ML20100G608
| ML20100G608 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/30/1984 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20100G581 | List: |
| References | |
| NUDOCS 8504080313 | |
| Download: ML20100G608 (43) | |
Text
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- GEORGIA POWER COMPANY PLANT E.
I. HATCH UNITS NO. 1&2 SEMI-ANNUAL REPORT PLANT-RADIOACTIVE EFFLUENT RELEASES JANUARY 1, 1984 - JUNE 30, 1984 O
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40W { $
1 j.
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PLANT E.
I. HATCH SEMIANNUAL REPORT PLANT RADI0 ACTIVE EFFLUENT RELEASES t
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
i 1.4 LIQUID EFFLUENT RELEASE DATA
~6 2
GASEOUS EFFLUENTS 24 2.1 REGULATORY LIMITS 21 2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 23 2.3 i,
GASEOUS EFFLUENT RELEASE DATA 27 3
SOLID WASTE 27 3.1 REGULATORY SPECIFICATIONS 27 3.2' SOLID WASTE DATA 27 4
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PLANT E.
I. HATCH SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES 5
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 10 l-3 LIQUID RADWASTE ANALYSIS - UNIT II 11-13 4.
LIQUID RADWASTE DISCHARGE PERMIT 14 1-5a, b LIQUID RADWASTE DATA' COMPILATION 15, 16 TABLE LIST OF TABLES PAGE l-la, b EFFLUENT ' AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 17, 18 1-2a,.b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-BATCH ONLY-19, 20 2-la-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT,. GASEOUS EFFLUENT-SUMt4ATION OF ALL RELEASES 28-30 2-2a-c EFFLUENT AND WASTE DISPOSAL SEMI-a ANNUAL REPORT, GASEOUS EFFLUENTS-ELEVATED RELEASE 31-33 2-3a-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-GROUND LEVEL 1 RELEASES 34-36 3-la,b_
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT,. SOLID WASTE AND IRRADIATED; FUEL-SHIPMENTS 37 s
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' PLANT. RADIOACTIVE EFFLUENT RELEASES 1_.
LIQUID EFFLUENTS 1
1.1.
REGULATORY LIMITS 1.,
The 7 concentration of radioactive materials released in
)
liquid wastes frca all reactors at the site shall not exceed the values specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for unrestricted area.
-2.
'The cumulative release of radioactive materials in liquid wastes, excluding tritium and dissolved gases, shall not exceed 10-Ci/ reactor / calendar quarter.
- 3. -
'The cumulative release of radioactive materials in liquid wastes, excluding tritium and dissolved gases, shall not exceed 20 Ci/ reactor in any 12 consecutive months.
4.
-During release of radioactive
- wastes, the-effluent control monitor shall be set to alarm and to initiate i
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.
'O the ti uid radioactive waste 6.
The e2eigment insta11ed in 2
i system shall. be maintained and shall be operated to process radioactive liquid wastes. prior to their discharge when the projected cumulative release rate could exceed 1.25 Ci/ reactor / calendar
- quarter, 1
ex.cluding. tritium and dissolved gases.
7.
The maximum radioactivity to be. contained in any liquid radwaste tank that can be discharged directly to the environs shall not exceed 10 Ci, excluding tritium and dissolved ga~es.
s 8.
If ' the cumulative release of radioactive materials in liquid effluents,
-excluding tritium and dissolved
- gases, exceeds 2.5 Ci/ reactor / calendar. quarter, the licensee shall make an investigation to identify the
.causes. of such releases, define and initiate a program of action to reduce ~ such-releases to the design objective levels and report these actions to the 2
Commission within 30 days from the end ' of the quarter l
during whigh the release occurred.
9.
.An unplanned or uncontrolled offaite 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 O
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 before the release of the batch.
To facilitate the measurements and calculations, the nuclides of Column 2 which can be produced in a fission reactor have been grouped according to MPC value and type of radiation as shown in Figure 1-1.
The concentration of each of the 29 gamma emitting nuclides specifically noted in Figure 1-1 is measured individually because of interest in that nuclide or because of inadequate sensitivity for the nuclide from a gross activity measurement.
For any of the 29 nuclides not detected in the gamma scan, the MDA limit is computed from the measured data for that sample.
Only two pure beta emitters, Sr-89 and Sr-90, have MPC values less than 9 X 10
-6 uCi/ml.
Individual measurements are made on proportional composite liquid radwaste samples to determine the Sr-89 and Sr-90 concentration or MDA value to be applied to individual batch release calculations.
Although the MPC limit for tritium is greater than 9 X 10 -6, a
separate measurement is made for tritium since the gross beta technique does not provide an acceptable tritium measurement.
A distillation and liquid scintillation counting technique is used to measure tritium concentration.
The maximum activity of gamma and peta emitting nuclides with MPC values greater than 9
X 10 uCi/ml, except for the 29 nuclides noted above, is determined by gross gamma and gross beta measurements.
Measurement sensitivity limits of approximately 2 cpm /ml allow a
null measurement to show that the sum (Ci/MPCi),
is less than 0.1 for gamma and beta nuclides not measured directly.
The cum of the ratios, (Ci/MPCi),
for alpha emitters can be shown to be less than 0.1 by a
null with a
geasurement sensitivity limit of approximately 1 X 10 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.
1-125, 1-129 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 i
release data are stored on a computer disc file.
The disc f i'le l
data is used to assure that quarterly and annual release limi are not exceeded.
Bases used for the data of Table 1-1 ar Q
follows:
"re l
.i A.
Ficcion cnd activation producto - The total relocsa volume
>t
.(not including tritium, gases, alpha) are comprised of the
/
sum of_ the ir.dividual radionuclide activities and include
'p I
the LLD concentration of all isotopes that were not measured tV but did not meet the minimum sensitivity limit as set forth in the Environmental Tech Specs.
This sum is for each batch released to the river for the respective quarter.
Percent of applicable limit is determined from a mixed nuclide MFC calculation.
The average concentration for each nuclide summed over all batches is divided by the corresponding individual MPC value.
The sum over all nuclides of the Ci/MPCi ratios times 100 is the percent of applicable limit for effluent releases during the quarter.
The measured tritium concentration in a composite B.
Tritium sample is used to calculate the total release and average diluted concentra tion 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 ef fluents 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 no ble 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 O
form are also determined during the isotopic analysis for V
each
- batch, therefore a
separate analysis for possible gaseous forms is not performed because it would not provide additional information.
A conservative release limit, the maximum sensitivity limit of 4
X 10-5 uCi/ml of each dissolved and entrained radionuclide as specified in Regulatory Guide 1.21, has been applied in determining the percent of applicable limit.
O l
l 1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY.
Details of the analytical procedures for liquid radwaste analysis are contained in operating procedure HNP-7601.
The following
' ~J'-
measurements are performed as indicated:
4 MEASUREME'NT 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
4.
Sr-89 Quarterly Chemical separation and Composite gas flow proportional counting 4
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 1
on-line computer i
1 d
lO 0
l 4
=
If-- a liquid radw'este tank cannot be reprocosced, a sample for analysis is taken -from the tank af ter 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.
i i
i The Ge(Li) deEector consist of a 10% and two 15% ef ficiency, 2.0 FWHM resolution-detectors. in 4-inch thick lead shields.
A one-liter radwaste liquid sample is poured in to a Marinelli i
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 cata for all significant. peaks are determined, and quantitative reduction or MDA calculations are performed for the nuclides listed in Figure i
1-1.
The quantitat: Lye - calculations include corrections for counting-time,_ decay
- time, sample
- volume, sample
- geometry, 4
udetector 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
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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 (Ci/MPCi) 'and allowable release A sample printout is shown in Figures 1-2 and 1-3. parameters.
l The Liquid Radwaste Discharge Permit Printout is transferred item
{0 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 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.
i The liquid radwaste monitor setting is calculated by the computer l-based on the gamma activity as measured in the sample used for t
laboratory -analysis.
A coefficient has been determined which i
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 I
terminated if the dilution flow rate falls below the flow rate i-
'used in the computer calculation.
When the release permit is returned from Radwaste Operations following discharge,. the discharge data is: combined with the analysis results'on the computer disc file.
The disc file' may be scanned to display trends in any recorded parameter, or may be summed for reporting purposes as shown in Figure 1-5a and b.
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All 'othat radionuclido - concentration mnesurements are parformsd as indicated in the -table given 'previously in this section and as detailed in the procedure HNP-7601.
The dissolved gases O
calculation is performed in the Ge(Li) spectrometry systed with V
computer data ~ reduction _ using the _ Liquid Radwaste~ Library which includes. ga se s,.-
Several comments are_ indicative of the success of the HNP liquid radwaste' program during this reporting period:
1.
The total measured activity released in liquid effluent for both' Units was 3.11. E-1 curies for-the first quarter and 2.04 E-1 ' curies for. the second quarter.
These values were approximately ~ 1/42 for Unit 1 and 1/117 for. Unit 2 for the first' quarter and 1/55 for Unit 1 and 1/458 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.
li radwaste During this report period 41.5% of the58.5% quid reaching the sample tanks was discharged; was recycled back into both of the reactor water systems.
3.
A complete isotopic scan, gross beta, and gross gamma counts and computer analysic were performed prior to the release of each of the 999 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 datia pertinent to batch releases of radioactive effluent from both units is as follows:
Number of batch releases: 999 Total time period for releases: 130,471 minutes Maximum time period for a batch release: 460 minutes Average time period.for batch. release: 130.5 minutes Minimust time period for a batch release: 60 minutes Average-stream flow during periods of release of effluent into a flowing stream:
21,430 CFS
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A FIGURE l -
METHODS OF MEETING, TABLE II, COLUMN 2 MPC LIMITS MPC RANGE GAMMA-RAY BETA ALPHA (U Ci/ml)
' EMITTERS EMITTERS EMITTERS 1
4 1-131,I-132, I-133 Sr-89, St-90 I-135, Cs-134 (Separation &
Gas Flow 9 X 10-6 (Ge(Li) Gamma-Ray Counting)
Spectroscopy)
ALL Tc-99m', Ce-141, Zn-69m, (Gas Flow
-W-187, Zr-97,-Mn-56,
- Counting, Cs-138, Sb-125, Rb-88, Sensitivity j
Cs-136, Sb-124, Ru-103, 0.01 CPM /ml) i Nb-97, Br-82, Lu-174m, Sr-91
{
Ba-La-140, Na-24,Cu-64 Tritium CO-60, Fe-59, Zn-65 9 X 10 Aa-110m,'Mn-54, C0-58 (Distillation &
Liquid Scintil-i lation Counting)
I Zr-Nb-95, Cs-Ba-137 l
As-76, F-18, Cr-51 All Others Np-239, Ce-141 Mo-Tc-99, Ce-Pr-144 (Gas Flow Count-(Ge(Li) Gamma-Ray ing Sensitivity Spectroscopy) 2 CPM /ml i
All others (Gross Gamma-Well Counter; Sensitivity 5-CPM /ml) i I
t i
'l FIGURE 1-2
+
-s~
-HHP-7601 DATE
/
E.
