ML20079M788

Semiannual Rept:Plant Radioactive Effluent Releases, Jul-Dec 1982

ML20079M788
Person / Time
Site:	Hatch
Issue date:	02/23/1983
From:	GEORGIA POWER CO.
To:
Shared Package
ML20079M777	List: ML20079M774 ML20079M783 ML20079M788
References
NUDOCS 8303030228
Download: ML20079M788 (51)

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{{#Wiki_filter:; Georgis Powtr Compiny Post Offica Box 439 Baxley, Georcia 31513 Tgliphons 912 367-7781 912 537-9444 O c eorgia go er Edwin 1. Hatch Nuclear Plant February 23, 19 GM-83-197 PLANT E. I. HATCH Semi-Annual Radioactive Effluent Release Report Director of Inspection and Enforcement % Distribution Services Branch U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen: Pursuant to Section 5.7.1.b in Appendix B, Environmental Technical O Specifications, of the Plant Edwin I. Hatch Operating

Licenses, please find enclosed the Semi-Annual Report for Plant Radioactive Effluent Releases, July 1, 1982 through December 31, 1982.

/.ly An m H. C. Nix / General Manager WHR/jak 1 l 1. g ia?"o*so223o ?u e a . :- =

10 ~ l GEORGIA POWER COMPANY 4' PLANT E. I. HATCH UNITS NO. 1& 2~ SEMI-ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JULY 1, 1982 - DECEMBER 31, 1982 s e O j I i 1 i f e t I l O. i I d

PLANT E. I. HATCH SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES SECTION TITLE PAGE 1. LIQUID EFFLUENTS 1 1.1 REGULATORY LIMITS 1 1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS 2 1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 4 1.4 LIQUID EFFLUENT RELEASE DATA 6 - 2 GASEOUS EFFLUENTS 29 2.1 REGULATORY LIMITS 29 2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 31 2.3 GASEOUS EFFLUENT RELEASE DATA 35 3 SOLID WASTE 35 3.1 REGULATORY SPECIFICATIONS 35 3.2 SOLID WASTE DATA 35 e 6 5 ._._.a a

PLANT E. I. HATCH SEMIANNUAL REPORT PLANT RAD'IOACTiVE EFFLUENT RELEASES ) FIGURE LIST OF FIGURES PAGE l-1 METHODS OF MEETING TABLE II 7 COLUMN 2 MPC LIMITS (10 CFR 20) 1-2 LIQUID RADWASTE ANALYSIS - UNIT I 8-12 l-3 LIQUID RADWASTE ANALYSIS - UNIT II 13-17 1-4 LIQUID RADWASTE DISCHARGE PERMIT 18 2-J 1-Sa, b LIQUID RADWASTE DATA COMPILATION 19, 22 TABLE LIST OF TABLES PAGE i 1-la, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 23, 24 1-2a, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLUENTS-BATCH ONLY 25, 28 2-la-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENT-i {) SUMMATION OF ALL RELEASES 36-38 l 2-2a-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-ELEVATED RELEASE 39-41 j 2-3a-c EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-l GROUND LEVEL RELEASES 42-44 i 3-la, b EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 45 i e 1 I e J

PLANT RADIOACTIVE EFFLUENT RELEASES 1 LIQUID EFFLUENTS 1.1. REGULATORY LIMITS O ~/ 1. The concentration of radioactive materials released in liquid wastes from all reactors at the site shall not exceed the values specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for unrestricted area. ~ 2. The cumulative release of radioactive materials in liquid wastes, excluding tritium and dissolved gases, shall not exceed 10 Ci/ reactor / calendar quarter. 3. The cumulative release of radioactive materials in liquid wastes, excluding tritium and dissolved gases, shall not exceed 20 Ci/ reactor in any 12 consecutive months. 4. During release of radioactive

wastes, the effluent control monitor shall be set to alarm and to initiate the automatic closure of the waste discharge valve prior to exceeding the limits specified in 1. above.

5. The operability of the automatic isolation valve in the liquid radioactive waste discharge line shall be-demonstrated quarterly. 6. The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to O process radioactive liquid wastes prior to their discharge when the projected cumulative release rate could exceed 1.25 Ci/ reactor / calendar

quarter, excluding tritium and dissolved gases.

7. The maximum radioactivity to be contained in any liquid radwaste tank that can be discharged directly to the environs shall not exceed l'0 Ci, excluding tritium and ~ dissolved gases. 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 Commission within 30 days from the end of the quarter during which the release occurred.

9. An unplanned or uncontrolled offsite release of radioactive materials in liquid effluents in excess of 0.5 Ci excluding dissolved gases shall be reported. O ^ 1 w+, s.. .~

