ML19341C797

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Semiannual Rept,Plant Radioactive Effluent Releases,Jul-Dec 1980
ML19341C797
Person / Time
Site: Hatch  
Issue date: 02/26/1981
From:
GEORGIA POWER CO.
To:
Shared Package
ML19341C793 List:
References
NUDOCS 8103040199
Download: ML19341C797 (43)
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Text

.

GEORGIA POWER COMPANY PLANT E.

I.

HATCH UNITS NO. 1& 2 SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JULY 1, 1980 - DECEMBER 31, 1980 J

8303040 6%

PLANT E.

I.

HATCH SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES O

SECTIONI 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 EFFLUENT 23 2.1 REGULATORY LIMITS 23 2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 25 2.3 GASEOUS EFFLUENT RELEASE DATA 29 3

SOLID WASTE 29 3.1 REGULATORY SPECIFICATIONS 29 O

3.2 SOLID WASTE DhT'A 29 O

PLANT E.

I. HATCH i

SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES O.

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 ANALYSIS - UNIT II 12-15 1-4 LIQUID RADWASTE DISCHARGE PERMIT 16 1-Sa, b LIQUID RADWASTE DATA COMPILATION 17, 18 TABLE LIST OF TABLES PAGE 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 ALL RELEASES 30-32 2-2a-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-ELEVATED RELEASE 33-35 2-3a-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-GROUND LEVEL RELEASES 36-38 3-la, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 39, 40 0

PLANT RADIOACTIVE EFFLUENT RELEASES 1

LIQUID EFFLUENTS 1.1.

REGULATORY LIMITS I

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 m

system shall be maintained and shall be operated to C

process radioactive _Uguid wastes prior to their discharge when the projected cumulative release rate could exceed 1.25 Ci/ reactor / calendar

quarter, excluding tritium and dissolved gases.

7.

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

8.

If the cumulative release of radioactive materials a

liquid effluents, excluding tritium and disse

gases, exceeds 2.5 Ci/ reactor / calendar
quarter, 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 uncontrollei offsite release of radioactive materials in liquid effluents in excess of 0.5 Ci excluding dissolved gases shall be reported.

v 1

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 O

8 etch ere determined 8v e mixed nuc11de aPC ce1cu1eeton verformed 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 Sr-90, have MPC values less than 9 X 10

-6 uCi/ml.

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

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

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

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

The maximum activity of gamma and beta emitting nuclides with MPC O

va1ues 9teater then 9

x 10.

-6 uCi/m1, exceve for the 29 nuclides noted above, is determined by gross gamma and gross beta measurements.

Measurement sensitivity limits of approximately 2 cpm /ml allow a

null measurement to show that the sum (Ci/MPCI),

is less than 0.1 for gamma and beta nuclides not measured directly.

The sum of the ratios, T.

(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 l

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:

O 2

l

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 O

ta ene saviroameate1 reca seece.

rnis sum is for each 8 etch 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 quarter.

B.

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

Average diluted concentration divided by the MPC limit, 3 X 10

-3 uCi/ml, is converted to percent to give the percent of applicable limit.

C.

Dissolved a:.J 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 1.'ves greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; Xe-135, Xe-133m, Xe-133, and Kr-85.

Iodine radionuclides in any form are also determined during the isotopic analysis for each

batch, therefore a

separate analysis for possible gaseous forms is not performed because it would not provide O

aaditione1 information.

A conservative release limit, the maximum sensitivity limit of 4

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

O 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:

O 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 Bate _h__

Ge(Li) spectrometry with on-line computer O

4

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.

O 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.

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

Although the computer could printout Q

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.

l l

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

analysis results on the computer disc file.

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

i o 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 computer data reduction using the Liquid Radwaste Library which O

tac "aes seees-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 1.85 E-2 curies for the third quarter and 2.32 E-2 curies for the forth quarter.

These values were approximately 1/800 for Unit 1 and 1/1658 for Unit 2 for the third quarter and 1/1709 for Unit 1 and 1/578 for Unit 2 for the fourth quarter of the allowed 10 curies per quarter per reactor.

2.

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

During this report period 22% of the liquid radwaste reaching the sample tanks was discharged; 78% was recycled back into both of the reactor water systems.

3.

A complete isotopic scan, gross beta, and gross gamma counts and computer analysis were performed prior to the release of each of the 610 discharge batches for both Units.

l.4 LIQUID EFFLUENT RELEASE DATA Regulatory Guide 1.21 Tables 2A and 2B are found in this report O

es re81e 1-te-8 eaa 1-2e, b.

Dete is gresented on e querter1y basis as per Regulatory Guide l'.2F.

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

Number of batch releases:

610 Total time period for releases:

78,054 minutes Maximum time period for a batch release:

197 minutes Average time period for batch release:

130 minutes Minimum time period for a batch release:

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

3951 CFS O

6

FIGURE l-1 METHODS OF MEETING, TABLE II, COLUMN 2 MPC LIMITS

()

MPC RANGE GAMMA-RAY BETA ALPHA (U Ci/ml)

EMITT2RS EMITTERS EMITTERS i

I-131,I-132, I-133 Sr-89, Sr-90 I-135, Cc-134 (Separation &

Gas Flow

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

Spectroscopy) l ALL (Gas Flow

Counting,

. Sensitivity l0.01 CPM /ml) t Ba-La-140, Na-24,Cu-64 Tritium CO-60, Fe-59, Zn-65 l

19 X 10-6 Ag-110m, Mn-54, C0-58 (Distillation &

Liquid Scintil-lation Counting)

Zr-Nb-95, Cs-Ba-137 As-76, F-18, Cr-51 All Others Np-239, Ce-141 Mo-Tc-99, Co-Pr-144 (Gas Flow Count-(Ge(Li) Gamma-Ray ing Sensitivity Spectroscopy)

~ 2 CPM /ml O

All others l

(Gross Gamma-Well l

, Counter; Sensitivity l ~ 5 CPM /ml)

I i

n v

7

i+0CELURE: HHP-Tio!

REVISIGH: 7 DATA SHEET U 1

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<1.93E-05 Cc -: 41 145.40

<1.002E-07

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<1.12E-03 Up-209 277.90

<2.426E-07 1E-04

<2.44E-03 Cr-51 90.t0 03.16CE-07 2E-03

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l I-131 164.41 2.700C-07 3 i *T1"E- 00 SE-07 9.00E-01 1

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<0.699E-OS 1E-OC

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<3.22E-04 I-t52 772.69

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FIGURE l-2 (CONT)

D A

d DI S? OL'!ED C AS.FS a

w n

'c - 13 3 60.11 1.555E-05 3.569E-0.
  • E-05 3.S?E-01 l'.r - C:?

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<1.42E-03 Xc - 13 3:a 233.10

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<1.180E-11 4E-05

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lle l l Crystal 4022 2034 e

20.0 2

4.97E+01 1.95E+00 Proportional 211 137 10.0 2

1.20C+00 9.97E-01 i

ESTlHATED llA3TE TAHK VOLIJttE:- 10500.00

gallons, ESTIt:aTED ACTIVITY THIS EATCH EXCLUDIliG GASES:

2.37E-02 Curie:

( 2.37E+04 Microcuries)

EXCLUDING H-3 AND CASES: 1.06E-04 Curies

( 1.06E+02 fli c r o c ur i e s )

THE ACT1YITY OF THIO EATCH (EMCLUDING H-3 AND GASES) IS 105.63 UCURIES THE HHMI 10!1 YOU HANT TO RELEASE IS 100 uCi THEREFORE YOU llEED YOUR SUPERVISOR TO Ol' THIS f: ELE ASE iliE GAi ACTIVITY OF THIS DATCH IS 1116.39 uCURIES THE HAMINUM YOU 1!A!!T TO FELENSE IS 1000 uCI !

7s

( ) THEFEF0fE YOU NEED YOUP S U F ER'/ I S O R TO 01: UHS PELEASE v

L i qu i d P sdo s 2 t.- Pe 1. rs.: Surai sr o 1 )!k a2. conc., cxcluding H-3 and dizzolved g 2.

(uCi/ul): 2.50E-06 +- 4.90E-0G lle a s. conc.,

including H-3, excluding gasez

" 01E-Oi 4. 0 5 E - ~. :

+-

2 ) C a l c u l.'.i d LLD concentration, excluding di.2olued g as e s

( uc i /rn i ) : O.72E-06 3)C alcol at c d HPC rat i.. < C/IIPC of rae a2., i nc l ud i og g az.s 2 > :

1. T': E + 0 0 4 ) M i n i rsura d i l u t i on f l o s.>

r at.. (g p ra ) :

10000 o > t t a x i tau ra tant di: charge riou r at e ( g p ra ) : 12625 G)Speeificd t :.nl: Olow r.t..

(gpo): OO

7) Pad.

Sta raonitor trip :etting: 725 A

=

m.TTE-05. u C 1 ra l D

150, Monitor DC CPS

=

C 7050'.0.00,ik ni t or C P': p:r uti n1 F

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othcr' nuclidc: and qasca but. c l u d e.i ;

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FIGUREl-2(CONT) oo ESTIMATED DOSES THi; T ATE % f!EEll I s o t o p.-

U.Lody Done Liver Thyroid Kidnc-y Lung GI-LLI

- lN-103 0.00E+00 0.00E+00 0.00E+00 0.00L200 0.00E+00 0.00E+00 0.00E+00 i

Ce-144 0.AAE+00 0.00E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 T c - 99 tn 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 0.OnE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mr-0E 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 Pa-13?u 0.00E+00 0.00E+00 0.00E+00 0.OnE+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-039 0.00E+00 0.00E+00 0.00Et00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mr-00u 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 0.00:400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i

i I-131' 3.55E-07 1.09E-07 2.'71E-07 8.07E-05 4.65E-07 0.00E+00 7.14E-03 Ur-ST 0.00E+00 0.00E+00- 0.00E+00 0.00E*00 0.00E+00 0.00E+00 0.00E+00 Xc-138 0.00E+00 0.00E+00 0.00E700 0.00E*00 0.00E+00 0.00E+00 0.00E+00 En-59a 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0nE+00; H-107 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00j l

F-19 0.00E+00 0.00E+00 0.00E+00 0.00i+00 0.OVE+00 0.00E+00 0.00E+00!

I-13?

0.00E+00 0.00E400 0.00Er00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Un-140 0.00E+00 0.00E+00 0.00E400 0.07E+00 0.00E+00 0.00E+00 0.:0E+00 0;-TG O.00E+00 0.00E+00 0.0n2400 0.03E+00 0.00C+00 0.00E+00 0.00E+00 C -134 0.00E+00 0.00E,00 0.00E-00 0.OnE+00 0.C3E+00 0.00E+00 0.00E+00 C;-137 0.00E+00 0.00E+00 0.00E+00

0. ore &OO 0.00E+00 0.00E+00 0.00E+00 flo-99 0.*0E+00 0.00E+00
0. 0 0 ~:+ 0 0 0.00 >00 0.00E+00 0.00E+00 0.u0E+00 4

E r-G U.OuE+00 n.00E+00 0.60900 0.Di +00 0.00T+00 0.00E+00 0.OUE+00 2r-95 0.00E+00 h.00E+00 0.00E+00 0.0 c+00 0.OnF+00 0.00E+00 0.n0E+00 lib-95 0.00Et00 0.00E400 0.00C+00 0.02T+00 0.00E+00 0.0?E+00 0.00E+00 I-1?2 0.00E+00 0.00E+00 0.00'+00 0.00d+00 0.00E+00 0.00E600 0.00E+00 Cc-53 0.uGE+00 0.00E+00 0.00E+00 0.C 4.600 0.'?E+00 0.00E+00 0.OOE+00 Mn-54 0.00E+00 0.00E+00 0.00E+00 0.00C+00 0.00E+00 0.00E+00 0.00E+00 0g-110a 0.00E+00 0.00E+00 0.00L>00 0.~0E+00

0. T '; E + 0 0 0.00E+00 0.00E+00

~.