I. Hatch Huclear Plant.
Liquid Raduaste Analysis l
Reactor #-1
~ Batch # 558 Tank: FDST1 Recirc time: 75 minutes
. Comment: HIGH COND.,TURB.,F.S.
Run date:
6/24/84 -0710 Count st art date:
6/24/84 0525 Sample volume: 1000.00 ml
, Clock time: 3000 secs Geometry. code: 1LHB-0 Live time: 3000 secs
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Detector # 1 MCR# 1 Library: LRWLB2.
Operat or: CJW Energy (kev)=.14 + 1.000*Ch# + 0.000E+00*Ch#^2 + 0.000E+00*Ch#^3 : 06/23/84 1457 Eff =.1/C7.186E-01
- E^(-1.7261E+00) + 642.799
- E^(9.6141E-01)3 : 06/03/84 1444 uhere E = Energy in MeV.
Ini t i al Pe ak Search Peak #
Energy Address Het Error LLD Channels Isotope Flag (Kev)
Channel-Counts Counts Counts In-Peak s am m a ssmaamma nnassmu sans mesmassansammassama n s,am usass m aamm ensmenums m uss amm en s amm e I
1 76.77 76.63 926 88 89 15 Pb X-ray Max Chan.
]
1 76.77 76.63 926 88 89:
15 Pb X-ray Mult.- ID '~
l:
2 364.75 364.65 323 24 23
~~ ' 5
'I-131' ~"~~
F 3.511.68 511.59 109 18 20 6
F-1S 3
511.68: 511.59 109 18 20 6
I-133 Mult. ID i
4 '605.85 605.76 213 24.
23 1,0 Cs-134 5
662.11 ~662.02 193
,17 15 5
Cs-137 6 795.70 795.63 113 13 11 5
Cs-134 l
6 795.70 795.63-113
.13 11.
5 Ac-228 Mult. ID i
7 1116.57 1116.53 87
,13 12 9
Zn-65 7.1116.57 1116.53 87 13 12 9
Xe-138' Mult. ID 8 1173.51 1173.48 36 8
9 4
Co-60 8 1173.51 1173.48 36 8
9 4
Kr-87 Mult. ID 9 1460.51.1460.50 147 13 6
8 K-40 to 1764.54 1764.56 15 4
3
~
4 31-214
~O-REPL ACE D---Pe ak at 76.77 kev Energy a-
.74.22 Het=
466 Error =,
51 LLD=
148 Channels =
7 ADDE D------P e ak at 1332.24 kev.
Energy a 1332.247Het=
.32 Error =
8 LLD=
19 Channels =
'6-FIGURE 1-2 (CONTINUED)
Ensegy(koV)=.. 14 + 1.000#Che + 0.000E+00eChS^2 + 0.000E+00eCh#^3 06/23/84 1457 Err =-1/[7.186E-01
- Ea(-1.7261E+00).+ 642.799
- E^(9.6141E-01>3 : 06/03/84 1444
_ here-E = Energy-in MeV.
j' w
ISOTOPE.
ENERGY.
CONCENTRATION ERROR MPC C/MPC (kev)
(uCt/ml)
(uCi/ml)
(uCi/ml)
====================================================================
- Ce-144 133.54
<3.862E-07 1E-05
<3.86E-02 Tc-99m 140.51
<4.536E-08 3E-03
<1.51E-05 Ce-141.
145.44:
<9.188E-08 9E-05
<1.02E-03
<3.20E-03
+
Hp-239 277.60
~<3.197E-07 1E-04
' <2.38E-04
. 4.752E-07 2E-03 Cr-51 320.08 I-131 364.75 8.912E-07 6.531E-08 3E-07 2.97E+00
~
438.63
<5.075E-08 6E -- <8.46E z.
2n-69m W-187 479.53
<2.067E-07 6E-05
<3.45E-03 F-18 511.68.
1.045E-07 1.685E-08 5E-04 2.09E-04 I-133
.529.87
<6.519E-08 1E-06
<6.52E-02 Ba-140 537.32
<2.141E-07.
<1.07E-02 As-76 559.10
.<1.151E-07.
<5.75E-03
'Cs-134-605.85 7.891E-07 8.845E-08 9E-06 8.77E-02 Cs-137 662.11 8.922E-07 8.016E-08 2E-05 4.46E-02 Mo-99 739.58
<3.092E-07 4E-05
<7.73E-03 Zr-97 743.36
<5.750E-08 2E-05
<2.87E-03 Zr-95 756.72
<9.708E-08 6E-05
<1.62E-03 Hb-95 765.79
<4.964E-08 1E-04
<4.96E-04 I-132 772.61
<4.731E-08' 8E <5.91E-03 Co-58 810.76
<6.303E-08'
~~
<7.00E-04 i
-834.83
<5.648E-08 1E-04
<5.65E-04 I
Ag-110m 884.67
<8.470E-08 3E-05
<2.82E-03 Zn-65 1116.57 1.106E-06 1.681E-07 1E-04 1.11E-02 I-135 1260.41
<1.'471E-07 4E-06'
<3.68E-02 6E-05
<2.23E-03 Fe 1291.56
<1.338E-07 4
Co-60 1332.24 2.463E-07 6.205E-08 3E-05 8.21E-03 Cu-64 1345.90 (5.215E-06 2E-04
<2.61E-02 Ha-24 1368.53
<2.572E-08 3E-05 (8.57E-04 La-140 1596.49
<4.191E-08 2E-05
<2.10E-03 Mn-56 1810.69
<9.178E-08' 1E-04 (9.18E-04 j
Sr -(BETR) 6.600E-08 4.990E-08 3E-08:
2.20E+00 Sr-90
. (BETA)
<2.810E-08 1E-08
<2.81E+00
+
H (BETR) 2.700E-03' 3.000E-04 3E-03 9.00E-01 Fe-55 (BETR)
(9.000E-07 8E-04
<1.13E-03 P;32,,,,_,$_[C 1,
$1 ggg[:g7' 2[;g5 15 gg[;g3 Measured totals 2.704E-03 3.000E-04 6.22E+00 LLD totals (9.419E-06
- v. "
<3.04E+00
. Totals 2.714E-03 9.26E+00 t
DISSOLVED GASES 1
j.
Xe-133 81.00
<1.522E-07 4E-05
<3.80E-03 Kr-88 196.32
<1.351E-07 4E-05
<3.30E-03 Xe-133M 233.22
<4.706E-07 4E-05
<1.18E-02
.Xe-135.
249.79
<4.599E-08 4E-05
<1.15E-03 j
Kr-85M 304.87.
<2.677E-07 4E-05
<6.69E-03 Kr-87 402.58-
<5.032E-08 4E-05
<1.26E-03 4
Xe-138 434.49
<3.883E-09 4E-05 (9.71E-05 p
Measured gas totals 0.000E+00-0.000E+00 0.00E+00 i.
LLD gas totals
<1.126E-06
<2.81E-02
_. - _..., _- 9.
FIGURE 1-2 (CONTINUED)
- (N.
(_)
~
Tot al gas
.1.126E-06 2.81E-02 GROSS ACTIVITY Counter Gross B ac k ground -Time Vol Het Error Counts Counts (Min) m1 ActivityCcpm/ml) 1 Sigma Well Cryst al 1268 891 20.0 2
9.43E+00 1.16E+00 Pronart i onal 287 220 10.0 2
3.35E+00 1.13E+00 ESTIMATED WASTE TAHK VOLUME = 11470.00 gal l ons ESTIMATED ACTIVITY THIS BATCH EXCLUDING GASES:
,1.78E-04 Curies
- ( 1.78E+02 Microcuries)-
1.17E-01 Curies EXCLUDING H-3 AND GASES:
. ( 1.17E+05 Microcuries)
Liquid Raduaste Release Summarv 0
) Meas.
1 conc., excluding H-3 and dissolved gases (uCi/ml): 4.10E-06 +- 2.31E-07 Meas. conc., including H-3, excluding gases
- 2.70E-03 +- 3.00E-04
- 2) Calculated LLD concentration, excluding dissolved gases (uCi/ml): 9.42E-06
- 3) Calculated MPC ratio (C/MPC of meas., including gases): 6.22E+00
- 4) Minimum dilution flou rate (gpm): ' '10000
~
- 5) Maximum tank discharge flou rate (gpm): 1915 i
6)Specified tank flou rat e (gpm): 75 7)Raduaste monitor trip setting: 1335 A = 4.03E-06,uC1/ml B.=
1100~, Monitor BG CPS C = 16810000.00, Monitor CPS per uCl/mi F = 2,Conserv. Factor A. includes me asured ' selected','other' nuelides and gases but excludes:
Sr-89, Se-90, H-3, Fe-55, P-32
- 8) Estimated conc. of meas. nuclides at point of release (uC1/ml): 2.013E-05 l
9)Monito'r maximum'to ensure 10CFR20 timits are not exceeded: 1462
~
t 4v
FIGURE 1-3 1
l at:).
HHP-7601 DATE
/
i E.
I.
Hat ch Nuc l ear Pl ant Liquid.Raduaste Analysis a
Reactor # 2 Batch # 409 Tank: FDST2
.Recirc time: 105 minutes Comment: HIGH COND Run date:
6/19/84 0742 Count start dat e:
6/19/84 0615 Sample volume: 1000.00 ml Clock time: 3000 secs Geometry code: 1LHB-0 Live time: 3000 secs Detector # 3 MCA# 3 Library: LR4LB2 Operator: CJW
(
. Energy (kev)=.26 + 1.000*Ch# + 0.000E+00*Ch#^2 + 0.000E+00*Cht^3 : 06/18/84 1540 E/F = 1/[5.032E-01
- Ea(-1.7287E+00) + 589.639
- E^(8.9371E-01)] : 06/04/84 1752 uhere E = Energy in MeV.
