ML20063K641
| ML20063K641 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/24/1982 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20063K633 | List: |
| References | |
| NUDOCS 8209080310 | |
| Download: ML20063K641 (44) | |
Text
Georgia PowIr Comptny Post offica Box 439 Bixliy, Georgia 31513 Telephone 912 367-7781 912 537-9444 1
GeorgiaPower Edwin 1. Hatch Nuclear Plant August 24, 1982 PM-82-808 90- 31 !
c- 'v PLANT E.
I.
HATCH Semi-Annual Radioactive Effluent Release Report Director of Inspection and Enforcement
% Distribution Services Branch U.
S.
Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
Pursuant to Section 5.7.1.b in Appendix B,
Environmental Technical Specifications, of the Plant Edwin I.
Hatch Operating
- Licenses, please find enclosed the Semi-Annual Report for Plant Radioactive Effluent Releases, January 1, 1982 through June 30, 1982.
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I GEORGIA POWER COMPANY PLANT E.
I. IIATCII UNITS NO. 1& 2 SEMI-ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JANUARY 1, 1982 - JUNE 30, 1982
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PLANT E.
I. HATCH SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES
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SECTION TITLE PAGE 1.
LIQUID EFFLUENTS 1
1.1 REGULATORY LIMITS 1
1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS 2
1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 4
6 1.4 LIQUID EFFLUENT RELEASE DATA 2
GASEOUS EFFLUENTS 24 2.1 REGULATORY LIMITS 24 2.2 MEASUREMENTS AND APPROXIMATIONS OF i
TOTAL RADIOACTIVITY 26 2.3 GASEOUS EFFLUENT RELEASE DATA 30 3
SOLID WASTE 30 3.1 REGULATORY SPECIFICATIONS 30 30 3.2 SOLID WASTE DATA I
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PLANT E. I. HATCH SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES l
5 FIGURE LIST OF FIGURES PAGE 7
l-1 METHODS OF MEETING TABLE II COLUMN 2 MPC LIMITS (10 CFR 20) 8-12 1-2 LIQUID RADWASTE ANALYSIS - UNIT I 1-3 LIQUID RADWASTE ANALYSIS - UNIT II 13-16 17 1-4 LIQUID RADWASTE DISCHARGE PERMIT 1-Sa, b LIQUID RADWASTE DATA COMPILATION 18, 19 PAGE TABLE LIST OF TABLES l-la, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 20, 21 1-2a, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-BATCH ONLY 22, 23 2-la-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENT-(
SUMMATION OF ALL RELEASES 31-33 2-2a-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-ELEVATED RELEASE 34-36 2-3a-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-GROUND LEVEL RELEASES 37-39 3-la, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 40, 41 9
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PLANT RADIOACTIVE EFFLUENT RELEASES 4
1 LIOUID EFFLUENTS 1.1.
REGULATORY LIMITS l.
The co'ncentration of radioactive -materials released in
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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.
f 3.
The cumulative release of radioactive materials in liquid wastes, excluding tritium and dissolved gases, l'
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 J
prior to exceeding the limits specified in 1. above.
l 5.
The operability of the automatic isolation valve in the liquid radioactive waste discharge line
'shall be demonstrated quarterly.
6.
The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to
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process radioactive. liquid wastes prior to their discharge when the projected cumulative release rate could.
exceed 1.25 Ci/ reactor / calendar
- quarter, excluding tritium and dissolved gases.
7.
The maximum radioactivity to be contained in any liquid l
radwaste tank that can be discharged directly to the environs shall not exceed 10 Ci, excluding tritium and dissolved gases.
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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 inv.estigation to identify the causes of such releases, define and initiate a program of action to reduce such releases to the design objective levels and report these actions to ' the Commission within 30 days from the end of the quarter during which the release occurred.
9.
An unplanned or uncontrolled offsite release of radioactive materials in liquid effluents'in excess of 0.5 Ci excluding dissolved gases shall be reported.
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1.2. MAXIMUM PERMISSIBLE CONCENTRATIONS The MPC values used in determining allowable liquid radwaste release concentrations are taken from 10 CFR Part 20, Appendix B, Table II, Column 2.
Release rate and dilution ratio for each batch are determined by a mixed nuclide MPC calculation performed
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before the release of the batch.
To facilitate the measurements and calculations, the nuclides of Column 2 which can be produced in a fission reactor have been grouped according to MPC value and type of radiation as shown in Figure 1-1.
The concentration of each of the 29 gamma emitting ~
nuclides specifically noted in Figure 1-1 is measured individually because of interest in that nuclide or because of inadequate sensitivity for the nuclide from a gross activity measurement.
For any of the 29 nuclides not detected in the gamma scan, the MDA limit is computed from the measured data for that sample.
Only two pure beta emitters, Sr-89 and St-90, have MPC values less than 9 X 10
-6 uCi/ml.
Individual measurements are made on proportional composite liquid radwaste samples to determine the Sr-89 and 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 values greater than 9
X 10
-6 uci/ml, except for the 29 nuclides noted above, is determined by gross gamma and gross beta mea su r e.nen ts.
Measurement sensitivity limits of approximately 2 cpm /ml allow a
null measurement to show that the sum (Ci/MPCi),
is less than 0.1 for gamma and beta nuclides not measured directly.
The sum of the ratios, I (Ci/MPCi), for alpha emitters can be shown to be less than 0.1 by a
null measurement with a
sensitivity limit of approximately 1 X 10
-2 cpm /ml'.
Gas flow counting is used to achieve the required sensitivity of measurement.
Thus, except for radionuclides produced in negligible quantities in a fission reaction (eg.
I-125, I-129 etc.),
the methods outlined above provide a
means to assign a
quantitatively measured or MDA value to all nuclides in Column 2.
These measured and calculated concentration values for each batch are used to calculate the dilution ratio, release rate, and dilution rate prior to release of each batch.
Both the concentration and release data are stored on a computer disc file.
The disc file data is used to assure that quarterly and annual release limits are not exceeded.
Bases used for the data of Table 1-1 are as I
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follows:
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A.
Fission end cctivation 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
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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 th.e 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 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 <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 additional information.
A conservative
. lease limit, the maximum sensitivity limit of 4
X 10-5 uCi/ml of each dissolved and entrained radionuclide as specified in Regulatory Guide 1.21, has been applied in determining the percent of applicable limit.
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1.3 MEASUREMENTS AND APPROXIMATIO!iS OF TOTAL RADIOACTIVITY.
Details of the analytical procedures for liquid radwaste analysis are con'tained in operating procedure HNP-7601.
The following measurements are performed as indicated:
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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 Batch Ge(Li) spectrometry with on-line computer o
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r 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 cf a composite sample.
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The Ge(LI) detedtor consist of a 10% and two 15% efficiencv, 2.8 FWIiM resolution detectors in 4-inch thick lead shield's.
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 E (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)
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by a laboratory technician.
Although the computer could printout the release permit and will inform the technician if a batch cannot be discharged as desired, a manual transfer of calculated i
results to the release permit by the technician was implemented as more likely to catch abnormal conditions in the data.
The liquid radwaste monitor setting is calculated by the computer based on the gamma activity as measured in the sample used for laboratory analysis.
A coefficient has been determined which relates laboratory gamma counts to the monitor count ~ rate.
If the monitor count rate exceeds the calculated setting during discharge, then the liquid passing through the monitor is not representative of the sample which was analyzed in the lab.
A monitor reading in excess of the calculated setpoint therefore results in an automatic termination of the liquid effluent discharge.
Liquid effluent discharge is also automatically terminated if the dilution flow rate falls below the ' flow rate used in the computer calculation.
When the release permit is returned from Radwaste Operations following discharge, the discharge data is combined with the The disc file may be analysis results on the computer disc file.
scanned to display trends in any recorded parameter, or may be summed for reporting purposes as shown in Figure 1-Sa and b.
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All other radionuclide concentration 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
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is performed in the Ge(Li) spectrometry system with computer data reduction using the Liquid Radwaste Library which includes-gases.
Several comments are indicative of the success of the HNP liquid radwaste program during this reporting period:
1.
The total measured activity released in liquid effluent for both Units was 1.85 E-l curies for the first quarter and
- 2. 21 E-1 curies for the second quarter.
These values were approximately 1/63 for Unit 1 and 1/394 for Unit 2 for the first quarter and 1/58 for Unit 1 and 1/208 for Unit 2 for the second 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 32.63% of the liquid radwaste reaching the sample tanks was discharged; 67.37%
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 1060 discharge batches for both Units.
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1.4 LIQUID EFFLUENT RELEASE DATA Regulatory Guide 1.21 Tables 2A and 2B are found in this report as Table 1-la, b and 1-2a, b.
Data is presented on a quarterly basis as per Regulatory Guide 1.21.
Other data pertinent to batch releases of radioactive' effluent from both units is as follows:
Number of batch releases:
1060 Total time period for releases:
139,759 minutes Maximum time period for a batch release:
478 minutes Average time period for batch release:
132 minutes Minimum time period for a batch release:
22 minutes t
Average stream flow during periods of release of effluent into a flowing stream:
16,968 CFS
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FIGURE l-1 METHODS OF MEETING, TABLE II, COLUMM 2 MPC LIMITS BETA ALPHA MPC RANGE GAMMA-RAY EMITTERS EMITTERS (U C1/ml)
EMITTERS I-131,I-132, I-133 Sr-89, Sr-90 I-135, Cs-134 (Separation &
Gas Flow 9 X 10-6 (Ge (Li) Gamma-Ray Counting)
ALL Spectroscopy)
(Gas Flow
- Counting, Sensitivity
- 0. 01 CPM /ml)
Ba-La-140, Na-24,Cu-64 Tritium CO-60, Fe-59, Zn-65 9 X 10-6 Aq-110m, Mn-54, CO-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, Ce-Pr-144 (Gas Flow Count,
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(Ge(Li) Gamma-Ray ing Sensitivity 2 CPM /ml Spectroscopy)
All others (Gross Gamma-Well Counter; Sensitivity 5 CPM /ml) l i
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PROCEDURE: HilP-7601 REVISIOll: 10 DATA SHEET S
- 4**********+**,,#+***++**+*+4#se
- +++.+,.+
E.
I. Hatch liuc le ar Plant Liquid Radwaste Analysis
- ++++++++++++,,+,+,,++,+++,,+,,++++,++++++,++
(-
l Reactor # 1 Batch # 101-Tank: WSTA1 Recirc time: 60 n.inutes Conime nt : MAltlTAlli CST Run date:
2/20/32 0448 Count start d at e :
2/20/82 0127 Sample voluh.e: '1000. 00 m1 Clock t i nie : 3000 secs Georuetry code: 1LHB-0 Live t irae: 3000 secs Detector #, 2 MCAN 2 j
Library: L RI-IL E2 Operator: DG En e r g y( k e t/ > =
. 05 + 1.001+Ch# + 0.000E+00*Ch#^2 + 0.000E+00*Ch#^3: 02/20/82 0040 E00 = 1/t8.002E-02
- E^<-2.7590E+00) 383.617
- E^(9.2169E-01>3 : 02/14/82 0000
+
where E = Energy in HeV.
