Text

Semiannual Radioactive Effluent Release Rept, Jan-June 1980
	ML19331D646
Person / Time
Site:	Hatch
Issue date:	08/30/1980
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML19331D642	List: ML19331D641; ML19331D646;
References
	NUDOCS 8009030419
	Download: ML19331D646 (44)
	v • d • e

George Power Company Post Off.cc Box 442 Baaley, George 31513 O Tc!ephonc912367 7781 912 537-9444 o Edwin 1. Hatch Nuclear Plant o

Georgia Power tre soutwn cWJrc sr2cm

. August 30, 1980 PM-80-887 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

(

N- S p e c.i f i c a t i o n s , of the Plant Edwin 1. Hatch Operating Licenses, please find enclosed the Semi-Annual Report for Plant Radioactive E f f,hu en t Releases, January 1, 1980 through June 30 1 &gfd )

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GEORGIA POWER COMPANY

PLANT E. I. HATCH i i j UNITS NO. 1& 2 4

SEMIANNUAL REPORT 3

PLANT RADIOACTIVE EFFLUENT RELEASES l

. JANUARY 1, 1980 - JUNE 30, 1980 4

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PLANT E. I. HATCH SEMIANNUAL REPORT

., PLANT RADIOACTIVE EFFLUENT . RELEASES SECTION TITLE PAGE

1. LIQUID EFFLUENTS 1 1.1 REGULATORY LIMITS 1 1.2- MAXIMUM PERMISSIBLE CONCENTRATIONS 2 1.3 MEASUREMENTS AND APPROXIMATIONS OF

, TOTAL RADIOACTIVITY 4 1.4 LIQUID EFFLUENT RELEASE DATA 6 t

2 GASEOUS EFFLUENT 23 2.1 REGULATORY LIMITS 23 2.2 MEASUREMENTS AND APPROXIMATIONS OF

, TOTAL RADIOACTIVITY 25 2.3 GASEOUS EFFLUENT RELEASE DATA 29 3 SOLID WASTE 29 3.1 REGULATORY SPECIFICATIONS 29 3.2 SOLID WASTE DATA 29

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PLANT E. I. HATCH SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES FIGURE LIST OF FIGURES PAGE 1-1 METHODS OF MEETING TABLE II 7 COLUMN 2 MPC LIMITS (10 CFR 20) 1-2 L7 QUID RADWASTE ANALYSIS - UNIT I 8-11 1-3 LIQUID RADWASTE ANALYSIS - UNIT II 12-15 1-4 LIQUID RADWASTE DISCHARGE PERMIT 16 1-Sa, b LIQUID RADWASTE DATA COMPILATION 17, 18 TABLE LIST OF TABLES PAGE 1-la, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 19, 20 1-2a, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-BATCH ONLY 21, 22 2-la-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES 30-32 2-2a-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-ELEVATED RELEASE 33-35 2-3a-c EFFLUENT AND WASTE DISPOSAL SLMI-ANNUAL REPORT, CASEOUS EFFLUENTS-GROUND LEVEL RELEASES 36-38 3-la, b EFFLUENT AND WASTE DISPOSAL' SEMI-ANNUAL REPORT, SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 39, 40 v

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,mu.,-rev- e PLANT RADIOACTIVE EFFLUENT RELEASES 1 LIQUID EFFLUENTS 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.

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

3. The cumulative release of radioactive materials in 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 alarm and to initiate the automatic closure of the waste discharge valve prior to exceeding the limits specified in 1. above.

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

6. The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to

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process radioactive liquid wastes prior to their discharge when the projected cumulative release rate could exceed 1.25 Ci/ reactor / calendar quarter, excluding tritium and dissolved 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 in liquid effluents, excluding tritium and dissolved 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 of action to reduce such releases to the design objective icvels and report these actions to the Commission within 30 days from the end of the quarter

during which the release occurred.

9. An unplanned or uncontrolled offsite release of 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 MPC 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 before the release of the batch. To facilitate the measurements and calculations, the nuclides of Column 2 which can be produced in a fission reactor have been grouped according to MPC value and type of raiiation as shown in Figure 1-1.

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

Only two pure beta emitters, Sr-89 and S r-9 0, . 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 acceptabic tritium measurement. A distillation and liquid scintillation counting technique is used to measure tritium concentration.

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The maximum activity of gamma and beta emitting nuclides with MPC values greater than 9 X 10 -6 uCi/m1, except for the 29

nuclides noted above, is determined by gross gamma and gross beta measurements. Measurement sensitivity limits of approximately 2 cpm /ml allow a null measurement to show that the sum 2 (Ci/MPCi), is less than 0.1 for gamma and beta nuclides not measured directly.

The sum of the ratios, 4E(Ci/MPCi), for alpha emitters can be 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 counting is used to achieve the required sensitivity of measurement.

Thus, except for radionuclides produced in negligible quantities in a fission reaction (eg. 1-125, I-129 etc.), the methods outlined above provide a means to assign a quantitatively measured or MDA value to all nuclides in Column 2. These measured and calculated concentration values for each batch are used 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 l data is used to assure that quarterly and annual release limits are not exceeded. Bases used for the data of Table 1-1 are as

. follows:

2

A. Fiesion and activation products -

The total release values (not including tritium, gases, alpha) are comprised of the cum cf 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 forth l g in the Environmental Tech Specs. This sum is for each batch

'g released to the river for the respective quarter. Percent of applicable limit i s' determined from a mixed nuclide MPC calculation. The average concentration for each nuclide summed over all batches is divided by the corresponding individual MPC value. The sum over all auclides of the Ci/MPCi ratios times 100 is the percent of applicable limit for effluent releases during the quarter.

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 t. o percent to give the percent of applicable li.it.

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 Xe-135, include noble gases with half lives g cater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; Xc-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 gaseous forms is not performed because it would not provide

' 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.

Datails of the analytical procedures for liquid radwaste analysis are contained in operating procedure HNP-7601. The following measurements are performed as indicated.

MEASUREMENT FREQUENCY METH3D

1. Gamma Isotopic Each Batch Ge ( LI) spectrometry with on-line computer.

2. Gross Gamma Each Batch 2 X 2 NaI well crystal ;

counting

3. Cross Beta Each Batch Gas flow proportional counting

4. Sr-89 Quarterly Chemical separation and Composite gas flow proportional 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

() 8. Dissolved Gases Each Batch Ge(Li) spectrometry with on-line computer i

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If a liquid redwaste tank cannot be reprocessed, a sample for analysis is taken frdm the tank after the required recirculation time. The sample is used for gammc-ray spectroscopy, gross gamma and gross beta counting, and for preparation of a composite sample.

OV The Ge(Li) detector consist of a 10% and two 15% efficiency, 2.0 FWHH resolution detectors in 4-inch thick lead shields. A one-liter radwaste 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, sampte volume, sample geometry, detector efficiency, baseline counts, and branching ratio. MDA calculations, including the above corrections, are made based on the counLs in two standard deviations of the baseline count at the location on the spectrum where a peak for that nuclide would be lvented if present.

The calculated radionuclide concentrations or MDA values from the 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 a n c' 1-3.

The Liquid Radwaste Discharge Permit Printout is transferred item by item to the first portion of the release permit (Figure 1-4) by a laboratory technician. Although the computer could printout the release permit and will inform the technician if a batch f(m) cannot be discharged as desired, 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 c o u .1 L 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 was 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 re'1 case permit is returned from Radwaste Operations following discharge, the discharge data is combined with the analysis results on the computer disc file. The disc file cay be scanned to display trends in any recorded parameter, or may be summed for reporting purposes as shown in Figure 1-Sa and b.

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All other radionuclide concentration ocasurements are performed as indicated in the t'able given previously in this section and as ~

detailed in the procedure HNP-7601. The dissolved gases calculation is performed in the Ge(Li) spectrometry system with computer data reduction using the Liquid Radwaste Library which includes gases.

O 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 -

both Units was 5.30 E-2 curies for the first quarter and 1.93 E-2 curies for the second quarter. These values were approximately 1/280 for Unit 1 and 1/574 for Unit 2 for the first quarter and 1/694 for Unit 1 and 1/2028 for Unit 2 for the second quarter of the allowed 10 curies per quarter per reactor.

2. The radwaste release procedure emphasized reprocessing rather than discharge of liquid radwaste. During this report period 27.3% of the liquid radwaste reaching the sample tanks was' discharged; 72.7% was recycled back into both of the reactor water systems.

l 3. A complete isotopic scan, gross beta, and gross gamma counts 4 and computer analysis were performed prior to the release of each of the 665 discharge batches for both Units.

1.4 LIQUID EFFLUENT RELEASE DATA RegulaLory Guide 1.21 Tables 2A and 2B are found in this report 1 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: 665 1

Total time period for releases: 87,023 minutes Maximum time period for a batch release: 218 minutes Average time period for batch release: 131 minu.es Minimum time period for a batch release: 2 minutes Average stream flow during periods of release of effluent into a flowing stream: 17968 CFS I

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. , yy, . . _ , , . - - . - _ ,,,_,,.~-.,y,,w,, --,m.,, . . , . . , , , , - , . . , _ _ _ , - _,-,_,,,y-

FIGURE 1-1 '

METHODS OF MEET-ING, TABLE II, COLUMN 2 MPC LIMITS MPC RANGE GAMMA-RAY BETA ALPHA EMITTERS

{}(UCi/ml) EMITTERS EMITTERS I-131,1-132, I-133 Sr-89, Sr-90 I-135, Cs-134 (Separation &

Gas Flow

<9X 10 -0 (Ge(Li) Gamma-Ray Counting)

Spectroscopy) ALL

,(Gas Flow

, Counting, Sensitivity

'0.01 CPM /ml)

Ba-La-140, Ne-24,cu-64 Tritium

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>9X 10 -6 Ag- bm Mn-b4 58 (Distillation &

Liquid Scintil-lation Counting)

Zr-Nb-95, Cs-Ba-137 .

As-76, F TET Ur:5T- 1 All Others Np-279, Ce-1ET Mo-Te-99, Ce-Pr-144 (Gas Flow Counting (Ge[Li) Gamma-Eay Sensitivity ~2 Spectroscopy) CPM /ml ,

() All others (Gross Gamma-Well Counter; Sensitivity

~ 5 CPM /ml) t h

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17di10BLC T 74 PROCEDURE: HNP-7601 REVISIGH: 7 DATA SHEET 8 caene***************ee*****o**ese************** y e E. I. Hatch fluc l e ar Pl ant o

Liquid Radwaste Analysis *

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' R e ac t e r #

Eatch# 322

('"'l Tank: FDSTI Recirc time: 72 minutes Ceramen t : itAItiTAlti CST Eun date: 6/20/80 1909 Count start d at e : 6/20/80 1710 Sample vo'une: 10 0 0. 0 0 ' n.1 Clock t i rn e : 3000 secs Geometry .: ode: 1LHE-0 Live time: 3000 secs Detectork 1 HCA# 1 i Li:rary: LE!!LE2 Operator: 11C l

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Energy (k e '/ > = .77 + 1.000+Ch# + 0.000E+00*Ch#^2 + 0.000E+00*Ch#^3 : 06/20/20 0021 t

Eff = 1/C6.528E-02 + E^(-2.6930E+00) + 531.006

E^(9.361;E-01>3 : 06/19e:2 0 0214 uhere E = Energy in MeV.

