Text

Semiannual Rept,Plant Radioactive Effluent Releases, Jul-Dec 1981
	ML20041C750
Person / Time
Site:	Hatch
Issue date:	02/25/1982
From:	Manry M; GEORGIA POWER CO.
To:	;
Shared Package
ML20041C742	List: PM-82-142, Semiannual Rept,Plant Radioactive Effluent Releases, Jul-Dec 1981; PM-82-143, Forwards Semiannual Rept,Plant Radioactive Effluent Releases,Jul-Dec 1981;
References
	PM-82-142, NUDOCS 8203020530
	Download: ML20041C750 (46)
	v • d • e

Georgia Powtr C:mpiny Post Office Box 439 B1xisy, Georgia 31513

. Telephone 912 367 7781 912 537-9444 O

GeorgiaPbwer Edwin 1. Hatch Nuclear Plant p$bhgaf.k225, 1982

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'l PLANT E.

I.

HATCH' Semi-Annual Radioactive Effluent Release Report Mr. James P. O'Reilly U. S.

Nuclear Regulatory Commission Office of Inspection and Enforcement Region II, Suite 3100 101 Marietta Street Atlanta, Georgia 30303 l

Dear Mr. O'Reilly:

Pursuant to Section 5.7.1.b in Appendix B,

Environmental Technical Specifications, of the Plant Edwin I.

Hatch Operating

Licenses, please find enclosed the Semi-Annual Report for Plant Radioactive Effluent Releases, July 1, 1981 through December 31, 1981.

G41A m

r' M. Manry Plant Manager WHR/tb xc:

G.

F.

Head (1)

J.

T.

Beckham (1)

C.

T.

Jones (1)

T.

V. Greene (1)

C.

L.

Coggin (1)

W.

H.

Pogers (4)

T.

E.

Byerley (3)

W.

H. Ollinger (1)

D.

B. Cockran (1)

J.

Setser, Ga Dept. Nat. Resources (1)

()

File:

M84-4 8203020530 820225 PDR ADOCK 05000321 R

PDR

Grorgia Powtr Comptny Post Office Box 439 Bzzley Georgia 31513 Telephone 912 367-7781 A

912 537-9444 O

Georgiar'bwer 1

Edwin 1. Hatch Nuclear Plant February 25, 1982 PM-82-143 i

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PLANT E.

I.

HATCH Semi-Annual Radioactive Effluent Release Report Director of Inspection and Enforcement

% Distribution Services Branch U.

S. Nuclear Regulatory Commission Washington, D. C.

20555 O ceatte=ea:

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, 1981 through December 31, 1981.

/1%kML M. Manry Plant Manager WHR/tb O

4

_ _.. _ _ _. ~

to GEORGIA POWER COMPANY PLANT E.

I.

HATCH UNITS NO. 1& 2 SEMI-ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JULY 1, 1981 - DECEMBER 31, 1981 O

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-+-

f PLANT E.

I.

HATCH SEMIANNUAL REPORT l

. PLANT RADIOACTIVE EFFLUENT RELEASES SECTION TITLE PAGE 1.

LIQUID EFFLUENTS 1

4 l.1 REGULATORY LIMITS 1

i l.2 MAXIMUM PERMISSIBLE CONCENTRATIONS 2

i i

1.3 MEASUREMENTS AND APPROXIMATIONS OF j

TOTAL RADIOACTIVITY.

4 t

1.4 LIQUID EFFLUENT RELEASE DATA 6

i i

2 GASEOUS EFFLUENTS 23 I

2.1 REGULATORY LIMITS 23 2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 25 2.3 GASEOUS EFFLUENT RELEASE DATA 29 O

3 SOLID WASTE 29 i

3.1 REGULATORY SPECIFICATIONS 29 3.2 SOLID UASTE DATA 29 4

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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 8-11 1-3 LIQUID RADWASTE $NALYSIS - UNIT II 12-15 1-4 LIQUID RADWASTE DISCHARGE PERMIT 16 1-Sa, b LIQUID RADWASTE DATA COMPILATION 17, 18 TABLE LIST OF TABLES PAGE l-la, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL. REPORT, LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 19, 20 1-2a, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-BATCH ONLY' 21, 22 2-la-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENT-O-

SUMMATION OF._AL_L RELEASES 30-32 2-2a-c EFFLUENT AND WASTE DISPOSAL SEMI- -

ANNUAL REPORT, GASEOUS EFFLUENTS-ELEVATED RELEASE 33-35

~

2-3a-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-GROUND LEVEL RELEASES 36-38 3-la, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, SOLID WASTE AND IRRhDIATED FUEL SHIPMENTS 39, 40 O

Iee' um

PLANT RADIOACTIVE EFFLUENT RELEASES 1

LIQUID EFFLUENTS 1.1.

REGULATORY LIMITS oO 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.

s 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 73y process radioactive._ Liquid wastes prior to their discharge when the projected cumulative release rate could exceed 1.25 Ci/ reactor / calendar

quarter, excluding tritium and dissolved gases.

7.

The maximum radioactivity to be contained in any liquid radwaste tank that can be discharged directly to ' the environs shall not exceed 10 C1, 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 desInn 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.

1

1.2. MAXIMUM PERMISSIBLE cot;CENTRATIONS 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 (U~l 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 finsion reactor have been grouped according to MPC value and type of radiation ar shown in Figure 1-1.

The cancentration 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 f roy 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, s

Only two pure beta emitters, Sr-89 and Sr-90, have MPC values less than 9 X N 10

-6 uCi/ml.

Individual measurements are made on proportional conposite liquid radwaste samples to determine the Sr-89 and Sr-90 co7 centration or MDA value to be applied to individual batch release calculations.

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

separate measurement is made for tritium since the gross beta technique does not provide an acceptable triticm measurement.

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

The maximum activity of gamma and beta emitting nuclides with MPC

}

values greater than 9

X 10._-6 uCi/ml, except for the 29

{s 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 ratics, 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 in a fission reaction (eg.

I-125, I-129 etc. ),

the methods outlined above provide a

iaeans to assign a

quantitatively measured or MDA value to all nuclides in Column 2.

These measured and calculated concentration values for each batch are

' aced to calculate the dilution ratio, release rate, and dilution rate prior to release of each batch.

Both the concentration and s

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:

2

A.

Fission and activation products - The total release values (not including tritium, gases, alpha) are comprised of the sum of the individual radionuclide activities and include the LLD concentration of all isotopes that were not measured but did not meet the minimum sensitivity limit as set forth

(~)

in the Environmental Tech Specs.

This sum is for each batch

\\_/

released to the river for the respective quarter.

Percent of applicable limit is determined from a mixed.nuclide MPC calculation.

The average concentration for each nuclide summed over all batches is divided by the corresponding individual MPC value.

The sum over all nuclides of the Ci/MPCi ratios times 100 is the percent of applicable limit for effluent releases during the y arter.

B.

Tritium - The measured tritium concentration in a composite sample is used to calculate the total release and avercge diluted concentration during each period.

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

C.

Dissolved and entrained gases - Concentrations of dissolved and entrained gases in liquid effluents are measured on each batch by Ge(Li) spectroscopy on a one liter sample from each liquid radwaste batch.

Dissolved and entrained gases for which measured or MDA concentrations are determined include noble gases with half lives greater than 8 hours9.259259e-5 days 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

,_s( j) additional information.

s A conservative release limit, the maximum sensi tivi ty limit of 4

X 10-5 uCi/ml of each dissolved a'nd entrai'ned radionuclide as specified in Regulatory Guide 1.21, has been applied in determining the percent of applicable limit.

O v

4 3

1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY.

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

The following measurements are performed as indicated:

n N'

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 3.

Gross Beta Each Batch Gas flow proportional counting.

4.

Sr-89

" Quarterly Chemical separation and Composite gas flow proportional counting 5.

Sr-90 Quarterly Chemical separation and Composite gas flow proportional counting 6.

Tritium Monthly Distillation and liquid Composite scintillation counting 7.

Alpha Monthly Gas flow proportional Composite counting

()

8.

Dissolved Gases Each Bat.c.h_

Ge(Li) spectrometry with on-line computer e

v 4

If a liquid radwaste tank cannot be reprocessed, a sample for O

eae1reis is e8xe# erom ene ee"x arter ene reaoirea reoiroo1eeioa 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.

Energy and net count data for all significant peaks are determined, and quantitative reduction _or MDA calculations are performed for the nuclides listed in Figure 1-1.

The quantitative calculations include corrections for counting

time, decay

time, sample

volume, sample

geometry, detector efficiency, baseline counts, and branching ratio.

MDA calculations, including the above corrections, are made based on the counts in two standard deviations of the baseline count at the location on the spectrum where a peak 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.

v The Liquid Radwaste Discharge Permit Printout is transferred item by item to the first portion cf the release permit (Figure 1-4) by a laboratory technician.

Although the computer could printout the release permit and will inform the technician if a batch cannot be discharged as d e s i r e~a",

a manual transfer of calculated results to the release permit by F.h e 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 reprocentative 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 shoun in Figure 1-Sa and b.

5

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 (m) 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 8.36 E-2 curies for the third quarter and 1.56 E-1 curies for the fourth quarter.

These values were approximately 1/150 for Unit 1 and 1/581 for Unit 2 for the third quarter and 1/74 for Unit 1 and 1/450 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 18.13% of the liquid radwaste reaching the sample tanks was discharged; 81.87%

was recycled back into both of the reactor water systems.

3.

A complete isotopic scan, gross beta, and gross gamma counts and computer cnalysis were performed prior to the release of each of the 696 discharge batches for both Units.

1.4 LIQUID EFFLUENT RELEASE DATA AU 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:

695 Total time period for releases:

86,761 minutes Maximum time period for a batch release:

350 minutes Average time period for batch release:

126.5 minutes Minimum time period for a batch release:

52 minutes Average stream flow during periods of release of effluent into a flowing stream:

2207.5 CFS O

6

i "IGURE l-1 METHODS OF MEETING, TABLE II, COLUMN 2 MPC LIMITS i

l I

- ;MPC RANGE GAMMA-RAY BETA ALPHA I

(U Ci/ml)

EMITTERS EMITTERS EMITTERS I-131,1-132, I-133 Sr-89, Sr-90 I-135, Cs-134 (Separation &

Gas Flow

< 9 X 176 (Ge(Li) Gamma-Ray Counting)

Spectroscopy)

ALL (Gas Flow

Counting,

' Sen'sitivity 0.01 CPM /ml)

Ba-La-140, Na-24,Cu-64 Tritium CO-60, Fe-59, Zn-65 19 X 10-6 Aa-110m, Mn-54, CD-S8 (Distillation &

Liquid Scintil-lation Counting)

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

No-239, Ce-141 Mo-Tc-99, Ce-Pr-144 (Gas Flow Count-(Ge(Li) Gamma-Ray ing Sensitivity Spectroscopy) 2 CPM /ml'

~

()

All others (Gross Gamma-Well Counter; Sensitivity

- 5 CPM /ml) 7 4

,---m r.

.--,,w-

,, - -, ~,,

---,---e-s-

--.-.L~

--,rn--

--~ --- -

FIGURE 1-2 PROCEDURE: HHP-7601 REVISION 1 0 DATA SHEET 8

+,++++r+or m m e m + m e m e,,e++++..++-.

m +

+

E.

