable, reactor operation may be continued for a period of time not to exceed 2 weeks, provided that either (a) grab samples are taken and analyzed for hydrogen concentration once every 4 hours, or (b) using .a

temporary hydrogen gas analyzer installed in the~offgas system line downstream of the recombiner, hydrogen concentration readings are taken and logged every 4 hours.

(2) The hydrogen concentration in the offgas system downstream of the recombiners shall not exceed 4% concentration by volume. If at any time during reactor power operation, it is determined that the hydrogen concentration limit is being exceeded, action shall be initiated within 4 hours to return the hydrogen concentration to within the prescribed limit. If the hydrogen concentration is not reduced to less than 4% by volume within 24 hours, the offgas system flow shall p be stopped. G (3) The installed hydrogen monitoring systems shall have daily sensor checks, monthly functional checks, tnd quarterly calibrations. The portable hydrogen gas analyzer shall be , calibrated immediately prior to installation and shall be subject to daily sensor checks, monthly functional checks, and quarterly calibrations until removed from service.

i. An unplanned or uncontrolled offsite release of radioactive materials in gaseous effluents in excess of 150 Ci. of noble gas or 0.02 Ci. of radioiodines in gaseous form shall be reported to the NRC within 30 days in accordance with

    .            section 5.7.2.

2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY i

          . Waste gas release at Hatch is confined to four paths.                       Each of these      four   paths       is   continuously      monitored         for   gaseous concentration and each has an integrating type collection device which concentrates particulates 'and iodine for each seven day period (Procedures are such that shorter collection times are used where applicable to Technical Specification requirements).

Each of these continuous samplers has a flow controller which maintains sample flow within about a 10 percent range over each seven day collection period. The offgas vent (ele'va ted release) and the reactor building vents have flow measurement devices which h continously record the flow rate of the gas released (accurary of these devices are within 10% of the actual flows as measured during preoperational testing). The recombiner building vent flow on Unit One is conservatively assumed to be constant at 500 CFM. In addition to the gaseous, particulate, and iodine release measurements tritium, gross alpha and gaseous isotopic measurements of each vent stream are conducted on a monthly schedule. After each calendar quarter (13 weeks) a summary of waste gas release from the four vents is compiled and as such is designed to meet the requirements for preparation of the 6-month report as specified in Regulatory Guide 1.21. Unit one and two releases were calculated together because the Tech. Specifications for the two reactors are identical in this respect. The methods for compilation of the quarterly releases are as follows:

1. FISSION AND ACTIVATION GAS The total curie release is determined from the continuously reading gaseous monitors in addition to the vent flow recorders. Activity monitors and vent flow rate readings are read hourly and input into the computer. From these readings a daily release is calculated. The calibration factors for the monitors are determined from the monthly isotopics when sufficient activity allows or by injection of a known amount of off-gas into the sample chambers. The total curie release is calculated by the computer for each of the individual nuclides released. This nunber is multiplied by the average energy per disintegration (E &

E)B along with the coefficients in the release limit formula in our Environmental Technical Specifications. All of the nuclides are summed and stored in their respective data files until the end of t.he quarter. Then the computer divides the sum of the nuclides by the s.econds in the quarter to determine the percent of the tech, spec. limit released.

2. RADIOIODINE RELEASES Iodine releases are determined weekly for I-131," I-133, and 1-135, for each vent. Where significant activity is not measured MDA releases are calculated. Since calculated MDA's are below Technical Specification detectable .

concentrations then 0 (zero) release is used for the weeks with only MDA values. Weekly releases are summarized with the aid of the counting room calculator - computer ' system and a quarterly total is prepared from the weekly summaries. The percent ^ Technical Specification for I-131 on Table 2-1 is based on the quarterly Technical Specification limit.

O

                                                                   -2 7 -

3. PARTICULATE P2 LEASES Particulate releases are determined weekly for each vent.

O where sieniticent ectivier is noe meesured MDA re1eese is calculated. Since calculated MDA's are below Technical Specification detectable concentrations, then 0 (zero) release is used for weeks with only MDA values. Weekly releases are summarized with the aid of the counting room calculator - computer. After each calendar month the particulate filters from each vent are combined, fused, and strontium separation is made. Since sample flows and vent flows are almost constant over each monthly period the filters from each vent .can be dissolved together. Decay corrections are made back to the middle of the quarterly collection period. Again the counting room calculator - computer is used to aid in the calculation of the Sr-89, 90 release. Where significant strontium activity is not detected MDAs are calculated. The percent of Technical Specification was calculated using quarterly average equation.

4. GROSS ALPHA RELEASE The gross alpha release is computed each month by counting the particulate filters each week for gross alpha activity in a proportional counter. The four or five weeks numbers are then recorded on a data sheet and the activity is summed at the end of the month, pd

5. TRITIUM RELEASE Tritium samples are obtained monthly from each vent by passing the sample stream from a cold trap immersed in a liquid nitrogen or an acetone and ice mixture. The grams of water vapor / cubic foot gas is measured upstream of the cold trap in order to alleviate the difficulties in determining water vapor collection efficiencies. The tritium samples are analyzed by an independent laboratory. From the uCi/ml tritium concentration, the grams water /ft3, and the vent flow rates, the monthly tritium release is calculated for each vent, and the quarterly summary can be generated from

, the monthly calculation forms. Hatch has attempted to maintain all calculated MDAs as low as possible by counting samples longer than what would be normally practical. For example at this time all weekly particulate and iodine counting times are 3000 sec and . .

strontium separations are counted for 100 minutes., .