ISOTOFE ENERGY CONCENTRAT O't ERROR MPC C/f1PC (kev) (uCi/ml) (uCi/ml) (uCi/n1)

===================================================u================

Ce-144 133.50 <3.854E-07 . 1E-05 <3.85E-02 Tc-99m 140.50 <4.508E-08 3E-03 <1.50E-05 Ce-141 145.40 <8.340E-08 -

9E-05 <9.27E-04 Hp-239 277.90 <2.SS6E-07 1E-04 <2.89E-03 320.10 <3.666E-07 2E-03 <1.83E-04

' ) Cr-51 I-131 364.73 1.117E-06 6.201E-08 3E-07 3.72E+00

Z n-6 9 t<, 438.70 <3.767E-08 6E-05 <6.28E-04 H-IS7 479.50 <1.352E-07 6E-05 <2.25E"03 F-18 511.00 <2.630E-08 SE-04 <5.26E-05 I-133 529.50 <4.430E-09 1E-06 <4.43E-02 Es-140 537.40 <1.630E-07 2E-05 <S.15E-03 As-76 559.30 <7.020E-03 2E-05 <3.51E-03 C2-134 606.32 6.237E-07 6.227E-08 9E-06 6.93E-02 Cs-137 661.90 4.76SE-07 5.496E-OS 2E-05 2.38E-02 Mo-99 739.70 <2.715E-07 4E-05 <6.79E-03 Zr-97 743.50 <3.720E-08 2E-05 <1.86E-03 Zr-95 756.90 <?.78?E-03 6E-05 <1.30E-03 Hb-95 765.80 <4.120E-08 1E-04 <4.12E-04 I-132 772.60 ('; . 6 4 6 E-08 SE-06 <3.56E-03 Co-58 810.60 s4.139E-08 9E-05 <4.60E-04 Mn-54 834.80 <3.907E-08 1E'-04 <3.-1E-04 Ag-110m Se4.70 <4.436E-OS 3E-05 <1.48E-03 Zn-65 1115.40 <1.213C-07 1E-04 <1.21E-03 I-135 1260.50 '<1.0522-07 4E-06 <2.63E-02 Fe-59 1291.60 <6.223E-08 6E-05 <1.04E-03 Co-60 1332.73. 2.314E-07 4.933E-OS 3E-05 7.71E-03 Cu-64 1345.90 <T.699E-06 2E-04 <3.85E-02 Ha-24 1368.55 <2.94SE-08 3E-05 <9.83E-04 La-140 1596.60 <3.044E-08 2E-05 <1.52E-03 Mn-56 1811.00 <3.666E-08 1E-04 <3.67E-04 Sr-89 (EETA) <4.250E-09 3E-06 <1.42E-03 (EETA) <2.770E-09 3E-07 <9.23E-03 f

(LJ H-3"TSr-90 (EETA) 4.760E-04 4.800E-05 3E-03 1.59E-01 Fe-55 (EETA) <1.000E-06 SE-04 <1.25E-03 P-32 ( EC ) <1.000E-07 2E-05 <5.00E-03 Measured totals 4.784E-04 4.800E-05 3.98E+00 LLD totals <1.142E-05 <2.05E-01 Totals 4.599E-04 ,

, 4.19E+00 m .

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DISSOLVED GASES FIGUREl-2(CONT)

Xe-133 31.47 2.560E-06 1,266E-0? 4E-05 6.40E-02 !n Kr-SS 196.10 (7.293E-08 4E-05 < 1.82E-03 Xe-133m 233.18 <4.044E-07 4E-05 < 1.01E-02 f!

Xe-135 250.11 4.131E-06 7.966E-03 4E-05 1.03E-01 305.00 <1.965E-07 4E-05 (4.91E-03 !

('sKr-85m -

4E-05 <7.91E-04 (s/ Kr-87 402.70 <3.165E-08 '

4E-05 <3./3E-05 Xe-138 434.50 <1.493E-09 Me asured g as tot al s 6.691E-06 1.496E-07 1.67E-01 LLD gas tot al s <T.070E-07 *

<1.77E-02 Tot al g as 7.39&E-06 1.85E-01 I

1 GROSS ACTIVITY .

vol Het Error Counter Gross Background Time 1 Sigma Counts Counts (Min) mi Act i vity(cpm /ml) 2 2.27E+01 1.73e+e0 Hell Crys t al 2e60 1952 20.0 1.29E+00 402 265 10.0 2 6.85E+00 Pr opor t i on al gallons ESTIMATED WASTE TANK VOLUME = 11470.00 ESTIMATED ACTIVITY THIS EATCH ( 2.08E+04 ft:crocuries)

EXCLUDING GASES: 2.08E-02 Curies EXCLULING H-3 AHD GASES: 1.06E-04 Curies ( 1.06E+02 M croceries)

IS 106.31 UCURIES THE ACTIV'TY OF THIS ERTCH (EXCLUDING H-3 AHD GASES)

THE MAXIf1Ut1 YOU WANT TO RELEASE IS 100 uCi THEREF0F.E YOU NEED YOUR SUPERVISOR TO OK THIS RELEASE Liquid Radwaste Release Sumnaro

1) Meas, conc., excluding H-3 and dissolved gases (uC1/ml):: 4.78E-04 '

2.45E-06 +- 1.155-07

+- 4.SOE-05 t1e as . conc., including H-3, excluding gases

2) Cal c ui r.ed LLD c onc en'trat i on, excluding dissolved gases (uCi/ml): 1.14E-05 3)Calcul at ed f1PC rat io (C/MPC of meas.. including gases): 4.15E+00 4)llinimum dilution flow rate (gpm): 10000 5)M ax i raum t ank discharge flow rate (gpm): 3174 6)Specirted tank flou rate (gpm): 75 7)Raduaste raonitor trip setting: 568 B = 400 , Monitor PG CPS A = 9.14E-06 ,uct/mi F = 2 ,Conserv. F ac t or C-= 5910000.00 , Monitor CPS per uCi/mi A inctodes measured 's e l ec ted' . 'othe r' nuc l i de s and gas es but excludas:

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Sr-89, Sr-90, H-3, Fe-55, P-32 8)Es t imat ed conc. of me a2. nuclides at point of release (uCt/ml): 3.562E-06

9) Monitor maximum to ensure 100FR20 Ilmits are not exceeded: 1751

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--v-y- -,r r w .-yn +mm.,-

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FIGURE 1-2 (CONT)

. ESTIMATED DOSES THIS EATCH, MREM A

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Isotege W.Eody Bone Liver Thyroid Kidney Lung GI-LLI Xe-133 0.00E+00 0. r'0 E- 0 0 v.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-144 0.00E+00 0.e0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-99a. 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-85 0.00E+00 0.00E-00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 "Xe-133m 0.00E+00 0.00E-00 0.00E-00 0.00E,-00 0.00E+00 0.00E+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+00 0.00E+00 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 I-131 6.83E-07 8.33E-07 1.19E-06 3.90E-04 2.05E-06 0.00E+00 3.14E-07 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 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 W-187 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F-18 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-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 Cs-134 1.99E-04 1.02E-04 2.43E-04 0.00E+00 7.88E-05 2.61E-05 4.25E-06 Cs-137 8.96E-05 1.00E-04 1.37E-04 0.00E+00 4.65E-05 1.55E-05 2.65E-06 Ms-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 Zr-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

[)

'- Co-58 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 0.00E+00

Hn-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 2n-65 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 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-60 0.43E-07 0.00E-00 3.82E-07 0.00E+00 0.00E+00 0.00E+00 7.19E-06 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 Ha-24 0.00E+00 0.00E+00 0.00F.+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 n.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-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 2.04E-07 0.00E+00 2.04E-07 2.04E-07 2.04E-07 2.04E-07 2.04E-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 0.0*i+00 0.00E+00 0.00E+00 0.00E-00 Total 2.90E-04. 2.03E-04 3.81E-0, 3.91E-04 1.2SE-04 4.18E-05 1.46E-05 i

9 v

10

FIGURE 1-2 (C0 tit)

Cumul at i ve dose this YEAR (includes estimate Percent for this of Tech Spec batch):

Limit: 5.06E-01 Whole body 1.52E-02 mrem 1.19E-01 Percent of Tech Spec Limit:

I'D

\#

Eone 1.18E-02 mrem Perce; t of Tech Spec L:mit: 2.07E-01 Liver 2.07'E-02 mrem 4.73E-01 4.73E-02 mrem Perces., of Tech Spec Ldmit:

Thyroid Percent of Tech Spec Limit: 7.26E-02 Kidney 7.26E-03 mrem- 2.25E-02 2.25E-03 mrem Percent of Tech Spec Limit:

Lung 2.49E-02 2.49E-03 mrem Percent of Tech Spec Ltmit*

GI-LLI Cumulative dose this GUARTER (includes estimate for this batch): 5.32E-01 Percent of Tech Spec L mit:

Hhole body 7.99E-03 mrem 1.22E-01 5

6.12E-03 meem Percent of Tech Spec L'mit:

Eone Percent of Tech Spec Limit: 2.17E-01 Liver 1.08E-02 mrem 3.79E-01 1.89E-02 meem Percent of Tech Spec L'mit:

Thyroid Percent of Tech Spec L mit: 7.55E-02 Kidney 3.77E-03 orem 2.35E-02 1.17E-03 mrem Percent of Tech Spec L mit:

Lung Percent of Tech Spec L mit: 1.43E-01 GI-LLI 7.15E-04 prem Project ed cumul ative dose t his OUARTER (includes estimate for this batch)*

Whole body 8.97E-03 mrem Fone 6.87E-03.meem ,

Liver 1.22E-02 mrem Thyroid 2.13E-02 meera Kidnsy 4.24E-03 mrem Lung 1.32E-03 n,reN ,

GI-LLI 8.03E-04 mrem Cumulative neasured activity thi s YEAR (inc ludes est imate for this batch):

N 4.503E-02 Curies, excluding H-3 and dissolved gases

_.)

EATCH# 322 DATA SUCCESSFULLY STORED SPECTRUff STORED AS: LPH1 t

l l

O) m 11

. - . , .. . .

W' '9v=ve r e ,.g,,, _,

FIGURE l-3 i REVIS!0H: 7 DRTA SHEET 8 PROCEDURE: HHP-7601 ocococe*ococcooooooc*****oedoo*oooosexoooosooooo

E. I. Hatch Huclear Plant

. Liquid Raduaste Analysis

~m 4,***********+,****+*******+++************es***

Estcht 302 Resctcr# 2 Recire time: 145 m nutes T ank

FLS 2 Comsent: HIGH TURE. 5 FIL SOL 6/13/80 0940 6/13/80 1043 Count start date:

Run date: Clock t i rn e " 3000 secs

Sauple vo*ume: 1000.00 al Live t i r.ie : 3000 secs Gc os..e t r y c od e : ILFP-0 MCA# 1 a Detector # 1 Oper at or: tisit Libescy: LRulL2 Energy (kevy. , ,2c + 1.000-Che + 0.000E+00-Che'2 4 0.000E+00+Ch#-3 : 06'13'i0 <C4

+ 521.263

E^(9.526:E-01>3 06/1*'iO 01 0 Ef- = 1/1L.601E-02

E^(-2.=9e0E+00:.

Uhsre E: E ni r g'! i n flG V.

EPP0F f1PC .C 'iPC 160TecE E t E P G'. 00140 E N T N T I O!!

n e ;> s C i e.i s <ucieml) (uCi nel %

m dru======u=n===========u--==== ===________-_=========..===============

<2.605E-97 1E-05 <2.60E-02 Ce-144 133.50 <1.09E-05

< 3. 2 6.: E-08 3E-03 Tc -994 140.50 9E-05 <6.61E-04 Ce-141 145.40 <5.94?E-3C

<2.475E-07 1E-04 <2.4SE-03 e' lip-217 277.90 <1.43E-04 2E-03

( ,'

Cr-51 320.10 <2.360E-07 (4.207E-08 3E-07 <1.40E-01 Ar131 364.50 438.70 <3.092E-38 6E-05 <5.15E-04 Zn-69.4 CE-05 <2.01E-03 H-137 47's.50 <1.205E-37

<3.935E-38 SE-04 <?.6SE-05 F - 13 511.10 <3.06E-02

<3.064E-08 1E-06 1-133 529.50 2E-05 <6.03E-0?

