Text

Semiannual Rept for Plant Radioactive Effluent Releases, Jul-Dec 1983
	ML20100J321
Person / Time
Site:	Hatch
Issue date:	12/31/1983
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML20100J268	List: ML20100J261; ML20100J293; ML20100J321;
References
	NUDOCS 8504100450
	Download: ML20100J321 (43)
	v • d • e

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y PLANT E. I. HATCH

', SEMIANNUAL REPORT

[i PLANT RADIOACTIVE EFFLUENT RELEASES

-1 Q 'SECTION TITLE PAGE

..l. LIQUID EFFLUENTS 1

,h j- 1.1 REGULATORY LIMITS 1 ,.

g y

1.2 . MAXIMUM PERMISSIBLE CONCENTRATIONS 2 ji 1.3 MEASUREMENTS-AND APPROXIMATIONS OF y TOTAL RADIOACTIVITY 4 a4 V 1.4 6 LIQUID EFFLUENT RELEASE DATA k

at 2 GASEOUS EFFLUENTS 24 p

$ 2.1 REGULATORY LIMITS 24 sis 2.2 MEASUREMENTS AND APPROXIMATIONS OF f? TOTAL RADI0 ACTIVITY 26

.2; 2.3 GASEOUS EFFLUENT RELEASE DATA '30 3 SOLID WASTE 30 ,

3.1 REGULATORY SPECIFICATIONS ,

30 3.2 SOLID WASTE DATA 30 k

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. PLANT E. I. HATCH SEMIANNUAL REPORT y

( ,) 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 LIQUID RADWASTE ANALYSIS - UNIT I 8-12 h ,

? 13-16 l-3 LIQUID RADWASTE ANALYSIS - UNIT II 1-4 LIQUID RADWASTE DISCHARGE PERMIT 17 1-Sa ,_ b LIQUID RADWASTE DATA COMPILATION 18, 19 3 TABLE LIST OF TABLES PAGE l-la, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-SUMHATION OF ALL RELEASES 20, 21

~

- 1-2a, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-BATCH ONLY 2% .23 -

2-la-c EFFLUENT AND WASTE DISPOSAL SEMI-f'/)

ANNUAL REPORT, GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES 31-33 2-2a-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-ELEVATED RELEASE 34-36 2-3a-c EFFLUENT AND WASTE DISPOSAL SEMI-

'J ANNUAL REPORT, GASEOUS EFFLUENTS-

a GROUND LEVEL RELEASES 37-39 ;

il4 3-1 EFFLUENT AND WASTE DISPOSAL SEMI-l

! ANNUAL REPORT, SOLID WASTE AND jj IRRADIATED FUEL SHIPMENTS 40

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n J:Il GEORGIA POWER COMPANY 3* PLANT E. I. HATCH

[ UNITS NO. 1 & 2

, SEMI-ANNUAL REPORT

( PLANT RADIOACTIVE EFFLUENT RELEASES

..; JULY 1, 1983 - DECEMBER 31, 1983 7

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PLANT RADIOACTIVE EFFLUENT RELEASES 1 LIQUID EFFLUENTS 1.1. REGULATORY LIMITS C 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. ,.

m" 3. The cumulative release of radioactive materials in liquid wastes, excluding tritium and dissolved gases, 7i shall not exceed 20 Ci/ reactor in any 12 consecutive 9 months.

^

4. During release of radioactive wastes, the effluent h control monitor shall be set to alarm and to initiate i 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 f system shall be maintained and shall be operated to 1 i process radioactive liquid wastes prior to their V 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 bi liquid effluents, excluding tritium and dissolved d gases, exceeds 2.5 Ci/ reactor / calendar quarter, the

([, licensee shall make an investigation to identify the q causes of such releases, define and initiate a program is of action to reduce such releases to the design d objective levels 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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!vl 1.2. MAXIMUM. PERMISSIBLE CONCENTRATIONS TheI 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 i l- 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 4 of-interest in that nuclide or because of inadequate sensitivity f Q

a for the nuclide from a gross activity measurement.

the 29 nuclides not detected in the gamma scan, the MDA limit is For any of I computed from the measured data for that sample. .

1 only two pure b' eta dmitters , Sr-89 and St-90, have MPC values i less than 9 X 10 -

uCi/ml. Individual measurements' are made j

e 3

on proportional composite liquid radwaste samples to determine the. Sr-89 and Sr-90 concentration or MDA value to be applied to . ,

b individual batch release calculations.

4 i

Although the MPC limit for tritium is greater than 9 X 10 -6, ,

separate measurement is made for tritium since the gross beta technique does not provide an acceptable tritium measurement. A J distillation and liquid scintillation counting technique is used to measure tritium concentration.

e ThemaximumactivityofgammaandpetaemittingnuclideswithMPC values ' greater than 9 X 10 .

uCi/ml, 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 (Ci/MPCi), is less than' 0.1 for gamma and beta nuclides . not measured directly. -

The sum ' of the ratios, (Ci/MPCi), for alpha emitters can be shown to be less than 0.1 by a . null qteasurement with a J sensitivity limit of approximately 1X 10 -4 cpm /ml. Gas flow L counting is used to achieve the. required sensitivity 'of

.g measurement. l 1

9 Thus, except for radionuclides produced in negligible quantities l d in . a -fission reaction (eg. 1-125, I-129 etc.), the methods M outlined above provide. a means to assign a quantitatively d 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

. data . is used to . assure that quarterly and ~ annual release limits are not ' exceeded..

Bases used for the data of Table 1-l'are as follows:

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A. Fission _ and . activation products . The total . release: values (not ' including 1 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 forth in~ the Environmental Tech Specs. This . sum is for each batch O' released to the river for the res of applicable limit is determined.pective quarter. Percent 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 nuclides of the Ci/MPCi ratios times 100 is the percent of applicable limit for effluent releases during the qu'arter.

g B.

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Tritium . . The measured tritium concentration in a composite

. sample is , used . to calculate the total release and average i

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- diluted concentration .during each period. Averag diluted Y:'i concentration divided. by the . MPC -limit , 3 X 10 - uCi/ml, is converted to percent-to give the percent of applicable 4}

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- -limit.

N.. C. Dissolved and entrained ~ gases - Concentrations of dissolved and entrained gases in liquid ef fluents 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; Xe-135, 1 Xe-133m, Xe-133, tand Kr-85. Iodine radionuclides in any form. are. also determined during the isotopic analysis for each batetir 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. 10-3 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 MEASUREMENTSLAND APPROXIMATIONS OF TOTAL RADI0 ACTIVITY.

Data 11s_of'the analytical procedures for liquid radwaste analysis are contained in operating procedure HNP-7601. The following measurements are performed as indicated:

-( ) MEASUREMENT FREQUENCY METHOD

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

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

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3. Gross Beta Each Batch Gas flow proportional ,

counting 11 4. St-89 Quarterly Chemical separa' tion and 4 Composite gas flow proportional j counting g'

4 5. St-90 Quarterly Chemical separation and A 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 c.1 i

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If a J liquid radwaste tank cannot be reprocessed, a sample for analysis is taken from the tank af ter 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, 2.0 FWHM 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 l' the on-line computer system. Energy and net count data for all 9 significant peaks are determined, and quantitative reduction or i MDA calcula'tions are performed for the nuclides listed in Figure i d 1-1. The quantitative calculations include corrections for l'

counting time, decay time, sample volume, sample geometry, i detector efficiency, baseline counts, and branching ratio. MDA A calculations, including the above corrections, are made based on d' the counts in two standard deviations of the baseline count at

d. the location on the spectrum where a peak for that nuclide would g be located if present.

e. .

]_ The calculated radionuclide concentrations or MDA values from the gamma _ scan and -from previously - stored St-89 and Sr-90 values are used to ' calculate the dilution ratio (Ci/MPCi) and allowable d release parameters. A sample printout is shown in Figures 1-2 7, and 1-3.~

The Liq'uid Radwaste_ Discharge Permit Printout by item to the first portion of the release permit is trag(gferred Figure item 1-4) by a laboratory technician. Although the computer' could printout the release Epermit and will inform the technician if a batch 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.

y The based liquid radwaste on the gammamonitor activitysetting is calculated as measured in the by the comp; sample usec uter for y 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 y discharge, then the liquid passing through the monitor is not ij representative of the sample which was analyzed in the lab. A monitor reading in excess of the calculated setpoint therefore.

4 results- in an automatic termination of the liquid effluent d discharge. Lic uid effluent discharge is also automatically J terminated if the dilution flow rate falls below the flow rate p used in_the computer calculation.

When . the release 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 may 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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_ _ _ _ _ _ _ _ _ ~ . - -.

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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 calculation is performed in the Ge (Li) spectrometry system with computer data reduction using the Liquid Radwaste Library which includes gases.

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 3.99 E-1 curies for the third quarter and r 2.12 E-1 curies for the fourth quarter. These values were g approximately 1/38 for Unit 1 and 1/75 for Unit 2 for the i s L third quarter and 1/56 for Unit 1 and 1/299 for Unit 2 for ti the Lfourth quarter of the allowed 10 curies per quarter per reactor..

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h72 2. - The radwaste reprocessing rather release than procedure discharge strongly emphasized of liquid radwaste.

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During this report period 33.'57% of the liquid radwaste reaching the sample tanks was . discharged; 66.43% was-7; recycled back into both of the reactor water systems.

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3. A complete-isotopic scan, gross beta, and gross gamma counts and. computer analysis were performed prior to the release of y each of-the 1109 discharge batches for both Units.

1.4 LIQUID EFFLUENT RELQ SE DATA 3 Regulatory Guide 1.21 Tables 2A and 2B are' found in this. report

' as Table 1-la , b and 1-2a ,- h. 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:

L, I Number of batch releases: ~ 1109 n.

4 Total time period for releases: 143,695 minutes Maximum time period for a batch release: 540 minutes

9) Q Average time period for batch release: 130 minutes- .

M- ~

r h Minimum, time period for a batch release: l minute 43' ^ Average. stream flow during periods of release - of effluent' into a i

f- flowing stream: 6,889 CFS--

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FIGURE l-1

METHODS- OF MEETING, TABLE' II, COLUMN 2 MPC LIMITS-MPC RANGE -GAMMA-RAY BETA ALPHA

.} - . (U Ci/ml) EMITTERS EMITTERS EMITTERS

^

I-131,I-132, I-133 St-89, St-90 I-135, Cs-134 (Separation &

Gas Flow 9 X 10-6 (ge(Li)-Gamma-Ray Counting)

' Spectroscopy) ALL i (U Tc-99m, Ce-141, Zn-69m, (Gas Flow fj W-187, Zr-97, Mn-56, '

Counting, 9 Cs-138, Sb-125,-Rb-88, Sensitivity Jj Cs-136, Sb-124, Ru-103, 0.01 CPM /ml)

? Nb-97, Br-82, Lu-174m,

[} Sr-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-Zr-Nb-95, Cs-Ba-137

'As-76, F-18, Cr-51 All Others Np-239,-Ce-141 i' 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) 7 iN.