Regulatory Guide 1.21 requires that estimated total error in analysis techniques be reported. These estimates are required for the total fission and activation gas release, total I-131 g release, total particulates wi": half-lives greater than 8-day v release, and total tritium relen.e. l _ -_ _ -__ - _ - - --1

_ . . = i "The total orwill maximum error associated with the effluent measurement include the cumulative errors resulting O from the total operation of sampling and V measurement. Because it may be very dif ficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error are not suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste." Estimated errors are based on errors in counting equipment calibration, counting statistics, vent flow rates, vent sample flow rates, non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges.

1. Fission and Activation Gas Total Release was calculated from process monitor readings. As 89.92% of this release was from the main stack the MDA release values of the ground level release points were small to the total release.

Monitor Error in Calibration 50% Vent Flow Rate 10% Non-Steady Release Rate 20% 86%

2. 1-131 Release was calculated from each weekly sample:

n U Statistical error 60% Counting Equipment Calibration 10% Vent Flow Rates 10% Vent Sample Flow Rates 10% Non-Steady Release Rates 10% Losses From Charcoal Cartridge 10% IT6%

3. Particulates with half-lives greater than 8 days release was dominated by the MDA calculations for 1-131 and Ba-La-140 hence the errors in the strontium determinations and gross alpha had negligible affects on the estimated error in the total particulate release:

Statistical Error at MDA concentration 60% Countng Equipment Calibration 10% Vent Flow Rates 10% Vent Samp'e Flow Rates 10% Non-Steady Release Rates 10% M l 0

                                           -2 9 -

Vent Sample Flow Rates 10% Non-Steady Release Rates 10% ' 100%

4. Total Tritium Release was dominated by the reactor building vent tritium release, hence, the larger statistical errors i O of the off-gas vent and reccmbiner building vent tritium releases do not affect the error in the total tritium release:

Water Vapor in Sample Stream Determination 20% Vent Flow Rates 10% Counting Calibration and Statistics 10% Non-Steady Release 50%_

                                                                      -                    90%                                             i 2.3. GASEOUS EFFLUENT RELEASE DATA Regulatory Guide 1.21 Tables lA,                  1B, and 1C are found in this report as Tables 2-la-c, 2-2a-c, and 2-3a-c.

Data is presented on a quarterly basis as per Regulatory Guide 1.21.

3. SOLID WASTE

3.1 REGULATORY SPECIFICATIONS shall be made to determine or estimate the

a. Measurements total curie quantity and principal radionuclide composition of all radioactive solid waste shipped offsite.

b. Solid wastes in storage and preparatory to shipment shall be i monitored and packaged to assure compliance with the applicable portions of 10 CFR Part 20, 10 CFR Part 71, and 3

49 CFR Parts 171-17G.

c. Reports of the radioactive solid waste shipments, volumes, principal radionuclides, and total curie quantity shall be submitted in accordance with subsection 5.6.1 of the.HNP-ETS.

3.2 SOLID WASTE DATA Regulatory guide 1.21 Table 3 is found in this report as Table 3-la, b. o

                                                     -3 0 -             .
           . - . -             -        . ~ .        ..       - - -_.        --. .               . - -      --_ -,.        - . - - .

TAELE 2-la UNIT 1 EFFLUEtiT AIID HASTE DISPOSAL set 1IAtillVAL REPORT 1983 CASEQUS EFFLUEllTS-SUttt1ATIOtt OF ALL RELEASES t Unit Quarter Quarter Est Tota! 1 E. I. H at c h fluc l e ar Fover Plant Ut1I T 1 1 2 Error *: A. Fission 8. activat, ton gases I 1. Total release Ci 8.97E+02 1.75E+03 8.00E+01)

2. Average rele ase rate for period uCi/see 1.14E+02 2.22E+02

3. % of Technical specification limit % 1.06E-01 4.07E-01 B. Iodines

1. Tot al todine-131 Ci 4.23E-03 1.57E-02 1.10E+02l ,

2. Average release rate for period uCi/sec 5.3SE-04 1.99E-03

3. % of Technical snecification limit % 2.11E-01 7.83E-01 C. P ar t i c ul at es t

1. Part1culates uith h al f-1 i ves >S davs Ci 7.65E-04 2.82E-03 . 1.00E+02l

2. Average release rate for period uCt/sec 9.74E-05 3.5SE-04 3.

                                . of Technic al specification 1tmit                                   %                1.74E-01     5.40E-01

, 4. Gros 1 al nh a r adi cac t i vi t v Ci 3.50E-06l 1.56E-04 -

                                   .T                                                                                                                           ,

D. Tritidm

1. Tot al release C1 1.14E+01 5.30E+00 9.00E+011

2. Average rele ase rat e for period uC1/sec 1.44E+00 6.74E-01 f 3. % of Te c hni c al soecirication limit I % 1.48E+01 7.73E+00!

4 o 4 I i I l i l ( I O .