Initial Pe ak Search Peak #
Energy Address Het Error LLD Channels Isotope Flag (Kev)
Channel Counts Counts Counts In Peak 1'
365.31 365.00 76 10 8
4 I-131 2
662.70 662.35 40 8
7 5
Cs-137 3 1117.24 1116.84-39 9
7 11 Zn-65 3 1117.24 1116.84 39 9
7 11 Xe-138 Nult. ID j
4 1173.37 1172.97 23 6
5 5
Co-60 5 1332.92-1332.49 39 7
4 5
Co-60 6 1461.39f1460.95 86
-10 4
6
.K-40 i
1 v
-11
FIGURE 1-3 (CONTINUED) d ISOTOPE ENERGY.
CONCENTRATION ERROR MPC C/NPC (kev)
(uCi/ml)
(uCi/ml)
(uCi/ml)
=a...................,...........................................................
Co-144 133.54
<1.285E-07 1E-05
<1.28E-02 Tc-99m 140.51
<1.542E-08
_3E-03
<5.14E-06 Cc-141 145.44
<2.571E-08 9E-05
<2.86E-04 Hp-239 277.60
<1.317E-07 1E-04
<1.32E-03 Cr-51 320.08
<1.702E-07 2E-03
<8.51E-05
)
1-131 365.31 2.055E-07 2.783E-08 3E-07 6.85E-01 Zn-69m 438.63
<1.367E-08 6E-05
<2.28E-04 W-187 479.53 (6.552E-08 6E-05
<1.09E-03 F-18 510.99 (6.165E-09 5E-04
<1.23E-05 t -$ 9 52.3 37
.i1.2 m -no
.
- s ac. _ z t. CE-n?,
Ba-140 537.32
<4.928E-08 2E-05
<2.4et-03 As-76 559.10
<2.411E-08 2E-05
<1.21E-03 Cs-134 604.70
<3.294E-08 9E-06
<3.66E-03 Cs-137 662.70 1.754E-07 3.384E-08 2E-05 8.77E-03 Mo-99 739.58
<2.101E-07 4E-05
<5.25E-03 Zr-97 743.36
<1.901E-OS 2E-05
<9.51E-04 Zr-95 756.72
<2.138E-08 6E-05
<3.56E-04 Hb-95 765.79
<2.239E-08 1E-04
<2.24E-04 1-132 772.61
<2.001E-08 8E-06
<2.50E-03 Co-58 810.76
<2.528E-08 9E-05
<2.81E-04 Mn-54 834.83
<2.236E-08 1E-04
<2.24E-04 Ag-110m 884.67
<2.647E-08 3E-05
<8.82E-04 Zn-65 1117.24 4.561E-07 1.012E-07 1E-04 4.56E-03 1260.41 R4.133E-99 4E-06
<1.03E-02 OI-135 Fe-59 1291.56 (6.967E-08 6E-05
<1.16E-03 Co-60 1332.92 2.701E-07 4.807E-08 3E-05 9.00E-03 Cu-64 1345.90
<3.891E-06 2E-04
<1.95E-02 3E-05
<4.51E-04 Na-24 1368.53
<1.352E-08
^
La-140 1596.49
<1.674E-08 2E-05 (8.37E-04 Mn-56 1810.69
<5.061E-08 1E-04
<5.06E-04 Sr-89 (BETA) 1.770E-07 7.900E-08 3E-08 5.90E+00 Se-90 (BETA)
<3.770E-08 1E-08
<3.77E+00 H-3 (BETA) 6.570E-04 7.200E-05 3E-03 2.19E-01 Fe-55 (BETA)
(9.000E-07 8E-04
<1.13E-03 P-32
( EC )
<5.000E-07 2E-05
<2.50E-02 Measured totals 6.583E-04 7.200E-05 6.83E+00 LLD totals (6.564E-06
<3.88E+00 Tot al s 6.648E-04 1.07E+01 J's DISSOLVED GASES
. 3.780E-08 4E-05
<9.45E-04 Xe-133 81.00 Kr-88 196.32
<4.814E-08 4E-05
<1.20E-03 Xe-133M 233.22
<1.589E-07 4E-05
<3.97E-03 4E-05 (4.11E-04 Xe-135 249.79
<1.645E-08 Kr-85M 304.87
<1.102E-07 4E-05
<2.75E-03 Kr-87 402.58 *
<2.254E-08 4E-05
<5.64E-04 Xe-138 434.49
<2.342E-09 4E-05 (5.85E-05 g _ Measured gas totals 0.000E+00 0.000E+00 0.00E+00 V
<9.91E-03 LLD gas totals
<3.963E-07 Tot al gas 3.963E-07 9.91E-03 m
u FIGURE 1-3 (CONTINUED)
()
CROSS ACTIVITY Counter Gross
Background
Time vol Het Error Counts Counts (Nin) ml Activity (cpm /ml) 1 Sigma Well Crystal 1240 994 20.0 2
6.15E+00
.1.18E+00 Proportional-
.193 186 10.0 2
3.50E-01 9.73E-01 ESTINRTED WASTE TANK VOLUME = 9135.00 gal l uns ESTINATED ACTIVITY THIS BATCH EXCLUDING GASES:
2.28E-02 Curies
( 2.20E+04 Microcuries)
EXCLUDING H-3 AND GASES: 4.44E-05 Curies
( 4.44E+01 Microcuries)
LIQUID RADWASTE RELEASE SUPNARY
- 1) Meas. conc., excluding H-3 and dissolved gases (uCi/ml): 1.28E-06 +- 1.44E-07 Meas. conc., including H-3, excluding gases
- 6.58E-04 +- 7.20E-05
- 2) Calculated LLD concentration, excluding dissolved gases (uCi/ml): 6.56E-06
- 3) Calculated MPC ratio (C/NPC of meas., including gases): 6.83E+00
- 4) Minimum dilution flou rate (gpm):
10000
- 5) Maximum tank discharge flou rate (gpm): 1716 6)Specified tank flou rate (gpm): 75 7')Raduaste monitor trip setting: 2361 A = 1.11E-06,uct/ml.
B = 2000, Monitor BG CPS C = 192300000.00,Nonitor CPS per uC1/ml
- = 2,Conseru.' Factor A includes measured ' selected','other' n,uclides and gases but ' excludes:
Sr-89, Sr-90, H-3, Fe-55, P-32
- 8) Estimated conc. of meas, nuclides at point of release (uCi/ml): 4.900E-06
- 9) Monitor maximum to ensure 10CFR20 Ilmits are not exceeded: 2229 e 1
~.. _ -
)
-FIGURE 1-4 PJun _[&,sy,1q DATCH NO.
LIC'.IID_R,cIJAT[_015Cw.n[C PCRMIT '
UNIT e t
DATE
(
TArc< TO BE RELEAOCD __
...\\
-RCAcord FCG ft'CCCOI1Y OF DISCHNICE RECIRC. STA9T TI:n SerOLE TIME RECIRC. DURATION MIffJTCS t-1.
LA90'tATORY ANALYSIS 1
(1) MEAStrtED RAOICit'CLIDE CONCCNTRATICN
.E
+
.E uCi/ml J
(2) -CALCULATED LLO LIMIT.CCNCCNTRATICNS
_,uCi/ml (3) CALCULATED MFC RATIO: 2 (Ci/PPCi)-
CPM (4) MINItC1 OILUTION FLCW RATE i
(5)
MAX. CALCULATED TANL( DISCHARGE RATE: IggE SEC. F.5._*g)
CFM i
(6) SPECIFIED TA.v( DISCHARCE. RATE: 1(5)/2 CPM i
(7) RADWASTE MONITOR TRIP SETTINC:'
__,,_f CPG A = Ce(LL)(1) uCi/ml B = MONITOR BC CPG C = MONITCR CPS F = CONSERVATIVE i
PER Ce(Li) uCi/ml FACTOR
[
FONITCR ALARM SETPOINT (CPS)' = (C X A X F) tB+3@
COWLETED BY DATC I
C3.'PCSITE LITER STORED (INITIALS)
LAS FORE W4 AcFROVED
/
i (8) 'RADWASTE.IC41 TOR MAX. CPS TO BE WITHIN 10 CFR EO LIMITS:
CX/ X if > + U. )
l
!!. CPERATIC:43 (6) (3) cps INIT.
(S) LIGUID RtO'.#.STE MONITCR TRIP SET AT:
CPS (10) CCNFIRPED DILUTICN FLC'<l RATE CPM 1
(11) VALV~. LINEUP C:f.CKED AS PER HN1'-
I a
TAM (
DIS. INTEGRATCR DIS. RATE DIL. TOT /4.
RIVER EL.
MCN! TOR RONG.
C P jG,__
j-D3T,g.. I, 's N_. _EVFL.T L
e e
'I j
$ TART e.
v:0 COMPLETC BY DATE l'
MIN.
CAL.
ClJtATICN -
TOTAL RELEASE l
- 9 10 MIN AFTER. START
- AFTER FLtEHING-
)
I!!.1/JICRATCRY
}
(12) TOT /L TM4( VOLUME DISCHARCE3 (CAL. X 3.7851 al uCi (13) TOTAL ACTIVITY DISCHNtCED f (1) X (12)3 (14) RIViiA FLCW RATE (FRCM FSAR 2.4-6)
CFS CCPPL1"TED BY DATE 4
i i
........i i
FIGURE 1-Sa j
Liquid Radwnste Dat a Compiltt ion for Reg. Guide 1.21 Rop:rt E.