2n-i5 0.00E+00 0.00E+00 0.00 +00 0 6'I +00.0.00E+00 0.00E+00 0.0uE+00 E

1-135 0.00E+00 0.CCE400 0.00E+00 0.002400 0.ClE+00 0.00E+00 0.0uE+00 Fe-59 0.03E+00 0.00E+00 0.00E+00 0.0 C+00 0.09E+00 0.03E+00 0.00E+00 i

Co-60

5. DOE-07 0.00E+00 1.7?E-07 0.00E400 0.COE400 0.00E+00 3.20E-06 Cu-G4 0.00E+00 0.00E+00 0.00E+00 0.00C+00 0.C7E+00 0.00E+00 0.00E+00; Hn-04 0.0DE+00 0.00E+00 0.00E!O3 0.03d+00 0..?E+00 0.00C+00 0.00E+00' La-140 0.00E+00 0.00L+00 0.00E+00 0.t/EF00 0.0 E+00 0.00E+00 0.00E+00 4

I!n-56 0.00E+00 0.00E+00

0. 00E- 00 0.00C+00 0.COE+00 0.n0E400 0.00E+00 Er-5y 0.00E+00 0.00E+00 0.00F^0^

^

_C+00 0.00E+00 0.00E+00 0.00E+00 cr - bn 0.nnE&OO

0. 00E-* 00 0.00d400 0.0 000 0.01E+00 0.0uE+00 0.00C+00 H-3 2.335-07

. 00Ein0

2. 3:!C -07 2.??E-07 2.:.%E-07 2.01E-07 2.33E-07 Fe-55 2.27E-08 1.41E-07 9.7CE-00 0.0 2+00
0. r 0E F00 5.*:E-03 5.50E-00 P-3C 1.5?E-04 2.92E-Oi 2.442-04 0.'.E+00 0.G3E+00 0. '_ _3 C + 0 0 4.41E-04 lctal 1.53E-04 3.92E-02 2.45E-04 3.,nE-05 6..' O C - 0 7
2. TOE-07 4.45E-04 10 1

)

==

FIGURE l-2 (CONT)

D " "'l0 *D'9~}$'

(includes estituate for this bit 'd o o N o a &.%

Cu.aul at i ve dos e t hi s YE AR Ilhole body 3.59E-02 mrem Percent of Tech Spec Limit:

1.20E+00 Bone 1.50E-01 raren Percent of Tech Spec Limit:

1.5CE+00 O

Liver

5. 01 E-02 rarem Percent of Tech Spec Limit:

5.01E-01 v

Thyroid

8. 61E-02 rarem Percent of Tech Spec L i ra i t :

0.61E-01 Kidney 1.45E-02 rarem Percent of Tech Spec L i ra i t :

1.45E-01 i

Luno

4. 57E-03 rarem Percent of Tech Spec Litait:

4.57E-02 GI-LLI 1.93E-02 mrem Percent of Tech Spec Limit:

1.93E-01 Cunulative dose this OUARTER (includes es t i ra nt e for this batch):

}

ilhole body 5.54E-03 rrem Percent of Tech Spec L i ra i t :

3.69E-01 Pone

9. 06E-02 rarem Percent of Tech Spec Limit:

1.97E+00 Liver

8. 4 SE-0 3 rar c m Percent of Tech Spec Lirait:

1.70E-01 Thyroid

6. 25E-03 rare m Percent of Tech Spec L i ra f t :

1.25E-01 Kidney 8.38E-04 mrem Percent of Tech Spec L i ra f t :

1.6SE-02 Lung 2.70E-04 ra re m Percent of Tech Spec L i ra i t :

5.40E-03 GI-LLI 1.14E- 02 rarcra Percent of Tech Spec L i ta i t :

2.29E-01 Proje c t ed curaul at ive dose this OUARTER (inc l ude s est i tuat e for this batch):

ilhole body

1. 4 7E-02 rare rn I:one 2.62E-01 rare rn Liver
2. 25E-02 rare ra Thyroid
1. 66E-02 rarem Kidney
2. 23E-03 rarera Lung 7.17E-04 mrem GI-LLI 3.04E-02 mrera Curuul at i ve ruc htured activity this YEAR (includes e s t i ra n t c for this batch):

\\

7.746E-02 Curies, exc luding H-3 and di zzolved gase s l

BATCH 4 499 DATA SUCCESSFULLY STORED l

SPECTRUrl STORED AS: LRt11 l

l I

i 11

FIGURE l-3 Po0CEDURE: HHP-7601 REVISION: 7 DATA SHEET 8

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

,+,+...+

++.4,.,,.+

+,e,,,++,+++

E.

I.

Hat ch liuc lear F 1 hnt Liquid Raduett* Analysis

,.++++,.s r++.r.,.r..*++,..a.....+.

  • ......++.

Reactor 4 2 Datchn 690 T s.d : ;lS T L2 Recirc time: 40 tainutes mm n

C :.orie nt : IIRIllT Alti CST D

D 9

Run dat e: 12/20/00 0631 Count $t ar t d at e : 1Y/M 0

4

~

Ssapic volune: 100 0. 00 ri.1 Clock time: 3000 secs Georaetry code: 1LHL-0 Live time: 3000 secs Detec'or# 1 11 CAW 1 Li t.r ary: LRULE2 Operator: CE Enirgp(1.<V)=.10 + 1.000*Ch4 + 0.000E+00*Chna2 + 0.000E+00*Ch#^3 : 12/20/80 0012 i

1/[1.702E-01. E^<-2.3716E+00) + 527.964

  • E^<9.7580E-01)] : 12/19/80 0000 '

E f t'

=

where E = Energy i n 114 V.

a ISOTOPE EHERGY CCHCENTRATIGH ERROR MPC C/11PC

< l: e V >

(uCi/ml)

(uCi/ul)

( u C 1/ta l )

==....======......=.n..........u..........,......................................

Ce-144 13?.50

<2.005E-07 1E-05

<2.89E-02 Tc-9?o 140.50

<3.404E-00 3E-03

<1.13E-05 Cc-141 145.40

<6.655E-08 9E-05

<7.39E-04 Hp-23?

277.90 (2.531E-07 1E-04

<2.53E-03 Cr-51 320.10

<2.870E-07 2E-03

<1.44E-04 I-131 364.50

<4.163E-03 3E-07

<1.39E-01 2n-69.a 438.70

<2.943E-03 GE-05

<4.90E-04

!!-107 479.50

<1.207E-07 GE-05

<2.01E-03 F-13 511.00

<2.390E-02 5E-04

<4.75E-OS 1-133 529.50

<2.969E-08 IE-06

<2.97E-02 D3-140 537.40

<1.223E-07 2E-05

<6.11E-03 Az-76 559.30

<7.059E-03 2E-05

<3.5?E-03 CI-134 604.70

<3.976E-0?

9E-06

<4.42E-03 C;-137 661.64

<4.916E-00 2E-05

<2.46E-03 I13-99 739.70

<2.767E-07 4E-05

<6.92E-03 2r-97 743.50

<3.290E-OS 2E-05 (1.65E-03 2r-95 756.90

<T.050E-00 6E-05

<1.1SE-03 H ti - 9 5 765.30

<3.907E-08 1E-04

<3.99E-04 I-132 772.60

<2.831E-08 SE-06

<3.54E-03 Co-58 810.60

<3.G50E-05 9E-05

<4.23E-04 I1n-54 S34.80

<4.406E-08 1E-04

< 4. 41 E -04 89-110ta 884.70

<4.241E-03 3E-05

<1.41E-03 2n-65 1115.40

<9.430E-05 1E-04

<9.43E-04 I-135 1260.50

<5.973E-03 4E-06

<1.47E-02 F(-59 1291.60

<6.251E-00 GE-05

<1.04E-03 Co-60 1332.90 1.185E-07 3.520E-03 3E-05 3.95E-03 Cu-64 1345.90

<5.407E-06 2E-04

<2.74E-02

!! a-2 4 1365.55

<2.714E-05 3E-05 (9.05E-04 La-140 1596.60

<3.085E-00 2E-05

<1.54E-03 11n - 51 1911.00

< 7. 532 E-e.i 1E-04

<7.53E-04 Sr-t?

<rETA)

<3.650E-02 3E-06

<1.22E-0?

(

l Sc-90 (DETA) 1.620E-Ot 7.830E-09 3E-07 5.40E-02 H-2 (rETAS 4.?90E-04 4.400E-05 3E-03 1.46E-01 F.-55 (LETA)

<1.000E-06 SE-04

< 1. 2 5 E -- 0 3 l

P-3J

( EC >

<1.000E-07 TE-05

<5.00E-03 lie a ur t f t ot 31 r 4.391E-04 4.400E-05 2.04E-01 LL1

  • c: al.

<?.002E-06

<3.0EE-01 Tot 212 4.401E-04 5.06E-01

o f

~kh l

U Dies 0LVEr. CASES FIGURE l-3 (CONT) oc Me-133

$0.99

<1.144E-07 4E-05

<2.06E-03 I:r -S C 196.10 (5.155E-08 4E-05

< 1. 29E X c - 133ra 233.16

<3.20SE-07 4E-05

<C.02E-03 Me-105 249.66 2.C36E-07 2.057E-OS 4E-05 7.09E-03 Kr-05:4 305.00

<1.707E-07 4E-05

<4.27E-03 Kr-07 402.70

<2.573E-08 4E-05

<6.43E-04 Xe-13 434.50 (1.539E-09 4E-05

<3.85E-05 lie uvred gli t o t al t, 2.336E-07 2.857t!-00 7.09E-00 LLD qu tota 12 (6.84eE-07

<1.71E-02 Tot al gas 9.633E-07 2.42E-02 s

e GROSS ACTIVITY Counter Gross I:ae k gr ound T t u.e Vd1 lie t Error Coum s Counti (tit n >

rn )

Ac t i v i t y < c pn./ra l )

1 S i gra s lic 11 Crys t al 2123 1831 20.0 2

6.05E+00 1.5sE+00 Pect. ort i o r. s 1 200 211 10.0 2

<3.34E+00 EST!!!ATED llGSTE TANK YOLUME= 963?.00 gallona 1

EST !!!6TED ACT 1YlT'e THIS I: ATCH E; CLUDIllG GAiES:

1.60E-02 Curies

( 1.60E+04 Microcurles)

E!;CLO!tIllG H-3 AND GA5E 3: 4.91E-06 Curie 2

( 4.91E+00 lli e roc ur i e : >

I L i qui d P,dn u t e Re le we S u n r<, w r o 1 )fle u. conc.. exclud.ng H-3 and dissolved g ases ( rC i /r.1 ) : 1.35E-07 3.61E-08

+-

lie t2.

conc.. includtrig H-3, e xc l udi ng g ase s

4.3?E-04 +- 4.40E-05 2)C t.l c u l at e d LLD cencentration, e xc l udi rig di 2 s ol ve d g az e.s

( u C i /rii l ) : 9.00E-06

3) Calculated 11PC ratio (C/lIPC of riie as., i nc l ud i ng g as c 3 ): 2.11E-Ol 4 ) fli n i niu ra dilution flow r at 4 ( gg: ra ) :

10000

5) flax i ruuo t ank discharge flow r e t.: (gpro): 47703 6)Specified t ant.: flow rate ( gpra ) : 90 7 ) P 3 d u a r t.' roorii t or t r i p setting: 613 A ' 4.02E-07, u C i /ra l B = 550, llon i t or I:G CPS C = 28-350000.00.!!oni t or CPS pe r oCi/ul F=0,Conserv. F;ctor A i nc l ud.: : nie u ur e d

'z e l e c t e d ', 'ot he r' nuc1idet and guc2 but e clude2:

]

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

C ) E.; t i.. s t.i d c o n c. :. f r..o n s, nuclidc: st point of r e l e a s.; i uc i 'ra l ) : 3.917E-Oi

^

9)fkni tor n. ac i eu u r..

to inzure 10CFFTO l i ra i t ; sre not.: cceded: 6046 4

13

FIGURE l-3 (C0flT)

D o m ID m

D "D

c o b o b.S i

l ESTIMATED DOSES THI3 E6TCH, UREM l

l 1:st ep.e IJ.Eody tone Liver Tim ncJ d kidnev Luna C1-LLI

'2-130 0.03E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 A.