I. Hatch Huc lear Plant Li qui d Radwast e Anal ysi s

+

/3 m.,++. m m m ++* m + m **-** m ***+*** m *+

z j Re ac t or# 1 Batch # 682 T ani: : llSTB1 Recirc time: 40 minutes Comment: HIGH SiO2 AHD TURE Run d at e : 12/18/81 0922 Count start date: 12/18/81 0830 Saraple vo l utae : 1000.00 ml C l oci: time: 3000 secs Ge orne t ry c ode: 1LHB-0 Live time: 3000 secs Detector # 2 MCA# 2 L i br ary: LPULE2 Operator: SL Energy (lev)=.42 + 1.000+Ch# + 0.000E+00+Ch#^2 + 0.000E+00+Ch#^3 : 12/19/81 0130 E-(-2.502?E+00) + 383.113 + E^(9.4863E-01)] : 12/18/81 0130 1/C1.498E-01 Eff

=

+

where E = Energy in Hev.

ISOTOPE EHERGY CCHCEHTF ATIGH EPROR HPC C/HPC t ! e '/ >

< uC 1/u l *

(uCi'ml)

(uCi/ml)

=========================-=======================_=================_

Cc-144 1;:.50

<4.102E-07 1E-05

<4.10E-02 Tc-99m 40.50

<4.787E-08 3E-03

<1.60E-05 Cc-141 145.40

<8.435E-08 9E-05

<9.37E-04 Hp-239 277.90

<3.479E-07 1E-04

<3.48E-03 Cr-51 320.10

<4.452E-07 2E-03

<2.23E-04 D

I-131 364.50

<5.772E-08 3E-07

<1.92E-01 (V

Z n-69 to 438.70

<4.816E-08 6E-05

<8.03E-04 H-187 479.50

<1.753E-07 6E-05

<2.92E-03 F-18 510.95 2.039E-07 8.622E-08 SE-04 4.08E-04 1-133 529.50

<5.347E-08 1E-06

<5.35E-02 Ba-140 537.40

<2.025E-07 2E-05

<1.01E-02 As-76 559.30

<1.194E-07 2E-05

<5.97E-03 Cs-134 604.81 3.490E-06 1.077E-07 9E-06 3.88E-01 Cs-137 661.61 4.204E-06 1.177E-07 2E-05 2.10E-01 Ho-99 739.70

<2.846E-07 4E-05

<7.11E-03 2r-97 743.50

<4.463E-08 2E-05

<2.23E-03 Zr-95 756.90

<8.223E-08 6E-05

<1.37E-03 Hb-95 765.80

<4.723E-08 1E-04

<4.72E-04 I-132 772.60

<4.847E-08 SE-06

<6.06E-03 Co-58 810.60

<5.593E-08 9E-05

<6.21E-04 Hn-54 834.e2 2.768E-07 4.408E-08 1E-04

2. 77E -03 Ag-110m 884.70

<5.221E-08 3E-05

<1.74E-03 Zn-65 1115.68 2.844E-06 1.840E-07 1E-04 2.84E-02 1-135 1260.50

<7.862E-08 4E-06

<1.97E-02 Fe-59 1291.60

<7.808E-08 6E-05

<1.30E-03 Co-60 1332.76 7.594E-07 6.609E-08 3E-05 2.53E-02 Cu-64 1345.90

<4.961E-06 2E-04

<2.48E-02 Ha-24 1368.55

<3.180E-08 3E-05

<1.06E-03 L a-14 0 1596.60

<4.777E-08 2E-05

<2.39E-03 Hn-56 1811.00

<3.602E-08 1E-04

<3.60E-04 Sr-89 (BETA)

<1.000E-08 3E-06

<3.33E-03 Sr-90 (EETA)

<1.000E-09 3E-07

<3.33E-03 H-3 (EETA) 4.040E-04 4.000E-05 3E-03 1.35E-01

[,)

Fe-55 (EETA)

<1.000E-06 SE-04

<1.25E-03 P-32

( EC >

<2.000E-07 2E-05

<1.00E-02 Hesaured t ot al 2 4.158E-04 4.000E-05 7.90E-01 LLD tot al z

<9.051E-06

<3.98E-01 Tot al s 4.248E-04 1.19E+00

.8

FIGURE 1-2 (CONTINUED)

DISSOLVED GASES Xe-133 81.40 6.020E-06 2.013E-07 4E-05 1.50E-01 Kr-88 196.10

<1.055E-07 4E-05

<2.64E-03 Xe-133ra 233.18

<4.852E-07 4E-05

<1.21E-02 q

Xe-135 249.87 4.775E-06 8.133E-08 4E-05 1.19E-01 Q

Kr-85m 305.00

<2.614E-07 4E-05

<6.53E-03 Kr-87 402.70

<7.836E-08 4E-05

<1.96E-03 Xe-138 434.50

<5.231E-08 4E-05

<1.31E-03 Measured gas totals 1.079E-05 2.171E-07 2.70E-01 LLD gas tot als

<9.827E-07

<2.46E-02 Total g s2 1.178E-05 2.94E-01 GP0ie ACTIVITY Ccunter Orcss

Background

Tiros Vol tie t Error C c., u r t 2 Counts

( fli n )

rn 1 Ac t i v i t y( c p m/ra l )

1 Sigma Well cryst.1 ISM 1355 20.0 2

3.68E+01 1.62E+00 P r c p o r t i c r. a t 392 199 10.0 2

9.65E+00 1.22E+00 ESTIMATEL HASTE TAtW VOLUf1E= 10694.00 gallons ESTIriATED ACTIVITY THIS EATCH EXCLUDIMG CASES:

1.6SE-02 Curies

( 1.68E+04 Microcuries)

EXCLUDIllG H-3 AtlD GASES: 4.77E-04 Curies

( 4.77E+02 Microcuries)

THE ACTIVITY OF THIS ERTCH (EXCLUDIrlG H-3 At4D GASES) IS 476.75 uCi O

THE NAMIMUM TAtlK RELEASE LIMIT IS 300 uCi V

LAB 5UPERVISOtt APPROVAL MEEDED FOR THIS RELEASE PELEASE APPRCVED BY: MCP Liquid Radu ast e Re1 ease S u m ra arv 1 )f te ns, conc., excluding H-3 and dissolved gases (uCi/ml): 1.1SE-05 +- 2.70E-07 Meas. conc.. including H-3, excluding gases

4.16E-04 +- 4.00E-05 2)Calcul at ed LLD concent rat ion, excluding dissolved gases (uCi/ml): 9.05E-06 3)C al c ul at ed MPC rat t o (C/MPC of meas., including g as e s ) : 1.06E+00 4 ) M i n i rnum dilution flou rate (gpm):

10000 5 ) M ax i m u ru t anL di s c h arge floo rate (gpm): 168113 6)Specifled t ank (100 r at e ( g ptn ) : 90 7)Pado as t e raonitor trip setting: 2344 A = 2.26E-05, u C i / ra l E, 2000, Monitor BG CPS C = 4653000.00, Moni t or CPS per uCi/ml F= 2,Conserv. F ac t or A includes rneaaured ' selected','other' nuclides and gases but excludes:

(p)

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

8)Es t i m at e d conc. of ru e as. nuclides at point of re l e as e (uCi/ml): 3.709E-06 9)!1onitor ro ax'i r urn to ensure 10CFR20 l i ra i t a are not exceeded: 11114 a

9 l

ESTIMAT SSTi5 MREM Isotope H. 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-T c - 99 ta 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 N-Kr-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Me-133%

0.00E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-125 0.00E+00 0.GOE-00 0.00E+00 0.00E+00 0.00E+00. 0.00E+00 0.00E+00 Up-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-C0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cc-!t 0.00E-Oe 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-E7 0.005-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Vc - R ?

0.00E-00 0.00E-00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2rrA9e 0.00" 00 0.00E+GO 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 W-137 0.00i. 00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F-13 6.79E-14 6.12E-13 0.00E+00 0.00E+00 0.'00E+00 0.00E+00 '1.81E-14 I-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.00E+00 ' O.~ 0 0 E + 0 0 0.'00E+00 Ba-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 As-76 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 1.04E-03 5.33E-04 1.27E-03 0.00E+00 4.11E-04 1.36E-04 2.22E-05 Cs-137 7.35E-04 S.24E-04 1.12E-03 0.00E+00 3.82E-04 1.27E-04 2.18E-05 Ho-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2r-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00Ed90 0.00E+00 0.00E+00 2r-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+10 0.00E+00 0.00E+00 Hb-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+AO 0.00E+00 0.00E+00-I-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 9.06E-OS 0.00E+00 4.75E-07 0.00E+00 1.41E-07 0.00E+00 1.45E-06 A g-110 rn 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2n-65 2.42E-05 1.6SE-05 5.37E-05 0.00E+00 3.59E-05 0.00E+00 3.38E-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 2.5SE-06 0.00E+00 1.17E-06 0.00E+00 0.00E+00 0.00E+00 2.20E-05 Co-64 0.00E+00 0.00E+00 0.00E+00- U.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 L a-14 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 'O.00E+00 0.00E+00 Mn-56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 1.61E-07 0.00E+00 1.61E-07 1.61E-07 1.61E-07 1.61E-07 1.61E-07 Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot al 1.80E-03 1.37E-03 2.44E-03 1.61E-07 S.29E-04 2.63E-04 1.01E-04 Curaul at i ve dose this YEAR (includes estimate for thi s b atch):

Whole body 5.98E-01 mrem Percent of Tech Spec Limit:

1.99E+01-Bone 4.58E-01 rarem Percent of Tech Spec Limit:

4.58E+00 l

Liver S.10E-01 rarem Percent of Tech Spec Limit:

S.10E+00 l

Thyroid 2.28E-01 mrem Percent of Tech Spec Limit:

2.2SE+00 Kidney 2.74E-01 mrem Percent of Tech Spec L i ra i t :

2.74E+00 4

Lung 8.81E-02 mrem Percent of Tech Spec Limit:

S.31E-01 l

GI-LLI 3.46E-02 mrera Percent of Tech Spec Limit:

3.46E-01 Curnul at i ve dose this GUARTER (i nc l ude s est i ra at e for this batch):

Whole body 1.71E-01 mrem Percent of Tech Spec Limit:

1.14E+01 Bone 1.31E-01 rur e m Percent of Tech Spec Limit:

2.62E+00 A(_)

Liuer 2.32E-01 mrem Percent of Tech Spec Limit:

4.64E+00 Thyroid 1.12E-01 mrem Percent of Tech Spec Limit:

2.25E+00 Vidnev

7. 92E-02 rarem Percent of Tech Spec Lirnit:

L.5SE+00 i

Lung

2. 50E-02 rare rn Percent of Tech Spec Limit:

5.01E-01 GI-LLI 1.03E-02 mreru Percent of Tech Spec Limit:

2.06E-01 10

FIGURE 1-2 (CO.lTINUED)

Pro jec t ed curaul at i ve dose this QUARTER (i nc l udes es t i raat e f or t hi s b at ch):

Hhole body 1.99E-01 mrem (q

Bone 1.53E-01 rar e ra v

Liver 2.70E-01 m r e ra Thyroid 1.31E-01 rar e m Kidney

9. 2 3E-02 rure ra Lung

2. 9 2 E - 0 2 r..r e ra G -LLI

..* C E - 02 ra r e r.i JEAP includes e s t i ra nt e for this bat c h):

Co al a e ei s - I '

<f

-*i i'.