Ea-140 537.40 <1.206E-37 559.30 <6.S76E-38 2E-05 <3.44E-03 As-76 9E-06 1.SOE-02 Cs-134 604.47 1.620E-07 3.850E-03 3.041E-07 4.16SE-08 2E-05 1.52E-02 Cc-137 661.34 4E-05 <5.15E-03 tio-99 739.70 <2.06;E-07 743.50 <2.771E-33 2E-05 < 1. 3.9 E - 0 3 Zr-97 6E-05 <9.37E-04 Zr-95 756.90 <5.623E-03 <3.75E-04 765.?O <3.752E-08 1E-04 Hb-95 SE-06 <5.03E-03 I-132 772.60 (4.022E-08

<2.91TE-OS 9E-05 <3.24E-04 Co-50 010.60 1E-04 <3.36E-04 Mn-54 834.80 <3.383E-09 <1.67E-03 894.T0 <5.019E-36 3E-05 As - 1 10iu (6.567E-OS 1E-04 <6.57E-04 2n-65 1115.40 <1.7?E-02 1260.50 <7.ce2E-38 4E-06 1-135 6E-05 <1.37E-0?

Fe-5? 12o1'.00 (8.235E-OS 5.91E-03 1332.26 1.773E-07 4.045E-03 3E-05 Co-40 2E-04 <2453E-02 Cu-64 1345.90 <5.056E-06 1360.55 <2.773E-08 3E-05 <9.24E-04 Ha-24 2E-05 <1.??E-03 La-140 1596.60 <3.745E-OS (9.35E-04 1811.00 <9.350E-03 1E-04 lin-56

<3.950E-09 3E-06 <1.32E-03 I_'

Sr-39 (PETA)

<2.650E-09 3E-07 <8.83E-03 Sr-90 (PETA) 1.66E-01

<EETA> - 4.980E-04 5.000E-05 3E-03 H-3 SE-04 1.75E-03 Fe-55 <EETA) 1.400E-06 9.000E-07

<5.00E-03

< EC ) <1.000E-37 2E-05 P-32 ----- ---------

5.000E-04 5.001E-05 2.07E-01 tieasured tot al s <2.91E-01 LLD tot als (7.360E-06 5.074E-04 4.93E-01 Totals .

to

DISSOLVED GASES FIGURE 1-3(CONT) 4E-05 <2.43E-03 ,

Xe-133 80.99 (9.712E-08 4E-05 <1.63E-03 4

Kr-88 196.10 <6.525E-03 4E-05 <7.11E-03 l Xe - 13?ri 233.18 <2.844E-07 4E-05 <7.32E-04 Xe-135 249.60 <2.929E-08 4E-05 <4.47E-03

/'S Kr-05m 305.00 (1.785E-07 .

4E-05 <1.19E-02

(_/ Kr-87 402.70 <4.75SE-08 4E-05 <4.46E-04 Xe-138 434.50 (1.783E-03 --------- ----- .--- ----

0.00E+00 Heasured g as t ot hi s 0.000E+00 0.000E+00 <1.60E-02 LLD gas tot als <7.203E-07 1.80E-02 T o t. a1 gas 7.203E-07 GPOSS 9CTIVITY E rt- w Cr: Is Eic n ground Ttrue V :e l Het, 1 S ' 7 h ",

Ac t a u t t y(c pM'fal >

c~ o u n t .t r ml g x.n v. s C un'.s (fli n ) - ..---- --------

....----- _-_ <5.14E+00 1965 20.0 2

. uvil cr ys+ al 1922 Proport i on al 6085 205 10.0 2 2.94E+02 5.9FE406 ESTIIIATEL 4ASTE T6HK VOLUME = 9744.00 gallons ESTIf18TEC ACTIVITY THIS EATCH 1.84E-02 Curies ( 1.84E+04 Hicrocuries)

E7.CLUDING GASES:

EXCLU?!NG H-3 AND GASES: 7.54E-05 Curies ( 7.54E+01 H crocuries)

C:)

L i c;u i d R-s dia a s t e Rel e ase S u r. m ary 1)Meus. conc., excluding H-3 and dissolved gases (uCi/ml): 2.04E-06 +- 9.03E-07 Heas. conc., including H-3, excluding gases : 5.00E-04.+- 5.00E-05

2) Calculated LLP concentektion, excluding dissolved gases (uCi/mi): 7.36E-06 3)Calcui n' ed NPC r st t o (C/MPC of .ieas. ,inc ludi ng g ase s): 2.07E-01 4 )!11 n i m u..) dilution flow rat e (gpm): 10000 5)t:Ex truuta tank d i s c h ar g e flou rate-(gpm): 46824 6)Specified tsnk flow rate ( gp:a): 75 7)R ad.eas s e r.ioni t or t r i p set t i ng: 317 A = 6.43E-07 ,uct/ml B = 220 .Monttor EG CPS C = 41190000.00 . Monitor CPS per uCi/rul F=2 ,Conserv. F ac t or A includes measured ' selected','other' nuclides and gases but excludes:

Sr-39, Sr-90, H-3, Fe-55, P-32

~

8)Est imated conc. of meas. nuclidts at point of release (uCi/ml): 3.722E-06

() 9)ttonitor 'n ax i tau a to ensure 100FR20 limits are not exceeded: 17209 5

- 13

I FIGURE l-3 (COMT)

ESTIKATED DOSES THIS BATCH, NREM Kidney Lung GI-LLI H. Body Bone Liver Thyroid Isotope 0.00E+00 0.00E+00 0.00E+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 0.00E+00 Ce-144 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 0.00 +00-() 0.00E+00 0.00E+00 0.00E+00 0.00E+00 s./ Ce-141 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 Kr-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xc-133a 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 Mc-135 0.00E+00 0.00E+00 0.00E+00 Hp-239 0.00E+00 0.00E+00 0.00E+00 0.00E"00 0.00E+00 0.00E-00 0.00E+00 0.00E+00 Mr-05: 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00C+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 0.00E+00 0.00E-00 0.00E+02 1-151 0.00E+00 0.0GE+0C 0.00E^OO 0.00E*00 0.00Eu?0 0.00E+00 0.00E+00 0.00E+00 0.00E'00 Kr-07 0.00E+00 0.00E-00 0.00E-00 0.00E+00 0.005:00 0.00E+0C 0.00E+00 0.00E+00 0.00E+00 0.00E*00 X9-135 0.00E+00 0.00E'00 0.00E+00 0.00E-00 Z r. - 6 .%. a.00E+00 0.00E'+30 0.00E+00 0.00E-00 0.00E+00 H-137 G.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 F-18 0.00E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00

'e

31 *).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 EL-140 0.00E+00 0.00E-00 O.00E+00 0.00E400

'"~'

0.00E+00 0.00E+00 .0.00E+00 0.00E+00 0.00E+00'

2-76 1.74E-05 5.77E-06 9.3SE-07 Cs-134 4.39E-05 2.26E-05 5.26E-05 0.00E+00 1.44E-06 5.44E-05 7.41E-05 0.00E+00 2.52E-05 8.3ee-06 C5-137 4.e5E-05 0.00E+00 0.00E+00 0.00E+00 Ho-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00Ev00 0.00E+00 2r-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 0.00E+00 0.00E+00 0.00E+00' O.00E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00Ev00 Hb-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4r132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00Ev00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-53 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E*00 Ag-110s. 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 2n-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 fg 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00

(,) I-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0. 00E4 00 0.00E+00 0.00E+00 0.00E+00 Ft-59 2.49E-07 0.00E+00 0.00E+00 =0.00E+00 4.6?E-06 Co-60 5.49E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0c ,

Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.00E+00 0.00E+00 Na-24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0C 0.00E-00 La-140 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 0.00E+00 0.00E+00 0.00E+00 Sr-39 0.00E+00 0.00E+00 0.00E'00 0.00E-00 0.00Ee00 Sr-90 0.00E+00 0.00E+00 1.s2E-07 1.82E-07 0.00E-00 1.82E-07 1.82E-07 1.82E-07 1.e e-07 H-3 0.00E+00 0.00E+00 3.44E-08 3.5 E-08 Fe-55 1.44E-08 8.91E-08 6.16E-OS 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E*00 P-52 0.00E+00 - -- ----- -------- --- ---- -------- --- ----

1.23E-04 1.82E-07 4.28E-05 1.44E-05 T.25E-06 Tot al 9.31E-05 7.71E-05 g

O 14

9 FIGURE 1-3(CONT)

Cumulative dose this YEAR (includes estimate Percent for this of Tech batch):

Spec Limit: 2.66E-02 Whole bocy 7.99E-04 mrew Percent of Tech Spec Limit: 5.30E-03

.() Eone Liver 5.30E-04 meen 1.29E-0? mrem Percent of Tech Spec Limit:

Percent of Tech Spec Limit:

1.29E-32 1.29E-02 Thyroid 1.29E-03 erem . 6.?2E-03 Kidney 6.92E-04 mrem. Percent of Tech Spec Limit!

Lung 1.00E-04 meca Percent of Tech Spec Limit: 1.00E-03 GI-LLI 1.45E-03 mrem Percent of Tech Spec Limit: 1.45E-02 Cuuul at ive dos e this GURPTER (includes Percentest of f uate TechforSpec St.i sLimit bat ch): 1.93E-02 Whole body 2.83E-04 neem 1.86E-04 meen Percent of Tech Spec Limit: 3.72E-03 Eone Liver 4.66E-04 oceu Percent of Tech Spec Limit: 9.32E-03 4.44E-C4 orem Percent of Tech Spec Limit: 8. 6?E- 03 Thyroid Kidnay 2.43E-04 meen Percent of Tech Spec Limit: 4.96E-03 3.35E-e5 meeu Percent of Tech Spec timit: 6.7eE-04 Lung

'4.56E-04 mrem Percent of Tech Spec Limit: 9.10E-05 GI-LLI Projected :umul at i ve dose this CUARTER <inc ludes est imate (cr this bat ch):

Whole body 3.55E-04 mrem Eone 2.29E-04 mrem Liver 5.73E-04 wrem Thyrcid 5.47E-04 mrem -

Kidnev 3.05E-04 mren Lung 4.12E-05 mrem .

GI-LLI 5.61E-04 mreu Cumulative ut aI'v e d a:t ivi ty this YEnR (includes' estimate for this b at :h):

2.414E-02 Curies. e:<clucing H-3 and cissolved gases PATCH # 302 DATR Se0CEliFULLi STO~ED SPECTEUit CTCRED 65: LF d O .

15

T 9

l FIGURE l-4 l PLANT E.I. HATCH BATCH NO. 1

( LIQUID H ADW ASTE DISCH ARGE PERMIT UNIT f l l

TANK TO DE RELEASED DATE !

REASON FOR NECESSITY OF DISCHANGE RECIRC. START TIMS .. SAMPLE TIME RECIRC. DURATION MINUTES I. LABORATORT ANALYSIS

~

(1) MSASUR ED R ADIONUCLIDE CONCE9TR ATION .E +

~

.E uCi/s1 .

(2) CALCULATED LLD LIMIT CONCENTRATIONS uCi/at (3) CALCULATED MR RATIO: E (C1/MPC1)

(4). MINIMUM DILUTION FLOW RATE GPM (5) MAX. CALCULATED TANK DISCHARdE RATE: DIEE SEC. F.4.c) GPM (6) SPECIFIED TANK DISCHARGE RATE: < (5)/2 GPM (7) RADVASTE MONITOR TRIP SETTING:- CPS A = Ge(Li)(11 uCi/n1 B = MONITOR BG CPS C = MONITOR CPS F = CONSERVATIVE PER Ge(Li) uC1/nl FACTOR 3 MONITOR ALARM SETPOINT TCPET = (C I A I F) + 7: U7T-l COMPLETED BT DATE

! COMPOSITE LITER STORED TINITIALS) 'APPR0vED ar (S) R ADWASTE MONITOR MAI. CPS TO BE WITHIN 10 CFR 20 LIMITS:

CIAI (6)+(4) )

TFT TIT ____ eps

-I OPERAM Ofis -

b '

INIT.

(9) LIQUID RADVASTE MONITOR TRIP SET AT: CPS ~

(10) CONFIRMED DILUTION FLOV RATE GPM i

(11) VALVE LINEUP CHECKED AS PER HNP.

TANK DIS. INTEGRATdR DIS. RATE DIL. TLTAL RIVER EL. M0!ilf6@

__ DATE_ TIME LEVEL -t RDKG. GPM GAL FT. C P 1__l

, TART _,

RND ** i

, . _ . _ . . . . . . - _ . . . . . . <........., i COMPLETED BT DATE MIN. GAL.