I. Hatch Huc lear Pl ant UNIT 1 n
~
Total Activity (Curies)
Qua'rter 1, 1934 Quarter 2, 1984 Batches 1 thru 290 Batches 291 thru 574
,Hame Measured Error High LLDs Tot al Measured Error High LLDs Total
-Ce-144' 5.66E-04 9.11E-05 0.00E+00 5.66E-04 1.17E-03 1.39E-04 0.00E+00 1.17E-03 Tc-99m 4.64E-04 5.80E-06 4.64E-04 4.13C-04 6.03E-06 4.13E-04 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00Ev00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hp-239 2.05E-05 6.35E-06 2.05E-05 0.00E+00 0.00E+00 0.00E+00 Cr-51 3.43E-03 8.05E-05 3.43E-03 3.04E-03 9.70E-05 3.04E-03 I-131' 7.03E-03 3.14E-05 0.00E+00 7.03E-03 7.86E-03 3.30E-05 0.00E+00 7.86E-03 Zn-69m 1.62E-05 2.47E-06 1.62E-05 0.00E+00 0.00E+00 0.00E+00 W-187 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F-18 1.45E-03 1.28E-05 1.45E-03 1.43E-02 2.06E-05 1.43E-02 1-133 9.10E-04 1.15E-05' 9.10E-04 1.35E-03 1.59E-05 1.35E-03 Ba-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 As-76 2.68E-04 1.05E-05 2.68E-04 2.29E-04 1.25E-05 2.29E-04 Cs-134 6.59E-02 7.72E-05 0.00E+00 6.59E-02 3.38E-02 6.47E-05 0.00E+00 3.38E-02 Cs-137 9.02E-02 9.62E-05 0.00E+00 9.02E-02 5.23E-02 8.46E-05 0.00E+00 5.23E-02 Mo-90 1.61E-04 5.02E-05 0.00E+00 1.61E-04 6.48E-04 1.09E-04 0.00E+00 6.48E-04 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 1.16E-04 6.52E-06 1.16E-04 3.28E-05 6.d7E-06 3.28E-05 Hb-96 1.81E-04 6.71E-06 1.81E-04 1.26E-04 8.23E-06 1.26E-04 I-132 6.88E-08 9.27E-08 6.88E-08 1.25E-07 2.17E-07 1.25E-07 Co-58 1.24E-03 1.68E-05 0.00E+00 1.24E-03 9.69E-04 1.75E-05 0.00E+00 9.69E-04 Mn-54 3.41E-03 2.70E-05 0.00E+00 3.41E-03 3.31E-03 3.07E-05 0.00E+00 3.31E-03 Ag-110m 0.00E+00 0.00E+00 0.00E+00 1.16E-05 2.73E-06 1.16E-05 s-2n-65 2.56E-02 9.78E-05 0.00E+00 2.56E-00 2.93E-02 1.23E-04 0.00E+00 2.93E-02 1-135 5.03E-04 1.26E-05 5.03E-04 2.96E-04 1.68E-05 2.96E-04 Fe-59 1.04E-04 8.13E-06 0.00E+00 1.04E-04 5.66E-05 5.70E-06 0.00E+00 5.66E-05 Co-60 1.06E-02 4.51E-05 0.00E+00 1.06E-02 1.50E-02 6.10E-05 0.00E+00 1.50E-02 Cu-64 6.54E-03-5.69E-04 6.54E-03 7.08E-03 8.50E-04 7.08E-03 Ha-24 5.10E-03 2.68E-05 5.10E-03 1.05E-02 4.01E-05 1.05E-02 La-140 2.16E-05 2.16E-06 2.16E-05 2.70E-05 3.25E-06 2.70E-05 Mn-56 7.14E-06 2.66E-06 7.14E-06 0.00E+00 0.00E+00 0.00E+00 Cs-138 2.68E-06 3.97E-07 2.68E-06 0.00E+00 0.00E+00 0.00E+00 Cs-136 8.72E-04 1.35E-05 8.72E-04 3.95E-04 1.09E-05 3.95E-04 Sb-125 1.47E-04 1.27E-05 1.47E-04 5.13E-05 8.39E-06 5.13E-05 Sb-124 1.85E-04 1.43E-05 1.85E-04 0.00E+00 0.00E+00 0.00E+00 Hb-97 0.00E+00 0.00E+00 0.00E+00 5.77E-06 1.12E-06 5.77E-06 Sr-89 6.46E-04 4.88E-04 0.00E+00 6.46E-04 5.00E-04 4.51E-04 0.00E+00 5.00E-04 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00Eru0 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 7.84E-04 3.14E-04 0.00E+00 7.84E-04.0.00E+00 0.00E+00 4.67E-02 4.67E-02 Tot al s 2.26E-01 8.42E-04 0.00E+00 2.26E-01 1.83E-01 1.00E-03 4.67E-02.2.29E-01 Xe-133 2.38E-02 5.63E-05 0.00E+00 2.38E-02 3.36E-03 3.24E-05 0.00E+00 3.36E-03 Kr-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133M 0.00E+0e 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 7.65E-03 2.00E-05 0.00E+00 7.65E-03 8.00E-03 2.75E-05 0.00E+00 8.00E-03 Kr-85N 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00Er00 0.00E+00 0.00E+00 s
I Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E,00 0.00E+00 0.00E+00
~
Xe-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M 3.82E-10 1.07E-10 0.00E+00 3.82E-10 1.16E-07 1.55E-08 0.00E+00 1.16E-07 Tot al s '
3.14E-02 5.97E-05 0.00E+00 3.14E-02 1.14E-02 4.25E-05 0.00E+00 1.14E-02 l
4LC%
{
-FIGURE 11-5b Liquid Reduaste Dat a Compi l at ion for Reg. Guide 1.21 Report
'l E.
I. Hat c h Nuc l ear P l ant UNIT 2
~
eq
<~[t}'
Total Activity (Curies)
Quarter 1, 1984 Quarter 2, 1984 Batches-1 thru 313' Bat c hes 314 thru 425 s
l Hame Measured Error High LLDs _To t al Measured Error High LLDs Total Ce-144-fl.83E-04 5.78E-05 0.00E+00 1.83E-04 8.18E-05 3.56E-05 0.00E+00 8.18E-05 Tc-99m-3.55E-04 6.32E-06 3.55E-04 6.25E-06 6.77E-07 6.25E-06 t
Ce-141' LO.00E+00 0.00E+00 0.00E+00 0.00E+00 0. JOE +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 Cr.1.68E-03 4.98E-05 1.68E-03 9.50E-05 1'.61E-05 9.50E-05 I-131
'1.77E-02.2.99E-05 0.00E+00 1.77E-02 2.11E-05 2.58E-06 0.00E+00 2.11E-05
~
'Zn-69m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.00E+00-0.00E+00 W-187 1.73E-06 2.09E-06 1.73E-06 0.00E+00 0.00E+00 9.00E+00
.F-18
.3.30E-04 4.18E-06 3.30E-04 9.80E-05 2.74E-06 9.80E-05 y
i 1-133 1.73E-03:9.95E-06 1.73E-03 0.00E+00 0.00E+00 8.00E+00 Ba-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00-9.00E+00 A -76 1.14E-05-1.84E-06 1.14E-05 0.00E+00 0.00E+00.
9.00E+00 l
Cs-134 1.52E-02 3.77E-05.0.00E+00.1.52E-02 4.61E-03-2.05E-05 0.00E+00 4.61E #
2.05E-02 4.65E-05 0.00E+00 2.05E-02 7.87E-03 2.88E-05 0.00E+00 7.87E-03 Mo-99 5.64E-05 2.18E-05'O.00E+00'5.64E-05.1.28E-04 3.20E-05 0.00E+00 1.28E-04 1
Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
[
Zr-95 6.23E-04 6.11E-06 6.23E-04 0.00E+00 0.00E+00 0.00E+00 Hb-95 9.51E-04 5.36E-06 9.51E-04 0.00E+00 0.00E+00 0.00E+00 l'
I-132 7.90E-06 9.30E-07 7.90E-e6 0.00E+00 0.00E+00' 9.00E+00 Co-58 0.86E-04l9.19E-06 0.00E+00 2.86E-04 3.'24E-05 3.09E-06.0.00E+00 3.24E-05 Mn-54 6.37E-04 1.17E-05 0.00E+00 6.37E-04 4.15E-04 1.01E-05 0.00E+00.4.15E-04 i=
Ag-110m 2.47E-05 3.17E-06 2.47E-05 1.19E-05 2.02E-06 1.19E-05.
Zn-65
-1.28E-02.6.51E-05 0.00E+00 1.28E-02 5.53E-03 5.04E-05 0.00E+00 5.53E-03
[
j-I-135
'2.78E-04't.08E-05 2.78E-04 5.74E-06 2.02E-06' 5.74E-06 Fe-59 7.63E-05 6.68E-06 0.00E+00 7.63E-05 2.15E-05'4.11E-06 0.00E+00 2.15E-05 Co-60 4.43E-03 2.87E-05 0.00E+00 4.43E-03,2.83E-03 2.62E-05 0.00E+00 2.83E-03 i
Cu-64 1.57E-03 2.83E-04 1.57E-03.0.00E+00 0.00E+00 9.00E+00 Ha-24 1.55E-03'1.20E-05 1.55E-03 2.12E-06 5.99E-07
~
- 2.12E-06
- =
La-140 7.07E-06 1.14E-06 7.07E-06 0.00E+00 0.00E+00' 9.00E+00 l
Mn-56 0.00E+00 0'00E+00-0.00E+00 0.00E+00 0.00E+00-9.00E+00 Cs-138 3.30E-06 5.98E-07 3.30E-06 0.00E+00 0;00E+00-0.00E+00 i-Cs-136-1.12E-03 1.11E-05 1.12E-03 0.00E+00 0.00E+00 9.00E+00 l-1132 5.24E-07 8.38E-08
-5.24E-07 0.00E+00 0.00E+00-9.00E+08
[
Ba-139 1.41E-03 1.05E
- 1.41E-03 0.00E+00 0.00E+00 9.00E+00 Ag110m 1.23E-05 2.45E-06 1.23E-05 0.00E+00:9.'00E+00 9.00E+00
[
Sn-113-2.67E-05 2.13E-06 2.67E-05 0.00E+00 0.00E+00 9.00E+00 l
Sb-125 1.59E-05 3.35E-06 1.59E-05 0.'00E+00 0.00E+00 1*
9.00E+00 F
.Sr-89 1.58E-03 7.07E-04 0.00E+00 1.58E-03 1.34E-04 1.12E-04.0.00E+00 1.34E-04
^
Sr-90:
0.00E400 0.00E+00 0.00E+00 0.00E+00.3.73E-05'O.00E+00 0.00E+00 3.73E-05
[
Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00.0.00E+00 0.00E+00 0.00E+00 0
- P-32' O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3
Tot al s 8.51E-02.7.80E-04 0.00E+00 8.51E-02 2.19E-02 1.40E-04 0.00E+00.2.19E-02 Xe-133
'1.13E-01'8.89E-05 0.00E+00 1.13E-01 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 0.00E+00 a
~
1 Xe-133M 3.01E-04 2.19E-05 0.00E+00 3.01E-04 0.00E+00;0.0CE+00 0.00E+00 0.00E+00 1 Xe-135 < 2.56E-03.1.00E-05LO.00E+00 2.56E-03 5.30E-05 2.87E-06 0.00E+00 5.30E-05 Kr-85M 0.00E+00 0.00E+00 0.00E+00-0.00E+00-0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87.
