Text

Semiannual Rept,Plant Radioactive Effluent Releases,Jul-Dec 1984s
	ML20100L132
Person / Time
Site:	Hatch
Issue date:	12/31/1984
From:	Nix H; GEORGIA POWER CO.
To:	Grace J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	GM-85-194, GM-85-195, NUDOCS 8504160391
	Download: ML20100L132 (45)
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PLANT E. I. HATCH 5

4 4 UNITS NO. 1&2 SEMI-ANNUAL REPORT !

J PLANT RADIOACTIVE EFFLUENT RELEASES !

JULY 1, 1984 - December 31, 1984 i

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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 2 GASEOUS EFFLUENTS 24 2.1 REGULATORY LIMITS 24 2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 26 2.3 GASEOUS EFFLUENT RELEASE DATA 30 3 SOLID WASTE 30 3.1 REGULATORY SPECIFICATIONS 30 3.2 SOLID WASTE DATA 30 o

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PLANT E. I. HATCH

( ) SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES FIGURE LIST OF FIGURES PAGE l-1 METHODS OF MEETING TABLE II 7 COLUMN 2 MPC LIMITS (10 CFR 20) 1-2 LIQUID RADWASTE ANALYSIS - UNIT I 8-12 1-3 LIQUID RADWASTE ANALYSIS - UNIT.II 13-16 1-4 LIQUID RADWASTE DISCHARGE PERMIT 17 1-5a, b LIQUID RADWASTE DATA COMPILATION 18-19 TABLE LIST OF TABLES PAGE 1-la, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 20-21 l / l-2a, b - EFFLUENT AND WASTE DISPOSAL-SEMI-(~- ANNUAL REPORT, LIQUID EFFLUENTS-BATCH ONLY 22-23 2-la-c EFFLUENT AND WASTE DISPOSAL SEMI-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-ANNUAL REPORT, GASEOUS EFFLUENTS-GROUND LEVEL RELEASES 37-39 i' 3-la EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 40 i'

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PLANT RADIOACTIVE EFFLUENT RELEASES 1 LIQUID EFFLUENTS 1.1. REGULATORY LIMITS

('v) 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

(~N 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 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 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.

O 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 p batch are determined by a mixed nuclide MPC calculation performed I Q 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 radiation as shown'in Figure 1-1.

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

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

Although the MPC limit for tritium is greater than 9X 10 -6, a separate measurement is made for tritium since the gross beta technique does not provide an acceptable tritium measurement. A distillation and liquid scintillation counting technique is used to measure tritium concentration.

3 The maximum activity of gamma and peta values greater than 9 X 10 emitting nuclides with MPC except for the 29 uCi/ml, (V 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, I (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 fission reaction (eg.

4 in a 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 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:

i

A. Fiesion and activation (not including tritium, products The total ~ release values gases, alpha) are comprised of the sum of the individual radionuclido 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 (m)

U released to the river for the. respective quarter. Percent of applicable limit is determined f rom 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 quarter. l B. Tritium - The measured tritium concentration in a composite sample is used to calculate the total release and average diluted concentration during each period. Averagq diluted concentration divided by the MPC limit, 3 X 10 -> uCi/ml, is converted to percent to give the percent of applicable limit.

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

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

4 Details of the analytical procedures for liquid radwaste analysis are contained in operating procedure - HNP-7601.

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The following rx measurements are performed as indicated:

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MEASUREMENT FREQUENCY METHOD Each Batch Ge(Li) spectrometry with

1. Gamma Isotopic on-line computer.

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

3. Gross Beta Each Batch Gas flow proportional counting i

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

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

. counting

6. Tritium Monthly Distillation and liquid Composite scintillation counting 4

7. Alpha Monthly Gas flow proportional

,. , Composite counting

\~ / 8. Dissolved Gases Each Batch Ge(Li) spectrometry with on-line computer l

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

(] sample.

The Ge(Li) detector consist of a 10% and two 15% efficiency, 2.0 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 the on-line computer system. and net count data for all significant peaks are determined, Energy.

and quantitative reduction or MDA calculations are performed for the nuclider listed in Figure 1-1. The quantitative calculations include corrections for counting time, decay time, sample volume, ' sample geometry, detector efficiency, baseline counts, and branching ratio. MDA calculations, including the above corrections, are made based on the counts in two standard deviations of the baseline count at the location on the spectrum where a peak for that nuclide would be located 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 I (Ci/MPCi) and allowable release parameters. A sample printout is shown in Figures 1-2 and 1-3.

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

Although the computer could printout

[V. by a laboratory technician.

the release permit 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.

The liquid radwaste monitor setting is calculated by the computer based on the gamma activity as measured in the sample used for laboratory analysis. A coefficient has been determined which relates laboratory gamma counts to the monitor count rate. If the monitor count rate exceeds the calculated setting during discharge, then the liquid passing through the monitor is not representative of the sample which 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 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 1-5a and b.

I

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 ON ' 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 3.32 E-1 curies . for the third quarter and 4.96 E-1 curies for the fourth quarter. These values were approximately 1/38 for Unit 1 and 1/143 for Unit 2 for the third quarter and 1/26 for Unit- 1 and 1/111 for Unit 2 for the fourth quarter of the allowed 10 curies per quarter per reactor.

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

During this report period 30.0% of the li radwaste reaching the sample tanks was discharged; 70. 0% was quid recycled back into both of the reactor water systems.

3. A complete isotopic scan, gross beta, and gross gamma counts and computer analysis were performed prior to the release of each of the 947 discharge batches for both Units.

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

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

Number of batch releases: 947 Total time period for releases: 126,945 minutes Maximum time period for a batch release: 209 minutes Average time period for batch release: 134 minutes Minimum time period for a batch release: 1 minute

Average stream flow during periods of release of ef fluent into a

. flowing stream: 6,811 CFS

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FIGURE l-1 METHODS OF MEETING, TABLE II, COLUMN 2 MPC LIMITS iPC RANGE GAMMA-RAY BETA ALPHA (U Ci/ml) DifTTERS EMITTERS EMITTERS I-131,I-132, I-133 Sr-89, St-90 1-135, Cs-134 (Separation &

Gas Flow 49 X 10-6 (Ge(Li) Gamma-Ray Counting)

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

Nb-97, Br-82, Lu-174m, Sr-91 Ba-La-140, Na-24,Cu-64 Tritium CO-60, Fe-59, Zn-65 3 9 X 10-6 Ag-110m, Mn-54, CO-58 (Distillation &

Liquid Scintil-lation Counting)

Zr-Nb-95, Cs-Ba-137 As-76, F-18, Cr-51 All Others s Np-239, Ce-141 I so-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) t I ~h (O

i l_ . . - - . - - -. - - . _ . - - .- -. -

FIGURE 1-2 FROCEDURE: HHP-7601 DATA SHEET 3

,.......,.,...,.*.. 4,*#.++..++,.......... 4...

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E. I. H atch Huc l e ar Pl ant

Q , Liquid Radwaste Anal 4,a,s++.*,..++++r*+++s++++++++,ysis ,++++.

s..+.s+=+

Re ac t or# 1 Batch # 1010 Tank: FDST1 Recirc time: 70 minutes Comment: HIGH COND1TURP Run date: 12/09/84 1822 Count start d at e : 12/09/84 1723 Sample volume: 1000.00 ml Clock time: 3001 secs Geomet ry- c ode: 1LHB-0 Live time: 3000 secs l

Detector # 3 MCA# 3 Library:.LRWLB2 Operator: BDR EnergyGeV)= .10 + 1.004 Ch8 + 0.000E+00+Che^2 + 0.000E+00+Che'3 : If 09 34 1404 Eff =

1/C4.42?E-01 + E-<-1.9409E+00> + 437.205 + E's9.".?30E-01) J : 11-15 24 1507 where E = Energy in Nev.

s

FIGURE 1-2 (CONTINUED)

, ISOTOPE ENERGY CONCENTRATION ERPOR MPC C/MPC

/ (kev) (uC1/ml) (uCt.ml) (uCt/ml)

(,,)\ ...............................................................................'

Ce-144 133.54 <3.117E-07 1E-05 <3.12E-02 Tc-99m 140.51 <3.400E-08 3E-03 <1.13E-05 Ce-141 145.44 <6.980E-08 9E-05 <7.76E-04 Np-239 277.60 <3.187E-07 1E-04 <3.19E-03 Cr-51 320.08 <4.568E-07 2E-03 <2.28E-04 I-131 364.48 (6.412c-08 3E-07 <2.14E-01 2n-69m. 438.63 <5.165 -08 6F-as <a.61E-84 14a197 479.53 <2.365E-07 6E-05 <3.94E-03 F-18 510.99 <2.347E-08 5E-04 <4.69E-05 I-133 , 529.87 <5.876E-08 1E-06 <5.88E-02 Ba-140 537.32 <2.007E-07 2E-05 <1.00E-02 As-76 559.10 <1.219E-07 2E-05 <6.09E-03 Cs-134 605.00 4.438E-06 1.214E-07 9E-06 4.93E-01 Cs-137 661.89 6.348E-06 1.592E-07 2E-05 3.17E-01 Mo-99 739.58 <2.363E-07 4E-05 <5.91E-03 Zr-97 743.36 <3.219E-08 2E-05 <1.61E-03 Zr-95 756.72 <7.663E-08 6E-05 <1.23E-03 Hb-95 765.79 <3.889E-08 1E-04 <3.89E-04 1-132 772.61 <3.895E-08 8E-06 <4.87E-03 Co-58 810.76 <5.049E-08 9E-05 <5.61E-04 Mn-54 835.11 2.361E-07 4.046E-08 1E-04 2.36E-03 Ag-110m 884.67 <6.234E-08 3E-05 <2.08E-03 Zn-65 1115.51 2.125E-06 1.734E-07 1E-04 2.12E-02 I-135 1260.41 <9.634E-08 4E-06 (2.41E-02 y_)