~

DURATION TOTAL RELEASE < ----------------------------+

6 10 MIN AFTER START

AFTER FLUSHING l a l f III.LABORATORT !

(12) TOTAL TANK VOLUME DISCHARGED GAL. I 1,735 31

! (ll) TOTAL ACTIVITY DISCHARGED (11 I (12) uCi (14) RIVER FLOW RATE (FROM FSAR'2.4-6) CFS CCMPLETED BY DATE

, . APPROVED BT 16 .

-m .+-----~..,m---+~w~ ~- g- s-- , - -,- ,- w -.,rr e--,e-m,e . - - g,-w, ----,e. -.r.,-ww,,r,--- c o men: , e A n - s-

FIGURE l-Sa e

Liquid Raduaste Data Compil ation for Reg. Guide 1.21 Report E. I. Hatch Huclear Plant UNIT 1

(~1 -

\2 Tot al Activity (Curies)

Quarter 1, 1980 Quarter 2, 1980 Batches 1 thru 217 Batches 218 thru 334 Hame fleasured Errer .High LLDs Tot al Measured Error High LLDS Tot al Cc-144 U.33E-04 7.23E-05 1.19E-04 6.52E-04 1.16E-05 7.41E-06 0.00E+00 1.16E-05 Tc-99m 4.00E-04 7.73E-06

4.00E-04 1.98E-04 6.14E-06

1.98E-04 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00.0.00E+00 Np-239 0.00E+00 0.00E+00

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

0.00E+00 Cr-51 9.86E-04 4.91E-05

9.86E-04 4.60E-04 3.78E-05 *. 4.60E-04 I-131 4.67E-03 2.24E-05 0.00E+00 4.67E-03 4.45E-03 2.26E-05 0.00E+00 4.45E-03 Zn-69m 0.00E+00 0.00E+00

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

0.00E+00 H-107 2.02E-05 4.74E-06

2.02E-05 0.00E+00 0.00E+00

0.00E+00 F-18 6.74E-04 7.95E-06

6.74E-04 6.29E-04 7.86E-06

6.29E-04 I-133 7.87E-04 1.16E-05

7.87E-04 4.20E-04 9.17E-06

4.20E-04 Es-140 0.00E+00 0.00E+00

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

0.00E+00 As-76 3.79E-05 4.75E-06

3.79E-05 2.90E-05 4.39E-06

2.90E-05 Cs-134 6.42E-04 1.01E-05 0.00E+00 6.42E-04 1.21E-03 1.5(E-05 0.00E+00 1.21E-03 Cs-137 9.30E-04 1.32E-05 0.00E+00 9.30E-04 1.44E-03 1.68Ecp5 0.00E+00 1.44E-03 Ho-99 6.46E-05 1.64E-05 0.00E+00.6.46E-05 8.5SE-05 1.74E-05 0.00E+00 8.58E-05 Zr-97 0.00E+00 0.00E+00

0.00E+00 0.00E+00 0.00E+00 + 0.00E+00 Zr-95 8.36E-06 1.97E-06

9.36E-06 0.00E+00 0.00E+00

0.00E+00 Hb-95 1.24E-05 1.85E-06

1.24E-05 7.04E-06 1.62E-06

7.04E-06 I-132 0.00E+00 0.00E+00

0.00E+00 0.00Z+00 0.00E+00

0.00E+00 Co-53 3.09E-05 3.34E-06 0.00E+00 3.09E-05 2.46E-05 2.7?E-06 0.00E+00 2.46E-05 7'} Hn-54 2.!SE-05 2.64E-06 0.00E+00 2.18E-05 1.03E-05 1.70E-06 0.00E+00 1.03E-05

(- Ag-110m 2.69E-05 ?.35E-06

2.69E-05 2.25E-06 7.56E-07

2.25E-06 Zn-65 6.00E-04 2.11E-05 0.00E+00 6.00E-04 7.40E-04 2.1;E-05 0.00E+00 7.40E-04 I-135 4.00E-05 5.22E-06

4.00E-05 2.42E-06 1.2?E-06

2.42E-06 Fe-59 4.61E-06 2.1?E-06 0.00E+00 4.61E-06 9.63E-06 2.52E-06 0.00E+00 9.63E-06 Co-60 1.25E-03 2.02E-05 0.00E+00 1.25E-03 7.21E-04 1.5;E-05 0.00E+00 7.21E-04 Cu-64 6.20E-03 5.??E-04

6.20E-03 0.00E+00 0.00E+00

0.00E+00 11 a-24 2.41E-06 1.12E-06

2.41E-06 0.00E+00 0.00E+00

0.00E+00 La-140 0.00E+00 0.00E+00

0.00E+00 5.82E-06 1.5?E-06

5.82E-06 Mn-56 0.00E+00 0.00E+00

0.00E+00 0.00E+00 0'.00E+00

0.00E+00 Hi-65 3.76E-06 1.65E-06

3.76E-06 1.10E-05 3.10E-06

1.10E-05 Hb-97 3.0SE-06 9.51E-07

3.08E-06 0.00E+00 0.00E+00

0.00E+00 Cs-136 7.60E-05 4.34E-06

7.60E-05 5.45E-05 4.10E-06 '

5.45E-05 Tc-104 3.98E-06 0.00E+00

3.98E-06 0.00E+00 0.00E+00

O.00E+00 Rb-98 2.25E-06 7.35E-07

2.25E-06 2.03E-05 5.7?E-07

2.03E-05 Sr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-55 2.75E-02 3.39E-03 0.00E+00 1.75E-02 3.85E-03 1.37E-03 7.10E-03 1.10E-02 P-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot al s 3.56E-02 3.93E-03 1.1?E-04 3.57E-02 1.44E-02 1.37E-03 7.10E-03 2.15E-02 Me-133 9.23E-02 1.15E-04 0. 0 0E+ 00 9. 23E-02 2. 04 E-02 6. 66E-05 0. 00E+ 00 2. 04 E-02 Kr-SS 1.82E-05 3.26E-06 0.00E+00 1.82E-05 0.00E+00 0.00E+00 0.00E+00 0.00E-00 Xc 133m 2.3GE-03 f.39E-05 0.03E+00 2.?SE-03 1.12E-04 1.4;E-05 0.00E+00 1.12E-04 f- Xe-135 S.34E-02 4.79E-05 0.00E+00 5.34E-02 1.81E-02 3.0;E-05 0.00E+00 1.91E-02

( )s Vr-S5m 8.61E-06 1.45E-06 0.00E+00 8.61E-06 0.00E+00 0.00E+00 0.00E+00 0.00E-00 Kr-87 1.?JE-05 2.94E-06 0.00Et00 1.76E-05 0.00E+00 0.00E+00 0.00E-00 0.00E-00 Xe-139 0.00E+00 0.00E+00 0.30E+00 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

.Xe-131m 1.76E 5.3?E-05 0.0:Ee00 1.76E-04 5.35E-03 2.04E-04 0.00E+00 5.35E-03 Tot al s 1.4GE-01 1.53E-04 0.00E+00 1.48E-01 4.39E-02 2.17E-04 0.00E+00 4.39E-02 17

FIGURE l-Sb Liquid Radwast e D'at a Corapi t ation for Reg. Guid2 1.21 Raport E. I. H at c h Huc l e ar P l ant UNIT 2

~N Total Activity (Curies)

Quarter 1, 1980 Quarter 2, 1980 B at :he s 1 thru 196 Eatches 197 t hru 331 Hame Measured Error High LLD Tot al Measured Error High LLD Tot a!

Ce-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0L Tc-99u. 2 35E-05 i.56E-07 + 1.35E-05 0.00E+00 0.00E+00

0.00E+06 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0e Up-239 0.00E+00 0.00E+00

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

0.00E+00 Cr-51 9.53E-04 3.66E-05

9.53E-04 1.25E-05 6.09E-06 E 1.25E-05 I-131 1.3GE-04 5.06E-06 0.00E+00 1.38E-04 1.1SE-04 4.70E-06 0.00E+00 1.18E-G4 2n-69to 0.00E+00 0.00E+00

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

0.00E+00 H-187 H.00E+00 0.00E+00

0.00E+00 7.12E-06 2.92E-06

7.52E-06 F-16 6.89E-05 2.69E-06

6.S9E-05 5.87E-05 2.17E-06

5.57E-05 I-133 U.26E-06 1.12E-06

5.26E-06 4.63E-06 8.2;E-07

4.63E-06 Ba-140 0.00E+00 0.00E+00

O.00E-00 0.00E+00 0.00E+00

0.00E+00 As-76 2.84E-05 3.93E-06

1.84E-05 1.02E-05 1.92E-06

1.02E-05 Cc-134 1.29E-05 1.3?E-06 0.00E+00 1.29E-05 1.84E-05 2.33E-06 0.00E+00 1.24E-05 Cs-137 3.97E-05 3.22E-06 0.00E+00 3.87E-05 2.79E-05 2.53E-06 0.00E+00 2.79E-05 Mo-99 0.00E+00 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 2r-95 3.80E-05 4.16E-06 + 3.80E-05 0.00E+00 0.00E+00

0.00E-00 Hb-95 1.24E-04 5.73E-06 * ,

1.24E-04 1.11E-05 1.74E-06

1.11E*-05 I-132 0.00E+00 0.00E+00

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

0.00E+00 Co-58 9.3SE-04 1.14E-05 0.00E+00 9.3SE-04 3.54E-04 7.22E-06 0.00E+00 3.54E-04 Mn-54 7.41E-05 4.13E-06 0.00E+00 7.41E-05 3.93E-05 3.i?E-06 0.00E+00 3.93E-05 r^ sag-110ta 0.00E+00 0.'00E+00

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

0.00E+00 k J2n-65 2.26E-03 2.34E-05 0.00E+00 1.26E-03 9.01E-04 1.98E-05 0.00E+00 ?.01E-04 I-135 1.4SE-05 3.51E-06 + 1.4SE-05 0.00E+00 0.00E+00

O.00E+00 Fe-59 7.31E-06 1.22E-06 0.00E+00 7.31E-06 3.69E-06 1.44E-06 0.00E+00 3.69E-06 Co-60 7.32E-04 1.46E-05 0.03E+00 7.32E-04~4.62E-04 1.14E-05 0.00E+00 4.62E-04 Cu-64 0.00E+00 0.00E+00

O.00E+00 0.00E+00 0.00E+00

0.00E+00 Ha-24 J.04E-04 1.15E-06 *. 1.04E-04 2.71E-04 5.69E-06

2.71E-04 La-140 0.00E+00 0.00E+00

0.00E+00 0.00E+00 0.00E+00 + 0.00E-00 Mn-56 U.06E-06 2.5SE-06

5.06E-06 0.00E+00 6.00E+00

0.00E-C0 Cs-156 5.35E-06 1.14E-06 + 5.35E-06 0.00E+00 0.00Ee00

0.00E-00 Hi-65 8.51E-06 3.51E-06

8.51E-06 0.00E+00 0.00E+00 + 0.00E+00 RP-SS 1.21E-05 1.55E-0? + 1.21E-05 2.62E-05 3.70E-06

2.61E-05 Cs-136 0.00E+00 0.00E+00

0.00E+00 2.01E-05 0.00E-00

2.01E-05 0.00E+00 9.49E-07 5.31E-07 + 9.49E-07 Hb-97 0.00E+00 0.00E+00 +

Sr-89 0.00E+00 0.00E-00 0.03E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 i Fe-55 3.29E-02 3.?3E-03 0.0?E+00 1.29E-02 2.59E-03 1.23E-03 f.2iE-03 8.!!E-0?

I P-32 0.00E+00 0.00E+0C 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot al s 1.74E-02 3.93E-01 0.00E+00 1.74E-02 4.93E-03 1.20E-03 6.22E-03 1.12E-02 Xs-132 U.03E-03 4.57E-05 0.00E+00 5.03E-03 3.11E-03 2.82E-05 0.00E+00 ?.11E-03 Mr-83 0.00E-00 0.00E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 Xe - 13 I r.. 2.00E-05 1.0?E-05 0.00E-00 2.00E-05 1.59E-05 5.00E-06 0.00E-00 1.59E-05 Ne-135 2.42E-Oi 1.24E-a! 0.0?E-00 2.43E-03 1.43E '? 8.54E-06 0.00E+00 1.43E-0?