2.635E-0 Curies. - c'ot

"-I v'd di s s olved ga343 u:.

s '. a e ne s t e r.. Ih:utd be OPEPABLE due to projected dole for Hhole Body LEU

s' men' s o s t e rn h as been demonstrated OPERABLE, confirmed by: SL T. A T C h :s 692 DATA 5UCCEs5 FULLY STORED SPECTRUM STORED AS: LRH1 l

11 s..

FIGURE 1-3 PPOCEDURE: HilP-7601 REVISIOll: 8 DATA SHEET 8 E.

I.

Hatch fluclear Pl ant Liquid Radwaste Analysis

- - - - m ***** m m m *** m

m ** m m

m m Q

Re ac t or # 2 Batch # 772 Tank: CHSTB2 Recirc time: 65 minutes Comment: HIGH C0tlD.,

All'., T U R B Run date: 12/07/81 1045 Count start date: 12/07/81 0940 Sample volume: 1000.00 ml Clock time: 3000 secs Geometry codc: 1LHB-0 Live time: 3000 secs Detector # 2 MCA# 2 Library: LRULB2 Operator: SL Energy (kev)=.40 + 1.000*Ch# + 0.000E+0,0*Ch#^2,+ 0.000E_+00*Ch#^3,: 12/07/81 0014 Ef f = 1/[1.098E-01

E^(-2.6546E+00) + 390.256

E^(9.4336E-01)3 : 12/04/81 0000 uhere E = Energy in HeV.

ISOTOPE EllERGY C0tiCEllTR A T I 0tt ERROR MPC

'C/MPC (kev)

(uCi/ml)

(uCi/ml>

(uCi/ml)

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

Ce-144 133.50

<2.605E-07 1E-05

<2.61E-02 Tc-99m 140.50

<3.314E-08 3E-03

<1.10E-05 Ce-141 145.40

<5.795E-08 9E-05

<6.44E-04 tip-239 277.90

<2.428E-07 1E-04

<2.43E-03 Cr-51 320.10 (2.982E-07 2E-03

<1.49E-04 h

I-131 364.50

<3.846E-08 3E-07

<1.28E-01 Zn-69m 438.70

<3.417E-08 6E-05

<5.70E-04 H-187 479.50

<1.113E-07 6E-05

<1.86E-03 F-18 511.96 6.944E-08 2.137E-08 SE-04 1.39E-04 I-133 529.50

<3.374E-08 1E-06

<3.37E-02 Ba-140 537.40

<1.307E-07 2E-05

<6.53E-03 As-76 559.30

<7.689E-08 2E-05

<3.84E-03 Cs-134 604.35 8.334E-07 5.165E-38 9E-06 9.26E-02.

Cs-137 661.72 1.216E-06 6.820E-08 2E-05 6.08E-02 Mo-99 739.70

<1.773E-07 4E-05

<4.43E-03 Zr-97 743.50

<2.605E-08 2E-05

<1.30E-03 Zr-95 756.90

<6.372E-08 6E-05

<1.06E-03 tib-95 765.80

<3.221E-08 1E-04

<3.22E.

I-132 772.60

<3.537E-08 8E-06

<4.42E-03 Co-58 810.60

<3.257E-08 9E-05

<3.62E-04 (1n-54 834.80

<2.538E-08 1E-04

<2.54E-04 Pg-110m 884.70

<3.762E-08 3E-05

<1.25E-03 Zn-65 1115.40

<7.449E-08 1E-04

<7.45E I-135 1260.50

<6.239E-08 4E-06

<1.56E-02 Fe-59 1291.60

<5.022E-08 6E-05

<8.37E-04' Co-60 1332.50

<4.45eE-08 3E-05

<1.49E-03 Cu-64 1345.90

<4.213E-06 2E-04

<2.11E-02 fla-24 1368.55

<3.202E-08 3E-05

<1.07E-03 La-140 1596.60

<1.974E-08 2E-05

<9.87E-04 Mn-56 1811.00

<5.975E-08 1E-04

<5.98E-04 Cs-138 1436.56 5.350E-08 1.440E-08 4E-05 1.34E-03 Sr-89 (BETA)

<1.000E-08 3E-06

<3.33E-03 Sr-90 (BETA)

<1.000E-09 3E-07

<3.33E-03 A

H-3 (BETA) 4.570E-04 6.000E-07 3E-03 1.52E-01 Fe-55 (BETA)

<2.000E-06 SE-04

<2.50E-03 P-32

( EC >

<1.000E-07 2E-05

<5.00E-03 t1easured t ot al s 4.592E-04 6.066E-07 3.07E-01 LLD tot als

<8.416E-06

<2.74E-01 Tot als 4.676E-04 5.81E-01 12

FIGURE 1-3 (CONTINUED)

I' DISSOLVED GASES Xe-133.

80.99

<1.243E-07 4E-05

<3.11E-03 Kr-88 196.10 (6.689E-08 4E-05

<1.67E-03 Xe-133ra 233.18

<2.865E-07 4E-05

-<7.16E-03 1

Xe-135 249.60

<3.130E-08 4E-05 (7.82E-04 Kr-85ta 305.00

<1.945E-07 4E-05

<4'.86E-03 l

Kr-87 402.70

<4.793E-08 4E-05

<1.20E-031 Xe-138 434.50

<1.905E-08 4E-05'

<4.76E-04 fleasured gas tot al s 0.000E+00 0.000E+00 0.00E+00 LLD gas t otals

<7.705E-07

<1.93E-02 Total gas 7.705E-07 1.93E-02 4

s.

GROSS ACTIVITY Counter Gross

Background

T i rn e Vol Het Error Counts Counts (Min) ml Ac t i vi t y(c ptn/m l )

1 S i grn a 3

lle 11 Crystal 2236 1780 20.0 2

1.14E+01 1.58E+00-Proportional 357 10 10.0 2

1.74E+01 9.58E-01 ESTIMATED UASTE T AHi: VOLUME = $615.00 gallons ESTIl1ATED ACTIVITY THIS EATCH EXCLUDING GASES:

9.76E-03 Curies

( 9.76E+03 Microcuries) j EXCLUDIllG H-3 AND GASES: 4.62E-05 Curies

( 4.62E+01 Microcuries) i s

I i

Liquid Radwaste Release Summarv i

4 1 )fle as. conc., excluding H-3 and dissolved gases (uC i /ra l ): 2.17E-06 +- 8.93E-08 Y

lle as. conc., including H-3, excluding gases

4.59E-04 +- 6.07E-07 2)Calcul at ed LLD concentrat i on, excluding dissolved gases (uCi/ml): 8.42E-06

3) Cal cul at ed 11PC -rat i o (C/MPC of meas., including gases): 3.07E-01 4 )lli n i mu ro dilut ion flou rate (gpra ):

10000 4

5) Maximum tank discharge flou rate (gpm): 32876 6)Specified tank flou rate (gpra): 75 i

7)R adwas t e raoni t or trip setting: 764 A = 2.17E-06,uCi/ml B = 550, Monitor EG CPS C = 33120000.00, Moni t or CPS per uCi /tal F'=

2,Conserv. F ac t or j

A includes roensured ' selected','other' nuclides and gases but excludes:

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

3)Est imat ed conc. of roeas. nuc lides at point of release (uCi/ml): 3.418E-06

9) Undiluted concentration r.2ets 10CFR20 limits.

1 l

13 i

4

..,.,,,n

,n.,

.wn.-,.

c w.

FIGURE l-3 (CONTINUED)

ESTIMATED DOSES THIS EATCH, HREM Isotope H. 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+R0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133m 0.00E+00 c.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-85n.

0.00E400 3.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E*00 0.00E+00 I-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00Ese0 0.00E+00 Kr-87 0.00E+00 0.00E+00 0'.00E+00

'O.00E+00' O.00E+00 'O.00E+00 'O'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 H-187 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4

F-18 1.22E-14 1.10E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.24E-15 I-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ea-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 Cz-134 1.30E-04 6.69E-05 1.59E-04 0.00E+00 5.16E-05 1.71E-05 2.78E-06 Cs-137 1.12E-04 1.25E-04 1.71E-04 0.00E+00 5.81E-05 1.93E-05 3.31E-06 Ho-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 2r-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hb-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

(,')

Co-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ag-110m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C.00E+00 0.00E+00 0.00E+00 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cu-C4 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 Mn-56 0.00E+00 0.00E+00 0.00E+C0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-138 1.29E-22 1.31E-22 2.63E-22 0.00E+00 1.91E-22 1.SSE-23 1.11E-27 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 6.00E+00 0.00E+09 0.00E+00 0.00E+00 H-3 9.60E-08 0.00E+00 9.60E-08 9.60E-08 9.60E-08 9.60E-08 9.60E-08 Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot al 2.42E-04 1.92E-04 3.30E-04 9.60E-08 1.10E-04 5.65E-05 6.19E-06 n

s-14

FIGURE 1-3 '(CONI'INUED).

1 3

4

~

Curuul at ive dos e thi s YEAR (includes estimate for this batch):

14 hole body 1.06E-01 mrem Percent of Tech Spec Limit:

3.54E+00 Bone 8.15E-02 mrem Percent of Tech Spec Limit:

8.15E-01 Liver 1.44E-01 mrem Percent of Tech Spec Limit:

1.44E+00 Thyroid 1.06E-02 mrem Percent of Tech Spec Limit:

1.06E-01 Kidney 4.93E-02 mrem Percent of Tech Spec Limit:

4.93E-01 Lung 1.56E-02 mrem Percent of Tech Spec Limit:

1.56E-01 GI-LLI 9.22E-03 mrem Percent of Tech Spec Limit:

9.22E-02 i

j Cumulative dose th.s GUARTER (includes estimate for this batch):

Whole body

9. 07E-03 rarem Percent of Tech Spec Limit:

6.05E-01 Eone 7.13E-03 mrem Percent of Tech Spec Limit:

1.43E-01 1

Liver

1. 24E-02 mrem' s' Percent of Tech Spec Limit:.2.48E-01 Thyroid 6.14E-03 mrem Percent of Tech Spec Limit:

1.23E-01 Kidney 4.23E-03 mrem Percent of Tech Spec Limit:

8.47E-02 Lung 1.36E-03 mrem

.ercent of Tech Spec Limit:

2.71E-02 GI-LLI 5.97E-04 ra r e m Percent-of Tech Spec Limit:

1.19E-02 i

Projec ted curuul at i ve dose this GUARTER (includes estimate for this batch):

!! hole body -1.23E-02 mrem Bone 9.65E-03 mrem Liver 1.68E-02 mrem i

Thyroid 8.31E-03 mrem i

Kidney 5.73E-03 mrem Lung 1.83E-03 mrem GI-LLI S.08E-04 mrem Cumulative measured activity this YEAR (includes estimate for this batch):

1.045E-01 Curies, excluding H-3 and dissolved gases EATCH# 772 DATA SUCCESSFULLY STORED SPECTRUM STORED AS: LRW2 9

6 15

FIGURE 1-4 f)AT/> PArl'A M ft (OATA Gldl] 3)

O D

Pt MIT E I. ItATCH DATCH NO.

l.1@l9.85fN Nid_,EIU$OUlOE_EEBdlT UNIT #

DATE TN!( 10 UE RELCA".r0 REATN F(41 NECESSITY OF DISCIL\\RGE _

(

RECIRC. START TIME __ _

UAMPLE TIME __

REC 1HC. DURATION.