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FIGURE 1-2 (CONTINUED 1 JSOTOPE EHERGY COHCENTRATIOli ERROR MPC.
C/MPC (kev)
(uCi/ml)
(uCi/ml)
(uCi/ml>
===================================================================
Cc-144 133.50
<3.275E-07 1E-05
<3.27E-02
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Tc -99ta 140.50
<3.745E-08 3E-03
<1.25E-05 Ce-141 145.40
<6.829E-03 9E-05
<7.59E-04 Hp-239 277.90
<2.125E-07 1E-04
'<2.12E-03 Cr-51 320.10
<2.632E-07 2E-03
<1.34E-04 I-131 364.50
<3.052E-08 3E-07
<1.02E-01 2n-69m 438.70
<2.285E-OS 6E-05
<3.81E-04 H-187 479.50 (9.499E-08 6E-05
<1.5SE-03 F-13 511.31
<3.485E-08 SE-04
<6.97E-05 I-133 529.50
<2.765E-OS 1E-06
<2.77E-02 Ba-140 537.40
<1.151E-07 2E-05
<5.76E-03 As-76 559.30
<5.984E-08 2E-05
<2.99E-03 Cs-134 606.00 6.399E-07 5.22SE-08 9E-06 7.11E-02 Cs-137 661.83 4.791E-07 4.715E-03 2E-05 2.40E-02 Mo-99 739.70
<1.672E-07 4E-05
<4.18E-03 Zr-97 743.50
<2.602E-OS 2E-05
<1.30E-03 2r-95 756.90
<5.10SE-08 6E-05
<8.51E-04 Hb-95 765.80
<3.083E-OS 1E-04
<3.0SE-04 I-132 772.60
<1.714E-08 SE-06
<2.14E-03 Co-58 810.60
<3.510E-OS 9E-05
<3.90E-04 Hn-54 835.29 1.860E-07 3.430E-08 1E-04 1.86E-03 Ag-110m 884.70
<2.98SE-08 3E-05
<9.96E-04 Zn-65 1115.56 7.475E-07 9.496E-08 1E-04 7.47E-03 1-135 1260.50
<5.473E-08 4E-06
<1.37E-02 Fe-59 1291.60
<5.295E-08 6E-05
<S.83E-04 Co-60 1332.55 4.510E-07 5.247E-08 3E-05 1.50E-02 Cu-64 1345.90
<3.979E-06 2E-04
<1.99E-02 lla-24 1368.55
<2.43SE-OS 3E-05
<S.13E-04 I
La-140 1596.60
<2.133E-08 2E-05
<1.07E-03 Mn-56 1811.00
<2.569E-08 1E-04
<2.57E-04 Sr-89 (EETA)
<1.000E-OS 3E-06
<3.33E-03 Sr-90 (EETA)
<1.000E-09 OE-07
<3.33E-03 H-3 (EETA) 1.520E-04 4.000E-07 3E-03 5.0TE-02 Fe-55 (EETR)
<1.000E-06 SE-04
<1.25E-03 P-32
< EC )
<2.000E-07 2E-05
<1.00E-02 Me azured totals 1.545E-04 4.21SE-07 1.70E-01 LLD totals
<7.026E-06
<2.41E-01 Tot al s 1.615E-04 4.11E-01 DISSOLVED GASE3 Xe-133 31.25 4.745E-06 1.682E-07 4E-05 1.19E-01 Kr-SS 196.10
<3.902E-08 4E-05 (9.76E-04 Xe-133m 233.18
<3.522E-07 4E-05
<3.81E-03 Xe-135 250.10 4.782E-06 6.929E-03 4E-05 1.20E-01 Kr-S5m 305.00
<1.143E-07 4E-05
<2.36E-03 Kr-87 402.70
<1.113E-OS 4E-05
<2.78E-04 Xe-138 434.50
<2.174E-11 4E-05
<5.44E-07 l
Me asured gas totals 9.52SE-06 1.820E-07 2.3SE-01 LLD gas totals
<5.167E-07
<1.29E-02 Total gas 1.004E-05 2.51E-01 g
CF 05.: ACTIVITY Count e r Gross Eackgrour d Time vol Het Error Counts Counts (Ili n )
ml Activity (cpm /tal) 1 S a g ra h 9
m FIGURE 1-2 (CONTINUED)
Hell Crystal 2273 1394 20.0 2
2.20E+01 1.51E+00 Proport i on al~
166' 7
10.0 2
7.95E+00 6.5SE-01
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ESTIMATED HASTE TANK VOLUME = 11257.00 gallons ESTIMATED ACTIVITY THIS EATCH EXCLUDING GASES:
6.58E-03 Curies
( 6.5SE+03 Microcuries)
EXCLUDING H-3 AHD GASES: 1.07E-04 Curies
( 1.07E+02 M i c roc ur i e s.)
Liquid Radoas te Pele ase S'um m ar y
- 1) Meas. ~
excluding H-3 and dissolved gases (uCi/ml): 2.50E-06 +- 1.34E-07 conc.,
Meas. conc., including H-3, excluding gases
- 1.55E-04 +- 4.22E-07
- 2) Calculated LLD concentration, excluding dissolved gases (uCi/ml): 7.03E-06
- 3) Calculated MPC ratio (C/MPC of meas., including gases): 4.08E-01 4 ) M i n i rau ru dilution flou rate (gpm):
10000 5 ) M ax i tuu m tank discharge flou rate (gpm): 24733 6)Specified tank flou rate (gpm): 90 7)Radwaste monitor trip setting: 3410
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A= 1.20E-05,uCi/ml B = 3000 Monitor BG CPS C= 10200000.00, Monitor CPS per uCf/mi F=2,Conserv. Factor A includes measured ' selected','other' nuc lides and gases but excludes:
Sr-89, Sr-90, H-3, Fe-55, P-32 8)Es t i raat e d c onc. of meas. nuclides at point of release (uCi/ml): 1.378E-06 9)dndiluted concentration meets 10CFR20 limits.
ESTIMATED DOSES THIS BATCH, MREM Isotope H.Eody 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-SS 0.00E+ 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133ra 0.00E*.3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I
Hp-239 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cc-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-1?3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2 n - 6 9..
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 U-187 0.00E+ 0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F-18 0.00E+
5 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00L+00 10
b%%'TK-74 (CONTINUED)
I-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E4-140 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 2.00E-04 1.03E-04 2.44E-04 0.00E+00 7.92E-05 2.63E-05 4.28E-06 Cs-137 S.32E-05 9.89E-05 1.35E-04 0.00E+00 4.5SE-05 1.52E-05 2.61E-06 Mo-99 0.00E+00 0.0JE+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-53 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 6.41E-OS 0.00E+00 3.36E-07 0.00E+00 1.00E-07 0.00E+00 1.03E-06 Ag-110m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2n-65 6.70E-06 4.66E-06 1.4SE-05 0.00E+00 9.92E-06 0.00E+00 9.34E-06 I-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 1.61E-06 0.00E+00 7.30E-07 0.00E+00 0.00E+00 0.00E+00 1.37E-05 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ha-24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La-140 0.00E+00 0.00E+00 0.'00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hn-56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+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 6.39E-08 0.00E+00 6.39E-08 6.39E-08 6.39E-08 6.39E-08 6.39E-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 0.00E400 Tot al 2.97E-04 2.06E-04 3.95E-04 6.39E-08 1.35E-04 4.16E-05 3.11E-05 Cumul ative dose this YEAR (iracludes estimate.for this batch):
(
uhole body 1.24E-01 su re m Percent of Tech Spec Limit:
4.14E+00 Bone
- 9. 74E-02 rarem Percent of Tech Spec Litait:
9.74E-01 Liver 1.71E-01 mrem Percent of Tech Spec Limit:
1.71E+00 Thyroid 7.16E-03 mrem Percent of Tech Spec L i ra i t :
7.16E-02 Kidney 5.91E-02 mrem Percent of Tech Spec L i ra i t :
5.91E-01 Lung 1.81E-02 mrem Percent of Tech Spec Limit:
1.81E-01 GI-LLI 1.20E-02 rnrem Percent of Tech Spec Limit:
1.20E-01 Curaul at i ve dose this OUARTER (includes estimate for this batch):
Whole body 1.24E-01 turem Percent of Tech Spec Limit:
8.29E+00 Eone
- 9. 74E-02 rarem Percent of Tech Spec Limit:
1.95E+00 Liver 1.71E-01 mrem Percent of Tech Spec Limit:
3.43E+00 Thyroid 7.16E-03 mrem Percent of Tech Spec Limit:
1.43E-01 Kidney 5.91E-02 rurem Percent of Tech Spec Limit:
1.1SE+00 Lung 1.81E-02 mrem Percent of Tech Spec L i ra i t :
3.63E-01 GI-LLI 1.20E-02 mrem Percent of Tech Spec Limit:
2.40E-01 Projected cumulat ive dose this OUARTER (includes estimate for this batch):
Nhole body 2.22E-01 mrem Bone 1.74E-01 mrem Liver 3.06E-01 mrem Thyroid 1.2SE-02 mrem Kidney 1.06E-01 mrem Lung 3.24E-02 mrem GI-LLI 2.14 E-02 rare m I
Cumul at ive measured act ivi ty thi s YEAR (includes e st i m at e for this batch):
8.495E-02 Curies, excluding H-3 and dissolved gases LPH treatroent s,'s t e ra should be OPERAELE due to projected dose for Hhole Body LPH t re st rae nt s, i t e rn h as bee n,de ruons t rat e d OPER ABLE, confirtued by: DG
N l
r (CONTINUED) 1 BATCHN 101 DATA SUCCESSFULLY STORED SPECTRUll STOPED AS: LPill
(
f
(
i l
1 i
(
n-12
u FIGURE 1-3 5
FROCEDURE: HHP-7601 REVISIGH: 10 DATA SHEET 3 E.
I. Hatch Huclear Plant
[
Liquid Radwaste Analysis
- ++******************+*************,****
Re ac t or # 2' Eatch# 102 Tank: FDST2 Recirc time: 105 minutes Comment: HIGH TURE F.S.
Run date:
2/13/82 1450 Count start dat e :
2/13/82 1245 Sample volume: 1000.00 m1 Clock time: 3000 secs Geometry code: 1LHE-0 Live time: 3000 secs Detector # 3 MCA# 3 Library: LRilLE2 Operator: EF Energy (l.eV)=. 22 + 1.000+Ch# + 0.000E+00*Ch#^2 + 0.000E+00*Ch#^3 : 02/13/82 0000 Eff = 1/[8.378E-02
- E^(-2.3530E+00) + 264.178
- E^(9.3543E-01)] : 02/13/82 0000 uhere E = Energy in MeV.