') Fe-59 Co-60

.1291.b6 1332.06

<6.415E-08 1.339E-06 8.929E-08 6E-05 3E-05

<1.07E-03 4.46E-02 Cu-64 1345.90 <5.31?E-06 2E-04 <2.66E-02 Ha-24 1368.53 <3.296E-08 3E-05 <1.10E-03 La-140 1596.49 <2.033E-08 2E-05 <1.02E-03 Mn-56 1810.69 (4.929E-02 1E-04 (4.93E-04 Sr-89 (BETA) < 2. 280E- 08 3E-08 <7.60E-01 Sr-90 (BETA) <1.040E-08 1E-08 <1.04E+00 H-3 (BETA) 9.800E-04 1.060E-04 3E-03 3.27E-01 Fe-55 ' BETA) <9.000E-07 8E-04 <1.13E-03 P-32 ( EC > (1.000E-07 2E-05 (5.00E-03 Measured t ot al s 9.945E-04 1~. 0iO E- 0 4 1.21E+00 LLD totals <9.097E-06 <2.21E+00 Totals 1.004E-03 3.41E+00 DISSOLVED GASES Xe-133 81.00 <9.605E-08 4E-05 <2.40E-03 Kr-88 196.32 <1.419E-07 4E-05 <3.55E-03 Xe-133M 233.22 <3.933E-07 4E-05 <9.93E-03 Xe-135 249.79 <4.580E-08 4E-05 <1.15E-03 Kr-85M 304.87 <2.818E-07 4E-05 (7.05E-03 l

Kr-87 402.58 <8.280E-08 4E-05 <2.07E-03 Xe-138 434.49 (4.017E-08 4E-05 <1.00E-03' Measured gas totals 0.000E+00 0.000E+00 0.00E+00 r3 <2.70E-02 l 1 LLD gas tot als <1.082E-06

's / Tot al gas 1.082E-06 2.70E-02

FIGURE 1-2 (CONTINUED)

GPOSS ACTIVITY Error B ac t ground Time vol Het Counter Cross Activity (cpm /ml) 1 Sigma (Nine mi Counts Counts -

----- ---- _---- 1.58E+00 1718 20.0 2 1.45E+01

')11 Crystal 2296 7.15E+00 1.14E*00 -.

( creportional 330 ,

187 10.0 2 g al l ons ESTIMATED WASTE TAHK VOLUME = 11000.00 .

ESTIMATED ACTIVITY THIS BATCH ( 4.14E+04 Microcuries)

EXCLUDING GASES:

4.14E-02 Curies Curies ( 6.03E+02 Microcuries)

EXCLUDING H-3 AND GASES: 6.03E-04 IS 603.11 uCi

==

THE ACTIVITY OF THIS' BATCH (EXCLUDING H-3 RHD GASES)

THE MAXIMUM TAHK RELEASE LIMIT IS 300-uCi LAB SUPERVISON APPROVAL HEEDED FOR THIS RELEASE RELEASE APPROVED BY: VM Liquid P aduast e Pele ase S u nim arv excluding H-3 and dissolved games (uCi<ml): 1.45E-05 +- 2.82E-07

1) Meas. conc., : 9.94E-04 +- 1.06E-04 Meas. conc., including H-3, excluding gase s (uCi/ml): 9.10E-06 2)Calcul at ed LLD concent rat i on, excluding dissolved g ase s 1.21E+00

)Calcul at e d MPC rat io (CrMF C, of me as. ,i nc l udi ng g as e s):

V 10000

4) Minimum dilution flow r at e ( g p m '> :

5) Maximum t anL di s c h arge fIou e at e (gemT: 4?f?4 6)Specified t ant flow r at e (gpm): 75 7)Padu ast e monit or trip setting: 1603 B = 1200 , Monitor EG CF3 A= 1.45E-05 ,uct/ml F = 2 ,Conserv. F ac t or C= 10340000.00 , Monitor CPS per uCi /ml A includes me as ured ' selected','other' nuclides and gases but excludes:

Sr-89, Sr-90, H-3, Fe-55, P-32 8)Est i mat ed c onc . of me as . nuclides at poin' of retease (uci/ml): 7.403E-06

9) Monitor maximum to ensure 10CFR20 T imi e r ar e not e<ceeded: 16692 ESTIMATED DOSES THIS BATCH, MPEM Thyroid Vidney Lung GI-LLI W. Body Bone Liver 0.00E+00 0.00E+00

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

/

Xe-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

\

' 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.t0E+00 Ce-144 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 0.00E+00 0.00E+00 Cc-141 0.00E+00

r i u.4 1-2 (COMTINU20)

Kr183 0.00E+00 0. gee +00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 'O.00E+00 Xe-133M 0.00E+00 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+ve 0.00E+00 Xe-135 0.00E+00 0.00E+00 0.00E+0C 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 0.06E+00 0.00E+00 0.00E+00 f' x 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 0.0&E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 A- ') I-131 0.00E+00 0.00E+0V 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-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 B a- 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 1.36E-03 6.98E-04 1.66E-03 0.00E+00 5.38E-04 1.78E-04 2.90E-05 Cs-137 1.14E-03 1.28E-03 1.75E-03 0.00E+00 5.94E-04 1.98E-04 3.39E-05 No-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2c-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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00C+00 0.00E+00 Co-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 7.97E-08 0.00E+00 4.r3E-07 0.00E+00 1.24E-07 0.00E+00 1.28E-06 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 1.87E-05 1.30E-05 4.13E-05 0.00E+00 2.76E-05 0.00E+00 2.60E-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 4.6?E-06 0.00E+00 2.12E-06 0.00E+00 0.00E+00 0.00E+00 3.99E-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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

[_j Mn-56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (s / 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 4.03E-07 0.00E+00 4.03E-07 4.03E-07 4.03E-07 4.03E-07 4.03E-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-?2 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 0.00E+00 Tot al 2.52E-03 1.99E-03 3.45E-01 4.03E-07 1.16E-03 3.76E-04 1. ;0E-0 4 Curnul at i ve dose this YEAR (includes estimate for this ba'ch):

Whcle body 2.27E-00 rn r e n. F e r c ent of Tech Spec L i nii t : 7.55E+01 Bone 2.47E+00 mrem Percent of Tech Spec L i rn i t : 2.47E+01 Liver 3.10E+00 mrem Percent of Tech Spec Limit: 3.10E+01 Thyrcid 1.?6E-01 mren. Fercen' of Tech Spec Limit: 1.SiE+00 Kidney 1.03E+00 meen. Percent of Tech Spec Limit: 1.03E+01 Lung 3.34E-01 mrem Percent of Tech Spec L i ni t t : 3.34E+00 GI-LLI 2.02E-01 mrem Percent of Tech Spec Limit: 2.02E+00 Cumul at ive doze this QUAPTER

includes e s t i m at e for t hi s b at ch):

Whole body 8.06E-01 nir e m Percent of Tech Spec Limit; 5.38E+01 Bone 6.36E-01 m r e rn Percent of Tech Spec Limit: 1.27E+01 Liver 1.10E+00 mrem Percent of Tech Spec Lirnit: 2.20E+01 Thyroid 1.70E-02 meen. Percent of Tech Spec Lirnit: 3.40E-01 Kidney 3.70E-01 mr e rn Percent of Tech Spec L i nii t : 7.40E+00 Lung 1.20E-01 rar e rn Percent of Tech Spec Limit: 2.11E+00 GI-LLI 3. 97E-02 mr e rn Percent of Tech Spec Limit: 7.74E-01

/

D} Projected cumul at ive dose this OVAFTEP (includes e s t i mat e for this batch):

Whole body 1.06E+00 mrem Bone 8.33E-01 mrem Liver 1.44E+00 mrem Thyroid 2. 23E-02 mre rn

Kidney 4.84E-01 nir e n .

I Lung 1.58E-01 mrem t GI-LLI 5.07E-02 mrem i.

Cumul at i ve me asured act ivi ty this YEAR < includes e s t i n. at e for this batch):

9.577E-01 Curies, excluding H-2: and diisolved g aJ e 2

> D i \ ________________________________________________________________________________

i !

!. ' LRW treatment system should be OPERABLE due to projected dose for Whole Body a

i i i l

! LRW treatment system should be OPERABLE due to projected dose for BONE i

i LRW treatment system should be OPERABLE due to projected dose for LIVER LRW treatment systeni has been deraons tr at e d OPER ABLE, confirmed by: BDR 2

BRTCH# 1010 DATA SUCCESSFULLY STORED i

j SPECTRUM STORED AS: LRW1 i

s t

i i

f 1

i 1-a l

I J

I 4

i l . ., ,

FIGURE 1-3 PRO 3EDURE: HNP-7601 DATA SHEET 8

,++++.. ,++,,,.,.+++.,,,.....++...,..,s++e,..+,

's f

E. I. Hatch Nuc le ar Plant +

( )

w/ Liquid Radwaste Analvsis

Re ac t or # 2 B at c h# 834 Tank: CWSTA2 Recirc time: 65 minutes Comment: HICH CONDU,CTIVITY Run date: 12/12/84 1611 Sample volume: 1000.00 ml Count st art d at e : 12/12/84 1410 Geometry code: 1LHB-0 Clock time: 3000 sees Detector # 3 Li"e time: 3000 secs Library: LRWLB2 HCA# 3 Operator: CAF Energy (kev)= -1.05 + 1.000+Ch# + 0.000E+00-Ch#'2 + 0.000E+00*Ch#^3

12/11/84 1737 Eff = 1/C4.42SE-01 +

where Ee Energy in Nev. E^(-1.9409E+00' + 487.205 + E^(9.5930E-01)] : 11/15/84 1507 ISOTOPE ENERGY CONCENTRATION EFPOP MPC C NPC (kev) (uCi/ml) (uC1/ml) (uCi/ml)

/'_ i ==============================================a m===============================

U Ce-144 133.54 <2.635E-07 1E-05 <2.64E-02 Tc-99m 140.51 <3'.106E-08 3E-03 <1.04E-05 Ce-141 145.44 <5.946E-0? 9E-05 <6.61E-04 Np-239 277.60 <2.594E-07 1E-04 <2.59E-03 Cr-51 320.08 <4.698E-07 2E-05 <2.35E-04 I-131 364.48 <5.631E-08 3E-07 <1.SSE-01 Zn-69m 438.63 <4.938E-08 6E-05 <8.23E-04 W-187 479.53 <2.088E-07 6E-05 <3.4SE-03 F-18 510.37 1.710E-07 1.776E-08 5E-04 3.42E-04 I-133 529.87 <6.380E-08 1E-06 <6.3SE-02 Ba-140 537.32 <1.905E-07 2E-05 <9.53E-03 As-76 559.10 <1.171E ,07 2E-05 <5.56E-03 Cs-134 604.23 3.357E-06 1.0??E-07 9E-06 3.73E-01 Cs-137 661.13 6.328E-06 1.641E-07 2E-05 3.16E-01 flo-99 739.58 <3.571E-07 4E-05 (8.93E-03 Zr-97 743.36 (4.259E-08 2E-05 <2.13E-03 Zr-95 756.72 (8.318E-08 6E-05 <1.39E-03 Nb-95 765.79 <4.759E-08 1E-04 <4.76E-04 I-132 772.61 :3.753E-08 8E-06 <4.69E-03 Co-58 810.76 (6.102E-08 9E-05 <6.87E-04 Mn 834.24 1.326E-06 8.492E-08 1E-04 1.33E-02 Aq-110m 884.67 (8.748E-08 3E-05 Zn-65 1114.77 <2.92E_03 5.549E-06 2.720E-07 1E-04 5.55E-02 I-13" 1260.41 <1.084E-07 AE-06 < 2. 71 E.-0 2 Fe-59 1291.56 (9.066E-08 6E-05 <1.51E-03

