ML20134N671
| ML20134N671 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/30/1985 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20134N657 | List: |
| References | |
| NUDOCS 8509050269 | |
| Download: ML20134N671 (45) | |
Text
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V 1
O i
GEORGIA POWER CONPANY
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4 PLANT E.-I. HATCH UNITS NO. 1 & 2 SENi-ANNUAL REPORT PLANT RADI0 ACTIVE EFFLUENT RELEASES t
i JANUARY 1,1985 - June 30,1985 4
t A
5 f
t s
1 I
i k
'5 850905 850826 PDR A
05000321 PDR ~
R i
i
l PLANT E. Is HATCH SEMIANNUAL REPORT PLANT RADI0 ACTIVE EFFLUENT RELEASES
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SECTION
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-TITLE PAGE 1.
LIOUID EFFLUENTS 1
1.1 REGULATORY LIMITS 1
1.2 MAXIMUMPERMISSIBLECONCENTRITIONS 2
1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADI0 ACTIVITY 4
1.4 LIQUID EFFLUENT RELEASE DATA 6
2 GASEOUS EFFLUENTS 24 2.1 REGULATORY LIMITS 24 2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADI0 ACTIVITY 26 2.3 GASEOUS EFFLUENT RELEASE. DATA 30 3
SOLID WASTE 30 3.1 REGULATORY SPECIFICATIONS 30 3.2 SOLID WASTE DATA 30 0
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PLANT E. I, HATCH SEMIANNUAL REPORT PLANT RADI0 ACTIVE EFFLUENT RELEASES
.m 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 8-12 1-3 LIQUID RADWASTE ANALYSIS - UNIT II 13-16 1-4 LIQUID RADWASTE DISCHARGE PERMIT 17 l-Sa, b LIQUID RADWASTE DATA COMPILATION 18-19 TABLE LIST OF TABLES PAGE l-la, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 20-21 1-2a, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL RFPORT. LIQUID EFFLUENTS-BATCH ONLY 22-23 2-la-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES 31-33 2-2a-c EFFL'UENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-ELEVATED RELEASE 34-36 2-3a-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-GROUND LEVEL RELEASES 37-39 3-la EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 40 O
l 1
.i, Ii
. PLANT RADI0 ACTIVE EFFLUENT RELEASES I!
t:
l_
-LIQUID EFFLUENTS
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1.1.
REGULATORY LIMITS 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 1
~ B Table-II, Column 2, for unrestricted area.
~2.
The cumulative release of radioactive materials in.
l-liquid wastes, excluding tritium and dissolved gases, shall not exceed 10 C1/ reactor / calendar quarter.
i'
~
i 3.-
The cumulative release of radioactive materials in liquid wastes, excluding tritium and dissolved gases,
- shall not exceed 20 C1/ 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 lutomatic closure of the waste discharge. valve.
l prior to exceeding the limits specified in 1. above.
l S.
The operability of the automatic isolation valve in the liquid radioactive waste discharge line shall be j
~ demonstrated quarterly.
i 6.
The e'quipment installed in the liquid radioactive waste system shall be maintained and shall be operated to
_ process radioactive. liquid wastes prior to their j
discharge when the projected cumulative. release rate i
could exceed 1.25 Ci/ reactor / calendar quarter,
{
excluding tritium and dissolved gases.
l.
7.
The maximum radioactivity to be contained in any liquid radwaste tank _that can be discharged directly to the environs shall not exceed 10 Ci, excluding tritium and dissolved gases.
8.
'Ifthecumulativereleaseofradioactivematerialsin liquid effluents, excluding tritium and dissolved gases, exceeds 2.5 C1/ reactor / calendar quarter, the licensee shall make an investigation to identify the causes of such releases,- define and initiate a program i
of action to reduce such releases to the design objective levels and report these actions to the p
Commission within 30 days from the end of the quarter i
during which the release occurred.
i
'9.
'An unplanned or uncontrolled offsite release of l
radioactive materials in liquid effluents in excess of l.
0.5 C1 excluding dissolved gases shall be reported.
!!O l -
= w.
...- -... -., _ - - -..-.._.-.-.. w
l.2. MAXIMUM. PERMISSIBLE CONCENTRATIONS The M'PC values used in dete pining allowable liquid radwaste release corcentrations are taken from 10 CFR Part 20, Appendix B, Table II Column 2.
Releyse rate and dilution ratio for each I
i batch are determined by'a(mixed nuclide NPC calculation performed 1
V before the release of the' batch. To facilitate the measurements and calculations.the nuc) ides of Column 2 which can be produced in a fission reactor have been. grouped according to MPC value and type of radiation as s)own in Figure 1.l.
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 gama scan, the MDA limit is computed from the measured data for that sample.
3 Only two pure beta emitters, Sr-89 and Sr-90, have MPC values less than 9 X 10 -6 uti/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 batchcrelease calculations.
Although the MPC timit for tritium is' greater than 9 X 10 -6, a
separate measurement is made for tritium since the gross beta technique does not provide an acceptable tritium measurement. A
~
distillation and liquid scintillation counting technique is used to measure tritium concentration.
The maximum activity of gamma and beta emitting nuclides with MPC values greater than 9 X lb -6 uti/ml except for the 29 nuclides noted above, is determined 6y gross gamma and gross beta measurements. Measurement sensitivity limits of approximately 2 cpm /mi allow a null measuremerit to shw that the sum (Ci/MPCi), is less than 0.1 for'gama and beta nuclides not measured directly.
The sum of the ratios, (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 quantitatiively measured or NDA 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.releasedataarestoredonacomputerdiscfile.oncentrationand Both th-c The disc file data is used to assure that quarterly-atd annuel release limits are not exceeded. Bases used for the data of Table 1-1 are as followsi
/,\\
Q t
.g
,___5_
A.
Fission and activation products - Ths total rolsaso valu3s (nst including tritium, gasas,' alpha) are comprissd of th2 sus cf the individual radicnuclido activities and include the LLO concentration of all' isotopes that were not measured but did not meet the minimum sensitivity limit as set.forth in the Environmental Tech Specs..This sum is for each batch O
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 sununed 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 i
for effluent releases during the quarter.
8.
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 uC1/ml, is converted to percent.to give the percent of applicable limit.
I C.
Dissolved and entrained gases - Concentrations of dissolved.
and entrained gases in. liquid effluents are measured on each batch byLGe(L1) spectroscopy on a one liter sample from each liquid radwaste batch. Dissolved and entrained gases for-which measured or MDA concentrations are determined include noble gases with half lives greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; Xe-135, Xe-133m,'Xe-133, and Kr-85.
Iodine radionuclides in any' form are also determined during the isotopic analysis for each batch,.therefore a separate analysis for possible gaseous forms.is not performed because it would not provide additional information.
A conservative release limit, the maximum sensitivity limit of 4 X 10-5 uCi/mi of each dissolved and entrained radionuclide as specified in Regulatory Guide 1.21, has been applied in determining the percent of applicable limit.
9 O,.
1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADI0 ACTIVITY.
D2 tails cf th2 analytical prcceduras for liquid radwaste analysis are contained in operating procedure HNP-7601. The following measurements are performed as indicated:
()
MEASUREMENT FREQUENCY METHOD 1.
Gamma Isotopic Each Batch Ge(L1) 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 I
7.
Alpha Monthly Gas flow proportional Composito counting 8.
Dissolved Gases Each Batch Ge(Li) spectrometry with
's T
on-line computer i
e-i
)
O
-4.
If a liquid radwaste tank cannot be riprecessed, a simple for analysis is takcn from the, tank af ter tha required recirculation time. Tha sample is used for gamma-ray spectresccpy. gross gama and gross beta counting, and for preparation of a composite sample.
O' The Ge(Li) detector consist of a 10% and two 15% efficiency, 2.0 O
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 I
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/MPC1) 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 O3 cannot be discharged as desired, a manual transfer of calculated results to the release permit by the technician was implemented
(
as more likely to catch abnormal conditions in the data.
The liquid radwaste monitor setting is calculated by the computer based on the gama activity as measured in the sample used for laboratory analysis. A coefficient has been determined which relates laboratory gamma counts to the monitor count rate.
If the monitor count rate exceeds the calculated setting during discharge, then the liquid passing through the monitor is not representative of the sample which was analyzed in the lab. A monitor reading in excess of the calculated setpoint therefore results in an automatic termination of the liquid effluent discharge. Liquid effluent discharge is also automatically terminated if the dilution flow rate falls below the flow rate used in the computer calculation.
When the release permit is returned from Radwaste Operations following discharge, the discharge data is combined with the analysis results on the computer disc file. The disc file may be scanned to display trends in any recorded parameter, or may be summed for reporting purposes as shown in Figure 1-Sa and b.
I 1
All:cthar.radienuclida cencentratien' measurements ~are parfcrmed cas indicated in.the table given_provicusly"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 i
~
radwaste program during'this reporting period:
^
1.
The total measured activity released in liquid effluent for both Units was 3.21 E-1 curies for the first quarter _and 1.46 E-1 curies for the second quarter.
These values were approximately 1/48 for Unit 1 and 1/86 for Unit 2 for the first quarter and 1/98 for Unit:l and 1/209 for Unit 2 for the second quarter of the allowed 10 curies per quarter per reactor.
2.
The radwaste release procedure strongly emphasized reprocessing rather than discharge of liquid radwaste.
-During this report period 32.0% of the liquid radwaste reaching the sample tanks-was discharged;.68.0% was recycled back into both of the reactor water systems.
3.
A complete isotopic' scan, gross beta, and gross gamma counts i
and computer analysis were performed prior to the release of I
each of the 1056 discharge batches for both Units.
1
-1.4 LIQUID EFFLUENT RELEASE DATA
. Regulatory Guide 1.21 Tables 2A and 28 are found in this report
! _ O as Table 1-la, b and 1-2a, b. ~ Data is presented on a quarterly basis as per Regulatory Guide 1.21.
4 Other data pertinent to batch releases of radioactive effluent from both units is as follows:
Number of batch releases: 1056 Total time period for releases: 131,769 minutes Maximum time period for a batch release: 190 minutes Average time _ period for batch release: 125 minutes 4
Minimum time period for a batch release:
2 minutes Average stream flow during periods of release of effluent into a flowing stream:
7,258 CFS O
-e-t:
FIGURE l-1
. METHODS OF MEETING. TABLE II, COLUMN 2 MPC LIMITS
/T MPC RANGE
. GAMMA-RAY BETA-ALPHA
\\m,)
(U C1/ml)
EMITTERS EMITTERS
. EMITTERS I-131.I-132. I-133 Sr-89, Sr-90 I-135. Cs-134' (Separation &
Gas Flow 9 X 10-6 (Ge(Li) Gamma-Ray Counting)
Spectroscopy)'
ALL Tc-99m. Ce-141. Zn-69m.
(Gas Flow W-187. Zr-97. Mn-56.
Counting.
Cs-138. Sb-125. Rb-88.