MINUTES

1.

LADORATORY Nb4YSIS (1) MEA"stJtED RADIC'."JCLIOC CONCErJTRATION

. E__ i __

.E___ uCi/ml uC1/ml (2) CALCtI.ATEO LLD LIMIT CONCENTRATIONS (3) CALCULATCD PPC ItATIO: E (Ci/MPCi)

(4) MIN!!@t DILUTION FLOW RATE __

CPM (5)

MAX. CALCULATFD T/M< DISCitARGE RATEI 10Eg_SSC. F.4.g)

CPM CPM (G) SPECIFIED TAN:( DISCHARGE RATEI 1(5)/2 ___ ~

+

CPS (7) RADWASTE,MCNITOR TRIP SETTINGI A = Ce(Li>(1) uC1/mi B = MONITOR GC CPS F = C'ONSERVATIVE C = MONITOR CPS PER Ce(Li) uCi/ml FACTOR MONITOR ALARM SETPDINT (CPS) = (C X A X F) +B+3&

..___............. a. ______

COMPLETED BY DATE COMPOSITE LITER STORED (INITI/4 S)

LAG FOREf%N APPROVEf

.t..._____,

(B) RADWASTE MONITOR MAX. CPS TO DE WITHIN 10 CFR 20 LIMITSI CXAX

_( E.1 + ( 4 )

(G) (3)

_ cps II. OPEllATIO'J3 ItJIT.

CPS (s) LIGUID RADWASTE MONITOR TRIP SET ATI

(-

(10) CONFIRMED DILUTION FLOW RATE CPM (11) VALVE LINEUP CHECKED AS PER HNP-TANK DIS. INIEGRATOR DIS. RATE DIL. TOTAL RIVER EL.

MONITOR DATE. Tpjg_. _t;EVEL.%

RDNG.

CPM CAL FT CPS t

SIART 4&

-...~

WO l

COMPLETED OY DATE MIN.

CAL.

FJ41FT FOREMAN APPROVED DURAfION TOTAL RELEASE u---------------------r----"

O 10 MIN AFTFR STNIT

AFTEH FLUSHING t

f III.LADORATORY

{

ml i

(12) TOTAL TANK VOLUvE DISCHARGED (CAL. X 3,7C5 3 l

(13) TOTAL ACTIVITY DICCitARCED ((1) X (1211

____ uCi CFS l

RIVER FLOW RATE (FROM FCAR 2.4-G)

(14)

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

i COMPLETED DY DATE A

(

)

v LM1 FORElW4 APPROVED 1

16

FIGURE 1-Sa

' Liquid Pne'u'c 10 s Compi l at i on for Reg..Gutc; 1.21 R port E.

1.

Hatch Nuc lear Plant UNIT 1 l )-

Total Activity (Curies)

Quarter 3, 1981 Quarter 4, 1981 Eatches 391 thru 518 Batches 519 thru 714 Hame Measured Error High LLDs Tot al Measured Error. High LLDs Tot al Ce-144 1.77E-03 8.87E-05 0.00E+00 1.77E-03 8.56E-04 7.85E-05 2.22E-05 8.79C-04 Tc-99m 5.22E-04 7.39E-06

'5.22E-04 2.82E-03'1.09E-05 2.82E-03 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.89E-05 3.39E-06 0.00E+00 3.89E-05

-Hp-239 3.12E-04 2.96E-05 3.12E-04 3.74E-04 2.79E-05 3.74E-04 Cr-51 1.51E-03 6.03E-05 1.51E-03 1.84E-03 6.17E-05 1.34E-03 I-131 6.60E-03 2.25E-05 0.00E+00 6.60E-03 2.74E-02 4.96E-05 0.00E+00 2.74E-02 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 1.37E-03 1.40E-05 1.37E-03 3.65E-04 1.04E-05 3.65E-04 I-133 2.24E-03 1.76E-05 2.24E-03 6.01E-04 1.04E-05 6.01E-04 Ba-140 0.00E+00 0.00E+00 0.00E+00 6.74E-05 1.11E-05

+

6.74E-05 As-76 0.00E+00 0.00E+00 0.00E+00 2.95E-05 3.47E-06 2.95E-05 Cs-134 1.50E-02 3.69E-05 0.00E+00 1.50E-02 2.41E-02 5.38E-05 0.00E+00 2.41E-02 Cs-137 1.94E-02 4.35E-05 0.00E+00 1.94E-02 3.06E-02 6.37E-05 0.00E+00 3.06E-02 Mo-99 6.12E-04 3.34E-05 0.00E+00 6.12E-04 1.89E-03 5.74E-05 0.00E+00 1.89E-03 Zr-97 8.50E-06 1.88E-06 8.50E-06 0.00E+00 0.00E+00 0.00E+00 Zr-95 3.92E-05 5.52E-06 3.92E-05 1.38E-04 9.55E-06 1.38E-04 Hb-95 1.28E-04 5.91E-06 1.28E-04 5.26E-04 1.32E-05 5.26E-04 I-132 G.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

+

0.00E+00 Co-58 2.26E-04 7.68E-06 0.00E+0G 2.26E-04 7.59E-0* 1.60E-05 0.00E+00 7.59E-04 Mn-54 5.09E-04 1.13E-05 0.00E+00 5.09E-04 2.10E-03 2.29E-05 0.00E+00 2.10E-03

/~%

Ag-110m 1.85E-04 6.22E-06 1.85E-04 9.28E-05 6.21E-06 9.28E-05 2n-65 6.17E-03 4.86E-05 0.00E+00 6.17E-03 2.28E-02 9.56E-05 0.00E+00 2.28E-02 1-135 2.12E-04 1.27E-05 2.12E-04 6.45E-05 4.58E-06 6.45E-05 Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.47E-04 1.02E-05 0.00E+00 1.47E-04 Co-60 5.58E-03 3.11E-05 0.00E+00 5.58E-03 8.04E-03 4.09E-05 0.00E+00 8.04E-03 Cu-64 2.26E-03 3.20E-04 2.26E-03 5.11E-03 4.89E-04 5.11E-03 Ha-24 1.47E-03 1.79E-05 1.47E-03 4.69E-04 5.83E-06 4.69E-04 La-140 1.16E-04 5.06E-06 1.16E-04 5.50E-04 1.17E-05 5.50E-04 Mn-56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C2-138 8.21E-05 3.01E-06 8.21E-05 1.38E-05 1.43E-06 1.38E-05 Rb-88 1.76E-05 1.54E-06 1.76E-05 1.36E-06 4.48E-07 1.36E-06 Hb-97 5.34E-05 2.57E-06 5.34E-05 5.50E-07 1.29E-08

+

5.50E-07 Cs-136 0.00E+00 0.00E+00 0.00E+00 7.58E-04 1.40E-05 7.58E-04 Sr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.38E-03 3.72E-04 0.00E+00 1.38E-03 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 3.54E-03 3.54E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 0.00E+00 0.00E+00 6.15E-03 6.15E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals 6.64E-02 3.52E-04 9.69E-03 7.61E-02 1.34E-01 6.43E-04 2.22E-05 1.34E-01 Xe-133 2.93E-02 7.07E-05 0.00E+00 2.93E-02 2.91E-02 8.15E-05 0.00E+00 2.91E-02 Kr-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.63E-06 1.07E-06 0.00E+00 2.63E-06 Xe-133m 7.15E-04 5.30E-05 0.00E+00 7.15E-04 1.74E-04 2.53E-05 0.00E+00 1.74E-04 Xe-135 3.87E-02 3.63E-05 0.00E+00 3.87E-02 9.81E-03 2.12E-05 0.00E+00 9.81E-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 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 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 5.61E-07 1.76E-07 0.00E+00 5.61E-07 3.41E-10 9.22E-11 0.00r+00 3.41E-10

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

00E+00 1.51E-02 3.50E-04 0.0bi*e

._-1:

i

'i> 0 2

3. 5 3E-05 0. 00E+00 6. 87E-02 5. 42E-02 3. 61 E -04 0.*.3

+

2 1

!40 LLD requirenent.in Tech. Specs.

17

FIGUES 1-5b Liqui: ~ s u a3 t e D at a Compilation for Reg. Guide 1.21 Report E.

I.

Hat ch Huc l ear Pl ant UNIT 2 (3

i

)

Total Activity (Curies)

Quarter 3, 1981 Qu art er 4, 1981 Batches 457 thru 682 Batches 683 thru 828 H am?

Hessured Error Higa LLDs Tot al Measured Error High LLD:

Tot al Ce-144 7.90E-05 1.46E-05 0.00E+00 7.90E-05 2.74E-05 2.02E-05 0.00E+00 2.74E-05 T c - 9 9.~

1.50E-06 2.71E-07 1.50E-06 3.13E-04 2.92E-06

+

3.13E-04 Cs-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 4.23E-06'1.16E-06 4.23E-06 1.33E-04 9.19E-06

+

1.33E-04 Cr-51 2.23E-04 1.27E-05 2.23E-04 7.48E-05 1.13E-05 7.48E-05

+

I-131 2.38E-04 4.43E-06 0.00E+00 2.38E-04 8.61E-04 8.57E-06 0.00E+00x9.61E-04 2n-69m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-187 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

+

0.00E+00 F-18 7.18E-04 5.30E-06 7.18E-04 2.95E-04 5.48E-06 2.95E-04 I-133 4.35E-05 2.18E-06

+

4.35E-05 7.10E-05 2.14E-06 7.10E-05 Ea-140 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 8.56E-06 2.21E-06 8.56E-06 C2-134 3.57E-03 1.56E-05 0.00E+00 3.57E-03 7.24E-03 2.23E-05 0.00E+00 7.24E-03 C2-137 4.53E-03 1.78E-05 0.00E+00 4.53E-03 9.57E-03 2.71E-05 0.00E+00 9.57E-03 Ho-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.16E-04 1.67E-05 0.00E+00 2.16E-04 2r-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

+

Zr-95 6.38E-05 3.21E-06 6.38E-05 4.10E-05 3.65E-06 4.10E-05 Hb-95 1.37E-04 2.90E-06 1.37E-04 8.78E-05 3.66E-06

+

8.78E-05 I-132 2.44E-06 3.59E-07 2.44E-06 3.22E-06 2.76E-07 3.22E-06 Co-58 2.62E-05 1.73E-06 0.00E+00 2.62E-05 1.23E-05 1.19E-06 0.00E+00 1.23E-05 gg Un-54 3.96E-05 2.34E-06 0.00E+00 3.96E-05 6.59E-05 3.33E-06 0.00E+00 6.59E-05

(_)

Ag-110r4 9.93E-06 1.43E-06 9.93E-06 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.98E-03 2.35E-05 0.00E+00 1.98E-03 1.65E-03 2.51E-05 0.00E+00 1.65E-03 I-135 1.55E-05 2.29E-06 1.55E-05 6.16E-06 1.37E-06,

6.1,6E-06 Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 1.21E-03 1.28E-05 0.00E+00 1.21E-03 7.17E-04 1.30E-05 0.00E+00 7.17E-04 Cu-64 0.00E+00 0.00E+00 0.00E+00 3.01E-04 1.51E-04 3.01E-04 Ha-24 4.14E-03 1.76E-05 4.14E-03 2.14E-04 4.72E-06 2.14E-04