ISOTOPE ENERGY CONCENTRATION ERROR MPC C/HPC
(
(kev)
(ut'i/ml)
(uCi/ml)
(uCi/ml>
====================================================================
Ce-144 133.50
<7.934E-08 1E-05
<7.93E-03 Tc-994 140.50 (9.131E-09 3E-03
<3.04E-06 Ce-141 145.40
< 1.590E-08 9E-05
<1.77E-04 Hp-239 277.90
<6.776E-08 1E-04
<6.78E-04 Cr-51 320.10
<8.615E-08 2E-03
<4.31E-05 I
~
e 13 e-
,w.
w --
-,+
_, -., - ~, - - - - - - -,
FTGURE 1-3 (CONTINUED)
I-131 364.50
<1.f36E-08 3E-07
<3.79E-02 2n-69m 438.70
<S.904E-09 6E-05
<1.4SE-04 W-187 479.50
<3.577E-OS 6E-05
<5.96E-04 F-18 511.37 1.447E-08 1.23SE-03 SE-04 2.89E-05 I-133 529.50
<9.344E-09 1E-06
<9.34E-03
(
Ba-140 537.40
<3.562E-08 2E-05
<1.78E-03 As-76 559.30
<2.383E-OS 2E-05
<1 19E-03 Cs-134 605.08 1.623E-07 1.312E-08 9E-06 1.80E-02 Cs-137 661.75 2.293E-07 2.322E-OS 2E-05 1.15E-02 Mo-99 739.70 (9.724E-08 4E-05
<2.43E-03 Zr-97 743.50
<S.861E-09 2E-05
<4.43E-04 Zr-95 756.90
<1.786E-08 6E-05
<2.93E-04 Hb-95 765.80
<1.059E-OS 1E-04
<1.06E-04 I-132 772.60 (9.487E-09 SE-06
<1.1?E-03 Co-58 810.60
<9.712E-09 9E-05
<1.0SE-04
._.Mn-54
... 834.80
<1.986E-08 1E-04
<1.99E-04
^ Ag-110m 804.70
<1.612E-OS 3E-05
<5.37E-04 2n-65
-1115.38 1.996E-07 3.763E-08 1E-04 2.00E-03 I-135 1260.50
<2.489E-08 4E-06
<6.22E-03 Fe-59 1291.60
<2.769E-08 6E-05
<4.61E-04 Co-60 1332.71 S.476E-08 1.910E-08 OE-05 2.83E-03 Cu-64 1345.90
<1.204E-06 2E-04
<6.02E-03 Ha-24 1368.55
<1.032E-08 3E-05
<3.44E-04 La-140 1596.60
<7.556E-09 2E-05
<3.78E-04 Mn-56 1811.00
<1.775E-08 1E-04
<1.77E-04 Sr-89 (EETA)
<1.000E-OS 3E-06
<3.30E-03 Sr-90 (BETA)
<1.000E-09 OE-07
<3.33E-03 H-3 (EETA) 5.000E-04 5.000E-05 3E-03 1.67E-01 Fe-55 (EETA)
<1.000E-06 SE-04
<1.25E-03 P-32
( EC >
(1.000E-07 2E-05
<5.00E-03 Me asured totals 5.007E-04 5.000E-05 2.01E-01 I
LLD tot als
<2.976E-06
<9.16E-02 Totals 5.037E-04 2.93E-01 DISSOLVED GASES Xe-133 80.99
<3.077E-OS 4E-05
<7.69E-04 Kr-SS 196.10
<1.523E-OS 4E-05
<3.81E-04 Xe-133ra 233.18
<9.442E-08 4E-05
<2.36E-03 l
Xe-135 250.20 5.783E-OS 8.696E-09' 4E-05 1.45E-03 Kr-85m 305.00
<5.385E-OS 4E-05
<1.35E-03 Kr-87 402.70
<6.515E-09 4E-05
<1.63E-04 Xe-13S 434.50
<3.50SE-10 4E-05 (8.77E-06
, Measured gss totals 5.783E-03 S.696E-09 1.45E-03 LLD gas totals (2.011E-07
<5.03E-03 I
Total g as 2.590E-0?
6.47E-03 l
I I
l GROSS ACTIVITY Counter Gross
Background
Time vol Het Error l
l Counts Counts (Min) m1 Activity (cpm /ml) 1 S i g ra h
- Well Crystal 1712 1347 20.0 2
9.13E+00 1.3SE+00 Proporjional 166 165 10.0 2
5.00E-02 9.10E-01 ESTIMANED WASTE TANK VOLUME = 9744.00 gallor EST1 MATED ACT1Y1TY THIS ERTCH EXCLUDIHG GASES:
1.35E-02 Curies
!.SSE+04 Microcuries) l 14
l FIGURE 1-3 2.55E-05(CONTINUED) (
Curies 2.55E+01 Microcuries)
EXCLUDING H-3 RND GASES:
(
Liquid Radusste Release Summsro
- 1) Meas. conc., excluding H-O and dissolved gases (uCi/mle: 6.90E-07 +- 5.29E-OS Meas. conc., including H-3, excluding gases
- 5.01E-04 +- 5.00E-05 2)Calcul ated LLD concentrat ion, excluding dissolved gases (uCi/ml): '2.9&E-06
- 3) Calculated MPC rat io (C/MPC of meas., including gazes): 2.02E-01 4 ) fli n i r.iura dilution flou rate (gpm):
10000 5)fl axi mum, t ank discharge flou r at e (gpra): 49886
- 6) Spec i fied t ank flou rat e (gpm): 75 7)Radwaste raonitor trip setting: 734 A = 7.4SE-07,uCi/ml E = 650, Monitor BG CPS C = 5271000.00, Monitor CPS per uCi/ml F = 2,Conserv. Fac t or A includes measured ' selected','other' nuclides and gase s but excludes:
Sr-89, Sr-90, H-3, Fe-55, P-32 8)Es t i tuat ed c onc. of meas. nuclides at point of release (uC i /ra l ): 3.727E-06
- 9) Undiluted concentration meets 10CFR20 limits.
I ESTIMATED DOSES THIS BATCH, 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+09 0.00E+00 0.00E+00 Cc-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 tn 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-80 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 0.00E+00 0.00E+00 0.00E+00. 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hp-239 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85ta 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
I-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-37 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0CE+00 0.00E+00 Xe-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-6?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 4.40E-15 3.96E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.17E-15 l
(
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 Cs-134 4.40E-05 2.26E-05 5.37E-05 0.00E+00 1.74E-05 5.78E-06 9.40E-07 Cs-137 3.66E-05 4.10E-05 5.59E-05 0.00E+00 1.90E-05 6.32E-06 1.0SE-06 tlo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-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.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H b '* 5 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 15
IGURE~1-3.
IINUED) C+00 u
v.uo 0.00E+00 0.00E+00 0.00E+00 1-132 0.00E+00 0.00E+00 0.0 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' O.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 In-65 1.55E-06 1.08E-06 3.44E-06 0.00E+00 2.30E-06 0.00E+00 2.16E I-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 k(
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 2.62E-07 0.00E+00 1.19E-07 0.00E+00 0.00E+00 0.00E+00 2.24E-06 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ha-24 0.00E+00 0.00E+00 0.00E+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+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 1.82E-07 0.00E+00 1.82E-07 1.82E-07 1.82E-07 1.82E-07 1.82E-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
~
Total 8.25E-05 6.47E-05 1.13E-04 1.82E-07 3.89E-05 1.23E-05 6.61E-06 i
Cumul at ive dose this YEAR (includes estimate for this batch):
Whole body 2.75E-02 mrem Percent of Tech Spec Limit:
9.16E-01 Bo ne-2.16E-02 mrem Percent of Tech Spec Limit:
2.16E-01 Liver 3.77E-02 mrem Percent of Tech Spec Limit:
3.77E-01 Thyroid
- 1. 37E-05 mrern Percent of Tech Spec Limit:
1.37E-04 Kidney 1.28E-02 mrern Percent of Tech Spec Limit:
1.28E-01 Lung 4.08E-03 rare m Percent of Tech Spec Limit:
4.08E-02 GI-LLI 1.78E-03 mrem Percent of Tech Spec Limit:
1.78E-02 Cumul at i ve dos e this OUARTER (irv ludes est imat e for thi s batch):
Whole body 2.75E-02 rurem
'rcent of Tech Spec Limit:
1.83E+00 g
Lone 2.16E-02 mrer arcent of Tech Spec Lirait:
4.33E-01 Liver 3.77E-02 mrem Percent of Tech Spec L i tu i t :
7.53E-01 Thyroid 1.37E-05 mrem Percent of Tech Spec Limit:
2.75E-04 Kidney 1.2SE-02 mrem Percent of Tech Spec Limit:
2.56E-01 Lung 4.08E-03 mrem Percent of-Tech Spec Limit:
8.15E-02 GI-LLI 1.78E-03 mrem Percent of Tech Spec Limit:
3.56E-02 Projected cumulative dose this QUARTER (i nc l udes est i rust e for thi s bat ch):
i Whole body 5.68E-02 mrem Bone 4.48E-02 mrem Liver
- 7. 79E-02 rurem Thyroid
- 2. 84 E-05 race m Kidney 2.65E-02 mrem Lung 8.43E-03 mrem GI-LLI 3.68E-03 mrem Curaul at i ve me as ured act i vi t y this YEAR < includes estimate for thi s bat ch):
l
~
1.383E-02 Curies, excluding H-3 and dissolved gases s
_----_--------__-_-____---_---_----__-------------_-_-__--_----~_---------------
BATCH # 102 DATA SUCCESSFULLY STORED SPECTRUM STORED AS: LRW2 s
i l
t t
16 x
FIGURE 1-4 ELANLGgh,,_UATC,y DATCH NO.
LloutD_B00'd^91C_01gcycorc PrnM_11 UNIT Q TANK TO DE RCt.EACCD _ _ _ _ _ _
DATE _
RCASON FOR NCCCCSITY OF DISCHARCC ____
(
RECIRC. DURATION
_MINUTCS RECIRC. STNIT TIf1C SAMPLE TIME I.
t'A00RATORY ANALYSIS (1) MEASURED RADIONUCLIOE CONCENTRATION
.E
+
.E __ uCi/ml (2) CALCULATED LLD LIMIT CCNCCNTRATIONS uCi/ml (3) CALCULATED MPC RATIO: 2 (Ci/MPCi)
(4) MINIMUM DILUTION FLOW RATE CPM (S)
MAX. CALCULATED TANK DISCHARCE RATE; 1EEE SEC., F.5.}) __
CPM (G) SPECIFICD TAff( DISCHARCC RATE: 4(S)/2 CPM (7) ItADWASTE MONITOR TRIP SETTINC:
CPS l
i A = Ce(Li)(1) uCI/ml 8 = MONITOR DC CPS C = MONITOR CPS F = CONCERVATIVE PER Ce(Li) uCi/ml FACTOR MONITOR ALARM SETPOINT (CPS) = (C X A X F) +Dt3k COMPLETED DY DATE COMPOSITE LITCR STORCD (1NITIALS)
LAU FORE *1AN APPROVCD l
1 (D) RADWASTE MONITOR MAX. CPS TO DE WITHIN 10 CFR 20 LIf11TSI CXAX (G)i(4)
(G) (3) cps i
I I. OPCitAT IONG INIT.