Sensitivity Cs-136. Sb-124. Ru-103.
0.01 CPM /ml)
Nb-97. Br-82. Lu-174m.
Sr-91 Ba-la-140. Na-24.Cu-64 Tritium CO-60. Fe-59. Zn-65 9 X 10-6 Aa-110m. Mn-54. CO-58 (Distillation &
Liquid Scintil-lation Counting)
Zr-Nb-95. Cs-Ba-137 As-76. F-18. Cr-51 All'Others No-239. Ce-141 Mo-Tc-99. Ce-Pr-144 (Gas Flow Count-(Ge(Li) Gamma-Ray ing Sensitivity Spectroscopy) 2 CPM /ml All others (Gross Gamma-Well Counter; Sensitivity 5 CPM /ml) i
?
O
~.
FIGURE 1-2 PROCEDURE: HHP-7601' DATA SHEET 8
- + m,u,e
,,,+,.uw,,u++,,+,+--+,.,,,,,,,,..,
E.
I. Hatc h Huc l e a'r Pl ant
. Liquid Raduaste Analys i s
- .,*+++,*,-++,*,4+,*,,,+++,.,,,,..,,4,,++,,
i i
I Reactor # 1 B at c h # 453 Tank: FDST1 Recirc time: 70 minutes Comment:.HIGH COND Run date:.6/01/S5 1757-Count start c at e :
6/01/85 1440
-Sample volume: 1000.00 m)
' Clock time: 2999 secs
-Geometry' code: 1LHB-0 Live t i nie : 3001 secs Detector #.3
-MCA# :
j
. Libetry: LRNLB2 Operator: JL i
Energy (lev)=.05'+ 1.000-Ch# + 0.000E+00?Ch#^2 + 0.000E+00*Ch#~3 : 06/01/85 1502
- Eff = 1/C3.173E-01
- E^(-1.6023E,003'+ 201.393 - E^i9.5702E-01)] : 05/30/85 1543 where E = Energy.in Nev.
T-4 k
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.. _,.. _... _. _. _ _......., _ _., -_.~.__.~..._.~...__._..._.!
~(CONTINUED)
ISOTOPE ENERGY CONCENTRATION ERROR MPC C/MPC
-(kev)
(uCi/ml)
(uCi/ml)
(uCi/ml) y v
Ce-144 133.54
<1.177E-07 1E-05
<1.18E-02 Tc-99m
'140.51
<1.071E-08 3E-03
<3.57E-06 Ce-141 145.44
<2.573E 9E-05
<2.86E-04 Hp-239 277.60
<1.145E-07 1E-04
<1.15E-03 Cc-51 320.08
<1.887E-07 2E-03
<9.44E-05 I-131
.364.48
<2.258E-08 3E-07
<7.53E-02 Zn-69m 438.63
<1.473E-08 6E-05
<2.45E-04 W-187 479.53
<6.589E-08 6E-05
<1.10E-03 F-18.
511.09 4.811E-07 9.854E-09 5E-04 9.62E-04 I-133 529.87
<1.867E-08 1E-06
<1.87E-02 Ba-140 537.32
<6.665E-08 2E-05
<3.33E-03 As-76 559.10
<3.158E-08 2E-05
<1.58E-03 Cs-134 604.76 6.664E-07 3.240E-08 9E-06 7.40E-02 Cs-137 661.81 1.195E-06 4.411E-08 2E-05 5.97E-02 Mo-99 739.58 (9.996E-08 4E-05
<2.50E-03 Zr 743.36
<1.184E-08 2E-05
<5.92E-04 Zr-95 756.72
<2.092E-08 6E-05
<3.49E-04 Hb-95 765.79
<1.476E-08 1E-04
<1.48E-04 I-132 772.61
<7.905E-09 8E-06
<9.88E-04 Co-58 810.76
<1.595E-03 9E-05
<1.77E-04 Mn 834.83
<1.798E-08 1E-04
<1.80E-04 Ag-110m 884.67
<2.332E-08 3E-05
<7.77E-04 2n-65 1115.70 4.801E-07' 5.277E-08 1E-04 4.80E-03 I-135 1260.41
<4.262E-08 4E-06
<1.07E-02 Fe-59 1291.56 (2.161E-08 6E-05
<3.60E-04 O
Co-60 1332.34 2.280E-07 2.581E-08 3E-05 7.60E-03 b
Cu-64 1345.90
<2.122E-06 2E-04
<1.06E-02 Ha-24 1368.31 3.245E-07 2.779E-08 3E-05 1.08E-02 La-140 15.96.49
<5.706E-09 2E-05
<2.85E-04 Mn-56 1810.69
<1.899E-08 1E-04
< 1.~ 90 E-0 4 Sr-89 (BETA) 4.970E-08 2.380E-08 3E-08 1.66E+00 Sr-90 (BETA)-
<1.020E-08 1E-08
<1.02E+00 H-3 (BETA) 1.140E-03 1.300E-04 3E-03 3.80E-01 Fe-55 (BETA)
<8.000E-07 8E-04
<1.00E-03 P-32
( EC )
<3.000E-07 2E <1.50E-02 Me asured t ot al s 1.143E-03 1.300E-04 2.19E+00 LLD totals
<4.211E-06
<1.18E+00 Totals.
1.148E-03 3.37E+00 DISSOLVED GASES Xe-133 81.00
<3.298E-08 4E-05
<8.24E-04 Kr-88 196.32
<3.057E-08
<?.64E-04 Xe-133M 233.22
<1.453E-07 4E-05
<3.63E-03 Xe-135 249.98
~1.171E-07 1.467E-08 4E-05
'2.93E-03 Kr-85M 304.87
- <8.291E-08 4E-05
<2.07E-03 Kr-87 402.58
<7.305E-09 4E-05
<1.83E-04 Xe-138 434.49
<1.498E-11 4E-05
<3.74E-07 Me asured ';1s t ot al s.
1.171E-07 1.467E-08 2.93E-03 LLD gas totals
<2.990E-07
<7.48E-03 p) i Total gaz 4.162E-07 1.04E-02
%./ -
j 4..w a. A-c (CCMTINL'ED)
GRO?? ACTIVITY Counte-Gro22 B ac k gr ound Time vol Het Error Counts Counte (Min) ml Activity (cpa/ml) 1 Sigma Wall Crystal 2028 1816 20.0 2
5.30E+00 1.55E+00 Trepor t i on al 210 190 10.0 2
1.00E+00 1.00E+00 cSTINATED WASTE TANK YOLUME= 11000.00 g al l ons ESTIMATED ACTIVITY THIS BRTCH EXCLUDING GASES:
4.76E-02 Curies
( 4.76E+04 Microcuries)
EXCLUDING H-3 AND CA3ES: 1.43E-04 Curies
( 1.43E+02 Microcuries)
Li qui d R aduast e Release Summ arv
- 1) Meas. conc., excluding H-3 and dissolved gases (uCi/ml): 3.42E-06 +- 8.88E-08 Me as. conc., including H-3, excluding gases
- 1.14E-03 +- 1.30E-04 2)Calcul at ed LLD concent rat ion, exc luding di ssol ved gases (uCi/ml): 4.21E-06
- 3) Calculated MPC rat io (C<MFC of mess., including gases): 2.20E+00
- 4) Minimum dilution flou rate (gpm):
10000
- 5) Maximum t ank d i s c h ar g e flow r at e (gpm): 8350 G) Spec i fi ed t ank flou r at e (gpm): 75
[ l)Raduaste monitor trip setting: 266
\\
/ A = 3.49E-06,uCi/ml B=
175, Monitor BG CPS C = 7337000.00, Monitor CPS per uCi/mi F=2,Conserv. Factor A includes me asured ' selected','other' nucitdes and gases but excludes:
Sr-89, Sr-90, H-3, Fe-55, P-32
- 8) Estimated conc. of meas. nuclides at point of re l e ase (uCi/ml): 8.512E-06
- 9) Monitor m ax i mum to ensure 10CFF20 limits are not exceeded: 1566 ESTIMATED DOSES THIS BATCH, MREM Isotope W. Body Bone Liver Thyroid Kidney Lung GI-LLI Xo-133 0.00E+00 0.00E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cc-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-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+0C 0.00E+00 0.00E+00 Xo-133M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xo-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9'r;-239 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
-85M 0.00E+00 'O.00Z+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ur-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xo-138 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2n-69m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 W-187 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 _
.w..v.
^^
^~
~(COMTINUED)-
LF-18~
,1.G5E-13 1.49E-12.20.00E+00 0.00E+00' O.00E+00 0.00E+00 '4.40E-14 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 'O.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 2.04E-04 1.05E-04 2.49E-04~ 0.00E+00 8.08E-05 2.68E-05 4.36E-06 O[
Cs-137 2.15E-04 2.41E 3.29E-04 0.00E+00 ;1.12E-04' 3.72E-05 6.38E-06
'Mo-99 LO.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 a
-Zr -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' O.00E+00 0.00E+00 0.00E+00 Nb-95 0.00E+00- 0.00E+00 0.00E+00 0.00E+00 0.00E+00.0.00E+00 0.00E+00 I-132-0.00E+00. 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00.0.00E+00 0.00E+00 0.00E+00 Mn-54.
0.00E+00- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 -0.00E+00 0.00E+00
- Ag-110m 10.00E+00 0.00E+00 'O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 4.21E-06 2.93E-06 9.33E-06 0.00E+00.6.24E-06 0.00E+00 5.87E-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.
-7.96E-07
'O.00E+00-3.61E-07 0.00E+00 0.00E+00 0.00E+00 6.80E-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 5.24E 5.24E-OS 5.24E-08 :5.24E-08 5.24E-08 5.24E-08 5.24E-08 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.'16E-09 2.50E-07 0.00E+00 0.00E+00 0.00E+00 -0.00E+00 4.02E-08 Sr-90 0.00E+00. 0.00E+00 0.00E+00 _0.00E+00 0.00E+00 0.00E+00 'O.00E+00 H-3 4.69E-07 0.00E+00 4.69E-07 '4.69E-07 4.69E-07 4.69E-07 '4.69E-07 Fe-55.
0.00E+00 0.00E+00' O.00E+00 0.00E+00 -0.00E+00 0.00E+00 0.00E+00
________ __'00E+00
~
P-32 0.