Mr- 85*. 0.00E-00 . 00E+00 0.00E*00 0.00E*00 0.00E. . 0.00E+00 0.00E+00 0.00E-00 Gr 87 0.00E*00 0.00E+00 0.00E-00 0.00E+00 0.00E+00 0.0aE+00 0.00E+00 0.00E-00 Xt-l?5 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E*00

. Tota 12 7. 4?E-0 3 4. ?6E- 3! 0. 0 ?E*00 7. 4?C-0 ? 4. 56E-0 ? 2. 94E-05 0. 00E-00

4. SiE-0 3 18

1 TABLE l-la O

V E. I. Hatch Huclear Pl ant UNIT 1 EFFLUEHT AND WASTE DISPOSAL SEtIIANNUAL REPORT 1980 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Total 1 2 Error %

A. Fission & act iuat ion produc t s

1. Tota' release (not including H3,

/ g as e s , a l p h.a) Ci 3.56E-02 1.44E-02 5.13E+01

2. Average diluted concentr& tion during period uCi/ml 2.43E-00 1.48E-OS

3. Percent of ap o l i c at. l e limit % 1.14E+00 1.59E+00 B. Tritium

1. Tota' re l e ase Ci 3.56E+00 3.56E+00 4.11E-01!

, 2. Average diluted ccncentration during period uCi/ml 2.43E-06 3.65E-06

3. Percent of apolicable' limit *: 8.11E-02l 1. 22E-01 C. Disso'ved and entrained gases

1. Tota' release C1 1.40E-01 4.39E-02 1.01E*0iT

2. Average diluted concentration

during period uCi/ml 1.01E-07 4.51E-09

3. Perce_nt of applicable limit % 2.54E-0; 1.13E-01 D. Gross alpha radioact ivi ty l 1. Tot a' release l Ci l 6.06E-06l 1.40E-06l 1.20E+021 r

lE. Volum.e of waste (prior to dilution)) liters l 8.96E+06l 4.79E+06l 1.00E+011 l

lF. Volum.t of dilutten w at e r used I liters l 1.45E+09l 9.69E+081 1.60E+02(

l a'

(:) -

I l

19 i .

N

TABLE .1-lb . -

("%

(_) . E. I. Hatch Huc le ar Plant UNIT 2 EFFLUENT AND HA3TE DISPOSAL SENIAHHUAL REPORT 1980

. LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Tot al 1 2 Er ror *:

A. Fission & activation products l 1. Tota' release (not. including H3, l c.ases . al ph a) Ci 1.74E-02 4.93E-03 6.44E+01_I

2. Average diluted concentration durina period uCi/mi 1.35E-08 4.80E-09

3. Percent or applic able limit % S.90E-02 1.71E-01

2. Tritium

1. Tota' release C1 3.91E+00 1.47E+00 4.07E+01i

2. Average diluted concentration during period uCi/ml 3.02E-06 1.44E-06

3. Percent of applicable limit % 1.01E-0; 4.79E-02 C. Disso'ved and entrained gases A)

(_ 1. Tota' release Ci 7.4SE-03 4.56E-03 1.01E+02l

2. Averrge diluted concentration during period uCi/mi 5.7?E-09 4.44E-09

3. P e r c e n t. or apolic able l i ra i t % 1.45E-02 1.11E-02

+ D. Gross al ph a radi oac t i vi ti.'

l 1. Tota' re l e as e l Ci l 7.55E-06l 4.25E-06l 1.20E+02!

l lE. Vclume of oaste (pr i or to dilution)l liters l 6.75E+06l 4.34E+06l 1.00E+01 1 l

l lF. Volunir or dilitton uster used I liters l 1.29E+09l 1.02E+09l 1.60E+01!

I I

l I

'A 20

+ TABLE l-2a E. I. Hatch Huclear Plant UNIT

(~h EFFLUE!4T AHD WA3TE DISPOSAL SEMI ANNUAL REPORT 1980 wu/

LIQUID EFFLUENTS COHT!HUOUS t10DE EATCH MODE Unit Guarter Qu art er Qu ar t e r Qu ar t e r iluc t i<fes Released 2 1 2 1 ~

Cc-144 Ci 5.33E-04 1. l f E-05]

Ci _4.00E-04 1.98E-04i Tc -99:n ). _

0.00E+001 Ci 1 0.00E+00 Ce-141 Ci T, 0.00E+DO O.00E+001 fip-239 Ci j_ 9.86E-04 c.f0E-041 Cr-51 c.45E-03l Ci i 4.67E-03 1-131 2 n - 6 9 ti. Ci 0.00E+00i 0.00E+0_04 C1 2.02E-05 0.00E+001 j 11-187 Ci 6.74E-04 6.2?E-04!

F-18 e.20E-04i Ci 7.87E-04 I-133 fa-140 Ci 0.00E+00: 0.00E+001 Ci 3.79E-05i 2.90E-051 As-76 1.21E-031 Ci ' 6. 4 2E-04 Cs-134 Cs-137 Ci 9.30E-04 1.44E-Oll No-99 Ci 6.46E-05 8.5BE-05l C1 0.00E400 0.00E+001 Zr-97 0.00E+001 C1 8.36E-06 2r-95 7. 0 4 E- 0 6,1 Ci 1.24E-05 tib-95 Ct 0.00E+00 0.00E+00:

I-132 2.46E-05l Ci 3.09E-05 Co-SS .

] g-~ ,

tin-54 Ci 2.18E.-05 1.03E-05t Ag-110ro Ci 2.69E-05 2.25E-06]

Ci 6.00E-04 7.40E-04:

Zn-65 1-135 Ci 4.00E-05) 2.42E-06l Fe-59 Ci 4,61E-061 9.63E-061 Co-60 Ci l'. 2 5 E - 0 3 7.21E-04[

l Ci 6.20E-03 0.00E+001 Cu-64 2.41E-06 0.00E+00I C l fla-24 La-140 Ci 0.00E+001 5.32E-Oit

.t tin-56 Ci 0.00E+006 0.00E+00!

ti t -65 C 3.76E-Oil 1.10E-05) tib-9 7 Cs 3.08E-061 0.00E+00L Cr-136 Ci 7.60E-05! *.45E-05 Tc-104 C 3.98E-Oil O.00E+00_

C 2.25E-06 2. ? ? E -0_5_i_

Rb-SS 0.00E+00 0.00E+00j Sr-89 Ci Ci i 0.00E+00 0.C3E+001 Sr-90

~

Cs i 1.75E-02. '. 35E-0 3 t Fe-55 0.00E+001 0.00E+00i P-32 Ci l Tet al for per sd ( at.c o a ) l Ci l l l 3.56E-02! 1.44E-02i l

i Ci l 9.23E-02' 2I?JE-021 xe-t?3 1.SIE-05 0. 0 0 E - 0 0 i_

i:r-S3 C:

2.3SE-0?' l.12E-04)

[ Se-133%

Me-135 Ci C

i 5.34E-02 S.61E-06 1.i1E-021 0.00E+001 Kr-65r l C:

Kr-67 l Ci 1.76E-051 0.30E+00)

.44-1?S i C ) 0.00E+00i 0.00E*00 C I i 1.7iE-041 5. ?5E-0 ? ,44-131 !

21

, TABLE l-2b E. I. Hatch flucle ar Plant UllIT 2 LFFLUEllT 5 TID 11ASTE DISPOSAL SE!!I AlltlUAL P.EPORT 1980 1

LIQUID EFFLUErlTS C0tlTItlUOUS l10DE EATCH l10 rE 11uc l iif e Reisered Unit Quarter Quarter Quarter Guarter 1 2 1 2 Cc-14: Ci 0.00E+00 0.00E+00 T c - 9 9 r.. Ci 1.35E-OL O.00E+00 Ce-141 Ci 0.00E+00l 0.00E+001 tip-239 l Ci 0.00E+00l 0.00E+001 Cr-51 Ci 9.53E-04! 1.25E-05[

I-131 Ci 1.36E-04l 1.1.!F.-04 !

Zn-69n. C1 l 0.00E+00] 0.00Et001 11-187 Ci f 0.00E+00l !.IIE-06 F- 1 s: Ci 6.89E-05l 5.97E-05; I-133 Ci 5.26E-06. *. 6?E-06 Ps-140 Ci 0.00E+00 0.00E+00 Ar-76 i C1 1.84E-05 1.02E-05 C2-134 i Ci 7.19E-05 1.84E-051 C3-137 i C1 3.87E-05 2.79E-05i tto-99 Ci i O.00E+00 0.00E+00_[

~Zr-97 Ci 0. 00E + 00 ! O. ;0E +00 f 2r-95 C1 3.80E-051 0.00E+006 ti t. - 9 5 C1 1.24E-0Jl 1.11E-OSI 1-132 Ci 0.00E+00 0.00E+001 C o - 5 :E Ci 9.3EE-04 ' . 5 4 E - 0.iT (7 f:n-54 C1 7.41E-05 J . ? 3 E - O 'i Es' Ag-11an Ci 0.00E+00l 0.00E+00 2n-65 C1 1.26E-03 9.01E-04 I-135 Ci 1.48E-05 0.00E+001 Fe-59 Ci 7.31E-061 3.69E-06!

Co-60 Ci 7.32E-04' c. 61E-0 E C o -- 6 4 Ci 0.00E+001 0.00E+00l

~

il5-24 Ci 1.04E-04i 2.~1E-04t La-140 Ci 0.00E+001 0.00E-001 tin-56 Ci 5.06E-06l 0.00E+00i C .s - 1 ? 6 Ci '

5.35E-061 0.00E+00)

- rii - 6 5 Ci 8.51E-06! 0.6 OE+001 P I: i - Ci 1.21E-05 -2.62E-05l Cs-135 Ci 0.00E+00 P.01E-05f tit. - 9 7 Ci 0.00Et00' 9.4. E-07; St*-69 C1 0.00E+00i O. 2E+00[ .

Sr-90 Ci 6.00E+00I O . 0 0 E - 0 :' !

Fe-55 C1 1.19E:02l 2.59E-Oil P-12 Ci 0.00E+00j 0. ?OE v0M l Tc t si fo- p e r i :.d t 3r : .e . l Ci l l l 1.74E-02l 4. ? ? E-0((

t e - l ': : Ci -

I 5.03E-031 3.11E-031 .

Ci

_e r .3 5 t 0.00E*00 O. 00E + 00 [

e M e - 1 : : ..

Y-135 r r -:-: S i.

i Ci Ci Ci i 2.00E-05 1.99E-05 2 13E-03l 1.43E-03 i 0.00E*00! 0.3:tE-001 fr-8T Ci 0.00E+006 0.00E-001 fe-1?* l Ci j 0. 0 0 E + it0 l 0.00E+00l 22

I I

2 CASEOUS EFFLUENTS 2.1. REGULATORY LIMITS

a. (1) The release rate limit of noble gases from the site shall be:

E 1,+n Qis 19E+ $1.0 E B" + Qiv -

11 E 6 + 44 EB -

11 where Q,= Total release rate from main stack for both Units in Ci/sec (elevated release)

Qv = Total release rate from vent in.Ci/sec (ground release) i = The individual nuclide n = total nuclides E

6

= The average gamma energy per disintegration EB = The average bcLa energy per disintegration (2) The re) case rate limit of all radioiodines and dioactive materials in particulate form with half t ..v e s greater than eight days, released from the site to the environs as part of the gaseous wastes, shall be.