(9) LICUID RADWASTE MONITOR TRIP SET AT:
CPS (10) CONFIRMED DILUTION FLOW RATE GPM (11) VALVE LINELP CHICKED AS PER HNP _
TANK DIS. INTCCHATOR DIS. fdTE OIL. TOTAL RIVER EL.
MCJ I TOP DATE TTME LCVFt. -%
ROMC.
CPhi CAL FT.
CPG e
1TArtT l
=No n
COMPLETCD BY DATC MIN.
CAL.
DUltATION TOTAL 3HIFT FOREtW4 API'ROYCD I*
RELEASE
- O 10 MIN AFTER START
- AFTER FLUSHINC III.LADORATORY l
(12) TOTAL TANK VOLUME DISCHARCED (CAL. X 3,7851 ml l
[
(13) TOTAL ACTIVITY DISCHARCCD ((1) X (12)I
_ uCi (14) RIVER FLOW RATE (FROM FSAR 2.4-6)
CFS COMPLETED DY DATE i
l t
17
, FIGURE 1-Sa Liquid Redwsste Data Compilct ion for Reg. Guide 1.21 Report E.
- 1. Hatch Huclear Plant UHIT 1
(
Total Activity (Curies)
Quarter 1, 1982 Quarter 2, 1982 Eatches 1 thru 248 Batches 249 thru 577 Hsme Measured Error High LLDs Tot al Measured Error High LLDs Tots)
Ce-144 6.09E-04 5.11E-05 0.00E+00 6.09E-04 4.55E-03 9.41E-05 0.00E+00 4.55E-03 Tc-99r 4.59E-05 1.67E-06 4.59E-05 1.69E-02 2.40E-05 1.69E-02 Ce-141 0.00E,96 0.00E+00 0.00E+00 0.00E+00 1.03E-04 3.95E-06 0.00E+00 1.03E-04 Hp-239 0.00E+00 0.GCE:33 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 2.91E-03 7.31E-05 2.91E-03 2.97E-03 8.10E-05 2.97E-03 1-131 1.77E-03 1.71E-05 0.00E+00 1.77E-03 2.61E-02 4.3SE-05 0.00E+00 2.61E-02 2n-69a 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F-10 7.54E-04 1.19E-05 7.54E-04 2.41E-04 9.22E-06 2.41E-04 1-133 8.72E-05 3.56E-06 8.72E-05 1.22E-03 1.10E-05 1.22E-03 EL-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 As-76 5.56E-06 1.4SE-06 5.56E-06 2.81E-04 1.29E-05 2.81E-04 Cs-134 3.06E-02 5.33E-05 0.00E+00 3.06E-02 2.38E-02 4.66E-05 0.00E+00 2.38E-02 Cs-137 4.36E-02 6.60E-05 0.00E+00 4.36E-02 3.59E-02 5.90E-05 0.00E+00 3.59E-02 Ho-99 7.74E-05 2.82E-05 2.19E-05 9.94E-05 1.43E-02 1.01E-04 0.00E+00 1.43E-02
+
7.89E-06 2r-97 0.00E+00 0.00E+00 0.00E+00 7.89E-06 2.41E-06 1.86E-04 2r-95 5.71E-04 1.73E-05 5.71E-04 1.86E-04 8.47E-06
+
Hb-95 1.10E-03 1.70E-05 1.10E-03 2.30E-04 8.67E-06 2.30E-04 1-132 0.00E+00 0.00E+00 0.00E+00 3.23E-06 7.00E-07
+
3.23E-06 Co-58 1.09E-03 1.89E-05 0.00E+00 1.09E-03 6.55E-04 1.31E-05 0.00E+00 6.55E-04
(
Mn-54 3.71E-00 2.90E-05 0.00E+00 3.71E-03 1.91E-03 2.13E-05 0.00E+00 1.91E-03 Ag-110m 0.00E+00 0.00E+00 0.00E+00 5.54E-05 4.33E-06 5.54E-05 2n-65 3.?3E-02 1.07E-04 0.00E+00 3.23E-02 2.82E-02 9.60E-05 0.00E+00 2.82E-02 1-135 0.00E+00 0.00E+00 0.00E+00 7.45E-05 6.98E-06 7.45E-05 Fe-59 1.95E-04 1.24E-05 0.00E+00 1.95E-04 5.67E-05 6.14E-06 0.00E+00 5.67E-05 Co-60 1.39E-02 4.95E-05 0.00E+00 1.39E-02 9.67E-03 4.03E-05 0.00E+00 9.67E-03 9.86E-03 3.4SE-03'3.57E-04 3.48E-03 Cu-64 9.86E-03 7.21E-04 Ha-24 6.77E-04 9.00E-06 6.77E-04 1.81E-03 1.30E-05 1.81E-03 La-140 6.82E-05 3.93E-06 6.82E-05 1.50E-04 5.54E-06 1.50E-04 Mn-56 0.00E+00 0.00E+00 0,00E+00 0.00E+00 0.00E+00 0.00E+00
' +
0.00E+00 Hb-97 3.18E-05 2.19E-06 3.1SE-05 0.00E+00 0.00E+00 7.41E-03 Cs-138 4.55E-07 1.37E-07 4.55E-07 7.41E-08 1.76E-08
+
Cr-136 0.00E+00 0.00E+00 0.00E+00 4.31E-04 1.08E-05 4.31E-04 er-89 9.59E-04 1.74E-04 0.00E+00 9.59E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-55 1.47E-02 3.60E-03 0.00E+00 1.47E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals 1.60E-01 3.68E-03 2.19E-05 1.60E-01 1.73E-01 4.16E-04 0.00E+00 1.73E-01 Xe-133 1.3SE-02 5.45E-05 0.00E+00 1.3SE-02 8.98E-03 5.77E-05 0.00E+00 8.98E-03 Kr-33 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133m 2.05E-04 1.73E-05 0.00E+00 2.05E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xc-135 1.09E-02 2.33E-05 0.00E+00 1.09E-02 4.52E-03 1.39E-05 0.00E+00 4.52E-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 g
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 Xe-123 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-131m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.35E-03 8.77E-05 0.00E+00 1.35E-03 Tot als 2.48E-02 6.17E-05 0.00E+00 2.4SE-02 1.4SE-02 1.06E-04 0.00E+00 1.4SE-02 Ho LLD requires ent in Tech Spec
+
1R
. =
- - _ - = _ _ _
FIGURE 1-5b l
Liquid Redwaste Data Compilation for Reg. Guid 1.21 Report E.
I. Hatch Huclear Pl ant UNIT 2
(
Total Activity (Curtes)
Quarter 1,
1982 Quarter 2, 1982 Batches 1 thru 227 Batches 228 thru 483 Hame Measured Error High LLDs Tot al Measured Error High LLDs Tot si j
Cc-144 1.06E-05 1.66E-05 0.00E+00 1.06E-05 2.06E-05 2.00E-05 0.00E+00 2.06E-05 Tc-99m 2.67E-05 1.77E-06 2.67E-05 9.86E-05 3.11E-06 9.S6E-05 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hp-239 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4
0.00E+00 Cr-51 3.58E-03 5.84E-05 3.58E-03 1.49E-03 4.90E-05 1.49E-03 1-131 4.22E-05 1.96E-06 0.00E+00 4.22E-05 4.03E-04 8.01E-06 0.00E+00 4.03E-04 2n-69m 0.00E+00 0.00E+00 0.00E+00 1.55E-06 3.52E-07
+
1.55E-06 H-187 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F-18 9.51E-04 1.01E-05 9.51E-04 4.58E-04 6.96E-06
+
4.58E-04 1-133 3.10E-05 2.20E-06 3.10E-05 7.68E-05 3.87E-06 7.68E-05 Ba-140 5.59E-06 1.72E-06 5.59E-06 0.00E+00 0.00E+00 0.00E+00 As-76 4.20E-05 3.52E-06 4.20E-05 5.06E-04 1.20E-05 5.06E-04 Cs-134 3.78E-03 2.07E-05 0.00E+00 3.78E-03 8.07E-03 2.2?E-05 0.00E+00 8.07E-03 1
Cs-137 4.95E-03 2.43E-05 0.00E+00 4.95E-03 1.33E-02 3.07E-05 0.00E+00 1.33E-02 I
Ho-99 1.40E-05 3.73E-06 0.00E+00 1.40E-05 4.41E-05 2.04E-05 0.00E+00 4.41E-05 2r-97 4.08E-06 1.60E-06 4.08E-06 3.56E-06 1.23E-06 3.56E-06 2r-95 5.10E-04 1.28E-05 5.10E-04 9.78E-05 8.42E-06 9.78E-05 Hb-95 7.37E-04 1.11E-05 7.37E-04 2.46E-04 7.37E-06 2.46E-04 I-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
+
0.00E+00 Co-58 2.41E-04 7.59E-06 0.00E+00 2.41E-04 2.48E-04 8.27E-06 0.00E+00 2.48E-04 Hn-54 5.13E-04 1.14E-05 0.00E+00 5.13E-04 4.87E-04 1.05E-05 0.00E+00 4.87E-04
[
Ag-110m 2.21E-05 2.72E-06 2.21E-05 2.92E-06 9.54E-07 2.92E-06 Zn-65 5.52E-03 4.74E-05 0.00E+00 5.52E-03 1.32E-02 6.44E-05 0.00E+00 1.32E-02 1-135 8.86E-06 2.19E-06 8.86E-06 0.00E+00 0.00E+00 0.00E+00 Fe-59 2.62E-05 3.85E-06 0.00E+00 2.62E-05 3.88E-05 6.01E-06 0.00E+00 3.8SE-05 Co-60 2.37E-03 2.19E-05 0.00E+00 2.37E-03 3.52E-03 2.50E-05 0.00E+00 3.52E-03 Cu-64 5.65E-04 1.26E-04 5.65E-04 3.70E-03 S.35E-04 3.70E-03 Ha-24 1.27E-03 1.15E-05 1.27E-03 2.05E-03 1.27E-05 2.05E-03 La-140 0.00E+00 0.00E+00 0.00E+00 2.84E-06 7.13E-07 4
2.84E-06 0.00E+00 Hn-56 1.12E-05 3.32E-06 1.12E-05 0.00E+00 0.00E+00
+
Cs-138 2.63E-06 4.78E-07 2.63E-06 9.47E-06 7.90E-07 9.47E-06 Hi-65 3.73E-06 1.18E-06 3.73E-06 3.85E-06 1.58E-06 3.85E-06 Hb-97 1.59E-07 1.61E-OS 1.59E-07 0.00E+00 0.00E+00 0.00E+00 Cs-136 0.00E+00 0.00E+00 0.00E+00 4.14E-07 7.55E-07
+
4.14E-07 Sb-125 0.00E+00 0.00E+00 0.00E+00 4.46E-05 4.87E-06
+
4.46E-05 Sr-89 1.45E-04 7.27E-05 0.00E+00 1.45E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals 2.54E-02 1.72E-04 0.00E+00 2.54E-02 4.81E-02 3.50E-04 0.00E+00 4.81E-02
(
Xe-133 2.83E-03 2.78E-05 0.00E+00 2.83E-03 6.53E-04 1.22E-05 0.00E+00 6.53E-04 Kr-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
(
Xe-135 1.24E-03 9.40E-06 0.00E+00 1.24E-03 3.97E-04 5.57E-06 0.00E+00 3.9?E-04 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 9.18E-06 1.51E-06 0.00E+00 9.18E-06 X=-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot al s 4.07E-03 2.94E-05 0.00E+00 4.07E-03 1.06E-03 1.35E-05 0.00E+00 1.06E-03 19 L
_ ~ _ _ _ _.
