ML20071D360
| ML20071D360 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/25/1981 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20071D344 | List: |
| References | |
| NUDOCS 8303090368 | |
| Download: ML20071D360 (43) | |
Text
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GEORGIA POWER COMPANY PLANT E. I. HATCH UNITS NO. 1& 2 5
SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JANUARY 1, 1981 - JUNE 30, 1981 O
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%d 8303090368 910825 PDR ADOCK 05000321 R PDR
PLANT E. I. HATCH r .
3 SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES SECTION TITLE PAGE
- 1. LIQUID EFFLUENTS 1 1.1 REGULATORY LIMITS 1 1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS 2 1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 4 1.4 LIQUID EFFLUENT RELEASE DATA 6 2 GASEOUS EFFLUENTS 23 2.1 REGULATORY LIMITS 23 2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 25 2.3 GASEOUS EFFLUENT RELEASE DATA 29 0 3 SOLID WASTE 29 3.1 REGUL'ATORY SPECIFICATIONS 29 3.2 SOLID WASTE DATA 29 1
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PLANT E. I. HATCH SEMIANNUAL REPORT
,, PLANT RADIOACTIVE EFFLUENT RELEASES FIGURE LIST OF FIGURES PAGE l-1 METHODS OF MEETING TABLE II 7 COLUMN 2 MPC LIMITS (10 CFR 20) 1-2 LIQUID RADWASTE ANALYSIS - UNIT I 8-11 1-3 ,
LIQUID RADWASTE $NALYSIS - UNIT II 12-15 1-4 LIQUID RADWASTE DISCHARGE PERMIT 16 1-Sa, b LIQUID RADWASTE DATA COMPILATION 17, 18 TABLE LIST OF TABLES PAGE l-la, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 19, 20 1-2a, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-BATCH ONLY 21, 22 2-la-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENT-hi 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 IRRhDIATED FUEL SHIPMENTS 39, 40
PLANT RADIOACTIVE EFFLUENT RELEASES 1 LIQUID EFFLUENTS 1.1. REGULATORY LIMITS r%" -
- 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 rel' ease of radioactive materials in liquid wastes, excluding . tritium and dissolved gases, shall not exceed 10 Ci/ reactor / calendar quarter.
- 3. The cumulative release of radioactive materials in liquid wastes, excluding tritium and dissolved gases, shall not exceed 20 Ci/ reactor in any 12 consecutive months.
- 4. During release of radioactive wastes, the effluent control monitor shall be set to alarm and to initiate the automatic closure of the waste discharge valve prior to exceeding the limits specified in 1. above.
- 5. The operability of the automatic isolation valve in the liquid radioactive waste discharge line shall be demonstrated quarterly.
, 6. The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to
- q process radioactive._ liquid wastes prior to their discharge when the projected cumulative release rate could exceed 1.25 C1/ 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 j dissolved gases.
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, 8. If the cumulative release of radioactive materials in liquid effl,uents, excluding tritium and dissolved gases, exceeds 2.5 Ci/ reactor / calendar quarter, the l licensee shall make an investigation to identify the I 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, i .
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1.2. MAXIMUM PERMISSIBLE CONCENTRATIONS s The MPC values used in determining allowable liquid radwaste release concentrations are taken from 10 CFR Part 20, Appendix B, 4 Table II, Column 2. Release rate and dilution ratio for each
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batch are determined by a mixed nuclide MPC calculation performed before the release of the batch. To facilitate the measurements and calculations, the nuclides of Column 2 which can be produced in a fission. reactor have been grouped according to MPC value.and 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 j
distillation and liquid scintillation counting technique is used to measure tritium concentration.
The maximum activity of gamma.and beta emitting nuclides with MPC 3 values greater than 9 X 10._-6 uCi/ml, except for the 29 nuclides noted above, ,is determined by gross gamma and gross beta i
measurements. Measurement sensitivity limits of approximately 2 cpm /ml allow a null measurement to show that the sum 1
(Ci/MPCi), is less than 0.1 for gamma and beta nuclides not measured directly.
The sum of the ratios, E (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 follows:
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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
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in the Environmental Tech. Specs. This sum is for each batch released to the river for the respective quarter. Percent of applicable limit is determined from a mixed nuclide MPC calculation. The average concentration for each nuclide summed over all batches is divided by .the corresponding individual MPC value. The sum over all nuclides of the Ci/3PCi 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, 4 is converted to percent to give the percent of applicable
- limit.
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, 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 h; additional 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.
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1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY.
Dstails of the analytical procedures for liquid radwaste analysis are contained 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 E a c h B a t.c.h _ _ Ge(Li) spectrometry with on-line computer
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If a liquid radwaste tank cannot be reprocessed, a sample for analysis is taken from the tank after the required recirculation time. The sample is used for gamma-ray spectroscopy, gross gamma and gross beta counting, and for preparation of a composite sample.
.~ The Ge(Li) detector consist of a 10% and two 15% efficiency, 2.0 FWHM resolution detectors in 4-inch thick lead shields. A one-liter radwaste liquid sample is poured in to a Marinelli beaker. in preparation for a 2000-3000 second Ge (Li) count. A peak search of the resulting gamma ray spectrum is performed by the on-line computer system. 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) by a laboratory technician. Although the computer could printout
{,' the release permit and will inform the technician if a batch cannot be discharged as desirem 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 j 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 terminared if the dilution flow rate falls below the flow rate used in the computer calculation.
When the release permit is returned from Radwaste Operations following discharge, the discharge data is combined with the analysis results on the computer disc file. The disc file may be scanned to display trends in any recorded parameter, or may be summed for reporting purposes as shown in Figure 1-Sa and b.
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All other radionuclido concentration :anasurements are parformed as indicated in the table given previously in this section and as detailed in the procedure HNP-7601. The dissolved gases
( calculation is performed in the Ge(Li) spectrometry system with computer data reduction using the Liquid Radwaste Library which includes gases.
Several comments are indicative of the success of the HNP liquid radwaste program during this reporting period:
- 1. The total measured activity releosed in liquid ef fluent for both Units was 6.42 E-1 curies for the first quarter and 2.31 E-1 curies for the second quarter. These values were approximately 1/200 for Unit 1 and 1/709 for Unit 2 for the first quarter and 1/82 for Unit 1 and 1/92 for Unit 2 for the second 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 34.67% of the liquid radwaste reaching the sample tanks was discharged; 65.33% 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 846 discharge batches for both Units.
{} 1.4 LIQUID EFFLUENT RELEASE DATA Regulatory Guide 1.21 Tables 2A and 2B are found in this report as Table 1-la, b and _1*2a, b. Data is presented on a quarterly basis as per Regulatory Guide 1.21.
Other data pertinent to batch releases of radioactive effluent from both units is as follows:
Number of batch releases: 846 Total time period for releases: 108,526 minutes Maximum time period for a batch release: 242 minutes I
Average rime period for batch release: 129 minutes Minimum time period for a batch releaset 1 minute Average stream flow during periods of release of effluent into a flowing stream: 9197 CFS 6
FIGURE l-1 METHOD'S OF MEETING, TABLE II, COLUMN 2 MPC LIMITS
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MPC RANGE GAMMA-RAY BETA ! ALPHA (U Ci/ml) EMITTERS EMITTERS EMITTERS I-131,'I-13 2 , I-133 Sr-89, Sr-90 I-135, Cs-134 (Separation &
Gas Flow
<9 X 10 (Ge(Li) Gamma-Ray '
Counting)
Spectroscony) ALL (Gas Flow Counting, Sensitivity
' O.01 CPM /ml)
Ba-La-140, Na-24,Cu-64 Tritium
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19 X 10-6 g_116m M 54 C0 58 (Distillation &
Liquid Scintil- j 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 i (Gas Flow Count-(Ge(Li) Gamma-Ray ; ing Sensitivity Spectroscopy) ~
2 CPM /ml c !
. (7 All others ~-~'
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(Gross Gamma-Well :
1 Counter; Sensitivity
~ 5 CPM /ml) i l
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FIGWE 1-2 _.
PROCEDURE: HNP-7601 REVIS!0 fit 7 DATA SHEET 8 esseseeseesseeeeeeeeeeeeeeeees***vesesseeeeeees,
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Reactor # 1 Batche 348 Tank: WSTA1 Rectre time: 55 minutes ,
Comment: f@lHTAIN CST ,
Run date: 6/14/81 1214 Count start date: 6/14/81 07b9 Sample volume: 1000.00 ml Clock time: 3000 secs Geometry code: 1LHB-0 Live time: 3000 secs Detector # 3 HCAR 3 !
Library: LRWLE2 Operat or: SLH Energy (kev)= .02 + 1.000eChe + 0.000E+00*Ch#^2 + 0.000E+00eChea3: 06/14/81 01 V
Err = 1/t6.950E-03
- Ea(-3.2297E+00) + 234.761 e Ea(8.9188E-01)3 : 06/10/81 00 uhere E = Energy in HeV.
9 ISOTOPE EHERGY COHCENTRATIOH ERROR HPC C/MPC (kev) (uCi/ml) (uC1/ml) (uCi/ml)
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. Ce-144 133.50 (6.045E-08 1E-05 (6.05E-03
. Tc-99m 140.50 (7.286E-09 3E-03 <2 43E-06 '
Ce-143 145.40 <1.496E-08
- 9E-05 <1.66E-04 (7.240E-08 IE-04 (7.24E-04 Cg '
- Ilp-239 Cc-51 277.90 320.10 (9.220E-08 2E-03 <4.61E-05
<2.86E-02 1-131 364.50 (8.573E-09 3E-07 438.70 <S.706E-09 6E-05 <1.45E-04 2n-69m 6E-05 <5.83E-04 W-187 479.50 <3.497E-08 511.00 (4.210E-09 5E-04 (8.42E-06 F-18 <9.24E-03 1-133 529.50 <9.238E-09 IE-06
<4.567E-08 2E-05 <2.28E-03 Ba-140 537.40 2E-05 <1.19E-03 As-76 559.30 <2.389E-08 604.86 2.189E-07 1.965E-08 9E-06 2.43E-02 Cs-134 2E-05 1.42E-02 i Cs-137 661.76 2.840E-07 2.454E-08 4E-05 (1.81E-03 l Ho-99 739.70 <7.229E-08 743.50 <9.880E-09 2E-05 <4.94E-04 l Zr-97
( Zr-95 756.90 <2.499E-08 6E-05 (4.16E-04 ;
<1.300E-08 1E-04 <1.30E-04 Hb-95 765.80 BE-06 <3.51E-04 I-132 772.60 (2.305E-0?
Co-58 810.60 (8.698E-09 9E-05 (9.66E-05 Hn-54 834.80 <1.309E-03 1E-04 <!.31E-04
<!.439E-08 3E-05 <4.SOE-04 Ag-110m 884.70 1.81E-03 1114.95 1.310E-07 3.221E-03 1E-04 Zn-65 4E-06 <4.37E-03 1-135 1260.50 <1.749E-08
<1.215E-08 CE-05 <2.02E-04 Fe-59 1291.60 Co-60 1333.03 7.164E-03 1.848E-08 3E-05 2.39E-03 Cu-64 1345.90 <9.377E-07 2E-04 (4.69E-03 Ha-24 1368.55 <6.683E-09 3E-05 <2.23E-04 !