/ Co-60 1331.60 2.047E-06 1.144E-07 3E-05 6.82E-02 k ,)s Cu-64 1345.90 (7.107E-06 2E-04 <3.55E-02 Na-24 1367.79 3.618E-06 1.480E-07 3E-05 1.21E-01 La-140 1596.49 <3.158E-08 2E-05 <1.58E-03 Mn-56 1810.69 <5.280E-08 1E-04 <5.28E-04 (CONTINUE 3)

Sr-89 (BETM) <2.340E-08 3E-08 <7.80E-01 Sr-90 (BETA) <1.070E-08 1E-08 <1.07E+00 H-3 (BETA) 4.800E-04 5.200E-05 3E-03 1.60E-01 Fe-55 < BETA) <7.000E-07 8E-04 <8.75E-04 P-32 ( EC > <8.000E-08 2E-05 _4.00E-03 Measured tot als 5.024E-04 5.'200E-05 1.11E+00 (V) LLD totals . <1.069E-05 <2.24E+00 Tot al s 5.131E-04 3.35E+00 DISSOLVED GASES Xe-133 81.00 <8.907E-08 4E-05 (2.23E-03 Kr-88 196.32 <9.299E-08 4E-05 <2.32E-03 Xe-133M 233.22 <3.646E-07 4E-05 <9.12E-03 Xe-135 249.40 2.673E-07 3.609E-OS 4E-05 6.68E-03 Kr-85M 304.87 <2.141E-07 4E-05 <5.35E-03 Kr-87 402.58 <3.942E-08 4E-05 <9.85E-04 Xe-138 434.49 <1.643E-09 4E-05 (4.11E-05 Me asured gas t ot al s 2.67?E-07 3.609E-08 6.6SE-03 LLD gas t ot al s <8.018E-07 <2.00E-02 Tot al gas 1.069E-06 2.67E-02 GPOT9 ACTIVITY Count er Gross E ad ground T i rn e vol Het Error Counts Counts n.1 Activitv<cpn, nil ) 1 s i g rci a

______ . ____ _': ll i n s____ ____ ________ ________

/ ) Well Cry s t a l 2291 1793 20.0 2 1.23E+01 1.60E+00 V Proportional 311 20T 10.0 2 5.20E+00 1.14E+00 E57IMATED WASTE TAth V O L'J f t E = 5553.00 g al l ons ESTIMATED ACTIVITY THIS EATCH EXCLUDING GASE9: 1.06E-02 Curtes ( 1.0iE*04 fli croc ur i e s S EXCLUDING H-3 AND CA5E3: 4.71E-04 Cariea r 4. TIE-02 Microcuries>

THE ACTIVITY OF THIS FATCH (EXCLUDING H-3 Ar4D GAiEi II 470.71 uCi

-THE NAXIMUM TANE FELEASE LIMIT IS 300 uCi LAE SUPEPVIs0N AFPROVAL NEEDED FOR TnI5 FELEA5E PELEASE APPROVED EY: RV Liquid P adu as t e Peleare S unan ar o

1) Meas. conc., exc l uding H-3 anc di s solvec g ases ( u C 1/ nil ) : 2.24E-05 +- 3.94E-07 Me as . conc., including H-3, excluding gases : 5.02E-04 +- 5.20E-05 l

2)Calcul at ed LLD concent r at ion, excluding dissoloed gases (uCi/ml): 1.07E-05 3)Calcul ated MPC rat io (C/MPC of me as . , i nc l udi ng g as e s ): 1.11E+00 .

l l

4) Minimum dilution flou r at e ( g p ni) : 10000 l

5) Maximum tank discharge flow rat e (gpm): 87704

FIGURE 1-3 (CONTINUED) 6)Specified scnk flow rat e (gpm): 75 7)Radwaste monitor trip setting: 1436

,-s; R.= 2.27E-05 ,uci/mi R = 300 , Monitor BG CPS

( ) C'= 23920000.00 , Monitor CPS per uCi/ml F = 2 ,Conserv. Factor

\s_/ A inc ludes ,me asured ' selected','other' nuclides and gase s but excludes:

Sr-89, Sr-90, H-3, Fe-55, P-32 8)Est imat ed conc. of meas. nuclides at point of release (uCi/ml>* 3.740E-06

9) Monitor maximum to ensure 10CFR20 limits are not exceeded: 65368 ESTIMATED LOSES THIS EATCH, MREM 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 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-88 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 1-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn -i ? nt 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+02 0.00E+00 0.00E+00 0.00E+00 F-13 2.96E-14 2.67E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.90E-15 I-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.~00E+00 0.00E+00 0.00E+00 Es-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 5.18E-04 2.66E-04 6.33E-04 0.00E+00 2.05E-04 6.51E-05 1.11E-05 Cs-137 5.75E-04 6.45E-04 8.79E 0.00E+00 2.99E-04 9.94E-05 1.71E-05 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 0.00E+00 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.

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+00 0.00E+00 0.00E+00 Mn-54 2.26E-07 0.00E+00 1 1SE-06 0.00E+00 3.52E-07 0.00E+00 3.62E-06 Ag-110ni 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 2.46E-05 1.71E-05 5.44E-05 0.00E+00 3.64E-05 0.00E+00 3.43E-05 1-135 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 3.61E-06 0.00E+00 1.64E-06 0.00E+00 0.00E+00 0.00E+00 3.08E-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 2.95E-07 2.99E-07 2.95E-07 2.95E-07 2.95E-07 2.95E-07 2.95E-07 La-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l 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 9.97E-08 0.00E+00 9.97E-OS 9.97E-08 9.97E-08 9.97E-09 9.97E-08 eN Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l

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

(' -) P-32 0.00E+00 Total 1.12E-03 9.29E-94 1.57E-03 3.95E-07 5.41E-04 1.69E-04 9.72E-05

FIGURE 1-3 (CONTINUED)

Cumuletive doso this YEAR (i nc l ude s est i mat e for t hi s batch):

Whole body 5.81E-01 mrem Percent of Tech Spec Limit! 1.94E+01 Bone 5.63E-01 meem Percent of Tech Spec Limit: 5.63E+00

,-q Liver 7.99E-01 mrem Percent of Tech Spec Limit: 7.99E+00 (N/ ) Thyroid 1.01E-01 mrem Percent of Tech Spec Limit: 1.01E+00 Kidney 2.69E-01 mrem Percent of Tech Spec Limit: 2.69E+00 Lung 8.64E-02 mrem Percent of Tech Spec Limit: 8.64E-01 GI-LLI 4.35E-02 mrem Percent of Tech Spec Limit: 4.35E-01 Cumul at ive dos e this QUARTER (includes est imate for this batch):

Whole body 1.81E-01 m r e ra Percent of Tech Spec Limit: 1.21E+01

sone 1.4?E-01 mrem Percent of Tech Spec L i ns i t: 2.94_E+00 Liver 2.49E-01 mrem Percent of Tech Spec Limit: 4.99E+00

_ Thyroid 1.43E-03 mrem Percent of Tecn Spec Limit: 2.65E-02 Kidney 3. 39E-02 niren. Percent of Tech _ Spec Limit: 1.68E+00 Lung 2.74E-02 mrem Percent of Tech Spec Limit: 5.47E-01 4 GI-LLI 8.31E-03 meeni Percent of Tech ' Spec Liniit: 1.66E-01 Projected cumul at ive dose t'hi s GU ARTER sincludes estimate for this batch):

Whole body 2.2SE-01 mrem Bone 1.85E-01 mrem Liver 3.13E-01 mrem

Thyroid 1.79E-03 meera Kidney 1.05E-01 mrem Lung 3.44E-02 mreni GI-LLI 1.04E-02 mrem Cumulative me asure d ac t i vi t y this YEAP (includes e s t i m at e for this b at ch)

2.442E-01 Curies, excluding H-3 and diisol"ed g as e s LRW t r'e .t n.e n t systera should be OPEFAELE due to pro,1ected dose for Whole Ecdv LPW t re at me nt s y s t e rn h as been dem:ns' r at e d OPEP4 ELE. confirmed bo: GAF -

BATCHe 834 DATA SUCCEiiFULLY STOPEL SPECTFuri STORED Ai: LFH2 i

s i 1 FIGURE 1-4 PL

-- A..r.J.1. r.. l .. - I.tA. T.C.i_t DATCH ND.

L

- T O'J I D R? fE'AG TF__O.I.S_ci

=------ t.A..R

- --- - C C_P CR M I T UNIT W TAM < TO eE RELCACCD .

DATE RCACCR4 FCn I;CCCEOI1Y CF DISCHARCE __,

GECIRC STA9T tit:2 SAMPLE TIME RECIRC. DURATION MI??JTES V .,

1. LASCRATCRY ArALYSIS (1) MEAS 1JRED RADICNUCLIDE CONCENTRATICN .E + .E uCi / nil (2) CALCU_ATED LLO LIMIT CC+4CENTRATIONS uCi/ nil (3) CALCULATED MFC RATIO: 2.(Ci/McGi) -

(4) MINItC1 DILUTICN FLCW R6TE CPM (5) MAX. CALCULATED TANT ( DISCHARGE F ATE: .JEE

( SEC. F.5.g) _ CPM (6) SPECIFIED TAN'( DISCHARGE RATE: 4(5)/2 CPM (7) RADWASTE MONITOR TRIP SETTINCI ___ CPS A = Ce(Li)(1) uCi/ml B = MONITOR BG _, CPS C = MONITCR CPS F = CONSERVATIVE PER Ce(Li) uCi/ml FACTOR tr:NITOR ALARM SETPOINT (CPS) = (C X A X F) +B+3h COT LETED BY .DATC l

COMPCSITE LITER STORED (INITIALS) LAS FCRE*AN AcFr.CVED (S) R/4NASTE ICNITOR MAX. CPS TD SE WITHIN 10 CFR EO LIMIT 5:

CXA: ( 61 ' U 1_

!!. C:ERATIC.;3 (6) (3) cps J I N ,. . .