_ ~..
i TABLE 1-lh E.
I. Hatch Nuclear Plant UNIT 1 I
EFFLUEllT AllD WASTE DISPOSAL SENIAHilUAL REPORT 1982 i
LIQUID EFFLUENTS-SUMMAT10tl 0F ALL RELEASES Unit Quarter Quarter Est Tot al 1
2 Error A.
Fi ssion & act ivat ion products 1.
Total release (not including H3, gases,alphs)
Ci 1.60E-01 1.73E-01 4.71E+01 2.
Average diluted concentration during period uCi /rn1 9.20E-08 5.94E-08 3.
Percent of applicable 1imit 7.44E-01 3.23E+00 1:. Tri t t ura I
1.
Tot al release Ci 2.16E+00 1.09E+01 3.21E+011 2.
Aver age dilut ed concentrat ion during period uC i /rn l 1.24E-06 3.74E-06 1
3.
Perccnt of applieable 1 i rn i t 4.15E-02 1.25E-01 C.
Dissolved and entrained gases
(,
1.
Tot al release Ci 2.48E-02 1.4SE-02 1.00E+02l 2.
Average diluted concentration during period uCi/mi 1.43E-08 5.09E-09 3.
Percent of appl i e ab i c 1 i en i t 3.58E-02 1.27E-02 D.
Gross alpha radioactivity l
1.
Total release l
Ci l 1.20'E-04l 4.50E-04l 1.20E+02l l
1 f
- 3. Volurr.e of waste < prior to dilution)l 1iters l 8.72E+06l 1.20E+07l 1.00E+011 1
lF. Vo l u rne of dilution water used l liters l 1.73E+09l 2.90E+09l 1.60E+02{
l l
I 20 t
TABLE 1-lb E.
I. Hatch fluclear Plant UllIT 2
'(
EFFLUEllT AllD LIASTE DISPOS AL SEMI AllllUAL REPORT 1982 LIQUID EFFLUEllTS-SullMATIOli 0F ALL RELEASES Unit Quarter Quarter Est Tot al 1
2 Error A.
Fission & act ivat ion product s 1.
Tot al re l eas e (not including H3, g as e s. al pha)
Ci 2.54E-02 4.81E-02 4.65E+01 2.
Average dilut e d concentrat ion during period uCi/mi 1.55E-OS 1.66E-08 3.
Percent or applichble limit 6.73E-02 1.16E-01 D.
Tritiuru
__1.
TotL1 re l e as e Ci 2.07E+00 5.74E+00 3.11E+01l 2.
Ave F age di l ut e d c onc ent rat i on dur i ng period uC i /ta l 1.26E-06 1.98E-06 3.
Pe rc ent of applichble l i rn i t 4.20E-02 6.61E-02 C.
Dissolved and ent rained gases 1.
Total rel e are Ci 4.07E-03 1.06E-0?
1.12E+02i
(
2.
nverage diluted concentration during period ut i /rn l 2.49E-09 3.66E-10 3.
Percent of appl i c ab l e l i rn i t 6.22E-03 9.15E-04 D.
Gross al pha radi oac t i vi t sj l
1.
Tot al release l
Ci l 2.04E-05l 2.51E-04l 1.20E+02l
@ Volutae of waste (prior to dilution)1 1iters l 7.27E+06l S.23E+06l 1.00E+01l IF. Vo l un.e of dilution w at er used l liters 1 1.63E+09l 2.89E+091 1.60E+02l I
21
TABLE 1-2a E.
I. Hatch Nuclear Plant UHIT 1
(
EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1982 LIQUID EFFLUENTS l
CONT!HUOUS HODE EATCH MODE Huclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2 Cc-144 Ci 6.09E-04 4.55E-03 Tc-99m Ci 4.59E-05 1.69E-02 Ce-141 Ci 0.00E+00 1.03E-04 j
HP-239 Ci 0.00E+00 0.00E+00 Cr-51 Ci 2.91E-03 2.97E-03 1-131 Ci 1.77E-03 2.61E-02 i
Zn-69m Ci 0.00E+00 0.00E+00 l
W-187 Ci 0.00E+00 0.00E+00 F-18 Ci 7.54E-04 2.41E-04 1-133 Ci 8.72E-05 1.22E-03 Ba-140 Ci 0.00E+00 0.00E+00 As-76 Ci 5.56E-06 2.81E-04
~~~
Cs-134 Ci 3.06E-02 2.38E-02 Cs-137 Ci 4.36E-02 3.59E-02 Ho-99 Ci 7.74E-05 1.43E-02 Zr-97 Ci 0.00E+00
- 7. 89 E-0,6 Zr-95 Ci 5.71E-04 1.86E-04 Hb-95 Ci 1.10E-03 2.30E-04 l
1-132 Ci 0.00E+00 3.23E-06 Co-58 Ci 1.09E-03 6.55E-04 Mn-54 Ci 3.71E-03 1.91E-03 Ag-110m Ci O.00E+00 5.54E-05 I
Zn-65 Ci 3.23E-02 2.82E-02 1-135 Ci 0.00E+00 7.45E-05 Fe-59 Ci 1.95E-04 5.67E-05 Co-60 C1 1.39E-02 9.67E-03 i
Cu-64 Ct 9.86E-03 3.4SE-03 Na-24 Ci 6.77E-04 1.81E-03 i
La-140 Ci 6.82E-05 1.50E-04 Mn-56 Ci 0.00E+00 0.00E+00 i
Hb-97 Ci 3.18E-05 0.00E400 Cs-138 Ci 4.55E-07 7.41E-05 Cs-136 Ci 0.00E+00 4.31E-04 Sr-89 Ci 9.59E-04 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 Fe-55 C1 1.47E-02 0.00E+00 P-32 Ct 0.00E+00 0.00E+0C i
l Tot al for period ( above )
l Ci l
l l 1.60E-011 1.73E-011 i
Xe-133 Ci 1.3SE-02 8.96E-03 i
Vr-SS Ci 0.00E+00 0.00E+00
(
Xe-133m Ci 2.05E-04 0.00E+00 Xe-135 C1 1.09E-02 4.52E-03 Fr-85m Ci 0.00E+00 0.00E+00_
Fr-87 Ct 0.00E+00 0.00E+00 X4-138 Ci 0.00E+00 0.00E+00 j
Xe-131m Ci 0.00E+00 1.35E-03l
??
i TABLE 1-2b i
E. I. Hatch Nucl ear Pl ant UNIT 2 I.
EFFLUEHT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1982 LIQUID EFFLUENTS COHT!HUOUS MODE EATCH NODE l
Huclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2 Ce-144 C1 1.06E-05 2.06E-05 Tc-99m C1 2.67E-05 9.86E-0'5" Ce-141 Ci 0.00E+00 0.00E+00
[
Np-239 C1 0.00E+00 0.00E+00 1
Cr-51 Ci 3.58E-03 1.49E-03 I-131 Ci 4.22E-05 4.03E-04 Zn-69m Ci O.00E+00 1.55E-06 i
U-187 Ci 0.00E+00 0.00E+00 F-18 Ci 9.51E-04 4.58E-04 I-133 C1 3.10E-05 7.68E-05 t
4 I:h-140 Ci 5.59E-06 0.00E+00 t
As-76 C1 4.20E-05 5.06E-04 l
3.78E-03 8.07E-03 Cs-134 Ci Cs-137 Ci 4.95E-03 1.33E-02 4
!!o-99 Ci 1.40E-05 4.41E-05 Zr-97 Ct 4.08E-06 3.5EE-06 l
Zr-95 Ci 5.10E-04 9.78E-05 I
Hb-95 Ci 7.37E-04 2.46E-04
{
I-132 C1 0.00E+00 0.00E+00 Co-58 Ci 2.41E-04 2.48E-04 Mn-54 Ci 5.13E-04 4.87E-04 80- 1 10 rn Ci 2.21E-Oi 2.92E-06 3
2n-65 Ci 5.5)E-03 1.32E-02 1-135 Ci 8.86E-06 0.00E+00 Fe-59 C1 2.62E-05 3.88E-05 t
i Co-60 C1 2.37E-03 3.52E-03 l
Cu-64 Ci 5.65E-04 3.70E-03 Ha-24 Ci 1.27E-03 2.05E-03 I
La-140 Ci 0.00E+00 2.84E-06 Mn-56 C1 1.12E-05 0.00E+00 2.63E-06 9.47E-06 Cs-138 Ci 3.73E-06 3.85E-06 Hi-65 Ct s
Nb-97 Ct 1.59E-07 0.00E+00 j
Cs-136 Ci 0.00E+00 4.14E-07 i
Sb-125 Ci 0.00E+00 4.46E-05 Sr-89 C1 1.45E-04 0.00E+00 Sr-90 C1 0.00E+00 0.00E+00 Fe-55 Ci 0.00E+00 0.00E+00 P-32 Ci 0.00E+00 0.00E+00 l
Total t' o r perted (above) l Ci l
l l 2.54E-02l 4.81E-02l
(
Xe-133 Ci 2.83E-03 6.53E-04 Kr-88 Ci 0.00E+00 0.00E+00 Xe-133m Ci 0.00E+00 0.00E+00 Xe-135 C1 1.24E-03 3.97E-04 F r-85 ta Ci 0.00E+00 0.00E+00 Kr-87 Ct t
0.00E+00 9.18E-06 Me-138 Ci
(([t 0.00E+00, 0.00E+00 23
2 GASEOUS EFFLUENTS 2.1. REGULATORY LIMITS a.
(1)
The release rate limit of noble gases from the site shall be:
(
_~
E Qin
,,,1.9 E6+ 1.0 EB
+Qv 11 E6
+ 44 EB I1 i
r 1
+n where Os =
Total release rate from main stack for both Units in Ci/sec (elevated release)
Total release rate from' vent in Ci/sec (ground release)
Oy
=
i=
The individual nuclide n = total nuclides 56
The average gamma energy per disintegration The average beta energy per disintegration 53
(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.