1596.60 (6.338E-09 2E-05 <3.17E-04 La-140 (C.57E-05 Mn-56 1811.00 (8.567E-09 1E-04 (EETA) 5.640E-09 2.020E-09 3E-06 1 88E-03 Sr-89 3E-07 (1.57E-03 Sr-90 (EETA) (4.700E-10 H-3 (EETA) 2.160E-04 4.000E-07 3E-03 7.20E-02 (EETA) <1.000E-06 8E-04 <!.25E-03 Fe-55 2E-05 s1.50E-02 P-32 ( EC ) <3.000E-07 ----- ---------
2.168E-04 4.030E-07 1.17E-01
- - Measured totals <8.0CE-02 LLD totals (2.831E-06 1.97E-01 Totals 2.196E-04 8.
FIGURE 1-2 (CONTINUED)
OrSSOLVED GASES i
<2.515E-08 4E-05 <6.29E-04 YX2-133 80.99 196.10 (7.955E-09 4E-05 <1.99E-04
Xr-88 4E-05 <2.18E-03 Xo-133m 233.18 <8.702E-08 9.565E-08 7.780E-09 4E-05 2.14E-03 X3-135 249.85 <8.54E-04 305.00 <3.415E-08 4E-05 Kr-85m 4E-05 <6.67E-05 Kr-87 402.70 <2.670E-09
<6.065E-13 4E-05 <1.52E-08 X2-138 434.50 8.565E-08 7.780E 2.14E-03 M2asured gas totals <3.92E-03 LLD gas totals <1.569E-07 2.426E-07 6.06E-03 ,
Tot al gas !
t GROSS ACTIVITY Yo1 Het Error i Counter Gross Background Time 1 Sigma Counts (Min) m1 Activity (cpm /ml)
Counts -__-_-_. --_--_-_
1851 1832 20.0 2 4.75E-01 1.52E+00 Well Crystal Proport i onal 167 175 10.0 2 <3.05E+00 10807.00 gallons -
(ESTIMATED WASTE TAHK VOLUME =
ESTIMATED ACTIVITY THIS BRTCH O EXCLUDING GASES: 8.87E-03 Curies ( 8.87E+03 Microcuries)
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EXCLUDING H-3 AND GASES: 3.11E-05 Curies ( 3.11E+01 Microcuries)
Liquid Raduaste Release Summarv ;
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- 1) Meas. conc., excluding H-3 and dissolved gases (uCi/ml): 7.61E-07 +- 4.87E-08 Meas. conc., including H-3, excluding gases : 2.17E-04 +- 4.03E-07
- 2) Calculated LLD concentration, excluding dissolved gases (uCi/ml): 2.83E-06
- 3) Calculated MPC ratio (C/MPC of meas. , including gases): 1.19E-01 !
- 4) Minimum dilution flou rate (gpm): 10000
- 5) Maximum tank discharge flow rate (gpm): 85059 6)Specified tank flou rate (gpm): 90 7)Raduaste monitor trip setting: 857 A = 8.41E-0? ,uCi/mi B = 750 , Monitor BG CPS C= 14660000.00 ,Nonitor CPS per uCi/ml F=2 ,Conserv. Factor A includes measured ' selected','other' nuclides and gases but excludes:
Sr-89, Sr-90, H-3, Fe-55, P-32 s
- 8) Estimated conc. of meas. nuclides at point of release (uCi/ml): 1.933E-06
- 9) Undiluted concentration meets 10CFR20 limits.
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FIGURE 1-2 (CNTINUED) UNIT 1
- " - ESTIM6TED DOSES THIS BATCH, MREM Isotope W. Body Bone Liver Thyroid Kidnay 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 f3 0.00E+00 0.00E+00 0.00E+00 ,,0.00E+00 0.00E+00
- 1 Tc-99m 0.00E+00 0.00E+00 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 0.00E+00 0.00E+00 'O.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+09 0.00E+00 0.00E+00 0.00E+00 Xe-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hp-239 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 0.005+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-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-69m 0.00E+00 C.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N-187 0.00E+00 0.00E+00" 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F-18 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '
As-76 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i C5-134 6.56E-05 3.38E-05 8.02E-05 0.00E+00 2.60E-05 8.63E-06 1.40E-06 CA-137 5.02E-05 5.63E-05 7.67E-05 0.00E+00 2.61E-05 8.67E-06 1.49E-06
-MesSS 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hb-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3 LI-b3e 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+06 Mn-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ag-110m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 1.56E-06 1.08E-06 3.45E-06 0.00E+00 2.31E-06 0.00E+00 2.17E-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 2.46E-07 0.00E+00 1.11E-07 0.00E+00 0.00E+00 0.00E+00 2.09E-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 7.97E-10 2.78E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.47E-09 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 8.72E-08 0.00E+00 8.72E-08 8.72E-08 8.72E-08 S.72E-08 8.72E-03 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.COE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ,
________ ________ ________ ________ ________ ________ ________ ________ j Tot al 1.18E-04 9.11E-05 1.60E-04 8.72E-08 5.45E-05 1.74E-05 7.25E-06 I l
i I
Cumul ative dose this YEAR (includes estimate for this batch):
Whole body 2.05E-01 mrem Percent of Tech Spec Limit: 6.82E+00 Bone 1.54E-01 mrem Percent of Tech Spec Limit: 1.54E+00 Liver 2.75E-01 mrem Percent of Tech Spec Limit: 2.75E+00 Thyroid 7.50E-02 mrem Percent of Tech Spec Limit: 7.50E-01 Kidney 9.28E-02 mrem Percent of Tech Spec Limit: 9.2SE-01
( '.. Lung 3.00E-02 meem Percent of Tech Spec Limit: 3.00E-01 G LLI 1.07E-02 mrem Percent of Tech Spec Limit: 1.07E-01 Cumu l at i ve dose this QUARTER (includes estimate for thi s b at ch): 7.30E+00 Percent of Tech Spec Limit:
Whole body 1.10E-01 meem Bone S.23E-02 mrem Percent of Tech Spec Limit: 1.65E+00 _ . _ _ _ _ _
10
FIGURE 1-2 (CONTINUED) 348 UNIT 1 e.ser+ee- wrwez+ee -,
h-y-Co-5S 0.00E+00 ~0.00E+00D.eeE+ee 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I Mn-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l.
Ag-110m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ~2.33E-06 0.00E+00 2.17E-06 !
Zn-65 1.56E-06 1.08E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.45E-06~
I-135 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 2.09E-06 2.46E-07 0.00E+00 1.11E-07 0.00E+00 0.00E+00 ,
Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cu-64 0.00E+00 0.00E+00 'O.00E+00 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 La-140 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 Mn-56 0.00E+00 0.00E+00 4.47E-09 2.78E-08 0.00E+00 0.00E+00 0.00E+00
, Sr-89 7.97E-10 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 8.72E-08 8.72E-08 8.72E-08 8.72E-08 8.72E-08 !
H-3 8.72E-08 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 0.00E+00 t P-32 0.00E+00 0.00E+00 -------- -------- --------
1.60E-04 8.72E-08 5.45E-05 1.74E-05 7.25E-06 Tot al 1.18E-04 9.11E-05 Cumulative dose this YEAR (includes estimate Percent for this of Tech Specbatch):
Limit: 6.82E+00 Whole body 2.05E-01 mrem 1.54E+00 1.54E-01 meem Percent of Tech Spec Limit:
Bone 2.75E+00 Liver 2.75E-01 mrem Percent of Tech Spec Limit: l 7.50E-02 mrem Percent of Tech Spec Limit: 7.50E-01 :
Thyroid 9.28E-01 Kidney 9.28E-02 mrem Percent of Tech Spec Limit: ,
Percent of Tech Spec Limit: 3.00E-01 Lung 3.00E-02 mrem C}'. ,
GI-LLI 1.07E-02 mrem Percent of Tech Spec Limit: 1.07E-01 f
, Cumulative dose this QUARTER ,(includes estimate for this batch): 7.30E+00 Percent of Tech Spec Limit: i Whole body 1.10E-01 mrem 1.65E+00 8.23E-02 mrem Percent of Tech Spec Limit:
Sone 2.95E+00 1.48E-01 mrem Percent of Tech Spec Limit: -
Liver 6.94E-02 Thyroid 3.47E-03 mrem Percent of Tech Spec Limit:
Percent of Tech Spec Limit: 9.91E-01 Kidney 4.95E-02 mrem 3.21E-01 1.60E-02 mrem Percent of Tech Spec Limit:
Lung 1.11E-01 5.54E-03 mrem Fercent of Tech Spec Limit:
GI-LLI Projected cumulative dose this QUARTER (includes estimate for this batch):
Whole body 1.35E-01 meem Sone 1.01E-01 mrem Liver 1.81E-01 mrem Thyroid 4.27E-03 mrem Kidney 6.09E-02 mrem Lung 1.97E-02 mrem GI-LLI 6.81E-03 mrem Cumulative measured activity this YEAR (includes estimate for this batch):
5.601E-02 Curies, excluding H-3 and dissolved gases BATCH # 348 DATA SUCCESSFULLY STORED SPECTRUtf STORED AS: LRW1 11
o************oo****5db b ~44*****************e o E. I. Hat c h Nuc l ear Pl ant o Liquid Raducste Analysis o
- ++*********************************** ~
PROCEDURE: HHP-7601 REVISIGH: 8 DATA SHEET S i
gag Reactor # 2 Batch # 450
_J Tank: FDST2 Recirc time: 105 minutes Comment: HIGH COND,FS,TURB SiO2 Run date: 6/29/81 1256 Count start dat e : 6/29/81 1202 Sample volume: 1000.00 ml Clock time: 3000 secs .
Geometry code: 1LHB-0 Live time: 3000 secs Detector # 1 MCA# 1.