C4-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-994 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.OuE+00 0.00E+00 0.00E+00 0.00E+00 Kr-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-1339 0.00E+00 0.00E+00 0.00E+v0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Me-135 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hp-23?

0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-e5m 0.00E.00 0.00E.00 0.00E.00 0.00E+00 0.00E.00 0.00E.e0 0.00E+00 Cr-51 0.00E+00 0.00E+00 0.00E+00 0.0cE+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-67 0.00E+00 0.00E+00 0.00E+00 0.00Ev00 0.00E+00 0.00E+00 0.00E+00 X(-138 0.00E+00 0.00E+00 0.00C+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2 r.- 69 m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00' H-107 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 Es-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 A:-76 0.00Ev00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 0.00E+00 0.00E&OO 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

[

Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2r-??

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 0.00E400 0.00E+00 I

I-132 0.00F400 0.00C&00 0.00E+00 0.00E&00 0.00E+00 0.00E+00 0.00E+00 Co-!3 0.00E'00 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00Ev00 0.00E+00 Hr.-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Og-110m 0.00E+00 0.00E+0C C.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2n-65 0.00E+00 0.00E+00 0.00E+00. G.00E+00 0.00E+00 0.00E+00 0.00E+00 1-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 rc-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ec-00 3.62E-07 0.00C+00 1.04E-07 0.0HE+00 0.00E+00 0.00E+00 3.09E-06 Ev-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 LC 140 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00

]

Mn S6 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00EA00 0.00E+00' Sr-69 0.00E+00 0.00E+00 0.00E+00 0.00C+00 0.00E*00 0.00E+00 0.00E+00 i

Er-?O 4.16E-07 1.70E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.13E-05 11-3 1.53E-07 0.00E+00 1.5?E-07 1.50E-07 1.58E-07 1.50E-07 1.50E-07; Fc-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00j 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 9.56E-07 1.78E-06 3.22E-07 1.5EE-0?

1.50E-07 1.525-07 3.30E-06' 4

e 14

nnimrmv-O FIGURE l-3 (CONT)

Cur..ul at i or doze t hi t '(E AR ( t rec l ude: a z t i t.i tet e for thia bat ctO:

{

1:h o '. 4 body 2.17E-02 rrcro h rccnt of Tech spec Linett:

7.22C-01 E s r.c 4.84C-01 sa r e rr Pcreent of Tc:h Spec L i r.i i t :

4.S4E 00 l

Liver

3. 4 ' E -0 2 in r e. :n Percent of T(ch Spec L)oit:

3.4SE-01 Thvroid

6. ? O E -0 3 r<,r e r.,

Percent of Tveh spec Li rii t :

6.0CE-02 t

Midney 0.10E-03 rar e rt.

Percent of Tcch S p e c L i r'ii t :

2.10E-02 i

Lung 4.04E-04 rar e ri, Percent of Tcch Sp.sc Litsit:

4. 04 E-O ';:

GI-LLI 5.7~E-02 suren Per c e nt of Tech Spec Liuit:

5.73E-01 i

l

'Curi.u l at i ve dose this OUARTER (includez e s t i ra kt e t' o r thl3 batch):

l j

lihole tody

1. 01 E-02 rnr e r.r Percent of Tech Spe c L i ra i t :

1.21E+00 l

i Itone 4.2?E-01 r,ir e ia Percent of Tech ?pec Lirsit:

8.-16E+C0 l

Liver

2. e9E-02 ruren Perc e nt o t' Tech s pe c L i ra i t
  • 5.77E-01 Thyroid
3. 04E-0 3 rare r.

Percent of Tech Spec L i tu i t :

6.6TE-02 Kidney 1.10E-0 3 rnr e ra Percent of Tcch Spec Lis i t:

2.20E-0?

Lung 2.44E-04 tc.r e r>.

Pctcent of Tech ?pec Lir..it:

4.09E-03 1

j i

GI-LLI

4. 87E-02 rare ra Percent of Tech Opec Lirait:

9.74E-01 d

l Pr:ijsetsd c u r.iu l at i '.> e d o s e t hi s OUf4-TER (inc l ude s est i n,at e f or thir batch):

l llhole body

2. 06E-02 rarc ra i

Lone 4.80E-01 rar e ra 4

Livcr

3. 27E-02 rar er:i 4

.i Thyroid

3. 78E-03 rar e ra Vide.ey
1. 25E-03 rarera

{

Lung

2. 7 7 E- 0 4 rnr e r.,

GI-LLI

5. 52E-02 tur e ra Cut..ul at i ve nie ss ure d ac t ivi t y t hi s YEAR (includar c a-t i r,ti t e for thia bitch):

5.CCCE-02 Curic, exc l udi rig H-3 a.nd d 1isolw d g 1:c s 1:hT CH3 (*i G LfiTA SUCCESSFULLY STORED ST EC T T:Ull STORED AS: LRil2

  • ^ ' ~

t 6

I i

i I

l I

i h

I 15

=-

4

,q FIGURE l-4

. JJ 4.. L g4 P f. f. ' Y E. T. !fATCH l' ?.T C H h 0. '

~

!.T 0fj I n R A D :A.s T I: D I.3 C H A E G E t t:R t I T U:lJ T 0

.. TM To 2E RELEASED

~ N.m

  • F03 :CCESSITY OF DISGHAP.GE DATE 4WEcta.STARTTIME SAMPLL TIttE

- a cC I:: c. Dtarvier MI!:aTES LA E0Rtd ORY AN ALYSIS (1) HEASURED R ADIO UCLIDE CD:lCE!!T : ATIO:t

.h

.E tic 1/nt'

+

(2) CALCULATED LLD LIMIT C0!;CE!;TRATIONS uCL/al

~~

(3) C ALCULATED !!D RATIO: I (C1/!!PCi)

~ ~ ~ ~

(!! ) HI!!I!!Ulf DILUTIC:t FL0tt R ATE CPM F 7f TU G P:!

(5) !! A%. C ALCUL ATED TAME DI*jCIIARGE R ATE:T5 ES ~ N C.

i 4

(6) SPECIFIED TAMX DIScitARGE RATE: < (5)/2 COM (7) E ADW ASTE !!O!!ITOR TRIP SETTI!!G : ~~

CPS A = Go(L1)(1) uC1/c1 De I:0IT03 T'. C CPS i

C = H0!!ITOR CPS P = C0!!SERVATit t:

i PER Ce(Li) uCi/nl PACTOR HONITOR ALARt SETTOIitT [CE3)

(C X A X F)

+B+

3 / P' ~

~

=

..... -.... ~.

C0!!PLETL'a SY DATE C0!!POSITE LI.TER STORED (INITIALS)

/.P Pi:O V C D M

.......---a-.

(8) R ADU ASTE !!OMITOR !!AX. CPS TO 13E IIITI:I:7 10 CPR PO !.IF" rS :

CXAX (6)+(c)

~

TO (3T en;- -

np ~~

O PER ATT6?id I ID,T.

i (9) LIQUID RADUASTE MONITOR TRIP SET 17:

CPS

~~~ ~

(10) C0!!FIRMf:D DTLUTION P L C'I RATE (11) VALVE LINEUP CHECTED AS pen Ents-

~

~

O P':

~

g i

1AtM Dis. 1Nif0HAYch DIS, aATE p1L. To 7 A s.

317ER SL.

!!C: ITod DATE

  • i !!! E LEVEL -%

R D!:C.

GPM C f. L PT.

CPS l

i-48 i

~. -....

s,.---. 7 j I DATE C0"PLETEP TY MIN.

C f.L.

DUl: ATIUN TOTAL RELEASE t 6 10 MI" ?.FTER STAT.T O' AFTER T L t* S H I::G A 6 P.C R A T O.'I Y

( 1 :- ) T O T A L T A ::.. vo l.'J M E D I SC :t ?,9 C ED G AI.. X 4,765 n1

( 3 ')

TOTAL A':T I V I T Y Dire:i AM;O (1) X (12)

- - -"~ ~ - ~

~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~

- ~ ~ uCL

( l P 'i

1. I V F. E F L O '..
1. A 7 E ( F L 0 ". F3A2 2.:4-6) ~._-._'..__"'.'._'~.."__Crr,

....-. ~....-

.icc"ets. a aT DATE

. ' n o. ::,

f I

s 16

FIGURE l-Sa Liqued Raduas'.* D at a Cornp i l at 10n for Peg. Gutde 1.21 Feport E.

I.

Hat ch Huclear Pl ant UNIT 1 D

D D q'y mmo o

i e

n TN Total Rc t iv it y (Curies)

WD U

Quarter 3, 1960 Qu ar t e r 4,

1980 Lheches 335 thru 458 Eatches 459 t bru 565 H arie itsasured Error High LLD4 Tot a He ssure d Err or High LLDs Total Ce-144 4.16E-04 5.03E-05 0.00E+00 4.16E-04 9.72E-04 7.86E-05 0.00E+00 9.72E-04 Tc -99m 4.66E-05 2.54E-06

+

4.66E-05 1.69E-05 1.70E-06

+

1.6?E-05 C4-141 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-2?9 0.00E+00 0.00E+00

+

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

+

0.00E+00 Cr-51 6.63E-05 1.38E-05

+

6.63E-05 7.98E-05 1.39E-05 7.98E-05 1-131 6.02E-03 2.39E-05 0.00E+00 6.02E-03 2.44E-03 1.77E-05 0.00E+00 2.4,E-03 Zn-69ta 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

+

0.00E+00 U-187 0.00E+00 0.00E+00

+

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

+

0.00E+00 F-18 1.35E-05 2.33E-06

+

1.35E-05 3.30E-05 2.25E-06 3.30E-05 1-133 3.90E-04 7.98E-06

+

3.90E-04 3.38E-04 S.25E-06

+

3.38E-04 Ba-140 0.00E+00 0.00E+00

+

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

+

0. 00E +00 i As-76 0.00E+00 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 C2-1?4 1.68E-03 1.67E-05 0.00E+00 1.69E-03 5.89E-04 1.01E-05 0.00E+00 5.39E-04 C2-107 2.12E-03 1.93E-05 0.00E+00 2.12E-03 S.45E-04 1.22E-05 0.00E+00 S.45E-04 Mo-99 1.36E-05 3.83E-06 0.00E+00 1.36E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-97 0.00E+00 0.00E+00

+

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

+

2r-95 5.94E-05 4.50E-06 5.94E-05 1.51E-05 6.29E-02

+

1.51E-05 Hb-95 3.61E-05 3.53E-06 3.61E-05 6.99E-06 1.56E-06 6.99E-06 I-132 2.90E-07 1.10E-07 2.90E-07 0.00E+00 0.00E+00 0.00E+00

+

Co-58 2.12E-05 2.60E-06 0.00E+00 2.12E-05 4.20E-06 7.2?E-07 0.00E+00 4.20E-06 Mn-54 1.10E-05 1.60E-06 0.00E+00 1.10 E -(15 3.04E-06 1.10E-06 0.00E+00 3.04E-06 Ag-110ra 5.00E-06 2.26E-06

+

5.00E-06 0.00E+00 0.00E+00 0.00E+00 p 2n-65 4.54E-04 1.77E-05 0.00E+00 4.64E-04 9.90E-05 S.03E-06 0.00E+00 9.90E-05 d I-135 5.35E-06 1.75E-06

5. 3 5E-06.- 0. 0 0 E + 0 0 0. 0 0E + 0 0

+

0.00E+00 Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.59E-06 1.67E-06 0.00E+00 0.59E-06 Co-60 4.45E-04 1.10E-05 0.00E+00 4.45E-04 3.53E-04 1.09E-05 0.00E+00 3.5?E-04 Co-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

+

+

Ha-24 2.03E-04 0.00E+00 2.03E-04 5.22E-06 1.01E-06 5.22E-06 L a-140 1.61E-05 2.04E-06 1.61E-05 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

+

C2 -l h 7.76E-05 4.44E-06 7.76E-05 1.73E-06 7.63E-07 1.73E-06 Rb-83 1.63E-05 1.63E-06 1.63E-05 5.37E-06 7.49E-07

+

5.37E-06

+

Cs-135

?.72E-05 2.09E-06 3.72E-05 1.03E-05 1.52E-06

+

1.03E-05

+

C2-134n 4.36E-06 1.70E-06

+

4.36E-06 0.00E+00 0.00E+00 0.00E+00 Sr-89 1.97E-04 7.03E-05 0.00E+00 1.97E 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 1.35E-04 3.03E-05 0.00E+00 1.35E-04 3.17E-05 3.09E-06 0.00E+00 3.17E-05 Fe-55 0.00E+00 0.00E+00 7.62E-03 7.62E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F-22 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 1.25E-02 1.02E-04 7.62E-03 2.01E-02 5.85E-03 6.29E-00 0.00E+00 5.85E-03 W -1 3

4.20E-02 3.70E-05 0.00E+00 4.20E-02 4.47E-02 9.35E-05 0.00E+00 4.47E-02!

1:r -ei 5.43C-06 2.01E-06 0.00E+00 5.43E-06 3.36E-06 2.27E-06 0.00E+00 6.21E-04l-

..:6E-06 W - t ? I n.

1.25E-03 5.00E-05 0.00E+00 1.25E-02 6.21E-Oa 3.:!E-05 0.00E+00 Me -l M 1.84E-02 2.66E-05 0.00E+00 1.64E-02 3.35E-02 3.92E-05 0.00E+00 3.15E-02 U - M r4 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0e 0.00E+00 0.00E+00 0.00E+00 Le -27 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M -13c 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0:1 0.00E+00 0.00E+00 0.00E+00

1-131n 1.06E-03 1.26E-04 0.00E+00 1.0iE-03 :.92E-04 9.s1E-05 0.00E+00 3.92E-04 U A -ilt, 1.05E-06 9.61E-Oi 0.00E*00 1.05E-06 5.40E-07 5.19E-09 0.00E+00 5.40E-07 To els 6.2EE 02 1.66E-04 0.00E+00 6.28E-02 7.93E-02 1.46E-04 0.00E+00 7.93E-02 17

-n.

)

FIGURE l-Sb Liquid Padoaste Dat & C e rep t I at i cn t'or Reg. Guide 1.21 Peport E.

1. Hatch Huclear Pl ant UNIT 2 g@

3 '

D kN

,f d

Tot al Actiusty (Curtes) hN kdh g

c3 Qu ar t e r 3, 1930 Outeter 4,

19S0 Ditches 332 thru 464 Datche!

465 t hru 710 Hsm fle ss ured Errce High LLD2 Tet al Measured Error High L L D s.

Total Ce-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.17E-05 1.69E-05 0.00E+00 3.17E-05 6.59E-05' 4.52E-05 6.59E-05 2.59E-06

+

Tc-95m 4.52E-05 2.12E-06

+

C s. - 141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

+

0.00E+00 Np-239 0.00E+0C 0.00E+00 0.00E+C0 0.00E+00 0.00E+00 1.11E-03 Cr-51 1.15E-04 1.67E-05 1.1SE-04 1.11E-03 3.95E-05

+

1-131 2.37E-04 6.22E-06 0.00E+00 2.37E-04 5.45E-04 9.92E-06 0.00E+00 5.45E-04 F

+

0.00E+00 0.00E+00 0.00E+00 0.00E+00 2n-69m 0.00E+00 0.00E+00

+

1.17E-06 H-107 0.00E+00 0.00E+00

+

0.00E+00 1.17E-06 2.29E-07 2.0SE-04 F-18 1.19E-03 5.95E-06 1.19E-03 8.0SE-04 5.93E-06

+

3.?6E-05 I-133 4.0SE-04 5.59E-06

+

4.06E-04 3.36E-05 2.35E-06

+

Ia-140 0.00E+00 0.00E+00 0.~0E+00 0.00E+00 0.00E+00 0.00E*00 fu-76 S.06E-05 4.92E-06 8.06E-05 2.05E-05 2.59E-06 2.05E-05 C2-134 1.46E-05 2.16E-06 0.00E+00 1.46E-05 1.15E-04 5.61E-06 0.00E+00 1.1SE-04 C2-137 3.54E-05 2.99E-06 0.00E+00 3.54E-05 2.2?E-04 8.06E-06 0.00E+00 2.23E-04 110-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.19E-05 2.34E-05 0.00E+00 1.19E-05

+

0.00E+00 3.09E-06 0.00E+00 0.00E+00 2r-97 3.09E-06 8.82E-07

+

9.86E-06 2r-95 7.75E-07 1.83E-07 7.75E-07 9.36E-06 2.25E-06

+

7.57E-05 Nt-95 9.26E-06 1.30E-06

+

9.26E-06 7.57E-05 4.35E-06 0.00E+00 I-132 S.00E-06 9.36E-07 8.00E-06 0.00E+00 0.00E+00

+

Co-59 7.16E-04 i.00E-06 0.00E+00 2.16E-04 7.38E-04 1.04E-05 0.00E+00 7.3?E-04 fin-54 4.67E-05 3.18E-06 0.00E+00 4.57E-05 1.34E-04 5.0SE-06 0.00E+00 1.34E-04 0.00t+00 0.00E+00 0.00E+00 0.00E+00 r 3 Ag-110ra 0.00E+00 0.00E+00

+

(_/ 2n-65 6.41E-04 1.73E-05 0.00E+00 6.41E-CA 1.81E-03 2.84E-05 0.00E+00 1.81E-03 1.35E-04 1.82E-06 7.56E-07

+

1.82E-06 I-;35 1.35E-04 ?.14E-06

+

Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.37E-06 2.71E-06 0.00E+00 S.37E-06 Co-60 4.13E-04 1.03E-OS 0.00E+00 4.13E-04 1.02E-03 1.71E-05 0.00E+00 1.02E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-64 0.00E+00 0.00E+00

+

Ha-24 2.31E-03 1.46E-05

+

2.31E-03 2.90E-03 1.62E-05 2.90E-03

+

5.21E-06 La-140 0.00E+00 0.00E+00 0.00E+00 5.22E-06 1.32E-06 9

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

+

Hn-56 0.00E+00 0.00E+00

+

C3-135 3.62E-05 2.02E-06 3.62E-05 3.76E-05 1.42E-06

+

3.76E-05 1.37E-05 1.75E-05 1.03E-06

+

1. 7 5E-0 5 '

Rb-si 1.37E-05 1.62E-06 0.00E+00 Ha-22 2.07E-06 6.23E-07 2.07E-06 0.00E+00 0.00E+00

+

6.73E-06 Hi-65 3.50E-06 1.7?E-06 3.50E-06 6.73E-06 2.24E-06

+

1.48E-07 0.00E+00 1.48E-07 3.43E-08 Hb-97 0.00E+00 0.00E+00 Sr-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 3r-90 6.47E-05 3.1?E-05 0.00E+00 6.47E-05 1.46E-04 2.12E-05 0.00E+00 1.46E-04 Fe-55 0.00E+00 0.00E+00 5.71E-01 5.71E-03 7.40E-03 2.00E-0? 0.00E+00 7.40E-03 F-12 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tor st a 6.03E-03 4.62E-05 5.71E-03 1.17E-02 1.73E-02 2.00E-03 0.00E+00 1.73E-02 i

i Xe-133 4.65E-03

3. 07E-05 0. 00E +00 4. 65E-0 3 5.12E-0 ? 2. 21 E-04 0.00E+00 8.12E-03>

l tr-$0 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-113m 1.20E-05 2.41E-06 0.00E+00 1.20E-05 6.04E-05 9.51E-06 0.00E+00 6. 04 E-0 5 '

'e~155 1.38E-01 1.07E-05 0.00E+00 1.53E-03 2.51E-03 1.23E-05 0.00E+00 2.51E-0?

Fr-559 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00, Fr-67 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

(~}/

A-