TABLE 2-lb t

UNIT 2 ' EFFLUEtlT AtlD llASTE DISPOSAL SEMI AtitlUAL REPORT 1983 GASEQUS EFFLUEtlTS-SUMMATI0tl 0F ALL RELEASES

                                                                                                                                                      ~                     '

Unit Quarter Quarter Eit ' T d i ~a l' E. I. Hat ch fluc le ar Power Plant UllIT 2 1 2 E r o r; ;*. , , l

A. Fission & activation gases; 1. Tot al release Ci 3.50E+03 4.60E+02 8.00E+01'T; 2. Average release rate for period uCi/sec 4.46E+02 5.85E+01; 3. % of Te c hni c al specification limit % 5.66E-01 2.87E-01 E. Iodines
1. Total iodine-131 Ci 5.45E-03 4.31E-03 1.10E+r721: 2. Average release rate for period uCt/sec 6.93E-04 5.48E-04 i 3. % of Technical specification limit % 2.73E-01 2.15E-01l C. Particulates; 1. P art icul at e s ut t h half-lives >8 d ans C1 3.70E-04 3.25E-04; 2. Average release rate for oeriod 1.20E OR[

uCi/sec 4.70E-05 4.13E-05

3. % of Te c hni c al specification limit % 4.91E-02 7.85E-02 4 Gross al oha r adi o ac t ivi tv Ci 1.34E-06 8.31E-06) r, -

D. Tei t f uni

1. Tot al. rel e as e Ci

2. Averaci re l e as e rate for period 7.91E+006 1.20E+00i

9. 00f-7;;l' :

1.01E+00l 1.53E-01t uCi/sec

3. % of Technic al speciricstion 1imit % 1.15E+011 1.16E,00t I

T 0 . 1

                                                                                    .   . _ _ _      - _ .               , . . . _ . . - . . - _       _     _.- _.__- . _ . . . _ _ _ . _ . . -                      -_    _ . ~ .          _ _ . - . _ .

TAELE 2-Ic SITE EFFLUEtlT AtID WASTE DISPOSAL set 11AtltlUAL REPORT 1983 CASE 00S EFFLUEtiTS-SUMilATI0tt OF ALL RELEASES Unit Quarter Quarter Est Total l E. I. Hat ch fluc le ar Power Plant SITE 1 2 Error % A. Fission & activation gases

1. Total release Ci 4.40E+03 2.21E+03 S.00E+01l

2. Average release rate for period uCt/sec 5.60E+02 2.31E+02

, 3. % of Technical spec i f i c at i on limit % 6.72E-01 6.94E-01 B. Iodines .

1. Total iodine-131 Ci 9.6SE-03 2.00E-02 1.102402l

2. Average release rate for period uCi/sec 1.23E-03 2.54E-03

3. % of Technical spec t fic at t on I t ra l t % 2.42E-01 4.99E-01 i C. P art i c ulit es

1. Particulates with half-lives >S davs Ci 1.14E-03 3.14E-03 1

1. 0.? E + 0 2 l

2. Averace release rate for oeriod uCi/sec 1.44E-04 4.00E-04

3. % of Tec hni c al specification limit % 2.23E-01 6.18E-01 4 Gross aloha radioactivito Ci 4.35E-06 1.64E-04

                        ~s D. 7ritium
!                1.

2. Tot al release Average release r at e for period Ci uCi/sec 1.93E+0! 2.45E+00

6. CE+00 8.27E-01 9755{6]

3. % of Technical spe c i fi c at i on limit % 2.63E+011 8.89E+00l u

I i l r )

4 i

                                                                                        -3 3-y          , + , , . -              y c- - - ,    -,-g-,~y c --,-rwv.---       -,y,,g-+,-yy,    y,,   reg-y.-,  ,  -r-,ver  w., ,,-     .m-.-,y-r   uw        me -e*  e e v e ,*  ee-.-r

TABLE 2-2a E. I. Hatch Nuclear Pouer Plant UNIT 1 EFFLUENT AND HASTE DISPOSAL SENIANNUAL REPORT 1983 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE EATCH MODE Huclid45 Relessed Unit Quarter Quarter Quarter Quarter 1 2 1 2

1. Fizzion gases Xe-133 Ci 5.23E+02 5.11E+02 0.00E+001 0.00E-00 Xe-131m C1 3.55E+01 0.00E+00 0.00E+00 0.00E+00 Kr-83 Ci 4.42E+01 3.05E+02 0.00E+00 0.00E+00 Xe-133M Ci 7.4SE+00 2.46E+01 0.00E+00 0.00E+00 Xe-135 Ci 4.50E+01 3.33E+01 0.00E+00 0.00E+00 Kr-85H Ci 6.95E+01 3.44E+02 0.00E+00 0.00E+00 I-131 Ci 1.83E-01 0.00E+00 0.00E+00 0.00E+00 Er-87 Ci 1.62E+01 1.00E+02 0.00E+00 0.00E+00 X4-13? C1 2.25E+01 2.55E+01 0.00E+00 - 0.00E+00 X4-137 Ci 6.4SE-01 0.00E+00 0.00E+00 0.00E+00 1 H-13 Ci 9.65E+00 ' 3.84E+01 0.00E+00 0.00E+00!