0.00E+00 'O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot al ~
4.24E-04 3.49E-04 5.88E-04 5.22E-07 1.99E-04 6.45E-05 2.40E-05 Cumulative dose this YEAR (includes estimate for, this batch):
s
_Whole body 6.32E-01 mrem Percent of Tech Spec Limit:
2.11E+01 Bone 5.14E-01 mrem _
Percent of-Tech Spec Limit: - 5.14E+00 Liver 8.72E-01 mrem Percent of Tech Spec Limit:
8.72E+00 Thyroid 8.22E-04 mrem Percent of Tech Spec Limit:
8.22E-03 Kidney 2.95E-01 mrem Percent of Tech Spec Limit:
2.95E+00 Lung 9.50E-02 mrem Percent of Tech Spec Limit:
9.50E-01 GI-LLI 3.93E-02 mrem Percent of Tech Spec Limit:
3.93E-01 Cumul ative dose this QUARTER (includes estimate; for this batch):
Whole body 1.61E-01 meem Percent of Tech Spec Limit:
1.07E+01
~ Bone 1.32E-01 meem-
-Percent of Tech Spec Limit: -2.63E+00 Liver 2.22E-01 mrem Percent of Tech Spec Limit:
4.44E+00 Thyroid 2.29E-04 mrem Percent of Tech Spec Limit:
4.53E-03 Kidney 7.50E-02 meem Percent of Tech Spec Limit:
1.50E+00 Lung 2.43E-02 mrem Percent of Tech Spec Limit:
4.86E-01 GI-LLI-8.62E-03 meem Percent of' Tech Spec Limit:
1.72E-01 Project ed cumulative dose this QUARTER.(includes estimat'e for this batch):
Whole body 2.40E-01 mrem Bone 1.96E-01 mrem' Liver J3.31E-01 mrem
. Thyroid
.3.42E-04 mrem Kidney 1.12E-01 mrem-Lung 3.63E-02 mrem GI-LLI 1.29E-02-mrem Cumul at ive me asured act ivi ty-this YEAP (includes estimate for this bhtch):
2.664E-01 Curies, excluding H-31snd dissolved gases
(
LEW treatment system should be.0PERAELE due to projected dose for Whole. Body _
(CO.4TI: IUD)
LRW t re at men t system has been demonstrated OPERRELE, confirmed by: WCP BATCH # 453 DATA SUCCESSFULLY STORED
]
SPECTRUM STORED AS: LRW1
+
0 4
J.,
c:
1 1
FIGURE 1 PROCEDURE 1 HHP-7C01 DATA SHEET 8
- ++**********+*******
E.-I. Hatch Nuclear Plant
('N Liquid'Raduaste Anal
.(,)-
- +,**ysis
- +,******
' Reactor # 2 Batch # 433 Tank: FDST2 Recirc time: 105' minutes Comment: HICH COND,TURB,FS Run date:
6/07/85 1929 Count start dat e :
6/07/85 1700 Sample volume: 1000.00 mi
. Clock time: 3000 secs Geometry code: 1LTB-0 Live time: '3000 secs Detector # 3 NCA# 3 Library: LRWLB2
' Oper at or: DB Energy (kev)=.07 + 1.000+Ch# + O.000E+00*Ch#^2 + 0.000E+00*Ch#^3 : 06/06/85 1457 Eff = 1/C1.028E+01 + E^(-6.3035E-01) + 830.956
- Ea(8.510?E-01>3 : 05/19/85 1535 where E = Energy in MeV.
ISOTOPE ENERGY CONCEHTPATION ERROR MPC-C/MPC (kev)
(uCi/ml)
(uCi/m (uCi/ml)
.............................................l)....................................
Ce-144 133.54
<2.603E-07 1E-05
<2.60E-02
.Tc-99m 140.51
<2.668E-08 3E-03'
<8.89E-06 Ce-141 145.44
<6.178E-08 9E-05 (6.86E-04 Np-239 277.60
<2.48?E-07 1E-04
<2.49E-03 D._
T u #....svts; Cr-51
~320'08
<3.679E-07 2E-03
<1.84E.
I-131 364.48
-<4.040E-08
_3E-07
<1.35E-01 Zn-69a 438.C3
<3.312E-08 CE-05
<5.52E-04 W-187
.479.53
.<1.429E-07 6E-05
<2.38E-03 F-18:
~ 510.99
<1.260E-08 5E-04
<2.52E-05 1-133.
529.87
<2.596E-08 1E-06
<2.60E-02 i
[~')
Ba-140, 537.32
<1.592E 2E-05
<7.96E-03 (s_/
As-76 559.10
<8.027E-08 2E-05
<4.01E-03 Cs-134
~604.80 6.826E-07 7.015E-08 9E-06 7.58E-02 Cs-137 661.91-1.305E-06 9.989E-08.
<2.407E-07.
<6.02E-03
.1.45E-03 Zr 743.36
<2.898E-08 2E-05 Zr-95 756.72
<3.795E-08 6E-05
<6.33E-04 Hb-95 765.79
<4.418E-08 1E-04 (4,42E-04 I-132 772.61
.<1.500E-08.
<1.88E-03 Co-58' 810.76
<3.413E-08 9E-05
<3.79E-04 Mn-54 834.83
<4.362E-08 1E-04
<4.36E-04 Ag-110m 884.67
<4.250E-08 3E-05
<1.42E-03 Zn-65'
-1115.40
<1.233E-07 1E-04
<1.23E-03 I-135 1260.41
<9.038E-08 4E-06
<2.26E-02 Fe-59' 1291.56
-<6.187E-08 6E-05
<1.03E-03 Co-60 1332.71 1.457E-07 5.665E-08 3E-05 4.86E-03 Cu-64 1345.90
<3.646E-06 2E-04
<1.82E-02 Ha-24 1368.53
<2.554E-08 3E-05
<8.51E-04 La-140 1596.49
<2.285E-08 2E-05
<1.14E-03 Mn-56 1810.69
<5.294E-08 1E-04
<5.29E-04 Sr-89 (BETA)'
(1.810E-08 3E-08
<6.03E-01 Sr (BETA)
<1.040E-08 1E-08
<1.04E+00 H-3 (BETA)-
6.730E-04 7.400E-05 3E-03 2.24E-01 Fe-55 (BETA)
<8.000E-07 8E-04
<1.00E-03 P-32
( EC )
<1.000E-07 2E-05
<5.00E-03 Measured totals 6.751E-04 7.400E-05 3.70E-01 LLD totals
<6.898E-06
<1.91E+00 Tot al s 6.820E-04 2.28E+00 DISSOLVED GASES Xe-133 81.00
<7.317E-08 4E-05
<1.83E-03 Kr-88 196.32
<7.845E-08 4E-05
<1.96E-03 Xe-133M 233.22
<3.422E-07 4E-05 (8.55E-03 Xe-135 249.79
<3.615E-08 4E-05 (9.04E-04 Kr-85M 304.87
<1.699E-07 4E-05
<4.25E-03 Kr-87 402.58
<2.460E-08 4E-05
<6.15E-04 Xe-138 434.49
<3.331E-10 4E-05
<8.33E-06 Measured gas tot als 0.000E+00 0.000E+00 0.00E+00 LLD gas totals
<7.248E-07
<1.81E-02 Tot al gas 7.243E-07 1.81E-02 CROSS ACTIVITY Counter.
Gross B ac k ground Time vol Het Error Counta Counts (Min) ml Activity (cpm /ml) 1 Sigma-Well Crystal 1905 1864 20.0 2
1.03E+00 1.53E+00 Proport i onal 206 204 10.0 2
1.00E-01 1.01E+00
~~
C ESTIMATED WASTE TAHK YOLUME= 9035.00 gallons ESTIMATED ACTIVITY THIS BATCH
~14-
~
r'iGUR: 1-3 (CONTINUED)
EXCLUDING GASES:
2.31E-02 Curies
( 2.31E+04 Microcuries)
EXCLUDING H-3 AND GASES: 7.29E-03 Curies
< 7.29E+01 Microcuries)
NM Licuid Radwaste Pe l e as e Summarp
- 1) Meas. conc., exc l udi ng H-3 and di s s ol ve d g as e s (uCi ml): 2.13E-06 +- 1.35E-07 Me as. conc., including H-3, exclucing gases
- 6.75E-04 +- 7.40E-05
- 2) Cal cul at ed LLD c onc entrat i on, exc ludi ng di ssolved gases (uCi/ml): 6.90E-06 3)Calcul at ed MPC rat i o (C/MPC of me ss., i nc ludi ng gases ): 3.70E-01
- 4) Minimum dilution flou rate (gpm):
10000
- 5) Maximum t ank discharge.flou rat e (gpm): 27278 6)Specified tank flou r at e (gpm): 75 7)R adwast e moni t or t ri p set t i ng: 373 A = 2.13E-06,uCi/mi B = 290, Monitor BG CPS C = 7472000.00, Monitor CPS per uCi/ml F = 2,Conserv. F ac t or A includes measured ' selected','other' nuclides and gases but excludes:
Sr-89, Sr-90, H-3, Fe-55, P-32
- 8) Estimated conc. of meas. nuclides at point of release (uCt/ml): 5.026E-06
- 9) Undiluted concentration meets 10CFR20 limits.
_)
ESTIMATED DOSES THIS BATCH, MPEM Isotope H. Body Bone Liver Thyroid Kidney Lung GI-LLI Xe-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tc-99m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 0.00E+00 0.00E+00 0.00E+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 Np-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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131
.0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-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-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 I-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 f-~s Ba-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
(
)
As-76 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
\\ '
Cs-134 1.71E-04 8.82E-05 2.09E-04 0.00E+00 6.80E-05 2.25E-05 3.67E-06
~-
Cs-137 1.93E-04 2.16E-04 2.95E-04 0.00E+00 1.00E-04 3.33E-05 5.72E-06 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 -
FIGURE 1-3 (CONTINUED)
Hb 0.00E+00 '0.00E+00 'O.00E+00. '0.00E+00- 0.00E+00 0.00E+00 0.00E+00 I-132 0.00E+00- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58
.0.00E+00. 0.00E+00,0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
'Mn-54.
'O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 y'
Ag-110m':0.00E+00 0.00E+00' O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 T
.Zn-65 0.00E+00' O.00E+00' O.00E+00
- 0. 00E+00- 0.00E+00 0.00E+00 0.00E+00 I-135 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
'Fe-59 0.00E+00 0.00E+00 0.00E+00 :0.00E+00 0.00E+00 0.00E+00 0.00E+00
-Co-60 4.18E-07 0.00E+00. 1.39E-07 'O.00E+00 0.00E+00 0.00E+00 3.57E-06 Cu 0.00E+00- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ha-24 0.00E+00 0.00E+00 '0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La-140 0.00E+00 0.00E+00. 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 Mn-56 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 0.00E+00 0.00E+00 'O.00E+00 0.00E+00- 0.00E+00 0.00E+00 0.00E+00 Sr-90
'O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 2.28E-07 0.00E+00 2.28E-07 2.28E-07 2.28E-07 2.28E-07 2.28E-07.
Fe'55 0.00E+00 0.00E+00 0.00E+00.'O.00E+00- 0.00E+00 0.00E+00 0.00E+00 P-32
-0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot al 3.65E-04 _3.05E-04.5.05E-04 2.28E-07 1.68E-04 5.61E-05 1.32E-05 Cumulative' dose this YEAR'(' includes estimate forLthis batch):
Whole body. 3.48E-01 meem Percent of Tech Spec Limit:
1.16E+01 Bone 2.86E-01 mrem Percent'of Tech Spec Limit:
2.86E+00' Liver 4.80E-01 mrem Percent of Tech Spec Limit:
4.80E+00 Thyroid 2.15E-03 mrem.