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FIGURE 1-2 Ch b

.,PR O C E DU R E : HHP-7601 DATA SHEET 8

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E. I. Hat ch Nuc l ear Pl ant *

Liquid Raduaste Analysis *

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Reactor # 1 B at c h# 1100-

Tank: CWSTB1 Recirc time: 65 minutes A

( Comnent: HI COND TB FS Run date: 12/20/83 1248 Count start dat e: 12/20/83 1137 Sample volume: 1000.00 n1 Clock time: 3003 secs Geonetry code: 1LHB-0 Live time: 3000 secs

- Detector # 3 MCA# 3 Library: LRWLB2 Operator: GMBW

(~N Energy (kev)= .17 + 1.000*Ch# + 0.000E+00*Ch#^2 + 0.000E+00*Ch#^3 : 12/20/83 0035 t )

Eff = 1/C3,117E+02

E^.1.0764E+00) + 12.719

E^(-4.9429E-01>3 : 12/19/83 025'5 uhere E = Energy in NeV. ,/

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FIGURE 1-2 (CONTINUED)

ERROR MPC C/MPC IS0"0PE EHERGY CONCENTRATION (kev) *:uC i /m l ) (uCi/ml) (uCi/ml)

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

<3.769E-07 1E-05 <3.77E-02 Ce-L44 133.54 <1.42E-05 140.51 (4.273E-08 3E-03 Tc-99m 9E-05 <9.38E-04 Cc-141 145.44 (8.446E-08

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<3.318E-07 1E-04 <3.32E-03 i Hp-239 277.60 2E-03 <2.51E-04 Cr-51 320.08 <5.028E-07

<6.905E-08 3E-07 <2.30E-01

. 1-131 364.48 6E-05 <9.86E-04 2n-69m 438.63 (5.914E-08 479.53 <2.469E-07 6E-05 (4.11E-03

- W-187 5E-04 3.56E-04 F-18 510.99 1.779E-07 5.927E-08 ,

3.091E-07 7.215E-08 1E-06 3.09E-01 /

q I-133 531.19 <1.08E-02 537.32 <2.156E-07 2E-05 lJ Ba-140 2E-05 <6.03E-03

.> As-76 559.10 <1 206E-07 8.71E-01 604.61 7.835E-06 1.294E-07 9E-06 Cs-134 2E-05 5.15E-01 Cs-137 661.50 1.029E-05 1.629E-07

<2.888E-07 4E-05 <7.22E-03 Mo-99 739.58 2E-05 <1.70E-03 Zr-97 743.36 <3.394E-08 756.72 (7.029E-08 6E-05 <1.17E-03 Zr-95 <3.62E-04

<3.615E-08 1E-04 Hb-95 765.79 8E-06 <4.91E-03 I-132 772.61 <3.929E-08 810.76 (4.347E-08 9E-05 <4.83E-04 Co-58 1E-04 2.51E-03 Mn-54 836.62 2.512E-07 5.194E-08 884.67 (5.272E-08 3E-05 <1.76E-03

)'Ag-110m 1.634E-06 1.371E-07 1E-04 1.63E-02 Zn-65 1115.44 1260.41 <t.104E-07 4E-06 <2.76E-02 1-135 6E-05 <1.22E-03 Fe-59 1291.56 (7.309E-08 1332.43 5.341E-07 5.734E-08 3E-05 1.78E-02 Co-60 - < 1,_7_9 E-02;

~

C~..Cd-64 ~2E-04

.1345.90 . I d3. 572 E-06 , .

4.02E-02 Ha-24 1367.75 1.206E-06 7.766E-08 3E-05 La-140 1596.49 _<2.418E-08 2E-05 X1.21E-03

-Mn-56 1810.69 -13.255E-08 1E-04 -<3.26E-04 M

e.%m g

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FIGURE 1-2 (CONTINUED)

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Sr-09 (BETA) 8.110E-08 1.580E-08 ' ' ~ ~

3E-08_ _ _ _ -- ~ 2. 7 0 E + 0 0 # ).

Sr-90 (BETA) (8.470E-09 1E-08 <8.47E-01 ,y p 3E-03 1. 04 E+ 0 0 F-( H-3 (3 ETA) 3.130E-03 4.500E-04 Fe-55 (BETA) L.400E-06 0.000E+00 SE+00 1.75E-07

$ ------ ---_ _ _. . 1 $_- 1- -- ---

1 ----

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" ~ ~ " ~ ~ Measured tot als -~ 3 .' 15 4 E- 0 3 ~4.'500E ^5.53E+00 36.435E-06 <1.21E+00

, ..__LLD t ot al s _

- -Tot al s . e-3.160E-03 _6. Z_4 E+ 0 0 ~

t-a .

Y DISSOLVED GASES 4

Xe-;33 81.00 <t.009E-07 4E-05 <2.52E-03 Kr-88 196.32 (1.585E-07 4E-05 <3.96E-03 L

(4.567E-07 4E-05 <1.14E-02

} Xe Xe-135 33M 233.22 249.96 1.750E-07 3.409E-08 4E-05 4.38E-03 q%

Kr-85M 304.87 <3.018E-07 4E-05 <7.55E-03 Kr-87 402.58 (7.580E-08 4E-05 <1.90E-03

) <2.322E-08 4E-05 (5.80E-04 Xe-138 434.49 ---------

Measured gas totals L.750E-07 3.409E-08 4.38E-03 LLD gas t ot al.s (L.117E-06 <2.79E-02 Total gas L.292E-06 3.23E-02

j. .-

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GROSS ACTIVITY Gross Bac k ground Time Vol Het Error Counter 1 Sigma Counts (Min) ml Activity (cpm /ml)

Counts -------- --------

/ --- .. ------ ------ ----_. ----- ----

2967 1035 20.0 2 4.83E+01 1.58E+00 Wel' Crystal 772 208 10.0 2 2.82E+01 1.57E+00 Proportional EST:NATED WASTE TANK VOLUME = 7000.00 g al l ons EST; MATED ACTIVITY THIS BATCH EXCLUDING GASES: 8.36E-02 Curies '( 8.36E+04 Microcuries)

^

EXCLUDING H-3 RHD GASES: 6.36E-04 Curies ( 6.36E+02 Microcuries) 3- /

3 THE ACTIVITY OF THIS BA"CH (EXCLUDING H-3 AND GASES) IS 636.49 uCi /

THE MAXIMUM TAHK RELEASE LIMIT IS 300 uCi 7 LAB SUPERVISON APPROVAL HEEDED FOR THIS RELEASE y

RELEASE APPROVED BY: WCP _,

Liquid Raduaste Release Summary

1) Meas. conc., excluding H-3 and dissolved gases (uCt/ml): 2.40E-05 +- 2.88E-07 )

Meas. conc., including H-3, excluding gases : 3.15E-03 +- 4.50E-04 2)Calcul at ed LLD concentration, excluding dissolved gases (uCt/ml): 6.44E-06 l l

-(g -()- 3) Calculated MPC ratio (C/MPC of meas. , including gases): 5.54E+00 -_

l 4)M nimum dilution flow rate -(gpm): 10000

5) Maximum tank discharge flou rate (gpm): '2204 l

' 1

FIGURE l-2 (CONTINU20)

~$ --6) Spec i fi ed t ank flou rat e (gpm):-75 -

'7)Radwaste monitor trip setting: 1632 B = 1000 , Monitor BG CPS R =~2.24E-05 ,uCi/ml C = 11980000.00 , Monitor CPS per uCi/ml F = 2 ,Conserv. Factor includes measured ' selected','other' nuclides and gases but excludes:

. _ _ _(~ ~~ __A Sr-09,~Sr-90 H-3._Fe-55, P-32 .

T 19)Est i mat ed c onc . - or: meas,=._ nuclides at point of release Cuci/_al): 2.348E-05 -- ,

j 3..- -

3

9) Monitor maximum to ensure 10CFR20 limits are not exceeded: 6515 l ESTIMATED DOSES THIS BATCH, MREN u

Isotope W. Body Bone 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 4

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-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-L33M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2 Xe-L35 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 0.00E+00 -0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O I-131 Kr-87 Xe-138 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 'O.00E+00 0.00E+00' O.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-10 3.88E-14 3.50E-13 0.00E+00 0.00E+00 0.00E+00 B.00E+00 1.04E-14 I-133 1.26E-08 2.36E-08 4.12E-08 6.06E-06 7'19E-08 0.00E+00 . 3.72E-08 Ba-L40 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 1.52E-03 7.84E-04 1.86E-03 .0.00E+00 6.04E-04 2.'00E-04 3.26E-05 Cs-L37 1.18E-03 1.32E-03 1.80E-03 0.00E+00 6.13E-04 2.04E-04 3.50E-05

's Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00.

J Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00-l 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

) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00-m I-132 d Co-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 5.39E 0.00E+00 2.83E-07 0.00E+00 8.41E-08 0.00E+00 8.66E-07

" Ag-L10m 0.00E+00 0.00E+00 0.00E+00 0.00E+00' O.00E+00 0.00E+00 0.00E+00 Zn-65 9.13E-06 6.35E-06. 2.02E-05 0.00E+00 1.35E-05 0.00E+00 1.27E-05 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 1.19E-06 0.00E+00 5.38E-07 0.00E+00 0.00E+00 0.00E+00 1.01E-05 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 1.24E-07 -1.24E-07 1.24E-07 1.24E-07 1.24E-07 1.24E-07 1.24E-07 '

La-L40 0.00E+00';0.00E+00 0.00E+00' O.00E+00 0.00E+00 0.00E+00 'O.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 7.44E-09 2.60E-07 0.00E+00 -0.00E+00 .0.00E+00 0.00E+00 '4.17E-08 Sr-90 0.00E+00 0.00E+00 4.00E+00 .0.00E+00- 0.00E+00 0.00E+00 0.00E+00

--H-3 0.20E-07 0.00E+00 0.20E-07 .0.20E-07 0.20E-07' O.20E-07 8.20E-07 "-

'~

r e-55 ~ ' 1; 93E-08 -$740E-08 ' 4. 43E-08 -8790E+00 ~ 0.00E+00 -2.47E-08 2.54E-08 P-32 1.48E-04' 3. 01E-03 2.38E-04 0.00E+00 0.00E+00 '0.00E+00 4.29E-04 Total 2.06E-03 5.93E-03 3.92E-03 7.00E-06 .1.23E-03 4.05E-04 5.22E-04 i

~

. . . . . _ . _ _ . _ _ _ _ (CONJINU' c 0J ______ _ _ _ . . . _ _ _ _

i I

Cunulctiva deco thio YEAR (includ2s ostimato (cr this batch):

Whole body 1.42E+00 mrem Percent of Tech Spec Limit: 4.72E+01 Bone 1.31E+00 mrem Percent of Tech Spec Limit: 1.31E+01 Liver _ ___1.95E+00 mrem Percent,of Tech Spec Limit: 1.95E+01 O(f['

,/

Thyroid 7 Kidney 6.27E-01 mrem 6.59E-01 aren.

Percent of Tech Spec Limit: 6.27E+00 Perce.nt of; Tech _ Spec Limig,: _6.59E+00 .

-~ Lung'~ 2.tBE-01 arem -Perc ent- of 'Tec h ' Spec ~timi s . 2.-10E + 00 GI-LLI 1.08E-01 meem Percent of Tech Spec Limit: 1.08E+00 Cumulative dose this QUARTER (includes estimate for this batch):

Whole body 3.17E-01 mrem Percent of Tech Spec Limit: 2.11E+01 Bone 4.08E-01 mrem Percent of Tech Spec Limit: 8.17E+00 Liver 4.32E-01 mrem Percent of Tech Spec Limit: 8.63E+00 i Thyroid 7.59E-02 mrem Percent of Tech Spec Limit: 1.52E+00 Kidney 1.41E-01 mrem Percent of Tech Spec Limit: 2.82E+00 Lung 4.62E-02 mrem Percent of Tech Spec Limit: 9.24E-01 h GI-LLI 3.03E-02 mrem Percent of Tech Spec Limit: 6.05E-01 o

I Projected cumulative done this QUARTER (includes estimate for this batch):

j Whole body 3.60E-01 mrem

) Bone 4.64E-01 mrem Liver 4.90E-01 mrem Thyroid 8.62E-02 mrem Kidney 1.60E-01 mrem ,

Lung 5.25E-02 mrem !

GI-LLI 3.44E-02 mrem

?

Cumulative measured act vity this YEAR (includes estimate for this batch):

,9.690E-01 Curies, excluding H-3 and dissolved gases LRW treatment system should be OPERABLE due to projected dose for Whole Body LRW treatment system has been demonstrated OPERABLE, confirmed by: GMBW BATCH # 1100 DATA SUCCESSFULLY STORED SPECTRUM STORED AS: L1100 i

l l

b - - '~

~+ " ?