Library: LRWLB2 Operator: DG/VC Energy (kev)= .24 + 1.000*Ch# + 0.000E+00*Ch#^2 + 0.000E+00*Ch#^3 : 06/29/81 0005 Eff = 1/C1.409E-03
- E^(-4.2388E200) + 541.223
- E^(8.9884E-01)3 : 06/25/81 0017' uhere E = Energy in MeV. ,
I ISOTOPE ENERGY COHCENTRATION ERROR MPC C/MPC ,
(kev) <uCi/ml> (uCi/ml) (uCi/ml)
====================================================================
Ce-144 133.50 <2.709E-07 1E-05 <2.71E-02 Tc-99m 140.50 <3.241E-08 3E-03 <'.08E-05 Ce-141 145.40 (6.048E-08 9E-05 <6.72E-04 '
Hp-239 277.90 <2.930E-07 1E-04 <2.93E-03 320.10 <3.329E-07 2E-03 <1.66E-04
, Cr-51
<4.110E-08 3E-07 <1.37E-01 i_ i 1-13' 364.50 438.70 <2.969E-08 6E-05 <4.95E-04 Zn-69m W-187 479.50 <1.014E-07 6E-05 <1.69E-03 511.00 <4.003f-08 5E-04 <8.01E-05 F-18 I-133 529.50 <3.832E-08 -
1E-06 <3.83E-02 Ba-140 537.40 (1.512E-07 2E-05 <7.56E-03 As-76 559.30 <7.635E-08 2E-05 <3.82E-03 Cs-134 604.70 <4.230E-08 9E-06 <4.70E-03 Cs-137 661.30 1.816E-07 3.889E-08 2E-05 9.08E-03 ,
Mo-99 739.70 <2.668E-07 4E-05 <6.67E-03 2r-97 743.50 <3.685E-08 2E-05 <1.84E-03 Zr-95 756.90 <7.120E-08 6E-05 <1.19E-03 ,
Hb-95 765.80 <4.713E-08 1E-04 <4.71E-04 I-132 772.60 <3.8600-99 SE-06 <4.83E-03 t Co-58 810.60 <3.5'.J-C6 9E-05 <3.96E-04 Mn-54 834.80 <C 391 -09 1E-04 <4.09E-04 l <1.61E-03 Ag-110m 984.70 re? Os 3E-05 2n-65 1115.40 ,$ y -P9 1E-04 <9.09E-04
(
<2.61E-02 I-135 1260.50 (1.6%.2-07 4E-06 Fe-59 1291.60 <5.623E-08 6E-05 <9.37E-04 Co-60 1332.50 <6.234E-08 3E-05 <2.08E-03 Cu-64 1345.90 <5.824E-06 2E-04 <2.91E-02 Na-24 1368.55 <3.122E-08 3E-05 <1.04E-03 La-140 1596.60 <2.196E-08 2E-05 <1.10E-03 Mn-56 1811.00 <4.895E-08 1E-04 <4.90E-04 Sr-89 (BETA) 9.660E-09 2.550E-C? 3E-06 3.22E-03 Sr-90 (BETA) <5.700E-10 3E-07 <1.90E-03 H-3 (BETA) 3.960E-04 5.000E-07 3E-03 1.32E-01 l
~
Fe-55 (BETA) <1.000E-06 8E-04 <1.25E-03 l
P-32 ( EC > <2.000E-07 2E-05 <1.00E-02 Measured totals 3.962E-04 5.015E-07 1.44E-01 LLD totals (9.536E-06 <3.17E-01 Tot al s 4.057E-04 4.61E-01 12
l FIGURE 1-3 (CINI'INUED)
DISSOLVED GASES
.O.;j Xe-133 80.99 <9.627E-08 4E-05 <2.41E-03 ; !
Kr-88 196.10 <7.385E-08 4E-05 <1.85E-03 '
Xe-133m 233.18 <3.281E-07 4E-05 <8.20E-03
<3.473E-08 4E-05 (8.68E-04 Xe-135 249.60
<5.29E-03 Kr-85m 305.00 <2.115E-07 4E-05 Kr-87 402.70 <5.682E-08 4E-05 <1.42E-03 Xe-138 434.50 <3.101E-08 4E-05 <7.95E-04 Measured gas totals 0.000E+00 0.000E+00 0.00E+00 LLD gas totals <8.331E-07 <2.08E-02 To t al gas 8.331E-07 2.08E-02 i
GROSS ACTIVITY Gross Background Time vol Het Error Counter 1 Sigma Counts Counts (Min) m1 Activity (cpm /ml)
Well Crystal 1957 1725 20.0 2 5.80E+00 1.52E+00 203 10.0 2 1.40E+00 1.04E+00 Proport i on al 231 ESTIMATED WASTE TANK VOLUME = 9243.00 gallons ESTIMATED ACTIVITY THIS BATCH 1.39E-02 Curies ( 1.39E+04 Microcuries)
EXCLUDING GASES:
0- #
EXCLUDING H-3 AND GASES: 6.69E-06 Curies ( 6.69E+00 Microcuries) .
s Liquid Raduaste Release Summarv
- 1) Meas. conc., excluding H-3 and dissolved gases (uci/ml): 1.91E-07 +- 3.90E-08 Heas. conc., including H-3, excluding gases : 3.96E-04 +- 5.02E-07 2)Calcul ated LLD concentrat ion, excluding dissolved gases (uCi/ml): 9.54E-06 3)Calcul ated MPC rat io (C/MPC of mess., including gases): 1.44E-01
- 4) Minimum dilution flou rate (gpm): 10000 *
- 5) Maximum t ank discharge flou rate (gpm): 69992
- 6) Spec i fi ed t ank flou rate (gpm): 75 7)Raduaste monitor trip setting: 789 A = 1.82E-07 ,uCi/ml - B = 700 , Monitor BG CPS l C = 27465000.00 , Monitor CPS per uCi/mi F=2 ,Conserv. F ac t or l
A includes measured ' selected','other' nuclides and gases but excludes:
Sr-89, Sr-90, H-3, Fe-55, P-32 l
l *4 8) Estimated conc. of meas, nuclides at point of release (uCi/ml): 2.949E-06 j
9"Jndi luted concentrat i on meet s 10CeR20 timits.
i l
i
- 13
FIGURE 1-3 (CCNfINUED) gxNg ESTIMATED DOSES THIS BATCH, MREM !
Isotope W. Body Bone Liver Thyroid Kidney Lung GI-LLI '
Xe-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00, 0.00E+00 0.00E+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0:00E+00 0.00E+00 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ,
Xe-133m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hp-239 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.20E+00 0.00E+00 0.00E+00 Kr-85m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-69m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 W-137 0.00E+00 0.00E+09 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+03 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 Ba-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 As-76 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 q Cs-137 2.75E-05 3.0SE-05 4.20E-05 0.00E+00 1.43E-05 4.75E-06 8.15E-07 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 li,b-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ~0.00E+00 0.00E+00 0.00E+00 l I,-132
,Co-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 h-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ag-110m 0.00E+00 0.00E+00. 6.~00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 0.00E+00 0.00E+00 0.00E+00 0.00E+0D 0.00E+00 0.00E+00 0.00E+00 i
h O
e 14
FIGURE 1-3 (CDNI'INUED)
Dh -
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 f.i 35 0.00E+00 0.00E+00 0 00E+00 0.00E+00 pe-59 0.00E+00 0.00E+00 0.00E+00 co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0. 00E+00 - 0. 00E+00 0.00E+00 Na-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 0.00C+00 0.00E+00 Sr-89 1.17E-09 4.09E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.56E-09 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 1.37E-07 0.00E+00 1.37E-07 1.37E-07 1.37E-07 1.37E-07 1.37E-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 2.76E-05 3.09E-05 4.21E-05 1.37E-07 1.44E-05 4.89E-06 9.58E-07 Cumul at ive dose this YEAR (includes estimate for this batch): 5 Whole body 5.77E-02 mrem Percent of Tech Spec Limit: 1.92E+00 i Bone 4.40E-02 mrem Percent of Tech Spec Liret t: 4.40E-01 Liver ,
7.S6E-02 mrem Percent of Tech Spec Limit: 7.86E-01 ,
Thyroid 2.81E-03 mrem Percent of Tech Spec Limit: 2.81E-02 Kidney 2.71E-02 mrem Percent of Tech Spec Limit 2.71E-01 Lung 8.36E-03 mrem Percent of Tech Spec Limit: 8.36E-02 GI-LLI 6.19E-03 mrem Percent of Tech Spec Limit: 6.19E-02
) Cumulative dose this QUARTER (includes estimate for this batch):
Nhole body 4.42E-02 mrem Percent of Tech Spec Limit: 2.95E+00 Bone 3.36E-02 mrem Percent of Tech Spec Limit: 6.72E-01 Liver 5.98E-02 mre'm Percent of Tech Spec Limit: 1.20E+00 Thyroid 1.86E-04 mrem Percent of Tech Spec Limit: 3.73E-03 Kidney 2.03E-02 mrem Percent of Tech Spec Limit: 4.06E-01 l
Lung 6.47E-03 mrem Percent of Tech Spec Limit: 1.29E-01 ,
GI-LLI 3.63E-03 mrem Percent of Tech Spec Limit: 7.27E-02 I Projected cumulative dose this QUARTER (includes estimate for this batch):
Whole body 4.52E-02 mrem Eone 3.43E-02 mrem Liver 6.12E-02 mrem Thyroid 1.91E-04 mre'm I Kidney 2.07E-02 mrem Lung 6.61E-03 mrem GI-LLI 3.72E-03 mrem Cumul at ive measured act ivi ty this YEAR (includes estimate for this batch):
4.099E-02 Curies, excluding H-3 and dissolved gases
=_--mem-m-_mem_--_me.--_-._-__.-----_--------==---------_ ----m===_--=_-_m-m--=E BATCH # 450 DATA SUCCESSFULLY STORED SPECTRUM STORED AS: LRW2 15 "
FIGURE l-4 PLANT E.I. HATCH BATCH NO.
b w
- LIQUID RXD'ITASTE DISCHARCE PERMIT UNIT l TANK TO DE RELEASED DATE REASON FOR NECESSITY OF DISCHARGE RECIRC. START TIME SAMPLE TIME RECIRC. DURATION MINUTES I. LABORATORY ANALYSIS (1) MEASURED RADIONUCLIDE CONCENTRATION .E + .E uCi/ml (2) CALCULATED LLD LIMIT CONCENTRATIONS uCi/ml*
(3) CALCULATED MPL RATIO: I (Ci/MPCi)
(4) MINIMUM DILUTION FLOW RATE GPM (5) MAX. CALCULATED TANK DISCHARGE RATE: (SEE SEC. F.4.q) GPM
< GPM (6) SPECIFIED TANK DISCHARGE RATE: - (5)/2 (7) RADWASTE MONITOR TRIP SETTING: CP.3 A = Ge(Li) (1) uCi/ml B = MONITOR BG CPS C = MONITOR CPS F = CONSERVATIVE PER Ge(LL) uCi/ml FACTOR MONITOR ALARM SETPOINT (CPS) = (C X A X F) + B + 3 /B COMPLETED BY DATE COMPOSITE LITER STORED (INITIALS) LAB FOREMAN APPROVED (8) RADWASTE MONITOR MAX. CPS TO BE WITHIN 10 CFR 20 LIMITS:
CXAX (6) +(4)_
(6) (3) cI,s pH II . OPERATIONS C CPS INIT.
(9) LIQUID RADWASTE MONITOR TRIP SET AT:
(10) CONFIRMED DILUTION FLOW RATE GPM j (11) VALVE LINEUP CHECKED AS PER HNP-TANK DIS. INTEGRATOR LIS. RATE DIL. TOTAL RIVER EL. MONITOR DATE TIME LEVEL -% RDNG. GPM GAL FT. CPS START END
. COMPLETED BY DATE MIN. GAL.
DURATION TOTAL SHIFT FOREMAN APPROVED RELEASE
- 0 10 MIN AFTER START
- AFTER FLUSHING III. LABORATORY <
(12) TOTAL TANK VOLUME DISCHARGED GAL. X 3,785 ml (13) TOTAL ACTIVITY DISCHARGED (1) X (12) uCi CFS (14) RIVER FLOW RATE (FROM FSAR 2.4-6) . . _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ . ..