Vr-85 Ci 0.00E+00 0.00E+00' O.00E+001 0.00E+00 X4-135ft Ci 3.36E+01 1.65E+01 0.00E+001 0.00E-00 I -d. 3 3 Ci 0.00E+00 0.00E+00 0.00E+00j 9.00E+00 KP189 Ci 0.00E+00 0.00E+00 0.00E+00! 0.00C+00' I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+c_ 6r-41 Ci 7.14E+00 4.80E+00 0.00E+00 0.00E+00_, Tot al for perio' Ci 8.15E+02 1.40E+03 0.00E+00 0.0*E-00 0 2. Iodines I-131 Ci 5.0SE-04 9.36E-03 0.00E+006 0.00E+00 Ci 3.52E-04 7.3SE-03 0.00E+00 0.00E,00 I-133 I-135 C1 1.31E-04 3.31E-03 0.00E+00 0. 0 0 E + 0 0_l, Tots) for period Ci 9.91E-04 2.01E-02 0.00E+00 0.00E+00_,

3. P ar t i c u l at e s Sr-89 Ci 2.98E-05 5.12E-04 0.00E+00 0.00E+00 Sr-90 Ci 1.89E-C9 4.36E-07 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .

Cr-51 Ci 3.94E-OS 0.00E+00 0.00E+00 0.00E+00 : 1-131 Ci 6.58E-07 1.53E-05 0.00E+00 0.00E+03]'; Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.'00E+00 Ba-140 Ci 6.15E-06 3.32E-05 0.00E+00, 0.00E+C0 C3-134 Ci 9.03E-OS 4.74E-07 0.00E+00; 0.00E+05" CA-137 Ci 3.6SE-07 2.14E-06 0.00E+001 0.00E+0'l_ - C4-144 Ct 0.00E+00 0.00E+00 0.00E+001 0.00E+00 2r->J Ci 0.00E+00 0.00E+00 0.00E+001 0.00E+00 Ho-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+0o: Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F4-59 C 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 1.0SE-07 3.77E-07 0.00E+00 0.00E+00[ Ci 1.1SE-05 6.09E-05 0.00E 00 0.00E+001 (*) L1-140

 %-)                                                     4.90E-05     6.25E-04        0.00E+00l0.006073, Total for period                             Ci
                  - _ - . ,                  .-            ,m   , -.   -

TABLE 2-2b E. I. H st ch Nuc l e ar Pouer Pl ant UNIT 2 EF.:LUENT AND 1!ASTE DISPOSAL SEMIANNUAL REPORT 1983 GA3EOUS EFFLUENTS-ELEVATED RELEASE CONTIHUOUS MODE EATCH NODE Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 1 2

1. Fission gases Xe-133 Ci 1.91E+03 0.00E+001 0.00E+00 0.00E+00 :

Xe-131m Ci 1.30E+02 0.00E+00 0.00E+00 0.00E+00 Kr-SS Ci 1.61E+02 0.00E+00 0.00E+00 0.00E+00 1 Xe-133M Ci 2.73E+01 0.00E+00 0.00E+00 0.00E+00 l Xe-135 Ci 1.64E+02 0.00E+00 0.00E+00 0.00E+00 Kr-85M Ci 2.54E+02 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 6.67E-01 0.00E+00 0.00E+00 0.00E+00 he-87 Ci 5.93E+01 0.00E+00 0.00E+00 0.00ETdII' Xe-138 Ci S.23E+01 0.00E+00 0.00E+00 0.00E+00 X4-137 C1 2.36E+00 0.00E+00 0.00E+00 0.00E+00 N-13 Ci 3.52E+01 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 X4-135M Ci 1.23E+02 0.00E+00 0.00E+00 0.00E+00 I-133 Ci C.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+001 0.00E+00 0.00E+00 1-135 Ci 0.00E+00 0.00E+001 0.00E+001 0.00E-C0 Ar-41 _Ci 2.61E+01 0.00E+001 0.00E-00 0.0CE+00_ Tot s) for period Ci 2.97E+03 0.00E+00 0.00E+00 0.0eE-00

2. Iodines I-131 Ci 1.S5E-03 0.00E+00' O.00E+00 0.00E+00 I-133 Ci 1.29E-03 0.00E+00 ; 0.00E+00 0.00E+00" I-135 Ci 4.77E-04 0.00E+00 0.00E+00 0.00Et01_

Totti for period Ci 3.62E-03 0.00E+00 0.00E+00 0.002-e0

3. P art i c ul at e s Sr-89 C1 1.09E-04 0.00E+00! 0.00E+001 0.00E+00 Sr-90 C1 6.89E-08 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 Cr-51 Ci 1.44E-07 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 2.40E-06 0.00E+00 0.00E+00 0.00E+0C <

Sn-113 Ci 0.00E+00 0.00E+001 0.00E+00 0.00E+00_ B s-140 Ci 2.25E-05 0.00E+00u 0.00E+00 0.00E+e3 ' C1-134 Ci 3.30E-07 0.00E+00 0.00E+00 0.00i+09,_ j Cs-137 Ci 1.35E-06 0.00E+00 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 0.00E+00' O.00E766"f Co-53 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 , Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l ' Co-60 Ci 3.95E-07 0.00E+006 0.00E+90 0.00E-00 Ci 4.29E-05 0.00E+00 0.00E+00 0.005~00 [)/ L s-140 Tot s1 for period Cl 1.79E-04 0.00E+00 0.00E+00. 0.002+ag_ _