'N-116 0.00E*00 0.00E+00 0.00E+00 0.00E 00 5.?!E-0E 2.42E-08 0.00E+00 5.31E-02 nc-135H 5.E2E-07 6.64E-Oi 0.00E+00 5.92E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00

[

Tot alz 6.54E-03 3.26E-05 0.00E+00 6.54E-03 1.07E-02 2.22E-04 0.00E+00 1.07E-02 18 Yi

TABLE l-la DA D

TD Wk E.

!. Hat ch Huc le ar Pl ant UN'T db-O EFFLUENT AHD WASTE DISPOSAL SErl! ANNUAL REPORT 1990 ba

[

LIOUID EFFLUENTS-SUrtt!ATIGH OF ALL RELEASES Unit Qu ar t er Quarter Est Tot al 3

4 Error A.

Fission t activktion products 1.

Tot al release (not including H3, gases, alpha)

Ci 1.25E-02 5.85E-03 3.96E+02 i

2.

Average di lut ed concent rat ion j

during period uCi/ml 1.1?E-08 6.55E-09

3. Percen' of anni t c abl e Itmte 1.92E+00 9.84E-01 E.

Trttium I

1.

Total r e l e.a s,

_Ci 3.06E+00 4.00E+00 4.14E+01l 2.

Average di lut e d concentrat ion during period u C i /ro l 2.76E-06 4.48E-06 3.

Fercent of applicable limit 4

9.20E-02 1.49E-01 C. Diazolved and entr ained g ase2 1.

Totsi release Ci 6.2GE-02 7.9?E-02 1.01E+02]

2.

Average di lut ed concent r at ion during period uCi/ml 5.66E-08 S.88E-08 3.

Fercent of appl i c abl e l i t., i t 1.41E-01 2.22E-01 D.

Gross al pha radi oac t ivi t y l

I.

Tot al releast l

C1 l 2. '3 7 E-06 l 4.17E-06) 1.20E+02l i

jE. V o l o r.. e of u ns t e (prior to dilutten'el liters l 5.06E+061 4.41E+06l 1.00E+0![

_lF.

Voluit ef diluttoo ustar ufed l ljters l 1.10E+09l S.8?E+08{ 1.60E+02]

O 19

TABLE l-lb om o

E.

I.

Hatch tiuclear Plant Ut1IT 2 O

O O

o[.

3 oc 1

EFFLUEt4T AtlD WA5TE DISPOSAL SEMIAtlilUAL REPORT 1980 (x,

V LIQUID EFFLUEt1TS-SUMMATIDt1 OF ALL RELEASES Unit Quarter Quarter Est Tot al 3

4 Error H.

Fission & ac t i vat i on produc t s 1.

Tot al release (not including H3, g as e s. sl ph a)

Ci 6.03E-03 1.73E-02 5.46E+0!

2.

A'se r age ciluted c onc e nt r at i on during period uCi/ml 6.13E-09 1.05E-08 3.

Percent of apolicable l i ra i t 1.58E-01 1.54E-01 E.

T r i t i u n.

i 1.

Total release Ci 2.10E+00 3.23E+001 4.07E+011 2.

Aver age di l ut ed c onc ent r at i on during period uCi'm1 2.13E-06 1.96E-06

?.

Percent o t' applicable limit 7.11E-02 6.53E-02 C.

Dissolved and e nt rai ne d g az e s 1.

Tot al releasc Ci 6.54E-03 1.07E-02 1.02E+02l 2.

Ascrage diluted c onc e nt r at i on c'u r i n g period oCi/ml 6.65E-09 6.49E-09 3.

Percent of app l i c ab l e l i ra i t 1.66E-02 1.6EE-02 r"~x D.

GroII al pha radi oac t i vi t y N.Y l

1.

Tot a! re l e as e l

Ci l 6.38E-071 6.06E-061 1.20E+02[

lE. Volume e f' u a a t. e (prior to d1lution)l 1itera i 4.00E+06! 8.32E+C6l 1.00E+01j lF. Volui.! of dilution unter used

! I!teri l 9.80E+08l 1.64E+09l 1.60E+02f (n'4

'w) 20

TABLE l-2a D ' 33

  • ID E.

I.

H at c h fluc l ear Pl ant UtlI T 1

' -d W K( '

EFFLUENT AllD WASTE DISPOSAL SEr11Allt4UAL REPORT 1930 i

/O

(,j LIQUID EFFLUEllTS CONTINUGUS HOLE EATCH t10DE iluc l i de s Pelensed Unit Quarter Quarter Quarter Qu ar t e r 3

4 3

4 C6-144 Ci 4.16E-04 9.72E-04 Tc-99ta Ci 4.66E-05 1.69E-05 Ce-141 Ci 0.00E+00 0.00E+00 No-239 Ci 0.00E+00-0.00E+00 Cr-51 Ci 6.63E-05 7.98E-05 i-131 Li 6.02E-03 2.44E-03 2n-69m Ci 0.00E+00 0.00E+00 W-187 Ci 0.00E+00 0.00E+00 F-16 Ci 1.35E-05 3.30E-05 1-133 Ci 3.90E-04 3.3SE-04 f:a-140 Ci 0.00E+00 0.00E+00 As-76 Ci 0.00E+00 0.00E+00 Cs-134 Ci 1.68E-03 5.89E-04 Cs-137 C1 2.12E-03 3.45E-04 Ho-99 Ci 1.56E-05 0.00E+00 Zr-97 Ci 0.00E+00 0.00E+00 Zr-95 Ci 5.94E-05 1.51E-05-~

Hb-95 Ci 3.61E-05 6.99E-06 I-132 Ci 2.90E-07 0.00E+00 Co-58 Ci 2.12E-05 4.20E-06 Hr-54 Ct 1.10E-05 3.04E-06 A a - 1 10 rc.

Ci 5.00E-06 0.00E+00 2n-65 Ci 4.64E-04 9.90E-05

()

I-135 Ci 5.35E-06 0.00E+00 Fe-59 Ci 0.00E+00 2.59E-06 Co-60 Ci 4.45E-04 3.53E-04 Cu-64 Ci 0.00E+00 0.00E+00 Ns-24 C1 2.03E-04 5.22E-06 La-140 Ci 1.61E-05 0.00E+00 Hn~56 Ci 0.00E+00 0.00E+00 CE-136 Ci 7.76E-05 1.73E-06 Pb-88 Ci 1.63E-05 5.37E-06 C3-138 Ci 3.72E-05 1.03E-05 C2-134f1 Ci 4.36E-06 0.00E+00 Sr-89 Ci 1.97E-04 0.00E+00 'l Sr-90 C1 1.35E-04 3.17E-05 l

Fa-55 Ci 0.00E+00 0.00E+00 P-32 Ci 0.00E+00 0.00E+00 1__

Tot al for period : abo"e ')

l Ci l

l l 1.25E-02] 5.G5E-03{

I I

X*-133 C1 4.20E-02 4.4TE-02 Er-69 Ci 5.43E-06 3.36E-06

': e - 13 3ru C1 1.25E-03 6.21E-04 i

Xe-135 Ci i

1.84E-01 3.35E-02~~

i t:r-65m Ci 0.00E+00 0.00E+0'O Fr-67 Ci 0.00E+00 0.00E+00 X4-138 Ci 0.00E+00 0.00E+00

()

X 4 - 131 rn Ci 1.06E-03 3.?2E-04 Xe-135m Ci 1.05E-06 5.40E-07 21 f

TABLE l-2b E.

I. Hatch fluc lear Pl ant Uti1T 2 EFFLUENT AtID HASTE DISPOSAL SEMIANNUAL REPORT 1980 i

D**

T)

'T LIQUID EFFLUENTS (Q

]..

cw w

4 Continuous MODE BATCH MODE tiuc l i des Pe l e as ed Unit Ouarter Qu ar t e r Qu ar t e r Qu art e r 3

4 3

4 Ce-14*

Ci 0.00E+00 3.1?E-05 T c - 9 9 tn C1 4.52E-05 6.59E-05 Ce-141 C1 0.00E+00 0.00E+00 14p-239 Ci 0.00E+00 0.00E+00 Cr-51 Ci 1.16E-04 1.11E-03 1-131 Ci 2.37E-04 5.45E-04 2n-69m Ci 0.00E+00 0.00E+00

^

U-197 Ci 0.00E+00 1.17E-06 F-18 C1 1.19E-03 8.08E-04 I-133 Ci 4.08E-04 3.36E-05 En-140 Ci 0.00E+00 0.00E+00 As-76 Ci 8.06E-05 2.05E-05 j

Cs-134 C1 1.46E-05 1.19E-04 Cs-137 Ci 3.54E-05 2.23E-04 t16-99 Ci

0. 0'tE +00 1.19E-05 Zr-97 Ci 3.0 E-06 0.00E+00 Zr-95 Ci 7.75E-07 9.86E-06 Hb-95 Ci 9.26E-06 7.57E-05 I-132 C1 8.00E-06 0.00E+00 Co-55 Ci 2.16E-04 7.38E-04 Mn-54 C1 4.57E-05 1.34E-04 A g - 1 10 r..

Ci 0.00E+00 0.00E+00 2n-65 Ci 6.41E-04 1.81E-03 I-135 Ci 1.35E-041 1.82E-06 gg

(

)

Fe-59 Ci 0.00E+00 9.37E-06 Co-60 C1 4.13E-04 1.02E-03 Cu-64 Ci 0.00E+00 0.00E+00 fta-24 C1 2.31E-03 2.90E-0?

Ls-140 Ci 0.00E+00 5.22E-06 fin-56 Ci 0.00E+00 0.00E+00 Cs-1?!

Ci 3.62E-05 3.76E-05 J

Rb-SS Ci 1.??E-05 1.75E-05 l

Ha-22 Ci 2.07E-06 0.00E+00 Ni-65 C1 3.50E-06 6.73E-06 I

Nb-97 Ci 0.00E+00 1.4?E-07 Sr-S9 Ci 0.00E+00 0.00E+00 i

Sr-90 C1 6.47E-05 1.46E-04 Fe-55 Ci 0.00E+00 7.40E-03 P-32 Ci O.00E+00 0.00E+00 l

Tot al for period (ato'e)

{

Ci l

l 6.03E-03l 1.73E-02l Ae-133 l

Ci 4.65E-031 8.12E-0?

i r-85 Ci U.00E+00 0.00E+00 9-135m Ci 1.20E-05 6.04E-i15

<e -135 Ci 1.89E-0?! 2.51E-02 I' r -:: S ia Ci 0.00F+00' O. 0 0 E + 0__0_

t r -:i ?

Ci 0.00E+00 0.00E+00 p)

Ne-1;i Ci 0.00E+00 5.31E-05 I

ss<

, :- 1 $tt Ci l

5.32E-07 0.00E+00 g

22 me

2 GASEOUS EFFLUENTS 2.1. REGULATORY LIMITS a.

(1)

The release rate limit of noble gases from the site O

ene11 'e E

Qin (1.9E6+1.0 B

+ Qiv 11 b

+ 44 E 51 6

B 1

+n where Os =

Total release rate f rom main stack for both Units in Ci/sec (elevated release)

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

=

i=

The individual nuclide n = total nuclides E6

= The average gamma energy per disintegration E

The average beta energy per disintegration

=

B (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 s =

Total release rate from the main stack p

for both Units in Ci/sec (as elevated S

relc e se)

.)

Total relea's'e~

Oy rate from vents for both Units

=

p in Ci/sec (ground releases) b.

(1)

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

Qs 12 56 + 3.0 Eg

+Qy 66 E6

+ 140 EB 11 I

i i

i

+n (2)

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

e T-Qs 24 E6 + 6.1 EBf+Ov

[130

._3 6+ 2 70 E__Bf f1 E

i i

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 Opv 5 1 (4)

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

23 l

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

2.6 x 106 7

Ops + 3.7 x 10 gpy,<1 m(j (5)

The amount 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 pr ogr ant of action to reduce the release rates to design objective levels listed in subsection 2.1 of the HNP-ETS and report these actions to the Commission within 30 days from the end of the quarter during which the releases occurred in accordance with section 5.7.2.

(1)

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

12 E ]

+ Q v h60 E'6 + 540 5 l > 1 Qs

,47 56 I

i

+

3 i

3 i+n (2)

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

O 5.0 x 106 ops + 7.2 x 102 agv >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 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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, 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 l

24

h.

(1)

Potentially explosive gas Inixtur es 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 Q,

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

hydrogen concentration by volume.

At least one continuous gas monitoring system and its associated alarm system shall be operable during reactor power operation.

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

hours, or (b) using a