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00-2Xe-138-1.40E-10 1.55E-10 0.00E+00'1.40E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00
=Sv-131m '3.93C-03 1.41E-04 0.00E+00 3.93E v3 0.00E+00 0.00E+00 0.6?E+00.0.00E+00 i
~ 5.30E-05 2.87E-06 0.00E+00 5.30E-05 I
' Tot al s '
1.20E-01L1.69E-04 0.00E+C'O 1.20E-01 3
=-
u
. e.;
TABLE 1-la E.
I.
Hatch Huclear Plant UNIT 1 EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1984 "o,
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Tot al 1
2 Error %
A.
Fission & activation. products 1.
Total release jnot including H3,
' gases, alpha)
Ci 2.26E-01 1.83E-01 4.79E+01
- 2. Average diluted concentrat t on dut inq period uCi/mi 9.02E-08 8.06E-08 3.
Percent of app l i c ab l e Itmit 1.49E+00 1.57E+00 B.
Tritium 1.
Total release C1 2.31E+01 2.43E+01 3.73E+011 2.
Average diluted concentrat ion 9.19E-06 1.07E-05 during period uCf/ml 3.
Percent of appi t c abl e Itmit 3.06E-01 3.57E-01 C.
Dissolved and entrained gases 1.
Tot al release C1 3.14E-02 1.14E-02 1.01E+021
-Os 2.
Average diluted concentration durino period uCi/mi 1.25E-08 5.01E-09 3; Percent of applicable Itmit 3.13E-02 1.25E-02 D. Gross alpha radioactivity l
1.
Tot al release l
Ci l 1.34E-07l 3.23E-06l 1.20E+021
?
j' IE. Volume of uaste (price to dilution)l Itters l 9.79E+06l 9.79E+061 1.00E+01l lF. Volume of dilution uater used l liters l 2.50E+09l 2.26E+09l 1.60E+02l A
/
C:F 9
A e
a p
M Y
TABLE 1-lb E.
I.
Hatch Nuc l ear Pl ant UNIT 2
. -~-
EFFLUENT AND MASTE DISPOSAL SEMIAHHUAL REPORT 1984 LIQUID EFFLUEhTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Total 1
2 Error %'
A. Fission & act ivat ion product s 1.
Total release (not including H3, case s, al pha)
Ci 8.51E-02 2.19E-02 5.02E+01 2.
Average. diluted concentratton during period uCi/ml 4.35E-08 1.96E-08 3.
Percent of applicable limit 3.35E+00 1.17E-01 B.
Tettium 1.
Tot.1 release C1 1.00E+01 1.87E+00 3.78E+011 2.
Average diluted concent rat ion
-during period uCi/ml 5.12E-06 1.67E-06 3.
Percent of appitcable Itmit 1.71E-01 5.56E-02 C. Dissolved and entrained gases 1.
Tot al release Ci 1.20E-01 5.30E-05 1.00E+021 0
2.
Average dilut6d concentration durino period uCi/mi 6.12E-08 4.74E-11 3.
Percent of appitcable limit 1.53E-01 1.18E-04 D.
Gress alpha radioactivity l
1.
Tot al release l
C1 l 4.39E-09l 2.15E-06l 1.20E+02l lE. Volume of waste (prior to dilution)l Itters l 8.95E+06l 3.33E+06l 1.00E+011 lF. Volume of dilution water used l liters l 1.95E+09l 1.12E+09l 1.60E+021 O
O i
l
~
TABLE l-2a i
E. I. Hatch Nuclear Plant UNIT 1 f'
}
EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT 1984 l
i LIQUID EFFLUENTS j
CONTINUOUS MODE BRTCH MODE i
Huclides Released Unit Ouarter Quarter Quarter Quarter i
1 2
1 2
l Ce-144 Ci 5.66E-04 1.17E-03 Tc-99m C1 4.64E-04 4.13E-04 Ce-141 Ct 0.00E+00 0.00E+00
-Np-239 Ct 2.05E-05 0.00E+00 Cr C1 3.43E-03 3.04E-03 s
I-131-Ct 7.03E-03 7.86E-03 2n-69m C1 1.62E-05 0.00E+00 W-187 Ci 0.00E+00 -9.00E+00 l
1 F-18
-C1 1.45E-03 1.43E-02 _
j I-133 C1 9.10E-04 1.35E-61 j
Ba-140 Ct 0.00E+00 0.00E+00 As-76 C
2.68E-04 2.29E-04 i
Cs-134 Ci 6.59E-02 3.38E-02 l
l Cs-137 Ci 9.02E-02 5.23E-02 No-99 Ct 1.61E-04 6.48E-04 5
Zr-97 Ci 0.00E+00 0.00E+00 1.16E-04 3.28E-05 I
Zr-95 Ct Hb-95 Ct 1.81E-04 1.26E-04 6.88E-00 1.25E-07
{()
1-132 Ci Co-58 Ct 1.24E-93 9.69E-04 Mn-54 Cf 3.41E-93 3.31E-03 Aa-110m Ci 9.00E+09 1.16E-05 j
Zn-65 Ci 2.56E-02 2.93E-02 l
1-135 C1 5.03E-04 2.96E-04 Fe-59 Ci 1.04E-04 5.66E-05 1
Co-60 Ct-1.96E-02 1.50E-92 6.54E-03 7.08E-03 l
j Cu C1 5.10E-03 1.05E-02 Ha-24 Ct 2.16E-05 2.70E-05 j'
La-140 C1 7.14E-06 0.00E+00 Mn-56 Ci 2.68E-06 0.00E+00 Cs-138 C1 8.72E-04 3.95E-04 Cs-136
-Ci 1.47E-04 5.13E-05 1
Sb-125 C1 i'
Sb-124 C1 1.85E-94 0.00E+00 6.00E+00 5.77E-06 j
l Hb-97 Ci 6.46E-04 5.00E-04 j
Sr-89 Ct 0.00E+00 0.00E+00 Sr-90 Ct 0.00E+00 0.00E+00 Fe-55 Ct 7.84E-04 0.00E+00 P-32 Ct t
l l
Tot al for-period (above) l Ct l
l l 2.26E-011 1.83E-011 f.
rs,
-2.38E-02 3.36E-03 Xe-133-Ct 0.00E+08 9.00E+00
?
Kr-88 Ci 0.00E+00 0.00E+00 J
Xe-133M Ci
~
8.00E-03 7.65E-03 s
l-Xe-135 Ct 0.00E+00 0.00E+00 Kr-85M Ct 0.00E+00 0.00E+00 l
Kr-87 Ct 0.00E+00 0.00E+09 J
-Xe-130 Ct 3.82E-10 1.16E-07 Xe-135H
-Ct i-
'A'
,, _ ' j:
TABLE 1-2b E.
I. Hatch Huc lear Pl ant UNIT 2
()
EFFLUENT AND WASTE DISPOSHL SENIANNUAL REPORT 1984 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Huclides Released Unit Qu art e r Quarter Quarter Quarter 1
2 1
2 Ce-144 Ci 1.83E-04 8.18E-05 Tc-99m C1 3.55E-04 6.25E-06 Ce-141 Ci 0.00E+00 0.00E+00 Np-239 Ct 0.00E+00 0.00E+00 Cr-51 Ci 1.68E-03 9.50E-05 I-131 C1 1.77E-02 2.11E-05 2n-69m Ci 0.00E+00 0.00E+00 W-187 Ci 1.73E-06 0.00E+00 F-18 Ci 3.30E-04 9.80E-05 I-133 C1 1.73E-03 0.00E+00 Ba-140 Ci 0.00E+00 0.00E+00 As-76 Ci 1.14E-05 0.00E+00 Cs-134 C1 1.52E-02 4.61E-03 Cs-137 Ci 2.05E-02 7.87E-03 Mo-99 Ci 5.64E-05 1.28E-04 Zr-97 Ci 0.00E+00 0.00E+00 Zr-95 Ci 6.23E-04 0.00E+00 Hb-95 Ci 9.51E-04 0.00E+00 I-132 Ci 7.90E-06 0.00E+00 O
Co-58 Ct 2.86E-04 3.24E-05 Mn-54 Ci 6.37E-04 4.15E-04 Ra-110m Ci 2.47E-05 1.19E-05 2n-65 C1 1.28E-02 5.53E-03 I-135 Ci 2.78E-04 5.74E-06 Fe-59 C1 7.63E-05 2.15E-05 Co-60 Ci 4.43E-03 2.83E-03 Cu-64 Ci 1.57E-03 0.00E+00 Ha-24 Ci 1.55E-03 2.12E-06 La-140 C1 7.07E-06 0.00E+00 Mn-56 Ci 0.00E+00 0.00E+00 Cs-138 Ct 3.30E-06 0.00E+00 1.12E-03 0.00E+00 Cs-136 C1 5.24E-07 0.00E+00 1132 Ci 1.41E-03 0.00E+00 Ba-139 C1 1.23E-05 0.00E+00 Aa110m C1 Sn-113 C1 2.67E-05 0.00E+00 1.59E-05 0.00E+00 Sb-125 C1 1.58E-03 1.34E-04 Sr-89 C1 0.00E+00 3.73E-05 Sr-90 Ci 0.00E+00 0.00E+00 Fe-55 Ci 0.00E+00 0.00E+00 P-32 Ct l
l Tot al for period (above) l Ci l
l l 8.51E-02l 2.19E-02l 1.13E-01 0.00E+00 Xe-133 Cf 0.00E+00 0.00E+00 f
Kr-88 Ct 3.01E-04 0.00E+00 Xe-133M Ci l
C1 2.56E-03 5.30E-05 Xe-135 0.00E+00 0.00E+00 I
Kr-85M Ct A.00E+00 0.00E+00
[1 Kr-87 Ct-1.40E-101 0.00E+00 Xe-138 Ci 3.93E-03 0.00E+00 Xe-131m Ci L
a
~.