TRELE 2-2c E. I& Hatch Nuclear Power Plant SITE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1933 (V~g GASEQUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE EATCH NODE , huclides Reisased Unit Quarter Qu art e r Qu art e r Qu ar t e r i 1 2 1 2

1. Fission gases -

Xe-133 C1 2.43E+03 5.11E+02 0.00E+00 0.00E+00 Xe-131hi Ci 1.65E+02 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 2.06E+02 3.05E+02 0.00E+00 - 0.00E+00 Xe-133M Ci 3.4SE+01 2.46E+01 0.00E+00 0.00E+00 Xe-135 Ci 2.09E+02 3.33E+01 0.00E+00 0.00E+00 Kr-85M Ci 3.23E+02 3.44E+02 0.00E+00 0.00E+00 1-131 Ci 8.50E-01 0.00E+00 0.00E+00 0.00E+00 Fr-?7 Ci 7.55E+01 1.00E+02 0.00E+00 0.00E+00 Xe-138 Ci 1.05E+021 2.55E+01 0.00E+00 0.00E+00 M*-137 Ci 3.01E+001 0.00E+00 0.00E+00 0.00E+00 N-13 Ci 4.49E+01! 3.84E+01" 0.00E+00 0.00E+00 Kr-35 C1 0.00E+001 0.00E+00' O.00E+00 0.00E+00 Xe-135M i Ci 1.56E+021 1.65E+01 0.00E+00 0.00E+00 1-t33 i Ci 0.00E+00 0.00E+00 0.00E+00! 0.00E-00 KF"89 Ci 0.00E+00 0.00E+00 ' O.00E+001 0.00i+00 I-1?5 Ci 0.00E+00 0.00E+00, 0.00E+001 0.00E+00 Ar-41 Ci 3.32E+01 4.80E+00 0.00E+00I 0.00E+00 () Tot al for oeriod Ci 3.79E+03 1.40E+03 0.00E+00 0.00E-?O

2. Iodines I-1?! I Ci 2.36E-031 9.36E-038 0.00E+00) 0.00E+00 I-133 Ci 1.64E-03 7.38E-031 0.00E+006 0.00E+00 Ci 6.08E-04 3.31E-03' O.00E+00 0.00E+00 I-135 Tot al for period Ci 4.61E-03 2.01E-02 0.00E+00 0.00E'OO,

3. Part i c ul at e s Se-89 C1 1.39E-041 5.12E-04' O.00E+00l 0.00EIUf' Sr-90 Ci 8.77E-08 4.36E-07 1 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+001 0.00E+00 0.00E+00 Cr-51 Ci 1.83E-07 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 3.06E-06 1.53E-05 1 0.00E+00 0.00E+00 Sn-113 Ct 0.00E+00 0.00E+00 1 0.00E+00 0.00E+00 Ba-140 Ci 2.86E-05 3.32E-05i 0.00E+006 0.00E+00 CA-134 Ci 4.20E-07 4.74E-07 0.00E+001 0.00E+0c '

C2-137 Ci 1.71E-06 2.14E-06 0.00E+00 0.00E+00 C4-144 Ci 0.00E+00 : 0.00E+001 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00f 0.00E+006 0.00E+006 0.00E+00 Mb-95 Ci 0.00E+00- 0.00E+00! 0.00E+001 0700E+00 Co-58 C1 0.00E+00 0.00E+00 0.00E+001 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+001 0.00E+00 F4-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 s Co-60 Ci 5.03E-07 3.77E-071 0.00E+00 0. 00 K_+,0,0 ,

 -            La-140                                 Ci      5.47E-05 6.09E-05' O.00E+00 0.00d*00 0.00E+00   0.002,00 Tot al for period                             Ci

2.2SE-04 6.25E-04

                                          -      - - - - - -                     _~__ __ . _                _,     ,

TAELE 2-3a E. I. Hat ch Hucle ar Power Plant UNIT 1 E.0 FLUENT AND HASTE DISPOSAL SEMIAHHUAL REPORT 1933 GASEOUS EFFLUENTS-GROUHD-LEVEL RELEASE CONTIHUOUS NODE EATCH NODE Quarter Quarter Quartir Quarter Huclidis Re l e as e d Unit 1 2 1 2. . .

1. Fission gases l Ci 1.89E+01 8.12E+01' O.00E+00 0.00E-0C Xe-133 0.00E+00 0.00E;00 Xe-131m l Ci 0.00E+00 0.00E+00 Ci 9.44E-01 3.67E+00 0.00E+00 , 0.00E+0c Kr-88 0.00E+00 . 0.00d.00 X4-133M Ci 0.00E+00 0.00E+00 C1 3.44E+01 2.17E+02 0.00E+00 . 0.00E+00 Xe-135 5.63E-01 0.00E+00 0.00E+00 Ci 5.82E-01 Kr-85M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 Ct 2.47E+00 5.55E+00i 0.00E+00 0.00E+00 K"-97 1.31E+016 0.00E+004 0.00Et001 X"-138 Ci 3.26E+00 Ct 2.40E+00 0.00E+00 0.00E+001 0.00E+0el Xi-137 C: 1.51E+00 6.03E+00 0.00E+001 0.00E+0?!