+

La-14G 9.69E-06 1.75E-06

+

9.69E-06 1.45E-05 1.77E-06 1.45E-05 Hn-56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-125 3.82E-05 2.72E-06 3.82E-05 0.00E+00 0.00E+00 0.00E+00 I-134 8.08E-06 8.80E-07

+

8.08E-06 0.00E+00 0.00E+00

+

0.00E+00 C2-138 6.93E-05 2.06E-06 6.93E-05 6.15E-06 6.79E-07

+

6.15E-06 Rb-88 1.39E-05 1.18E-06 1.39E-05 0.00E+00 0.00E+00

+

0.00E'+00 Hi-65 0.00E+0V 0.00E+00

+

0.00E+00 2.17E-06 1.34E-06 2.17E-06 C2-136 0.00E+00 0.00E+00 0.00E+00 3.13E-05 1.72E-06 3.13E-05 Sr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.22E-04 1.58E-04 0.00E+00 2.22E-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 5.89E-03 5.89E-03 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 1.72E-02 4.55E-05 5.89E-03 2.30E-02 2.22E-02 2.25E-04 0.00E+00 2.22E-02 Me-133 9.69E-03 3.2SE-05 0.00E+00 9.69E-03 1.46E-03 2.03E-05 0.00E+00 1.46E-03 Vr-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00Et00 N e - 133 rn 3.15E-04 1.53E-05 0.00E+00 3.15E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 1.66E-03 8.75E-06 0.00E+00 1.66E-03 1.32E-03 8.73E-06 0.00E+00 1.?2E-03

[')

Fr-85m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00

\\l Vr-87 1.11E-06 3.95E-07 0.00E+00 1.11E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Me-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

~2-02 3.72E-05 0.00E+00 1.17E-02 2.78E-03 2.21E-u"

..: e E C

_. 'SE-u3 Ho _L3 requircruent in Tech Spec 18

TABLE l-la r

E.

I. Hat c h fluc l e ar Plant UllIT 1

-]

'wi EFFLUEllT AtID HASTE DISPOSAL SEMI Atit4UAL REPORT 1981 LIQUID EFFLUEt4TS-SUMMATIOtt OF ALL RELEASES Unit Quarter Quarter Est Tot al 3

4 Error.

A.

Fission & activation products 1.

'n' al release (not including H3,

~

ise: ..1pha)

Ci 6.64E-02 1.34E ^1!

4,J4E-O'

.werage diluted concentration 1urir.a period uCi/mi 7.23E-08 8.3 E_-

l J.

F e r c e n' of app l i c ab l e 1imit 2.99E+00 6.C

,1+ v o l B.

Tritium 1.

Tot al release Ci 2.24E+00 2.0SE+00 2.82E+011 2.

Average diluted concentration during period uCi/mi 2.44E-06 1.30E-06 3.

Percent of applicable 1imit 8.14E-02 4.34E-02 C.

Dissolved and entrained gases 1.

Total re l e as e Ci 6.87E-02 5.42E-02 4.23E+01[

O 2.

Average diluted con entration k- '

during period uCi/ml 7.48E-08 3.38E-OS 3.

Percent of applicable Itmit 1.87E-01 8.46E-02 D.

Gross alpha radi oac t ivi ty l

1.

Tot al release l

Ci I 3.31E-07l 1.52E-061 1.20E+02l

~

lE. Volume o t' waste (prior to dilution >l liters l 5.19E+06l 7.91E+06l 1.00E+01l lF. Volume of dilution u at er used l 1iters l 9.14E+08l 1.59E+09l 1.60E+02-l l

l i

l'h

,5 19

' T ABLE.1-lb

/"

E.

I.

Hatch Huc lear Pl ant UNIT 2-C).

EFFLUEHT AHD HASTE DISPOSAL SEMIAHHUAL REPORT 1981 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter-Est Tot al 3

4 Error A.

Fission & act.ivation products 1.

Tc t al release (not including H3,

[

g ase s, al ph a)

Ci 1.72E-02 2.22E-02 4s1(E+01[

2.

Auerage di lut ed conc entrat iver during period uCi/mi 1.50E-08 2.44E-08!

3.

Percent of applicable limit 1.47E-01 4.80E-01i E.

Tritium 1.

Total r e l e as e C1 2.70E+00 1.60E+00 2.80E+01[

2.

Average diluted concentration during period uCi/mi 2.37E-06

-1.76E-06 3.

Percert of applicable limit 7.89E-02 5.87E-02 C.

Dissolved and entrained gases 1.

Total release C1 1.17E-02 2.78E-03 4.23E+01l

(

2.

Average dilut ed concentrat ion during period uCi/ml 1.02E-08 3.06E-09 3.

Percent of applicable limit

4 2.55E-02 7.65E-03 D. Gros s al pha radi oac t i vi t y l

1.

Total release l

Ci j 0.00E+00l 4.56E-071 1.20E+02l lE. Volume of waste (prior to dilution >l liters l 5.77E+06l 4.27E+06l 1.00E+01]

[F. Volume of dilution water used l liters l-1.14E+09l

9. 04E+08 l li60E+02 l O

20

TABLE l-2a i ()

E.

I.

Hat ch Huc l ear Plant UNIT 1 EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1981 i

LIQUID EFFLUENTS CONTINUOUS MODE B ATCH 110DE Huclides Released Unit Quarter Quarter Quarter Quarter 3

4 3

4 Ce-144 Ci 1.77E-03 8.56E-04 Tc-99m Ci 5.22E-04 2.82E-03 Ce-141 Ci 0.00E+00 3.89E-05 Hp-239 Ci 3.12E-04 3.74E-04 Cr-51 Ci 1.51E-03 1.84E-03 1-131-Ci 6.60E-03 2.74E-02 Zn-69m Ci 0.00E+00 0.00E+00 W-187 Ci 0.00E+00 0.00E+00 F-18 Ci 1.37E-03 3.65E-04 I-133 01 2.24E-03 6.01E-04 Ba-140 C1 0.00E+00 6.74E-05 As-76 Ci 0.00E+00 2.95E-05 C2-134 Ci 1.50C-02 2.41E-02 Cs-137 C1 1.94E-02 3.06E-02 Mo-99 Ci 6.12E-04 1.89E-03 Zr-97 Ci 8.50E-06 0.00E+00 Zr 45 Ci 3.92E-05 1.38E-04 Hb-45 Ci 1.28E-04 5.26E-04 cg g) 1-1;I Ci I

0.00E+00 0.00E+00 Co-58 Ci

[~

2.26E-04 7.59E-04 Mn-54 Ci 5.09E-04 2.10E-03 Ag-110m Ci 1.85E-04 9.2SE-05 2n-65 Ci 6.17E-03 2.28E-02 I-135 Ci 2.12E-04 6.45E-05 Fe-59 Ci 0.00E+00 1.47E-04 Co-60 Ci 5.58E-03 8.04E-03 Cu-64 Ci 2.26E-03 5.11E-03 Ha-?4 Ci 1.47E-03 4.69E-04 La-140 Ci 1.16E-04 5.50E-04 Mn-56 Ci 0.00E+00 0.00E+00 Cs-138 Ci 8.21E-05 1.38E-05 Rb-88 Ci 1.76E-05 1.36E-06 Hb-97 Ci 5.34E-05 5.50E-07 Cs-136 Ci 0.00E+00 7.58E-04 3r-89 Ci 0.00E+00 1.38E-03 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

Tot al for period (aboue) l Ci l

l l 6.64E-02l 1.34E-011 i

Xe-133 Ci 2.93E-02 2.91E-02 Kr-88 Ci 0.00E+00 2.63E-06 Xe-133m Ci 7.15E-04 1.74E-04 Xe-135 Ci 3.87E-02 9.81E-03 s,