2 GASEOUS' EFFLUENTS' 2.1.-REGULATORY LIMITS a.
(1)
The release rate limit of noble gases from the site
.Q shall be:
g -Qis 1.9 Ef+ 1.0 EB
+ Qiv 11 E6
+ 44 EB 11 i
+n where Qs =
Total release rate from main stack for both Units in Ci/sec (elevated release)
Qy =
Total release rate from vent in Ci/sec (ground release) i=.The individual ~nuclide n = total nuclides E6
The average gamma energy per disintegration E3
The. average beta energy per disintegration (2)
The release rate limit of all radioiodines and i
radioactive materials' in particulate form with half i
lives greater than eight days, released from the site to the environs as part of the gaseous wastes, shall be.
-1.0 X 105 6
Qps + 1.5 X 10 qpy-gi
~
Where Qps =
Total release rate from the main stack for both Units in Ci/sec- (as elevated l
release)
Qpy Total release rate from vents for both Units
=
in Ci/sec- (ground releases)
.b.
(1)
The average release rate of noble - gases from the site during any calendar. quarter shall be:
1 g
Qis
- d2 E6
+ 3.0 EB
'+ Qiv 66 E6
+ 140 E
'51 B
i
+n i
(2)
The average release rate of noble gases during any 12 consecutive months shall be:
24 E6
+ 6.1--EB
' Qiv 1306 E + 270 E 51 g 'Qi,
-B i
+n-4 1
(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 dur ir.g any calendar quarter shall be:
l'.'3 X'106 qps + 1,9 X 107
~
qpy $1 (4)
The-average release rate of all radio iodines and radioactive materials in particulate form from the site.
'O.
l e
-21
~
with - hblf lives greater than eight days during any pariod of 12 consecutive months shall be:
2.6 X 106 Qps + 3.7 x 107 qpy,s,1 (5)
The amount of Iodine - 131 released during any calendar
_ quarter shall not exceed 2 Ci/ reactor.
~
131 released during any period (6)
The amount of Iodine of 12 consecutive months shall not exceed 4 Ci/ reactor.
c.
Should the conditions of 2.1. c (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 i
HNP-ETS and. report these actions to the Commission within 30 j
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 ooble gases during any calendar quarter is:
E Qis 47 E 6 + 12 EB
+ Qiv 260 EF + 540 fB
>1 i+n (2)
If the average release rate from the site of all radio iodines and radioactive materials in particulat-form with half lives greater than eight days during any 4
calendar quarter is:
5.0 X 106 Qps + 7.2 X 107 qpy > 1 (3)
If the amount of Iodine 131 relea' sed 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 th, waste gas discharge valve prior to. exceedic3 the limits specified in Section 2.1. a 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 pretrea tment 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 of the E.T.S.
g.
The reactor containment; for each Unit shall-'be. purged through the st.andby gas treatment system for that Unit.
O l _ _
b.
(1)~ Potentially
. explosivo - gno mixtures of hydrogen and oxygen contained in the of fgas system downstream of the recombiners shall be continuously monitored during reactor power operation for hydrogen concentration.
The hydrogen gas monitoring system shall provide alarms h.
locally and in the control room at a set point of 4%
hydrogen concentration by volume.
At least one contin.uous 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 i
concentration once every 4
- hours, or (b) using a
temporary hydrogen gas analyzer installed in the of fgas system line downstream of the recombiner, hydrogen i
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 concentrathion in the offgas system downstream of the recombiners shall not exceed 4%
1 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%
1 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.
O 4
(3)
The installed hydrogen monitoring systems shall have i
daily sensor
- checks, monthly functional
- checks, and quarterly calibrations.
The portable hydrogen. gas 4
analyzer shall be calibrated immediately prior to l
installation and shall _be subject to daily sensor
- checks, monthly functional
- checks, and quarterly calibrations until removed from service.
2 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 i
reported to the.NRC within 30 days-in accordance,with section 5.7.2 of the E.T.S.
2.2 MEASUREMENTS'AND APPROXIMATIONS OF TOT,AL RADI0 ACTIVITY Waste gas release ~at Hatch is confined ' to fourL paths. -
Each of these-four paths is continuously. monitored for-gaseous-
. concentration and each has an integrating type. collection device which concentrates particulates 'and lodine -for each seven day period (Procedures are such -that shorter collection times are used where applicable to Technical Specification requirements);.
i.h t
r 23-
'Each of-thoza continuous samplers has a
flow controller which
.m:intains semple flow within about a 10 parcent range over each seven day collection period.
The 'of fgas vent (elevated release) and the reactor-building vents have flow measurement devices which Sontinously. record the flow rate of the gas released (accurary of
, h hese devices are _ within 10% of the actual flows as measured during j
preoperational testing).
The recombiner building vent flow on Unit One is conservatively assumed to be constant at 500 CFM.
In addition l
to the gaseous, particulate, and iodine release measurements tritium, gross alpha and gaseous isotopic measurements of each vent stream are i
. 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 i
recorders.
Activity monitors and vent flow rate readings j
are read hourly and input into the computer.
From these readings a daily release is calculated.
The calibration i
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 i,A total curie release is calculated by the computer for each U
of the individual nuclides released.
This number is multiplied by the average energy per disintegration (Ey &
E) along with the coefficients in the release limit B
formula in our Environmental Technical Specifications.
All of the nuclides are summed and stored in their respective data files until the end of the quarter.
Then the computer divides the sum of the nuclides by the seconds in the quarter to determine the percent of the tech. spec. limit released.
2.
RADIOI0 DINE RELEASES i
Iodine releases are determined weekly for I-131, I-133, and 1-135, for each vent.
Where significant ' activity is not measured MDA releases are calculated.
Since calculated MDA's are below
-Technical Specification detectable concentrations then 0 (zero) release is used for the weeks with only ~ MDA values.
Weekly releases are summarized with the aid of the counting room calculator computer system
~
and
-a quarterlyi total is prepared from the weekly
. s ummar ies. -
The percent Technical Specification for I-131 on
- Table ~ 2-1 is based on th'e quarterly Technical Specification
)
limit.
i l
O 1
1 1
3.
PARTICULATE RELEASES n
-fQ 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 s'id 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 4
. strontium activity is not detected MDAs are calculated.
The percent of Technical Specification was calculated using quarterly average equation.
4.
~ GROSS' ALPHA RELE'ASE The-gross alpha release is computed each month by counting
~
the. particulate filters each week for gross alpha activity in a proportional counter.
The~ fo'ur or five weeks numbers then recorded on a data sheet and the activity is summed are O
"d
= "'"-
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. 3, rom the uCi/ml F
tritium concentration, the grams water /ft and the vent flow rates,- the monthly tritium release is calculated for each vent, and the quarterly summary can be generated from the monthly-calculation fo'rms.-
9 Hatch 'has attempted to maintiain all' calculated MDAs as low i
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 -
p
- release, total particulates with half-lives ' greater than 8-day'
~
y release-, and total' tritium release.
9
-25,
"Tha total or maximum error conociated 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 69.09% of. this release was from the main stack the MDA release values of the ground 7
level release points were small to the total release.
Monitor Error in Calibration 50%
i Vent Flow Rate 10%
Non-Steady Release Rate 20%
E 2.
1-131 Release was calculated from each weekly sample:
1 Statistical error 60%
Counting Equipment Calibration 10%
=
Vent - Flow Ra tes 10%
Vent Sample Flow dates 10%
Non-Steady Release Rates 10%-
Losses From Charcoal Cartridge 10%
TITTI 3.
Particulatec with half-lives greater than 8 days release was dominated by the MDA calculations for I-131 and Ba-La-140 hence the errors in the strontium determinations and gross alpha had negligible affects on the estimated error in the total particulate release:
~
~
Statistical Error at MDA concentration 60%
Countng Equipment Calibration 10%
Vent Flow Rates 10%
Vent Sample Flow Rates 10%.
Non-Steady Release Rates 10%-
TUDI Q
l l
l 26-~
~
4.
Total Tritium' Releaee was dominated by the reactor building vent. tritium release, hence, the larger statistical errors of the ' of f-gas vent and recombiner building vent tritium i h-releases do not affect the error in the total tritium release:
l Water Vapor,in Sample Stream Determination 20%
Vent Flow Rates 10%
l Counting Calibration and Statistics 10%
Non-Steady Release 50%
VDT I
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.
J b.
-Solid wastes in storage and preparatory to shipment shall be O
monitored and packaged to assure compliance with the applicable portions of 10 CFR Part 20, 10 CFR. Par t 71, and 49 CFR Parts 171-178.
t Reports of the radioactive solid waste shipments, volumes, c.
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 i
3-L OL 4.- -
F S
~
TABLE 2-la Unit I LO.
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1984 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Tot al E.
I. Hatch Nuclear-Power Plant UNIT 1 1
2 Error %
A. ' Fi ssi on & ac t ivat ion gases
-1.
Total release Ci 3.61E+03 1.60E+03 8.00E+01l 2.
Average release rate for period uCi/sec 4.59E+02 2.04E+02 3.
% of Technical spec i fi c at i on Itmit 1
1.62E-01 2.26E-01
.B.
Iodines 1.
Tot al iodine-131 Ci 8.69E-03 6.10E-03 1.10E+02l 2.
Average release rate for period uCi/sec 1.11E-03 7.76E-04 3.
% of Tec hni c al spec i fi c at i on limit 4.35E-01 3.05E-01
- C.
Part i c ul at e s 1.
Part i c ul at es ui th hal f-l i ves >8 days Ci 8.81E-04 2.93E-03 1.00E+02l 2.
Average release rate for-period uCt/sec 1.12E-04 3.73E-04 3.
% of Tec hni c al' spec i fic at ion limit 1.98E-01 6.53E-01 4.
Gross alpha radioactivity-Ci 2.17E-06 2.07E-06
~
D.
Trittum 1.
Tot al release C1 1.09E+01 1.26E+01 9.00E+01l 2.
Average release rate for period uCi/sec 1.38E+00 1.60E+00 3.
% of Technical spec i fi c at i on limit 1.22E+01 2.22E+01 l
i L
F
' O e
r m
- -m
~
- ' ^
m TABLE 2-lb Unit II EFFLUENT-AND WASTE DISPOSAL SEMIAhMURL REPORT 1984
~r i GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter.
Quarter Est Tot al E.
I.
Hatch Huc lear Pouer Pl ant UNIT 2 1
2 Error %
A. - Fi ssion & act ivat ion gases 1.
Total release Ci 1.32E+03 1.05E+02 8.00E+01l 2.
Average release rate for period uCi/sec 1.68E+02 1.33E+01 3.
% of-Technical specification limit 1.33E-01 5.62E-02 B.