temporary hydrogen gas analyzer installed in the offgas system line downstream of the recombiner, hydrogen concentration readings are taken and logged every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(2)

The hydrogen concentration in the offgas system downstream of the recombiners shall not exceed 4%

cencentration by volume.

If at any time during reactor power operation, it is determined that the hydrogen concentration limit is being exceeded, action shall be initiated within 4

hours to recurn 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the offgas system flow shall be stopped.

(3)

The installed hydr ogen _ moni toring systems 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

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 l

Waste gas release at Hatch.i s confined to four paths.

Each of these four paths is coratinuously 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).

i (3

v 25

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 O

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

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

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

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

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

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

1.

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

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

From these readings a daily release is calculated.

The calibration factors for the monitors are determined from the monthly isotopics when sufficient activity allows or by injection of a known amount of off-gas into the sample chambers.

The O

tote 1 c"rie reteeee is ca1ce1eted by ene comooter ror each of the individual nuclides released.

This number is multiplied by the average energy per disintigration (E y &

E) along 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 tne 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 1

and a

quarterly total is prepared from the weekly summaries.

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

O 26

. ~

3.

PARTICULATE RELEASES l

Particulate releases are determined weekly for each vent.

Where significant activity is not measured MDA release is i

calculated.

-Since calculated MDA's ~ are below Technical 1

~O srecification deteceas1e

.concentretions, then o

(zero) release 'i s 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 l

vont 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 monthly collection period.

Again the counting room calculator - computer is used to aid in the calculation 1

of.the Sr-89, 90 release.

Where significant strontium i

activity is not detected MDAs are calculated.

In order to eliminate the need'for a quarterly composite Sr-89 and Sr-90 activity is calculated for each monthly composite.

The i

percent of-Technical Specification was calculated using quarterly average equation.

4.

GROSS ALPHA RELEASE i

i

]

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 1

I are then record on a data sheet and the activity is summed i

at the'end of t Tonth.

O s-ra T ox netense i

Tritium samples me 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 l

water vapor / cubic foot gas is measured upstream of the cold trap in order to alleviate the difficulties in determining i

water vapor collection efficiencies.

The tritium samples are analyzed by an independent laboratory.

From the uCi/ml 4

tritium concentration, the grams water /ft3, and the vent j

flow rates, the monthly tritium release is calculated for each vent, and the quarterly summary can be generated from the monthly calculation forms.

i Hatch has attempted to maintain all calculated MDAs as low as possible by counting samples longer than what would be normally practical.

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

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

These estimates are required j

for the total fission.and activation gas release, total I-131 O

I f

27

1-i release, total particulates' with ; half-lives greater than 8-day.

7 release, and total tritium relence.

"The total or maximum error associated with the effluent measurement will include the cumulative errors resulting

, h from the total operation of sampling and measurement.

Because-it may be very difficult to assign error terms fcr 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 frore process monitor readings.

As 95.3% of this release was from the main stack the MDA release values of the ground level release points were insignificant to the total release.

Monitor Error in Calibration 50%

Vent Flow Rate 10%

Non-Steady Release Rate 20%

80%

j 2.

I-131 Release was calculated trom each weekly sample:

1 Statistical error 60%

O Countino E2uiement Ce11bree. ion 10%

Vent Flow Rates 10%

Vent Sample Flow Rates 10%

Non-Steady Release Rates 10%

Losses From Charcoal Cartridge 10%

110%

i 3.

Particulates with half-lives greater than 8 days release was dominated by the MDA calculations for I-131 and Ba-La-140 4

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%

j Vent Flow Rates 10%

Vent Sample Flow Rates 10%

l Non-Steady Release Rates 10%

100%

i 4.

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

)

of the off-gas vent and recombiner building vent tritium i

releases do not affect the error in the total tritium A

release:

%)

-28

Water Vapor in Sample Stream Determination 20%

Vent Flow Rates 10%

Counting Calibration and Statistics 10%

Non-Steady Release 50%

90%

3

)

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

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

3.

SOLID WASTQ 3.1 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 offsite.

b.

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

c.

Reports of the radioactive solid waste shipments, volumes, principal radionuclides, and total curie quantity shall be submitted in accordance with subsection S.6.1 of the HNP-ETS.

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

O l

l l

29 1

TABLE 2-la EFFLUEtlT At4D (JASTE DISPOSAL SEllI AtitlUAL REPORT 1980 GASEGUS EFFLUEtlTS-SUMMATI0li OF ALL RELEASES (UNIT I)

Unit Quarter Quarter Est Tota 1 E.

I. Hatch fluc l e ar Power Plant Uti1 T 1

  • 3 4

Error *:

A.

Fission t, ac t ivat i on g ases 1.

Tot al release Ci 1.17E+04' 1.60E+04 8.00E+011 2.

Ave r age re l e as e rate for period uC1/sec 1.49E+03 1.97E+03 3.

of Technical specification limit l 7.65E-01 1.06E+00 E.

Iodines 1.

Tot al iodine-131 Ci 1.70E-01 9.82E-021 1.10E+02l 2.

Ave r age release r at e for period UCi/sec 2.16E-02 1.21E-02l of Te c hn i c al spec i f i c at t on 1imit 8.50E+00 4.91E+001 C.

Par t i c ul at es t

1.

P art icul at e s wi t h h al f-l i ves >8 davs Ci 5.53E-03 1.31E-02' 1.00E+02l 2.

Average release rat e for period UCi/sec 7.03E-04 1.61E-03 3.

of Tec hni c al spe c i fi c at i on inmit 1.09E+00 2.69E+00 4.

Grom al pha radi oac t i o s to Ci 2.71E-06 2.94E-06 D.

Tritium 1.

Tot al re l e as e Ct 3.88E+00 1.27E+00 9.00E+01[

2.

Ave r age re l e ase r at e for period uCi/sec 4.94E-01 1.56E-01 3.

of Technicni spe c 10 i c at i on 11 ne i t 4.44E+00 1.54E+00 b

o 33

TABLE 2-lb EFFLUEllT AtID WiSTE DISPOSAL set 1IAtitlUAL REPORT 1980 GP2EGUS EFFLUEtiTS-SUllfl0T 1011 OF ALL RELEASES (UNIT 2)

Unit Qu art e r Quarter Est Tot al E.

I.

Hatch 14uc l e ar Pouer Pl ant UtlI T 2 3

4 Error R.

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

Total r e l e as e Ci 5.98E+01 8.63E+01 1.00E+01]

2.

Average re le ase rate f o r-period uCi/sec 7.60E+00 1.0TE+01 3.

% of Tec hni c al spectrication 1 t ra i t 2.34E-02 9.82E-02 B.

Iodines 1.

Tot al iodine-131 Ci 9.00E-03 1.06E-03 1.10E+02l 2.

Average release r at e for period uCi/sec 1.14E-03 1.31E-04 1

9.

of Te c hnic al spe c i f i c at i on l i ro i t 4.50E-01 5.32E-02 C.

P ar t i c u l at e s, 1.

P art i cul at eI uith h al f-l i oes >8 davs Ci 9.39E-04 l 2.04E-04 1.00E+021:

2.

Average release rate for period uCi/sec 1.19E-04 2.51E-05 3.

. of Tec hrit c al spec t (i c at i on 1 i ta i t 2.26E-01 4.73E-02 4.

Gross al ph a r Edi cac t t oi t v Ci 2.19E-06 1.42E-06 i

D.

T r i t i u rn -

i 1.

Total release

. _ __ C 1 2.09E+00 4.52E-01 9.00E+01l 2.

Average release rate for period uCi/sec 2.65E-01 5.56E-02 l

3.

of Technical s pe c i f i c at i on l i ra i t 2.24E+00 4. 6 2 E_- O 'L D

1 N

O D""dD At

=

n l

V I

l 31 l

TABLE 2-Ic EFFLUEt4T At1D WASTE DISPOSAL SEMIAfillVAL REPORT 1980 fl GASEOUS EFFLUEllTS-SUt1MATI0tl 0F ALL RELEASES (SITE) l l