Percent of Tech Spec Limit:
Kidney 1.62E-01 mrem Percent of Tech Spec Limit:. 2.15E-02 1.62E+00 Lung 5.26E-02 arem Percent of. Tech Spec Limit:
5.26E-01 GI-LLI 1.73E-02 meem Percent of Tech Spec Limit:
1.73E-01 Cumulat ive dose - thi s QUARTER (includes estimate for this batch):
Whole body 5.93E-02 mrem Percent of Tech Spec Limit:
3.96E+00 Bone 4.82E-02 mrem' Percent of Tech Spec. Limit:
9.65E Liver 8.24E-02 mrem Percent of Tech Spec Limit 1.65E+00 Thyroid 5.22E-05 mrem Percent of Tech Spec Limit: - 1.04E-03 Kidney 2.83E-02 erem Percent'of Tech Spec Limit:
5.66E-01 Lung 8.83E-03 mrem Percent of Tech Spec Limit:
1.77E-01 GI-LLI 5.39E-03 mrem Percent of Tech Spec Limit:
1.08E-01 Projected cumulative dose this QUARTER (includes estimate for this batch):
Whole body' 6.55E-02 mrem 8.06E-02 mrem Bone Liver 1.12E-01 mrem
-Thyroid
.7.09E-05 mrem-Kidney 3.85E-02 mrem Lung 1.20E-02 meem GI-LLI 7.32E-03 mrem Cumul at ive measured act ivi ty this YEAR (includes estimate for this batch):
1.554E-01 Curles, excluding H-3 and dissolved gases BATCH # 433 DATA SUCCESSFULLY STORED-SPECTRUN STORED AS: LRW2 m
i.
. ~
...... FIGURE.1 _
CL^*.fl C 1t.l.FilQ.
DATCH NC. __,__
s MC. '.lf D _ RrowACTr.O..l.'='C_ v t.".RC C PCRM f T UNIT @
=
DATE T.W< TO CE DELEACIO --
=
- m RCACO:4 FCn FCCCC 1Y CI DISCHARCC,,,,,,
l
'T;ECIRC. STA9T TI C SN'PLE TIME RCCIRC. CURATION
_._M!ttJTCG sl
.1.
LA9CGATCRY ANV.YSIG 4
(1) MEASURED RADIC?tJCLIDE CCNCENTRATIC 4
.E
+
___. E uCi/n1 (2)- CALCULATED LLO LIMIT CCNCCNTRATIONS
_ uCi/ nil (3) CALCULATED MPC RATIO: 2 (Ci/t'PCi)
CPM (4) MINIrC1 OILUTION FLCW R6TE (5)
MAX. CALCULATED TANK DISCHARGE RATE: ig{E_SEC. F.5._})
CPM (6) SPECIFIED TAN'< DISCHARCE RATE:.i(5)/2 CPM (7) RADWASTE MONITOR TRIP SETTINC.
CPS A = Ce(Li)(1) uCL/mi B = MONITCR BC
__ CPG C = MONITCR CPS F = CONSERVATIVE PER Ce(Li) uCI/ml FACTCR tONITCR M ARM SETPOINT (CPS) = (C X A X F) tB+3h COT LETED BY LCATC l
CC.'FCSITE LITER STCRED (INITIALS)
LA3 FCRE**.Ari ACFr7CvEO (S) RA:NAST'E 1041T09 MAX. CPS TO SE WITHIN 10 C~R E3 LIM *TE:
CXAX ( 6 ) + ( t.1 1:. C:ERATIO.3 (6) (3) eps INIT.
(9) LIGL'IO Rt.".WA5'E MO*... on inIF SET AT:
CPS (10) CONFIR.".D DILL'T*04 F.O.i RATE C F."'.
(II) VA1.V~. Li!.E'..? C:".EOME3 A3 PER ENC-i "I TMK CIS. -IN EGRAirJi iO'5. RATE lO*L. TOTA. I R fcE.:. E;. Ei'f-I
. _C2 T
.dtg
- _S=. -
Pc a.
I cp-I c
I r.
.__C = ry l
gTe.-- I 4
q':S e.._
C '.t'.:LETEC G (
~., A E MIti.
C4.
_ TCTA1.
CLRATICN pr erS2
- 9 10 Mi'; AFTER ST/RT
- '* MTER FLtGHING III.L/JORATORY i
(IE) TCTA!. TN.14 VOLT?.E CISCH/RCED (CA:.. X 3,7551 m
(13) TOTAL ACTIVI~Y DISCHARCEO f (1) X (12)I tCs (14) RIVER FLCW RATE (FROM FSAR 2.4-6)
_ _ __ C F S
..................... -........a, (q _
CCMPLETED BY FATE V) i t
y.....
.......................t m
FIGURE I-5a Liquid Rcdunsto Deto'Comptintion for Reg. Guids 1.21 Report E.
I. Hat ch Nuc l ear Pl ant UNIT 1 p)
,(,-
Total Activity (Curies)
Quarter 1,
1985 Quarter 2, 1985 Batches 1 thru 286 B at c hes 287 thru 555
'Hame Measured Error High LLDs Total Measured Error High LLDs Tot al Ce-144 2.51E-04 6.51E-05 4.00E-05 2.91E-04 3.71E-05 4.24E-05 0.00E+00 3.71E-05 Tc-99m 8.92E-05 2.93E-06 8.92E-05 1.06E-04 2.70E-06 1.06E-04 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 Np-239 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 4.07E-03.6.34E-05 4.07E-03 4.84E-04 2.38E-05 4.84E-04 I-131 3.17E-05 2.93E-06 0.00E+00 3.17E-05 6.24E-05 1.19E-05 0.00E+00 6.24E-05 0.00E+00 Zn-69m 1.06E-05 1.51E-06 1.06E-05 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 5.19E-03 1.30E-05 5.19E-03 2.86E-03 9.80E-06 2.86E-03 I-133 6.19E-04 1.03E-05 6.19E-04 2.66E-04 6.83E-06 2.66E-04 Ba-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 As-76 4.29E-05 5.00E-06 4.29E-05 1.28E-04 8.82E-06 1.28E-04 Cs-134 4.36E-02 6.18E-05 0.00E+00 4.36E-02 1.85E-02 4.21E-05 0.00E+00 1.85E-02 Cs-137 7.30E-02 8.30E-05 0.00E+00 7.30E-02 3.63E-02 5.88E-05 0.00E+00 3.63E-02 Mo-99 3.16E-04 8.32E-05 0.00E+00 3.16E-04 8.65E-05 5.78E-05 0.00E+00 8.65E-05 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 9.67E-05 5.89E-06 9.67E-05 6.34E-06 1.15E-06 6.34E-06 Hb-95 2.51E-04 8.43E-06 2.51E-04 1.05E-05 9.58E-07 1.05E-05 1-132 4.67E-07 1.20E-06 4.67E-07 0.00E+00 0.00E+00 0.00E+00 Co-58 1.68E-03 1.90E-05 0.00E+00 1.69E-03 1.97E-03 1.58E-05 0.00E+00 1.97E-03 Mn-54 4.79E-03 3.08E-05 0.00E+00 4.79E-03 1.56E-03 1.72E-05 0.00E+00 1.56E-03 5.91E-05 y
Ag-110m 4.41E-05 3.18E-06 4.41E-05 5.91E-05 3.16E-06
\\
Zn-65 3.10E-02 1.03E-04 0.00E+00 3.10E-02 1.06E-02 6.75E-05 0.00E+00 1.06E-02 I-135 1.16E-04 7.65E-06 1.16E-04 0.00E+00 0.00E+00 0.00E+00 Fe-59 8.19E-05 6.96E-06 0.00E+00 8.19E-05 3.88E-04 1.13E-05 0.00E+00 3.88E-04 Co-60 2.03E-02 5.55E-05 0.00E+00 2.03E-02 6.95E-03 3.37E-05 0.00E+00 6.95E-03 Cu-64 1.19E-02 7.28E-04
+
1.19E-02 4.92E-04 5.90E-05 4.92E-04 Ha-24 7.16E-03 3.02E-05 7.16E-03 1.62E-02 4.43E-05 1.62E-02 La-140 5.51E-06 8.88E-07 5.51E-06 4.22E-04 7.01E-06 4.22E-04 Mn-56 7.12E-06 2.27E-06 7.12E-06 0.00E+00 0.00E+00 0.00E+00 Cs-138 1.98E-07 7.31E-08 1.98E-07 5.47E-06 4.39E-07 5.47E-06 Hb-97 2.72E-06 1.70E-07 2.72E-06 0.00E+00 0.00E+00 0.00E+00 Rb-88 1.68E-07 5.61E-08 1.68E-07 6.59E-06 2.34E-06 6.59E-06 Sr-89 4.58E-04 2.19E-04 0.00E+00 4.58E-04 8.46E-04 4.27E-04 0.00E+00 8.46E-04 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot al s 2.05E-01 7.87E-04 4.00E-05 2.05E-01 9.84E-02 4.53E-04 0.00E+00 9.84E-02 Xe-133 8.10E-04 1.23E-05 0.00E+00 8.10E-04 2.49E-03 2.27E-05 0.00E+00 2.49E-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+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 2.56E-03 1.49E-05 0.00E+00 2.56E-03 5.74E-03 1.74E-05 0.00E+00 5.74E-03 Kr-85M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.90E-05 2.10E-06 0.00E+00 3.90E-05 Kr-87 1.53E-07 3.18E-10 0.00E+00 1.53E-07 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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.46E-07 2.87E-08 0.00E+00 1.46E-07 g
Xe-131m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.36E-04 2.43E-05 0.00E+00 1.36E-04 s
Tot al s 3.37E-03 1.93E-05 0.00E+00 3.37E-03 8.41E-03 3.76E-05 0.00E+00 8.41E-03
- No LLD requirement in Tech Spec -
FIGURE 1-5b Liquid Redweste Dat a Compilct ion -for Reg. Guide 1.21 Report E.