6 1.0 X 105 Ops + 1.5 X 10 gpy 1
Total release rate from the main stack Where O
=
for both Units in Ci/sec (as el'evated p3 release) 4(
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:
B
+Qv
_66 56
+ 140 E i
3, 51 I
Qin 12 E6 + 3.0 E 1
+n (2)
The average release rate of noble gases during any 12 consecutive months shall be:
B i
130 E 6+ 27 0 E 6.1 E ]
+ Q v B
1 1 E
Qis 24 56 +
l i
+n (3)
The average release rate of all radio iodines and radioactive materials in particulate form from the site with half lives greater than eight days during any calendar quarter shall be:
7 1.3 X 106 Ops + 1.9 X 10 Opv i 1 The average release rate of all radio iodines and (4) radioactive materials in particulate form from the site
(
24
with half lives greater than eight days during any period'of 12 consecutive months shall be:
2.6 X 106 Ops + 3.7 x 107 Opv 5 1 k.
(5)
The amount of Iodine - 131 re.1. eased 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 listed below occur, the licensee shall make an investigation to identify the causes of the release
- rates, define and initiate a program of action to reduce the release rates to design objective levels listed in subsection 2.1 of the HNP-ETS and report these actions to the Commission within 30 days from the 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 + 54 0 En>1 I
Ois 47 E6 + 12 E3
+ Oiv 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:
5.0 X 106 Ops + 7. 2 X. -102 Opv >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 siall 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
- 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.
l
'25
explosive gas mixtures of hydrogen and h.
(1)
Potentially 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 I
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%
concentration by volume.
If at any time during reactor power operation, it is determined that the hydrogen concentration limit is being exceeded, action shall be initiated within 4
hours to return the hydrogen concentration to within the prescribed limit.
If the hydrogen concentration is not reduced to less than 4%
by volume within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the of fgas system flow shall
(
be stopped.
(3)
The installed hydrogen monitoring systems shall have daily sensor
- checks, monthly functional checks, and quarterly calibrations.
The portable hydrogen gas analyzer shall be calibrated immediately prior to installation and shall be subject to daily sensor
- checks, monthly functional
- checks, and quarterly calibrations until removed from service.
i.
An unplanned or uncontrolled of fsite release of radioactive materials in gaseous effluents in excess of 150 Ci. of noble gas or 0.02 Ci. of radioiodines in gaseous form shall be reported to the NRC within 30 days in accordance with section 5.7.2.
2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY
. Waste gas release at Hatch is confined to four paths.
Each of these four paths is continuously monitored for gaseous concentration and each has an integrating type collection device which concentrates particulates 'and iodine for each seven day period (Procedures are such that shorter collection times are used where applicable to Technical Specification requirements).
26
Each of these cont'inuous samplers has a flow controller which maintains sample flow within about a 10 percent range over each seven day collection period.
The of fgas 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 The recombiner building measured during preoperational testing).
at flow on Unit One is conservatively assumed to be constant 500 CFM.
In addition to the gaseous, particulate, and iodine vent 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 from the four vents is compiled and as such is designed release the 6-month report as the requirements for preparation of specified in Regulatory Guide 1.21.
Unit one and two releases to meet were calculated together because the Tech. Specifications for the two reactors are identical in this respect.
The methods for compilation of the quarterly releases are as follows:
1.
FISSION AND ACTIVATION GAS The total curie release is determined from the continuously reading gaseous monitors in addition to the vent flow recorders.
Activity monitors and vent flow rate readings are read hourly and input into the computer.
From these readings a daily release is calculated.
The calibration factors for the monitors are determined from the monthly
(
isotopics when sufficient activity allows or by injection of a known amount of off-gas into the sample chambers.
The total curie release is calculated by the computer for each of the individual nuclides released.
This number is multiplied by the average energy per disintigration (E
E) along with the coefficients in the release limit formula in our Environmental Technical Specifications.
All B
of the nuclides are summed and stored in their respective Then the computer data files until the end of the quarter.
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 computer system the aid of the counting room calculator total is prepared from the weekly quarterly and a
The percent Technical Specification for I-131 on summaries.
quarterly Technical Specification
{
Table 2-1 is based on the limit.
77 1
J
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 counti.ng room calculator - computer.
After each calendar month the particulate filters from each vent are combined, fused, and strontium separation is made.
Since sample flows and vent flows are almost constant over each monthly period the filters from each vent.can be dissolved together.
Decay corrections are made back to the middle of the quarterly collection period.
Again the counting room calculator computer is used to aid in the calculation of the Sr-89, 90 release.
Where significant strontium activity is not detected MDAs are calculated.
The percent of Technical Specification was calculated using quarterly average equation.
4.
GROSS ALPHA RELEASE The gross 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 colc) trap immersed in a liquid nitrogen or an acetone and ice mixture.
The grams of water vapor / cubic foot gas is measured upstream of the cold trap in order to alleviate the difficulties in determining water vapor collection efficiencies.
The tritium samples are analyzed by an independent laboratory.
From the uCi/ml tritium concentration, the grams water /ft3, and the vent flow rates, the monthly tritium release is calculated for I
each vent, and the quarterly summary can be generated from the monthly calculation forms.
Hatch has attempted to maintain all calculated MDAs as low as possible by counting samples longer than what would be normally practical.
For example at this time all weekly particulate and iodine counting times are 3000 sec and strontium separations are counted for 100 minutes.
l l
Regulatory Guide 1.21 requires that estimated total error in l
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 l
release, and total tritium release.
28
"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 was;te."
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 87.25% of this release was from the main stack the MDA release values of the ground level release points were small when compared to the total release.
1 Monitor Error in Calibration 50%
Vent Flow Rate 10%
Non-Steady Release Rate 20%
80%
2.
1-131 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%
l Countng Equipment Calibration 10%
Vent Flow Rates 10%
29
Vent Sample Flow Rates 10%
Non-Steady Release Rates 10%
100%
4.
Total Tritium Release was dominated by the reactor building j
vent tritium release, hence, the larger statistical errors
\\
of the off-gas vent and recombiner building vent tritium releases do not affect the error in the total tritium release:
Water Vapor in Sample Stream Determination 20%
Vent Flow Rates 10%
Counting Calibration and Statistics 10%
~
50%
Non-Steady Release 90%
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 WASTE 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 w !.th 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 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.
i
(
30
TABLE 2-la UNIT 1 EFFLUEllT AND WASTE DISPOSAL SENIAHl1URL REPORT 1982 GASEOUS EFFLUENTS-SUMf1ATIOH OF ALL RELEASES
(
A Unit Quarter Quarter Est Total E.
I.
Hat ch Nucle ar Power Plant UNIT 1 1
2 Error t A.
Fis s ion & act ivat ion gas es 1.
Total releaze C1 3.27E+02 5.61E+02 8.00E+01l 2.
Ave e age re 1 e ase r at e f or period uC1/sec 4.16E+01 7.13E+01
[3. % of Tec hni c al specificatton l i ra i t 6.48E-02 6.46E-02 E.
Iodines 1.
Tot al 1odine-131 Ci 1.15E-03 1.03E-01 1.10E+02]
]
Average release rat e for period uCt/sec 1.46E-04 1.31E-02 3.
% of Technical specificatton 1 1 :n i t 5.76E-02 5.14E+00 C.
Particulates
- 1. P art i c ul ht es wi t h half-lives >8 davs Ci 1.62E-03 9.23E-04 1.00E+02l
~ ~2.
Average release rate for period ECi/sec 2.07E-04 1.17E-04
~3.
- . of Te c hnic al specification 1 1 ta i t 2.33E-01 1.54E-01 4.
Gross sipha radioactivitv Ci 2.81E-06 1.11E-05 D.
T r i t i ura 4
1.
Tot al release Ci 3.66E-01 3.19E-01 9.00E401l 2.
Averaqe release rate for period uCi/sec 4.66E-02 4.06E-02
{
3.
- . of Technical spec i fi c at i on l i r.. i t 5.63E-01 2.28E+00 i
i t
I l
(
31
.e.,.-----~4---,,.--2,
--r--,,
y_
.v.r
-.., - - ~ -
,-.-----,r-y
-r-
TABLE 2-lb UNIT 2 4
EFFLUEHT AND WASTE DISPOSAL SEMIAHUUAL REPORT 1o32
(
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Tots)
E.
I. Hat ch Huc le sr Power P l ant UNIT 2 1
2 Error %
A.
Fission L act ivat ion gases Ci 1.85E+00 1.72E-01 8.00E+01l t
l 1.
Total release
- 2. Average rel e as e rat e ('or period uCi/see 2.35E-01 2.19E-02
- 3. % of Technical s pec i f i c at i-on limit 1.20E-03 1.29E-05 i
B.
Iodines Ci 2.58E-05 2.10E-03 1.10E+02l 1.
Tot al iodine-131 2.
Average release rate for period uCi/sec 3.2SE-06 2.67E-04
]
3.
. of Techni c al spec i f i c at i on l i ra i t 1.29E-03 1.05E-01 C.
Part i c u l at e s 1.
Part i c ul at es. wi t h hal f-l i ve s >S davs Ci 1.10E-04 2.77E-05 1.00E+02l 2.
Average release r at e for period uCi/sec 1.40E-05 3.52E-06
- 3. % of T ec hni c al s pec i fi c at i on limit 2.59E-02 6.66E-03 Ci 6.96E-07 2.05E-06 4.
Gross al pha radi oac t ivi to J
D.
Tritium Ci 8.96E-01 8.44E-02 9.00E+01l 1.
Tot al release 2.
Average rele ase rate for period uCi/sec 1.14E-01 1.07E-02
- 3. % of Tec hni c al spec i f i c at i on limit 3
8.64E-01 8.32E-02 4
I i
i l
1
(
32
TABt.E 2-Ic SITE EFFLUENT AND WASTE DISPOSAL set 11 AHilUAL REPORT 1982 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 1
Unit Quarter Quarter Est Total E.
I.
Hatch Nuclear Pouer Plant SITE 1
2 Error t
A.
Fission & act ivat ion gases 1.
Total release Ci 3.29E+02 5.61E+02 8.00E+01l 2.
Average rele ase rate for period uCi/sec 4.19E+01 7.14E+01 3.
% of Technical spec i fi c at i on l i ra i t 6.61E-02 6.46E-02 E.
Iodines 1.
Total iodine-131 Ci 1.18E-03 1.05E-01 1.10E+02l 2.
Average release rate for period uCi/sec 1.50E-04 1.34E-02 i
3.
% of Techntca) s pec i fi c at i on 1 i ra i t 2.94E-02 2.62E+00 1
C.
Particulates l
1.
Part i c ul at es. wi t h hal f-l i ves >8 davs Ci 1.74E-03 9.51E-04 1.00E+02l 2.
Avernge reicase rate for period uCi/sec 2.21E-04 1.21E-04
~. *. o f Tec hni c al spec i f i c at i on l i ra i t 2.59E-01 1.61E-01 3
4.
Gross alpha radioactivito Ci 3.50E-06 1.32E-05 D.
Tri t t urn 1.
Tot al re l e as e Ci 1.26E+00 4.03E-01 9.00E+01]
(
2.
Average release rate for period uCi/sec 1.61E-01 5.13E-02 3.
- of Technical spec i fi c at i on 1 i ta i t 1.43E+00 2.36E+00 3
i l
9 1
\\
33
TABLE 2-2a UNIT 1 E.