(9) LIGUID RA_7 WASTE MCN*TCR TRIP SET AT: CPS (10) CCNFIRPED DILLi~'*4 FLC'.J RATE CPM (l1) VALVE LI <EU? C:ECMED AG FER ENo-TN3 CIS. INTEGRATCR DIS. RATE lD*L. TCTAL R*VER EL. MON!TCE VOL -T P C N". . C P '" I Ct4 C. C Sj-S -.I C._A T~_ . . .. T_I_-F_ F.f.5..

gT4:tT I l _

.:2. .--_ -_------------_---.-----

CC '. LETED BY CATE MIN. C/4 .

CtAATICN TOTM.

REI_ EASE

O 10 MIN AFTER START

- AFTER FLtGHINO III.LASORATCRY (12) TOTAL TMs VC'_ty.E DISCHARCEO (Cte_. X 3,7551 ml (133 TOTAL ACTIVI~Y DISCHAROEO I(1) X (12)I uC1 (14) RIVER FLCW RATE (FRCM FEAR 2.4-6) _ CFS x ..___________________. . _ _ _ _ - _ - <

CCMPLETED GY CATE 4

. _ - . _ _ _ _ _ _ _ _ . . _ . . . .- .--_-t o

FIGURE 1-Sa Li qui d Rcdweste Dat a Compi l at i on for Reg. Guide 1.21 Report E. I. Hatch Nuclear Plant UNIT 1

~

k,,) ,,

Total Activity (Curies)

Quarter 3, 1984 Quarter 4, 1984 Batches 575 thru 847 Batches 848 thru 1070 Hame Measured Error H'igh LLDs Tot al Me asured Error High LLDs Tot al Ce-144 7.70E-03 2.58E-04 0.00E+00 7.70E-03 1.22E-03 1.53E-04 0.00E+00 1.22E-03

-Tc-99m 4.85E-04 9.04E-06

4.85E-04 1.38E-05 1.83E-06

1.38E-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 0.00E+00 0.00E+00

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

0.00E+00 Cr-51 3.58E-03 1.04E-04

3.58E-03 2.55E-03 8.72E-05

2.55E-03 I-131 1.65E-02 4.95E-05 0.00E+00-1.65E-02 4.13E-03 2.91E-05 0.00E+00 4.13E-03 Zn-69m .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 F-18 '2.96E-03 1.48E-05

2.96E-03 7.87E-04 9.67E-06

7.87E-04 I-133 1.02E-02 4.03E-05

1.02E-02 1.03E-04 5.64E-06

1.03E-04 Ba-140 0.00E+00 0.00E+00 + 0.00E+00 0.00E+00 0.00E+00

0.00E+00 As-76 7.39E-05 6.52E-06

7.39E-05 0.00E+00 0.00E+00

0.00E+00 Cs-134 5.84E-02 8.63E-05 0.00E+00 5.84E-02 1.12E-01 1.04E-04 0.00E+00 1.12E-01 Cs-137 8.59E-02 1.09E-04 0.00E+00 8.59E-02 1.58E-01 1.32E-04 0.00E+00 1.5?E-01 Mo-99 1.04E-03 1.23E-04 0.00E+00 1.04E-03 8.14E-04 1.23E-04 0.00E+00 8.14E-04 Zr-97 0.00E+00 0.00E+00 + 0.00E+00 0.00E+00 0.00E+00

0.00E+00 Zr-95 4.15E-05 5.65E-06 + 4.15E-05 0.00E+00 0. JE+00 *. 0.00E+00 Hb-95 1.15E-04 5.77E-06 + 1.15E-04 9.58E-05 5.99E-06

9.58E-05 I-132 1.08E-05 2.36E-06 + 1.08E-05 0.00E+00 0.00E+00 + 0.00E+00 Co-58 4.66E-04 1.31E-05 0.00E+00 4.66E-04 4.61E-03 3.46E-05 0.00E+00 4.61E-03 1.84E-03 2.54E-05 0.00E+00 1.84E-03 9.69E-03 4.50E-05 0.00E+00 9.69E-03

(/~w)Mn-54 Ag-110m 5.93E-05 5.68E-06 + 5.93E-05 1.65E-05 3.99E-06 + 1.65E-05

' 2n-65 4.34E-02 1.39E-04 0.00E+00 4.34E-02 5.11E-02 1.38E-04 0.00E+00 5.11E-02 I-135 1.59E-03 4.17E-05 + 1.59E-03 0.00E+00 0.00E+00 + 0.00E+00 Fe-59 7.55E-06 2.79E-06 0.00E+00 7.55E-06 1.76E-04 9.42E-06 0.00E+00 1.76E-04 Co-60 1.05E-02 5.01E-05 0.00E+00 1.05E-02 3.39E-02 7.86E-05 0.00E+00 3.39E-02 Cu-64 1.39E-03 2.31E-04 + 1.39E-03 0.00E+00 0.00E+00 + 0.00E+00 Ha-24 1.15E-02 4.68E-05 + 1.15E-02 5.50E-05 3.64E-06

5.50E-05 L a- 140 6.47E-05 4.63E-06 + 6.47E-05 1.21E-05 1.57E-06 + 1.21E-05 Mn-56 0.00E+00 0.00E+00 + 0.00E+00 0.00E+00 0.00E+00 + 0.00E+00 Cs-136 2.14E-03 2.3?E-05 + 2.14E-03 1.59E-03 1.85E-05 + 1.59E-03 Cs-138 1.72E-05 1.97E-06 + 1.72E-05 0.00E+00 0.00E+00 + 0.00E+00 Rb-88 1.58E-08 4.41E-09 + 1.5SE-08 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 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.08E-05 7.03E-05 0.00E+00 7.0SE-05 Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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 2.60E-01 4.44E-04 0.00E+00 2.60E-01 3.81E-01 3.30E-04 0.00E+00 3.81E-01 Xe-133 3.71E-02 9.17E-05 0.00E+00 3.71E-02 2.75E-03 2.87E-05 0.00E+00 2.75E-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 1.24E-04 1.63E-05 0.00E+00 1.24E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 7.16E-02 6.82E-05 0.00E+00 7.16E-02 4.30E-05 2.66E-06 0.00E+00 4.30E-05 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 Kr-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 1.60E-03 7.38E-05 0.00E+00 1.60E-03 4.64E-09 5.61E-09 0.00E+00 4.64E-09

[N,s Xe-135M 1.38E-06 7.15E-08 0.00E+00 1.38E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m 3.67E-04 7.91E-05 0.00E+00 3.67E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tet als 1.11E-01 1.55E-04 0.00E+00 1.1!E-01 2.79E-03 2.89E-05 0.00E+00 2.79E-03

+ h rkhuIfkmkn Il e f}

FIGURE 1-5b Li qui d Reducste Dat a Compil at i on for Reg. Guide 1.21 Report E. I. H at ch Nuc l ear Plant UNIT 2 7

%_/ ,

Total Activity (Curies)

Quarter 3, 1984 Quarter 4, 1984 Batches 426 thru 648 B at c he s 649 thru 876 Name Measured Error High LLDs Tot al Measured Error High LLDs Total Ce-144 4.09E-04 6.43E-05 0.00E+00 4.09E-04 1.10E-04 3.43E-05 0.00E+00 1.10E-04 Tc-99m 3.02E-05 1.53E-06

3.02E-05 1.73E-04 2.87E-06

1.73E-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 Hp-239 0.00E+00 0.00E+00

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

0.00E+00 Cr-51 7.41E-05 1.26E-05

7.41E-05 2.89E-04 1.45E-05

2.89E-04 I-131 7.03E-05 3.62E-06 0.00E+00 7.03E-05 1.70E-04 5.56E-06 0.00E+00 1.70E-04 Zn-69m 1.83E-05 1.74E-06

1.83E-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 3.10E-04 3.83E-06

3.10E-04 1.81E-03 7.67E-06

1.81E-03 I-133 4.94E-05 3.11E-06

4.94E-05 6.16E-04 9.21E-06

6.16E-04 Ba-140 0.00E+00 0.00E+00

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

0.00E+00 As-76 6.06E-05 5.21E-06

6.06E-05 1.44E-04 7.06E-06 + 1.44E-04 Cs-134 2.59E-02 3.93E-05 0.00E+00 2.59E-02 2.12E-02 3.92E-05 0.00E+00 2.12E-02 Cs-137 2.95E-02 5.19E-05 0.00E+00 2.95E-02 3.53E-02 5.34E-05 0.00E+00 3.53E-02 No-99 1.55E-04 4.91E-05 0.00E+00 1.55E-04 1.71E-04 3.74E-05 0.00E+00 1.71E-04 Zr-97 0.00E+00 0.00E+00

0.00E+00 0.00E+00 0.00E+00 + 0.00E+00 Zr-95 9.32E-05 6.24E-06 + 9.32E-05 5.65E-06 1.58E-06

5.65E-06 Hb-95 2.07E-04 6.16E-06

2.07E-04 2.22E-06 5.93E-07

2.22E-06 1-132 3.40E-07 2.76E-07 + 3.40E-07 2.21E-06 7.84E-07 + 2.21E-06 Co-58 1.24E-05 1.43E-06 0.00E+00 1.24E-05 1.60E-04 5.07E-06 0.00E+00 1.60E-04

(^h Mn-54 3.37E-04 9.21E-06 0.00E+00 3.37E-04 9.67E-04 1.20E-05 0.00E+00 9.67E-04

( ) Ag-110m 5.11E-06 1.24E-06

5.11E-06 1.78E-06 7.05E-07 + 1.78E-06 Zn-65 9.96E-03 5.7?E-05 0.00E+00 9.96E-03 7.79E-03 4.93E-05 0.00E+00 7.79E-03 I-135 1.10E-05 2.12E-06

1.10E-05 6.95E-05 7.42E-06 + 6.95E-05 Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.55E-06 2.23E-06 0.00E+00 8.55E-06 Co-60 3.39E-03 2.45E-05 0.00E+00 ?.39E-03 4.36E-03 2.44E-05 0.00E+00 4.36E-03 Cu-64 0.00E+00 0.00E+00 + 0.00E+00 0.00E+00 0.00E+00 + 0.00E+00 Ha-24 1.42E-03 1.15E-05 + 1.42E-03 1.44E-02 3.86E-05 + 1.44E-02 L a- 14 0 0.00E+00 0.00E+00 + 0.00E+00 1.01E-05 1.88E-06 + 1.01E-05 Mn-56 0.00E+00 0.00E+00 + 0.00E+00 0.00E+00 0.00E+00