FIGURE 1-3 l t,

PROCEDURE: HHP-7601 DATA SHEET 8

E. I . Hatch Nuc le ar Pl ant -

Liquid'Radwaste Analysis

e,***** o.ee ********************************** ,

Reactor # 2 Batcht 1998 Tank: FDST2 Recirc time: 105 minutes Comnent: HI COND Count-start date: 12/13/83 0330 Run date:' 12/13/83 0910 Sample volume: 1000.00 n1 Clock time: 3000 secs .

Geonetry code: 1LHB-0 Live time: 3000 secs Detector # 3 MCA# 3 Library: LRWLB2 .._

Oper at or: BHW,___ , _ _ .

Energy (kev)= .18 + 1.000+Ch# + 0.000E+00*Che*2 + 0.000E+00*Ch#^3 : 12/13/83 0005 Eff = 1/[2.040E+00 + E^-1.1879E+00) + 329.028

Ea(9.3537E-01)3 : 11/27/83 0130 3

where E = Energy in MeV.

\

FIGURE 1-3 (CONTINUED)

ISO ~ OPE ENERGY CONCENTRATION ERROR MPC C/MPC (kev) i:uCi /m i ) CuCi/ml) (uCi/ml)

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

Ce-t44 133.54 (9.019E-08 1E-05 <9.02E-03 !

Tc-99m 140.51 (7.132E-09 - -3E-0 3 <2.38E-06 l Ce-141 145.44 <2.152E-08 9E-05 <2.39E-04 i Hp-239 277.60 <7.063E-08 1E-04 <7.06E-04 Cr-!51 320.08 (L.162E-07 2E-03 <5.81E-05 ,

I-131 364.48 <L.566E-08 3E-07 <5.22E-02 Zn-69m 438.63 <8.023E-09 6E-05 <1.34E-04 l W-107 479.53 <4.247E-08 6E-05 <7.08E-04 F-10 511.00 <4.239E-09 5E-04 <8.48E-06 I-133 529.87 (L.273E-08 1E-06 <1.27E-02 Ba-140 537.32 <4.484E-08 2E-05 <2.24E-03 As-76 559.10 <2.489E-08 2E-05 <1.24E-03 Cs-134 604.70 1.246E-07 1.947E-08 9E-06 1.38E-02 Cs-t37 661.78 t.914E-07 2.730E-08 2E-05 9.57E-03 Mo-99 739.58 <7.539E-08 4E-05 <1.88E-03 Zr-97 743.36 <1.194E-08 2E-05 <5.97E-04 Zr-95 756.72 <2.058E-08 6E-05 <3.43E-04 Hb-95 765.79 (L.32BE-08 1E-04 <1.33E-04 I-132 772.61 <4.037E-09 8E-06 <5.05E-04 Co-ti8 810.76 <1.574E-08 9E-05 <1.75E-04 Mn-ti4 835.21 7.386E-08 1.989E-08 1E-04 7.39E-04 Ag-110m 884.67 <2.219E-08 3E-05 <7.40E-04 Zn-65 1115.27 -4.013E-07 5.951E-08 1E-04 4.01E-03 1-135 1260.41 <3.358E-08 4E-06 <8.39E-03 Fe-!i9 1291.56 <4.651E-08 6E-05 <7.75E-04 Co-60 1332.42 2.641E-07 3.451E-08 3E-05 8.80E-03 Cu-64 1345.90 (L.238E-06 2E-04 <6.19E-03 Na-24 1368.53 <0.921E-09 3E-05 <2.97E-04 La-140 1596.49 <8.876E-09 2E-05 <4.44E-04 Mn-!!6 1810.69 <9.335E-09 1E-04 <9.34E-05 Sr-89 (BETA) <i.660E-08 3E-08 <5.53E-01 Sr-90 (BETA) <0.940E-09 1E-08 <8.94E-01 H-3 (BETA) L.250E-03 1.800E-04 3E-03 4.17E-01 Fe-!)5 (BETR) <9.000E-07 8E-04 <1.13E-03 P-32 ( .EC ) 2.000E-07 0.000E+00 2E-05 1.00E-02 Measured totals 1.251E-03 1.800E-04 4.64E-01 LLD totals (2.893E-06 <1.55E+00 Tot al s L.254E-03 2.01E+00 DISSOLVED GASES Xe-133 81.56 1.385E-07 2.719E-08 4E-05 3.46E-03 Kr-08 196.32 <t.128E-08 4E-05 <2.82E-04 Xe-t33M 233.22 (L.046E-07 4E-05 <2.61E-03 Xe-135 250.11 3.532E-08 8.628E-09 4E-05 8.83E-04 Kr-85M 304.87 <3.424E-08 4E-05 (8.56E-04 Kr-87 402.58 (L.329E-09 4E-05 <3.32E-05 Xe-L38 434.49 <?.679E-15 4E-05 <1.92E-10 Meas.ured gas t ot al s L.738E-07 2.853E-08 4.35E-03 s LLD gas totals _ (L.514E-07 <3.79E-03 Tot al gas 3.252E-07 8.1.3 E-0 3 l

l l

(CONTINUED)

GROSS ~CCTIVITY Counter Grecs Orckground Tico Vol Nat Error Counts Counts (Min) al Retivity(cpm /ml) 1 Sigma Soll Cryst al 1394 1296 20.0 2 2.70E+00 1.29E+00

)coport i onal ' _ __ 105 170 10.0 2 3.50E-01 9.53E-01 ESTIMRTED WRSTE TRHK VOLUME = 9135.00 gallons ESTIMRTED RCTIVITY.THIS BRTCH EXCLUDING GASES: 4.33E-02. Curies ( 4.33E+04 Microcuries) .

EXCLUDING H-3 RND GRSES: 4.34E-05 Curies ( 4.34E+01 Microcuries)

Liquid Radwaste' Release Summary J

1) Meas, conc., excluding H-3 and dissolved gases (uCi/ml): 1.26E-06 +- 7.91E-08 Meas. conc., including H-3, excluding gases : 1.25E-03 +- 1.80E-04

2) Cal cul at ed LLD c onc ent rat i on, excluding dissolved gases (uC1/ml): 2.89E-06 ,

j 3)Calcul ated MPC ratio a:C/MPC of meas. ,inc luding gases): 4.68E-01 4)M'nimum dilution flou rate (gpm): 10000 S) Maximum t ank . di sc harge flow r at e (gpm): 21582 i

6) Spec i fi e d t ank flou rate (gpm): 75

< 7)Radwaste monitor trip setting: 375 i A= 1. 23E-06 , uc i /ral B = 300 , Monitor BG CPS C = 9530000.00 , Monitor CPS per uCi/mi F = 2 ,Conserv. Factor R includes measured ' selected','other' nuclides and gases but excludes:

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

8)Ent imat ed conc. of meas, nuclides at point of release (uCi/ml): 9.315E-06

9) Undiluted concentration meets 10CFR20 limits.

t ESTIMRTED DOSES THis BRTCH, MREN

!sotope W. Body Bone Liver Tnyroid Kidney Lung GI-LLI Xe-t33 0.00E+00 0.00E+00 0.00E+00 0.00E+00~ 0.00E+00 0.00E+00 0.00E+00 Co-L44 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 Co-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

X2-133M 0.00E+00 0.00E+00 'd.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 X3-135 0.00E+08 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 0.00E+00

~~-O(,,/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__

Cc-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 X2-t30 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0. 00E + 00-

FIGUME 1-3 (CONTINUED)

Zn-693 0.00E+98 8.99E+00 W-187 0.00E+00 8.00E+00 9.89E+00 9.80E+00~~0.00E+06 8.88E+88 8.89E+00 0.00E+00 F-18 0.00E+88 0.00E+99 8.00E+00 8.00E+00 0.00E+88 8.00E+00 0.80E+00 I-133 8.88E+00 8.88E+09 8.80E+00 0.00E+00 9.89E+00 9.89E+00 0.00E+00 Ba-;48 0.88E+08 9.90E+00 8.88E+00 0.89E+00 0.00E+00 Cs-76 8.88E+00 0.00E+00 8.80E+0B 8.89E+00 9.80E+00 0.00E+00 8.88E+88 0.00E+00 9.80E+00 Os Co-;37 Co-;34 3.16E-05 1.63E-05 3.06E-05 8.00E+00 0.00E+0B 0.90E+00 0.00E+00 0.00E+00 2.06E-05 3.21E-05 4.37E-95 8.00E+00 1.25E-05 4.16E-06 6.77E-07 Mo-99 0.00E+00 0.00E+00 1.49E-05 -4.94E-06 8.48E 2r-97 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 Zr-95 0.00E+00 0.00E+00 9.00E+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 0.00E+00 1-132 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+0Q 0.00E+00 Mn-54 0.00E+00 2.07E-08 0.00E+00 1.08E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ag-;10m 0.00E+00 0.00E+00 0.00E+00 3.23E-08 0.00E+00 3.32E-07 2n-65 0.00E+00 2.93E-06 2.03C-06 6.48E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 0.00E+00 0.00E+00 0.00E+00 4.33E-06 0.00E+00 4.08E-06 Fo-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 7.66E-07 0.00E+00. 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.47E-07 0.00E+00 Cu-64 Ha-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 6.54E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 L a- :. 4 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 Sr-09 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 0.00E+00 l H-3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i 4.27E-07 0.00E+00 4.27E-07 Fo-55 0.00E+00 4.27E-07 4.27E-07 4.27E-07 0.00E+00 0.00E+00 4.27E-07 P-32 1.29E-04 3.32C-03 2.07E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00

... .... ........ ........ ........ 0.00E+00 0.00E+00 0.00E+00 3.74E-04 Total 1.93E-04 3.37E-03 .. . ... ........

2.96E-04 4.27E-07 3.22E-05 9.53E-06 ,

3.86E-04 Cumulative dose5.98E-01 Whole body this YEHR mrem(includes est imat e for this batch):

O.N Bone 5.26E-01 mrem Percent of Tech Spec Limit: 1.99E+01 Liver 8.25E-01 mnem Percent of Tech Spec Limit: 5.26E+00 Thyroid 1.34E-01 mrem Percent of Tech Spec Limit: 8.25E+00 Kidney 2.79E-01 mrem Percent of Tech Spec Limit: 1.34E+00 Lung 8.97E-02 mrem Percent of Tech Spec Limit: 2.79E+00 GI-LLI 3.62E-02 mrem Percent of Tech Spec Limit: 8.97E-01 Percent of Tech Spec Limit: 3.62E-01 Cumulatioe dose this QUARTER Whole body 7.20E-02 mrem(includes est imate for this batch):

Bone 1.00E-01 mrem Percent of Tech Spec Limit: 4.80E+00 l Liver 1.00E-01 mrem Percent of Tech Spec Limit: 2.00E+00 Thyroid 2.80E-03 mrem Percent of Tech Spec Limit: 2.00E+00 '

f Kidney 3.29E-02 mrem Percent of Tech Spec Limit: 5.59E-02 Lung Percent of Tech Spec Limit: 6.58E-01 1.07E-02 mrem Percent of Tech Spec Limit: 2.14E-01 GI-LLI 0.23E-03 mrem Percent of Tech Spec Limit: 1.65E-01 Pro.iected Whole body Bone-cumulat 8.95E-02 ive done this QUARTER (includes estimate for this batch mrem 1.25E-01 mrem Liver 1.24E-01 arem Thyroid 3.48E-03 aren Kidney 4.09E-02 meem Lung 1.33E-02 mrem GI-LLI 1.92E-02 mrem Cumulat ive measured act' vity this YEAR (includes estimate for this batch):

3.162E-01 Curies, excluding H-3 and dissolved gases )

33TEH# 1998 DATA SUCCESSFULLY STORED ......