Kr-85m Ci 0.00E+00 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 T' ~ ~

Xe-135M Ci 3.61E-07 3.41E-10 Xe-131m Ci

! 0.00E+00 1.51E-02

~~~'

21

T ABLE l-2b '

r.

E.

I.

Hatch Nucl ear Pl ant UNIT 2 EFFLUEllT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1981 LIQUID EFFLUENTS C0t4TINUOUS MODE BATCH MODE lluclides Released Unit Quarter Luarter Quarter Quarter 3

4 3

4 Ce-144 Ci 7.90E-05 2.74E-05 Tc-99m Ci 1.50E-06 3.13E-04 Ce-141 Ci 0.00E+00 0.00E+00 Ci 4.23E-06 1.33E-04 Hp-239 Cr-51 Ci 2.23E-04 7.48E-05 I-131 C1 2.38E-04 8.61E-04 Zn-69m Ci 0.00E+00 0.00E+00 N-187 Ci 0.00E+00 0.00E+00 F-18 Ci 7.18E;04 2.95E-04 I-133 C1 4.35E-05 7.10E-05 Ba-140 Ci 0.00E+00 0.00E+00 As-76 Ci 0.00E+00 8.56E-06 Cs-134 Ci 3.57E-03 7.24E-03 C5-137 Ci 4.53E-03 9.57E-03 (1o-99 Ci 0.00E+00 2.16E-04 Zr-97 Ci 0.00E+00 0.00E+00 Zr-95 Ci 6.38E-05 4.10E-05 4

tib-95 Ci 1.37E-04 3.78E-05

/"

i I-132 Ci 2.44E-06 3.22E-06 k

j Co-58 Ci 2.6LE-05 1.23E-05(

Mn-54 C1 3.96E-05 6.59E-05l Ag-110m Ci 9.33E-06 0.00E+00 2n-65 Ci 1.98E-03 1.65E-03 I-135 Ci 1.55E-05 6.16E-06 Fe-59 Ci 0.00E+00 0.00E+00 l

Co-60 Ci 1.21E-03 7.17E-04 Cu-64 Ci 0.00E+00 3.01E-04 l

tia-24 Ci 4.14E-03 2.14E-04 La-140 Ci 9.69E-06 1.45E-05 Mn-56 Ci 0.00E+00 0.00E+00 Sb-125 C1 3.82E-05 0.00E+00 l

I-134 Ci 8.08E-06 0.00E+00 l

Cs-138 Ci 6.93E-05 6.15E-06 Rb-88 Ci 1.39E-05 0.00E+00 Hi-65 Ci-0.00E+00 2.1?E-06 Cs-136 Ci 0.00E+00 3.13E-05 Sr-89 Ci 0.00E+00 2.22E-04 l

Sr-90 Ci 0.00E+00 0.00E+00 f

Fe-55 Ci 0.00E+00 0.00E+00 P-32 Ci 0.00E+00 0.00E+00 l

Total t'o r period (above) l Ci l

l l 1.72E-02l 2.22E-02l i

l l

l Xe-133 Ci 9.69E-03 1.46E-03 gg

()

Kr-88 Ct 0.00E+00 0.00E+00 Xe-133m Ci 3.15E-04 0.00E+00 l

l Xe-135 Ci 1.66E-03 1.32E-03 l

1_ _ __ _

Kr-85m Ci 0.00E+0i_ t.00E+00 j_

_ Kr-87 Ct i. 11 E -ui,

' 00E+00 Xe-138 Ci

,___1 0.00E4001 0.00E+00 22

2 GASEOUS EFFLUENTS 2.1. REGULATORY LIMITS a.

(1)

The release rate limit of noble gases from the site (v3 shall be:

Z Qig

_1.9 E6+ 1.0 Eg

+Qy (11E6

+ 44 b I1 i

B i

+n where Q Total release rate from main stack for both Units

=

3 in Ci/ cec (elevated release)

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

=

i=

The individual nuclide n = total nuclides E6 The average gamma energy per disintegration

=

5 Yhe average beta energy per disintegration

=

3 (2)

The release rate limit of all radiciodines and radioactive materials in particulate form with half lives greater than eight days, released from the site to the environs as part of the gaseous wastes, shall be.

1.0 X 105 6

Ops + 1.5 X 10 gpy 5 1 Where O Total release rate from the main stack

=

p3 for both Units in Ci/sec (as elevated release)

L)

Total release rate from vents for both Units Oy

=

p in Ci/sec (ground releases) b.

(1)

The average release rate of noble gases from the site during any calendar quarter shall be:

3.0 Eg '

I Qig 12 E6 +

+Qy

,66 E6

+ 140 EB I1 i

1

+n (2)

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

6.1 E ]

+ Q v E

Qi3 24 56

+

B i

130 E 6+ 2 7 0 EB 51 1

+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 Ops + 1.9 X 107 gpy 3 1 (4)

The average release rate of all radio iodines and radioactive materials in particulate form from the site

(

v 23

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

7 L

2.6 X 106 Ops + 3.7 x 10 Opv $1

{d

- ( 5)-

The amount of Iodine - 131 released during any calendar s

quarter shall not exceed 2 Ci/ reactor.

1 I

(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 oojective levels listed in subsection 2.1 of the Ht1P-ETS and report these actions to the Commission within 30 days from the end of the quarter during which the releases occurred in accordance with section 5.7.2.

(1)

If the average release rate of noble gases during any calendar quarter is:

h60E6 + 540 EB Qn

,4 7 E 6 - + 12 Eg

+ Qiv I

>1 i

i+n (2)

If the average release rate f rom-the site of all radio iodines and radioactive materials in particulate form with half lives greater than eight days during any calendar quarter is:

O s.o x 106 ogs + 7.2 x.107 Ogv,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 2.1.3a above.

The operability of the automatic isolation valve shall be demonstrated quarterly.

e.

If the pos t-tr ea,tmen t 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

hours, 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.

O 24

h.

' (1)

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

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 i ts-associated alarm system shall be operable during _ reactor power

-operation.

If both of the hydrogen gas monitors or both of the associated alarm systems are inoperable, reactor operation may be continued for a period of time not to exceed 2 weeks, provided that either (a) grab samples are taken and analyzed for hydrogen concentration once every 4

hours, or (b) using a

temporary hydrogen gas analyzer installed in the offgas system line downstream of.the recombiner, hydrogen concentration r'eadings 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 ~ to return the hydrogen exceeded, action shall be initiated within 4

hours 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.

O

<3)

The inste11ed hydrosen_ monitorine svseems ehe11 heve daily sensor

checks, monthly functional checks, and quarterly calibrations.

The portable hydrogen gas analyzer shall be -calibrated immediately prior-to installation and shall be subj ect to daily sensor

checks, monthly functional

checks,

'and quarterly calibrations until removed from service.

i.

An unplanned or uncontrolled offsite release of radioactive materials in gaseous effluents in excess of 150 Ci'. of noble gas or 0.02 Ci.

of 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 those 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 4

period (Procedures are such that shorter collection times are used where applicable to Technical Specification requirements).

. O i

25 y

m--,

Each of these continuous samplers has a flow controller which maintains sample flow within about a 10 percent range over each seven day collection period.

The offgas vent (elevated release) and the reactor building vents have flow measurement devices

,,[")

which continuously record the flow rate of the gas released

~

(accuracy of these devices are within 10% of the actual flows as measured during preoperational testing).

The recombiner building vent flow on Unit One is conservatively assumed to be constant at 500 CFM.

In addition to the gaseous, particulate, and iodine release measurements tritium, gross alpha and gaseous isotopic measurements of each vent stream are conducted on a monthly schedule.

After each calendar quarter (13 weeks) a summary of waste gas release from the four vents is compiled and as such is designed to meet the requirements for preparation of the 6-month report as specified in Regulatory Guide 1.21.

Unit one and two releases were calculated together because the Tech. Specifications for the two reactors are identical in this respect.

The methods for compilation of the quarterly releases are as follows:

1.

FISSION AND ACTIVATION GAS The total curie release is determined from the continuously reading gaseous monitors in addition to the vent flow recorders.

Activity monitors 'and vent flow rate readings are read hourly and input into the computer.

From these readings a daily release is calculated.

The calibration factors for the monitors are determined from the monthly O

isotopics when sufficient activity allows or by injection C

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 disintigration (E3 &

E) alor)g with the coefficients,,in the, release limit B

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.

RADIOIODINE RELEASES Iodine releases are determined weekly for I-131, I-133, and I-135, for each vent.

Where significant activity is not measured MDA releases are calculated.

Since calculated MDA's are below Technical Specification detectable concentrations then 0 (zero) release is used for the weeks with only MDA values.

Weekly releases are summarized with the aid of the counting room calculator - computer system and a

quarterly total is prepared from the weekly summaries.

The percent Technical Specification for I-131 on Table 2-1 is based on the quarterly Technical Specification limit.

26

On July 23, 1981, the sight glass on the flow gauge for the Main Stack sample panel was removed and cleaned.

When it was returned to service, the flow indicator was accidentally installed upside down.

This was corrected on December 21, g

(,/

1981, and the readings for the flow during that time period were corrected so this report reflects the corrected values.

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.

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.

On July 23, 1981, the sight glass on the flow gauge fro the Main Stack sample panel was removed and cleaned.

When it p>

was returned to service, the flow indicator was accidentally s

installed upside down.

This was corrected on December.21, 1981, and the readings for the flow during that time period were corrected so this report reflects the corrected values.

4.

GROSS ALPHA RELEASE The gross alpha release is computed each month by counting the particulate filters each week for gross alpha activity in a proportional counter.

The four or five weeks numbers are then recorded on a data sheet and the activity is summed at the end of the month.

5.

TRITIUM RELEASE Tritium samples are obtained monthly from each vent by passing the sample stream from a cold trap immersed in a liquid nitrogen or an acetone and ice mixture.

The grams of water vapor / cubic foot gas is measured upstream of the cold trap in order to alleviate the difficulties in determining water vapor collection efficiencies.

The tritium samples are analyzed by an independent laboratory.

From the uCi/ml tritium concentration, the grams water /ft3, and the vent flow rates, the monthly tritium release io calculated for each vent, and the quarterly summary can be generated from O,,

the monthly calculation forms.

m 27

l Hatch has attempted to maintain all calculated MDAs as low as possible by counting samples longer than what w o u l d.. b e normally practical.