O Unit Quarter Quarter Est Total E.

I. Har ch tioc le ar Power Plant SITE 3

4 Error ";

j A. Fission & ac t ivat ion gases l

Total r e l e ase C1 1.18E+04 1.61E+04 8.00E+011 2.

Auer;ge rel e ase rate for period uCi/sec 1.50E+03 1.98E+03 3.

% of Techniesi specification I f ra t t 7.89E-01 1.16E+00 B.

Iodines 1.

Total iodine-131 Ci 1.79E-01 9.93E-02 1.10E+02l 2.

Auersge release rate f o r-period _

uCi/sec 2.25E-02 1.22E-02 3.

of TechnicEl spec i fi c at i on l i n, 4 t 4.48E+00 2.48E+00 C.

Particulates

1. P srt i cul stes ui t h h al f-l i ve s >3 dans Ci 6.47E-03 1.33E-02 1.00E+02l 2.

Roersos release rate for pe r-i co uCi/sec 8.23E-04 1.64E-03 3.

. of Technich1 specification 1 i ta i t 1.32E+00 2.74E+00 4.

Gross si ph s radi o ac t i vi t v Ci 4.89E-06l 4.35E-06[

D.

Tritium 1.

Total release C1 5.97E+00 1.72E+00 9.00E+01l 2.

Aver ace release rate for period uCi/sec 7.59E-01 2.11E-01

3. *: of Technical spec t f i c at i on I t r,i l t 6.68E+00 2.00E+00 1

Q D

D oo o

q'

~

D< e[

_o e

l k

l 32 I

0**

T Y'

TABLE 2-2a S.A ao o

.m E.

I. Hat ch Nuclear Power Pl ant UtlI T 1 i

EFFLUENT AND WASTE DISPOSAL set 11AHHUAL REPORT 1980 fs GASEGUS EFFLUENTS-ELEVATED RELEASE (v)

CONTINUOUS MODE BATCH I40DE tiuc l i de s Re l e as ed U r. i t Quarter Qu ar t e r Quarter Quarter 3

4 3

4 1.

Fission gases Xe-133 Ci 7.50E+03l

8. 0 4 E + 0 :-

0.00Ev00 0.00E+00 Me-131f1 Ci 2.44E+00j 1.52E+03 0.00E+00 0.00E+00 Vr-88 C1 4.6SE+02 1.16E+03 0.00E+00 0.00E+00 Xe - 133ri Ci 6.57E-01 4.75E+01 0.00E+00 0.00E+00 Xe-135 Ci 2.10E+02 2.68E+02 0.00E+00 0.00E+00 K r - 85 f1 Ct 1.80E+03 2.62E+03 0.00E+00 0.00E+00 I-131 Ci 3.3SE-02 4.62E-01 0.00E+00 0.00E+00 tr-a?

Ci 1.15E+02 2.04E+02 0.00E+00 0.00E+00:-

Xe-12.:

Ci 5.23E+02 6.67E+02 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 6.15E+01 0.00E+00 0.00E+00 H-13 Ci 1.70E+02 2.67E+02 0.00E+00 0.00E+00 tr-35 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135t1 Ci 4.32E+02 4.50E+02 0.00E+00 0.00E+00 I-133 Mr-09

~~

Ci 0,00E+00 0.00E+00 0.00E+00 0.00E+00 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 2 21E+01 8.84E-01 0.00E+00 0.00E+00 Tot al for period Ci 1.12E+04 1.53E+04 0.00E+00 0.00E+00 2.

Iodines

("#)

I-131 Ci 1.08E-01 2.98E-02 0.00E+00 0.00E'00 1-133 Ci 1.02E-01 8.35E-03 0.00E+00 0.00E+05T' I-135 C1 1,13E-02 2.50E-05 0.00E+00 0.00Ev00 Tct al for period Ci 2.21E-01 4.07E-02 0.00E+00 0.00E+00 3.

Part i c ul at e z 5r-99 Ci 2,68E-04 1.38E-03 0.00E+001 0.00E+00!

sr-90 Ci 2.74E-07 7.97E-07 0.00E+00-0.UDE+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 0.00Ev00 0.00E+00 I-til Ci 3.28E-04 1.24E-04 0.00E+00 0.00E+00 in-113 Ci 0,00E+00 0.00E+00 0.00E+00 0.00E+00 1:n-140 Ci 1 31E-04 5.21E-05 0.00E+00 0.00E-00

_C2-134 C1 1,50E-06 4.56E-06 0.00E+00 0.00E+00 C1-137 C1 3.60E-05 8.63E-06 0.00E+00 05 C+00 Cc-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 1.91E-06 8.36E-06 0.00E+00 0.00E+00 C - S i.

C 0.00E+00 0.00E+00 0.00E+00 0.00E+00 iln - 5 4 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+001 Fe-59 C

0.00E+00 0.00E+001 0.00E+00, 0.00E+007 Cc-60 Ci 7 39E-07 5.79E-07 0.00E+00 0.00E,00{

La-140 Ci 3.14E-04 1.26E-04 0.00E+00 0.00E+001 p}

70, 31 +or neriod Ci 1:0SE-03 1.71E-01 0.00E+00 0.00E+00 33 1

l l

l

E.

I. Hat c h leuc l e ar Pouer Pltnt UllIT 2 EFFLUEt4T AtlD WASTE DISPOSAL SEMI Atit1UAL REPORT 1980 GASEQUS EFFLUEtiTS-ELEVATED PELEAS C0tiTil100US 110DE E ATCH T10DE

(

)

Unit Qu ar t e r Quarter Qu ar t e r Quarter tiuclides Released 3

4 3

4 1.

Fission gases i

Xe-133 C1 2.00E+01 8.77E+00 0.00E+00 0.00E+00 Xe-151M Ci 6.48E-03 1.66E+00 0.00E+00 0.00E+00 Kr-83 C1 1,24E+00 1.26E+00 0.00E+00 0.00E+00 Xe-1??M C1 1 75E-03 5.19E-02 0.00E+00 0.00E+00 Me-135 Ci 5.59E-01 2.93E-01 0.00E+00 0.00E+00 Vr-85M C1 4.7EE+00 2.36E+00 0.00E+00 0.00E+00 1-131 Ci 8,99E-05 5.04E-04 0.00E+00 0.00E+00 Kr-17 Ci 3.06E-01 2.22E-01 0.00E+00 0.00E+00 ha-138 Ci 1.39E+00 7.27E-01 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 6.70E-02 0.00E+00 0.00E+00 ti-13 C1 4.51E-01 2.91E-01 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l

Xe-135t1 C1 1,15E+00 4.90E-01 0.00E+00 0.00E+00 I-133 Ci 0 00E+00 0.00E+00 0.00E+00 0.00E+00 Vr-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 5.8SE-02 9.64E-04 0.00E+00 0.00E+00 Total for period Ci 2 99E+01 1.67E+01 0.00E+00 0.00E+00 f

2.

Iodines v

f'%

(_)

I-131 C1 2.37E-04 3.25E-05 0.00E+00 0.00E+00 1-133 C1 2,71E-04 9.10E-06 0.00E+00- 0.00E+00 i

I-135 C1 2,99E-05 2.73E-06 0.00E+001 0.00E+00 Tot al for per iod Ci 5<SSE-04 4.44E-05 0.00E+00 0.00E+00 3.

P ar t i c ul at es Sr-89 Ci 7.13E-07 1.51E-06 0.00E+00 0.00E+00 3r-90 Ci 7,28E-10 S.69E-10 0.00E+00 0.00E+00 Ce-141 Ci 9.00E+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 I-131 C1 3.72E-07 1.35E-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 3.49E-07 5.6SE-03 0.00E+00 0.00E+00 Cs-134 C1 4.00E-09 4.97E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C2-137 Ci 9.56E-OS 9.41E-09 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2r-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ut 25 Ci 5 08E-09 9.11E-09 0.00E+00 0.00E+00 Co-53 C1 0,00E+00 0.00E+00 0.00E+00 0.00E+00 ftn-54 Ci 0,00E+00 0.00E+00 0.00E+00 0.00E+00 de-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 1.96E-09 6.31E-10 0.00E+00 0.00E+00 L a-140 Ci 8.35E-07 1.3SE-07 0.00E+00 0.00E+00 Tot al for paried Ci 2.88E-06 1.86E-06 0.00E+00 0.00E+00 gS

(/

34 t

E.

I Hatch Huc l e ar Power Pl ant SITE O q.

[

TABLE 2-2C mp m

d c o u \\1 o Ju.

1.

.r

{

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1980

{

CASE 00$ EFFLUENTS-ELEVATED RELEASE

~

()

CONTINUGUS MODE EATCH MODE h

Nuclics2 Feleased Unit Qu art er Quarter Quarter Quarter 3

4 3

4 1.

Fission gases Xe-133 Ci 7.52E+03 S.05E+03 ' O.00E+00 0.00E+00 Xe-131M C1 2.44E+00 1.52E+03 0.00E+00 0.00E+00 Kr-68 Ci 4.69E+02 1.16E+03 0.00E+00 0.00E+00 Xe-133M Ct 6.5SE-01 4.75E+01 0.00E+00 0.00E+00 Xe-135 Ci 2.11E+02 2.69E+02 0.00E+00 0.00E+00 Kr-85M Ci 1.00E+03 2.62E+03 0.00E+00 0.00E+00 l-131 Ci 3.39E-02 4.63E-01 0.00E+00 0.00E+00 Kr-87 Ci 1.15E+02 2.04E+02 0.00E+00 0.00E+00 Xe-1?8 Ci 5.25E+02 6.67E+02 0.00E+00 0.00E+00 Xe-137 Ci 0 00E+00 6.16E+01 0.00E+00 0.00E+00 N-13 Ci 1.70E+02 2.67E+02 0.00E+00 'O.00E+00

^

Kr-35 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135t1 C1 4,33E+02 4.50E+02 0.00E+00 0.00E+00 I-133 C

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 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 2.21E+01 8.85E-01 0.00E+00 0.00E+00

~~713E+04 1.53E+04 0.00E+00 0.00E+00 Tot al for period Ci 1

2.

Iodines

()l 1-131 Ci 1,08E-01 2.99E-02 0.00E+00' O.00E+00 I-133 C1 1.02E-01 8.36E-03 0.00E+00 0.00E+00 1-135 C1 1.13E-02 2.50E-03 0.00E+00 0.00E+00 Total for period C1 2.22E-01 4.07E-02 0.00E+00 0.00E+00 3.

Part i c ul at es Sr-89 C1 2,69F-04 1.38E-03 0.00E+00 0.00E+00 Sr-90 C1 2,74E-07 7.98E-07 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4

Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 3.29E-04 1.24E-04 0.00E+00 0.00E+00

$n-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci le32E-04 5.21E-05 0.00E+00 0.00E+00 C3-134 C1 1.51E-06 4.57E-06 0.00E+00 0.00E+00 Cs-137 Ci 3.60E-05 3.64E-06 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2r-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 Ci 1.92E-06 3.36E-06 0.00E+00 0.00E+00 Co-58 C1 0 00E+00 0.00E+00 0.00E+00 0.00E+00 lin-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 t

Co-60 Ci 7,41E-07 5.80E-07 0.00E+00 0.00E+00 l

ls-140 Ci 3 15E-04 1.27E-04 0.00E+00 0.00E+00 T

for oeriod Ci 1 08E-03 1.71E-03 0.00E+00 0.00E+00 O

ot al l

l L

i 35 b

VhuLL l-Ja ma m

h E.

I. H at ch Hu;l e ar Power Pl ant Uti!T 1 cw o

EFFLUENT AND WASTE DISPOSAL SEMIANHUAL REPORT 1980

?

GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE G-)

CettTit4UQUS MODE EATCH MODE i

Nuclides P+1 eased Unit Qu art er Qu ar t er Qu ar t e r Gu ar t e r l'

3 4

3 4

I. Fission gases C1 1 77E+02 5.87E+02' O.00E+00 0.00E+00 Xe-133 Cl 0.00E+00 7.91E-04 0.00E+00 0.00E+00 Xe-131rt Kr-??

C1 1 37E+00 2.00E-01 0.00E+00 0.00E+00 Xe-133M Ci 2.15E+00 1.14E+01 0.00E+00 0.00E+00 Xe-135 Ci 1,71E+02 6.65E+01 0.00E+00 0.00E+00 kr-85M Ci 2,72E-01 4.12E-01 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 6.15E-03 0.00E+00 0.00E+00 Kr-S7 Cs 5,53E+00 2.53E+00 0.00E+00 0.00E+00 Ci 1,60E+00 7.S6E+00 0.00E+00 0.00E+00 Xe-133 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-13 Ci 3.09E-02 1.09E+00 ' O.00E+00 0.00E+00