0.00E+00 Hi-65 4.34E-06 3.08E-06 + 4.34E-06 0.00E+00 0.00E+00

0.00E+00 Rb-88 7.27E-06 1.49E-06 + 7.2TE-06 0.00E+00 0.00E+00 + 0.00E+00 Cs-136 1.00E-05 1.85E-06 + 1.00E-05 0.00E+00 0.00E+00 + 0.00E+00 Cs-138 3.87E-06 7.76E-07 + 3.87E-06 0.00E+00 0.00E+00 + 0.00E+00 Sb-125 0.00E+00 0.00E+00 + 0.00E+00 3.22E-05 4.29E-06 + 3.22E-05 Sr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.41E-04 1.25E-04 0.00E+00 3.41E-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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-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 7.21E-02 1.24E-04 0.00E+00 7.21E-02 8.81E-02 1.67E-04 0.00E+00 8.81E-02 Xe-133 8.20E-04 1.42E-05 0.00E+00 8.20E-04 1.82E-03 1.65E-05 0.00E+00 1.82E-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+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 1.44E-03 9.35E-05 0.00E+00 1.44E-03 2.80E-03 1.40E-05 0.00E+00 2.80E-03 7-~s Kr-85M Kr-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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

(

x- 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 Tot al s 2.26E-03 9.46E-05 0.00E+00 2.26E-03 4.62E-03 2.17E-05 0.00E+00 4.62E-03

+ Ho LLL requirement in Tech spec TABLE 1-la

,- s. E. I. Hatch Nuc l e ar Pl ant UNIT 1 EFF,LUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1984 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Tot al 3 4 Error %

A. Fission & activation products

1. Total re l e ase (not including H3, cases alpha) Ci 2.60E-01 3.81E-01 4. 81 '.' ~~~

r 01

2. Average _ dt luted concentration during period uCi/mi 1.15E-07 1.97E-07

3. Percent of applicable limit % 3.46E+00 1.88E+00 B. Tritium

1. Total release Ci 2.66E+01 6.23E+00 3.76E+01)

2. Average diluted c onc e nt r at i on durino period uCi/ml 1.17E-05 3.22E-06

3. Percent of app l i c ab l e limit ". 3.91E-01 1.07E-01 C. Dissolved and entrained gases

1. Tot al release Ci 1.11E-01 2.79E-03 1.01E+02l

/N 2. Aver age dt luted concent rat ion

( ) 3.

during period Percent of app l i c ab l e limit uCi/mi 4.89E-08 1.22E-01 1.44E-09 3.61E-03 D. Gross alpha radi oact i vi t y l 1. Tot al release l Ci l 7.52E-05! 2.75E-05! 1.20E+02!

lE. Volume of waste (prior to dilution >l liters l 1.01E+07l 8.20E+06l 1.00E+01l lF. Volume of dilution w at er used l 11ters l 2.26E+09l 1.93E+091 1.60E+02l v)

TAELE 1-lb E. I. Hatch Nuclear Pl ant UNIT 2 s - EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1984 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Tot al 3 4 Error 4' A. Fission & activation products

1. Tot al release (not including H3, c ases , al pha) Ci 7.21E-02 8.81E-02 5.01E+01

2. Average diluted concentration during period uCi/ml 4.89E-08 6.43E-08

3. Percent of applicable limit % 3.36E-01 4.51E-01 B. Tritium

1. Total release Ci 6.19E+00 3.21E+00 3.76E+01l

2. Average diluted c onc ent rat i on during period uCi/mi 4.19E-06 2.35E-06

3. Percent of applicable limit . 1.40E-01 7.82E-02 C. Dissolved and ent r ai ned g as e s

1. Tot al release Ci 2.26E-03 4.62E-03 1.01E+02]

,~ 2. Average diluted c onc e nt r at i on

(

d during period uCi/mi 1.53E-09 3.37E-09

# Percent of appl i c abl e l i ru i t ". 3.83E-03 8.43E-03 3.

D. Gross al pha r adi o ac t i vi t y l 1. Tot al re l e ase ! Ci l 4.80E-06l 9.19E-06l 1.20E+021 lE. Volume of vaste (prior to dilutton'sl liters j 6.25E+06l 5.64E+06l 1.00E+01l lF. Volume of dilution w at e r used l liters l 1.47E+09l 1.36E+09l 1.60E+02l 7_ .,

i e

'/

y TABLE 1-2a E. I. Hatch Nuc l ear Plant UNIT 1

__,/ EFF,LUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1984 r

LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Huclides Released Unit Quarter Quarter Quarter Quarter 3 4 3 4 Ce-144 Ci 7.70E-03 1.22E-03 Tc-99m Ci 4.85E-04 1.38E-05 Ce-141 Ci 0.00E+00 0.00E+00 Hp-239 Ci 0.00E+00 0.00E+00 Cr-51 Ci 3.58E-03 2.55E-03 I-131 Ci 1.65E-02 4.13E-03 Zn-69m Ci 0.00E+00 0.00E+00 W-187 Ci 0.00E+00 0.00E+00 F-18 Ci 2.96E-03 7.87E-04 1-133 Ci 1.02E-02 1.03E-04 Ba-140 Ci 0.00E+00 0.00E+00 As-76 Ci 7.39E-05 0.00E+00 Cs-134 Ci 5.34E-02 1.12E-01 Cs-137 Ci 8.59E-02 1.58E-01 Mo-99 Ci 1.04E-03 8.14E-04 Zr-97 Ci 0.00E+00 0.00E+00 Zr-95 Ci 4.15E-05 0.00E+00 Hb-95 Ci 1.15E-04 9.58E-05

, ~' 3 I-132 Ci 1.08E-05 0.00E+00 t ) Co-58 Ci 4.66E-04 4.61E-03

' Mn-54 Ci 1.84E-03 9.69E-03 Ag-110m Ci 5.93E-05 1.65E-05 Zn-65 Ci 4.34E-02 5.11E-02 I-135 C1 1.59E-03 0.00E+00 Fe-59 Ci 7.55E-06 1.76E-04 Co-60 C1 1.05E-02 3.39E-02 Cu-64 Ci 1.39E-03 0.00E+00 Ha-24 Ci _

1.15E-02 5.50E-05 La-140 Ci 6.47E-05 1.21E-05 Mn-56 Ci 0.00E+00 0.00E+00 Cs-136 Ci 2.14E-03 1.59E-03 Cs-138 Ci 1.72E-05 0.00E+00 Rb-88 C1 1.58E-08 0.00E+00 Sr-89 Ci 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 7.08E-05 Fe-55 Ci 0.00E+00 0.00E+00 P-32 Ci 0.00E+00 0.00E+00 l Tot al for period (above) l Ci l l l 2.60E-01l 3.81E-01l Xe-133 Ci 3.71E-02 2.75E-03 Kr-88 Ci 0.00E+00 0.00E+00 Xe-133M C1 1.24E-04 0.00E+00 Xe-135 Ci 7.16E-02 4.30E-05

/,,,) Kr-85M Ci 0.00E+00 0.00E+00

(,,/ Kr-87 Ci 0.00E+00 0.00E+00 Xe-138 Ci 1.60E-03 4.64E-09 Xe-135M Ci 1.38E-06 0.00E+00 Xe-131m Ci 3.67E-04 0.00E+00 TABLE 1-2b-E. I. Hatch Huclear Plant UNIT 2 7-f )

\_/ EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1984 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter. Quarter Quarter 3 4 3 4 Ce-144 C1 '

4.09E-04 1.10E-04 Tc-99m C1 3.02E-05 1.73E-04 Ce-141 Ci 0.00E+00 0.00E+00 Hp-239 Ct 0.00E+00 0.00E+00 Cr-51 Ci 7.41E-05 2.89E-04 I-131 Ci 7.03E-05 1.70E-04 Zn-69m Ci 1.83E-05 0.00E+00 W-187 Ci 0.00E+00 0.00E+00 F-18 Ci 3.10E-04 1.81E-03 I-133 Ci 4.94E-05 6.16E-04 Ba-140 Ci 0.00E+00 0.00E+00 As-76 Ci 6.06E-05 1.44E-04 Cs-134 C1 2.59E-02 2.12E-02 Cs-137 Ci 2.95E-02 3.53E-02 No-99 C1 1.55E-04 1.71E-04 Zr-97 Ci 0.00E+00 0.00E+00 Zr-95 Ci 9.32E-05 5.65E-06 Hb-95 Ci 2.07E-04 2.22E-06 I-132 Ci 3.40E-07 2.21E-06

/~~N 1.60E-04

) Co-58 Ci 1.24E-05

( '# Mn-54 Ci 3.37E-04 9.67E-04 Aq-110m Ci 5.11E-06 1.78E-06 Zn-65 Ci 9.96E-03 7.79E-03 I-135 Ci- 1.10E-05 6.95E-05 Fe-59 Ci 0.00E+00 8.55E-06 Co-60 Ci 3.39E-03 4.36E-03 Cu-64 Ci 0.00E+00 0.00E+00 Na-24 C1 1.42E-03 1.44E-02 La-140 Ct 0.00E+00 1.01E-05 Mn-56 Ci 0.00E+00 0.00E+00 Ni-65 Ci 4.34E-06 0.00E+00 Rb-88 Ci 7.27E-06 0.00E+00 Cs-136 Ci 1.00E-05 0.00E+00 Cs-138 Ci 3.87E-06 0.00E+00 Sb-125 Ci 0.00E+00 3.22E-05 Sr-89 Ci 0.00E+00 3.41E-04 Sr-90 Ci 0.00E+00 0.00E+00 Fe-55 Ci 0.00E+00 0.00E+00 P-32 Ci 0.00E+00 0.00E+00 l Total for period (above) l Ci l l l 7.21E-02l 8.81E-02l Xe-133 Ci 8.20E-04 1.82E-03 Kr-88 Ci 0.00E+00 0.00E+00

,_ 0.00E+00

/ Xe-133M Ci 0.00E+00 k ,)\ Xe-135 Ci 1.44E-03 2.80E-03 Kr-85M Ci 0.00E+00 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 Xe-138 C1 0.00E+00 0.00E+00

,_.23--

2 GASEOUS EFFLUENTS 2.1. REGULATORY LIMITS

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

I Qig k.9 SF 1.0 E B + Qiv 11 56 + 44'EB 11 i-n _

- _ j where Qs = Total release rate from main stack for both Units in Ci/sec (elevated release)

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

Qy i'= The individual nuclide n = total nuclides E6 =

The average gamma energy per disintegration 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 106 qpy gi Where Qps = Total release rate from the main stack r3 for both Units in Ci/sec (as elevated V 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:

r ,

E Qis 12 E 6 + 3.0 EB + Qiv 166 E 6 + 140 E B C1 1-n -

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

I Qis 24 26 + 6.1 fB + Qiv 130 E6 + 270 EB- il i --. n _

j L J (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 10 7 Qpv i 1 (4) The average release rate of all radio iodines and radioactive materials in particulate form from the site j . - - _ --- - = -- -_ _ .

with half lives greator than eight days during any period of 12 consecutive months shall be:

2.6 X 106 Qps + 3.7 x 107 Qpv g_1 f

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

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

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

E Qis 47 E 6 + 12 EB + Qiv 260 56 + 540 EB >l i ->n - -

-(2) If ' the average release rate from the site of all radio iodines and radioactive materials in particulate form 7

with half lives greater ,

than eight days during any

( ) calendar quarter is:

V 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 ' of fgas 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 2.1.3a 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 Commission in writing within 10 days, identifying the causes of activity and in accordance with section 5.7.2.