SPECTRUM STORED AS: LRW2 I n . __

FIGURE 1-4 Q AffT,[313,QQH DATCH NO. _ _ _

(J.GUID RANAGTE OtGCHARGE PCRMIT UNIT e DATE p TArc< TO BE RELEAOCD _ __

HEACON FCG t,0CCEO!1Y CF DISCHARGE MItyTCg g'- S:J'1PLE TIRE RECIRC. DURATION RECIRC. START TIttI _

1. LAScrtATORY ANALYSIS

.E + .E uti / nil (I) MEAStrtED RADICNL'CLIOE CCNCChrTRATION ,_,,__ uC i /ni!

(2) CALCU_ATED LLO LIMIT CCNCCNTRATIONS (3) CALCULATED MPC RATIO: 2 (Ci/PPCi) CPM

. (4) MINItC1 O!LUTION FLCW RATE __

CPM (5) MAX. CALCLLATED TAN ( DISCHARCE RATE: IgEE SEC. F.S.g) CPM (6) SPECIFIED TAN ( OISCHARCE RATE: 6(51/2 ,,,,,,,, C P G (7) RADWASTE MONITCR TRIP SETTINCI uCi/mi B = MONITOR BG CPS A = Ge(Li)(1)

C = IC4ITCR CPS F = CONSERVATIVE i FACTOR

.PER Ce(Li) uCi/ml [

tr.NITCR ALARM SETPOINT (CPS) = (C X A X F) tB+3@

1 COIPLETED BY OATC CDrPCSITE LITER STORED

' (INITIALS) LAS FOREMAN AFPRCVED (B) RADWASTE IC41 TOR MAX. CPS TO SE WITHIN 10 CFR EO LIMITS:

CXAX (6)*(4)

(6) (3) cps II . C. ER ATIC* 3 INIT.

(9) LIGUIC RtOWAETE MONITCR TRIP SET AT: CPS (10) CCNFIRPED OILUTION FLCW RATE CPM ,,,,,

(11) VALVE LINEUP C;ECXFD AS PER HNP-TANK CIS. INTEGRATCR DIS.-RATE OIL. TOTAL RIVER EL. MCN!Tb DATE T !?f l- IEVFL -! RONG. CPM CAL FT. CPS e e BTeltT cac

. . . . . . . _ . . . . . _ . . . . . . . . . . .__...s COMPLETED BY CATE i _ . .

MIN. CAL.

CLRATICN TOTAL RP EASE-

9 IO MIN AFTER START

- ##TER FLtGHING III.L./GCRATORY f

(12).-TOTAL TN,N. VOLUME DISCHARCED (CAL. X 3,7551 m1~

(13) TOTAL ACTIVITY DISCHARCED I(1) X (12)I uCi.

(14) . RIVER FLC4 RATE (FROM FSAR 2.4-6) CFS CCPLETED BY- DATE

[ ~ .

o i

o.......__............,--.....i l

-17 . , ,

FIGURE 1-Sa a-?

Liquid Reduaste Dcta Compi1ctisn for Reg. Guide 1.21 Report #U E. I. Hatch Nuc lear Plant UNIT 1

) Tot al Actiutty (Curies)

Quarter 3, 1983 Batches Quarter 4, 1983 581 thru 891 Bat c hes 892 thru 1127 Hane Me a.s ur e d. Error High LLDs Ce-144 Tot al Measured Error High LLDs Total Tc-99m 8.E6E-04 1.57E-04 2.99E-05 1.28E-03~9.51E-06

9.16E-04 3.34E-04 6.96E-05 0.00E+00 3.34E-04 Ce-t41 1.28E-03 4.17E-04 5.58E-06 .* 4.17E-04 Np-239 0.E0E+001.01E-05 3.13E-04 0.00E-00 0.00E+00

0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 2.39E-03 7.12E-05

3.13E-04 3.39E-05 5.86E-06

3.39E-05 I-131 2.39E-03 3.24E-04 2.80E-05

3.24E-04 Zn-69m 8.25E-02 0.00E-00 0.E0E+00 7.10E-05 0.00E+00* 8.25E-02 1.47E-02 3.47E-05 0.00E+00 1.47E-02 W-107 0.E0E+00 0.00E-00

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

0.00E+00 F-18 4.20E-03 1.62E-05

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

0.00E+00 I-133 3.57E-02 5.42E-05

4.20E-03 8.18E-04 9.14E-06

8.18E-04 Ba-t40 0.E0E+00 0.00E-00

3.97E-02 4.91E-03 2.05E-05

4.91E-03 As-76 5.55E-04 1.52E-05

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

0.00E+00 Cs-L34 5.95E-04 1.46E-05 2.52E-06

1.46E-05 _

Cs-137 3.46E-02 5.52E-05 0.00E+00 3.46E-02 5.53E-02 6.25E-05 0.00E+00 5.53E-02 Mo-99 5.56E-02 7.30E-05 0.00E+00 5.56E-02 7.26E-02 7.65E-05 0.00E+00 7.26E-02 Zr-97 1.E2E-030.00E-00 0.E0E+00 5.60E-05 2.32E-05

1.04E-03 2.36E-04 3.57E-05 0.00E+00 2.36E-04 Zr-95 1.58E-06 1.37E-06

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

0.00E+00 Nb-95 0.E0E+00 0.00E-00

1.98E-06 5.20E-05 6.29E-06

5.20E-05 I-132 1.57E-04 4.50E-06

0.00E+00 6.98E-05 4.90E-06

6.98E-05 Co-58 1.57E-04 3.47E-05 2.66E-06

3.47E-05 '

Mn-54 3.93E-05 2.76E-06 0.00E+00 3.93E-05 4.39E-04 9.09E-06 0.00E+00 4.39E-04 7.E4E-041.75E-06 Ag-110m 8.92E-06 1.32E-05 0.00E+00

7.84E-04 1.52E-03 1.59E-05 0.00E+00 1.52E-03 l O% Zn-65 8.92E-06 1.65E-05 3.75E-06

1.65E-05 I-135 1.E6E-025.44E-05 6.54E-03 6.41E-05 0.00E+00

1.06E-02 1.16E-02 6.05E-05 0.00E+00 1.16E-02 Fo-59 6.94E-03 6.50E-04 1.58E-05

6.50E-04 Co-60 0.E0E+00 0.00E-00 0.00E+00 0.00E+00 3.98E-05 3.80E-06 0.00E+00 3.98E-05 Cu-64 4.50E-03 2.97E-05 0.00E+00 7.45E-03 5.17E-04

4.50E-03 5.19E-03 2.79E-05 0.00E+00 5.19E-03 Ha-24 5.28E-03 2.35E-05

7.45E-03 2.29E-03 2.98E-04

2.29E-03 La-t40 1.59E-04 6.00E-06

5.28E-03 1.09E-03 1.22E-05

1.09E-03 Mn-56 0.20E+00 0.00E-00

1.99E-04 1.03E-04 4.08E-06

1.03E-04 Cs-136 1.E2.E-03 1.23E-05

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

0.00E+00 Cs-L38 2.33E-05 1.67E-06

1.02E-03 4.04E-04 7.92E-06

4.04E-04 Rb-88 7.76E-06 1.25E-06

2.33E-05 8.44E-05 3.27E-06

8.44E-05 Cd-LO9 8.E0E-05 1.15E-06

7.76E-06 8.14E-05 5.05E-06

8.14E-05 Co-57 8.12E-05 1.28E-06

8.80E-05 0.00E+00 0.00E+00

0.00E+00 Bn-139 2.E8E-05 8.38E-07

8.12E-05 0.00E+00 0.00E+00

0.00E+00 I-134 0.E0E+00 0.00E-00

2.88E-05 0.00E+00 0.00E+00

0.00E+00 Hb-97 0.E0E+00 0.00E-00

0.00E+00 7.14E-07 1.49E-07

7.14E-07 Sr-09 0.00E+00 1.44E-06 3.41E-07

1.44E-06 Sr-90 S.59E-04 2.81E-04 0.00E+00 8.59E-04 2.27E-03 3.62E-04 0.00E+00 2.27E-03 Fe-55 0.E0E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.E1E-03 P-32 1.90E-03 0.00E+00 3.81E-03 2.93E-03 1.80E-03 0.00E+00 2.93E-03 0.E0E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.51E-03 4.51E-03 Totals 2.65E-01 2.01E-03 5.31E-05 2.65E-01 1.79E-01 1.87E-03 4.51E-03 1.83E-01 Xo-133 Kr-08 2.44E-02 6.97E-05 0.00E+00 2.44E-02 3.15E-03 3.13E-05 0.00E+00 3.15E-03 i fr~$o-133M 0.E0E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

. ( h-135 5.21E-05 8.53E-06 0.00E+00 5.21E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I \-Ur-85M 2.13E-02 3.40E-05 0.00E+00 2.13E-02 1.77E-03 1.18E-05 0.00E+00 1.77E-03 Mr-07 0.E0E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 0.E0E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Re-135M 0.E9E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot als 2.21E-06 2.13E-07 0.00E+00 2.31E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.57E-02 7.80E-05

Ho LLD recuirement in Tech0.00E+00 Spec 4.57E-02 4.92E-03 3.35E-05 0.00E+00 4.92E-03

_gg, k n

FIGURE 1-5b Liquid Redwesto Data Compilat ion for Reg. Guid2 1.21 Report E. I. Hatch Nuclear Plant UNIT 2 O Tot al Activity (Curies)

Quarter 3, 1983 Quarter 4, 1983 Batches 569 thru 899 B at c hes 900 thru 1130 Hame Measured' Error High LLDs Total Measured Error High LLDs Tot ai Ce-144 2.36E-04'7.11E-05 0.00E+00 2.36E-04 1.55E-04 4.62E-05 0.00E+00 1.55E-04 *

-Tc-99m 1.33E-04 2.92E-06 * ~1.33E-04 1.09E-05 9.97E-07

1.09E-05 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 Hp-239 1.03E-03 3.59E-05

1.03E-03 3.83E-05 4.24E-06

3.83E-05 Cr-51 3.25E-05 6.86E-06 * . 3.25E-05 1.32E-04 1.27E-05

1.32E-04 I-131 1.04E-03 1.31E-05 0.00E+00 1.04E-03 5.27E-04 8.21E-06 0.00E+00 5.27E-04 Zn-69m 4.12E-05 3.03E-06

4.12E-05 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-18 2.11E-04 5.82E-06

2.11E-04 9.08E-04 7.78E-06

9.08E-04 I-133 8.77E-04 9.66E-06

8.77E-04 2.90E-04 5.90E-06

2.90E-04 i Ba-140 0.00E+00 0.00E+00

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

0.00E+00 As-76 1.10E-04 6.22E-06

1.10E-04 2.93E-05 2.84E-06

2.93E-05 .--

Cs-134 3.17E-02 4.27E-05 0.00E+00 3.17E-02 7.76E-03 2.72E-05 0.00E+00 7.76E-03 Cs-137 5.19E-02 5.75E-05 0.00E+00 5.19E-02.1.37E-02 3.74E-05 0.00E+00 1.37E-02 Mo-99 1.26E-04 4.59E-05 0.00E+00 1.26E-04 2.73E-05 1.49E-05 0.00E+00 2.73E-05 Zr-97 0.00E+00 0.00E+00

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

0.00E+00 Zr-95 4.68E-06 1.15E-06

4.68E-06 2.38E-06 7.69E-07

2.38E-06 Hb-95 1.49E-05 1.62E-06

1.49E-05 0.00E+00 0.00E+00

0.00E+00 1-132 7.24E-06 6.78E-07

7.24E-06 4.56E-06 5.79E-07

4.56E-06 2.21E-04 6.66E-06 0.00E+00 2.21E-04 6.17E-06 8.39E-07 0.00E+00 6.17E-06 Mn-54 9.72E-04 1.28E-05 0.00E+00 9.72E-04 1.19E-04 4.38E-06 0.00E+00 1.19E-04 O' Co-585.31E-05 3.23E-06 Ag-110m