COMPLETED BY DATE LAB FOREMAN APPROVED 16
EIGURE l-Sa
~
Li qui d Radwast e D at a Compi l at i on for Reg. Guide 1.21 Repcr*
w E. I. Hat c h Nuc l e ar Pl ant UNIT 1 Total Activity (Curies)
Quarter 1, 1981 Quarter 2, 1981 Batches 1 thru 189 Batches 190 thru 390 Hame Measured Error High LLDs Total Measured Error High LLDs Total Ce-144 7.25E-04 6.98E-05 2.00E-05 7.45E-04'8.93E-05 2.13E-05 0.00E+00 8.93E-05 Tc-99m 3.03E-04 7.03E-06
- 3.03E-04 5.40E-05 1.55E
- 5.40E-05l Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00' Hp-239 0.00E+00 0.00E+00
- 0.00E+00 0.00E+00 0.00E+00
- 0.00E+00 Cr-51 1.02E-03 3.68E-05
- 1.02E-03 6.18E-05 8.09E-06
- 6.18E-05 I-131 1.36E-02 3.71E-05 0.00E+00 1.36E-02 5.97E-04 1.06E-05 0.00E+00 5.97E-04' Zn-69m 0.00E+00 0.00E+00
- 0.00E+00 0.00E+00 0.00E+00
- 0.00E+00 W-187 1.33E-05 0.00E+00
- 1.33E-05 0.00E+00 0.00E+00
- 0.00E+00 F-18 1.28E-04 6.36E-06
- 1.28E-04 0.00E+00 0.00E+00
- 0.00E+00 I-133 2.40E-04 6.39E-06
- 2.40E-04 0.00E+00 0.00E+00
- 0.00E+00 Ba-140 0.00E+00 0.00E+00
- 0.00E+00 0.-00E+00 0.00E+00
- 0.00E+00 As-76 0.00E+00 0.00E+00
- 0.00E+00 0.00E+00 0.00E+00
- 0. 00E+00 ;
Cs-134 1.24E-02 3.94E-05 0.00E+00 1.24E-022.21E-024.87E-050.00E+002.21E-02l Cs-137 1.36E-02 4.38E-05 0.00E+00 1.36E-02 2.61E-02 5.56E-05 0.00E+00 2.61E-02 Mo-99 2.92E-05 9.19E-06 0.00E+00 2.92E-05 8.65E-05 2.53E-05 0.00E+00 8.65E-05 Zr-97 9.97E-07 1.38E-06
- 9.97E-07 0.00E+00 0.00E+00
- 0.00E+00 Zr-95 2.98E-05 4.13E-06
- 2.98E-05 5.84E-05 4.17E-06
- 5.84E-05 Hb-95 1.39E-04 5.83E-06
- 1.39E-04 2.74E-04 8.03E-06
- 2.74E-04 I-132 0.00E+00 0.00E+00
- 0.00E+00 0.00E+00 0.00E+00
- 0.00E+00
,{3 Co-58 8.86E-05 4.10E-06 0.00E+00 8.86E-05 6.48E-05 3.74E-06 0.00E+00 6.48E-05 Mn-54 2.92E-04 8.34E-06 0.00E+00 2.92E-04 4.98E-04 1.11E-05 0.00E+00 4.98E-04 Ag-110m 1.62E-05 1.84E-06 .* 1.62E-05 2.21E-05 3.04E-06
- 2.21E-05 Zn-65 3.79E-03 4.41E-05 0.V0E+00 3.79E-03 7.98E-03 5.93E-05 0.00E+00 7.98E-03 I-135 0.00E+00 0.00E+00
- 0.00E+00 0.00E+00 0.00E+00
- 0.00E+00 Fe-59 2.48E-05 3.50E-06 0.00E+00 2.48E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 2.62E-03 2.48E-05 0.00E+00 2.62E-03 4.39E-03 3.09E-05 0.00E+00 4.39E-03 Cu-64 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 La 1.82E-04 6.09E-06
- 1.82E-04 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 Cs-136 8.28E-04 1.31E-05
- 8.28E-04 6.08E-05 4.28E-06 + 6.08E-05
- 1.58E-06 2.61E-06 7.76E-07 + 2.61E-06 Cs-138 1.58E-06 2.86E-07 Rb-88 4.94E-09 1.19E-09
- 4.94E-09 0.00E+00 0.00E+00
- 0.00E+00 Ni-65 0.00E+00 0.00E+00
- 0.00E+00 4.10E-06 1.48E-06 + 4.10E-06 Sr-89 4.30E-05 1.54E-05 0.00E+00 4.30E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.92E-02 6.24E-03 0.00E+00 5.92E-02
(
Fe-55 I P-32 0.00E+00 0.00E+00 0.00E+Po 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot al s 5.01E-02 1.20E-04 2.0dE-05 5.01E-02 1.22E-01 6.24E-03 0.00E+00 1.22E-01 l
l l
Xe-133 5.10E-02 8.78E-05 0.00E+00 5.10E-02 4.36E-04 1.23E-05 0.00E+00 4.36E-04 l Kr-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133m 1.19E-03 4.65E-05 0.00E+00 1.19E-03 0.00E+00 0.00E+00 0.03E+00 0.00E+00 Xe-135 3.45E-02 3.54E-05 0.00E+00 3.45E-02 9.33E-04 7.95E-06 0.00E+00 9.53E-04 Kr-85m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.31E-05 3.51E-06 0.00E+00 1.31E-05 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m 2.27E-03 1.60E-04 0.00E+00 2.27E-03 5.20E-04 7.32E-05 0.00E+00 5.20E-04
- Xe-13!m 2.95E-06 2.68E-07 0.00E+00 2.95E-06 0.00E+00 0.00E+00 0.00E+00 0.00E-00 Totals 3.89E-02 1.92E-04 0.00E+00 8.89E-02 1.90E-03 7.47E-05 0.00E+00 1.90E-03 17 , _ __
FIGURE l-5b Liquid Radwast e D at a Co'mpi l at i on ' f or Reg. Guide 1.21 Repor*
E. I. Hatch Nuclear Plant UNIT 2 b Tot al Activity (Curies)
Quarter 1, 1981 Quarter 2, 1981 Batches 1 thru 253 Batches 254 thru 456 Error High LLDs Tot al Measured Error High LLDs Total Hame Measured Ce-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00,3.47E-04 2.16E-05 0.00E+00 3.47E-04 Tc-99m 8.48E-06 1.23E-06
- 8.48E-06 6.15E-05 1.33E-06
- 6.15E-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 0.00E+00 Hp-239 0.00E+00 0.00E+00
- 0.00E+00 0.00E+00 0.00E+00
- 1.77E-04 1.57E-05
- 1.77E-04 3.72E-04 2.21E-05
- 3.72E-04 Cr-51 I-131 4.60E-04 7.08E-06 0.00E+00 4.60E-04 1.93E-05 1.46E-06 0.00E+00 1.93E-05 0.00E+00 Zn-69m 0.00E+00 0.00E+00
- 0.00E+00 0.00E+00 0.00E+00
- 0.00E+00 0.00E+00
- 0.00E+00 0.00E+00 0.00E+00
- 0.00E+00 W-187 F-18 3.99E-05 2.72E-06
- 3.99E-05 1.15E-04 5.06E-06
- 1.15E-04 0.00E+00 0.00E+00
- 0.00E+00 1.47E-05 1.52E-06
- 1.47E-05 I-133 0.00E+00 0.00E+00
- 0.00E+00 0.00E+00 0.00E+00
- 0.00E+00 Ba-140 As-76 5.51E-06 9.88E-07
- 5.51E-06 5.23E-06 1.18E-06
- 5.28E-06 Cs-134 1.21E-03 1.06E-05 0.00E+00 1.21E-03 3.92E-03 2.00E-05 0.00E+00 3.92E-03 Cs-137 1.59E-03 1.38E-05 0.00E+00 1.59E-03 4.59E-03 2.18E-05 0.00E+00 4.59E-03 Mo-99 1.73E-05 7.87E-06 0.00E+00 1.73E-05 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
- 1.79E-04 9.31E-06
- 1.79E-04 2.34E-05 2.51E-06
- 2.84E-05 Zr-95 Hb-95 4.40E-04 8.64E-06
- 4.40E-04 9.12E-05 3.41E-06
- 9.12E-05 0.00E+00 0.00E+00
- 0.00E+00 0.00E+00 0.00E+00 + 0.00E+00 I-132 Co-58 9.74E-04 1.04E-05 0.00E+00 9.74E-04 1.70E-04 4.73E-06 0.00E+00 1.70E-04!
(); Mn-54 3.53E-04 7.43E-06 0.00E+00 3.53E-04 1.97E-04 6.24E-06 0.00E+00 Ag-110m 2.71E-06 6.64E-07 + 2.71E-06 0.00E+00 0.00E+00
- 1.97E-04 0.00E+00-Zn-65 6.24E-03 4.20E-05 0.00E+00 6.24E-O' 3.04E-03 3.25E-05 0.00E+00 3.04E-03 1.37E-06 I-135 1.38E-06 6.81E-07
- 1.38E-06 1.37E-06 8.59E-07
- Fe-59 1.16E-05 3.07E-06 0.00E+00 1 16E-05 3.94E-06 1.14E-06 0.00E+00 3.94E-06 Co-60 2.05E-03 1.92E-05 0.00E+00 2.05E-03 2.00E-03 1.77E-05 0.00E+00 +
2.00E-03 Cu-64 0.00E+00 0.00E+00
- 0.00E+00 1.14E-04 4.23E-05 1.14E-04.
Ha-24 2.13E-04 4.81E-06
- 2.13E-04 3.35E-03 1.55E-05
- 3.35E-03!
0.00E+00 0.00E+00
- 0.00E+00 0.00E+00 0.00E+00
- 0.00E+00 La-140 0.00E+00 Mn-56 0.00E+00 0.00E+00
- 0.00E+00 0.00E+00 0.00E+00
- Cs-136 4.53E-05 2.11E-06
- 4.53E-05 7.94E-06 1.76E-06
- 7.94E-06 2.72E-06 0.00E+00 0.00E+00
- 0.00E+00 Cs-138 2.72E-06 3.04E-07 *
+ 0.00E+00 Rb-88 2.28E-06 1.06E-06 + 2.29E-06 0.00E+00 0.00E+00 Sr-89 7.98E-05 2.11E-05 0.00E+00 7.98E-05 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 9.09E-02 5.14E-03 0.00E+00 9.09E-02:
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' 1.41E-02 6.01E-05 0.00E+00 1.41E-02 1.09E-01 5.14E-03 0.00E+00 1.09E-01l Tot al s Xe-133 3.92E-03 8.70E-04 0.00E+00 3.92E-03 4.40E-04 1.24E-05 0.00E+00 4.40E-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 7.03E-06 1.72E-06 0.00E+00 7.03E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 2.78E-03 1.19E-05 0.00E+00 2.78E-03 5.88E-04 7.03E-06 0.00E+00 5.88E-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 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.43E-08 2.65E-09 0.00E+00 1.43E-08 Tot al s 6.72E-03 8.70E-04 0.00E+00 6.72E-03 1.03E-03 1.42E-05 0.00E+00 1.03E-03
+ No LLD requirement in Tech Spec -
.38. . .