- 1. - Tot al iodine-131 Ci 8.82E-03 3.17E-05 1.10E+02]
2.
Average release rate for period uCi/sec 1.12E-03 4.03E-06 3.
/. of -Tec hni c al spec i fi c at i on limit 4.41E-01 1.58E-03 C. Particulates
-- 1. Part i cul at es ui th -hal f-l i ves >8 days Ci 6.44E-05 5.03E-05 1.00E+02l 2.
Averace release rate for period uCi/sec 8.19E-06 6.40E-06 3.
% of Technicti spec i fi c at i on Itmit 1.10E-02 1.22E-02 4.
Gro.s alpha radioactivito Ci 8.16E-07 2.03E-07 D. Tritium N
1.
Total release Ci 3.71E+00 1.16E-01 9.00E+01l 2.
Average release rate for period uC1/sec 4.72E-01 1.47E-02 3.
% of Technical specification limit 4.86E+00 2.49E-01 6
t J
'U TABLE-2-Ic Site
. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1984 GASEOUS EFFL'UENTS-SUMMATION OF ALL RELEASES RUnit Quarter Quarter Est Total E.
I. ' Hat ch Nuc l ear ' Power Plant SITE 1
2 Error %
A.. Fission' & activation gases 1.
Tot al release Ci 4.93E+03 1.71E+03 8.00E+01l 2.
Averace release rate for period uCi/sec 6.27E+02 2.17E+02 l
3.
% of Technical spec i fi c at i on limit 2.95E-01 2.82E-01 B.JIodines 1.
Tot al iodine-131 Ci 1.75E-02 6.13E-03 1.10E+021
-2.
Average release rate for period uCi/sec 2.23E-03 7.80E-04 3.
% of Technical spec i fi c at i on limit 4.38E-01 1.53E-01 C. Part 'i c ul at es 1.
Part i cul at es wi th hal f-I l ves >8 days Ci 9.46E-04 2.98E-03 1.00E+02l 2.
Average release rate for period uCi/sec 1.20E-04 3.79E-04 3.1 of Technical spec i fi c at i on. limit 2.09E-01 6.65E-01 4.
Gross alpha radi oact ivity Ci l 2.98E-06 2.28E-06 D.
Tritium 1.
Total-release Ci 1.46E+01 1.27E+01 9.00E+01l 2.
Average release rate for period uCi/sec 1.85E+00 1.62E+00 3.
% of Technical specification limit 1.71E+01 2.25E+01 t
~
r em
TABLE 2-2a E.
I.
Hatch Huclear Pouer Plant UNIT 1 l
EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1984
. GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH NODE Huclides Released Unit Quart *r Quarter Quarter Quarter 1
2 1
2 1.
Fission gases Xe-133 Ci 2.58E+03 5.82E+02 0.00E+00 0.00E+00 Xe-131m Ci 8.80E+00 4.97E+00 0.00E+00 0.00E+00 Kr-88 Ci 1.45E+02 4.73E+02 0.00E+00 0.00E+00 Xe-133M C1 1.33E+02 1.06E+01 0.00E+00 0.00E+00 Xe-135 Cs 4.99E+02 9.88E+00 0.00E+00 0.00E+00 Kr-85M Ct 9.24E+01 3.39E+02 0.00E+00 0.00E+00 1-131 C1 9.45E-01 0.00E+00 0.00E+00 0.00E+00 Kr-871 -
Ci 2.48E+01 6.05E+01 0.00E+00 0.00E+00 Xs-138 Ci 3.98E+00 1.30E+01 0.00E+00 0.00E+00 Xe-137-Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N-13 Ci 1.20E+01 4.18E+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 5.62E+00 6.62E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 3.62E+00 8.21E+00 0.00E+00 0.00E+00 Tot al for period Ci 3.51E+03 1.55E+03 0.00E+00 0.00E+00 2.
Iodines I-131 Ci 6.76E-03 2.24E-03 0.00E+00 0.00E+00 I-133 C1 4.98E-04 6.75E-04 0.00E+00 0.00E+00 I-135 C1 2.07E-04 4.96E-04 0.00E+00 0.00E+00 Tot al for period Ci 7.47E-03
~3.41E-03 0.00E+00 0.00E+00 i
.3.
Par t i c u l at es i
Sr-89 Ci 0.00E+00 0.00E+00 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 0.00E+00 1.48E-06 0.00E+00 0.00E+00 I-131 C1 1.15E-05 7.06E-06 0.00E+00 0.00E+00 L
Sn-113 Ci 0.00E+00 3.63E-08 0.00E+00 0.00E+00 Ba-140 C1-2.01E-05 6.80E-05 0.00E+00 0.00E+00 Cs-134 Ci 7.15E-07 6.45E-07 0.00E+00 0.00E+00 Cs-137 Ci 2.68E-06 2.30E-06 0.00E+00 0.00E+00 Ce-144-Ci 0.00E+00 9.24E-06 0.00E+00 0.00E+00 Zr-95 C1-0.00E+00 0.00E+00 0.00E+00 0.00E+00
+
Hb-95 Ci 0.00E+00 2.04E-07 0.00E+00 0.00E+00 Cc-58 Ci 0.00E+00 4.09E-08 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 2.08E-07 0.00E+00 0.00E+00 Co-60 C1 1.62E-06
-1.63E-06 0.00E+00 0.00E+00 La-140 C1 2.89E-05 1.56E-04 0.00E+00 0.00E+00 Total'for period Ci 6.55E-05 2.47E-04 0.00E+00 0.00E+00 i-g
U l
TABLE 2-2b t
E.
I. Hatch Huclear Pouer Plant UNIT 2 EFFLUENT AH3 WASTE. DISPOSAL SEMIANHURL REPORT 1984
. GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE Huclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2 4
- 1. Fission gases Xe-133 Ci 7.94E+02 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 2.71E+00 0.005+00 0.00E+00 0.00E+00 4
Kr-88 C1 4.48E+01 0.00E+00 0.00E+00 0.00E+00 Xe-133M Ci 4.10E+01 3.0cE+00 0.00E+00 0.00E+00 Xe-135 Ci 1.54E+02 0.00E+00 0.00E+00
-0.00E+00 Kr-85M Ct 2.85E+01 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 2.91E-01 0.00E+00 0.00E+00 0.00E+00 Kr-87
'Ci 7.66E+00 0.00E+00 0.00E+00 0.00E+00 Xe-138 Ci 1.23E+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 3.70E+00 0.00E+00 0.00E+00 0.00E+00 L
Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
-Xe-135M Ci 1.73E+00 0.00E+00 0.00E+00 0.00E+00 I-133-Ci 0.00E+00 0.00E+00
-0.00E+00 0.A0E+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 1.12E+00 0.00E+00 0.00E+00 0.00E+00 i
Total for period Ci 1.08E+03
-0.00E+00 0.00E+00 0.00E+00 2.
Iodines I
l I-131 Ci 2.09E-03 0.00E+00 0.00E+00 0.00E+00 I-133 Ci 1.54E-04 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 6.38E-05 0.00E+00 0.00E+00 0.00E+00 Tot al for period-Ci 2.30E-03 0.00E+00 0.00E+00 0.00E+00 3.'Particulates I
Sr-89 Ci 0.00E+00 0.00E+00 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 4
Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 C1 3.56E-06 0.00E+00 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00
-0.00E+00 Ba-140 Ci 6.21E-06 0.00E+00
'O.00E+00 0.00E+00 Cs-134 C1 2.21E-07 0.00E+00 0.00E+00 0.00E+00 Cs-137 Ci 8.25E-07 0.00E+00 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 0.00E+00
-0.00E+00
-0.00E+00 Hb-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+90 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00
'O.00E+00 Co-60 Ci 5.00E-07 0.00E+00 0.00E+00 0.00E+00 La-140 Ci 8.90E-06 0.00E+00
-0.00E+00 0.00E+00 Total for period Ci 2.02E-05 0.00E+00 0.00E+00 0.00E+00 i
~
^
Q@
TABLE 2-2C 1
E.
I& Hat ch Huc lear Power Pl ant SITE
()
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1984
, GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH NODE Huclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2 1.
Fission gases Xe-133 Ci 3.37E+03 5.82E+02 0.00E+00 0.00E+00 Xe-131m Ci 1.15E+01 4.97E+00 0.00E+00 0.00E+00 Kr-88 Ci 1.90E+02 4.73E+02 0.00E+00 0.00E+00 Xe-133M C1 1.74E+02 1.06E+01 0.00E+00 0.00E+00 Xe-135 Ci 6.53E+02 9.88E+00 0.00E+00 0.00E+00 Kr-85M Ci 1.21E+02 3.39E+02 0.00E+00 0.00E+00 I-131 Ci 1.24E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ci 3.25E+01 6.05E+01 0.00E+00 0.00E+00 Xe-138 C1 5.21E+00 1.30E+01 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-13 Ci 1.57E+01 4.18E+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 7.36E+00 6.62E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E*00 0.00E+00 Kr-89 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 4.74E+00 8.21E+00 0.00E+00 0.00E+00 Tot al for period Ci 4.59E+03 1.55E+03 0.00E+00 0.00E+00 2.
Iodines 1-131 Ci 8.85E-03 2.24E-03 0.00E+00 0.00E+00 I-133 Ci 6.51E-04 6.75E-04 0.00E+00 0.00E+00 I-135 Ci 2.70E-04 4.96E-04 0.00E+00 0.00E+00 Tot al for period Ci 9.77E-03 3.41E-03 0.00E+00 0.00E+00
- 3. Part i c u l at e s Sr-89 Ci 0.00E+00 0.00E+00 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 0.00E+00 1.48E-06 0:00E+00 0.00E+00 I-131 Ci 1.51E-05 7.06E-06 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 3.63E-08 0.00E+00 0.00E+00 Ba-140 Ci 2.63E-05 6.80E-05 0.00E+00 0.00E+00 Cs-134 Ci 9.36E-07 6.45E-07 0.00E+00 0.00E+00 Cs-137 Ci 3.50E-06 2.30E-06 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 9.24E-06 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hb-95 Ci 0.00E+00 2.04E-07 0.00E+00 0.00E+00 Co-58 C1 0.00E+00 4.09E-08 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
fs Fe-59 Ci 0.00E+00 2.08E-07 0.00E+00 0.00E+00 I
Co-60 Ci 2.12E-06 1.63E-06 0.00E+00 0.00E+00 La-140 Ci 3.78E-05 1.56E-04 0.00E+00 0.00E+00 Total for period Ci 8.57E-05 2.47E-04 0.00E+00 0.00E+00
, )
L TABLE 2-3a E
k a
E.