5.31E-05 1.19E-05 1.77E-06

1.19E-05 2n-65 1.76E-02 6.36E-05 0.00E+00 1.76E-02 4.26E-03 4.10E-05 0.00E+00 4.26E-03 I-135 2.88E-04 1.16E-05

2.88E-04 7.74E-05 6.15E-06

7.74E-05 Fe-59 9.96E-06 1.54E-06 0.00E+00 9.96E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 4.52E-03 2.56E-05 0.00E+00 4.52E-03 1.28E-03 1.68E-05 0.00E+00 1.28E-03 Cu-64 1.13E-03 1.74E-04

1.13E-03 1.25E-03 2.18E-04

1.25E-03 Ha-24 2.11E-03 1.39E-05

2.11E-03 1.71E-03 1.40E-05

1.71E-03 La-140 6.55E-06 8.39E-07

6.55E-06 0.00E+00 0.00E+00

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

0.00E+00 8.08E-07 3.69E-07

8.08E-07 Cs-138 1. 32E-05 9. 57E

1.32E-05 3.48E-05 2.05E-06

3.48E-05 Ab-88 9.19E-06 1.16E-06

9.19E-06 3.49E-05 3.24E-06

3.49E-05 Cs-136 6.65E-06 1.08E-06

6.65E-06 0.00E+00 0.00E+00

0.00E+00 Hb-97 3.45E-06 6.18E-07

3.45E-06 0.00E+00 0.00E+00

0.00E+00 Sr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.74E-04 2.56E-04 0.00E+00 9.74E-04 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 1.98E-02 5.36E-03 0.00E+00 1.98E-02 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 4.68E-02 4.68E-02 Totals 1.34E-01 5.36E-03 0.00E+00 1.34E-01 3.34E-02 3.47E-04 4.68E-02 8.02E-02 Xe-133 2.58E-03 2.58E-05 0.00E+00 2.58E-03 2.10E-03 2.22E-05 0.00E+00 2.10E-03 Kr-88 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-133M 0.00E+06 0.00E+00 0.00E+00 0.00E+00 4.68E-05 1.30E-05 0.00E+00 4.68E-05 Xe-135 5.56E-03 1.62E-05 0.00E+00 5.56E-03 2.73E-03 1.13E-05 0.00E+00 2.73E-03 Kr-85M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

, sKr-87 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-138 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-135M 1.56E-08 3.08E-09 0.00E+00 1.56E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .

Totals 8.13E-03 3.05E-05 0.00E+00 8.13E-03 4.88E-03 2.81E-05 0.00E+00 4.88E-03

Ho LLD requirement in Tech Spec

, - .. .19- .- -. .- . _ _ . .. --

TABLE 1-la E. I. Hatch Hucl ear Plant UNIT 1 'Il

( -

i EFFLUENT AND WASTE DISPOSAL SENIANNURL REPORT 1983 LIQUII) EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Total 3 4 Error %

A. Fi ssion & act ivat ion product s

1. Tot al release (not i nc l udi ng- H3, ,

c ase s , a.1 pha) Ci 2.65E-01 1.79E-01 4.66E+01

2. Average diluted concentration during period uCl/mi 1.05E-07 8.06E-08

3. Percent of applicable Itmtt % 1.29E+01 2.94E+00 B. Tritium

1. Tot al release C1 2.85E+01 1.73E+01 3.68E+01l

2. Average di luted concentrat ion during period uCt/mi 1.13E-05 7.82E-06

3. Percent of applicable 1tmit % 3.76E-01 2.61E-01 C. Dissolved and entra ned gases

(g 1. Total release C1 4.57E-02 4.92E-03 1.00E+021

( / 2. Average diluted concentration during period uCi/mi 1.81E-08 2.22E-09

3. Percent of applicable limit % 4.53E-02 5.55E-03 D. Gross alpha radioactivity 4

l 1. Tot al release l Ci l 3.69E-041 6.45E-061 1.20E+021 l

lE. Volume of uaste (prior to dilution)l liters l 1.06E+071 7.69E+06l 1.00E+01l IF. Volume of dilution water used I liters l 2.52E+091 2.21E+09l 1.60E+02l O

TABLE 1-lb E. I.

Hatch Nuclear Plant

,, UNIT 2 i

\v'1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1983 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter 3

Est To t a l-4 Error %

A. Fission & activation products .

1. Total release (not including H3, cases, alpha) -

Ci 1.34E-01 3.34E-02

2. Average diluted concentration 4.92E+01 during period uCt/ml 5.98E-08

3. Percent of appi t c abl e limit 2.47E-08

% 4.91E-01 3.05E-01 B. Tritium

1. Total release

2. C1 8.40E+00 .

Average diluted concentration 8.08E+00 3.79E+011 durino period

3. Percent of applicable limit uCi/ml 3.74E-06 5.99E-06 t % 1.25E-01 2.00E-01 C. Dissolved and entrained gases

1. Total release

2. Average diluted concentration Ci 8.13E-03 4.88E-03 1.00E+02l

9. 3.

durina period Percent of appitcable Itmtt uCt/mi 3.62E-09 9.06E-03 3.61E-09 9.03E-03 D. Gross alpha radioactivity l 1. Total release l C1 l 3.78E-051 1.15E-05l 1.20E+02]

lE. Volume of uaste (prior to dilution >l liters l 9.82E+06l 6.41E+061 1.00E+011 lF. Volume of dilution uater used i liters l 2.23E+091 1.34E+09) 1.60E+02l l

I

/; ,

L.j' o

TABLE 1-2a E. I. Hatch Nuc lear Pl ant UNIT 1

.,s i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1983 l l

LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 3 4 3 4 Cs-144 Ci 8.86E-04 3.34E-04 l Tc-99m C1 1.28E-03 4.17E-04 Ce-141 Ci 0.00E+00 0.00E+00 Np-239 Ci 3.13E-04 3.39E-05 Cr-51 C1 2.39E-03 3.24E-04 I-131 Ci 8.25E-02 1.47E-02 Zr-69m Ci 0.00E+00 0.00E+00 W-187 Ci 0.00E+00 0.00E+00 F-18 Ct 4.20E-03 8.18E-04 I-133 Ci 3.97E-02 4.91E-03 B a.- 14 0 C1 0.00E+00 0.00E+00 As-76 Ct 5.?5E-04 1.46E-05 -

Cs-134 C1 3.46E-02 5.53E-02 Cs-137 C1 5.56E-02 7.26E-02 Mo-99 C1 1.02E-03 2.36E-04 Zr-97 Ct 0.00E+00 0.00E+00 Zr-95 C1 1.98E-06 5.20E-05 Nb-95 C1 0.00E+00 6.98E-05 I-132 C1 1.57E-04 3.47E-05 Cc-58 C1 3.93E-05 4.39E-04 7N

() Mr-54 Ac-110m C1 Ci 7.84E-04 8.92E-06 1.52E-03 1.65E-05 Zr-65 C1 1.06E-02 1.16E-02 1-135 C1 6.94E-03 6.50E-04 Fe-59 C1 0.00E+00 3.98E-05 Co-60 Ci 4.50E-03 5.19E-03 Cu-64 Ci 7.45E-03 2.29E-03 Na-24 C1 5.28E-03 1.09E-03 La-140 C1 1.99E-04 1.03E-04 Mn-56 Ci 0.00E+00 0.00E+00 Cs-136 C1 1.02E-03 4.04E-04 Cs-138 C1 2.33E-05 8.44E-05 Rb-88 Ci 7.76E-06 8.14E-05 Cd-109 Ci 8.80E-05 0.00E+00 Co-57 Ci 8.12E-05 0.00E+00 Ba-139 C1 2.88E-05 0.00E+00 I-134 Ci 0.00E+00 7.14E-07 Hb-97 C1 0.00E+00 1.44E-06 Sr-89 Ci 8.59E-04 2.27E-03 Sr-90 Ci 0.00E+00 0.00E+00 Fe-55 C1 3.81E-03 2.93E-03 P-32 Ct 0.00E+00 0.00E+00 l

l l

l Tot al fcr period (above) l Ci l l l 2.65E-01l 1.79E-01l h Xe-133 C1 2.44E-02 3.15E-03 l [/

(s, Kr-88 Xe-133M Ci Ci 0.00E+00 ,,0.00E+00 5.21E-05: 0.00E+00 Xe-135 C1 2.13E-02 1.77E-03 Kr-85M C1 0.00E+00 0.00E+00 Kr-87 C1 ~

0.00E+00 0.00E+00

~

Xe-130 Ci 0.00E+00 0.00$+00

[ Xe-135M C1 2.31E-06 0.00E+00

_ _ _ -Z?-

i TABLE 1-2b l

E. I.

Hatch Nuclear Plant rN UNIT 2 1 (v) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1983 l

l 1

LIQUID EFFLUENTS Nuclides Released CONTINUOUS MODE BATCH NODE (

Unit Quarter Quarter 3

Quarter Quarter 1 Ce-144 4 3 Ci 4 Tc-99m Ct 2.36E-04 1.55E-04 Ce-141 Ci 1.33E-04 1.09E-05 Np-239

- C1 0.00E+00 0.00E+00 Cr-51 C1 1.03E-03 3.83E-05 I-131 C1 3.25E-05 1.32E-04 Zn-69m Ci 1.04E-03 5.27E-04 W-187 Ci 4.12E-05 0.00E+00 I F-18 Ct 0.00E+00 0.00E+00 i I-133 Ci 2.11E-04 9.08E-04 l Ba-140 Ct 8.77E-04 2.90E-04 .-

As-76 C1 0.00E+00 0.00E+00 Cs-134 Ct 1.10E-04 2.93E-05 Cs-137 Ct 3.17E-02 7.76E-03 Mo-99 Ct 5.19E-02 1.37E-02 Zr-97 Ci 1.26E-04 2.73E-05 Zr-95 Ct 0.00E+00 0.00E+00 Hb-95 Ci 4.68E-06 2.38E-06 I-132 Ct 1.49E-05 0.00E+00

/N Co-58 Ct 7.24E-06 4.56E-06

(' 'f Mn-54 2.21E-04 Ct 6.17E-06 Ao-110m Ci ' 9.72E-04 1.19E-04 Zn-65 C1 5.31E-05 1.19E-05 I-135 Ct 1.76E-02 4.26E-03 Fe-59 C1 2.88E-04 7.74E-05 Co-60 Ct 9.96E-06 0.00E+00 Cu-64 Ci 4.52E-03 1.28E-03 Ha-24 C1 1.13E-03 1.25E-03 La-140 Ci 2.11E-03 1.71E-03 Mn-56 Ct 6.55E-06 0.00E+00 Cs-138 C1 0.00E+00 8.08E-07 Rb-88 Ct 1.32E-05 3.48E-05 Cs-136 Ct 9.19E-06 3.49E-05 Hb-97 C1 6.65E-06 0.00E+00 Sr-89 Ct 3.45E-06 0.00E+00 Sr-90 Ct 0.00E+00 9.74E-04 Fe-55 Ct 0.00E+00 0.00E+00 P-32 Ci 1.98E-02 0.00E+00 0.00E+00 0.00E+00 1 Total for period (above) l C1 ( l l 1.34E-01) 3.34E-021 l Xe-133 C1 l Kr-88 C1 2.58E-03 2.10E-03 l Xe-133M 0.00E+00

,J C1 0.00E+00 Xe-135 Ct 0.00E+00 4.68E-05 Kr-85M C1 5.56E-03 2.73E-03 m Kr-87 Ct 0.00E+00 0.00E+00 l Xe-138 Ci 0.00E+00 0.00E+00 l Xe-135M Ct 0.00E+00 0.00E+00 1.56E-08 0.00E+00 2~ GASEOUS EFFLUENTS 2.l'.. REGULATORY LIMITS a .. -(l) The release rate limit of noble gases from the site

'shall be:

'q - - - -.

t Qis 1.9 E6+ 1.0 EB + Qiv 11 E6 + 44 EB <l i +n - - - -

where Qs = Total release rate from main stack for both Units i in Ci/sec (elevated release) .

i Qy = Total release rate from vent in Ci/sec (ground release) ;

i = The individual nuclide n = total nuclides !