'G- .
TABLE l-la
,E. I. Hatch Nuclear. Plant UNIT 1 4
6;fy EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1981 i LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Tot al 1 2 Error %
R. Fission & activation products-
~~
- 1. Total release (not including H3, qases, al pha) Ci 5.01E-02 1.22E-01 4.56E+01
- 2. Average diluted concentration durino period uCi/mi 3.39E-08 '6.89E-08
- 3. Percent of applicable Ilmtt % 3.25E+00 3.44E-01 B. Tritium
- 1. Total release 1 Cs 5.37E+00 1.94E+00 3.23E+01l
- 2. Average diluted concentration durino period uCi/ml 3.64E-06 1.10E-06
- 3. Percent of appitcable Ilmit % 1.21E-01 3.66E-02 C. Dissolved and entrained gases
- 1. Total release Ci 8.89E-02 1.90E-03 1.00E+02l
- 2. Average diluted concentration
durino period uCi/ml 6.02E-08 1.08E-09
- 3. Percant of applicable limit % 1.51E-01 2.69E-03 D. Gross alpha radi oact ivi ty l 1. Total release l Ci l 1.17E-061 1.52E-05l 1.20E'02) lE. Volume of uaste (orior to dilution)l liters i 7.62E+06l 7.92E+06l 1.00E+01l lF. Volume of dilution w at er used l liters l 1.47E+09) 1.76E+091 1.60E+02l 19
=.'
TABLE l-Do g4 (g ,E. I. Hatch Nuclear Plant UNIT 2 EFFLUENT AND WRSTE DISPOSAL SEMIANNURL REPORT 1981 LIQUID EFFLUENTS-SUMMRTION OF ALL RELEASES Unit Quarter ' Quarter Est Tot al 1 2 Error %
4 A. Fission & activation products
- 1. Total release (not including H3, cas e s , al pha) Ci 1.41E-02 1.09E-01 4.62E+01
- 2. Average diluted concentration durino period uCi/mi 6.67E-09 8.81E-08
- 3. Percent of applicable limit % 9.15E-02 8.93E-02 B. Tritium
- 1. Total release Ci 2.40E+00 2.58E+00 3.12E+01l
- 2. Average diluted concentration i
durino period uCi/ml 1.13E-06 2.08E-06
- 3. Percent of applicable limit % 3.78E-02 6.94E-02 C. Dissolved and entrained gases
- 1. Total release Ci 6.72E-03 1.03E-03 1.11E+02l
- 2. Average diluted concentration durino period uCi/ml 3.17E-09 8.28E-10
- 3. Percent of appl i c abl e limit % 7.94E-03 2.07E-03 D. Gross alpha radioactivity l 1. Total release l Ci l 1.60E-07i 2.45E-06) 1.20E+02l lE. Volume of uaste (prior to dilution >l liters l 8.26E+06l 6.34E+06l 1.00E+01l IF. Volume of dilution water used I liters l 2.11E+091 1.23E+091 1.60E+02l 20
TABLE 1-2a 4*Eh E. I. Hatch Nucl ear Pl ant UNIT.1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 i ,
LIQUID EFFLUENTS I
- CONTINUOUS MODE BRTCH MODE Nuclides Released Unit Quacter Quarter Quarter Quarter 1 2 1 2 Ce-144 Ci 7.25E-04 3.93E-05 Te-99m Ci 3.03E-04 5.40E-05 Ce-141 Ci 0.00E+00 0.00E+00 Hp-239 Ci 0.00E+00 0.00E+00 Cr-51 Ct 1.02E-03 6.18E-05 I-131 Ci 1.36E-02 5.97E-04 Zn-69m Ci 0. ROE +00 0.00E+00 W-137 Ci 1.33E-05 0.00Ef00 F-18 Ci 1.23E-04 0.00E+t0 I-133 Ci 2.40E-04 0.00E+00 Ba-140 Ci 0.00E+00 0.00E+00 As-76 Ci 0.00E+00 0.00E+00 l Cs-134 Ci 1.24E-02 2.21E-02 Cs-137 Ci 1.36E-02 2.61E-02 I
Mo-99 C1 2.92E-05 8.65E-05 Zr-97 Ci 9.97E-07 0.00E+00 4
Zr-95 Ci 2.98E-05 5.84E-05 _
Nb-95 C1 1.39E-04 2.74E-04 I-132 Ci 0.00E+00 0.00E+00
.." 8.86E-05 6.48E-05 Co-58 Ci Mn-54 Ci 2.92E-04 4.98E-04 Ro-110m C1 1.62E-05 2.21E-05 Zn-65 Ci 3.79E-03 7.98E-03
. I-135 Ci 0.00E+00 0.00E+00 Fe-59 Ci 2.48E-05 0.00E+00 Co-60 Ci 2.62E-03 4.39E-03 Cu-64 Ci 0.00E+00 0.00E+00 Ha Ci 0.00E+00 0.00E+00 La-140 C1 1.82E-04 0.00E+00 Mn-56 Ci 0.00E+00 0.00E+00 Cs-136 Ci 8.28E-04 6.08E-05 Cs-138 -
C1 1.58E-06 2.61E-06 Rb-88 C1 4.94E-09 0.00E+00 Ni-65 Ci 0.00E+00 4.10E-06
> Sr-89 Ci 4.30E-05 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 j' Fe-55 Ci 0.00E+00 5.92E-02 P-32 Ci 0.00E+00 0.00E+00 l Total for period (above) l Ci l l l 5.01E-02l 1*.22E-011 Xe-133 Ci 5.10E-02 4.36E-04 Kr-88 Ci 0.00E+00 0.00E+00 Xe-133m Ci 1.19E-03 0.00E+00 Xe-135 C1 3.45E-02 9.33E-04 Kr-85m Ci 0.00E+00 1.31E-05 Kr-87 Ci 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 Xe-131m Ci 2.27E-03 5.20E-04 Xe-135m Ci 2.95E-06 0.00E+00 21
. I t---
T ABLE l-Zb ^
Mu h .
E. I. Nat c h Nuc l ear P l ant UNIT 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 l
LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quacter Quarter Quarter Quarter 1 2 1 2 Ce-144 Ci 0.00E+00 3.47E-04 Tc-99m Ci 8.48E-06 6.15E-05_ '
Ce-141 Ci 0.00E+00 0.00E+00 No-239 Ci 0.00E+00 0.00E+00 Cr-51 Ci 1.77E-04 3.72E-04
, I-131 C1 4.60E-04 1.93E-05 i Zn-69m Ci 0.00E+00 0.00E+00 W-187 Ci 0.00E+00 0.00E+00 F-18 Ci 3.99E-05 1.15E-04 1-133 Ci 0.00E+00 1.47E-05 Ba-140 Ci 0.00E+00 0.00E+00 As-76 Ci 5.51E-06 5.28E-06 Cs-134 Ci 1.21E-03 3.92E-03 l Cs-137 Ci 1.59E-03 4.59E-03 Mo-99 C1 1.73E-05 0.00E+00 Zr-97 Ci 0.00E+00 0.00E+00 Zr-95 C1 1.79E-04 2.84E-05 IA Hb-95 Ci 4.40E-04 9.12E-05
- I-132 Ci 0.00E+00 0.00E+00 Co-58 Ci 9.74E-04 1.70E-04 Mn-54 Ci 3.52E-04 1.97E-04 Aa-110m Ci 2.71E-06 0.00E+00 Zn-65 Ci 6.24E-03 3.04E-03 I-135 C1 1.38E-06 1.37E-06 i Fe-59 Ci 1.16E-05 3.94E-06 Co-60 Ci 2.05E-03 2.00E-03 Cu-64 Ci O.00E+00 1.14E-04 Na-24 Ci 2.13E-04 3.35E-03 La-140 Ci 0.00E+00 0.00E+00 Mn-56 Ci 0.00E+00 0.00E+00
! Cs-136 C1 4.53E-05 7.94E-06 Cs-138 -
Ci 2.72E-06 0.00E+00 Rb-88 Ci 2.2SE-06 0.00E+00 Sr-89 Ci 7.98E-05 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 Fe-55 Ci ) 0.00E+00 9.09E-02 P-32 Ci j 0.00E+00 0.00E+00 .
l Total for period (above) l Ci l l l 1.41E-02l 1.09E-011 Xe-133 Ci 3.92E-03 4.40E-04 Kr-88 Ci 0.00E+00 0.00E+00 Xe-133m Ci 7.03E-06 0.00E+00
' 2.78E-03 5.88E-04 Xe-135 Ci
'~
Kr-85m Ci 0.00E+00 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 1.43E-08 22
2 GASEOUS EFFLUENTS 2.1. REGULATORY LIMITS
- a. (1) The release - rate limit of noble gases from the site p',};
shall be:
_ _~ . _ _
E Qis ,1.9 E6+ 1.0 E3, + Qiy ,11 E6 + 44 E B, 11 i +n where Qs = Total release rate from 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 56 = The average gamma energy per disintegration E B= The average beta energy per disintegration (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 Ops + 1.5 X 10 6 gpy <1 Where Op s = Total release rate from the main stack for both Units in Ci/sec (as elevated release)
Oy p = Total release rate from vents for both Units in.Ci/sec (ground releases)
- b. (1) The average release rate of noble gases from the site during any calendar quarter shall be:
E Qis 12 E6 + 3.0 EB + Qiv '66 56
+ 140 E B, 11 1 +n -
(2) The average release rate of noble gases during any 12 consecutive months shall be:
r E Qs i _
24 E6 + 6.1 EB! +Ov i L13 -E6+ 270 E B ; l 11 1 +n " -
l (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 10 7 gpy <1 i
(4) The average release rate of all radio iodines and radioactive materials in particulate form from the site s
l 23
with half lives greater than eight days during any period of 12 consecutive months shall be:
2.6 X 106 Qps + 3.7 x 10 7 Opv <1
/$ (5) The amount of Iodine - 131 released during any calendar v quarter shall not exceed 2 Ci/ reactor.
(6) The amount of Iodine - 131 released during any period of 12 consecutive months shall not excced 4 Ci/ reactor.
- c. Should the conditions of 2.1.3c (1), (2) , or (3) listed below occur, the licensee shall make an investigation to identify the causes of the release. rates,
~
define and initiate a program of action to reduce the release rates to design objective levels listed in subsection 2.1 of the HNP-ETS and report these actions to the Commission within 30 days from the 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:
E Qis 47 E6 + 12 Ea, +Qv i
h60E6 + 540 Es '
>1 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:
h:/ 5.0 X 106 Ops + 7. 2 X. J.07 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 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.
i i...