- 1. Hatch Huclear Pl ant UNIT 2 s_)
Tot al Activity (Curies)
Quarter 1, 1985 Quarter 2, 1985 B at c hes 1 thru 258 Batches 259 thru 501 Hame Measured Error High LLDs Tot al Measured Error High LLDs Tot al Ce-144 1.17E-04 3.20E-05 0.00E+00 1.17E-04 1.90E-05 6.36E-06 0.00E+00 1.90E-05 Tc-99m 5.10E-04 4.58E-06 5.10E-04 5.90E-07 1.72E-07 5.90E-07 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.70E-05 4.78E-07 0.00E+00 1.70E-05
+
0.00E+00 1.09E-05 0.00E+00 0.00E+00 Np-239 1.09E-05 3.91E-06 Cr-51 2.50E-03 6.31E-05 2.50E-03 2.97E-04 1.60E-05
+
2.97E-04 1-131 1.70E-04 4.48E-06 0.00E+00 1.70E-04 7.48E-05 1.26E-05 0.00E+00 7.48E-05
+
5.07E-06 0.00E+00 5.07E-06 9.42E-07
.Zn-69m 0.00E+00 0.00E+00
+
0.00E+00 0.00E+00 0.00E+00 0.00E+00 W-187 0.00E+00 0.00E+00 1.06E-03 7.07E-03 1.06E-03 4.15E-06 F-18 7.07E-03 1.06E-05 1.57E-03 1.12E-05 9.37E-07 1.12E-05 I-133 1.57E-03 1.01E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 0.00E+00 0.00E+00 7.03E-04 5.87E-06 9.69E-07 5.87E-06 As-76 7.03E-04 1.24E-05
+
Cs-134 2.48E-02 4.19E-05 0.00E+00 2.48E-02 7.48E-03 2.34E-05 0.00E+00 7.48E-03 Cs-137 4.40E-02 5.80E-05 0.00E+00 4.40E-02 1.34E-02 3.08E-05 0.00E+00 1.34E-02 Mo-99 2.33E-05 1.53E-05 0.00E+00 2.33E-05 2.12E-05 8.64E-66 0.00E+00 2.12E-05 Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
+
0.00E+00 8.87E-06 0.00E+00 0.00E+00 0.00E+00 Zr-95 8.87E-06 1.18E-06 IHb-95 1.35E-05 1.71E-06
+
1.35E-05 1.01E-05 1.38E-06 1.01E-05 1.62E-05 0.00E+00-0.00E+00 0.00E+00 I-132 1.62E-05 1.41E-06
+
'Co-58 3.20E-04 7.56E-06 0.00E+00 3.20E-04 1.27E-03 9.74E-06 0.00E+00 1.27E-03 IMn-54 7.81E-04 1.00E-05 0.00E+00 7.81E-04 1.60E-03 1.06E-05 0.00E+00 1.60E-03
+
1.83E-04
(
IAg-110m 1.43E-05 2.36E-06 1.43E-05 1.83E-04 3.91E-06
- Zn-65 6.76E-03 4.45E-05 0.00E+00 6.76E-03 8.66E-03 3.98E-05 0.00E+00 8.66E-03 I-135 5.11E-04 1.42E-05 5.11E-04 0.00E+00 0.00E+00 0.00E+00 IFe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.21E-04 8.77E-06 0.00E+00 6.21E-04 8Co-60 4.68E-03 2.39E-05 0.00E+00 4.68E-03 4.51E-03 2.06E-05 0.00E+00 4.51E-03 ICu-64 7.96E-03 5.14E-04 7.96E-03 1.22E-03 9.69E-05 1.22E-03 6.78E-03 IHa-24 1.31E-02 3.03E-05
+
1.31E-02 6.78E-03 3.92E-04 ILa-140 0.00E+00 0.00E+00 0.00E+00 4.51E-05 1.73E-06 4.51E-05
+
0.00E+00 IMn-56 1.47E-06 1.92E-07 1.47E-06 0.00E+00 0.00E+00 3.77E-06 0.00E+00 0.00E+00 0.00E+00 lHb-97 3.77E-06 5.72E-07
~Sr-91 9.74E-06 2.65E-06 9.74E-06 0.00E+00 0.00E+00 0.00E+00 Cs-138 8.34E-06 2.06E-07 8.34E-06 0.00E+00 0.00E+00 0.00E+00
'Sr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.97E-04 3.23E-04 0.00E+00 3.97E-04 Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot al s 1.16E-01 5.28E-04 0.00E+00 1.16E-01 4.77E-02 5.21E-04 0.00E+00 4.77E-02 Xe-133 8.02E-04 1.55E-05 0.00E+00 8.02E-04 2.32E-04 6.64E-06 0.00E+00 2.32E-04 Kr-88 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 4.11E-03 1.50E-05 0.00E+00 4.11E-03 1.85E-04 2.90E-06 0.'00E+00 1.85E-04 Kr-85M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.47E-04 3.73E-06 0.00E+00 1.47E-04 Kr-87 1.64E-07 4.48E-07 0.00E+00 1.64E-07 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 9.87E-04 4.97E-05 0.00E+00 9.87E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00
_s Tot al s 5.90E-03 5.42E-05 0.00E+00 5.90E-03 5.65E-04 8.15E-06 0.00E+00 5.65E-04
+ Ho LLD requirement in Tech Spec..
TAELE 1-la E.
I.
Hatch Nuc lear Plant UNIT 1
.f"%
i
)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1985 LIQUID EFFLUENTS-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, cases, alpha)
Ci 2.05E-01 9.84E-02 4.63E+01 2.
Average diluted concentratton durino period uCi/mi 1.01E-07 5.18E-08 3.
P e r c e r. t of appi t c abl e limit 5.31E-01 2.95E-01 B.
Tritium 1.
Total re l e ase C1 1.19E+01 1.24E+01 3.70E+01l 2.
Average diluted concentratton during period uCi/ml 5.83E-06 6.51E-06 3.
Percent of appi t c ab l e Itmit 1.94E-01 2.17E-01 C.
Dissolved and entrained gases 1.
Tot al rel e ase C1 3.37E-03 8.41E-03 1.00E+02l 2.
Average diluted concentration
[\\d')
during period uCi/mi 1.65E-09 4.43E-09 3.
Percent of appi t c abl e Itmit 4.14E-03 1.11E-02 D.
Gross alpha radioactivity l
1.
Total release l
Ct i 3.43E-04l 7.02E-06l 1.20E+02l lE. Volume of waste (prior to dilution)l Itters l 9.21E+06] 8.89E+06! 1.00E+011 lF. Volume of dilutton water used i liters l 2.03E+091 1.89E+09] 1.60E+021 O
m 6
i 1
TABLE 1-lb E.
I.
Hatch Nuclear Plant UNIT 2 I
i
(,j EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1985 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Tot al 1
2 Error /.
A.
Fission & activation products 1.
Tot al release (not including H3, cases. alpha)
C1 1.16E-01 4.77E-02 4.65E+01 2.
Average di luted concentrat i on durina period uCi/ml 7.49E-08 2.78E-08 3.
Percent of app i t c abl e Itmit 5.20E-01 1.41E-01 B.
Tritium 1.
Tot al release Ci 4.41E+00 4.60E+00 3.68E+011 2.
Average diluted concentration during period uCi/mi 2.85E-06 2.68E-06 3.
Percent of appitcable limit 9.51E-02 8.93E-02 0.
Dissolved and entrained gases 1.
Tot al release C1 5.90E-03 5.65E-04 1.01E+021 2.
Average Ut luted concentrat t on (h
during period uCi/ml 3.82E-09 3.29E-10 I
ss 3.
Percent of appi t c ab l e limit 9.55E-03 8.22E-04 D.
Gross alpha radioactivity l
1.
Tot al release l
C1 l 1.75E-04) 4.45E-06l 1.20E+02l lE. Volume of uaste (prior to dtiutton)l liters l 6.29E+06l 7.09E+06l 1.00E+01l lF. Volume of dilution uater used l liters l 1.54E+09l 1.71E+09) 1.60E+021
()
1
TABLE 1-2a E.
I. Hat ch Nuc l ear Pl ant UNIT 1
\\
f EFFLUENT AND W6STE DISPOSAL SEMIAHHUAL REPORT 1985 j
LIQUID EFFLUENTS CONTINUOUS MODE BATCH NODE Huclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2 Ce-144 C1 2.51E-04 3.71E-05 Tc-99m Ct 8.92E-05 1.06E-04 Ce-141 Ci 0.0bE+00 0.00E+00 Np-239 Ci 0.00E+00 0.00E+00 Cr-51 C1 4.07E-03 4.84E-04 I-131 C1 3.17E-05 6.24E-05 Zn-69m C1 1.06E-05 0.00E+00 W-187 Ci 0.00E+00 0.00E+00 F-18 C1 5.19E-03 2.86E-03 I-133 Ci 6.19E-04 2.66E-04 Ba-140 Ci 0.00E+00 0.00E+00 As-76 C1 4.29E-05 1.28E-04 Cs-134 C1 4.36E-02 1.85E-02 Cs-137 Ci 7.30E-02 3.63E-02 Mo-99 Ci 3.16E-04 8.65E-05 Zr-97 Ct 0.00E+00 0.00E+00 Zr-95 Ct 9.67E-05 6.34E-06 Hb-95 C1 2.51E-04 1.05E-05 I-132 C1 4.67E-07 0.00E+00
[ \\
Co-58 C1 1.68E-03 1.97E-03
\\~ l Mn-54 C1 4.79E-03 1.56E-03 Ac-110m C1 4.41E-05 5.91E-05 Zn-65 C1 3.10E-02 1.06E-02 1-135 C1 1.16E-04 0.00E+00 Fe-59 C1 8.19E-05 3.88E-04 Co-60 C1 2.03E-02 6.95E-03 Cu-64 C1 1.19E-02 4.92E-04 Na-24 Ci 7.16E-03 1.62E-02 La-140 Ci 5.51E-06 4.22E-04 Mn-56 Ct 7.12E-06 0.00E+00 Cs-138 C1 1.98E-07 5.47E-06 Hb-97 C1 2.72E-06 0.00E+00 Rb-88 C1 1.68E-07 6.59E-06 Sr-89 Ct 4.58E-04 8.46E-04 Sr-90 C1 0.00E+00 0.00E+00 Fe-55 Ct 0.00E+00 0.00E+00 P-32 Ct 0.00E+00 0.00E+00 l
Tot al for period (above) l C1 l
l l 2.05E-01l 9.84E-021 Xe-133 C1 8.10E-04 2.49E-03 Kr-88 Cl 0.00E+00 0.00E+00 Xe-133M C1 0.00E+00 0.00E+00 Xe-135 C1 2.56E-03 5.74E-03
[~}
Kr-85M Ci 0.00E+00 3.90E-05
(,)
Kr-87 C1 1.53E-07 0.00E+00 Xe-138 C1 0.00E+00 0.00E+00 Xe-135M C1 0.00E+00 1.46E-07 Xe-131m C1 0.00E+00 1.36E-04 _
TABLE 1-2b E.
I.