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

n!

t

-V

i t

l

h. (1) Potentially -

explosive gas mixtures of hydrogen and oxygen contained in the offgas system downstream of the recombiners shall be continuously monitored during g reactor power operation for hydrogen concentration.

i L'j The hydrogen gas monitoring system shall provide alarms locally and in the' control room at a set point of 4%

hydrogen concentration by volume. At least one continuous . gas monitoring system and its associated alarm system shall be operable during. reactor power operation. .If both of the hydrogen gas monitors or both of thes associated alarm systems are inoperable, reactor operation may be continued for a period of time

not to exceed 2 weeks, provided that either (a) grab samples are taken and analyzed for hydrogen concentration once every 4 . hours, or (b) using a temporary hydrogen gas analyzer installed in the offgas system line downstream of the recombiner, hydrogen concentration readings are taken and logged every 4 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 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 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.

(]

v (3) The installed hydrogen mon itor ing _ 4 sys tems shall have daily sensor checks, monthly functional checks, and quarterly calibrations. The portable hydrogen gas analyzer shall be calibrated immediately prior to installation and shall be subject to daily sensor and checks, monthly functional checks, quarterly calibrations until removed from service.

,,i. An unplanned or uncontrolled of fsite release of radioactive materials in-gaseous effluents in excess of 150 Ci. of noble gas or 0.02 Ci. of radiciodines in gaseous form shall be reported to the NRC within 30 days in accordance with section 5.7.2.

2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 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 U

Each of thase continuous samplers has a flow controller which maintains sample flow within about a 10 percent range over each seven day collection period. The offgas vent (elevated release) and the actor building vents have flow measurement devices which ntinously record the flow rate of the gas released (accurary of h:se devices are within 10% of the actual flows as measured during prcoperational testing). The recombiner building vent flow on Unit One is conservatively assumed to be constant at 500 CFM. In addition to the gaseous, particulate, and iodine release measurements tritium, gross alpha and gaseous isotopic measurements of each vent stream are conducted on a monthly schedule.

After each calendar quarter (13 weeks) a summary of waste gas release from the four vents is compiled and as such is designed to meet the requirements for preparation of the 6-month repor t as specified in Regulatory Guide 1.21. Unit one and two releases were calculated together because the Tech. Specifications for the two reactors are identical in this respect. The methods for compilation of the quarterly releases are as follows:

1. FISSION AND ACTIVATION GAS The total curie release is determined from the continuously reading gaseous monitors in addition to the vent flow recorders. Activity monitors and vent flow rate readings are read hourly and input into the computer. From these readings a daily release is calculated. The calibration factors for the monitors are determined from the monthly isotopics when sufficient activity allows or by injection of

( a known amount of off-gas into the sample chambers. The total curie release is calculated by the computer for each of the individual nuclides released. This number is multiplied by the average energy per disintegration (E &

E)

B along with the coefficients in the release limit formula in our Environmental Technical Specifications. All of the nuclides are summed and stored in their respective data files until the end of 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 1-131, I-133, and 1-135, for each vent. Where significant activity is not measured MDA releases are calculated. Since calculated MDA's are below Technical Specification detectable concentrations then 0 (zero) release is used for the weeks with only MDA values. Weekly releases are summarized with the aid of the counting room calculator - computer system and a quarteri/ total is prepared from the weekly summaries. The percent Technical Specification for I-131 on Table 2-1 is based on t' e quarterly Technical Specification limit.

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

Where significant activity is not measured MDA release is (O")

calculated. Since calculated- MDA's are below Technical Speci fica ti-on detectable concentrations, then 0 (zero) release is used for weeks with only MDA values. Weekly releases are summarized with the aid of the counting room calculator - computer.

After each calendar month the particulate filters from each vent are combined, fused, and strontium separation is made.

Since sample flows and vent flows are almost constant over each monthly period the filters from each vent can be dissolved together . Decay corrections are made back to the middle of the quarterly collection period. Again the counting room calculator - computer is used to aid in the calculation of the Sr-89, 90 release. Where significant strontium activity is not detected MDAs are calculated. The percent of Technical Specification was calculated using quarterly average equation.

4. GROSS ALPHA RELEASE The gross alph a 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.

v]

[ 5. TRITIUM RELEASE Tritium samples are obtained mon th ly 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. F the uCi/ml tritium concentration, the grams water /ft3, rom 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 FDAs as low as possible by counting samples longer than what would be normally practical. For example, at this time all weekly particulate and iodine counting times are 3000 sec and strontium separations are counted for 100 minutes.

Regulatory Guide 1.21 requires tha t estimated total error in analysis techniques be reported. These estimates are required for the total fission and activation gas release, total I-131 release, total par ticula tes with half-lives greater than 8-day -

release, and total tritium release.

(

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

(j Because it-may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error are not suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste."

~

Estimated errors are based on errors in counting- equipment calibration, counting statistics, vent flow rates, vent sample flow rates, non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges.

1. Fission and Activation Gas Total Release was calculated from process monitor readings. As 84.55% of this. release was from the main stack the MDA release values of the ground level release points were small when compared to the total release.

Monitor Error in Calibration 50%

Vent Flow Rate 10%

Non-Steady Release Rate 20%

F5%

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

Statistical error 60%

- [b Counting Equipment Calibration 10%

Vent Flow Rates 10%

Vent Sample Flow Rates 10%

Non-Steady Release Rates 10% ,

Losses From Charcoal Cartridge 10%

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

. alph a 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%

T5DI

, v f

4. = Total Tritium Release was dominated by the reactor building vent tritium release, hence, the larger statistical errors ,

,m of the off-gas vent and recombiner building vent tritium .

( ) releases- do not affect the error in the total tritium j release: .

Water Vapor in Sample Stream Determination 20% i Vent Flow Rates 10% p Counting Calibration and Statistics 10%

Non-Steady Release 50%

90T J.3. GASEOUS EFFLUENT RELEASE DATA -

Regulatory Guide 1.21 Tables l A, 1B, and 1C ar e found in this report as Tables 2-la-c, 2-2a-c, and 2-3a-c.

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

.. SOLID WASTE 4.1 REGULATORY SPECIFICATIONS

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

\ Solid wastes in storage and preparatory to shipment shall be

[/

.b monitored and. packaged to assure compliance with the applicable portions of 10 CFR Par t 20, 10 CFR Part 71, and 49 CFR Parts 171-178.

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.

t.2 SOLID WASTE DATA Regulatory guide 1.21 Table 3 is found in this report as Table 3-la.

O T ABLE 2-la i UNIT 1 EFFLUENT AHD WASTE DISPOSA'L'SEMIAHHUAL REPORT 1984 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES k/ Unit Quarter Quarter Est Total E. I. Hat c h Nuc l e'ar Power Pl ant UNIT 1 3 4 Error %

A. Fission & act ivat ion gases

1. Tot al release C1 4.95E+03 4.97E+01 8.00E+01l

2. Average release rate for period uC1/sec 6.30E+02 6.12E+00

3. % of Technical spec i f i c at i on limit % 6.89E-01 3.21E-02 B. Iodines

1. Tot al iodine-131 Ci 2.64E-02 2.25E-03 1.10E+02l

2. Average release rate for period uCi/sec 3.36E-03 2.77E-04

3. % of Tec hni c al specification limit % 1.32E+00 1.12E-01 C. P art i c ul at e s

1. Particulates with half-lives >8 davs Ci 1.6SE-02 1.63E-03 1.00E+021

2. Average release rate for period uCi/sec 2.14E-03 2.01E-04

3. % of Technic al spec i fi c at i on limit % 3.96E+00 3.82E-01

4. Gross al pha radi oac t i vi t v C1 1.97E-05 4.59E-06 D. Tritium

1. Total release Ci 1.89E+01 9.51E+00 9.00E+01l

2. Average release r at e for period uC1/sec 2.41E+00 1.17E+00

[g 3. % of Tec hni c al J pe c i fi c at i on 1 1 ra t t . 2.47E+01 9.89E-01

(

t . -

~

TABLE 2-lb UNIT 2

, _ , EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1984

( \

V ,, GASEOUS EFFLUENTS-SUMMATION OF,ALL RELEASES Unit Quarter Quarter Est Tot al E. I. Hatch Nuclear Power Plant UNIT 2 3 4 Error /.

A. Fission.A activation gases

1. Tot al release Ci 1.52E+02 7.87E+02 S.00E+01)

2. Average release rate for period uCi/sec 1.93E+01 9.69E+01

3. /. of Tec hni c al specification Itmit % 7.07E-02 7.33E-01 B. Iodines

1. Total todine-131 Ci 7.98E-04 1.46E-03 1.10E+02l

2. Average release rate for period uCi/sec 1.02E-04 1.80E-04

3. % of Tec hn i c al specification limit . 3.99E-02 7.31E-02 C. Particulates

1. Part icul at es wi t h h al f-l i ves >S d av s Ci 1.21E-04 1.56E-04 1.00E+02l

2. Aver age- re l ease rate for period uCi/sec 1.53E-05 1.92E-05

3. % of Technt c al spec i f i c at i on 1imit . 2.88E-02 1.96E-02

4. Gross al pha radi oac t i v t t u Ci 5.21E-07 1.42E-06 D. Tritium

( 1. Tot al release Ci 3.82E-01 4.46E+00 9.00E+01l

(']';

2.