24 i
- h. (1) Potentially - explosiva gas mixtures of hydrogen and oxygen contained in the offgas system downstream of the recombiners shall be. continuorsly 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%
v 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, 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 I 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.
n Q (3) The installed hydrog.en_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 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 l 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 l period (Procedures are such that shorter collection times are
- used where applicable to Technical Specification requirements).
l -
'4 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 g'i (accuracy of these devices are within 10% of the actual flows as measured during preoperational testing) . The recombiner building vent flow on Unit One is conservatively assumed to be constant at 500 CFM. In addition to the gaseous, particulate, and iodine release measurements tritium, gross alpha and gaseous isotopic measurements of each vent stream are conducted on a monthly schedule.
After each calendar quarter (13 weeks) a summary of waste gas release from the four vents is compiled and as such is designed to meet the requirements for preparation of the 6-month report as specified in Regulatory Guide 1.21. Unit one and two releases were calculated together because the Tech. Specifications for the two reactors are identical in this respect. The methods for compilation of the quarterly releases are as follows:
- 1. FISSION AND ACTIVATION GAS The total curie release is determined from the continuously reading gaseous monitors in addition to the vent flow recorders. Activity monitors and vent flow rate readings 4
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 Q, 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 y &
E)
B along with the coefficients in the release limit formula in our Environmental Technical Specifications. All of the nuclides are summed and stored in their respective data files until the end of the quarter. Then the computer divides the sum of the nuclides by the seconds in the quarter to determine the percent of the tech. spec. limit released.
- 2. RADIOIODINE RELEASES Iodine releases are determined weekly for I-131, I-133, and I-135, for each vent. Where significant activity is not measured MDA releases are calculated. Since calculated MDA's are below Technical Specification detectable concentrations then 0 (zero) release is used for the weeks with only MDA values. Weekly releases are summarized with the aid of the counting room calculator - computer system and a quarterly total is prepared from the weekly summaries. The percent Technical Specification for I-131 on Table 2-1 is based on the quarterly Technical Specification limit.
e 26
~
f 4
- 3. PARTICULATE RELEASES Particulate releases are determined weekly for each vent.
Where significant activity is not measured MDA release is calculated. Since calculated MDA's are below Technical Specification detectable concentrations, then 0 (zero) release is used for weeks with only MDA values. Weekly releases are summarized with the aid of the counting room calculator - computer.
After each calendar month the particulate filters from each vent are combined, fused, and strontium separation is made.
Since sample flows and vent flows are almost constant over each monthly period the filters from each vent can be dissolved together. Decay corrections are made back to the middle of the quarterly collection period. Again the counting room calculator - computer is used to aid in the calculation of the Sr-89, 90 release. Where significant strontium activity is not detected MDAs are calculated. The percent of Technical Specification was calculated using quarterly average equation.
- 4. GROSS ALPHA RELEASE The gross alpha release is computed each month by counting
, the particulate filters each week for gross alpha activity in a proportional counter. The four or five weeks numbers are then recorded on a data sheet and the activity is summed at the end of the month.
- 5. TRITIUM RELEASE Tritium samples .are obtained monthly from each vent by passing the sample stream from a cold trap immersed in a liquid nitrogen or an acetone and ice mixture. The grams of
. water vapor / cubic foot gas is measured upstream of the cold trap in order to alleviate the difficulties in determining water vapor collection efficiencies. The tritium samples are analyzed by an independent laboratory. From the uCi/ml tritium concentration, the grams water /ft3, and the vent flow rates, the monthly tritium release is calculated for each vent, and the . quar terly 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.
Regulatory Guide 1.21 requires that estimated total error in analysis techniques be reported. These estimates are required for the total fission and activation gas release, total I-131 27 l
release, total particulates with half-live's greater than 8-day release, and total tritium release.
"The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total operation of sampling and measurement.
Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error are not suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste."
Estimated errors are based on errors in counting equipment calibration, counting statistics, vent flow rates, vent sample flow rates, non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges.
- 1. Fission and Activation Gas Total Release was calculated from process monitor readings. As 96.71% of this release was 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%
I-131 Release was calculated from each weekly sample:
{ 2.
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%
l 3. Particulates with half-lives greater than 8 days release was i
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%
i Countng Equipment Calibration 10%
Vent Flow Rates 10%
Vent Sample Flow Rates 10%
Non-Steady Release Rates 10%
1 TOT
- 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 l (_- releases do not affect the error in the total tritium
! release:
28 l
~
Water Vapor in Sample Stream Determination 20%
Vent Flow Rates 10%
Counting Calibration and Statistics 10%
Non-Steady Release 50%
, , , 90%
fr9 '
- 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 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 5.6.1 of the HNP-ETS.
h' 3.2 SOLID WASTE DATA , _ _
Regulatory guide 1. 21. Table 3 is found in this report as Table 3-la, b.
9 9
29
~
TABLE 2-la jf34 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 kbr GASEQUS EFFLUENTS-SUMMATION OF ALL RELEASES (UNIT 1) '
Unit Quarter Quarter Est Total E. I. Hatch Nuc l ear Power Plant UNIT 1 1 2 Error %
A. Fission & activation gases
- 1. Total release Ci 4.53E+03 8.18E+01 8.00E+01l
- 2. Average release rate for period uCi/sec 5.76E+02 1.04E+01
- 3. % of Technical specification limit % 3.02E-01 1.09E-02 B. Iodines
- 1. Tot al iodine-131 Ci 6.95E-02 2.10E-03 1.10E+02l
- 2. Average release rate for period uCi/sec 8.84E-03 2.67E-04
- 3. % of Technical specification limit % 3.48E+00 1.05E-01 C. Particulates
- 1. P art i cul at es wi th hal f-l i ves >8 davs C1 3.70E-03 1.26E-03 1.00E+02l
- 2. Average release rate for period uCi/sec 4.70E-04 1.61E-04
- 3. % of T e c h r. i c al specification limit % 7.34E-01 2.41E-01
- 4. Gross alph a radi oact ivi tv Ci 3.53E-06 1.91E-06 D. Tritium
- 1. Total release C1 1.16E+00 1.07E+00 9.00E+01l J. 2. Average release rate for period uCi/see 1.47E-01 1.37E-01
' 3. % of Tec hni c al specification limit % 2.62E+00 1.18E+00 e
Y 30
TABLE 2-Da ja .,
EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1981 is GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (QC00 2).
Unit Quarter Quarter Est Total E. I. Hatch Nuc lear Pouer Pl ant UNIT 2 1 2 Error %
A. Fission & activation gases
- 1. Total release C1 1.94E+01 4.24E+01 8.00E+01l
- 2. Aversoe release rate for period uCi/sec 2.47E+00 5.39E+00
- 3. % of Technical specification limit % 1.23E-02 2.71E-02 B. Iodines
- 1. Tetal iodine-131 C1 1.40E-03 7.44E-05 1.10E+02l
- 2. Average release rate for period uCi/sec 1.78E-04 9.47E-06
- 3. % of Technical spec i fi c at i on limit % 7.00E-02 3.72E-03 C. Part i c u l at e s
- 1. Particulates uith half-lives >8 davs C1 6.01E-05l 1.18E-04 1.00E+02l
- 2. Average rel ease rate for period uCi/sec 7.65E-06i 1.50E-05
- 3. % of Technical spec i fi c at i on limit % 1.42E-02 5.90E-03
- 4. Gross alpha radioactivity Ci 9.83E-08 1.48E-07 D. Tritium
- 1. Total release Ci 4.41E-01 1.23E+00 9.00E+01l l q.
{,2- 2. Average release rate for period uCi/sec 5.61E-02 1.57E-01
- 3. % of Technical spec i fi c at i on limit % 7.81E-01 2.35E+00 e
k a
31
T ABLE 2-ic
/ - EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 GASEOUS EFFLUENTS-SUMMRTION OF ALL RELEASES (SITE)
Unit Quarter Quarter Est Total E. I. Hatch Nuclear Power Plant SITE 1 2 Error %
R. Fission & activation gases
- 1. Total release C1 4.55E+03 1.24E+02 8.00E+011
- 2. Averace release rate for period uCi/sec 5.78E+02 1.58E+01
- 3. % of Tec hni c al spec i f i c at i on limit % 3.14E-01 3.80E-02 B. Iodines
- 1. Total iodine-131 Ci 7.09E-02 2.18E-03 1.10E+021
- 2. Average release rate for period uCi/sec 9.02E-03 2.77E-04
- 3. % of Technical spec i fi c at i on limit % 1.77E+00 5.44E-02 C. Part i c ul at e s
- 1. Particulates with half-lives >8 davs Ci 3.76E-03 1.38E-03 1.00E+02l
- 2. Average rel ease rate for period uCi/sec 4.78E-04 1.76E-04
- 3. % of Technical spec i f i c at i on limit % 7.49E-01 2.47E-01 4 Gross al pha radi oact i vi to Ci 3.62E-06 2.06E-06 1 D. Tritium
- 1. Tot al release C1 1.60E+00 2.31E+00 9.00E+01l
- 2. Average release rate for period uCi/see 2.03E-01 2.93E-01 29 % 3.40E+00 3.53E+00
- 3. % of Technical spec i f i c at i on limit i
I i
l l
32
~ i TABLE 2-2a E. I . ' Hatch Nuc l ear Pouer Pl ant UNIT 1 p t 1,;j7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE Huclides Released Unit Quarter Quarter Quarter, Quarter 1 2 1 2
- 1. Fission gases Xe-133 C1 3.01E+03 9.79E+00 0.00E+00 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
! Kr-88 Ci 2.92E+02 1.26E+00 0.00E+00 0.00E+00 Xe-133M Ci 6.25E+01 0.00E+00 0.00E+00 0.00E+00 Xe-135 Ci 8.75E+01 3.07E+01 0.00E+00 0.00E+00 Kr-85M C1 5.30E+02 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ci 5.29E+01 2.54E+00 0.00E+C0 0.00E+00
! Xe-138 Ci- 1.53E+02 1.54E+01 0.00E+00 0.00E+00 1 Xe-137 Ci 8.82E+00 0.00E+00 0.00E+00 0.00E+00 N-13 C1 1.G5E+02 1.33E+01 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ci 7.98E+01 2.76E-01 0.00E+00 0.00E*00 I-133 Ci 0.00E+00 0.00'E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 C1 1.53E+01 7.02E+00 0.00E+00 0.00E+00 C($ Tot al for period Ci 4.39E+03 8.02E+01 0.00E+00 0.00E+00
- 2. Iodines :
I-131 Ci 2.11E-02 7.51E-05 0.00E+00 0.00E+00 I-133 C1 1.26E-02 6.65E-04 0.00E+00 0.00E+00 1-135 C1 2.67E-03 1.70E-04 0.00E+00 0.00E+00 Tot al for period Ci 3.64E-02 9.10E-04 0.00E+00 0.00E+00
- 3. Part i c u l at es Sr-89 Ci 2.70E-04 1.16E-04 0.00E+00 0.00E+00 Sr-90 Ci 6.90E-07 2.43E-07 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 1-131 C1 1.09E-04 2.03E-08 0.00E+00 0.00E+00 i Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 C1 1.03E-04 5.98E-05 0.00E+00 0.00E+00 Cs-134 C1 1.88E-06 3.33E-07 0.00E+00 0.00E+00 Cs-137 Ci 7.36E-06 2.40E-06 0.00E+00 0.00E+00 Ce-144 C1 2.42E-06 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ct 1.13E-07 1.98E-07 0.00E+00 0.00E+00 Hb-95 C1 1.03E-05 3.81E-06 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 6.91E-07 0.00E+00 0.00E+00 La-140 Ci 2.00E-04 1.04E-04 0.00E+00 0.00E+00 Tot al for period Ci 7.05E-04 2.87E-04 0.00E+00 0.00E+00 33 ... _ - .