For example at this time all weekly particulate and iodine counting times are 3000 sec and h-strontium separations are counted for 100 minutes.

Regulatory Guido 1.21 requires that estimated total error in analysis techniques be reported.

These estimates are required for the total fission and activation gas release, total I-131

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

"The total or maximum error associated with the effluent measurement will include the cumulative errors resulting 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 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 96.71% of this release was (N

from the main stack the MDA release values of the ground U

level release points were insignificant to the total release.

Monitor Error in Calibration 50%

Vent Flow Rate 10%

Non-Steady Release Rate 20%

80%

2.

I-131 Release was calculated from each weekly sample:

Statistical error 60%

Counting Equipment Calibration 10%

Vent Flow Rates 10%

Vent Sample Flow Rates 10%

Non-Steady Release Rates 10%

Losses From Charcoal Cartridge 10%

110%

3.

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

Statistical Error at MDA concentration 60%

Countng Equipment Calibration 10%

Q Vent Flow Rates 10%

28 l

l

Vent Sample Flow Rates 10%

Non-Steady Release Rates 10%

T06f 0

4.

Total Tritium Release was dominated by the reacter 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:

i Water Vapor in Sample Stream Determination 20%

Vent Flow Rates 10%

Counting Calibration and Statistics 10%

Non-Steady Release 50%

90%

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

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

3.

SOLID WASTE i

3.1 REGULATORY SPECIFICATIONS a.

Measurements shall be made to determine or estimate the p'

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

v b.

Solid wastes in storage and preparatory to shipment shall be monitored and packaged to assure compliance with the applicable portions of 10 CFR Part 20, 10 CFR ~ Pa r t 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.

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

O 29

TAELE 2-la

']

EFFLUEtlT AtID WASTE DISPOSAL SEMIAllHUAL REPORT 1981

~

GASEQUS EFFLUENTS-SUMMATION OF ALL RELEASES (UNIT I)

Unit Quarter Quarter Est Tot al E.

I.

H at c h fluc l e ar Pouer Plant UNIT 1 3

4 Error A.

Fiasion & ac t i v at i on gases 1.

Tot al release Ci 1.72E+04 5.84E+03 8.00Et01l 2.

Average release r at e for period uCi/sec 2.19E+03 7.27E+02 3.

of Technic al s pe c i f i c at i on 1 i ru t t 6.23E-01 3.28E-01 E.

Iodines 1.

Total iodine-131 Ci 6.65E-02 6.22E-02 1.10E+02l 2.

A"e r age release r at e for pericd uCi/sec 8.46E-03 7.74E-03 3.

of Technical s pec i f i c at i on 1imit 3.32C+00 3.11E+00 C.

Parti:ulates 1.

P art i c ul at e s with hal f-l i ves >8 d av s Ci 5.04E-03! 1.67E-031 1.00E+02l 2.

Average release rat e for period uCi/sec 6.41E-04 2.08E-04 3.

of Tech ical spe c i f i c at i on l i ra i t 9.30E-01 3.36E-01 4.

Gross al ph a rad i o ac t i v i t v Ci 1.47E-06 8.00E-07 D.

Tritium l'

1.

Tot al re 1 e are Ci 1.18E+00 1.07E-C1 9.00E+01l Ave r age release r at e for period uCi/sec 1.51E-01 1.33E-02 c.

3.

". of Technical s pe c 1 f i c at i on 1imit 1.41E+00 5.91E-01 G-30

TABLE 2-lb EFFLUEHT AND HASTE DISPOSAL SEMIAHHUAL REPORT 1981 v

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (UNIfII)

Unit Quarter Quarter Est lot al E.

I.

H at c h Huclear Power Plant UNIT 2 3

4 Error *:

A.

Fission & act ivation gases 1.

Tot al release Ci 6.18E+01 8.28E+01 8.00E+011 2.

Average release r at e for period uCi/sec 7.85E+00 1.03E+01 3.

of Technical s pe c i f i c at i on 1imit 2.93E-02 4.32E-03[

B.

Iodines 1.

Total iodine-131 Ci 5.20E-03 1.94E-03 1.10E+02l 2.

Average release r at e for period uCi/sec 6.61E-04 2.41E-04 3.

of Tec hni c al spec i fi c at i on 1 i nii t 2.60E-01 9.70E-02 C.

Part i c ul at e s 1.

P art i c ul at es with hal f-l i ve s >8 davs Ci 4.96E-04 1.36E-04 1.00E+02l 2.

Ft v e r ag e release rate for period uC1/sec 6.31E-05 1.69E-05 3.

o t' Te c hni c al spe c i fi c at i on 1imit 1.19E-01 3.12E-02 4.

Gross al ph a r adi o ac t t vi t v Ci 6.62E-07 2.82E-07 D.

Tr i t t urn O

1.

Tot al re l e as e Ci 2.77E+00 1.64E+00 9.00E+01l V

2.

Aver age release r at e for period uti/3ec 3.52E-01 2.04E-01 3

of Tec hni c al spec i f i c at i on 1 i tii i t

,92E+00 1.55E+00 31

_------------------J

TREl.E 2-Ic

/~

EFFLUENT AND HASTE DISPOSAL SEMIR4HUAL REPORT 1981.

(_T/

GASEQUS EFFLUENTS-SUMMRTION OF ALL RELEASES (SITE)

Unit Quarter Quarter Est Total E.

I. Hat ch Nuc l ear Power P' ant SITE 3

4 Error %

A.

Fission t ac t i vat i on gases 1.

Tot al release C1 1.73E+04 5.92E+03 8.00E+011 2.

Average release rate for period uCi/sec 2.19E+03 7.37E+02 3.

% of Technical spe c i f i c at i on limit 6.52E-01 3.32E-01 B.

Iodines-l 1.

Tot al iodine-131 Ci 7.17E-02 6.42E-02 1.10E+02[

2.

Average release rat e for period UCi/sec 9.12E-03 7.98E-03 3.

of Tec hni c al spec i fi c at i on limit 1.79E+00 1.60E+00 C.

P art i c u l at es f

1 Part i cul at es wi th half-lives >8 davs Ci 5.54E-03 1.81E-03 1.00E+02l-l 2.

Average release r at e for period uCi/sec 7.P4E-04 2.25E-04 3.

of Tec hni c al pec i fi c at i on limit 1.05E+00 3.67E-01 4.

Gross wiphs radioactivits Ci 2.13E-06 1.08E-06 D.

Tritium

! ()

1.

Tot al release C1 3.95E+00 1.74E+00 9.00E+01l 2.

Average rel e ase rat e for period uCi/sec 5.03E-01 2.17E-01 l

3.

of Te c hni c al specification limit 4.33E+00 2.14E+00 l

I l

l O

32

~

TABLE 2-2a E.

I.

Hatch Huclear Power Plant UNIT 1 EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1981 CASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH NODE Huclides Released Unit Quarter Quarter Quarter Quarter 3

4 3

4 1.

Fission gases Xe-133 Ci 1.24E+04 3.65E+03 0.00E+0C 0.00E+00 Xe-131H Ci 1.83E+03 5.81E+02 0.00E+00 0.00E+00 Kr-88 Ci 8.10E+02 3.62E+02 0.00E+00 0.00E+00 Xe-133H Ci 1.59E+02 4.45E+01 0.00E+00 0.00E+00 Xe-135 Ci 4.74E+01 1.48E+01 0.00E+00 0.00E+00 Kr-85H Ci 1.03E+03 3.57E+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 1.26E+02 6.44E+01 0.00E+00 0.00E+00 Xe-138 Ci 1.99E+02 1.56E+02 0.00E+00 0.00E+00 Xe-137 C1 1.82E+02 1.60E+02 0.00E+00 0.00E+00 H-13 Ci 1.33E+02 1.34E+02 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135H Ci 1.25E+02 5.00E+01 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 1.74E+0!

2.41E+02 0.00E+00 0.00E+00 Tot al for period Ci 1.71E+04 5.81E+03 0.00E+00 0.00E+00 2.

Iodines I-131 Ci 2.89E-02 4.18E-02 0.00E+00 0.00E+00 I-133 Ci 1.85E-02 8.18E-04 0.00E+00 0.00E+00 I-135 Ci 8.51E-03 6.63E-03 0.00E+00 0.00E+00 Tot al for period Ci 5.59E-02 4.93E-02 0.00E+00 0.00E+00 3.

" art i c ul at e s Sr-89 Ci 1.12E-04 1.38E-04 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 6.81E-08 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 2.05E-06 0.00E+00 0.00E+00 1-131 Ci 5.19E-04 4.20E-05 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 1.92E-08 0.00E+00 0.00E+00 Ea-140 Ci 2.20E-04 2.30E-05 0.00E+00 0.00E+00 Cs-134 Ci 3.98E-07 8.45E-06 0.00E+00 0.00E+00 Cs-137 Ci 3.24E-06 1.18E-05 0.00E+00 0.00E+00 Ce-144 Ci 4.40E-05 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 3.43E-07 0.00E+00 0.00E+00 Hb-95 Ci 0.00E+00 5.76E-06 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hn-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 Co-60 Ci 0.00E+00 1.42E-06 0.00E+00 0.00E+00

[~}

\\~/

La-140 C1 3.84E-04 3.80E-05 0.00E+00 0.00E+00 1_ " L ' 11 for period Ci 1.2SE-03 2.71E-04 0.00E+00 0.00E+n0 33

TABLE 2-2b' E.

I.

Hatch Nuc l ear Power Plant UNIT 2

/~N

(/

EFFLUENT AHD HASTE DISPOSAL SEMIAHHURL REPORT 1981 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTIHUOUS MODE EATCH MODE Huclides Released Unit Quarter Quarter Quarter-Quarter 3

4 3

4 1.

Fission gases Xe-133 Ci 2.85E+01 5.19E+01 0.00E+00 0.00E+00 Xe-131M Ci 4.20E+00 8.27E+00 0.00E+00 0.00E+00 Kr-88 C1 1.86E+00 5.16E+00 0.00E+00 0.00E+00 Xe-133M Ci 3.64E-01 6.33E-01 0.00E+00 0.00E+00 Xe-135 Ci 1.09E-01 2.11E-01 0.00E+00 0.00E+00 Kr-85M Ct 2.35E+00 5.09E+00 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-37 C1 2.89E-01 9.17E-01 0.00E+00 0.00E+00 Xe-138 Ci 4.56E-01 2.22E+00 0.00E+00 0.00E+00 Xe-137 Ci 4.175-01 2.28E+00 0.00E+00 0.00E+00 H-13 Ci 3.06E-01 1.91E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00Ev00 0.00E+00 Xe-135M C1 2.86E-01 7.12E-01 0.00E+00 0.00E+00 I-133 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ct 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 3.99E-02 3.43E+00 0.00E+00 0.00E+00

.)

Tot al for period Ci 3.92E+01 8.28E+01 0.00E+00i 0.00E+00 2.

Iodines Ci 6.62E-05 5.95E-04 0.00E+00 0.00E+00 I-131 1-133 Ci 4.23E-05 1.17E-05 0.00E+00 0.00E+00 1-135 Ci 1.95E-05 9.44E-05 0.00E+00 0.00E+00 Tot al for period Ci 1.2SE-04 7.02E-04 0.00E+00 0.00E+00 3.

Part i cul at es Sr-89 Ci 2.57E-07 1.96E-06 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 C1 0.00E+00 9.69E-10 0.00E+00 0.00E+00 Cr-51

.i 0.00E+00 2.93E-08 0.00E+00 0.00E+00 1-131 Ci 1.19E-06 5.98E-07 0.00E+00 0.00E+00 En-113 C1 0.00E+00 2.73E-10 0.00E+00 0.00E+00 Ba-!40 Ci 5.04E-07 3.28E-07 0.00E+00 0.00E+00 Cs-134 Ci 9.13E-10 1.20E-07 0.00E+00 0.00E+00 C:-137 Ci 7.43E-09 1.68E-07 0.00E+00 0.00E+00 Ce-144 Ci 1.01E-07 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 4.89E-09 0.00E+00 0.00E+00 Hb-95 C1 0.00E+00 8.20E-08 0.00E+00 0.00E+00 4

1 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

(')

Co-60 Ci 0.00E+00 2.02E-08 0.00E+00 0*.00E+00 La-140 Ci 8.80E-07 5.42E-07 0.00E+00 0.00E+00 1'

i i T :t si (e n a r i.- d Ci 2.94E-06 3.85E-06 0.00E+00 0.00E+00 34

TAPLE 2-2c E.

It Hat ch Huc lear Power Pl ant SITE O~.

EFFLUEHT AND HASTE DISP 00RL SEMIANNUAL REPORT 1981 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTIHUOUS MODE BATCH MODE Huclides Rcleased Unit Quarter Qu art e r Quarter Quarter !

3 4

l 1.

Fission gases Xe-133 Ci 1.25E+04 3.70E+03 0.0JE+00 0.00E+00 Xe-131M Ci 1.84E+03 5.89E+02 0.03E+00 0.00F+00 Kr-89 Ci 8.12E+02 3.67E+02

0. 0 v $ +~0 0 0.00E+00 Xe-123M Ci 1.59E+02 4.51E+01 0.00E+00 0.00E+00 Xe-135 Ci 4.75E+01 1.50E+01 0.00E+00 0.00E+00 Kr-85M Ci 1.03E+03 3.63E+02 0.00E+00 0.00E+00 1-131 Ci 0.00E+00 0.00E+00 0 00E+00 0.00E+00 Kr-87 Ci 1.26E+02 6.53E+01 C.00E+00 0.00E+00