E6 = The average gamma energy per disintegration

i. EB= The average beta energy per disintegration (2) The release rate limit of all radioiodines 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 Qps + 1.5 X 10 6 qpy gi Where Qps = Total release rate from the main stack for both Units in Ci/sec (as elevated release)

Qpy

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

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

t Qis 12 E6 + 3.0 E B + Qiv 66 E6 + 140 E B 51

! i +n - - - -

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

r Qi, 24 E6 + 6.1 EB + Qiv -

1306 E + 270 E B $1 i +n - - -

(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:

1.3 X 106-Qps + 1.9 X 107 qpy si (4) The average release rate of all radio iodines and radioactive materials in particulate form from the site O .

.U with half . lives greater than eight days during any pariod of 12 consecutive months shall be:

2.6 X 106 Qps.+ 3.7 x 10 7 Qpy A 1

'(5) . 'The amount of : Iodine - 131 released during any calendar quarter shall not exceed 2 Ci/ reactor.

-(6) The amount J of Iodine -

131 released duriag any period of 12 ' consecutive months shall not exceed 4 Ci/ reactor.

~

c. Should the. conditions' of 2.1._ c (1), (2), or (3) l'isted 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 _repor t 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:

L Qis 47 E 6 + 12 Eg + Qiv 260 E6 + 540 EB >1 i+n m - -

(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 Qps + 7.2 X 107 Qpv >1 (3) . If- the amount of Iodine -

131 released during any calendar quarter is' greater than 0.5 Ci/ reactor.

d. The post-treatment offgas monitors' shall 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. a above. -The operability of- the automatic isolation valve shall be demonstrated quarterly.

e. 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- noble gases measured at the pretreatment monitor exceeds 260,000 uci/sec ' for a- period greater than ' 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , notify the Co:nmission - in writing within '10 days, identifying the causes of activity and in accordance with section 5.7. 2 of the E.T.S. -

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

O b 1s

, "h.- (1) Potentially ; - explosive gas mixtures of hydrogen and

[ oxygen conceined -in :the of fgas system downstroem of tha

, recombinars shall be -continuously monitored during

!- reactor power- operation for hydrogen concentration.

! The hydrogen gas monitoring system shall provide alarms O . locally and in the ' control room at a set point of 4%

. hydrogen concentration by volume.

continuous gas monitoring system and At its least one associated l, alarm system -shall be operable during reactor power 4

operation. If both of the hydrogen- gas monitors- or .

'both of the ' associated alarm systems are inoperable, l

. 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 downs.tream of the recombiner, hydrogen concentration readings are taken and logged every 4 j- 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 ~

i' power operation, it is determined. that- the hydrogen concentration limit is being exceeded, action shall be initiated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to return the hydrogen

! concentration to within the prescribed limit. If the i 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 1

. be stopped.

(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' i installation and shall be subject to daily sensor checks, monthly functional checks, 'and -quarterly >

calibrations until removed from service.

i. An unplanned or uncontrolled of fsite -release of radioactive l materials in gaseous effluents in excess of 150 Ci. of noble

! gas or 0.02 Ci. of radioiodines in gaseous form shall be repor ted ' to . the 30- days i NRC within in accordance with !

! section 5.7.2 of the E.T.S.

i

2. 2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL. RADI0 ACTIVITY i

Waste gas release at - Hatch is confined to four . pa ths. Each of these four . paths is continuously monitored for gaseous

concen tra tion 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 i-Each of thora continuous sempicrs has e flow controllar which I maintcins semplo flow within cbout c 10 perc:nt rengo over cech s:v:n day collection period. The offgas vent (elevated release) and the r=ctor building vents have flow measurement devices which ontinously record the flow rate of the gas released (accurary of base devices. are within 10% of the actual flows as measured during reoperational testing). The recombiner building vent flow on Unit a 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 (3 total curie release is calculated by the computer for each

() of the individual nuclides released. This number is multiplied by the average energy per disintegration (Ey &

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 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 1

Iodine releases are determined weekly for I-131, 1-133, 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 l and a quarterly total is prepared from the weekly l summaries. The percent Technical Specification for I-131 on Table 2-1 is based on the quarterly Technical Specification limit.

O Q,J h

-E- ]

U 1

3. PARTICULATE RELEASES Particulate ' releases are determined weekly for each vent.

Where significant activity is not measured MDA release 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.

Af ter 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 O 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 tritium by an independent-concentration, laboratory. 3 From the uCi/mi the grams water /ft , . 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 ' lodine countin g times -are 3000 sec and strontium separations are countec for 100' minutes.

' Regulatory Guide 1.21 requires that estimated total error <in analysis techniques be reported. These estimates are required for the total I-131-release, -total total ifission and activation with half gas release, O

particulates lives greater than . 8-day release, and total tritium release.

m

"Tha total or maximum orror escocietsd with tha offlusnt tocsurcment will includ2 the cumulativa errors resulting 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

{Vi i

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 ef fluents and solid waste."

, Es tima ted 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 69.09% 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%

E

.]

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

Statistical error 60%

Counting Equipment Calibration 10%

Vent Flow Rates 10%

O Vent Sample Flow Rates Non-Steady Release Rates 10%

10%

Losses From Charcoal Cartridge 10%

TI'U%

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%

j Countng. Equipment Calibration 10%

Vent Flow Rates 10%

Vent Sample Flow Rates 10%

Non-Steady Release Rates 10%

TUDT i

i i

u

l

4. . Tctn1 Tritium R11acs1 wsc doninstad by the resctor 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:

Water Vapor in Sample Stream Determination 20%

Vent Flow Rates 10%

Counting Calibration and Statistics 10%

Non-Steady Release 50%

. W% .

. 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.

4 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 curie quantity and principal radionuclide composition i of all radioactive solid waste shipped offsite.

b. Solid wastes in storage and preparatory to shipment shall be

O v

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.

4

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 3-1, O

l l

{

I

-30 --. --

TAILE 2-la UNIT 1 EFFLUENT AND WASTE' DISPOSAL SEMIAHHUAL REPORT 1983

, GASEQUS EFFLUENTS-SUMMATION OF ALL RELEA!;ES E. Unit Quarter " Quarter I. Hatch Hu:l ear Power Plant UNIT 1 Est Total 3 4

, Error %

A. Fission & ac t ivat ion gases

1. Total re l e sse C1 1.30E+04 [3591E+03

2. Aver 4Qe release rate for pertod uCi/see 1.65E+03 ,,4 . 0 6 E + 0 2 0.00E+011

3. % of Technical spectftcat on limit % 1.60E+00 ,_5.15E-01 B. Iodines

1. Total todtie-131 C1 3.00E-02 65 87E-03

2. Average release rate for period. uCt/see 3.81E-03 _8. !5 5 E-0 4 ' l.10E+02f

3. % ,p f Technical spec ificat on 1 t ra t t

% 1.50E+00 ',3. 4 3 E -01 C. Part i c ul at e s

1. PU't t c ul at es wi t h hal f-I t ues >8 days Ci 6.50E-03 l2.77E-03

2. Aigerace release r. ate for pertod uCi/sec 8.27E-04 _,3.44E-04 L.00E+02f

3. % ,p f Technical spec t f t c at on limit

% 1.49E+00 ,,3. 9 7 E-01

4. Grpss alpha radtonctivity C1 3.21E-06 2.37E-06 D. Tritium

1. Tot al release

2. Average release rate for period C1 9.97E+00 [II'12E+03 9.00E+011

3. uC1/see 1.27E+00 1.39E+02

("N % of Technical specificat on I t ta t t

\m I

% 2.84E+01 [,8.05E+02 I

c,nn'"ikMb oo z

%.1 O m

TAnLE 2-lb UNIT 2

'FFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1983 (Al V GASEQUS EFFLUENTG-SUMMATION OF ALL RELEA!;ES E.

I._ Hatch Nuclear Power Plant UNIT 2 Unit Quarter "6uarter E:st Total 3 4 !!rror %

A. Fi s:s on & ac t t. vat ion gases

1. To t. a 1 re l e as e

2. Average release rate for period C1 6.64E+02 _,8 . :. 5E + 0 3 uC1/sec 8.45E+01 1.01E+03 0.00E+01[

3. % j)f Technical specifieat on 1 t in t t % 3.86E-01 8.85E+00 B. Iodines -

z

1. Tit. a 1 iodine-131 C1 4.08E-03 ._1. 31 E-03

2. Average release rate for period uCt/sec 5.19E-04 1.63E-04 1.10E+02l

3. % j)f Technical specificat on 1 1 rn i t % 2.04E-01 __6. 54 E-0 2 1

C.

articulates

1. Particulates uith hal f-l i ues >8 days C1

2. Average release r ate for period uC1/sec 7.44E-04 9.47E-05

[i)9E-03 L.00E+02l

3. % of Technical specificat on l i in i t 3.59E-04 4 Gross alpha radioact ivi ty % 1.78E-01 6.27E-01 C1 1.23E-06 "7.86E-07 D. Tritium

1. Total release Ct 4.66E+00 [,[29E+00

2. Average release r.at e for period uC1/sec 5.93E-01 ,9.08E-01 9.00E+011

3. % j)f Technical specificat on l i tn i t % 4.62E+00 ,7.56E+00 i

O <

U 1

-32

l

TABLE 2-lc SITE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1983 GASEOUS EFFLUENTS-SUMMATION OF ALL REi"A!;ES

~

Unit Quartd Quarter Est Total E. I. Hatch Nu: lear Power Plant SITE 3 4 Error %

A. Fi sst on & ac t ivat ion gases

1. Total release C1 1.36E+04 ,_1.2)E+04 0.00E+01l

2. Average release rate for period uC1/see 1.74E+03 ,1.50E+03

3. % of Technical spec i fi c at on 1 1 :n i t % 1.99E+00 9.37E+00 B. Iodines -

1. Tot al todine-131 C1 3.41E-02 [_8. t 0E-03 L.10E+021

2. Average release rate for period uCt/sec 4.33E-03 1.02E-03

3. % of Technical spec i fi c at on 1 1 :n i t % 8.51E-01 _,2. 0 4 E-01 C.

art i c ul at es

1. Part i c ul at es wi t h hal f-11 oes >8 davs Ci 7.25E-03 [5.65E-03 L.00E+02l

2. Average release rate for period uCi/sec 9.22E-04 _7.04E-04

3. % of Technical specificat on l i en t t % 1.67E+00 _ _1. 0 2 E + 0 0

4. Gross alpha radioactivity C1 4.44E-06 __3.15E-06 D. Tritium

1. T o t. 41 re l e ase C1 1.46E+01 "1.13E+03 9.00E+01l I 2. Average release rate for period uC1/see 1.86E+00 _ _1. 4 0 E + 0 2

3. % of Technical spec i fi c at on l i in i t % 3.30E+01 8.12E+02 .

c sl l-

- 3 3-m

. .mx _

TR5LE 2-2a E. I. Hatch Nuclear Power Plant UNIT 1

() EFFLUENT AND WASTE DIGPOSAL SEMIANNUAL REPORT 1983 GASEQUS EFFLUENTS-ELEVATED RELEASE 1

CONTINUOUS MODE _

BATCH N0DE Hacl ides Released Unit Quarter Quarter Quarter Quarter i 3 4 3 4

1. - F! ssi on g ases .