- F TABLE 2-?t E. I. Hatch Nuc lear Power Pl ant UNIT 2 O. ; . .
Lie EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE Huclides Released Unit Quarter Quarter Quarter Quarter 1 2 1 2
, 1. Fission gases 4
Xe-133 Ci 7.18E+00 3.42E+00 0.00E+00 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 6.97E-01 4.41E-01 0.00E+00 0.00E+00 Xe-133M C1 1.49E-01 0.00E+00 0.00E+00 0.00E+00 Xe-135 C1 2.09E-01 1.07E+01 0.00E+00 0.00E+00 Kr-85M C1 1.27E+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-87 C1 1.26E-01 8.85E-01 0.00E+00 0.00E+00 Xe-138 Ci 3.64E-01 5.36E+00 0.00E+00 0.00E+00 Xe-137 Ci 2.11E-02 0.00E+00 0.00E+00 0.00E+00 N-13 C1 2.50E-01 4.63E+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 1.91E-01 9.63E-02 0.00E+00 0.00E+00 I-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 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 C1 3.65E-02 2.45E+00 0.00E+00 0.00E+00 Tot al for period Ci 1.05E+01 2.80E+01 0.00E+00 0.00E+00 f
- 2. Iodines I-131 Ci 5.03E-05 2.62E-05 0.00E+00 0.00E+00 I-133 C1 3.02E-05 2.32E-04 0.00E+00 0.00E+00 I-135 Ci 6.38E-06 5.93E-05 0.00E+00 0.00E+00 Tot al for period Ci 8.69E-05 3.18E-04 0.00E+00 0.00E+00
- 3. P ar t i c u l at es Sr-89 Ci 6.45E-07 4.04E-05 0.00E+00 0.00E+00 3r-90 Ci 1.65E-09 8.49E-08 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- Cc-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 2.61E-07 7.09E-09 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 2.46E-07 2.09E-05 0.00E+00 0.00E+00 Cs-134 C1 4.48E-09 1.16E-07 0.00E+00 0.00E+00 C2-137 Ci 1.76E-08 8.38E-07 0.00E+00 0.00E+00 Ce-144 Ci 5.79E-09 0.00E+00 0.00E+00 0.00E+00 l 2r-95 Ci 2.70E-10 6.93E-08 0.00E+00 0.00E+00 l Hb-95 C1 2.46E-08 1.33E-06 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00
'q Co-60 Ci 0.00E+00 2.41E-07 0.00E+00 0.00E+00 l
l La-140 Ci 4.77E-07 3.63E-05 0.00E+00 0.00E+00 Tot al for period Ci 1.68E-06 1.00E-04 0.00E+00 0.00E+00 34
21 TABLE 2-2c E. I& Hatch Hu'1 ear Power Plant SITE
$?+'
u 14 EFFLUENT AND WASTE DISPOSAL' SEMIANNUAL REPORT 1981 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE Huclides Released Unit Quarter Quarter Quarter Quarter 1 2 1 2
- 1. Fission gases Xe-133 C1 3.02E+03 1.32E+01 0.00E+00 0.00E+00 Xe-131M Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 2.93E+02 1.70E+00 0.00E+00 0.00E+00 Xe-133M Ci 6.27E+01 0.00E+00 0.00E+00 0.00E+00 Xe-135 Ci 8.77E+01 4.14E+01 0.00E+00 0.00E+00 Kr-85M Ci 5.31E+02 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 0.00E+00 0.00E+004 0.00E+00 Kr-87 Ci 5.30E+01 3.42E+00 0.00E+00 0.00E+00 Xe-138 C1 1.53E+02 2.07E+01 0.00E+00 0.00E+00 Xe-137 Ci 8.84E+n0 0.00E+00 0.00E+00 0.00E+00 N-13 C1 1.05E+02 1.79E+01 0.00E+00 0.00E+00 Kr-85 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ct 8.00E+01 3.72E-01 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 Ar-41 Ci 1.53E+01 9.47E+00 0.00E+00 0.00E+00
} Tot al for period Ci 4.41E+03 1.08E+02 0.00E+00 0.00E+00 t
- 2. Iodines .
! I-131 Ci 2.11E-02 1.01E-04 0.00E+00 0.00E+00 I-133 Ci 1.27E-02 8.98E-04 0.00E+00 0.00E+00
}
i I-135 Ci 2.68E-03 2.29E-04 0.00E+00 0.00E+00 Total for period Ci 3.65E-02 1.23E-03 0.00E+00 0.00E+00
- 3. P art i c u l at es Sr-89 Ci 2.71E-04 1.56E-04 0.00E+00 0.00E+001
$r-90 Ci 6.91E-07 3.28E-07 0.00E+00 0.00E+001 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+001 Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+001 I-131 Ci 1.10E-04 2.74E-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 1.03E-04 -8.06E-05 0.00E+00 0.00E+00 C5-134 Ci 1.88E-06 4.50E-07 0.00E+00 0.00E+00 Cs-137 Ci 7.38E-06 3.24E-06 0.00E+00 0.00E+00 Ce-144 Ci 2.43E-06 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ci 1.13E-07 2.68E-07 0.00E+00 0.00E+00 Nb-95 C1 1.03E-05 5.14E-06 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 9.33E-07 0.00E+00 0.00E+00 0.00E+00 La-140 Ci 2.00E-04 1.40E-04 0.00E+00 l
l Tot al for period Ci 7.07E-04 3.87E-04 0.00E+00 0.00E+00 35
l 63 00+E00 0 00+E00 0 40-E77 9 30-E99 2 iC doirep rof la tot 00+E00.s 00+E00 0 00+E00 0 60-E83 6 iC 041-aL 00+E00 0 00+E00 0 40-E23 1 50-E94 7 iC 06-oC ' '
00+E00 0 00+E00 0 00+E00 0 00+E00 0 iC 95-eF 00+E00 0 00+E00 0 60-E79 5 60-E47 8 iC 45-nM 00+E00 0 00+E00 0 00+E00 0 00+E00 0 iC 85-oC 00+E00 0 00+E00 0 50-E94 6 50-E62 3 iC 59-bM I
00+E00 0 00+E00 0 60-E55 6 70-E00 8 iC 59 -rZ 00+E00 0 00+E00 0 00+E00 0 00+E00 0 iC 441-eC 00+E00 0 00+E00 0 40-E34 3 40-E10 6 iC 731-zC 00+E00 0 00+E00 0 40-E04 2 40-E62 5 iC 431-sC i 00+E00 0 00'E00 0 00+E00 0 00+E00 0 iC 041-aB 00+E00 0 00+E00 0 00+E00 0 00+E00 0 iC 311-nS 00+E00 0 00+E00 0 60-E39 9 30-E86 1 iC 131-I 00+E00 0 00+200 0 40-E55 1 60-E18 5 iC 15-rC 00+E00 0 00+E00 0 00+E00 0 00+E00 0 iC 141-eC 00+E00 0 00+E00 0 70-E32 5 60-E48 1 iC 09-rS 00+E00 0 600+E00 0 50-E29 1 50-E83 5 iC - 98-rS setalucitraP 3 00+E00 0 00+E00 0 30-E72 2 20-E75 5 iC doirep rof la tot 1
00+E00 0 00+E00 0 40-E32 1 30-E49 2 1C 531-I 00+E00 0 00+E00 0 40-E92 1 30-E21 6 iC 331-I 00+E00 0 00+E00 0 30-E20 2 20-E76 4 iC 131-I senidoI 2 00+E00 0 00+E00 0 00+E06 1 20+E13 1 iC doirep rof la tot ;
00+E00 0 00+E00 0 00+E00 0 00+E00 0 iC 14-rA 00+E00 0 00+E00 0 00+E00 0 00+E00 0 iC 531-I 00+E00 0 00+E00 0 00+E00 0 00+E00 0 iC 98-rK ~
00+E00 0 00+E00.O '00+E00 0 00+E00 0 iC 331-1 00+E00 0 00+E00 0 10-E96 7 10+E15 3 iC M531-eX 00+E00 0 00+E00 0 00+E00 0 00+E00 0 iC 58-rK 00+E00 0 00+E00 0 20-E65 9 10-E13 2 iC 31-H '
00+E00 0 00+E00 0 00+E00 0 00+E00 0 iC 731-eX 00+E00 0 00+E00 0 10-E74 2 00+E32 1 iC 831-eX 00+E00 0 00+E00 0 20-E48 2 00+E57 3 iC 78-rK 00+E00 0 00+E00 0 00+E00 0 00+E00 0 iC 131-I I
! 00+E00 0 00+E00 0 00+E00 0 10-E28 9 iC M58-rK 00+E00 0 00+E00 0 10-E36 4 10+E96 4 iC 531-eX (00+E00 0 00+E00 0 00+E00 0 10-E36 9 iC M331-eX
,.0+E00 0 00+E00 0 00+E00 0 00+E01 1 iC 88-rK
'^+E00 0 00+E00 0 00+E00 0 00+E00 0 iC M131-eX 00+E00 0 00+E00 0 00+E00 0 10+E80 4 iC 331-eX sesag noissiF 1 t 2 1 2 1 retrauQ retrauQ retrauQ retrauQ tinU desaeleR sedilcuH EDOM HCTRB EDOM SUOUNITNOC ESAELER LEVEL-DNUORG-STNEULFFE SUOESAG 1891 TROPER LAUNNAIMES LASOPSID ETSAW DNA TNEULFFE "EC 1 TINU tna lP reuoP rae l cuN hctaH .I .E a3-2 ELB AT
TABLE 2-3a' E. I. Hatch Nuclear Power Plant UNIT 1 f*V- "
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTINUOUS MODE BATCH NODE Huclides Released Unit Quarter Quarter Quarter Quarter 1 2 1 2 s'
- 1. Fission gases Xe-133 Ci 4.08E+01 0.00E+00 0.00E+00 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 1.10E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133M Ci 9.63E-01 0.00E+00 0.00E+00 0.00E+00 Xe-135 Ci 4.69E+01 4.63E-01 0.00E+00 0.00E+00 Kr-85M Ci 9.82E-01 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ci 3.75E+00 2.84E-02 0.00E+00 0.00E+00 Xe-138 Ci 1.23E+00 2.47E-01 0.00E+00 0.00E+00 Xe-137 Ci 0.00E400 0.00E+00 0.00E+00 0.00E+00 i N-13 Ci 2.31E-01 9.56E-02 0.00E+00 0.00E+00 Kr-85 Cf 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M C1 3.51E+01 7.69E-01 0.00E+00 0.00E+00
- I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t
I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 0.00E+00 0.00E+00~ 0.00E+00 0.00E+00 Tot al for period Ci 1.31E+02 1.60E+00 0.00E+00 0.00E+00
, i
- 2. Iodines .