I. Hatch Huclear Pouer Plant UNIT 1 3
{)
EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1984 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE v-CONTINUOUS MODE BRTCH NODE p
Huclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2 1.
Fission gases Xe-133 Ci 6.31E+01 3.75E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7
Kr-88 Ci 3.29E-02 1.74E-01 0.00E+00 0.00E+00
[
Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 Ci 2.51E+01 1.85E+01 0.00E+00 0.00E+00 Kr -85M Ci 1.08E-02 3.44E-02 0.00E+00 0.00E+00 t
I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ci 1.89E-02 1.80E-01 0.00E+00 0.00E+00 Xe-138 Ci 9.82E-02 8.86E-01 0.00E+00 0.00E+00 f
Xe-137 Ci 9.35E-02 7.37E-01 0.00E+00 0.00E+00 N-13 Ci 1.92E-01 1.84E+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 1.81E+01 2.44E+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 2.72E-02 1.37E-01 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 1.07E+02 5.07E+01 0.00E+00 0.00E+00 2.
lodines a
r I-131 Ci 1.81E-03 3.71E-03 0.00E+00 0.00E+00 L
I-133 Ci 3.98E-04 1.87E-03 0.00E+00 0.00E+00 I-135 Ci 9.05E-04 1.12E-03 0.00E+00 0.00E+00 g
h Tot al for period Ci 3.11E-03 6.70E-03 0.00E+00 0.00E+00 E
3.
Part i c u l at es r
Sr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2
Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 3.91E-07 0.00E+00 0.00E+00 Or-51 C1 1.79E-04 7.51E-04 0.00E+00 0.00E+00
.-131 Ci 1.13E-04 1.45E-04 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 5.00E-06 0.00E+00 0.00E+00 Ba-140 Ci 1.58E-05 3.46E-05 0.00E+00 0.00E+00 Cs-134 Ci 1.33E-04 4.20E-04 0.00E+00 0.00E+00 t
Cs-137 Ci 2.08E-04 6.16E-04 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 8.54E-05 0.00E+00 0.00E+00
=
Zr-95 Ci 0.00E+00 1.36E-05 0.00E+00 0.00E+00 Hb-95 Ci 0.00E+00 5.74E-06 0.00E+00 0.00E+00 Co-58 Ci 3.43E-05 1.59E-04 0.00E+00 0.00E+00 m
Mn-54 Ci 0.00E+00 2.01E-05 0.00E+E0 0.00E+00
+
Fe-59 Ci 0.00E+00 4.52E-07 0.00E+00 0.00E+00 s
Co-60 Ci 1.26E-04 3.43E-04 0.00E+00 0.00E+00 i
La-140 Ci 7.09E-06 8.67E-05 0.00E+00 0.00E+00 h
Tot al for period Ci 8.16E-04 2.69E 3
0.00E+00 0.00E+00 E.
TABLE 2-3b E.
I. Hatch Nuc lear Pouer Plant UNIT 2
)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1984
, GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTINUOUS MODE BRTCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2
- 1. Fission gases Xe-133 Ci 1.99E+02 7.16E+01 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 4.78E+00 0.0AE+00 0.00E+00 Kr-88 Ci 3.22E+00 6.88E+00 0.00E+00 0.00E+00 Xe-133M Ci 0.00E+00 6.69E-01 0.00E+00 0.00E+00 Xe-135 Ci 2.07E+01 1.64E+01 0.00E+00 0.00E+00 Kr-85M Ci 9.27E-01 2.97E+00 0.00E+00 0.00E+00 I-131 Ci 8.13E-01 8.66E-03 0.00E+00 0.00E+00 Kr-87 C1 1.62E+00 1.46E+00 0.00E+00
- 0. 0 0 E+ 0 0___
Xe-138 Ci 4.43E+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 7.18E-01 1.27E-02 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ci 5.02E+00 0.00E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 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 To t al for period Ci 2.36E+02 1.05E+02 0.00E+00 0.00E+00 2.
Iodines I-131 Ci 6.72E-03 2.83E-05 0.00E+00 0.00E+00 I-133 Ci 2.49E-04 1.98E-05 0.00E+00 0.00E+00 I-135 Ci 8.67E-05 1.30E-05 0.00E+00 0.00E+00 Total for period Ci 7.06E-03 6.11E-05 0.00E+00 0.00E+00 3.
Particulates Sr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3
Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 3.52E-08 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 6.33E-06 0.00E+00 0.00E+00 I-131 Ci 7.12E-06 3.37E-06 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 1.98E-07 0.00E+00 0.00E+00 Ba-140 C1 2.47E-06 2.18E-06 0.00E+00 0.00E+00 Cs-134 Ci 7.89E-07 3.14E-06 0.00E+00 0.00E+00 Cs-137 Ci 1.29E-05 1.10E-05 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 9.62E-06 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 1.26E-06 0.00E+00 0.00E+00 Hb-95 Ci 0.00E+00 2.00E-07 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 8.88E-08 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+09 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 s,)
Co-60 Ci 1.90E-05 9.04E-06 0.00E+00 0.00E+00[
La-140 Ci 1.95E-06 3.85E-06 0.00E+00 0.00E+01, Total for period Ci-
_4.42E-05 5.03E-05 0.00E+00 0.00E+00 u
TABLE 2-3c
.E. I& Hatch Huclear Pow:r Pl ant SITE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1984 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTINUOUS MODE BRTCH MODE Nuclides Released Unit Quarter Quarter Guarter Quarter 1
2 1
2
.1.
Fissiore gas 2s Xe-133 C1 2.62E+02 7.54E+01 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 4.78E+00 0.00E+00 0.00E+00 Kr-88 Ci 3.26E+00 7.06E+00 0.00E+00 0.00E+00 Xe-133M Ci 0.00E+00 6.69E-01 0.00E+00 0.00E+00 Xe-135 Ci 4.58E+01 3.50E+01 0.00E+00 0.00E+00 Kr-85M Ci 9.38E-01 3.00E+00 0.00E+00 0.00E+00 I-131 Ci 8.13E-01 8.66E-03 0.00E+00 0.00E+00 Kr-87 C1 1.64E+00 1.64E+00 0.00E+00 0.00E+00 Xe-138 Ci 4.53E+00 8.86E-01 0.00E+00 0.00E+00 Xe-137 Ci 9.35E-02 7.37E-01 0.00E+00 0.00E+00 H Ct 9.10E-01 1.85E+00 0.00E+00 0.00E+00 l
Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
Xe-135M C1 2.32E+01 2.44E+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 2.72E-02 1.37E-01 0.00E+00 0.00E+00 I2 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 3.43E+02 1.56E+02 0.00E+00 0.00E+00 w
2.
Iodines I-131 Ci 8.53E-03 3.73E-03 0.00E+00 0.00E+00 I-133 Ci
.6.47E-04 1.89E-03 0.00E+00
-0.00E+00 I-135 Ci 9.92E-04 1.14E-03 0.00E+00 0.00E+00 Total for period Ci-1.02E-02 6.76E-03 0.00E+00 0.00E+00
- 3. Part i c ul at es 0.00E+0h l
Sr-89 Ci 0.00E+00 0.00E+00 0.00E+00 l
Sr -90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 4.26E-07 0.00E+00 0.00E+00 Cr-51 Ci 1.79E-04 7.57E-04 0.00E+00 0.00E+00 I-131 Ci 1.20E-04 1.48E-04 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 5.20E-06 0.00E+00 0.00E+00 Ba-140 1.83E-05 3.68E-05 0.00E+00 0.00E+00 Cs-134 4.
1.33E-04 4.24E-04 0.00E+00 0.00E+00 Cs-137 Ci 2.21E-04 6.27E-04 0.00E+00 0.00E+00
- 1 Ce-144 Ci G.00E+00 9.50E-05 0.00E+00 0.00E+00 lc Zr-95 Ci 0.00E+00 1.48E-05 0.00E+00 0.00E+00 Hb-95
'Ci 0.00E+00 5.94E-06 0.00E+00 0.00E+00 Co-58 C1 3.43E-05 1.59E-04 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 2.01E-05 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 4.52E-07 0.00E+00 0.00E+00 l: O Co-60 C1 1.45E-04 3.52E-04 0.00E+00 0.00E+00 t
'La-140 Ci 9.04E-06 9.05E-05 0.00E+00 0.00E+00 l-Total' for period Ci 18.60E-04
~2.74E-03 0.00E+00
'O.00E+00 1.
L Mb.
V U
TABLE 3-1
]
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1984 l
i January 1, 1984 -. June 30, 1984 SOLID WASTE ANO IRRADIATED FUEL SHIPMENTS FOR UNIT 's I and II A. SOLID WASTE SHIPPED OFFSITE FOR BURIAt. OR DISPOSAt. (Not irradiated fuel)
- 1. Type of waste
' unas 5"ionth En. Tod Pwiod Enor. %
. spent r: sins, fdier sludges, enpora:or rd
- 2. 85 E+2 tnttor.s. ete.
Ci
- 1. 38 E+3 1.0 E +1
- b. Dry corr.;resso.e waste, contarmnsted m'
5 67 EF2 equip, etc.
Cl
- 6. g7 Een 1,0 E ti m'
- 9. 79 E+1 c.-1:rmisted components, control ro<:s. ete.-
Ci 4.81 91 1.0 E +1 m'
l.05 92
- d. Other (des:nbe)
Ci 1.56F*0 1.0 E +1 2 Estimste of maior nuclide composidon (by type of waste) i ISOTOPE PERCENT CURIES I
.All others 24.89 347.767 O
- b. Zn-65 51.63 7 R7A Co-60 27.90
.All others 11.00 5.?RA
- d. In-65 53.05 0.R7A Co-60 28.51
- 0. dad 7.45 0.116 Cs-137 All others 10.99 0.171 1
3.
. Solid Weste Disposition Numhet of Shi;:rnents Mode of Transportation D:stination 1
53 Cask Barnwell, S. C.
7 Van Barnwell, S.
C'.
& IRRADIATED UEL SHIPMCJTS (Din ag;,,3 Hanford, WA Number of Shior-ents Mode ef Tsensportation Destination
'n/a O
n/a O
v 37
_