H-13 0.00E+001 0.00E+00[ 0.00d+00 Kr-95 i Ci 0.00E+00 l Ci 1.75E+01 1.72E+011 0.00E+001 0.00E-00 X4-135M 0.00E+001 0.00E+006 I-433 Ci 0.00E+00 O.00E+00j 0.00E+00-0.00E-06[ Ci 0.00E+00 0.00E+00' Kr*69 Ct 0.00E+00 0.00E+00 0.00E+006 0.00E+001 1-135 Ci 7.S9E-03; 0.00E*00 0.00E+00 0.00E+00' Ar-41 3.44E+02. 0.00E*00 0.00E+00

 \   Tet al for period                                                Ci                  8.19E+01

2. Iodines Ci 3.5SE-03: 5.SSE-03: 0.00E*00l 0.00E-00 I-131 Ci 2.99E-03 3.17E-03 0.00E+00i 0.00E+6E]

1-133 I-135 Ci 1.01E-03 2.65E-03 0.00E-00 0.00E+oO Tot at for period Ci 7.53E-03 1.17E-02 0.00E+00 0.00E+00

3. P art i c ul at e s

                                 ~                                '

Ci 5.57E-05 2.06E-041 0.00E+00l 0.00E+00 Sr-39 Ci 9.0SE-OS 2.75E-061 0.00E+00; 0. 0 V E +15"' ~ Sr-90 0.00E+001 0.00E+004 0. 0 0 E + 0 6'" Ci 0.00E+00 Ce-141 Ci 1.4SE-06 2.62E-04 0.00E+00 0.0CE III Cr-51 ~ 1.44E-04 3.95E-04i 0.00E+00l 0. 00E +.:0 . , I-131 Ci 0.00E+001 0.00E+00 0. 0 0 E + 0 9['_[ Sn-113 Ci 0.00E+00 Ci 4.66E-05 9.99E-056 0.00E+00 0.00E+00 1.09E-04 3.'31E-041 0.00E+00 0.00E+01 B a- 140 ~ Ci 1.98E-04 4.78E-041 0.00E+00 0.00E+00 C2-134

Ci 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 Cs-137 '

Ce-144 Ci

~~

Ci 1.97E-09 0.00E+00' O.00E+001 0.00E+00 Zr-95 Hb-95 Ci 0.00E+00 0.00E+00, 0.00E+001 0.00E+00 j

Ct 2.67E-09 5.0SE-051 0.00E+006 0.00E+00 Co-58 "

Ci 9.10E-06 2.20E-05l 0.00E+00i 0.00E+00 0.00E+00 0.00E+00 0.00E+00I 0.005 F#T Mn-54 ~ Fe-59 Ci Co-60 Ci .9.49E-05 1.25E-041 0.00E+00i O.00m+00

(~N

 \-           La-140                                             's       Cs                  5.76E-05 2.1?E-041 0.00E+00! 0.00E*03 l

2.19E-03 0 . 0 0 E +'? ? 0 . 0 f',E +p 0_ Total for period . , C ,.,_ 7.17E-04 l __ _ _ - 3 7, . _

TAELE 2-3b E. I. Hatch Huc l e ar Pouer Pl ant UNIT 2 O ts _/ EFFLUENT AHD WASTE DISPOSAL SEMIANNUAL REPORT 1933 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTIHUOUS NODE BATCH N00E Hucindes Released . Unit Quarter Quarter Qu ar t e r Quartie 1 2 1 2

1. Fission gases X+-133 Ci 8.78E+01 2.72E+02 0.00E+00 0.00E+00I X4-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-83 Ci 2.52E+01 3.87E+01 0.00E+00 0.00E+00 Xe-133H Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 Ci 2.21E+02 9.35E+01 0.00E+004 0.00E+00 Kr-85H Ci 3.59E+00 4.85E+01 0.00E+00 0.00E+00 1-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I Kr-ST Ci 2.56E+01 7.02E+00 0.00E+00 0.00E+IiE~

Xe-138 Ci 4.2SE+00 0.00E+00 0.00E+00' O.00E-00' Xe-137 Ci 0.00E+00 0.00E+00 0.00E+001 0.00E+00 H-13 Ci 0.00E+00 0.00E+00 0.00E+00l 0.00E+00 VF-35 Ci 0.00E+00 0.00E+006 0.00E+00 0.00E+00; X4-135M C1 1.62E+02 0.00E+00l 0.00E+00 0.00E+00 I - 53 3 Ci 0.00E+00 0.00E+001 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+001 0.00E+00 0.00E+00l I-135 Ci 0.00E+00 0.00E+00, 0.00E+00 0.00E+00 Er-41 Ci 0.00E+00 0.00E+00 0.00E+001 0.00E+F0I Tot al for period Ci 5.29E+02 4.60E+02 0.00E+00 0.00E+00

2. Iodines

' 1-131 Ci 3.53E-03 4.2SE-03 0.00E+006 0.00E-001 I-133 Ci 2.00E-03 3.52E-04 0.00E+00' O.00E+00l 1-135 Ci 6.53E-04 6.42E-05 0.00E+00 0.00E+00 Total for period Ci 6.19E-03 4.70E-03 0.00E+00 0.00E+00