I-131 C1 4.67E-02 2.02E-03 0.00E+00- 0.00E+00 I-133 Ci 6.12E-03 1.29E-04 ,0.00E+GO 0.00E+00 l I-135 C1 2.94E-03 1.23E-04 9.00Ev00 0.00E+00 Tot al for period Ci 5.57E-02 2.27E-03 0.00E+00 0.00E+00
- 3. Particulates Sr-89
- Ci 5.38E-05 1.92E-05 0.00E+00i 0.00E+00 Sr-90 Ci 1.84E-06 5.23E-07 0.00E+00 0.00E+00 Ce-141 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cc-51 Ci 5.31E-06 1.55E-04 0.00E+00 0.00E+00 I-131 Ci 1.68E-03 9.93E-06 0.00E+00 0.00E+00 l Sn-113 Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 Ci 5.26E-04 2.40E-04 0.00E+00 0.00E+00 Cz-137 Ci 6.01E-04 3.43E-04 0.00E+00 ' O.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00; 0.00E+00
- Zr-95 Ci 8.00E-07 6.55E-06 0.00E+00 0.00E+00
[ Hb-95 Ci 3.26E-05 6.49E-05 0.00E+00 0.00E+00
! Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Mn-54 Ci 8.74E-06 5.97E-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 7.49E-05 1.32E-04 0.00E+00 0.00E+00 La-140 Ci 6.38E-06 0.00E+00 0.00E+00 0.00E+00 l Tot al for period Ci 2.99E-03 9.77E-04 0.00E+00 0.00E+00 i
i 36
L 3-:
TABLE 2-3b E. I. Hatch Nuc l ear Power Pl ant UNIl 2
("Vi -
'tJJ EFFLUENT.AND WASTE DISPOSAL SENIANNUAL REPORT 1981 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTINU3US MODE BATCH MODE Huclides Reitased Unit Quarter Quarter Quarter Quarter 1 2 1 2 e
- 1. Fission gases Xe-133 Ci 0.63E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 9.81E-01 0.00E+00 0.00E+00 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 Ci 4.65E+00 1.05E+00 0.00E+00 0.00E+00 Kr-85M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ct 8.39E-01 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 4.91E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
) H-13 Ci 2.05E+00 8.01E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ci 3.73E-01 4.21E-01 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
$ Tot al for period Ci 8.89E+00 1.44E+01 0.00E+00 0.00E+00
- 2. Iodines I-131 C1 1.34E-03 4.82E-05 0.00E+00 0.00E+00 I-133 Ci 6.16E-05 3.46E-06 0.00E+00 0.00E+00 I-135 Ci 4.45E-05 0.00E+00 0.00E+00 0.00E+00 Tot al for period Ci 1.44E-03 5.17E-05 0.00E+00 0.00E+00
- 3. Par t i c u l at e s Sr-89 Ci 9.55E-06 7.23E-06 0.00E+00 0.00E-001 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E-001 Ce-141 Ci 0.00E+00 0.00E+00- 0.00E+00 0.00E-00 Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E-00 I-131 Ct 1.20E-05 0.00E+00 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 1.65E-07 0.00E+00 0.00E+00 Ba-140 Ci 2.70E-06 2.00E-06 0.00E+00 0.00E+00 Cs-134 Ci 8.66E-06 4.27E-07 0.00E+00 0.00E+00 Cs-137 Ci 1.32E-05 2.70E-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 2.25E-07 0.00E+00 0.00E+00 Hb-95 Ci 1.52E-06 2.41E-06 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 9.26E-07 ?.33E-07 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 y Co-60 Ci 9.43E-06 7.59E-07 0.00E+00 0.00E+C3 La-140 Ci 4.16E-07 1.41E-06 0.00E+00 0.00E+00 ,
Tot al for period Ci 5.84E-05 1.76E-05 0.00E+00 0.00E+00 37
TABLE 2-3c E. I& Hatch Nuclear Pouer Plant SITE y}h.5, .7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 GASEOUS EFFLUENT 3-GROUND-LEVEL RELEASE CONTINUOUS MODE BATCH NODE Huclides Released Unit Quarter Quarter Quarter Quarter 1 2 1 2
- 1. Fission gases ,
Xe-133 C1 4.08E+01 0.00E+00 0.00E+00 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 C1 2.08E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133M Ci 9.63E-01 0.00E+00 0.00E+00 0.00E+00 Xe-135 Ci 5.15E+01 1.51E+00 0.00E+00 0.00E+00 Kr-85M Ci 9.82E-01 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Kr-87 Ci 4.58E+00 2.84E-02 0.00E+00 0.00E+00 Xe-138 Ci 1.23E+00 5.15E+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 2.28E+00 8.11E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ci 3.54E+01 1.19E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-39 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot al for period Ci 1.40E+02 1.60E+01 0.POE+00 0.00E+00
{}
- 2. Iodines I-131 Ci 4.80E-02 2.07E-03 0.00E+00 0.00E+00 1-133 Ci 6.18E-03 1.33E-04 0.00E+00 0.00E+00 I-135 C1 2.98E-03 1.23E-04 0.00E+00 0.00E+00 Tot al for period Ci 5.72E-02 2.32E-03 0.00E+00 0.00E+00
- 3. P art i c u l at es Sr-89 - l Ci I 6.34E-05 2.64E-05 0.00E+00 0.00E+00j Sr-90 1 Ci i 1.84E-06 5.23E-07 0.00E+00 0.00E+00l L Ce-141 i Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+001 Cr-51 i Ci 5.StE-06 1.55E-04 0.00E+00 0.00E+001 I-131 Ci 1.69E-03 9.93E-06 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 1.65E-07 0.00E+00 0.00E+00 -
Ba-140 Ci 2.70E-06 2.00E-06 0.00E+00 0.00E+00-i Cs-134 Ci 5.35E-04 2.41E-04 0.00E+00 0.00E+00 Cs-137 Ci 6.15E-04 3.45E-04 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ci 8.00E-07 6.77E-06 0.00E+00 0.00E+00 Hb-95 Ci 3.41E-05 6.73E-05 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ct 9.67E-06 6.20E-06 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 L . Co-60 Ci 8.44E-05 1.33E-04 0.00E+00 0.00E+00 La-140 Ci 6.79E-06 1.41E-06 0.00E+00 0.00E+00 Total for period Ci 3.05E-03 9.95E-04 0.00E+00 0.00E+00 38
i TABLE 3-la -
- January 1 through June 30, 1981 .
EFFLUENT AND WASTE DISPOSAL SE.'.1! ANNUAL REPORT (YEAR)19al SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
. FOR UtilT 1 A.SOLIO %'ASTE SHIPPED OFFS 17E FOR UURIAt. OR DISPOSAt. (? tot Irradiated fuell
'~
- 1. Type of waste ' ung, s.nonin Est. To ot Period Error. %
- 4. Spent r: sins, filter SMges, enporator nf 1 14 E+2 bottor-s. etc. Ci 7 .1 o E&1 1.n E&1
- b. Dry,compteutsie waste. contstmasted rn* 1.og E& 2 equip, .e10- . C1 - 6 .13 E+0 1.0 ta-1
- c. Irt:4isted components, control m' n E rods, etc.
Cl 0. E E
- d. Other (desenbe) m' 3.3 6 E+ 2 Contaminated fuel racks Ci 4 63 E+1 . E
- 2. Est im:te of maior nuclide composi:fon (by type of waste)
ISOTOPE !
PERCEllT l CURIES
- a. Cs 137 47.07 :
1499.27 -
cs 134 35.33 1125.38_
Zn 65 8.36 266.18 cn 60 2.07 65.91 Others 7.17 228.37
- b. cs 137 28.17 1.73 Co 60 20.89 1.28 Cs 134 '-
18.76 1.15i Zn 65 '
16.17 .99
. Cr 51 2.83 .17 Others 13.18 .81
- d. co 60 36.20 16.76 Nb 95 24.50 11.34
- r. Zn 65 17.50 8.10 2r 95 12.80 5.93 Cs 137 - ;2.44 1.13 Others .
6.56 3.04 1
- 3. Solid h*:ste Disposition .
Numher orShi:ments Mede of Tans ., ort: tion D::t! nation i 43 Truck or Van ,
Barnwell, SC l 22 Truck or Van Hanford, WA B. IRRADIATED FUEL SillPMCJTS (Dispo ition)
Number of Shior-ents Mod: of Tran:oor:stion Ek stination
~.
~- \
l 39 l
i I
_ _ _ _ . = - . - _ _ . - , _ - - _-_ . - - _ . -_ . _ _ . . . _ _ _ - . - . _ _ ._ -
i
, TABLE 3-lb '
- January 1'through June 30, 1981 h
) EFFLUENT AND V/ ACTE DISPOSAL SE.'.11 ANNUAL REPORT (YEAR) 1981-SOLID WASTE AND IRRADIATED FUEL SHIPT.1ENTS
, FOR UtlIT 2 ,
A. SOLID WASTE SHIPPEt) OFFSITE FOR BURIAL OR DISPOOA L (Not irradiated fuel)
- 1. Type of waste ~~' unt: 8'***a m Est. bool Period Error. x
- a. Spent r: sins, filter sit.dges, enporator m' 1 .1 1 E+ 2 i bottor-.s. etc. Ci
- b. Dry,compressiste waste, contarmnsted
. _ . a .o 5 E+ 1 I.0 E+1 m' 8 57E+2 equip. etc. . Cl 1.nn E+1 1.n t:+ 1
- c. Irt:Jiated cornponents, control m'- Ma E NA rods, etc.
Cl NA E NA E
- d. Other (deser:be) m' vs E_ Ma .
Ci yg E E 33
- 2. Est!:n:te of maior nuclide composition (by type of waste) .
ISOTOPE l PERCEllT CURIES a
a_ Zn 65 36.61 32.66 Cs 137 16.79 14.98 :
en 134 15.00 13.38
), Co 60 9.78 8.73 cr 51 h i Nb 95 co 58 -
9.06 3.16 3.85 8.08 2.82 3.44 others '
6.06 5.41
- b. Cs 137 30.85 -3.33 Co 60 , , 21.59 2.33 cs 134 20.21 2.18 en A9 16.11 1.74 cr 51 2.39 .26 i ch 199 1_83 _2O re 119 1_65 _1R Mn 94 -
1.22 .13 nehorn -
4.13 .45
- 3. Solid Waste Dis;:odtion .
Number of Shi:mgts Mcde ofTr:nsportation D::tfn: tion l
29 Truck or Van , Hanford, WA 23 Truck or Van Barnwell, SC B. IRRADt.',TED FUEL SHIPMENTS (Dis,v.itien)
Number of shier-ents MoJ orTranmortation Dutinstion
~
NA NA NA
~'
fi q
- c. ,
40
_ - - , _ . _ . _ . . - _ _ _ _ _ , _ _ _ .__