Hatch Nuc l ear Plant UNIT 2
(~)
\\ j EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1985 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2 Ce-144 Ct 1.17E-04 1.90E-05 Tc-99m C1 5.10E-04 5.90E-07 Ce-141 Ci 0.00E+00 1.70E-05 Hp-239 C1 1.09E-05 0.00E+00 Cr-51 Ct 2.50E-03 2.97E-04 I-131 C1 1.70E-04 7.48E-05 Zn-69m Ci 0.00E+00 5.07E-06 W-187 C1 0.00E+00 0.00E+00 F-18 C1 7.07E-03 1.06E-03 I-133 C1 1.57E-03 1.12E-05 Ba-140 Ci 0.00E+00 0.00E+00 As-76 Ci 7.03E-04 5.87E-06 Cs-134 Ci 2.48E-02 7.48E-03
~Cs-137 C1 4.40E-02 1.34E-02 Mo-99 Ci 2.33E-05 2.12E-05 Zr-97 C1 0.00E+00 0.00E+00 Zr-95 Ci 8.87E-06 0.00E+00 Hb-95 C1 1.35E-05 1.01E-05 1-132 C1 1.62E-05 0.00E+00 f s\\
Co-58 Ci 3.20E-04 1.27E-03 1\\~-
Mn-54 Ct 7.81E-04 1.60E-03 Ac-110m C1 1.43E-05 1.83E-04 Zn-65 Ci 6.76E-03 8.66E-03 1-135 Ci 5.11E-04 0.00E+00 Fe-59 Ct 0.00E+00 6.21E-04 Co-60 Ci 4.68E-03 4.51E-03 Cu-64 Ci 7.96E-03 1.22E-03 Na-24 C1 1.31E-02 6.78E-03 La-140 Ci 0.00E+00 4.51E-05 Mn-56 C1 1.47E-06 0.00E+00 Nb-97 C1 3.77E-06 0.00E+00 Sr-91 Ci 9.74E-06 0.00E+00 Cs-138 Ci 8.34E-06 0.00E+00 Sr-89 Ct 0.00E+00 3.97E-04 Sr-90 Ci 0.00E+00 0.00E+00 Fe-55 Ct 0.00E+00 0.00E+00 P-32 Ct 0.00E+00 0.00E+00 l
Total for period (aboue) l Ci l
l l 1.16E-011 4.77E-02l Xe-133 C1 8.02E-04 2.32E-04 Kr-88 Ci 0.00E+00 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 Xe-135 C1 4.11E-03 1.85E-04 n-Kr-85M Ci 0.00E+00 1.47E-04 Kr-87 C1 1.64E-07 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 Xe-131m Ct i 9.87E-04 0.00E+00
2 GASEOUS EFFLUENTS
- 2.l. REGULATORY LIMITS D
a.
(1)
The ' release rate. limit of noble gases from the site
.(j shall-be:
t Qis 1.956&l.05B
+ Qiv 11 56
+ 44 EB-il i -. n j
where Qs.=
Total release rate from main stack for both Units in Ci/sec (elevated release)
Total release rate from vent'in Ci/sec (ground. release)
Qy
=-
i=
The individual nuclide n = total nuclides E6 = The average gamma energy per disintegration EB=
The average beta energy per disintegration 4
(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 Qps + 1.5 X 106 qpy gi i
Where Qps =
Total release rate from the main stack for both Units in Ci/sec (as elevated I-D release)
V 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 curing any calendar quarter shall be:
f 1
I I Qi3 12 E 6 + 3.0 Eg
+ Qiy I66 E6 + 140 EB-1l i --n-1
+
(2)
The average release rate of noble gases during any 12 consecutive months shall be:
r f
I Qis
- 24 5 6. + 6.1 E'B Qiv
{130 ES+ 270 Eg-
- 1
+
1-n I
J (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 7
Qps + 1.9.X 10 Qpv i 1 (4)
The average release rate of all radio iodines and
/]
radioactive materials in particulate form from the site
, Q 4.
with half livas greator then eight days during any p'eriod of 12 consecutiva months shall be:
2.6 X-106~Qps +~3.7 x 107 Qpv
<1
(_8
-s.)
(5)
The amount of Iodine - 131~ released during any calendar quarter shall not= exceed 2 Ci/ reactor.
-(6)- The amount of Iodine 131 released during any period of 12. consecutive months shall not exceed 4 Ci/ reactor.
c.
"Should the conditions of 2.1.3c (1),
(2),
or (3) listed below occur, the licensee shall make an investigation to identify the causes of the release
- rates, define and initiate a program of action to reduce the release rates to design objective _ levels listed in subsection 2.1 of the HNP-ETS and repor t 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 9
calendar quarter is:
l I Qis 47 E 6 + 12 EB
+ Qiv 260 E6 + 540 E '
>l B
1 J
i en (2)
If the average release rate from the site of all radio iodines and radioactive materials in particulate form with half lives greater than eight days during any calendar quarter is:
5.0 X 106 Qps + 7.2 X 107 Qpv
>1 (3)
If the amount of Iodine 131 released during any calendar quartet is greater than 0.5 Ci/ reactor.
I 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
shutcown 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 uct/sec for a period greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, notify the Commission' in writing
-within 10 days,
identifying the causes of activity and in accordance with'section 5.7.2.
g.
The reactor containment for-each Unit shall be purged through the standby gas treatment system for that Unit.
O v
d..
h.
(1)- Potentially - explosive gas mixtures of hydrogen and e
oxygen contained in the offgas system downstream of the
(
recombiners shall be.intinuously monitored during reactor power operation for hydrogen concentration.
The hydrogen gas monitoring system shall provide alarms locally and in the control room at a set point of 4%
hydrogen concentration by volume. At least one continuous gas monitoring system and its associated alarm system shall be operable during reactor power 4
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 of fgas system downstream of the recombiners shall not exceed 4%
concentration by volume.
If at any t-ime during reactor power operation, it is determined that the hydrogen concentration limit is being exceeded, action shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to return the hydrogen concentration to within the prescribed limit.
If the j
hydrogen concentration is not reduced to less than 4%
v by volume within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the offgas system flow shall be stopped.
(3) The installed hydrogen monitoring systems shall have daily sensor checks, monthly functional checks, and quarterly calibrations. The portable hydrogen gas analyzer shall be calibrated immediately prior to installation and shall be subject to daily sensor checks, monthly functional checks, and quarterly calibrations until removed from service.
1.
An unplanned or uncontrolled offsite release of radioactive materials in gaseous effluents in excess of 150 C1. of noble gas or 0.02 C1. 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 RADI0 ACTIVITY Waste gas release at Hatch is confined to four paths. Each of these four paths is continuously monitored for gaseous concentration and each has an integrating type collection device which concentrates particulates and iodine for each seven day period (Procedures are such that shorter collection times are p
used where applicable to Technical Specification requirements).
l
}
U -
Each of these continuous samplers has a flow controller which l
- maintains. sample flow within about a=10 percent range over each seven i (
day collection period. The offgas vent (elevated release) and the 7
5 reactor building. vents.have flow measurement devices which j'
continously record the flow rate of the gas released (accurary of i
these devices are within 105 of the actual flows as measured during
+
i preoperational testing).
The recombiner building vent flow on Unit 0ne.is conservatively. assumed to be constant at.500 CFM.
In addition r
Lto the gaseous, particulate, and iodine release measurements tritium, i
gross alpha and gaseous isotopic measurements of each vent stream are l
conducted on a monthly schedule.
l l
.i After each calendar quarter;(13 weeks) a summary of waste gas i
3 release from the four vents is compiled and as such is designed i-
'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-i two reactors are identical in this respect.
The methods for l
compilation of the quarterly releases are as follows:
~
1.
' FISSION AND ACTIVATION GAS
'i j
The total curie release is determined from the continuously reading gaseous monitors in addition to the vent flow j
recorders. Activity monitors and vent flow rate readings 1-are read hourly and input into the. computer.
From these j
readings a daily release is calculated. The calibration factors for the monitors are determined from the monthly i
l 1sotopics when sufficient activity allows or by injection of j
a known amount.of off-gas into the sample chambers. The j
{
total curie release is calculated by the computer for each l
4 of-the individual nuclides released.. This number is j
multiplied by the average energy per disintegration (E &
j Eg) 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.
l 2.
RAOIDIODINE RELEASES
?
j Iodine releases are determined weekly for I-131, I-133, and I-135, for each vent. Where significant activity is not l
measured MOA releases are calculated. Since calculated j
MOA's are below Technical Specification detectable l
concentrations then 0 (zero) release is used for the weeks t
with only MDA values. Weekly releases are summarized with j
.the aid of'the counting room calculator - computer system j
and 'a quarterly total,is prepared from the weekly sunnaries. The percent Technical Specification for I-131 on O
Table 2-1 is based on the quarterly Technical Specification limit.
4 i
t k
b'
'3.
PARTICULATE RELEASES Particulate releases are determined n ekly for each vent.
!Where significant activity is-not measured MOA release is
/%'
calculated. Since calculated ~MOA's are below Technical V
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,
~
Af ter each calendar month the particulate filters from each a
{
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 i
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 i
strontium activity is not detected MOAS are calculated.
The i
percent of Technical Specification was calculated using j-quarterly average equation.
t 1
i 4.
GROSS ALPHA RELEASE
)
The gross alpha release is computed each month by counting l
l 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 i
j at the end of the month.
5.
TRITIUM RELEASE i
l Tritium samples are obtained monthly from each vent by passing the sample stream from a cold trap immersed in a 1
i liquid nitrogen or an acetone and ice mixture.
The grams of
[
}
water vapor / cubic foot gas is measured upstream of the cold i
trap in order to alleviate the difficulties in determining
{
water vapor collection efficiencies.
The tritium 56mples i
are analyzed by an independent laboratory.
From the uC1/mi 3
tritium concentration, the grams water /ft, and the vent i
flow rates, the monthly tritium release is calculated for i
each vent, and the quarterly summary can be generated from
]
the monthly calculation forms.
Hatch has attempted to maintain all calculated MDAs as low j
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 j
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 4
for the total fission and activation gas release, total I-131 release, total particulates with half-lives greater than 8-day
{
release, and total tritium release.
1 l
"The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total operation of sampling and measurement.
fm
(
)
Because it may be very difficult to assign error terms for each parameter af fecting 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 sLch items as charcoal cartridges.
1.
Fission and Activation Gas Total Release was calculated from process monitor readings. As 87.07% of this release was from the main stack the MDA release values of the ground level release points were small when compared to the total release.
Monitor Error in Calibration 50%
Vent Flow Rate 10%
Non-Steady Release Rate 20%
80%
2.
1-131 Release was calculated from each weekly sample:
Statistical error 60%
pd Counting Equipment Calibration 10%
Vent Flow Rates 10%
Vent Sample Flow Rates 10%
Non-Steady Release Rates 10%
Losses From Charcoal Cartridge 10%
110%
3.
Particulates with half-lives creater 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%
1 Countng Equipment Calibration 10%
Vent Flow Rates 10%
Vent Sample Flow Rates 10%
Non-Steady Release Rates 10%
100%
4 b
l l
i 4.
Total Tritium Release was dominated by.the reactor building vent tritium release, hence, the larger statistical errors of the off-gas vent and recombiner building vent tritium p
releases do not affect the error in the total tritium v
release:'
' Water Vapor in Sample Stream Determination 20%
Vent Flow Rates 10%
Counting Calibration and Statistics 10%-
Non-Steady Release 50%
1 90%
4 i
'(
2.3.GASE00S EFFLUENT RELEASE DATA s
4 j
l Regulatory Guide 1.21 Tables lA, 18 and 1C are found'in this report is Tables 2-la-c, 2-2a-c, and 2-3a-c.