I. Hatch Nucitar Pouer Plant UNIT 1
(
EFFLUENT AND HASTE DISPOSAL SEMIAHHUAL REPORT 1982 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE EATCH MODE
.Huclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2 1.
Fission gases Xe-133 Ci 5.SSE+01 1.06E+02 0.00E+00 0.00E+00 Xc-131M Ci 8.42E+00 9.73E+01 0.00E+00 0.00E+00 Kr-98 Ci 2.02E+01 5.71E+01 0.00E+00 0.00E+00 Xc-133M Ci 2.76E+00 3.00E+01 0.00E+00 0.00E+00 M+-135 Ci 2.59E+01 9.46E+00 0.00E+00 0.00E+00
,____ Vr-85M Ci 3.50E+01 1.35E+02 0.00E+00 0.00E+00 1-131 Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00
~
Kr-87 C1 1.49E+01 5.70E+00 0.00E+00 0.00E+00 Xe - 138 Ci 3.47E+01 1.33E+01 0.00E+00 0.00E+00 t
Me-137 Ci 7.96E+00 0.00E+00 0.00E+00 0.00E+00 H-13 Ci 1.37E+01 3.19E+01 0.00E+00 0.00E+00 Pr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Me-135M Ci 1.87E+01 1.36E+01 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Er-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 l
Ar-41 Ci 1.95E+01 1.49E+01 0.00E+00 0.00E+00 Total for period Ci 2.61E+02 5.15E+02 0.00E+00 0.00E+00 2.
Iodines l-131 Ci 4.41E-04 8.74E-07 0.00E+00 0.00E+00 1-133 Ci 1.44E-03 1.20E-02 0.00E+00 0.00E+00 1-135 Ci 7.97E-04 3.42E-04 0.00E+00 0.00E+00 Tot al for period Ci 2.68E-03 9.97E-02 0.00E+00 0.00E+00 3.
Part i cul ates l
Sr-89 Ci 1.87E-04 5.45E-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 8.64E-07 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 3.95E-06 d.30E-05 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ea-140 Ci 1.4SE-04 5.52E-05 0.00E+00 0.00E+00 C5-134 Ci 6.44E-07 4.42E-06 0.00E+00 0.00E+00 C2-137 Ci 2.26E-06 7.14E-06 0.00E+00 0.00E+00
~~
CE-144 Ci 3.58E-07 3.31E-06 0.00F+00 0.00E+00 l
Zr-95 Ci 0.00E+00 5.02E-07 0.00E+00 0.00E+00 Hb-95 Ci 2.32E-06 0.00E+00 0.00E+00 0.00E+00 Co-58 ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 1
0.00E+00 4.06E-07 0.00E+00 0.00E+00 Fe-59
- i 6.5SE-09 6.07:-08 0.00E+00 0.00E+00 Co-60
- i 2.11E-07 1.S:E-06 0.00E+00 0.00E+00 1a-140 31 3.61E-04 1.2"E-o4 0.00E+00 0.00E+00 Tot al for period Oi 7.OSE-04 3.0 E-4 0.00E+00 0.00E+00 nn
.-- ~. - _ _. -,
_.e.,
TABLE 2-2b UNIT 2 E.
I.
Hatch Huclear Pouer Plant UNIT 2 EFFLUENT AND HASTE DISPOSAL SEMIAHHUAL REPORT 1982
'[
GASEOUS EFFLUENTS-ELEVATED RELEASE COHTINUOUS MODE EATCH t10DE Huclidi2 Re l e as e d Unit Quarter Quarter Quarter Quarter 1
2 1
2 1.
Fis sion gates Xe-133 Ci 2.61E-01 3.56E-02 0.00E+00 0.00E+00 Xe-131M Ci 3.73E-02 3.25E-02 0.00E+00 0.00E+00 1:r-SS Ci 8.96E-02 1.91E-02 0.00E+00 0.00E+00 Xe-133f1 Ci 1.22E-02 1.00E-02 0.00E+00 0.00E+00 Xe-135 Ci 1.15E-01 3.16E-03 0.00E+00 0.00E+00 Fr-SSM Ci 1.55E-01 4.52E-02 0.00E+00 0.00E+00 I-1 31 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fr-87 Ci 6.60E-02 1.90E-03 0.00E+00 0.00E+00
/e-138 Ci 1.54E-01 4.44E-03 0.00E+00 0.00E+00 k-13?
Ci 3.53E-02 0.00E+00 0.00E+00 0.00E+00 H-13 Ci 6.09E-02 1.06E-02 0.00E+00 0.00E+00 tr-05 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mc-135M Ci 8.28E-02 4.53E-03 0.00E+00 0.00E+00 1-13?
Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.r -09 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 8.67E-02 4.98E-03 0.00E+00 0.00E+00 Tot al for period Ci 1.16E+00 1.72E-01 0.00E+00 0.00E+00 2.
Iodines 1-131 Ci 1.95E-06 2.92E-05 0.00E+00 0.00E+00 I-133 Ci 6.39E-06 4.01E-06 0.00E+00 0.00E+00 1-135 Ci 3.54E-06 1.14E-07 0.00E+00 0.00E+00 Total for period Ci 1.19E-05 3.33E-05 0.OOE+00 0.00E+00 3.
Particulates Sr-89 Ci 8.31E-07 1.82E-OS 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 f
Cr-51 Ci 3.84E-09 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 1.75E-08 1.77E-08 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 6.59E-07 1.84E-08 0.00E+00 0.00E+00 Cs-134 Ci 2.86E-09 1.4SE-09 0.00E+00 0.00E+00 C1-137 Ci 1.00E-08 2.39E-09 0.00E+00 0.00E+00 Ce-144 C1
-1.59E-09 1.11E-09 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 1.6SE-10 0.00E+00 0.00E+00 Hb-95 Ci 1.03E-08 0.00E+00 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
(.
Mn-54 Ci
.00E+00 1.36E-10 0.00E+00 0.00E+00 Fe-59 Ci
.92E-11 2.03E-11 0.00E+00 0.00E+00 Co-60 Ci
._3 F E - 10 6.03E-10 0.00E+00 0.00E+00 La-140 Ci
.p~E-06 4.15E-08 0.00E+00 0.00E+00 Tot s) for period Ci
.1 E-06 1.02E-07 0.00E+00 0.00E+00 3!
TABLE 2-2c SITE I
E.
It Hatch Huclear Pouer Plant SITE
(
EFFLUEHT AND HASTE DISPOSAL SEMIAHHUAL REPORT 1932 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTIMUOUS MODE EATCH MODE Huclides Relehzed Unit Quarter Quarter Quarter.
Ouhrter 1
2 1
2 1.
Fission gases Xe-13?
Ci 5.90E+01 1.06E+02 0.00E+00 0.00E+00 Me-131M Ci S.45E+00 9.73E+01 0.00E+00 0.00E+00 Kr-SS Ci 2.03E+01 5.71E+01 0.00E+00 0.00E+00 Xe-133M Ci 2.77E+00 3.00E+01 0.00E+00 0.00E+00 Xe-135 Ci 2.61E+01 9.47E+00 0.00E+00 0.00E+00 Vr-85M Ci 3.52E+01 1.35E+02 0.00E+00 0.00E+00 1-131 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fr-87 C1 1.49E+01 5.70E+00 0.00E+00 0.00E+00 Xe-138 Ci 3.49E+01 1.33E+01 0.00E+00 0.00E+00 Me-137 Ci 8.00E+00 0.00E+00 0.00E+00 0.00E+00 H-10 Ci 1.38E+01 3.19E+01 0.00E+00 0.00E+00 Kr-85 Ci O.00E+00 0.00E+00 0.00E+00 0.00E+00 Xc-135M Ci 1.87E+01 1.36E+01 0.00E+00 0.00E+00 1-133 Cl 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
, f.r - 41 Ci 1.96E+01 1.49E+01 0.00E+00 0.00E+00 Tot al for period Ci i 2.62E+02 5.15E+02 0.00E+00 0.00E+00 2.
Iodines 1-131 Ci 4.42E-04 8.74E-02 0.00E+00 0.00E+00 1-133 Ci 1.45E-03 1.2DE-02 0.00E+00 0.00E+00 I-135 Ci 8.01E-04 3.42E-04 0.00E+00 0.00E+00 Total for period Ci 2.69E-03 9.97E-02 0.00E+00 0.00E+00 l
3.
Part i c ul at es Sr-89 Ci 1.88E-04 5.45E-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 8.68E-07 0.00E+00 0.00E+00 0.00E+00 l
I-131 Ci 3.96E-06 5.30E-05 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sa-140 Ci 1.49E-04 5.52E-05 0.00E+00 0.00E+00 Cs-134 Ci 6.47E-07 4.42E-06 0.00E+00 0.00E+00 Cs-137 Ci 2.27E-06 7.15E-06 0.00E+00 0.00E+00 Cc-144 Ci 3.60E-07 3.31E-06 0.00E+00 0.00E+00 2r-95 Ci 0.00E+00 5.00E-07 0.00E+00 0.00E+00 Nb-95 Ci 2.33E-06 0.00E+00 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
Hn-54 Ci 0.00E+00 4.06E-07 0.00E+00 0.00E+00 Fe-59 Ci 6.61E-09 6.0SE-08 0.00E+00 0.00E+00 1
Co-60 Ci 2.12E-07 1.81E-06 0.00E+00 0.00E+00 La-140 Ci 3.63E-04 1.24E-04 0.00E+00 0.00E+00 Total for period Ci 7.11E-04 3.05E-04 0.00E+00 0.00E+00 36
TABLE 2-3a UNIT 1 E.
I. Hatch Nuclear Power Plant UNIT 1 EFFLUENT AllD WASTE DISPOSAL SENIAHHUAL REPORT 1982 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE C0tiTINUOUS 110DE EATCH MODE liuc l i de s Released Unit Quarter Quarter
- Quarter, Quarter 1
2 1
2 1.
Fission gases Xe-133 Ci 1.37E+01 1.10E+01 0.00E+00 0.00E+00 Xe-131H Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l'r-88 Ci 0.00E+00 8.48E-03 0.00E+00 0.00E+00 Xe-133M Ci 3.13E-01 6.47E-02 0.00E+00 0.00E+00 Xe-135 Ci 2.20E+01 1.77E+01 0.00E+00 0.00E+00 i:r-85M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 0.00E+00' O.00E+00 0.00E+00 1:r-87 Ci 1.37E-03 1.66E-02 0.00E+00 0.00E+00 he-138 Ci 2.27E-02 4.68E-02 0.00E+00 0.00E+00 Xc-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N-13 Ci 3.28E-03 7.06E-03 0.00E+00 0.00E+00 f.r-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 de-135H Ci 3.05E+0!
1.70E+01 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I'r-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 4.29E-01 0.00E+00 0.00E+00 0.00E+00 fir-41 Ci 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Tot al for period Ci 6.6?E+01 4.59E+01 0.00E+00 0.00E+00 2.