1.0 X 105 Qps + 1.5 X 106 qpy 5t Where Qps = Total release rate from the main stack for both Units in Ci/sec (as elevated release) ry Qyp

= Total release rate from vents for both Units in Ci/sec (ground releases)

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

,E Qs i 12 E6 + 3.0 EB + Qiv 66 E 6 + 140 EB <1 1 +n -

(2) The average release rate of nobic gases during any 12 consecutive months shall be:

~ '

- _ _1 1

E

+n Qs i

-24 E 6 + 6.1 EB -

+ Qiv ,

130 E6+ 270 EB <- 1 l

l (3) The average release rate of all radio iodines and radioactive materials in particulate form from the site with half lives greater than eight days during any calendar quarter shall be:

l

! 1.3 X 106 Ops + 1.9 X 107 Qpv <1 (4) The average release rate of all radio iodines and radioactive materials in particulate form from the site b

u 23

(

with hcif 1.ivas greater than eight dcys during any period of 12 consecutiva conths shall be:

2.6 X 106 qp, # 3,7 x 107 qpy <g (5) The amount of Iodine - 131 released during any calendar (Vl quarter shall not exceed 2 Ci/ reactor. <-

1 (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 licensec shall make an investigation to causes of the release rates, define and identify the initiate a program of action to reduce the release rates to 2.1 of the design objective levels listed in subsection llNP-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 nobic gases during any calendar quarter is:

~ -

E 9si 47 E 6 + 12 Eg + Qiv 260 E6 + 540 EB >1

~ -

i +n (2) If the average release rate from the site of all radio

" iodines and radion:tive materials in particulate form with half lives greater than eight days during any calendar quarter is:

n U 5.0 X 106 Qps + 7.2 X 107 Qpv >l Iodine 131 released during any (3) If the amount of -

calendar quarter is greater than 0.5 Ci/ reactor.

The post-treatment offgas monitors shall be operating and d.

set to alarm and to initiate the automatic closure of to c: cceding the the limits waste gas discharge valve prior specified in Section 2.1.3a above. TL- operability of the automatic isolation valve shall be demo..strated quarterly.

c. If the post-treatment offgas monitor is not operating, a shutdown shall be initiated so that the reactor will be in the hot shutdown condition within 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

f. If the release rate of nobic gases measured at the pretreatment monitor exceeds 260,000 uci/sec forin a writing period greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , notify the Commission within- 10 days, identifying the causes of activity and in accordance with section 5.7.2.

containment for each Unit shall be purged

g. The reactor through the standby gas treatment system for that Unit.

24

h. (1) Potentia 11*y -

explosive gas nixtures of hydrogen and oxygen contcined in the offgas systen downstream of the recombiners shall be continuously monitored during reactor power operation for hydrogen concentration. !

The hydrogen gas monitoring system shall provide alarms

,S locally and in the control room - at a set point of 4%

tg 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 'we eks , provided 'that either (a) grab samples. are taken and analyzed for hydrogen concentraticn once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

(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 liLit 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the offgas system flow shall be stopped.

lO (3) The installed hydrogen monitoring systems shall have daily sensor checks, monthly functional checks, and quarterly calibrations. The portable hydrogen gas analyzer shall be calibrated immediately prior to j installation and shall be subject to daily sensor

checks, monthly functional checks, and quarterly calibrations until removed from service.

l

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 report'ed to the NRC within 30 days in accordance with section 5.7.2.

2.2 MEASUREME?lTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 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).

O 25 , .

n _ _ _ , _ _ . _ . _ _ _ _ _ . _ _ _ _ _

Each of these continuous samplers has a flow controller which oaintaine saeple f 1'ow within about a 10 percent range over each seven dcy collection period. The offgas vent (elevated release) and the reactor building vents have flow measurement devices which continuously record the flow rate of the gas releas'ed (accuracy of these devices are within 10% of the actual flows as hs 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 gaseoue, particulate, and iodine release measurements tritium, gross a,1pha 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 curic 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 OV total curic release is calculated by the computer for each released. This number is of the individual nuclides m_ultiplied by the average energy per disintigration (Eg &

EB) 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 the quarter. Then the computer divides the sum of the nuclides by the seconds in the quarter to determine the percent of the tech. spec. limit released. ,

2. RADI0 IODINE RELEASES Iodine releases are determined weekly for I-131, I-133, and I-135, for each vent. Where significant activity is not measured MDA releases are calculated. Since calculated MDA's are below Technical Specification detectable concent cations then 0 (zero) release is used for the weeks with.caly 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 Tabic 2-1 is based on the quarterly Technical Specification limit.

m U

26 .

3. PARTICULATE RELEASES Particulate releases are deteruined weekly for ecch vent.

Where significant activity is not measured MDA release is calculated. Since calculated MDA's are below Technical q 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 par.ticulate 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 thd monthly 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. In order to eliminate the need for a quarterly composite Sr-89 and Sr-90 activity is calculated for each monthly composite. 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.

( 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 esiculation for,ms.

Hatch has attempted to maintain all calculated MDAs as low as possibic by counting samples longer than what would be normally practical. For example at this time all weekly particualte and iodine counting times are 3000 see 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 27

-, , , , , - . - - . . - - ----.n.-

rolossa,. total pergieulates with half-lives greater than 8-day release, and total tritium release.

"The total or maximum error associated with the effluent measurement will include the cumulative errors resulting r- from the total operation of sampling and measurement.

Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed s t a t i s t i c. a 1 evaluation of error are not suggested. The objective should be to obtain an overall estimate of the error associated with messuruments of radioactive materials released in lir,uid 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 98.3% of this release was from the main stack the MDA release values of the ground level release points were insignificant to the total release.

Monitor Error in Calibration 50%

Vent Flow Rate 10%

Non-Steady Release Rate 20%

EUT

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

Statistical error 60%

Counting Equipment Calibration 10%

Vent Flow Rates 10%

Vent Sampic Flow Rates 10%

Non-Steady Release Rates 10%

Losses From Charcoal Cartridge 1,0%

110%

3. Particulates with half-lives greater than 8 days release was dominated by the MDA calculations for I-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 Sample Flow Rates 10%

Non-Steady Release Rates 10%

TUUI

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

28

Water Vcpor in Scaple Strean Deternination 20%

Vent Flow Rates - 10%

Counting Calibration and Statistico 10%

Non-Steady Release 50%

90%

2.3. GASEOUS EFFLUENT RELEASE DATA Regulatory Guide 1.21 Tables 1A, IB, and 1C are found in t,his 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

a. Measurements shall be made to determine or estimate the total curic quantity and principal radionuclide composition of all radioactive solid waste shipped offsite.

b. Solid wastes in storage and preparatory to shipment shall be monitored and packaged to assure compliance with the applicable portions of 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 171-178.

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

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

9 4

0 29

___t__ _ _ _ .

TAELE I-la UNIT 1

() EFFLUENT AND HASTE DISPOSAL SEHIAHHUAL REPORT 1960 GASEOUS EFFLUENTS-SUf1t1ATION OF ALL RELEASES Unit Quarter Quarter Est Tot al 2 Error *.

E. I. H at ch Huc l e ar Power Plant UNIT 1 1 A. Fission & activation gases Ci 4.52E+03 5.98E+03 8.00E+01l

1. Tot al release 7.61E+02

2. Aver tge rel e ase rat e for oeriod uCi/sec 5.74E+02

% of Technical s pe c i f i c at i on limit % 2.41E-01 3.86E-01 3.

B. Iodines

1. Tot al todine-131 C1 3.24E-02 1.05E-0!! 1.10E+02l

2. Average rel e as e rat e for oeriod uC1/sec 4.12E-03 1.33E-02l

3. % of Technical s pe c i f i c at i on limit % 1.62E+001 5.23E+001 C. Particulates

1. Part icul at es with hal f-l i ves >8 d avs Ci 2.42E-03 2.75E-03c 1.00E'02l Aver.tge release rat e for oeriod uCi/sec 3.08E-04 3.50E-04 2.

of Te c hni c al s pe c i f i c at i on limit % 4.85E-J11 5.51E-91 3.

4. Gros s al pha r adi oac t i vi t o Ci 3.05E-06 2.37E-06)

D. Tritium Ci 1.96E400 1.49E+001 9.00E+011

1. Total release Aver, age rel e as e ' rat e for oeriod uC1/sec 2.49E-01 1.89E-01 2.

of T echni c al spe c i f i c at i on limit % 8.91E-01 1.24E+00 .

3.

l l .

l t

30

TABLE 2-lb _

EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT 1980 0 GASEOUS EFFLUENTS-SunnATIOM OF ALL RELEASES Unit Qisarter Quarter Est Total 2 E:rror %

E. I. Hatch Huc l e ar Power Pl ant UNIT 2 1 A. Fission L activation gases

1. Ci S.2SE+01 6.51E+01 L 8.00E+01l Tota). release 1.05E+01 8.2SE+00

2. Average rel e as e r at e f or oeriod uCi/sec

% of Technic al s oe c i f i c at i on limit % { 4.33E-02 1.75E-02 3.

B. Iodinen

1. Tot al iodine-131 Ci 5.47E-04 1.37E-03! !.10E+02l

2. Average release r at e for ocriod uCi/sec 6.96E-05 1.74E-04i

3. % of Techn i c al s pec i f i c at i on limit % 2.74E-02 6.84E-02l C. Particulates Farti cul at e s with hal f-l i ve s )S daus Ci 7.3SE-05 6.47E-05 1.00E-02l 1.

Average release rat e for oeriod oCi/sec 9.3SE-06 8.22E-06 2.

. of Tec hni c al spe c i f i c at i on limit % 1.75E-02 1.51E-02 3.

Gross al pha r adi o ac t i ut t o C1 1 1.02E-06 5.60E-07 4.

D. Tritiun

1. Tot al release Ci 3.11E+01 1.06E+01! 9.00E+0!i

2. Average rel e as e rat e for oeriod uCi/sec 3.95E+00 1.34E+00l

3. % of Technical s pe c i f i c at i on limit % 3.37E+01 1.16E+0!l i

l I

4 i

31

O TABLE 2-lc PLANT SITE EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1980 GASEOUS EFFLUENTS-SUt1MATION OF ALL RELEASES Unit Quarter Quarter Es t Tot al E. I. Hatch Hucle r Power Plant SITE 1 2 Errer ".

A. Fission & activation gases

1. Tota) release Ci 4.60E+03 6.05E+03 8.00E+011

2. Average release rate for period uCi/sec 5.85E+02 7.69E+02

3. % of Technical spec i fi c at i on limit % 2.85E-01 4.04E B. Iodiner, i

~

1. Total iodine-131 1 Ci 3.3CE-02 1.06E-01 1.10E+021

2. Average release rate for oeriod uCi/sec 4.19E-03 1.35E-02 4

3. % of Technical specification limit % l 8.24E-01 2.65E+00 '

C. Part i c ul at es

1. Facticulates with hal f-l i ves >8 davs Ci 2.50E-03 2. 82F 1.00E+021

2. Average release rat e for period uCi/sec 3.17E-04 3. 5.d E- 0 4

/' 3. % of Tec hn i c al s pe c i f i c at i on limit % 5.03E-01 5.66E-01

4. Grosa alpha r adi oac t ivi tv Ci 4.07E-06 2.93E-06 D. Tritium ,

1. Tot al re l e ase Ci 3.30E+01 1.21E+011 9.00E+01l

2. Average release rate for oeriod uCi/sec 4.20E+00 1.53E+00 3.

. of Technical spec i f i c at i on limit % 3.46E+01 1.2SE+01 4

I f

O 32 ,

t TAELE 2-2a E. I. Hatch Nuc lear' Power Pl ant UNIT

EFFLUEllT AtID WA3TE DISPOSAL SEMIAlltIUAL REPORT 1980 GASEOUS EFFLUEllTS-ELEVATED RELEASE COtlTIllVOUS MODE EATCH MODE

!!ve l ides Released Unit Quarter Quarter Quarter Outrter 1 2 1 2

1. Fission gases .

) Xe-233 Ci 3.10E403 ! 2.55E+031 0.00E+00 1 0.00E+001 Xe-231H Ci 3.40E-01; 2.79E+011 0.00E+00 ' O.00E+00 ,

Kr-88 Ci 1.8SE+02o 2.8SE+02i 0.00E+00 0.00E+00 Xe-233H Ci 2.97E+011 9.94E+011 0.00E+00 0.00E+001 ~

Xe-135 Ci *.31E+611 7.24E+021 0.00E+00 0.00E+00)

Kr-85r1 Ci 6.65E+02 l 1.15E+03 ' O.00E+00! O.00E+00 -

I-131 Ci 4.70E-03 l 3.72E-01 0.00E+006 0.00E+00 :

Kr-87 Ci 2.71E+01 8.05E+01- 0.00E+001 0.00E+001 Xe-238 Ci 1.00E+02 3.17E+02 0.00E+00! O.00E+00s Xe-237 Ci 4.23E+01 0.00E+00 0.00E+001 0.00E+001 ti-13 C1 3.46E+01 3.53E+02 0.00E+001 0.00E+001 Kr-85 Ci 0.00E+00 0.00E+00d 0.00E+00 ~ O.00E+001 ;

Xe-235M Ci 1.01E+021 3.34E+02 1 0.00E+00 0.00E+00f I-133 Ci 0.00E+001 0.00E+00: 0.00E+00h O.00E+00!