Data is presentech on a quarterly basis as per Regulatory Guide t
1.21.
,3 3.
SOLIO WASTE s
3.1 REGULATORY SPECIFICATIONS l
a.
Measurements shall be made to determine or estimate the total curie quantity and principal radionuclide composition of all. radioactive solid waste shipped of fsite, 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 Part 71, and 49 CFR Parts 171-178.
c.
Reports of dhe radioactive solid waste shipments, volumes, principal radionuclides, and total curie quantity shall be submitted in accordance with subsection 5.6.1 of the HNP-ETS.
~
3.2 SOLIO WASTE DA1A.
?
l Regulatory guide 1.21 Table 3 is found in this report as Table 3-la.
9 i
^j I
O
T ABLE 2-la UNIT 1 l
EFFLUENT AND WASTE DISPOSAL SEMIAHHUAL REPORT 1983
-GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES
[ b
_~
Unit Quarter Quarter Est Total
'\\m /
E.
I. Hatch Nuc lear Power Plant UNIT 1 1
2 Error %
)"
A.
Fission & activation gases 1.
Tot al release Ci 2.39E+02 1.80E+02 8.00E+011 2.
Average release rate for period uCt/sec 3.04E+01 2.29E+01 3.
% of Technical spec t f t cat ion Itmit 6.43E-02 1.31E-01 B.
Iodines 1.
Total todine-131 Ci 7.14E-05 3.18E-04 1.10E+02l 2.
AveraQe release rate for period uCt/sec 9.09E-06 4.04E-05 3.
% of Technical spec i fi c at i on limit 3.57E-03 1.59E-02 C. Particulates
- 1. Particulates with half-lives >8 davs Ci 2.05E-03 2.09E-03 1.00E+02l 2.
Average release rate for period uC1/sec 2.61E-04 2.66E-04 3.
. of Technical s pec i fi c at i on limit 3.19E-01 2.43E-01 4
Gross alpha radioact ivity C1 3.13E-06 1.80E-05 D.
Tritium 1.
Tot al release C1 1.91E+03 2.18E+00 9.00E+011 2.
Average release rate for period uC1/sec 2.44E+02 2.77E-01 3.
% of Technical s pec i fi c at i on Itmit 2.20E+001 8.04E+00
. 1 n-m
TABLE 2-1b UNIT 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1985
( )
CASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est Total E.
I. Hatch Nuc lear Power Flant UNIT 2 1
2 Error './
A.
Fission & activation gases 1.
Tot al release C1 4.67E+02 2.55E+01 8.00E+011
__2.
Average release rate for period uCt/sec 5.94E+01 3.24E+00 3.
% of Tec hn t c al spectftcation Itmit 2.81E-01 4.23E-03 B.
- 1. Total todine-131 C1 8.57E-05 2.46E-05 1.10E+021 2.
Average rele ase rate for period uCtesec 1.09E-05 3.13E-06 3.
- of Tec hni c al spectftcation Itmit 4.28E-03 1.23E-03 l
3 C. Particulates 1.
Part t eul at es u t t h hal f-l i ves >8 days C1 1.46E-03 4.94E-04 1.00E+02l 2.
Average release rate for period uCt/sec 1.86E-04 6.28E-05
- 3. % of Tec hni c al spec t f t c at ion Itmtt 1.16E-01 5.77E-02 4
Gross alpha radioactivttv C1 1.49E-06 8.46E-06 l
D.
Tritium i
1.
Tot al release i
C1 3.81E+04 1.22E+00 9.00E+01l
( 'N 2.
Average release rate for pertod uCt/sec 4.85E+03 1.55E-01
(,s
- 3. % of Tec hni c al spec t f t eat t on ilmtt 2.98E+00 2.81E+00 l
0 v
TABLE 2-Ic SITE EFFLUENT AND WASTE DISPOSAL SEMIAHNUAL REPORT 1985 rx
(}
GASEOUS EFFLUENTS-SUNNATION OF ALL RELEASES Unit Quarter Quarter Est Total E.
I. Hatch Nuc lear Power Plant' SITE 1
2 Error %
A. Fission & activation gases 1.
Total release Ct 7.06E+02 2.06E+02 8.00E+01l 2.
Average release cate for perted uC1/sec 8.98E+01 2.62E+01 3.
% of Technical spec i fic at ion Itmtt 3.46E-01 1.35E-01 B. Iodines
- 1. Total todtne-131 C1 1.57E-04 3.42E-04 1.10E+02l 2.
Average release rate for period uCt/sec 2.00E-05 4.36E-05 3.
% of Technical specification Itmit 3.93E-03 8.56E-03 C. Particulates
- 1. Part icul at es ui t h hal f-lives >8 davs C1 3.51E-03 2.59E-03 1.00E+021 l
2.
Average release rate for period uCt/sec 4.46E-04 3.29E-04 3.
% of Techrical spectftcation limit 4.34E-01 3.01E-01
- 4. Gross alpha radioact ivt ty C1 4.62E-06 2.64E-05 D.
Tritium 1.
Total release Ct 4.01E+04 3.39E+00 9.00E+011
/N 2.
Average release rate for period uCt/sec 5.10E+03 4.32E-01
\\,)
3.
% of Technical specification limit 5.18E+00 1.09E+01 l
l J
I l
i i
i
TABLE 2-2a E.
I. Hat c h Nuc l e ar Power P l ant UNIT 1 EFFLUEHT AND WASTE DISPOSAL SEMIANNUAL AEPORT 1985 k
~
GASEOUS EFFLUENTS-ELEVATED RELEASE s-CONTINUOUS MADE BATCH NODE Huclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2 1.
Fission gases Xe-133 Ci 4.56E+00 1.12E+00 0.00E+00 0.00E+00 Xe-131m C1 1.49E+01 0.00E+00 0.00E+00 0.00E+00 Kr-88 C1 2.34E+01 1.42E+01 0.00E+00 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 C1 7.96E+00 1.07E+00 0.00E+00 0.00E+00 Kr-85M C1 1.52E+01 1.09E+01 0.00E+00 0.00E+00 I-131 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 C1 9.85E+00 2.22E+00 0.00E+00 0.00E+00 Xe-138 C1 2.09E+01 9.53E+00 0.00E+00 0.00E+00 Xe-137 C1 1.96E+01 2.56E+01 0.00E+00 0.00E+00 N-13 C1 4.03E+01 1.18E+01 0.00E+00 0.00E+00 Kr-85 C1 9.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ct 5.68E+00 2.56E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 5.56E+01 2.99E+01 0.00E+00 0.00E+00
"~}
Tot al for period Ci 2.18E+02 1.09E+02 0.00E+00 0.00E+00 v
2.
Iodines I-131 Ci 4.51E-05 7.23E-05 0.00E+00 0.00E+00 I-133 Ci 1.32E-04 3.76E-04 0.00E+00 0.00E+00 I-135 Ci 6.31E-05 3.86E-04 0.00E+00 0.00E+00 Total for period Ci 2.40E-04 8.34E-04 0.00E+00 0.00E+00 3.
Par t i c u l at e s Sr-89 Ct 7.45E-04 1.09E-03 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 Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 4.06E-08 0.00E+00 0.00E+00 0.00E+00 1
Sn-113 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 1.26E-05 9.66E-06 0.00E+00 0.00E+00 Cs-134 Ci 6.10E-07 1.68E-05 0.00E+00 0.00E+00 Cs-137 C1 1.18E-06 2.94E-07 0.00E+00 0.00E+00 Ce-144 Ct 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 Nb-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-50 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 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 4.30E-07 3.41E-07 0.00E+00 0.00E+00 l
[ 'T La-140 C1 2.46E-05 4.97E-05 0.00E+00 0.00E+00 I
N,,)
~
Total for period Ci 7.85E-04 1.17E-03 0.00E+00 0.00E+00 _
l TABLE 2-2b l
E.
I.
Hatch Nuclear Power Pl ant UNIT 2 s
EFFLUENT AND WASTE DISPOSAL set 11 ANNUAL REPORT 1985 1
\\--
GASEQUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2 1.
Fission gases Xe-133 Ci 6.12E+00 2.63E-01 0.00E+00 0.00E+00 Xe-131m Ci 2.00E+01 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ct 3.14E+01 3.31E+00 0.00E+00 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 C1 1.07E+01 2.51E-01 0.00E+00 0.00E+00 Kr-85M C1 2.04E+01 2.56E+00 0.00E+00 0.00E+00 1-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 C1 1.32E+01 5.20E-01 0.00E+00 0.00E+00 Xe-138 Ct 2.81E+01 2.23E+00 0.00E+00 0.00E+00 Xe-137 Ci 2.63E+01 S.995+00 0.00E+00 0.00E+00 N-13 Ci 5.40E+01 2.76E+30 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1
Xe-135M Ci 7.61E+00 6.00E-01 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 7.46E+01 7.02E+00 0.00E+00 0.00E+00 S
Tot al for period Ci 2.92E+02 2.55E+01 0.00E+00 0.00E+00 2.
Icdtnes I-131 I
Ci 6.05E-05 1.69E-05 0.00E+00 0.00E+00 I-133 Ci 1.77E-04 8.81E-05 0.00E+00 0.00E+00 I-135 Ci 8.47E-05 9.04E-05 0.00E+00 0.00E+00 Tot al for period Ci 3.22E-04 1.95E-04 0.00E+00 0.00E+00
- 3. Particulates Sr-89 C1 1.00E-03 2.56E-04 0.00E+00 0.00E+00__
Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 5.45E-08 0.00E+00 0.00E+00 0.00E+00 Sn-113 Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ct 1.69E-05 2.26E-06 0.00E+00
'O.00E+00 Cs-134 Ci 8.18E-07 3.93E-06 0.00E+00 0.00E+00 Cs-137 C1 1.58E-06 6.88E-08 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+0e Zr-95 Ct 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+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 5.77E-07 7.98E-08 0.00E+00 0.00E+00
,e 3
(
)
La-140 Ci 3.30E-05 1.16E-05 0.00E+00 0.00E+00 Total for period Ci
-1.05E-03 2.74E-04 0.00E+00 0.00E+00l
TABLE 2-2c E.
It Hatch Nuclear Pouer Plant SITE EFFLUENT'AND WASTE DISPOSAL SENIANNUAL REPORT 1985 4
l GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE BATCH MODE y
Nuclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2 1.