Me-133 Cl 5.42E+03 1.13E+03 0.00E+00 0.00E+00 Me-131m Ci 3.61E+01 1.51E+02 __0.00E+00 0.00E+00 _

Kr-88 - Ci 3.76E+03 1.10E+03 0.00E+00 0.00E+00 Me-133M Ci 1.35E+02 2.24E+01 __0.00E+00 0.00E+00 Me-135 Cl 1.09E+02 4.86E+01 0.00E+00 0.00E+00 Kr-85M C1 2.35E+03 9.09E+02 0.00E+00 0.00E+00

(-131 Cl 0.00E+00 0.00E+00 'O.00E+00 0.00E+00 Kr-87 Ci 4.32E+02 9.39E+01 ,_0.00E+00 0.00E+00 Me-138 Cl 1.74E+02 1.45E+02 0.00E+00 0.00E+00 Me-137 Cl 5.90E+01 8.27E+01 "O.00E+00 0.00E+00 -

H-13 Ci 2.55E+02 5.60E+01 "0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4

Me-135M Cl 8.76E+01 5.66E+01 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 __0.00E+00 0.00E+00 f Kr-89 Ci 0.00E+00 0.00E+00 ,0.00E+00 0.00E+00 l t-135 Cl 1.44E+00 1.65E-01 0.00E+00 0.00E+00 Ar-41 Cl 2.67E+01 2.91E+01 0.00E+00 0.00E+00 T ot al for period Cl 1.28E+04 3.83E+03 ,0,00E+00 0.00E+00

2. todines t-131 Cl 5.12E-03 3.80E-03 'O.00E+00 0.00E+00 t-133 Cl 1.11E-02 8.74E-04 0.00E+00 0.00E+00 t-135 Ci 4.55E-03 2.56E-04 ['O.00E+00 0.00E+00

Total fer period Ci 2.08E-02 4.93E-03 0.00E+00 0.00E+0'O

3. Particulates Gr-89 C1 3.56E-05 9.17E-04 'O.00E+00 0.00E+00 Gr-90 Cl 5.31E-09 4.80E-07 'O.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 __0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 0.00E+00 ,0.00E+00 0.00E+00 t-131 Ci 6.45E-05 1.20E-05 ,_0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3a-140 Ci 7.15E-05 8.26E-05 'O.00E+00 0.00E+00 Cn-134 Cl 4.82E-06 5.47E-07 ,_0.00E+00 0.00E+00 Cn-137 Cl 1.17E-05 4.73E-06 ,_0.00E+00 0.00E+00 Co-144 Ci 0.00E+00 0.00E+00 __0.00E+00 0.00E+00

, 2 -95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Hb-95 Ci 0.00E+00 0.00E+00 "0.00E+00 0.00E+00 f.#o - 5 8 Cl 0.00E+00 0.00E+00 [0.00E+00 0.00E+00 Mn-54 Cl 0.00E+00 1.91E-07 ,0.00E+00 0.00E+00

! Fe-59 Cl 0.00E+00 0.00E+00 _,0.00E+00 0.00E+00 Co-60 Ci 2.56E-06 2.14E-06 0.00E+00 0.00E+00 IIIt-140 Cl 1.74E-04 1.49E-04 "0.00E+00 0.00E+00 Total for period Ci 3.65E-04 1.17E-03 ,,0j00E+00 0.00E+00

_ . . . . . . . . . . . . . , . - -.. - . . m- .

I TA!LE 2-2b I

E. I. Hatch Nuclear Power Plant UNIT 2 IFFLUENT AND WASTE DISPOSAL SEMIANHUAL REPORT 1983 GASEOUS EFFLUENTS-ELEVATED RELEASE l

CONTINUOUS MODE BATCH N0DE i NJclides Released Unit Quarter Quarter Quarter Quarter l 3 4 3 4 .

1. Fi ssion gases -

<e-133 Cl 1.07E+02 2.46E+02 [0.00E+00 0.00E+00

<e-131m Ci 7.14E-01 3.28E+01 0.00E+00 0.00E+00 Kr-88 Cl 7.43E+01 2.39E+02 __0.00E+00 0.00E+00 l<e-133M Ci 2.67E+00 4.86E+00 ,,0.00E+00 0.00E+00

<e-135 Ci 2.16E+00 1.05E+01 0.00E+00 0.00E+00 Kr-85M Ci 4.66E+01 1.97E+02 ,_0.00E+00 0.00E+00 t-131 CI 0.00E+00 0.00E+00 0.00E+00 6.00E+00 Kr-87 Ci 8.55E+00 2.04E+01 0.00E+00 0.00E+00

<e-138 Ci 3.44E+00 3.14E+01 __0.00E+00 0.00E+00

~~'

<e-137 Cl 1.17E+00 1.79E+01 [0.00E+00 0.00E+00 H-13 Ci 5.04E+00 1.22E+01 0.00E+00 6.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 __0.00E+00 0.00E+00

<e-135M Cl 1.73E+00 1.23E+01 0.00E+00 0.00E+00 t-133 Ci 0.00E+00 0.00E+00 9.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-135 Cl 2.86E-02 3.58E-02 'O.00E+00 0.00E+00 Ar -41 Ci 5.29E-01 6.31E+00 0.00E+00 0.00E+00 O

Total for- period C1 2.54E+02 8.31E+02 0.00E+00 0.00E+00

2. todines t-131 Ci 1.01E-04 8.25E-04 ,0.00E+00 6.00E+00 I-133 Ci 2.20E-04 1.90E-04 _0.00E+00 0.00E+00 t-135 Ci 9.00E-05 5.57E-05 ,_0.00E+00 6.00E+00 Total for period Ci 4.11E-04 1.07E-03 0.00E+00 0.00E+00

3. Particulates ,

St-89 Ci 7.04E-07 1.99E-04 ,,0.00E+00 0.00E+00 St-90 Ci 1.05E-10 1.04E-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 0.00E+00 0.00E+0G 0.00E+00 0.00E+00

[~131 Cl 1.28E-06 2.60E-06 "_0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3n-140 Cl 1.41E-06 1.79E-05 _0.00E+00 0.00E+00 Cn-134 Ci 9.54E-08 1.19E-07 0.00E+00 6.00E+00 Cn-137 Ci 2.32E-07 1.03E-06 ,_0.00E+00 0.00E+00 Cc-144 Ci 0.00E+00 0.00E+00 ,,0.00E+00 0.00E+00 2r-95 Ci 0.00E+00 0.00E+00 ,,0.00E+00 0.00E+00 ljp-95 Cl 0.00E+00 0.00E+00 __ 0 .00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 6.00E+00 Mn-54 Ci 0.00E+00 4.15E-08 [_0.00E+00 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.edE+00 i

O Co-60 1.n-140 Ci Cl 5.06E-08 3.44E-06 4.64E-07 "0.00E+00 0.00E+00 3.23E-05 ,,0.00E+00 0.00E+00 Total,,for period Cl 7.22E-06 2.54E-04 0.00E+00 0.00E+00

T AILE 2-2C E. It Hatch Nuclear Pouer Plant SITE

() IFFLUENT AND WASTE DISPOSAL SEMIANHUAL REPORT 1983 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE HJclides Released Unit Quarter Quarter Quarter Quarter 3 4 ,

3 4 .

1. F* ssion gases -

~

Me-133 Ci 5.52E+03 1.38E+03 0.00E+00 0.00E+00 Me-131m Ci 3.68E+01 1.84E+02 ~

0.00E+00 0.00E+00 j 15-88 Cl 3.83E+03 1.34E+03 0.00E+00 0.00E+00 Me-133M Cl 1.37E+02 2.72E+01 _0.00E+00 0.00E+00 Me-135 Cl 1.11E+02 5.91E+01 _0.00E+00 0.00E+00 Kr-85M C1 2.40E+03 1.11E+03 ~

0.00E+00 0.00E+00 t-131 Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 C1 4.41E+02 1.14E+02 0.00E+00 0.00E+00 Me-138 C1 1.78E+02 1.76E+02 "0.00E+00 0.00E+00 -

Me-137 Ci 6.02E+01 1.01E+02 ,_0.00E+00 0.00E+00 H-13 Ci 2.60E+02 6.81E+01 _ _0. 0 0 E + 00 0.00E+00 Kr-85 Cl 0.00E+00 0.00E+00 __0.00E+00 0.00E+00 Me-135M Ci 8.94E+01 6.89E+01 __0.00E+00 0.00E+00 t-133 Ci 0.00E+00 0.00E+00 ,_0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

(-135 Cl 1.47E+00 2.01E-01 0.00E+00 0.00E+00 Ar-41 Ci 2.73E+01 3.54E+01 0.00E+00 0.00E+00 Total for period Cl 1.31E+04 4.66E+03 ,,0.00E+00 0.00E+00

2. todines I 131 Ci 5.22E-03 4.62E-03 _,0.00E+00 0.00E+00 t-133 Cl 1.13E-02 1.06E-03 ,0.00E+00 0.00E+00 t-135 Ci 4.64E-03 3.12E-04 0.00E+00 0.00E+00 T ot al for period Ci 2.12E-02 6.00E-03 _,0. 0 0 E + 0 0 0.00E+00

3. Part i c ul at es fr-89 Ci 3.63E-05l 1.12E-03 __0.00E+00 0.00E+00 Gr-98 Ci 5.41E-09 5.84E-07 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 "0.00E+00 0.00E+00 Cr-51 Cl 0.00E+00 0.00E+00 ,0.00E+00 0.00E+00 t-131 Ci 6.58E-05 1.46E-05 __0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 ,_0.00E+00 0.00E+00 3 a- 14 0 Ci 7.30E-05 1.01E-04 ,_0.00E+00 0.00E+00 Cn-134 Ci 4.92E-06 6.65E-07 0.00E+00 0.00E+00 Cn-137 Cl 1.19E-05 5.76E-06 ~

0.00E+00 0.00E+00 Ce-144 Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2r-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hb-95 Cl 0.00E+00 0.00E+00 "0.00E+00 0.00E+00 Co-58 Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hn-54 Ci 0.00E+00 2.33E-07 0.00E+00 0.00E+00 7-sg fe-59 Ci 0.00E+00 0.00E+00 "O.00E+00 0.00E+00 Co-60 Ci 2.61E-06 2.60E-06 ,,0. 0 0E+ 0 0 0.00E+00

( } 1.a-140 Cl 1.77E-04 1.81E-04 ,0.00E+00 0.00E+00 ,

Tot al for period Ci 3.72E-04 1.42E-03 _0.00E+00 0.00E+00

._ . .__ _ _ _ . _ _ _ _ _ .__ _ _ __ ~ . _ _. _ - ._-- ____.- . -. . _ . . _ . _

i t

i TABLE 2-3a l

i E. I. Hatch H"uclear Power Plant UNIT 1 I

. "FFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1983

GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE t CONTINUOUS MODE BATCH MODE ,

NJclides Rele ased Unit Quarter Quarter __ Quarter Quarter t 3 4 -

3 4 ,

. . t

1. F1 ssion gas'es ,

<e-133 C1 1.61E+01 2.77E+01 ,,0.00E+00 0.00E+00

<e-131m Ci 0.00E+00 0.00E+00 __0.00E+00 0.00E+00 ,

l Kr-80 - C1 2.04E+00 9.31E-01 0.00E+00 0.00E+00 i :<c-133M Ci 8.00E+00 0.00E+00 __0.00E+09 0.00E+00

<e-135 Ci 5.87E+01 3.66E+01 ,,0.00E+00 0.00E+00 Kr-85M Ci 7.28E-04 0.00E+00 0.00E+09 0.00E+00

I-131 Ci 8.00E+00 9.00E+00 _,0. 00E + 0 0 6.00E+00 l Kr-87 Cl 6.02E+00 6.60E+00 _0.00E+00 0.00E+00 4

<e-138 Ci 5.15E+00 0.00E+00 0.00E+00 0.00E+00

<c-137 Ci 8.00E+00 0.00E+00 ,_0.00E+00 0.00E+00 -

H-13 Cl 6.02E-01 0.00E+00 ~

0.00E+00 0.00E+00 i Kr -85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l 4