~~ Xe-138 Ci 1.99E+02 1.58E+02 0.00E+00 0.00E+00 Xe-137 Ci 1.83E+02 1.62E+02 0.00E+00 0.00E+00 H-13 C1 1.34E+02 1.36E+02 0.00E+00 0.00E+00 Kr-85 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ci 1.25E+02 5.07E+01 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 C1 1.74E+01 P.45E+02 0.00E+00 0.00E+00 0

Total for period C1 1.71E+04 5.89E+03 0.00E+00 0.00E+00 2.

Iodines I-131 Ci 2.90E-02 4.24E-02 0.00E+00 0.00E+00

"-~

I-133 Ci 1.85E-02 8.30E-04 0.00E+00 0.00E+00 I-135 Ci 8.53E-03 6.73E-03 0.00E+00 0.00E+00 Tot al for peiiod Ci 5.60E-02 5.bOE-02 0.00E+00 0.00E+00 3.

Part i c ul at es Sr-89 Ci 1.13E-04 1.40E-04 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 6.90E-08 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 2.08E-06 0.00E+00 0.00E+00 I-131 Ci 5.20E-04 4.26E-05 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 1.95E-08 0.00E+00 0.00E+00 Ba-140 Ci 2.20E-04 2.34E-05 0.00E+00 0.00E+00 CA-134 Ci 3.99E-07 8.57E-06 0.00E+00 0.00E+00 C5-137 Ci 3.25E-06 1.20E-05 0.00E+00 0.00E+00 Ce-144 Ci 4.41E-05 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ct 0.00E+00 3.4SE-07 0.00E+00 0.00E+00 Hb-95 Ci 0.00E+00 5.84E-06 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.0PE+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 O.

. o - 6 0 Ci 0.00E+00 1.44E-06 0.00E+00 0.00E+00 La-140 Ci 3.85E-04 3.86E-05 0.00E+00 0.00E+00 Tots) fer pertoe Ci 1.29E-0?

2.74E-04 0.00E+00 0.00E+00 35

TABLE 2-3a E.

I. Hatch Huc lear Power Pl ant UNIT 1 EFFLUENT AND WASTE DISPOSAL SENIAP4UAL REPORT 1981 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE

(}

COHTINUOUS MODE SATCH MODE Huc l i des Rel e ased Unit Quarter Quarter Quarter Quarter 3

4 3

4 1.

Fission gases Xe-133 Ci 2.51E+01 0.00E+00 0.00E+00 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4

/

Kr-88 C1 1.99E-01 0.00E+00 0.00E+00 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Me-135 C1 2.85E+01 7.01E+00 0.00E+00 0.00E+00 Kr-85M Ci 1.02E-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 Ci 3.12E-01 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 5.53E-01 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 7.84E-02 9.04E+00 0.00E+00 0.00E+00 Kr-85 Ci 2.38E-01

6. 5 7 E_-01 0.00E+00 0.00E+00 Xe-135M Ci 3.59E+01 9.84E+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 C.00E*00 0.00E+00 0.00E+00 I-1?S 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 Tot al for period Ci 9.10E+01 2.66E+61 0.00E+00 0.00E+00 OQ 2.

Iodines 1-131 Ci 3.6CE-02 2.02E-02 0.00E+00 0.00E+00 1-133 Ci 3.88E-02 1.53E-03 0.00E+00 0.0GE+00 I-135 Ci 1.31E-02 2.75E-04 0.00E+00 0.00E+00 Tot al for period Ci 8.7CE-02 2.20E-02 0.00E+00 0.00E+00 3.

P ar t i c u l at e s Sr-89 Ci 3.04E-05 3.00E-05 0.00E+00 0.00E+00 Sr-90 Ci 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 1.22E-04 5.55E-05 0.00E+00 0.00E+00 I-131 Ci 1.11_E-03 2.06E-04 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 3.70E-05 1.77E-05 0.00E+00 0.00E+00 Cs-134 Ci 9.94E-04 4.12E-04 0.00E+00 0.00E+00 Cs-137 Ct 1.31E-03 4.99E-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 1.01E-08 0.00E+00 0.00E+00 Hb-95 Ci 0.00E+00 3.23E-05 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 1.79E-05 0.00E+00 0.00E+00 Mn-54 Ci 9.42E-07 5.41E-06 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ct 5.26E-05 6.65E-05 0.00E+00 0.00E+00 La-140 Ci 1.10E-04 6.00E-05 0.00E+00 0.00E+00 O)

(_

Tot al for pertos Ci 3.76E-03 1.40E-0~

0.00E+00 0.00E+00 36 h

L v

Y $ i Nw sp,,

,p 9

-4.r;..,op, g

T ABLE 2-3b E.

I. H atch Huc l ear Pouer Pl ant UNIT 2

(

EFFLUENT AND HASTE DISPOSAL SEMIAHHUAL REPORT 1981 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTINUOUS MODE EATCH MODE Huclides Released Unit Quarter Quarter Qu ar t e r Quarter 3

4 3

4 1.

Fission gases Xe-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 2.77E+00 0.00E+00 0.00E+00 3.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E&OO 0.00E+00 Xe-135 Ci 1.66E+01 0.00E^00

0. 0 Gf. + 00 0.00E+00 Er-85M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Er-87 Ci 2.86E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 0.00C+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-13 Ci 0.00E+00 0.00E+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 3.25E-01 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 Ci O.00E+00 0.00E+00 0.00E+00 0.00E+00 1-135 Ci 0.00E+00 0.00E+00 0.00E+0t*

0.00Ct00 Ar-41 C) 0.00E+00 0.00E+00 0.00E+00 0.00E&OO_

g

' ~)

Tot al for period Ci 2.26E+01 0.00E+00 0.00E+00 0.00E+00 2.

Iodines 1-131 Ci 4.80E-03 1.32E-03 0.00E+00 0.00E+00 1-133 Ci 5.59E-03 1.93E-04 0.00E+00 0.00E+00 I-135 Ci 2.19E-03 8.44E-05 0.00E+00 0.00E+00 Tot al for period Ci 1.26E-02 1.60E-03 0.00E+00 0.00E+00 3.

P ar t i c u l at e s

_sr-89 Ci 1.13E-05 1.25E-05 0.00E+00 ~

0.0CE+00 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l

Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 2.79E-06 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 3.35E-04 2.42E-05 0.00E+00 0.90E+00 l

Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l

Ba-140 Ci 4.78E-05 2.69E-05 0.00E+00 0.00E+00 Cs-134 Ci 2.20E-06 5.46E-07 0.00E+00 0.00E+00 C5-137 Ci 1.72E-06 1.75E-06 0.00E+00 0.00E+00 l

Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l

Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hb-95 Ci 0.00E+00 1.01E-05 0.00E+00 0.00E+00 l

Co-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-34 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

\\/

Co-60 Ci 9.32E-07 4.88E-06 0.00E+00 0.00E+00 Li-140 Ci 9.17E-05 5.09E-05 0.00E+00 0.00E+00 peri l ___ _ _ ___

Ci 4.93E-04 1.32E-04 0. 0 :' E - 0 0

'. 00E + 0 t_

','s1

rr 37 l

T ABLE 2-3c E.

I& Hatch Huclear Power Plant SITE O

V

' EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1981 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTINUOUS NODE EATCH l10DC Huclides Released Unit Quarter Quarter Quarter.

Qu art e r 3

4 3

4 1.

Firsion gases Xe-133 Ci 2.51E+01 0.00E+00 0.00E+00 0.00E+00 Xe-131H Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 2.97E+00 0.00E+00 0.00E+00 0.00E+00 X'

133H Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 X -135 Ci 4.52E+01 7.01E+00 0.00E+00 0.00E+00 Kr-85H C1 1.02E-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 Ci 3.18E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 5.53E-01 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 7.84E-02 9.04E+00 0.00E+00 0.00E+00 Kr-85 Ci 2.38E-01 6.57E-01 0.00E+00 0.00E+00

(e-235H Ci 3.62E+01 9.84E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-82 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O

Total for period Ci 1.14E+02 2.66E+01 0.00E+00 0.00E+00 2.

Iodines

!~2T31 Ci 4.07E-02 2.15E-02 0.00E+00 0.00E+00 I-133 Ci 4.43E-02 1.72E-03 0.00E+00 0.00E+00 I-135 Ci 1.53E-02 3.59E-04 0.00E+00 0.00E+00 Tot al for period Ci 1.00E-01 2.36E-02 0.00E+00 0.00E+00 3.

Par t i c u l at es Sr-89 Ci 4.16E-05 4.2'6E-05 0.00E+00 0.00E+00 Sr-90 Ci 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 1.24E-04 5.55E-05 0.00E+00 0.00E+00 I-131 Ci 1.44E-03 2.30E-04 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 8.48E-05 4.45E-05 0.00E+00 0.00E+00 Cs-134 Ci 9.96E-04 4.13E-04 0.00E+00 0.00E+00 Cs-137 Ci 1.31E-03 5.01E-04 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 U.00E+00 0.00E+00 0.00E+00 2r-95 Ci 0.00E+00 1.01E-08 0.00E+00 0.00E+00 Hb-95 Ci 0.00E+00 4.24E-05 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 1.79E-05 0.00E+00 0.00E+00 Hn-54 Ci 9.42E-07 5.41E-06 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Os Co-60 Ci 5.36E-05 7.14E-05 0.00E+00 0.00E+00 L2-140 Ci 2.02E-04 1.11E-04 0.00E+00 0.00E+00

) ~ :. ' s i f:r J-riod.

Ci 4.25E-03 1.53E-03 0.00E+00i 0.00E+00 38

TABLE 3-la EFFLUT.r:T AND '.".'ASTE DISPOSAL SE.'.!! ANNUAL REPORT (Y EAH) 1981 COLID V!ASTE AND triH ADIATED FUEL SHIPT.1ENTS FOR UillT 1

A. 00L1D W AST I SHIPPED O!"FSITE FOR StJRI AL OR C!SPOS AL (flot irradiated fuet) t;nis M ? nth c st. To ct

1. Type of waste Perio<1 Error. %

2. Spent r: sir.s. :d::t sit.d;::. caperator d

l 90 E 7 tott m. e::-

Cl 1

16 E 3 1.00E O r-:'

p.51 E 2 l

b. Dry,m:.; ten::;: w::te, contannaste::

(c. 'P e t:-

Ci 5 27 E 1 e 1. 00E O F

r-/

E

c. lir:J.st:d cc:apanent centrol rvh. et:

l Ci E

E m-E

d. 0:l.:t (d:scr.be)

Ci E

E

2. Estirn-te ci r.::ict avc!ide ecmposi:icn (by type of w:gre)

IS0 TOPE l PERCEilT l

CURIES 1

a. Cs-137 28.38 329.06 Cs-134 23.18 268.78 Co-60 18.87 218.80 All others 29.57 342.89

b. Zn-65 22.46 11.82 Cs-137 16.78 8.83 Co-60 16.45 8.66 All others 44.31 23.34 c.

d.

3.

Solid W::tc D*spostion Muder of Shi::ments -

Mode o(Trans:>ct:stion D:: tin. tion 57 Tractor & Trailer Chem-Nuclear Systems, Inc.

hasicolobshington 6

Tractor & Trailer

Richland, tt innAott.Tcc ruct. SitiPMS:JTs (Dis,mitien)

Num!<r of S!dur~nts MoJ: of Tran: ocatinn Destimtion s

39

TABLE 3-lb EFI LUER 2T AfJO !ASTE DISI'OSAL SE!.il ANtJUAL REPORT (YEAR) 1981 SOLID V!ASTE ANO 1RR ADIATED FUEL Sli!Pt.1ENTS FOR UtllT 2

A. SOLID Y!ASTE SHIPPED OFFSITE FOR SURIAL OR DISPOS AL (t.'ot irradiated fuel)

" '*"th C Toct

!. Type of wnte Uni:

Periorf Err or.' *4 e

d C1 i

85 E2 t ra:r.s. !d::t sit.d.;:s, coperator 1

52 E2 1.00 E O Mt.yra. c::.

b. D y cc:..:::n:::: wate. cor.tsrmnate::

m' 2 51E2 l (4 8P.e!-

Ci S. P7 El i 1.00 E0

c. jared.st:d comp 3nents, control rf E

ttv3.etc.

Ci E

E in-E

d. 0:Ir:t (des:rne)

Ci E

E

2. Estim:tc of m:ict ot cUde composi:icn (by ty7c of w=ste)

ISOTOPE I PERCEilT 1

CURIES 1

a.

Zn-65 37.34 E6.67 Cr-51 17 17 an 79 Cs-137 9 19 19 19 All others 22.37 33.93 b.

Zn-65

??.46 11 R7 16.78 8.83 Cs-137

~

16.45 8.66 C0-60 O

All others 44.31 23.34 L

c.

d.

3.

SoUd Vinte Dispodtion

?!uder of Shi::ments -

Mode ofTnnspor: tion D-:tinnion

' hem-N gle g Systems, Inc.

~33 Tractor & Trailer ja570coto' 7

Tractor & Trailer Richland'bshington Ik IGRADit.TED FUCL SHIP.*4ENTS (Dis.v.ition) 1 umNr of Shior : its Mo!: of Tnr.ror stinn Dutitution

's 40

_

PM-82-142, Semiannual Rept,Plant Radioactive Effluent Releases, Jul-Dec 1981

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PM-82-142, Semiannual Rept,Plant Radioactive Effluent Releases, Jul-Dec 1981

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