3. P art i c ul at es Sr-89 Ct 8.71E-05 2.16E-04 0.00E+00 0.00E+00 Sr-90 Ci 2.36E-03 7.16E-07 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 1.05E-06 0.00E+00 0.00E+00 0.00E+00 1-131 C1 6.04E-05 2.27E-05 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+0) 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 1.09E-05 2.53E-05 0.00E+00 0.00E+00 Cs-134 Ci 1.34E-06 3.99E-07 0.00E+00 0.00E+00 C5-137 Ci 4.98E-06 3.12E-06 0.00E+00 0.00E+00 Ce-124 Ci 0.00E+00 0.00E+00 0.00E+00 1 0.00E+00 Zr-95 Ct 5.56E-07 0.00E+00 0.00E+00 0.00E-00~

Hb-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+50 ~ Co-58 Ci O.00E+00 0.00E+00 0.00E+00 0.00E+0E Hn-54 Ci 2.57E-07 0.00E+00 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+001 0.00E+00 () Co-60 L a-14 0 Ci Ci 3.97E-06 2.04E-05 5.25E-06 5.12E-05 0.00E+00 0.00E+00 0.00E+v0 0.00E+00

T o t .a t for period Ci 1.91E-04 3.25E-04 0.00E+00 0.00E+00 M-

TABLE 2-3C E. IS Hktch Nuclear Pouer Plant SITE EFFLUE!!T A!1D 11A?TE DISPOSAL SEllI ANtlUAL REFORT 1933 GAiE003 EFFLUENTS-GROUND-LEVEL PELEASE COHTINUOUS NODE BATCH NODE leuclides Released Unit Quarter Quarter Quarter Quarter

                             .                                                  1                2           1               2

1. Fission gases Xe-133 C1 1.07E+02 4 3.53E+02 0.00E+00i 0.00E2 0iI 4 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+001 0.00E+00 '

Kr-SS Ci 2.62E+01 4.24E+01 0.00E+00 0.00E+00 l 0.00E+00 0.00E+00 0.00E+00 Xe-133M Ci 0.00E+00 l Xe-135 Ci 2.55E+02' 3.10E+02 0.00E+00 0.00E+00 Kr-85M Ci 4.18E+00 4.91E+01 0.00E+00 0.00E+00 j 0.00E+00

'         I-131                                                       Ci    0.00E+00         0.00E+00    0.00E+00 Kr-87                                                       Ci    2.81E+01         1.26E+01    0.00E+00         0.00E+00 Xe-!??                                                      Ci    7.54E+001        1.31E+01    0.00E+00         0.00E-00 i

X4-137 Ci 2.40E+001 0.00E+00 0.00E+00! 0.00E+00l t3-13 Ci 1.51E+001 6.03E+00 0.00E+00 0.00E+001 4' Kr-85 Ci 0.00E+001 0.00E+00 0.00E+00 0.005756T X4-135H C1 1.SOE+021 1.72E+01 0.00E+00 0.00E+dET j 0.00E+006 0.00E+00 0.00E+001 0.00Ee00 I-133 Ci Ci 0.00E+001 0.00E+00t 0.00E+00 0.00E-00 } K[-59 _ 0.00E+00' O.00E+004 0.00E+00 0.00E+00

I-135 Ci Ar-41 Ci 7.39E-03 0.00E+00- 0.00E+00 0.00E-00 TotEl for period Ci 6.11E+02 8.04E+02 0.00E+00 0.00E+00

2. Iodines I I-131

Ci 7.11E-031 1.02E-021 0.00E+00: 0.00E,.?][ I-133 Ci 5.00E-038 3.52E-031 0.00E+00 0.00E-00 . I-135 C1 1.66E-034 2.71E-03 0.00E+00 0.00E+03 [ . Tot al for period Ci 1.33E-02 1.64E-02 0.00E+00 0.00E-00 t

3. Particulates 1

~~

Sr-89 C1 1.43E-04 4.22E-04 0.00E+00 0.00E+00 " i SP-90 Ci 1.14E-07 3.47E-06 0.00E+00 0.00E+00 0.00E+00l 0.00E+00 .i Ce-141 Ci 0.00E+00 0.00E+00 i Cr-51 . Ci 2.54E-06 2.62E-04 0.00E+00l 0.00E+06" I-131 'l Ci 2.05E-04 4.18E-04 0.00E+001 0.00E400 Sn-113

Ci 0.00E+00 0.00E+00 0.00E+001 0.00E+0'i' Ba-140 Ci 5.75E-05 1.25E-04 0.00E+00f 0.00E+00' ;

Cs-134 Ci 1.10E-04 3.31E-04 0.00E+00 0.00E+001 i Cs-137 -

                                                                   '" 71    2.03E-04         4.81E-04     0.00E+00         0.00E76E Ce-144                                                 - ~C I~    0.00E+00'        O.00E+00     0.00E+00 0.00E+00 l          2r-95                                                       Ci    5.5SE-07         0.00E+001 0.00E+00 0.00E+00 Hb-95                                                       Ci    0.00E+00         0.00E+006 0.00E+00) 0.00E+00 l          Co-53                                                       Ci    2.67E-09          5.05E-05 . 0.00E+001_0.00E+00 Nn-54                                                       Ci    9.36E-06          2.20E-05 i 0.00E+001 0.00E+00

Fe-59 Ci 0.00E+00: 0.00E+00 0.00E+00l 0.00E+00 '

j Co-60 Ci 9.89E-05 1.30E-04 0.00E+006 0.00E70< L a- 140

Ci <.80E-05 2.70E-04 0.00E+00' O.00E ! 00 , Tot al for period , Ci 9.07E-04 2.52E-03 0.00E+00 0.00E+00 I 4