<e-135M Ci 4.67E+01 7.85E+00 0.00E+00 0.00E+00 t-133 Ci 8.00E+00 0.00E+00 '0.00E+00 0.00E+99 :

Kr Ci 8.00E+00 0.00E+00 'O.00E+00 0.00E+00 t-135 Ci 8.00E+09 9.00E+00 ,,0.00E+00 0.00E+00 Ar-41 Ci 8.00E+00 0.00E+00 ,0.00E+00 0.00E+00 Total for period Cl 1.35E+02 7.97E+01 0.00E+00 0.00E+00

2. todines t-131 Cl 2.19E-02 2.80E-03 '0.00E+00 0.00E+09

(-133 Ci 5.27E-02 2.83E-03 "0.00E+00 0.00E+00 t-135 Ci 2.68E-02 1.89E-93 8.00E+00 6.00E+00 Tot al for period Cl 1.01E-01 7.53E-03 _ _0. 00E+ 00 0.00E+09

3. Particulates Gr-89 Ci 7.18E-05 8.02E-04 0.00E+00 0.00E+00 St-90 Ci 9.00E+00 9.00E+00 8.00E+99 6.00E+00 i

Co-141 Ci 6.00E+00 0.00E+00 "0.00E+09 0.00E+00-Cr Ci 3.55E-04 1.29E-04 [0.00E+00 0.00E+08 t-131 Cl 2.92E-03 2.55E-04 0.00E+00 0.00E+00 l Sn-113 Ci 0.00E+00 0.00E+99 ,'02 00E+00 0.00E+00 3a-140 Cl 1.10E-04 1.19E-05 -0.00E+00 0.00E+09 >

Cr.-134 Cl 1.01E-03 1.04E-04 "02_00E+00 0.00E+00 Cr.-137 Ci 1.30E-03 1.75E-04 ~

-9.00E+00 8.00E+00 Ce-144 Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2r-95 Cl 2.85E-09 0.00E+00 '0.00E+00 0.00E+00 Hb-95 Ci 9.00E+00 2.25E-06 'O.00E+00

~

6.00E+00 Co-50 Cl 1.72E-05 1. 53E -#5 ,0.00E+00 0.00E+091 Mn-54 C1 1.52E-06 3.50E-07 0.00E+00 0.00E+00i Fe-59 Ci 8.00E+00 4.31E-06 "0.00E+00 0. 00E+ 00 ),

Co-60 Ci 1.72E-04 7.68E-05 ,,0.09E+09 0.00E+00!

La-140 Cl 1.79E-04 2.39E-05 0.09E+00 0.00E+08 Total'for period Cl 6.14E-03 1.60E-03 ,,0.00E+00 0.EGE+00

. .. . . _ _ _ . . _ _ . _ _ __ . _-2 7 _ ___ _ .. .

u TAILE 2-3b ,

i i

E. I. Hatch Nuclear Pouer Plant UNIT 2 k EFFLUENT AND WASTE DISPOSAL SEMIANHUAL REPORT 1983 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTINUOUS MODE BATCH MODE H;clides Rele ased Unit Quarter Quarter Quarter Quarter 3 4 3 4

1. Fi ssion gases Me-133 Ci 2.16E+02 1.31E+03 'O.00E+00 0.00E+00 Me-131m - Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 4.31E+01 1.22E+03 __0.00E+00 0.00E+00 Me-133M Ci 4.78E+00 0.00E+00 0.00E+00 0.00E+00 Me-135 Ci 4.13E+00 2.90E+03 0.00E+00 0.00E+00 Kr-85M Ci 4.99E+01 1.07E+01 __0.00E+00 0.00E+00

(-131 Ci 0.00E+00 0.00E+00 ,_0.00E+00 0.00E+00 Kr-87 Ci 6.30E+00 9.20E+02 __0.00E+00 0.00E+00 Me-138 Ci 3.21E+01 6.69E+01 0.00E+00 0.00E+00 .-

Me-137 Ci 0.00E+00 3.06E+01 0.00E+00 0.00E+00 H-13 Ci 4.59E+01 4.45E+01 __0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 _ _0. 0 0 E + 0 0 0.00E+00 Mc-135M Cl 7.55E+00 8.13E+02 ,_0.00E+00 0.00E+00 t-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Cl 0.00E+00 0.00E+00 ____0.00E+00 0.00E+00 t-135 Ci 0.00E+00 0.00E+00 __

0.00E+00 0.00E+00 Ar-41 Ci 6.14E-01 2.85E-01 ,,0.00E+00 0.00E+00 T 3t al for period Ci 4.10E+02 7.32E+03 0.00E+00 0.00E+00

2. todines t-131 Ci 3.72E-03 4.70E-04 0.00E+00 0.00E+00 t-133 Ci 7.92E-03 1.77E-04 [0.00E+00 0.00E+00 t-135 Cl 4.60E-03 0.00E+00 0.00E+00 0.00E+00 T ot al for period Cl 1.62E-02 6.48E-04 ,,0.00E+00 0.00E+00

3. Particulates Gr-89 Ci 1.04E-04 2.56E-03 0.00E+00 0.00E+00 Gr-90 Cl 0.00E+00 0.00E+00 __0.00E+00 0.00E+00 Ce-141 Ci 1.01E-06 0.00E+00 0.00E+00 0.00E+00 Cr-51 Cl 6.03E-07 0.00E+00 'O.00E+00 0.00E+00 t-131 Ci 2.58E-04 9.87E-06 'O.00E+00 0.00E+00 Gn-113 Cl 0.00E+00 0.00E+00 ~

0.00E+00 0.00E+00 3a-140 __

Ci 9.29E-05 7.93E-06 0.00E+00 0.00E+00 Cn-134 Ci 2.78E-06 1.49E-06 'O.00E+00 0.00E+00 Cn-137 Ci 2.16E-05 1.61E-05 ~

0.00E+00 0.00E+00 Cc-144 Ci 0.00E+00 2.20E-05 0.00E+00 0.00E+00 2r-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hb-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C0-58 C6 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 G.00E+00

[ )\

Am Co-60 Ci 9.00E-06 1.06E-05 '0.00E+00 0.00E+00 f.a-140 Ci 2.47E-04 0.00E+00 0.00E+00 0.00E+00 .

Tot al for period Ci 7.37E-04 2.63E-03 0.00E+00 0.00E+00 A

TMLE ,2-3c E. It. Hatch Nuc lear Power Plant SITE EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1983 GASEQUS EFFLUENTS-GROUND-LEVEL RELEASE CONTINUOUS MODE ,,_, BATCH N0DE HJclides Released Unit Quarter Quarter Quarter Quarter 3 4 3 4 .

1. F ssion gases -

<e-133 Ci 2.32E+02 1.34E+03 ;;0.00E+00 0.00E+00

<e-131m Ci 0.00E+00 0.00E+00 _,0.00E+00 8.00E+00 Kt-88 Cl 4.51E+01 1.23E+03 0.00E+00 0.00E+00

<e-133M Ci 4.78E+00 0.00E+00 0.00E+00 0.00E+00

<e-135 Ci 6.28E+01 2.93E+03 __0.00E+00 0.00E+00 Kr-85M Ci 4.99E+01 1.07E+01 0.00E+00 0.00E+00 1~131 Ci 0.00E+00 0.00E+00 0.00E+00 8.00E+00 Kt-87 Cl 1.23E+01 9.27E+02 __0.00E+00 0.00E+00

<e-138 Ci 3.73E+01 6.69E+01 __0.00E+00 0.00E+00 '

<e-137 Ci 0.00E+00 3.06E+01 ,_0.00E+00 0.00E+00 N-13 Ci 4.66E+01 4.45E+01 __0.00E+00 8.00E+00 Kt-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

<e-135M Ci 5.43E+01 8.21E+02 "O.00E+00 0.00E+00 t-133 Ci 0.00E+00 0.00E+00 ,_0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Cl 0.00E+00 0.00E+00 __0.00E+00 0.00E+00 Ar-41 Ci 6.14E-01 2.85E-01 __0.00E+00 0.00E+00 Tstal for period Ci 5.46E+02 ?.40E+03 0.00E+00 0.00E+00

2. Iodines I 131 Cl 2.56E-02 3.27E-03 'O.00E+00 0.00E+00 I-133 Ci 6.07E-02 3.01E-03 0.00E+00 0.00E+00 I-135 Ci 3.14E-02 1.89E-03 __0.00E+00 0.00E+00 Total _ for period Cl 1.18E-01 8.18E-03 ,_0.00E+00 0.00E+00

3. Particulates St-89 Ci 1.75E-04 3.37E-03 0.00E+00 8.00E+00 St-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 1.01E-06 0.00E+00 'O.00E+00 0.00E+00 Cr-51 Ci 3.55E-04 1.29E-04 "O.00E+00 0.00E+00

(-131 __

Ci 3.18E-03 2.65E-04 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 ,_0.00E+00 0.00E+00 3a-140 Ci 2.03E-04 1.98E-05 0.00E+00 0.00E+00 Cn-134 '

Cl 1.01E-03 1.05E-04 "0.00E+00 0.00E+00 Cn-137 Cl 1.32E-03 1.91E-04 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 2.20E-05 "0.00E+00 0.00E+00 2r-95 Ci 2.85E-09 0.00E+00 "0.00E+00 0.00E+00 Hb-95 Ci 0.00E+00 2.25E-06 0.00E+00 8.00E+00 Co-58 Cl 1.72E-05 1.53E-05 [0.00E+00 0.00E+00 Hn-54 Cl 1.52E-06 3.50E-07 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 4.31E-06 0.00E+00 0.00E+00 Co-60 Cl 1.81E-04 8.74E-05 "0.00E+00 0.00E+00 V La-140 Cl 4.26E-04 2.39E-05 ,,0.00E+00 0.00E+00 Total for period Ci 6.87E-03 4.23E-03 0.00E+00 0.00E+00

~

TABLE 3-1 h- EFFLUENT AND VIASTE DISPOSAL SEMIANNUAL REPORT (YEAR)

July 1 - December 31 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 1983 FOR UNIT 1&2 A.501.1D %'ASTE SHi? PED OFFS!TE FOR BURIAL OR DISPOSAL (tJotIrradiated fuell uni, s month E st,To ot

1. Type of waste Pwd Enw. s

a. Spent resir.s. fdier sli.dges, evsporator r# 2 .15 E+2 tnttor s. cie.

~

C'i~ 10 .73 E+2 1.00 E+2

b. Dry compreum.e waste, contst:nnsted rd 'l .70 f+2 equip. etc. 9 Ci 17 02 E O 1.00 E+2

c. larad.attJ components, centrol mi n .nn E I rods. et:. Ci 0,00 E . E m' 4 .57 E+1

d. Other (des:nbe)

Absorbed Oil Ci 2 98 E-1 1 00 E+2

2. Estim:te of rasier nuclide composi: ion (by type of waste)

ISOTOPE PERCENT l CURIES

a. 44.4 476.22 2n-65 Cs-137 17.0 182.54 Cs-134 13.8 148.11 24.8 265.86 O b.

All Others Zn-65 Co-60 46.7 29.4 7.94 5.00 Cs-137 16.0 2.73 All Others .I 1.35

c. N/A N/A N/A

d. Zn-65 47.0 .14 Co-60 30.2 . .09 16.8 .05 Cs-137 _

6.7 .02 All Others

3. Solid Weste Disposition .

Number of Shipments Mode of Transpor:: tion D:stination 59 Tractor and Trailer .

Barnwell Tractor and Trailer Hanford, Wash.

- 2 1 ORRADIATED FUEL SHIPMCJTS (Dis ciition)

Mode eiTransportation Destfrution Number of Shior-ents 0 0 0 . _ _ _

O V

ML20100J321

Text

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