(

Kr-85 C) 0 00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M C1 1 17E+02 4.42E+01 0.00E+00 0.00E+00 I-133 Cs 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 O.00E+00 Ar-41 Ci 0.00E+00 0.00E+00 0.00E+00 Tot al for neriod Ci

'~4776E+02 7.21E+02 0.00E+00 0.00E+00

/

2.

Iodines Ci 5.89E-02 6.47E-02' O.00E+00 0.00E+00 I-131 Ci 4.69E-02 2.34E-02 0.00E+00 0.00F+00 I-133 Ci 1,87E-02 9.26E-03 0.00E+00 0.00E+00 I-135 Tot al for period Cl 1,24E-01 1.01E-01 0.00E+00 0.00E+00 3.

P ar t i c u l at e s Sr-89 Ci 1.48E-05 4.85E-05 0.00E+001 0.00E+00 Br-90 C1 0 00E+00 1.47E-05' O.00E+00' O.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 1 92E-05 3.54E-04 0.00E+00 0.00E+00 I-131 Ci 2,94E-03 3.5SE-03 0.00E+00 0.00E+00 Sn-113 Ci 0 00E+00 1.05E-06 0.00E+00 0.00E+00 Ba-140 Ci 1 37E-06 1.70E-05 0.00E+00 0.00E+00 C2-134 Ci 6 24E-04 3.41E-03 0.00E+00 0.00E+00 Cs-137 Ci 7,95E-04 3.73E-03 0.00E+00 0.00E+00 Cc-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2r-?5 Ci 0 00E+00 1.99E-09 0.00E+00' O.00E+00 Hb-95 C1 0.00E+00 1.26E-08 0.00E+00 0.00E+00 Co-53 C1 0:00E+00 2.67E-05 0.00E+00 0.00E+00 Mn-54 Ci OiOOE+00 2.63E-06 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 C1 3 67E-05 9.56E-05 0.00E+00 0.00E+00 L a-140 Ci 2.23E-05 4.41E-05 0.00E+00 0.00E+00 Tot al for period Ci 4 :45E-03 1.14E-02 0.00E+00 0.00E+00

(}

36 1

d

II\\BLE 2-30 D

  • E'T

'i E.

I.

H atch Hucle ar Power Pl ant UNIT 2 W

@ N b ird EFFLUENT AND WASTE DISPOSAL SEHIAHHUAL REPORT 1980 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE hk f

COHTINUOUS MODE EATCH NODE Huclides Re l e ase d Unit Oyarter Qu ar t e r Qu ar t er Quarter 3

4 3

4 1.

Fission gases q

Xe-133 C1 1.26E+01 1.64E+01 0.00E+00 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-83 C1 1.26E+00 4.42E+00 0.00E+00 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 Ci

9. 91E+00 2.91E+01l 0.00E+00 0.00E+00 Kr-85H Ci 8,34E-01 3.09E+00 0.00E+00 0.00E+00 1-131 Ci 1.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-37 C1 3,95E-01 1.76E+00 0.00E+00 0.00E+00

.Xe-138 Ci 0 00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N-13 Ci 3.96E+00 3.53E+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 0.00E+00 0.00E+00' O.00E+00 0.00E+00 I-133 C1 3.96E-01 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 1.18E+01 0.00E+00 0.00E+00 1-135 C1 4 57E-01 0.00E+00 0.00E+00 0.00E+00 Ar-41 C1 3.16E-02 0.00E+00 0.00E+00 0.00E+00 Tot al for period Ci

~~7799E+01 7.01E+01 0.00E+00 0.00E+00 2.

lodines I-131 Ci 7.83E-031 9.0SE-04 0.00E+00 0.00E+00 I-133 Ci 1 21E-02 6.31E-04 0.00E+00 0.00E+00 1-135 Ci 5,55E-03 1.79E-04 0.00E+00 0.00E+00 Tot al for period Ci 2,55E-02 1.72E-03 0.00E+00 0.00E+00 3.

Part i c ul at e2

~,

Sr-89 Ci 1.82E-05 5.33E-05 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 6.83E-07 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 1.16E-07 0.00E+00 0.00E+00 Cr-51 C1 0,00E+00 0.00E+00 0.00E+00 0.00E+00

^

I-131 Ci 8.80E-04 1.23E-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 1.67E-05 1.84E-06 0.00E+00 0.00E+00 Cs-134 Ci 1.32E-07 1.27E-06 0.00E+00 0.00E+00 Cs-137 Ci 2629E-07 8.91E-06 0.00E+00 0.00E+00 Cs-144 Ci 0 00E+00 5.19E-06 0.00E+00 0.00E+00 2r-95 Ci 0,00E+00 0.00E+00 0.00E+00 0.00E+00 Hb-95 Ci 0.00E+00 4.81E-07 0.00E+00 0.00E+00 Co-53 Ci 0,00E+00 0.00E+00 0.00E+00 0.00E+00 Un-54 Ci 0.00E+00 1.99E-07 0.00E+00 0.00E+00 Fe-59 Ci 0 00E+00 0.00E+00 ! 0.00E+00 0.00E+00 Co-60 Ci 3.68E-06 3.65E-06 0.00E+00 0.00E+00 L a-14 0 Ci 1 81E-05 2.94E-06 0.00E+00 0.00E+00 O

Tots 1 for period Ci 9.37E-04 2.02E-04 0.00E+00 0.00E+00 e

37

TABLE 2-3c D**

  • D 3'

b E.

10 H at c h Huc t s ar Powe r Pl ant SITE ab m

oc-EFFLUENT AtID WASTE DISPOSAL SEMIANNUAL REPORT 1980 h

CASE 003 EFFLUEtiTS-GROUND-LEVEL RELEASE k_')N

/

C0tiTINUOUS 110DE BATCH MODE j

huclides Released Unit Qu art e r Qu art er Qu ar t e r Qu ar t e r f

3 4

3 4

1.

Fission gases Xe-133 C1 1 39E+02 6.03E+02 0.00E+00 0.00E+00 Xe-131M Ci 0600E+00 7.91E-04 0.00E+00 0.00E+00

\\

kr-99 Ci 2.63E+00 4.62E+00 0.00E+00 0.00E+00 Xe-133M Ci 2 15E+00 1.14E+01 0.00E+00 0.00E+00 Xe-135 Ci

-1. 81 E + 0 2 9.56E+01 0.00E+00 0.00E+00 K r-? 5 r1 Ci 1,11E+00 3.50E+00 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 6.15E-03 0.00E+00 0.00E+00 Kr-97 Ct 5.92E+00 4.29E+00 0.00E+00 0.00E+00 Xe-138 Ci 1.60E+00 7.66E+00 0.00E+00 0.00E+00 g

Mi-137 Ci 0,00E+00 0.00E+00 0.00E+00 0.00E+00 ti-13 Cs 3 99E+001 4.62E+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 1,17E+02 4.42E+01 0.00E+00 0.00E+00 I-133 Ci 3.96E-01 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 1.18E+01 0.00E+00 0.00E+00 1-135 C1 4.57E-01 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 8,16E-02 0.00E+00 0.00E+00 0.00E+00 Tot al for period Ci 5.06E+02 7.91E+02 0.00E+00 0.00E+00

~~"~~

2.

Iodines Ci I-131 Ci 6.67E-02 6.56E-02 0.00E+00 0.00E+00 1-133 Ci 5.90E-02 2.91E-02 0.00E+00 0.00E+00 I-135 Ci 2.42E-02 8.46E-03 0.00E+00 0.00E+00 Tct al for period Ci 1.50E-01 1.03E-01 0.00E+00 0.00E+00 3.

Par t i c u l at e s 4

Sr-99 Ci 3,30E-05 1.02E-04 0.00E+00

0. 06 +00 Sr-90 Ci 0,00E+00 1.53E-05 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 1.16E-0?

0.00E+00 0.00E+00 Cr-51 C1 1.92E-05 3.54E-04 0.00E+00 0.00E+00 I-131 Ci 3,82E-03 3.70E-03 0.00E+00 0.00E+00 Sn-113 Ci 0,00E+00 1.05E-06 0.00E+00 0.00E+00 Ba-140 Ci 1.60E-05 1.89E-05 0.00E+00 0.00E+00 Cs-1?4 Ci 6 24E-04 3.41E 0.00E+00 0.00E+00 Cs-137 Ci 7 95E-04 3.74E-03 0.00E+00 0.00E+00 Ce-144 Ci 0,00E+00 5.19E-06 0.00E+00 0.00E+00 2r-95 Ci 0,00E+00 1.99E-09 0.00E+00 0.00E+00

(

Hb-95 Ci 0.00E+00 4.94E-07 0.00E+00 0.00E+00 Co-SS Ct 0.00E+00 2.67E-05 0.00E+00 0.00E+00 Mn-54 Ci 0,00E+00 2.83E-06 0.00E+00 0.00E+00 Fe-59 C1 0,00E+00 0.00E+00 0.00E+00 0.00E+00 Cc-60 Ci 4r04E-05 9.93E-05 0.00E+00 0.00E+00 La-140 Ci 4,03E-05 4.72E-05 0.00E+00 0.00E+00

()

Tot al for oeriod Ci 5 39E-03 1.16E-02 0.00E+00 0.00E+00 e

38

TABLE 3-1 a PLANT E. I. HATCH EFFLUENT AND WAWE DISPOSAL SEMIANNUAL REPORT (YEAR) 1980 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNIT I

JULY THRU DECEMBER A. SOLID WASTE SHIPPEQ OFFS!TE FOR BURIAL OR DISPOS / L (Notirradia

1. Type of waste unis konm Est Tool Period Error. %
a. Spent t: sins, futer sindg:s, emporstor md ' l.34 E+21 g.

bottor s. etc.

Ci 6 sq E+2)

.b E +1

b. Dry compreuro;: ws:te contsrmnsted m3 A 70 E+ 1 i

equip.e::.

C1 2.77 5+0

.b E ti

c. Irt:Jiated cornponents, control m3 E

~

rods. et:.

NA C1, NA E

NA E

d. Other (desense) md i

E 9#

NA Ci NA E

NA E 1 Estim:te of cuier nuclide composition (by type of w=ste)

IS0 TOPE I PERCENT CURIES Xel33 1.75%

11.01 Ci a.1131 ALL OTHER5.9a 25.5%

160.44 Ci Csl34 ALL OTHER5 0.66 C1 25.5%

160.44 Ci Csl37 33.1%

208.25 Ci Zn65 O

9.2%

57.88 Ci co6o 2 7x

'6 99 ci Cr51 1.4%

8.81 Ci

b. Znbo ALL UlHtK5 la 61.0%

1.32 Ci Cobd ALL OTHERS.02 Ci 9.7%

21 Ci Cob 0 8.1 %

.18 Ci Crbi 9.3%

.20 CL Nb95 6.6%

.14 Ci Zr93 3.5%

.08 Ci Mn94 1.2%

.03 Ci 3.

SoUd Weste Dbpostion i

Number of Shipments Mode ofTransper:::fon D:stinttion 47 TRUCK BARNWELL, S.C.

E 1ARADIATED FUEL SHIPMCJTS (Disposition) k Number of Shioments Mode of Tran:.x:r:2 tion

[estination

-]

N/A N/A N/A p

O

\\

e 39

TABLE 3-lb D*P W

plain E. I. HATCH Oe bs e

a EFFLUENT AND V/ASTE DISPOSAL SEMIANNUAL RE 1980-()

SOLID VIASTE AND tRRADIATED FUEL SHIPMENTS FOR UNIT 2

JULY THRU DECEMBER A. SOLID Y!ASTE SHIPPED OFFS!TE FOR DURIAt. OR DISP

1. Type of waste

' unti s-rion en ear. ro c.:

Period Enor. %

a. Spent resins. fdter sh.dges, euporator a

2 bottor.s. e::.

m

9. 98 E+11 Ce c; anE+11 5 E +1
b. Dry compreurme w:st, contarmasted equip..e tc.

_ _ rn' 1 a E+1!

Ci si 0 E-1

.5 t +1

c. Irradiated componenu, conuol rof.s.et:.

r 1' E

NA Ci NA E NA E

d. Other (desenbe) m' E

NA Ci NA E NA E

2. Esti:=te of maior aueUde composiden (by r>Te of w:ste)

ISOTOPE

! PERCENT 1

CURIES Znos 56.67%

35.72 Ci

a. Cob 8 ALL OTHERS 0.7%

13.72%

8.65 Ci Cobu ALL OTHERS

.44 Ci Batal4U 7.95%

5.01 Ci Lal40 5.43%

3.42 Ci q\\_-

Crbi 4.95%

3.12 Ci 1131 4.76%

3.00 Ci Mnb4 4.61%

2.91 Ci 1.22%

.77 Ci

b. Cst 4/

Csl44

' 50.9%

.25 Ci

~

1831 38'.9%

.19 Ci Znbb 4.6%

.02 Ci

'y Cobu

~

3.9%

.02 Ci 1.19%

.01 Ci

~

i 1

3.

SoUd Y!aste Dis;:odtion Nu r.ber of Sid:m:nts Mede ofTr:n: port::fon D=tination 21 TRUCK BARNWELL, S.C.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shloments Mode of Tran:cor stion Destination e'

NA ta fM O) 40 W

t

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