3.

Average re l e ase rat e for period

of Technical s p e c i f i c at i o r, 1imit l

. uCt/sec 4.86E-02 2.51E+00 5.50E-01 4.07E+00

(

k v

TABLE 2-Ic SITE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1984 s ,

\~ / GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Total E. I. Hatch Nuclear Pouer Plant SITE 3 4 Error %

A. Fission &. activation gases

1. Total-release Ci 5.11E+03 9.37E+02 8.00E+01l

2. Average release rate for period uCt/sec 6.50E+02 1.03E+02

3. % of Technical spec i f i c at i on limit *: 7.60E-01 7.65E-01 B. Iodines

1. Total iodine-131 Ci 2.72E-02 3.71E-03 1.10E+02).

2. Average release rate for period uCi/sec 3.46E-03 4.57E-04

3. % of Tec hni c al spec i fi c at i on limit % 6.80E-01 9.28E-02 C. Part i c ul at e s ,

1. Part i cul at es wi t h h al f-l i ve s >8 davs C1 1.69E-02 1.79E-03 1.00E+02l

2. Average release r at e for period uC1/sec 2.15E-03 2.20E-04

3. % of Technical spec i fi c at i on Itmit . 3.99E+00 4.01E-01 4 Gross al ph a r adi oac t i vi t v C1 2.02E-05 6.01E-06 D. Tritium g'"% 1. Total release Ci 1.93E+01 1.40E+01 9.00E+011

? 2. Average re l e ase e at e for pertod uC1/sec 2.46E+00 1.72E+00

3. % of Technic al spec i f i c at i on limit . 2.72E+01 5.06E+00 v

TABLE 2-2a E. I. Hat ch Huc lear Pouer Pl ant UNIT 1

(' S EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1984 d

GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE Huclides Released Unit Quarter Quarter Quarter Quarter 3 4 3 4

1. Fission gases Xe-133 C1 1.80E+03 2.06E-01 0.00E+00 0.00E+00 Xe-131m Ci 2.20E+02 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 1.34E+03 3.04E-02 0.00E+00 0.00E+00 Xe-133M Ci 2.55E+01 4.30E-03 0.00E+00 0.00E+00 Xe-135 Ci 1.10E+02 6.02E-03 0.00E+00 0.00E+00 Kr-85M Ci 7.41E+02 1.73E-02 0.00E+00 0.00E+00 I-131 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ci 4.27E+02 8.21E-03 0.00E+00 0.00E+00 Xe-138 C1 2.16E+01 4.07E-02 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-13 Ci 7.06E+01 1.70E-01 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ci 1.06E+01 1.05E-02 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 C1 4.08E+00 9.49E-02 0.00E+00 0.00E+00

()

l Tot al for' period Ci 4.77E+03 5.88E-01 0.00E+00 0.00E+00

2. Iodines I-131 Ci j 4.89E-03 2.90E-06 0.00E+00 0.00E+00 I-133 Ci j 2.63E-03 1.11E-06 0.00E+00 0.00E+00 I-135 Ci j 1.22E-03 9.20E-07 0.00E+00 0.00E+00 Tot al for period Ci ( ).74E-03 4.94E-06 0.00E+00 0.00E+00

3. Particulates Sr-89 Ci __9.08E-06 ?.94E-08 0.00E+00 0.00E+00 Sr-90 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 C1 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 1-131 C1 5.09E-05 2.34E-09 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 C1 1.21E-04 3.48E-08 0.00E+00 0.00E+00 Cs-134 Ci 5.42E-07 1.79E-09 0.00E+00 0.00E+00 Cs-137 Ci 5.11E-06 1.4?E-08 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ftp-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Lo-58 Ci 0.00E+00 1.12E-09 0.00E+00 0.00E+00 Mn-54 C) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

[ j Co-60 Ci 1.20E-06 5.98E-09 0.00E+00 0.00E+00 (m,/ La-140 C1 2.46E-04 4.58E-08 0.00E+00 0.00E+00 Tot al for period Ci 4.34E-04 1.96E-07 0.00E+00 0.00E+00

TABLE 2-2b E. I. Hatch Nuclear Power Pl ant UNIT ?

[ EFFLUENT AHD WASTE DISPOSAL SEMIANNUAL REPORT 1984 v' ,

GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter l Quarter Quarter Quarter 3 l 4 3 4

1. Fission gases Xe-133 Ci 7.24E+00 8.13E+01 0.00E+00 0.00E+00 Xe-131m Ci 8.84E-01 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 5.37E+00 1.20E+01 0.00E+00 0.00E+00 Xe-133M Ci 1.02E-01 1.70E+00 0.00E+00 0.00E+00 Xe-135 Ct 4.41E-01 2.38E+00 0.00E+00 0.00E+00 Kr-85M Ci 2.97E+00 6.81E+00 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ci 1.71E+00 3.24E+00 0.00E+00 0.00E+00 Xe-138 Ci 8.68E-02 1.61E+01 0.00E+00 0.00E+00 Le-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N-13 Ci 2.83E-01 6.71E+01 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ci 4.24E-02 4.14E+00 0.00E+00 0.00E+00 I-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 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 1.64E-02 3.75E+01 0.00E+00 0.00E+00 f)'\

(

Tot al for period C1 1.91E+01 2.32E+02 0.00E+00 0.00E+00

2. Iodines I-131 Ci 1.96E-05 1.15E-03 0.00E+00 0.00E+00 1-133 Ci 1.06E-05 4.39E-04 0.00E+00 0.00E+00 I-135 Ci 4.8SE-06 3.63E-04 0.00E+00 0.00E+00 Tot al for period Ci 3.51E-05 1.95E-03 0.00E+00 0.00E+00

3. Part i cul at e s Sr-89 Ci 3.6*2-08 3.53E-05 0.00E+00 0.00E+00

$r-90 Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 2.04E-07 9.25E-07 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 4.86E-07 1.37E-05 0.00E+00 0.00E+00 Cs-134 Ci 2.17E-09 7.0SE-07 0.00E+00 0.00E+00 Cs-137 C1 2.05E-08 5.79E-06 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-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 0.00Ev00 Co-58 Ci 0.00E+00 4.42E-07 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

. Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

[h

(/

Co-60 La-140 C1 Ci 4.80E-09 9.85E-07 2.36E-06 1.81E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for period Ci 1.74E-06 7.74E-05 0.00E+00 0.00E+00

TABLE 2-2c E. I& Hatch Huclear Power Plant SITE I) EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1984

\

w]

GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH NODE Huclides Released Unit Quarter Quarter Quarter Quarter 3 4 3 4

1. Fission gases Xe-133 Ci 1.81E+03 8.15E+01 0.00E+00 0.00E+00 Xe-131m Ci 2.21E+02 0.00E+00 0.00E+00 0.00E+00 Kr-88 C1 1.34E+03 1.20E+01 0.00E+00 0.00E+00 Xe-133M Ci 2.56E+01 1.70E+00 0.00E+00 0.00E+00 Xe-135 Ci 1.11E+02 2.38E+00 0.00E+00 0.00E+00 Kr-85M Ci 7.44E+02 6.83E+00 0.00E+00 0.00E+00 1-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ci 4.29E+02 3.25E+00 0.00E+00 0.00E+00 Xe-138 C1 2.17E+01 1.61E+01 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N-13 Ci 7.09E+01 6.73E+01 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ci 1.06E+01 4.15E+00 0.00E+00 0.00E+00 I-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 1-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 4.10E+00 3.76E+01 0.00E+00 0.00E+00 C '\

( , ) Tot al for period Ci 4.79E+03 2.33E+02 0.00E+00 0.00E+00

2. Iodines I-131 C1 4.91E-03 1.15E-03 0.00E+00 0.00E+00 I-133 Ci 2.64E-03 4.40E-04 0.00E+00 0.00E+00 I-135 C1 1.22E-03 3.64E-04 0.00E+00 0.00E+00 Total for period Ci 9.78E-03 1.95E-03 0.00E+00 0.00E+00

3. Particulates Sr-89 Ci 9.11E-06 3.54E-05 0.00E+00 0.00E+00 Sr-90 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 C1 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 1-131 C1 5.11E-05 9.29E-07 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 1.22E-04 1.38E-05 0.00E+00 0.00E+00 Cs-134 Ci 5.44E-07 7.09E-07 0.00E+00 0.00E+00 Cs-137 Ci 5.13E-06 5.80E-06 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-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 Co-58 Ci 0.00E+00 4.43E-07 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

,-s

, Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Co-60 Ci 1.20E-06 2.36E-06 0.00E+00 0.00E+00

(/

N_ La-140 Ci 2.47E-04 1.81E-05 0.00E+00 0.00E+00 Tot al for period Ci 4.35E-04 7.75E-05 0.00E+00 0.00E+00 TABLE 2-3m E. I. Hat ch Nuc lear Pouer Pl ant UNIT 1

.' ~'T EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1984 i ,.,!

GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTIHUOUS MODE BATCH MODE Huclides Released Unit Quarter Quarter Quarter Quarter 3 4 3 4

1. Fission gases Xe-133 Ci 1.94E+01 6.79E-02 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ct 6.80E-01 1.45E-01 0.00E+00 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 Ci 5.79E+01 1.73E+01 0.00E+00 0.00E+00 Kr-85M Ci 2.27E-01 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 C1 7.62E-01 2.00E-01 0.00E+00 0.00E+00 Xe-138 Ci 3.53E+00 5.24E-01 0.00E+00 0.00E+00 Xe-137 Ci 3.01E+00 2.79E-01 0.00E+00 0.00E+00 H-13 Ci 3.10E+00 5.16E-01 0.00Ee00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ci 9.21E+01 3.00E+01 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 C1 3.10E-01 0.00E+00 0.00E+00 0.00E+00 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 0.00E+00 f%

g ) Tot al for period Ci 1.81E+02 4.91E+01 0.00E+00 0.00E+00 xy -

2. Iodines I-131 Ci 1.92E-02 2.16E-03 0.00E+00 0.00E+00 I-133 Ci 1.98E-02 6.02E-05 0.00E+00 0.00E*00 1-135 Ci 1.62E-02 6.96E-05 0.00E+00 0.00E+00_

- Tot al for period Ci 5.52E-02 2.29E-03 0.00E+00 0.00E+00

3. Part icul at ez Sr-89 C1 4.24E-05 2.58E-05 0.00E+00 0.00E+00 Sr-90 Ci 1.69E-07 5.22E-07 0.00E+00 0.00E+00 Ce-141 Ci 7.51E-10 0.00E+00 0.00E+00 0.00E+00 Cr-51 C1 2.18E-03 s.25E-04 0.00E+00 0.00E+00 1-131 Ci 2.26E-03 8.52E-05 0.00E+00 0.00E+00 Sn-113 Ci 1.65E-09 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 Ci 5.2SE-03 1.49E-04 0.00E+00 0.00E+00 Cs-137 Ci 5.38E-03 2.90E-04 0.00E+00 0.00E+00 Ce-144 Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hb-95

Ci 0.00E+00 4.79E-06 0.00E+00 0.00E+00 Co-58 Ci 2.85E-04 3.24E-05 0.00E+00 0.00E+00 Mn-54 Ci 7.49E-05 7.81E-05 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 7.83E-08 0.00E+00 0.00E+00

/ Co-60 Ci 7.54E-04 6.31E-04 0.00E+00 0.00E+00

\ ,N) La-140 Ci 1.30E-04 9.29E-06 0.00E+00 0.00E+00 Tot al for period Ci 1.64E-02 1.63E-03 0.00E+00 0.00E+00 T ABLE ~ 2-3b E. I. Hatch Nuclear Power Plant UNIT 2 i EFFLUENT.AND WASTE DISPOSAL SEMIANNUAL REPORT 1984 O

GASEOUS EFFLUENTS-GROUND-LEVEL' RELEASE CONTINUOUS MODE BATCH MODE Nuclides Released Unit- Quarter Quarter Quarter Quarter 3 4 3 4

1. Fission gases Xe-133 Ci 8.33E+01 1.21E+02 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 C1 4.82E+00 7.24E+01 0.00E+00 0.00E+00 Xe-133M Ci 1.98E+00 1.96E+00 0.00E+00 0.00E+00 Xe-135 Ci 3.74E+01 3.75E+01 0.00E+00 0.00E+00 Kr-85M Ci 4.93E+00 6.71E+01 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 C1 5.29E-01 4.47E+00 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-13 Ci 3.11E-02 6.87E+00 0.00E+00 0.00E+00 Kr-85 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00

-I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 C1 0.00E+00 2.43E+02 0.00E+00 0.00E+00 7s i ( ) Tot al for period Ci 1.33E+02, 5.55E+02 0.00E+00 0.00E+00

.O

2. Iodines I-131 C1 7.36E-04 3.12E-04 0.00E+00 0.00E+00 I-133 Ci 9.62E-04 1.00E-04 0.00E+00 0.00E+00 I-135 Ci 5.E4E-04 1.24E-04 0.00E+00 0.00E+00 Tot al for period C1 2.23E-03 5.36E-04 0.00E+00 0.00E+00 I 3. Par t i c ul at es Sr-89 C1 2.36E-05 1.13E-05 0.00E+00 0.00E+00 sr-90 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 7.45E-06 0.00E+00 0.00E+00

! I-131 C1 4.23E-05 2.63E-06 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci t.06E-07 4.14E-06 0.00E+00 0.00E+00 Cs-134 Ct 1.65E-06 9.68E-06 0.00E+00 0.00E+00 4 Cs-137 C1 2.15E-05 2.68E-05 0.00E+00 0.00E+00 Ce-144 Ci s.00E+00 0.00E+00 0.00E+00 0.00E+00 2r-95 Ct 0.00E+00 1.89E-06 0.00E+00 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00

\ Co-60 Ci 5.46E-06 1.47E-05 0.00E+00 0.00E+00

(# 0.00E+00 0.00E+00

(_, La-140 Ct 2.35E-05 0.00E+00 Total for period Ci 1.19E-04 7.86E-05 0.00E+00 0.00E+00 i

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

r TABLE 2-3c E. I& Hatch Nuc l e ar Power Pl ant SITE EFFLUENT AND NASTE DISPOSAL SEMIANNUAL REPORT 1984 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 3 4 3 4

1. Fission gases Xe-133 Ct 1.03E+02 1.21E+02 0.00E+00 0.00E+00 Xe-131m Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 5.50E+00 7.25E+01 0.00E+00 0.00E+00 Xe-133M Ci 1.98E+00 1.96E+00 0.00E+00 0.00E+00 Xe-135 Ci 9.53E+01 5.48E+01 0.00E+00 0.00E+00 Kr-85M Ci 5.16E+00 6.71E+01 0.00E+00 0.00E+00 1-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ci 1.29E+00 4.67E+00 0.00E+40 0.00E+00 Xe-138 Ci 3.53E+00 5.24E-01 0.00E+00 0.00E+00 Xe-137 Ci 3.01E+00 2.79E-01 0.00E+00 0.00E+00 N-13 Ci 3.13E+00 7.39E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ci 9.21E+01 3.00E+01 0.00E+00 0.00E+00

" '33 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr -89 Ci 3.10E-01 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 0.00E+00 2.43E+02 0.00E+00 0.00E+00 Tot al for period Ct 3.14E+02 6.04E+02 0.00E+00 0.00E+00

2. Iodines I-131 Ci 1.99E-02 2.47E-03 0.00E+00 0.00E+00 I-133 Ci 2.09E-02 1.60E-04 0.00E+00 0.00E+00 1-135 C1 1.68E-02 1.93E-04 0.00E+00 0.00E+00 Tot al for period Ci 5.75E-02 2.83E-03 0.00E+00 0.00E+00

3. P art i c ul at e s Sr-89 Ci 6.60E-05 :.71E-05 0.00E+00 0.00E+00 Sr-90 Ci 1.6?E-07 5.22E-07 0.00E+00 0.00E+00 Ce-141 Ci .'.51E-10 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 2.18E-03 3.33E-04 0.00E+00 0.00E+00 1-131 Ci 2.30E-03 8.78E-05 0.00E+00 0.00E+00 Sn-113 Ci 1.65E-09 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 8.06E-07 4.14E-06 0.00E+00 0.00E+00 Cs-134 Ci 5.28E-03 1.59E-04 0.00E+00 0.00E+00 Cs-137 Ci 5.40E-03 3.17E-04 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 1.89E-06 0.00E+00 0.00E+00 HL -95 Ci 0.00E+00 4.79E-06 0.00E+00 0.00E+00 Co-58 Ci 2.85E-04 3.24E-05 0.00E+00 0.00E+00 Mn-54 Ci 7.49E-05 7.81E-05 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 7.83E-08 0.00E+00 0.00E+00 Ct 7.60E-04 6.46E-04 0.00E+00 0.00E+00

( } Co-60 1.53E-04 9.29E-06 0.00E+00 0.00E+00

,j La-140 C1 Tot al for period Ci 1.65E-02 1.71E-03 0.00E+00 0.00E+00 I

I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1984 hJ .I-

^

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNIT I & II

( 84 to 12-31-84) f A. SOLIO WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) unis 6*non th E st. To ol

1. Type of waste Perios Eqor.16

a. Spent resins. t~ilter sit.dg:s. enporator m 8 E39.38 E O tnttor .s. etc. Ci h6A.A1 E n 1. 0 E+1

b. Dry compreutste waste, contstmasted m' i nn. R 2 E +1 equip. etc. C1 255. 06 E O 1 .0 ta.1 C. Irradiated components. conttog W 21. 8 7 E O rods. etc. Ci 21. 69 E o '

1. 0 E+1

d. Other (desenbe) m' 91. 21 E 0 Ci 0. 44 E O 1.0 E +1

2. Esttmste of maior nuclide composition (by tyy of waste)

ISOTOPE PERCENT l CURIES

a. zn-65 40 346.57 Cs-137 17 147.29 Cs-134 13 112.64 All others 30 259-93 p, b. zn-65 Co-60 49 30 124.98 76.52 G Cs-137 9 22.96 All Others 12 30.61 C. zn-b] 51 '

11.10 Co-bo 28 6.10 Mn-J4 10 2.17 All Others 11 2.19

d. zn-65 '

53 0.21 Co-60 l 29 0.11 Cs-137 0.03 7

All Others 11 0.05 1

4

3. SoUd Weste D:sposition Number of shi:ments Mede of Tr:.-:ccr stion D:stination 47 Cask Barnwell, S.C.

47 Van Hanford, WA

& IRRADIATED FUEL SHIPMCJTS (Disposition)

Number of Shier-ents Mode ef Transportstion Destitution N/A N/A N/A l

l

Georgia Pow:r Compiny Post offica Box 439 8:xty, Georgia 31513 Telephone 912 367-7781 912 537-9444 Edwin 1. Hatch Nu'elear Plant February 20, 1985 GM-85-194 PLANT E. I. HATCH Semi-Annual Radioactive Effluent Release Report Dr. J. Nelson Grace U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II, Suite 3100 101 Marietta Street Atlanta, Georgia 30303 J

Dear Dr. Grace:

Pursuant to Section 5.7.1.b in Appendix B, Environmental Technical Specifications, of the Plant Edwin I. Hatch Operating Licenses, please find enclosed the Semi-Annual Report for Plant Radioactive Effluent Releases, July 1, 1984 through December 31, 1984.

--' ra Q1

<... T.;,-;<-

C. Nix :

i M . H.General Man ( er d

HCN/WHR/jce xc: J.T. Beckham (1) '

T.V. Greene (1) D H.L. Sumner (1)

C.T. Jones (1)

R.W. Zavadoski (1)

W.H. Rogers (4)

-m T.E. Byerley (3)

[ ') W.H. Ollinger (1)

'd-L. Cross (ANI) (1)

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

File: M84-4 1 1 TdG6

Georgia Power company Post Office Box 439 Barley. Georgia 31513 Telephone 912 367-7781 912 537-9444

,r)

\d . GeoisiaPower Edwin 1. Hatch Nuclear Plant February 20, 1985 GM-85-195 PLANT E. I. HATCH Semi-Annual Radioactive Effluent Release Report Director of Inspection and Enfotnement

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

I V Pursuant to Section 5.7.1.b in Appendix B, Environmental Technical Specifications, of the Plant Edwin I. Hatch Operating Licenses, please find enclosed the Semi-Annual Report for Plant Radioactive Effluent Releases, July 1, 1984 through December 31, 1984.

~

H. C. Nix General Mar.ager HCN/WHR/Jce l

(-)

l

ML20100L132

Text

==

Dear Dr. Grace:

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