Iodines 1-13!
Ci 6.00E-04 1.53E-02 0.00E+00 0.00E+00 1-133 Ci 1.12E-03 3.19E-03 0.00E+00 0.00E+00 I-135 Ci 1.09E-03 9.61E-04 0.00E+00 0.00E+00 Total for period Ci 2.81E-03 1.95E-02 0.00E+00 0.00E+00 3.
Part i c u l at es Sr-89 C1 2.54E-06 1.46E-05 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 3.89E-10 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 3.37E-04 9.66E-05 0.00E+00 0.00E+00 1-131 Ci 1.07E-04 1.26E-04 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ea-140 Ci 4.10E-05 3.33E-05 0.00E+00 0.00E+00 C5-134 Ci 6.49E-05 9.02E-05 0.00E+00 0.00E+00 C5-137 Ci 1.0SE-04 1.50E-04 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 4.40E-OS 0.00E+00 0.00E+00 2r-95 Ci 1.14E-05 S.47E-10 0.00E+00 0.00E+00 Hb-95 Ci 4.59E-05 0.00E+00 0.00E+00 0.00E+00 Co-58 Ci 3.97E-05 1.24E-05 0.00E+00 0.00E+00
(
Mn-54 Ci 2.56E-05 1.45E-06 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 6.56E-05 3.26E-05 0.00E+00 0.00E+00 L a-140 Ci 6.86E-05 6.14E-05 0.00E+00 0.00E+00 Totsi for neriod Ci 9.1?E-04 6.18E-04 0.00E+00 0.00E+00 37
_ -__]
TABLE 2-3b UNIT 2 E.
I. Hatch Huclear Pouer Plant UNIT 2 EFFLUENT AND HASTE DISPOSAL SEMIAHHUAL REPORT 1982
(
GASEOUS EFFLUENTS-GROUllD-LEVEL RELEASE CONTINUOUS MODE BATCH MODE liuc l i de s Re l e as e d Unit Qu ar t e r Quarter Quart e r. -
Quarter 1
2 1
2 1.
Fission gases Xe-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
Xe-13111 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I
Kr-SC C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xc-133H Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Vr-SSH 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 Kr-97 Ci 0.00E+00 0.00E+00 0.00E+00 0.0CE+00 Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N-13 Ci 6.89E-01 0.00E+01 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 Xe-135H Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-133 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 fir-41 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot al for period Ci 6.39E-01 0.00E+00 0.00E+00 0.00E+00 2.
Iodines I-131 Ci 2.08E-05 2.06E-03 0.00E+00 0.00E+00 I-133 Ci 2.03E-05 1.S'7E-04 0.00E+00 0.00E+00 I-135 Ci 2.29E-05 2.39E-05 0.00E+00 0.00E+00 Tot al for period Ci 7.50E-05 2.27E-03 0.00E+00 0.00E+00
- 3. P ar t i c ul at e s Sr-39 Ci 6.03E-06 4.69E-06 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci O.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 1.31E-06 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 4.96E-06 0.00E+00 0.00E+00 Sn-113 Ci 8.92E-07 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 1.66E-06 6.14E-06 0.00E+00 0.00E+00 Cs-134 Ci 5.13E-07 0,00E+00 0.00E+00 0.00E+00 Cs-137 Ci 9.84E-07 1.16E-06 0.00E+00 0.00E+00 1
Ce-144 C1 0.00E+00 0.00E+00 0.00C+00 0.00E+00 Cr-95 C1 1.19E-05 0.00E+00 0.00E+00 0.00E+00 Nb-95 C1 8.04E-05 3.24E-06 0.00E+00 0.00E+00 Co-58 Ci 5.58E-07 0.00E+00 0.00E+00 0.00E+00 l
Mn-54 Ct 1.09E-07 0.00E+00 0.00E+00 0.00E+00 Fe-59 Ci 1.51E-07 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 2.01E-06 S.41E-07 0.00E+00 0.00E+00 L a-140 Ci 5.44E-07 6.52E-06 0.00E+00 0.00E+00 Total for period Ci 1.07E-04 2.76E-05 0.00E+00 0.00E+00 oo
TABLE 2-3C SITE t
~
~
E. It Hatch Huclear Power Plant SITE EFFLUEHT AND HASTE DISPOSAL SENIAHHUAL REPORT 1982 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTlHUOUS HODE EATCH NODE
_ _Huc l i de s. Re l e as e d Unit Quarter Quarter Quarter Qu ar t e r 1
2 1
2 1.
Fission gases Xe-133 Ci 1.37E+01 1.10E+01 0.00E+00 0.00E+00 Xe-131H Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 8.48E-03 0.00E+00 0.00E+00 Me-13311 Ci 3.13E-01 6.47E-02 0.00E+00 0.00E+00 1
Xe-135 Ci 2.20E+01 1.77E+01 0.00E+00 0.00E+00 Kr-85M C) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ci 1.37E-03 1.66E-02 0.00E+00 0.00E+00 Xe-13?
Ci 2.27E-02 4.68E-02 0.00E+00 0.00E+00 "e-137 Ci 0.00E+00 0.00E+00 0.00E+00
- 0. r:0 E + 00 H-19 Ci 6.92E-01 7.06E-03 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ci 3.05E+01 1.70E+01 0.00E+00 0.00E+00 1-133 C1 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 4.29E-01 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 6.76E+01 4.59E+01 0.00E+00 0.00E+00 2.
_ _ I-131 Ci 6.24E-04 1.74E-02 0.00E+00 0.00E+001 1-133 Ci 1.15E-03 3.37E-03 0.00E+00 0.00E+00 I-135 C1 1.11E-03 9.85E-04 0.00E+00 0.00E+00 Tot al for period Ci 2.89E-03 2.17E-02 0.00E+00 0.00E+00 3.
Part i c ul at es Sr-89 Ci 8.57E-06 1.93E-05 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 3.89E-10 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 3.39E-04 9.66E-05 0.00E+00 0.00E+00 I-131 Ci 1.07E-04 1.31E-04 0.00E+00 0.00E+00 Sn-113 C1 8.92E-07 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 4.26E-05 3.95E-05 0.00E+00 0.00E+00 l
Cs-134 Ci 6.54E-05 9.02E-05 0.00E+00 0.00E+00 Cs-137 C1 1.09E-04 1.51E-04 0.00E+00 0.00E+00 Ce-144 C) 0.00E+00 4.40E-08 0.00E+00 0.00E+00 2r-95 Ci 2.33E-05 8.47E-10 0.00E+00 0.00E+00 Hb-95 C1 1.26E-04 3.24E-06 0.00E+00 0.00E+00 Co-58 Ci 4.03E-05 1.24E-05 0.00E+00 0.00E+00
(
Mn-54 C1 2.57E-05 1.45E-06 0.00E+00 0.00E+00 Fe-59 Ci
!"51E-07 0.00E+00 0.00E+00 0.00E+00 Co-60 C1
Tot al for period Ci
._0E :-03 6.46E-04 0.00E+00 0.00E+00 39
TABLE 3-la EFFLUENT AND WA'HE DISPOSAL SEf.t!ANNU AL REPORT (YEAR).1982 January 1, 1982 - June 30, 1982 I
SOLID WASTE AND 1RRADIATED FUEL SHIPMENTS FOR UNIT 1 A. SOLID V.'ASTE SHIPPED OFFSITE FOR UURIAL OR DISPO:;AL (! Jot inadiated fuel) h oath C5'. To ol Unit
- 1. Tyy of wzste tutiod En or. %
- 2. 29 E2 } t.o E +1
- a. Spent t: sir.s. tdter :lt.d;:s. coperator m*_
- 2. 23 E3,
Li Inttor s. c:e.
rn' 2.25'.2
- b. Dry cornpreu:oi: ws:te cortsminated ci
- 4. 53 E0 1 0 E+1 equip. e tc.
r.V
- 0. 00_E _
- c. Irradated compsnents, control Ci 0.00J E
ro s. ete.
m'
- 3. 50 E1
- d. O:het (des:noe)
Ci 2 38E2 E
Absorbed Oil J
- 2. Estimmte of maior nuclide compo:idon (by type of weste)
I PEltCEllT CURIES 150 TOPE 27.35 60_9.35
- a. Zn-65 24.11 537.03 Cs-137 17.52 390.39 Cs-134 31.02 692.05 All others 47.89 2.17
[
___ _b. Cs-137 28.56 1.29 Cs-134 11.7_2 0.53 Co-60 11.83 0.54 All others
- c. None 37.82 0.01
- d. Cs-137 25.21 0.01 Zn-65 21.01 0.01 Cs-134 15.96 0.00 All others l
l 3.
Solid Y!aste Disposition l
Number of Shiprnents Mode of T.an: port: tion D:: tinction SC 41 cask Barnwell, WA 2
cask Richland, WA
- Richland, 9
van B. IRRADIATED FUEL SHIPT.1ENTS (Dis,wition)
Number of S!dpr-ents MoJ: of Tran mr.stion mstimtion N/A N/A N/A
{
40
TABLE 3-lb EFFLUENT AND WACTE DISPOSAL SE.'.11 ANNUAL REPORT (YEA January 1, 1982 - June 30, 1982
(~
SOLID WASTE ANO IRR ADIATED FUEL SHIPT.1ENTS FOR Uti1T 2
A. SOLID \\*.'ASTE SHIPPED OFFSITE FOR CUntAL OR DISI'OSAL(flotirv
' unis G<acath Ci'. To c)8
- 1. Type of wiste Period En or. %
m' l.00 E 2 '
- a. Sp:n1 tss.ns. 'dter s!:;dps. capr: tor d~ T 5Y2 1.O E+1 tottor-s. c:c.
rn' 2.25 E 2
- b. Dry cornpreuisie w:ste. conismmated Ci 4 53 E O
- 1. O li+1 equip.etc.
ra' OT(TO E
/
- c. Irradist d cornpnents, cont:ol Ci 0.00 E E
to h. etc.
m' 3.50 E 1
- d. Other (des:n'oe)
Ci 2 38 E 2 E
Absorbed Oil l
- 2. Estimate of maior nucUd: composi: ion (by t)y: of etc)
I PE!!CEllT CURIES ISOTOPE 53_._4 5 1.32.83
- a. 7n-65 1190
- 31.27 Cr-51 11.13 75 10 Co-60 19.13 45.04
(
All others 47.R4 9 17
- b. C1-137
_ 2A.56 1 90
_ Cs-134 11.72 0.63 Co-60 0.54 11.83 All others C. Ncno n n1
__.31.R7
- d. Cs-137 25.21 0.01 -
Zn-65 21.01 i
0.01 Cs-134 15.96 0.00 All others l
3.
Solid t'aste Disposition Mod: of Trans;> ort: tion D::tination_
Number of Shi:.ments SC cask 8arnwell, WA cask Richland, WA 12 1
- Richland, i
9 van IL IRRADIATED FUEL SHIPf.1ENTS (Dismition)
Destfrution_
MoJ: of Tran:nortation Number of SMor-ents N/A N/A N/A
(
l 41