TABLE 3-la EFFLUENT AND V!ASTE O!Si'OSAL SE!.11 ANNUAL REPORT (YEAR) 1983 January 1 - June 30, 1983 SOLID YlASTE ANO IRRADIATED FUEL SHlot.iENTS FOR UillT I 1 l A.50 LID YlASTE SHIPPEO OFFS!TE FOR CURIAL OR DISPOOAL(Notirradiated fuel) h ath Ep.TocI

1. Type of waste Unit hetoo Err e,r. %

a. SPent t: sins. fdter sh.d;::, coperator rn' 1. ocE7 I inttor.s. etc. Ci R .7aE9 1 1_ . n E -1

        .           b. Dry cornpreu::i: w::::. cont:rninst:d                         rn'    '   4 .apEp eqt:ip. et:.                       .                            Ci      1    61 E1 : 1.n E 49
      -             c.1:::d:sted components, cent:01                                 rn'        n.nnE I roe's. et:.                                                      Ci   10.00E l . E m*      I ? . F;? E l I

d. Other (d:s::.be) Ci l 8 00 E-2l1.0 E-1

2. Estim:te of m:ior at: cud: composi:icn (by type of w:s::)

I PERCENT l CURIES ISOTOPE I

a. Zn-65 an 7a I 97n 9n Cs-137 7s.18 999 91 17 o' 1c7 c1 Cs-134 ~

Otners , 25 og i Ho ic

b. Zn-65 1 ac cc i 7 cn

9a an i a io s) . Co-60 Cs-137 1 1 la oc I o c? _

         +                 Others                                                                 7.9A 1           1 oo
           .          c. None                                                                    _____ i l

t i I h i ac oc I n no

d. Cs-137 9n oo 0 o' Cs-134 Zn-65 {cij I o no-Others 17 79 1 0.01 i I

3. SoUd Viss:: Disposition Mede ofTr:nsecrt:tien D ::!nstion Number oiShi:rnents 50 Tractor-trailer Barnwell 5 Tractor-trailer Richland D. IRRADIATED FUEL SHIP.'.1ENTS (Disrcsitien)

Mod: orTr:n: or:stian ce:tirution Number or s!icrents . 0 N/A N/A O . 6

TABLE 3-lb EFFLUENT AND'.'!ASTE DISPOSAL SE:.tlANNUAL RE? ORT (YEAR) 1983' January 1 - June 30, 1983 SOLIO ViASTE ANO 1RR ADIATED FUEL SHIPT.iENTS O , FOR UNIT rr A.501.1D Y.'ASTE SHIFFED OhFSITE FCR GURIAL OR DISTO';AL (?!ot irradiated fuell Unic

                                                                                                 """"i                   Eu.Toct

1. Type of wute P"d En or. %

a. Spent t: sir.s. Idter s! d;:5. c o perato r rd 1 .n1 E 9 Inttor .s. etc. Ci ? .7R E 9 1. n1E-1

       .         b. Dry compress::t: w::::. cont:rr.tnsted                            c'       4 42 E 2 equip. etc.                               .                          Ci. 1 .sqE1l1.nnb?

c.1:: dated corr.panents. centrol 6 r-f n .00E I roe:s. et:. I Ci l 0 .00 E l . E m' ? .s? E 1 '

d. Other (des:.T:e) Ci ,8 00 E-2 1 00E-1

2. Estim:te of m:ior nucUde composition (by type of w=ste) i PERCENT l CURIES ISOTOPE

a. I-131 35.61 00 00 91 po An_oo Zn-65 Cs-137 14 so an oc Others 97_70 I 77 90 i Mc cc 7 cn

b. Zn-65 2e 48 a >e O .

co-so Cs-137 i 1A os ?_g? Utners 7.99 1_po

          .        c.None

t I

I ag ?g n no d.Cs-137 Cs-134 9039 l n 97 Zn-65 1c 73 n n7 Others 17_71 n n3 r (1

3. SoUd Vlaste Dispedtion Mode ofTr:nsport:tien D::tination Number of Sid:ments 32 Tractor-trai;er Barnwell 4 Tractor-trat er Richland D. IRRADIATED FUEL SHIPME:'TS (Disrcsition)

MM: of Tr:n::ortation De:tiration Numb <r of Shier. nts. 0 N/A N/A O -

                                                     . , - .                .-+-                   ,           - . - - - ,          ,

Georgia Power Company Routo One. Box 278 Basley. Georgia 31513 Telephone 912 367-7/81 # ** 912 537 9444 Edwin I. Hatch Nuclear Plant GeorgiaPower August 25, 1983 GM-83-850 PLANT E. I. HATCH Semi-Annual Radioactive Effluent Release Report Director of Inspection and Enforcement

 % Distribution Services Branch U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

Pursuant to Section 5.7.1.b in Appendix B, Environmental Technical Specifications, of the Plant Edwin I. Hatch Operating Licenses, please find enclosed the Semi-Annual Report for Plant Radioactive Effluent Releases, January 1, 1983 through June 30, 1983.

,/

C H. C. Nix General Manager WHR/jak i

I 1}}

ML20080C993

Text

Dear Mr. O'Reilly:

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