Fission gases Xe-133 Ci 1.07E+01 1.38E+00 0.00E+00 0.00E+00 Xe-131m Ci 3.48E+01 0.00E+00 0.00E+00 0.00E+00 f
l Kr-88 C1 5.48E+01 1.75E+01 0.00E+00 0.00E+00 l
Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
-Xe-135 C1 1.86E+01 1.32E+00 0.00E+00 0.00E+00 Kr-85M C1 3.56E+01 1.35E+01 0.00E+00 0.00E+00 1-131 Ci 0.00E+00
-0.00E+00 0.00E+00 0.00E+00 i
i Kr-87 Ci 2.31E+01 2.74E+00 0.00E+00 0.00E+00 Xe-138 C1 4.90E+01 1.18E+01 0.00E+00 0.00E+00 Xe-137 Ci 4.59E+01 3.15E+01 0.00E+00 0.00E+00 l
N-13 C1 9.43E+01 1.45E+01 0.00E+00
-0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
Xe-135M Ct 1.33E+01 3.16E+00 0.00E+00 0.00E+00 i
I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t
Kr-89 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I
I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 C1 1.30E+02 3.70E+01 0.00E+00 0.00E+00 Tot al for period Ci 5.10E+02 1.34E+02 0.00E+00 0.00E+00 j
2.
Iodines i
j I-131 Ci 1.06E-04 8.92E-05 0.00E+00 0.00E+00 I-133 C1 3.09E-04 4.64E-04 0.00E+00 0.00E+00 i
j I-135 Ci 1.48E-04 4.76E-04 0.00E+00 0.00E+00 j
Tot al for period Ci 5.62E-04 1.03E-03 0.00E+00 0.00E+00 1
3.
Particulates l
Sr-89 Ci 1.74E-03 1.35E-03 0.90E+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 0.00E+00 0.00E+00 0.00E+00 i
l I-131 Ci 9.51E-08 0.00E+00 0.00E+00 0.00E+00 i
Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
Ba-140 C1 2.95E-05 1.19E-05 0.00E+00 0.00E+00 Cs-134 C1 1.43E-06 2.07E-05
-0.00E+00 0.00E+00 Cs-137 C1 2.76E-06 3.62E-07 0.00E+00 0.00E+00 i
Ce-144 C1 0.00E+00 0.00E+00 0.00E+00 0.00i+06 i
Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+90 Nb-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+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
-Co-60 Ci
'1.01E-06
-4.20E-07 0.00E+00 0.00E+00 La-140 Ct 5.76E-05 6.13E-05 0.00E+00 0.00E+00 1
Total for period Ci 1.84E-03 1.44E-03 0.00E+00 0.00E+00 Y'.
-36 '
TABLE 2-3a E.
I.
Hatch Nuclear Pouer Plant UNIT 1 l
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1985 1
l
\\
GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2 1.
Fission gases Xe-133 Ci 4.68E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m C1 0.0AE+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 6.69E-01 5.59E-02 0.00E+00 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 Ci 2.16E+00 1.65E+01 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 Ci 9.85E-01 7.87E+00 0.00E+00 0.00E+00 Xe-138 Ci 5.60E+00 1.01E+00 0.00E+00 0.00E+00 Xe-137 Ci 1.46E-01 1.67E+00 0.00E+00 0.00E+00 H-13 Ci 5.46E+00 4.40E+01 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M C1 1.51E+00 2.38E-01 0.00E+00 0.00E+00 I-133 Ct 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 6.83E-02 0.00E+00 0.00E+00 0.00E+00 fS Total for period Ci 2.13E+01 7.13E+01 0.00E+00 0.00E+00
\\)
2.
Iodines I-131 C1 2.37E-05 3.48E-05 0.00E+00 0.00E+00 I-133 Ci 1.17E-04 1.39E-04 0.00E+00 0.00E+00 I-135 Ci 5.37E-05 1.43E-05 0.00E+00 0.00E+00 Tot al for period Ci 1.95E-04 1.88E-04 0.00E+00 0.00E+00 f
3.
Part i c ul at es Sr-89 Ci 8.76E-04 3.67E-04 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 4.52E-05 5.93E-05 0.00E+00 0.00E+00 I-131 Ci 2.54E-06 2.11E-04 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 3.31E-07 0.00E+00 0.00E+00 0.00E+00 Cs-134 Ci 5.00E-05 1.70E-05 0.00E+00 0.00E+00 Cs-137 C1 1.33E-04 6.71E-05 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 2.79E-06 0.00E+00 0.00E+00, Nb-95 Ci 0.00E+00 2.26E-05 0.00E+00 0.00E+00 Co-58 Ci 2.42E-06 4.37E-05 0.00E+00 0.00E+00 Mn-54 Ci 1.57E-05 8.87E-06 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 4.20E-09 0.00E+00 0.00E+00 Co-60 Ci 1.39E-04 1.21E-04 0.00E+00 0.00E+00
[
La-140 Ci 1.08E-06 4.70E-06 0.00E+00 0.00E+00 C
Tot al for period Ci 1.27E-03 9.25E-04 0.00E+00 0.00E+00 TABLE 2-3b E.
I. Hat c h Nuc l e ar Pouer Plant UNIT 2
{
<w EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1985
(
\\-
GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTINUOUS MODE BATCH MODE Huclides Released Unit
- Quarter Quarter Quarter Quarter 1
2 1
2 1.
Fission gases Xe-133 Ci 3.17E+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 3.08E+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 1.63E+01 0.00E+00 0.00E+00 0.00E+00 Kr-85M Ci 2.79E+01 0.00E+00 0.00E+00 0.00E+00 4
1-131 Ci 0.00E+00 0.00E+00 0.00E+30 0.00E+00 Kr-87 C1 3.62E+00 0.00E+00 0.00E+6' O.00E+00 Xe-138 C1 0.00E+00 0.00E+00 0.00E+03 0.00E+00 Xe-137 Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N-13 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 C1 6.41E+01 0.00E+00 0.00E+00 0.00E+00
- (}
Total for period Ci 1.74E+02 0.00E+00 0.00E+00 0.00E+00 V
2.
Iodines I-131 C1 2.47E-05 7.71E-06 0.00E+00 0.00E+00
[
I-133 Ci 1.07E-04 2.56E-05 0.00E+00 0.00E+00 I-135 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tot al for period Ci 1.31E-04 3.33E-05 0.00E+00 0.00E+00 3.
Particulates Sr-89 C1 3.84E-04 1.97E-04 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 [
I-131 C1 3.57E-07 0.00E+00 0.90E+00 0.00E+00 Sn-113 Ci 2.78E-07 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 4.59E-06 0.00E+00 0.00E+00 0.00E+00 Cs-134 Ci 2.82E-06 9.16E-06 0.00E+00 0.00E+00 Cs-137 C1 7.55E-06 2.07E-06 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 C1 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+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 6.53E-06 1.75E-06 0.00E+00 0.00E+00
-(s La-140 C1 0.00E+00 9.81E-06 0.00E+00 0.00E+00
~
Tot al for period Ci
'4.06E-04 2.20E-04 0.00E+00 0.00E+00J
TAELE 2-3c E. I& Hatch Nuclear Power Pl ant SITE fs EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1985 l
GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 1
2 1
2 1
- 1. Fission gases Xe-133 Ci 3.64E+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 3.15E+01 5.59E-02 0.00E+00 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 C1 1.84E+01 1.65E+01 0.00E+00 0.00E+00 Kr-85M Ci 2.79E+01 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ci 4.60E+00 7.87E+00 0.00E+00 0.00E+00 Xe-138 Ci 5.60E+00 1.01E+00 0.00E+00 0.00E+00 Xe-137 Ci 1.46E-01 1.67E+00 0.00E+00 0.00E+00 N-13 C1 5.46E+00 4.40E+01 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M C1 1.51E+00 2.38E-01 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 Ci 6.42E+01 0.00E+00 0.00E+00 0.00E+00 s
Tot al for period Ci 1.96E+02 7.13E+01 0.00E+00 0.00E+00 2.
Iodines I-131 Ci 4.85E-05 4.25E-05 0.00E+00 0.00E+00 I-133 Ci 2.24E-04 1.65E-04 0.00E+00 0.00E+00 I-135 Ci 5.37E-05 1.43E-05 0.00E+00 0.00E+00 Total for period Ci 3.26E-04 2.22E-04 0.00E+00 0.00E+00
- 3. Part i c ul at e s Sr-89 Ci 1.26E-03 5.64E-04 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 C1 4.52E-05 5.93E-05 0.00E+00 0.00E+00 I-131 Ci 2.89E-06 2.11E-04 0.00E+00 0.00E+00 Sn-113 Ci 2.78E-07 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 5.32E-06 0.00E+00 0.00E+00 0.00E+00 Cs-134 Ci 5.28E-05 2.61E-05 0.00E+00 0.00E+00 Cs-137 Ci 1.41E-04 6.92E-05 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 2.79E-06 0.00E+00 0.00E+00 Nb-95 Ci 0.00E+00 2.26E-05 0.00E+00 0.00E+00 Co-58 C1 2.42E-06 4.37E-05 0.00E+00 0.00E+00 Mn-54 C1 1.57E-05 8.87E-06 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 4.20E-09 0.00E+00 0.00E+00
~
Co-60 Ci 1.45E-04 1.23E-04 0.00E+00 0.00E+00 (g)
La-140 Ci 1.08E-06 1.45E-05 0.00E+00 0.00E+00 Tot al for period Ci 1.67E-03 1.15E-03 0.00E+00 0.00E+00 r
EFFLUENT AND WASTS DISPOSAL SEMIANNUAL REPORT (YEAR) 1985 January 1 1985 - June 30, 1985 f-S'OLID WASTE AND IRR ADIATED FUEL SHIPMENTS FOR UNIT I-
& II A. SOLID %'ASTE SHIPPED OFFSITE FOR BURIAL OR DISPCSAL (fJot inadiated fuell koam E p. To ol unis
- 1. Type of waste Pwiod Error %
~
- a. Spent r:s:ns, h!ter sh.as:s, enporstor m#
l_2.32E+2 tntter.s. ete.
Ci i 5.13 E+2 1.0 E +1 D. Dry compresa::: waste, contst:unstee r".'
5 82 E+2 equip, etc.
Cl 1.13 E+1 1.O En
- c. Irred.sted components, centrol 2+ 2d W '
m' re,'.s. e::.
C1
- 2. 85~E+4 1.0 E+z
$N1d5N#ddoil, sources 1.0 E-2
- 2. Estim:te of maior aucUde composi: ion (by tm of waste)
ISOTOPE PERCENT l
CURIES a.
Zn-65 41 As 911 A7 Cs-137 19.79 QA 11 Cs-134 14.24 71 l a All others 25.47 lan a; m
b.
Zn-65 37.16 a 14 Cs-137 11.37 1 ?R Co-60 40.00 4 61 All others-11.52 1.3n c.
Co-60 47.10 13414 97 Fe-55 44.09 19657.73 Mn-54 4.16 11R3 ao All others 4.65 1324.61 d.
Co-60 55.06 0.2RG LS-137 l
4.42 0.073 Ln-bo 32.49 0.16R 8.03 0.047 All others 3.
SoUd Weste D:sposition Number of Shi:ernts Mede o rTr:.nsoort: tion D:stination 46 Cask Barnwell, S. C.
29 Van Hanford, Washington S. IRRADIATED FUEL SHIPMENTS (Dis,wition)
Number of Shier-ents Mode ef Transportation Destfrution N/A N/A N/A
' pa a
.~
-,