Kr-89 Ci 0:00E+001 0.00E+00 0.00E+001 0.00E+00{

I-135 Ci 0.00E+00i 0.00E+00 0.00E+001 0.00E+001

() Ar-41 Total for period C1 Ci 3.53E+01 2.48E+011 0.00E+001 0.00E+001 4.37E+03 5.95E+03 0.00E+00 0.00E+00

2. Iodines I-131 C1 1.45E-02 l 6.74E-02 l 0.00E+001 0.00E+00 :

1-133 Ci S.76E-03 l 2.91E-02 0.00E+001 0.00E+00 I-135 C1 2.97E-03 1.21E-02 0.00E+00I O.00E+00 Tot al for period Ci 2.63E-02 1.09E-01 0.00E+00 0.00E+00

3. Particulates Sr-89 Ci 2.32E-04 2.45E-04l 0.00E+00{ O.00E+00)

Sr-90 Ci 2.37E-07 2.50E-071 0.00E+006 0.00E+001 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 1 0.00E+001 Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+001 1-131 C 4.32E-05' 1.26E-04 0.00E+00 0.00E+001 Sn-113 Ci 0.00E+00 0.00E+00- 0.00E+00 0.00E+006 Ba-240 -

Ci 6.02E-05 2.30E-05: 0.00E+00 0.00E+004 Cs-234 Ci 0.00E+00 7.17E-07 0.00E+00 0.00E+001 C5-237 Ci 1.69E-06 2.32E-06 0.00E+00 0.00E+001 Ce-144 Ci 1.18E-056 4.31E-051 0.00E+00 0.00E+006 Zr-45 Ci 0.00E+001 0.00E+001 0.00E+00' O.00E-00!

tib-95 C 0.00E+001 0.00E+00 0.00E+001 0.00E+001 Co-55 Ci 0.00E+00 ~ 0.00E+00 0.00E+00 ' O.00E+001

(',S s/ Hn-S4 Ci 0.00E+00 ' O.00E+00 0.00E+00 0.00E*00 Fe-59 Ci 0.00E+00 0.00E+00' O.00E+00 0.00E+00 Co-60 Ci 2.96E-06 2.17E-06 0.00E+00 0.00E+00 La-140 Ci 9.?9E-05 6.72E-05 0.00E+00' O.00E+00 Tot al f ir period Ci 4.45E-04 5.10E-04 0.00E+00 0.00E+00 33

TABLE 2-2b E. I. Hatch fluelear Pouer Plant UNIT 2 EFFLUEllT AllD HASTE DISPOSAL SENIAHHUAL REPORT 1980

/'

(_ GASEOUS EFFLUEllTS-ELEVATED RELEASE CONTINUOUS MODE EATCH NODE Hucliden Released Unit Quarter , Quarter Quarter Guarter 1 2 1 2

1. Fission gases Xe-133 Ci 9.50E+00 l 1.26E+01 0.00E+00 0.00E+00l_

Xc-J 31 f1 Ci 1.04E-03 1.38E-01 0.00E+00 0.90E+001 Kr-OS Ci 5.75E-01 1.42E+00 0.00E+00 0.00E+00 Xe-133M Ci 9.09E-02 4.92E-01 0.00E+00 0.00E+00 Xe-235 C1 1.32E-01 3.5SE+00 0.00E+00 0.00E+00 Kr-85r1 Ci 2.04E+00 5.71E+00 0.00E+00 0.00E+00 1-131 Ci 1.44E-05 1.84E-03 0.00E+00 0.00E+00 Kr-87 Ci 8.30E-02 3.99E-01 0.00E+00 0.00E+00 Xe-138 Ci 3.07E-01 1.57E+00 0.00E+00 0.00E+00 Xe-137 Ci 1.30E-01 0.00E+00 0.00E+00 0.00E*001 H-13 Ci 1.07E-01 1.75E+00 0.00E+00: 0.00E+00f Kr-85 Ci 0.00E+00 0.00E+00 0.00E+001 0.00E+001 Xe-3 3511 C1 3.09E-01 1.65E+00 0.00E+00 - 0.00E+00l I-133 Ct 0.00E+00 u 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 1.08E-01 1.23E-01 0.00E+00 0.00E+00 Tot al for period Cl 1.34E+01 2.94E+01 0.00E+00 0.00E+00

2. Iod nes I-131 Ci 4.45E-05 3.33E-04 0.00E+00 0.00E+001 I-133 Ci 2.6SE-05 1.44E-04 0.00E+00 0.00E+00 1-135 Ci 9.10E-06 5.99E-05 0.00E+00 0.00E+00 Tot al for period Ci 8.05E-05 5.37E-04 0.00E+00 0.00E+00

3. Part i c ul at es Sr-09 Ci 7.10E-07! 1.21E-06 0.00E+00 0.00E+00 Sr-90 Ci 7.25E-10j 1.24E-09 0.00E+00 0.00E+00-Ce-141 Ci 0.00E+001 0.00E+00 0.00E+00 0.00E+00 :

Cr-S1 Ci 0.00E+00! 0.00E+00 0.00E+001 0.00E*00 l 1-131 Ci 1.32E-07l 6.24E-07 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+001 0.00E+00 0.00E+00 - 0.00E+00 l Ba-240 Ci 1.84E-07 1.14E-07 0.60E+00 0.00E+00l Cs-134 Ci 0.00E+00 3.55E-09 0.00E+00 0.00E+067 C5-137 Ci 5.18E-09 1.15E-03 0.00E+00 0.00E+00 Ce-344 Ci 3.60E-08 2.13E-07 0.00E+00 0.00E+00 2r-95 Ci 0.00E+00 0.00E+00 0.00E+00 ' O.00E+001 ilb-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l

Co-53 Ci 0.00E+00i 0.00E+00 0.00E+00 0.00E+00 fin-S4 Ci 0.00E+001 0.00E+00 0.00E+00 0.00E+001 Fe-59 Ci 0.00E+001 0.00E+00 0.00E+00 0.00E-00' I\ 0.00E+00 0.00E+00 Co-60 Ci 9.07E-091 1.07E-08 La-140 Ci 2.85E-07 3.33E-071 0.00E+00 0.00E+00 Tot al for period Cl 1.36E-06 2.52E-06 0.00E+00 0.00E+00 34

d TABLE'2-2C E. IL Hatch Huclear Pouer Plant SITE EFFLUENT AND HA5TE DISPOSAL SEMIAHHUAL REPORT 1980 q

GRSEOUS EFFLUENTS-ELEVATED RELEASE CONTIHUGUS HODE PATCH NODE Hucliden Released Unit Quarter Quarter Quarter Guarter 1 2 1 2

1. Fitnion gases I Xe-133 Ci 3.11E+03 2.56E+03 0.00E+00 0.00E+00 Xe-131H Ci 3.41E-01 2.80E+01 0.00E+00 0.00E+00 Kr-US Ci 1.CSE+02 2.89E+02 0.00E+00 0.00E+00 Xe-133M C1 2.98E+01 9.99E+01 0.00E+00 0.00E+00 j 0.00E+00 0.00E+00 Xe-135 Ci 4.33E+01 7.28E+02 1

Kr-0511 Ci 6.67E+02 1.16E+03 0.00E+00 0.00E+00 1-131 Ci 4.71E-03 3.74E-01 0.00E+00 0.00E+00 Kr-07 Ci 2.72E+01 8.09E+01 0.00E+00 0.00E+00 Xe-138 Ci 1.01E+02 3.19E+02L 0.00E+00 0.00E+00 Xe-137 Ci 4.25E+01 0.00E+00 0.00E+00 0.00E+00

[ 0.00E+00 0.00E+00 H-13 Ci 3.49E+01 3.54E+02

Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00t Xe-135Il Ct 1.01E+02 3.36E+02 0.00E+00 0.00E+00I 1-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-09 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7

i 1-135 Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00" Ar-41 Ci 3.54E+01 2.50E+01 0.00E+00 0.00E+06 Total for period Ci 4.38E+03 5.98E+03 0.00E+00 0.00E+00 l 2. Iod nes 1-131 Ci 1.46E-02: 6.77E-02 0.00E+00 0.00E+001 1-133 Ci 8.79E 2.93E-02 0.00E+00 0.00E+00 1-135 Ci 2.98E-03 1.21E-02 0.00E+00 0.00E+00 Tot al for pertod Ci 2.64E-02 1.09E-01 0.00E+00 0.00E+00

3. Part icul at es i

Sr-89 C1 2.32E-04 2.46E-04 0.00E+00 0.00E+00 1

$r-90 C1 2.37E-07 2.51E-U7 0.00E+00 [i.00E+00 Cc-341 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i

Cr-S1 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 4.34E-05 1.27E-04 0.00E+00 0.00E+00 Sn-313 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Ba-240 Ci 6.04E-05l 2.31E-uS 0.00E+00 - 0.00E+00-Cs-134 Ci 0.00E+006 7.20E-07 0.00E+00 0.00E+00 l

l Cs-137 Ci 1.70E-06l 2.33E-06 0.00E+00 d.00E*00 Cc-144 C1 1.18E-05I 4.33E-U5 0.00E+00 0.00E+(((

2r-45 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ,

0.00E+00 0.00E+00 t

Hb-45 Ci 0.00E+00 0.00E+H0 Co-59 Ci 0.00E+00i 0.00E+00 0.00E+00 0.00E+00-Hn-M4 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe 'i9 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 g

Co-e;0 C1 2.97E-061 2.1SE-06 0.00E+00 _ji.00E+00 .

Lh-140 Ci 9.32E-05' 6.76E-05 0.00E+00 0.00E+00 :

Tot h1 for period Ci 4.46E-04 5.12C-04 0.00E+00 0.00E+00 35 '

TABLE 2-3a E. I. Hatch Nuclear Power Plant UNIT 1

-- EFFLUENT AND HASTE DISPOSAL.SEM1 ANNUAL REPORT 1980 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE COHTIHUOUS t10DE BATCH MODE Hucliden Released Unit Quarter Quarter Quarter Qu ar t er 1 2 1 2

1. Fission gases Xe-133 Ci 7.86E+01 2.64E+00 0.00E+00 0.00E+00 Xe-231H Ci 8.79E+00 0.00E+00 0.00E+00 0.00E+00 Kr-39 Ci 1.15E-01 6.90E-03 0.00E+00 0.00E+00 Xe-133tl Ci 1.67E-01 2.90E-03 0.00E+00 0.00E+00 Xe-135 Ci 3.91E+01 2.1LE+01 0.00E+00 0.00E+00 Kr-05t1 Ci 4.29E-02 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.CCE+00 Kr-87 Ci 1.17E-01 3.26E-02 0.00E+00 6700E+00 Xe-138 Ci 2.14E-01 2.18E-02 0.00E+00 0.00E+00I Xe-237 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-13 Ci 3.89E+00 0.00E+00 0.00E+00 0.00E+00 Kr-05 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00' Xe-J35M Ci 1.71E+01 8.58E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-09 Ci 0.00E+00 0.00E+00 0.bOE+00 0.00E+00 1-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00_

Ar- Il Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

,( Tot al for period Ci 1.48E+02 3.25E+01

2. Iod nes I-131 Ci 1.69E-02 3.63E-02 0.00E+00 0.00E+00 1-133 Ci 4.81E-03 1.36E-02 0.00E+00 0.00E+00 I-135 Ci 1.79E-03 3.83E-03 0.00E+00 0.00E+00 Tot al for period Ci 2.35E-02 5.37E-02 0.00E+00 0.00E+00

3. Particulates Sr-89 C1 1.58E-05 1.61E-05 0.00E+00 0.00E+0_0_

Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00' Cc-241 Ci 0,00E+00 1.42E-05 0.00E+00 " 9.00E+006 Cr-51 1-131 Ci 9.61E-04 7.93E-04 0.00E+00 0.00E+00!

Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+001 Sn-113 Ba-140 Ci 0.00E+00 0.00E+00 0.00E+001 0.00E+00[

Cs-334 Ci 3.74E-04 5.99E-04 0.00E+001 0.00E+00" Ci 5.01E-04 7.37E-04 0.00E+00! O.00E+00 C5-137 -

Ci 6.61E-05 1.42E-05 0.00E+00 0.00E+00 Ce-244 Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+001 Hb-95 Ci 0.00E+00 - 0.00E+00 0.00E*00 0.00E+001 Co-SS Ci 3.57E-06 0.00E+00 0.00E+001 0.00E+001 Ci 5.18E-06 0.00E+00 0.00E+00i O.00E+00 Hn-54

/~ Fe-S9 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 kh/ Co-60 Ci 5.11E-05 7.13E-05 0.00E+00 0.00E+001 ~

La-240 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot ti for period Ci 1.93E-03 2.24E-03 0.00E+00 0.00E+00 36

TABLE 2-3b E. I. Hatch Hucle5r Pouer Plant UNIT 2 r~ . EFFLUENT AND HA5TE DISPOSAL set 1IAHilUAL REPORT 1980

(

GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE COHTINUdOS MODE EATCH NODE Hucliden Released Unit Quarter Quarter Quarter Guarter 1 2 1 2

1. Fission gases Xe-233 Ci 5.32E+01 2.42E+01 0.00E+00 0.00E+00 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-1,31M Ci 0.00E+00 2.86E-02 0.00E+00 0.00E+00-Kr-OS Xe '33M Ci 0.00E+00 1.65E-02 0.00E+00 0.00E+00 Xe-135 Ci 4.39E+00 1.13E+01 0.00E+00 0.00E+00-Kr-85ft Ci 0.00E+00 1.6SE-02 0.00E+00 0.00E+00 1 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+001 1-131 Kr-87 Ci 2.91E-01 2.70E-02 0.00E+00 0.00E+00 Xe-238 Ci 2.86E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 2.68E+00 0.00E+00 0.00E+00 0.00E+00 l H-13 Ci 6.02E+00 5.80E-04 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+DO 0.00E+00 0.00E+00 Xe-135M Ci 0.00E+00 7.53E-04 0.00E+00 0.00E+00 1 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-133 Kr-09 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ar-41 Ci 0.00E+00 0.00E+00 0.01E+00 0.00E+00 Tot al for period Ci 6.94E+01 3.57E+01 0.00E+00 0.00E+00

2. Iod nes I-131 Ci 4.67E-04 9.93E-04 0.00E+00 0.00E+00 1-133 Ci 4.79E-04 6.12E-04 0.00E+00 ' O.00E+00 I-135 Ci 1.17E-04 2.07E-04 0.00E+00 0.00E+00 Tot al for period Ci 1.06E-03 1.81E-03 0.00E+00 0.00E+00

3. P art i cul at e s l

Ci 1.SSE-05 1.50E-05 0.00E+00 0.00E+00 l Sr-39 Ci 0.00E+00 0.00E+00 0.00E+00; O.00E+00 Sr-90 C c -:. 41 Ci 0.00E+00 0.00E+00 0.00E+00c O.00E+00 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-S1 Ci 3.57E-05 4.0SE-05 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn-113 Ci C.00E+00 2.32E-06 0.00E+00 0.00E+00 Ba-140 Cs-334 Ci 7.30E-07 0.00E+00 0.00E+00- 0.00E+00 Cs-137 C1 3.92E-06 2.22E-07 0.00E+001 0.00E+001 Ce-344 Ci 0.00E+00 0.00E+00 0.00E+00l 0.00E+00t 2r-95 Ci 0.00E+00 0.00E+00 0.00E+00i O.00E+00i l Hb-95 Ci 0.00E+00 0.00E+00 0.00E+001 0.00E+001 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-53 Mn-S4 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FG-59 Ci 0.00E+00' O.00E+00 0.00E+00 0.00E+00

(~T 1.33E-05: 3.69E-06 0.00E+00 0.00E+00j

%,) Co-eio Ci La-140 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+001 I 0.00E+00

! Tots 1 for period Ci ?.24E-05 6.2tE-n5 0.00E+00 i 37 i

TABLE 2-3c E. IIL Hat c h fluc l ear; Pouer Plant SITE 7 -

() EFFLUEtlT AtlD WASTE DISPOSAL SE!11Allt1UAL REPORT 1980 GASEOUS EF~LUEllTS-GROUtlD-LEVEL RELEASE .

COllTItlUOUS MODE BATCH t10DE tluclide:. Released Unit Quarter Our'rter Quarter Quart e r 1 2 1 2

1. F i ssi on g ase s.

Xe-133 Ci 1.32E+02' 2.69E+01 0.00E+00 : 0.00E+001

? Xe-131H Ci S.79E+00 0.00E+00 0.00E+00 0.00E+00i Kr-83 Ci 1.15E-01 3.55E-02 0.00E+00 0.00E*00I Xe-133t1 Ci 1.67E-01 1.94E-02 0.00E+00 0.00E+00l Xe-335 Ci 4.35E+01 3.25E+01 0.00E+00 0.00E+00f Kr-65t1 Ci 4.29E-02 1.68E-02 0.00E+00 0.00E+00i I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-07 Ci 4.08E-01 5.96E-02 0.00E+001 0.00E+00 Me-138 Ci 3.08E+00- 2.18E-02 0.00E+00i O.C2E+00 Xe-237 Ci 2.68E+00 0.00E+00 0.00E+00 0.00E+00]

ti-13 Ci 9.91E+00 5.60E-04: 0.00E+00 0.00E+001 Kr-U5 Ci 0.00E+00 0.00E+001 0.00E+00 0.30E+001 Xe-135f1 Ci 1.71E+01 8.58E+00 0.00E+00 0.00E+00l 1-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00i Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+C0 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 0.00E+00 0.00E+00 0.00E+00 D.00E+00I

./

V Total for period Ci 2.17E+02 6.82E+01 0.00E+00 O.00E+00

2. Iodines 1-131 Ci 1.73E-02 3.73E-02 0.00E+001 0.00E+00' 1-133 . Ci 5.29E-03 1.42E-02 0.00E+001 0.00E+00 I-135 Ci 1.91E-03 4.03E-03 0.00E+001 0.00E+00 TotEl for g riod Ci 2.45E-02 5.55E-02 0.00E+00 0.00E+00

3. Part. i c ui at e s Sr-89 Ci 3.45E-05 3.12E-05 0.00E+00 0.00E+00i Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+001 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+008 Cr-?il Ci O.00E+00 - 1.42E-05 0.00E+006 0.00E+004 I-131 Ci 9.96E-04 8.34E-04 0.00E+00 0.00E+001 Sn-113 Ci 0.00E+00. 0.00E+00 0.00E+00 0.02E*00l Fa-140 Ci O.00E+00 2.32E-06 0.00E+00i O.00E+00i Cs-134 Ci 3.75E-04 5.99E-04 0.00E+001 0.:3E+00 Ci-137 Ci 5.05E-04! 7.37E-04 0.00E+00i O.20E+00 CE-144 Ci 6.61E-05t 1.42E-05 0.00E+001 0.20E+00;

-' r -" 5 Ci 0.00E+00l 0.00E+00 0.00E+00i O.00E+00I tib-95 Ci 0.00E+00 0.00E+610 0.00E+001 0.00E+001 Co-!is Ci 3.5?E-06 0.00E+00 0.00E+00l O.:UE*00 Mn 'i4 Ci 5.18E-06 0.00E+tt0 0.00E+001 0.00E+ed O Fe -?;9 Co-60 Ci Ci 0.00E+00 6.45E-05 0.00E+00 7.50E-05 0.00E+001 O.30E+00 0.00E+00! O.00E+00

)

La-140 C1 0.00E+00 0.00E+00 0.00E+00i O.00E+00 Tot al for period Ci 2.05E-03 2.31E-03 0.00E+00 0.00E+00 38

l TABLE 3-la PLANT E. I. HATCH EFFLUENT AND V!ASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1980 SOLID VIASTE AND IRRADIATED FU,EL SHIPMENTS FOR UNIT l JANUARY THRU JUNE A. SOLID Y!ASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (flot irradiated fuel)

Unit G m onth E st. To m3

1. Type of waste Furiod Error. %

a. Spent resir.s. filter s! d;es. coperator m' l.47E+2 tottor s. et:. Ci 3. 30 ET2 1.0 E +2

b. Dry cor . ressdie w:ste, contarnan2ted rn' 9.62E+1

~

equip. eti Ci 1. lW O l ._U E +2

c. Irradiated components. centrol m' E ;

rods et:. Ci N/AE N/A E

d. Other (des:nbe) m* E Ci N/AE N/A E i

' I

2. Est!m:te of maict nuclide composition (by type of w:ste)

,,, ISOTOPE I PERCENT CURIES

(] ,

1 'f'

a. Csl34 14.19 18.31 46.84 60.50 i Cs !?' 26.78 88.49 Zn?f 20.19 66.72 Co U 15.12 49.96 All _0ther Isotopes 5.41 17.88

b. I143 _ 14.19. .16 Csid4 18.31 .21 i CsiJ7 26.78 .31 Zn65 20.19 .23 (g60 . 15.12 .17 All Other Isotopes 5.41 .06

3. Sokid Y!aste D;5 position . ,

Number of Shipments Mode of T.ans:>ortation D:stination ,

40 .

CHEM NUCLEAR BARNWELL, S.C.

TRUCK ti. IRRADIATED FUEL SHIPME7JTS (Dispositien) -

(

Number of Shienents Mod: of Tran:cor:stion Destirution

. 0 N/A N/A

>~*

39 w... . . . - .. -

TABLE 3-lb (3

V' HATCH PLtdIT E. .I .

EFFLUENT AND V!ASTE DISPOSAL set.11 ANNUAL REPORT (YEAR) 1980 -

SOLID V/ASTE AND IRRADIATED FUEL SHIPT.1ENTS FOR UillT 2 JANUARY.THRU, JUNE A. SOLID Y.'ASTE SillPPED OFFSITE FOR BURIAL OR O!SPOSAL (flot inadiated fucil l .

konm E n. To ol

1. Type of waste Unit i

rvriod Err or. %

a. Spent resins. It! ct s!d::s. cupotator ~"

nf 1.24 E4 2 tottons. etc. Ci~ ]32__E ]

1.0 E 4 7

b. Dry,cotr.;:ressioie waste. contarninated m i._1.27 E ~

e quip. .e tc. Ci 31B EM _1 n E +2

c. Irradiated companents. conuol . m'

ods.ete. _

C _jf/A.E y/A E

d. Other (describe) m J._

Ci N/A E N/A E

2. Estbuste of maior nuclide composi:icn (by typ: of waste)

~

PERCEllT CURIES IS0 TOPE Znb6 -

31.49 6.07_

a.TibD .

11.82 _ 2.27 i

~

16f6 3.19 Cs734 Cp7 19.34 3.71 3.97 All -

b. gt5Others Y 69i_

__~ 31. 4 9 .01 _

Nb95 11.82 .0F 16.66 .01 Csl34 .01_

Cs- 13 7 19.3W Alrothers 20 69 .01

'.3 Solid Waste Disposition .

Number of Shipments Mode of Tran:portstien D:stination CHEM NUCLEAR . BARilWELL, S.C.

. 21 .

TRUCK IL IRRADIATED FUEL StilPMENTS (Disposition)

(D V Number of Shiprnents tfod: of Transmrtation Destination

'O N/A N/A 40

~

= - -- ._ _ _ _ .

ML19331D646

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