1.2. MAXIMUM PERMISSIBLE CONCENTRATIONS The MPC values used in determining allowable liquid radwaste release concentrations.are taken from 10 CFR Part 20, Appendix B, Table II, Column 2. Release rate and dilution ratio for each batch are determined by a mixed nuclide MPC calculation performed before the release of the batch. To facilitate the measurements w and calculations, the nuclides of Column 2 which can be produced g in a fission reactor have been grouped according to MPC value and type of radiation as shown in Figure 1-1. .J 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 f rom 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 I' individual batch release calculations. Although the MPC limit for tritium is greater than 9 X 10 -6, a separate measurement is made for tritium since the gross beta technique does not provide an acceptable tritium measurement. A distillation and liquid scintillation counting technique is used to measure tritium concentration. The maximum activity of gamma and beta emitting nuclides with MPC O ve1ues ere eer enea 9 x 1o -6 uci/=1-exceve cor the 2e nuclides noted above, is determined by gross gamma and gross beta i measurements. Measurement sensitivity limits of approximately 2 l cpm /ml allow a null measurement to show that the sum I (Ci/MPCi), is less than 0.1 for gamma and beta nuclides not I measured directly. The sum of the ratios, I (Ci/MPCi), for alpha emitters can be j shown t'o be less than 0.1 by a null measurement with a i 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 i in a fission reaction (eg. I-125, I-129 etc.), the methods i 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 catch are "used to calculate the dilution ratio. release rate, and dilution rate prior to release of each batch. Both the concentration and 7 l release data are stored on a computer disc file. The disc file data is used to assure that quarterly and annual release limits i are not exceeded. Bases used-for the data of Table 1-1 are as follows: O. i I z a

A. Fission and activation products - The total release values (not including tritium, gases, alpha) are comprised of the sum of the individual radionuclide activities and include the LLD concentration of all isotopes that were not measured but did not meet the minimum sensitivity limit as set forth ( in the Environmental Tech Specs. This sum is for each batch released to the river for the respective quarter. Percent of applicable limit is determined from a mixed nuclide MPC calculation. The average concentration for each nuclide summed over all batches is divided by the corresponding individual MPC value. The sum over all nuclides of the Ci/MPCi ratios times 100 is the percent of applicable limit for effluent releases during the quarter. B. Tritium - The measured tritium concentration in a composite sample is used to calculate the total release and average diluted concentration during each period. Average ' diluted concentration divided by the MPC limit, 3 X 10 -3 uCi/ml, is converted to percent to give the percent of applicable limit. C. Dissolved and entrained gases - Concentrations of dissolved and entrained gases in liquid effluents are measured on each batch by Ge (Li) spectroscopy on a one liter cample 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 hours; Xe-135, Xe-133m, Xe-133, and Kr-85. Iodine radionuclides in any form are also determined during the isotopic analyris 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/ml of each dissolved and entrained radionuclide as specified in Regulatory Guide 1.21, has been applied in determining the percent of applicable limit. P e O ~ i 3 4 1

1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY. Details.of the analytical procedures for liquid radwaste analysis are contained in operating procedure HNP-7601. The following measurements are performed as indicated: MEASUREMENT FREQUENCY METHOD 1 1. Gamma Isotopic Each Batch Ge (Li) spectrometry with on-line computer. 2. Gross Gamma Each Batch 2 X 2 NaI well crystal 2 counting 3. Gross Beta Each Batch Gas flow proportional counting 4. Sr-89 Quarterly Chemical separation and Composite gas flow proportional counting 5. Sr-90 Quarterly Chemical separation and Composite gas flow proportional counting 6. Tritium Monthly Distillation and liquid Composite scintillation counting 7. Alpha Monthly Gas flow proportional Composite counting (} 8. Dissolved Gases Each Batch Ge(Li) spectrometry with I on-line computer I { l i I I I i i i 4 4

If a liquid radwaste ~ tank cannot be reprocessed, o sample for analysis is taken from the tank after the required recirculation time. The sample is used for gamma-ray spectroscopy, gross gamma and gross beta counting, and for preparation of a composite sample. The Ge(Li) detector consist of a 10% and two 15% efficiency, 2.0 FWHM resolution detectors in 4-inch thick lead shields. A one-liter radwaste liquid sample is poured in to a Marinelli beaker in preparation for a 2000-3000 second Ge(Li) count. A peak search of the resulting gamma ray spectrum is performed-by the on-line computer system. Energy and net count data for all significant peaks are determined, and quantitative reduction or MDA calculations are performed for the nuclides listed in Figure 1-1. The quantitative calculations include corrections for counting

time, decay

time, sample

volume, sample

geometry, detector efficiency, baseline counts, and branching ratio.

MDA calculations, including the above corrections, are made based on the counts in two standard deviations of the baseline count at the location on the spectrum where a peak for that nuclide would be located if present. The calculated radionuclide concentrations or MDA values from the gamma scan and from previously stored Sr-89 and Sr-90 values are used to calculate the dilution ratio I (Ci/MPCi) and allowable release parameters. A sample printout is shown in Figures 1-2 and 1-3. The Liquid Radwaste Discharge Permit Printout is transferred item by item to the first portion of the release permit (Figure 1-4) by a laboratory technician. Although the computer could printout l Q the release permit and will inform the technician if a batch v cannot be discharged as desired, a manual transfer of calculated l results to the release permit by'the technician was implemented as more likely to catch abnormal conditions in the data. The liquid radwaste monitor setting is calculated by the computer based on the. gamma activity as measured in the sample used for laboratory analysis. A coefficient ' has been determined which l 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 l monitor reading in excess of the calculated setpoint therefore results in an automatic termination of the liquid effluent l discharge. Liquid effluent discharge is also automatically i 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 l scanned to display trends in any recorded parameter, or may be summed for reporting purposes as shown in Figure 1-Sa and b. l O 5 a .a

All other radionuclide. concentration measurements are performed as indicated in the table given previously in this section and as detailed in the procedure HNP-7601. The dissolved gases calculation is performed in the Ge(Li) spectrometry system with 'O come ter date reductioa usine the Lieuid aedwesee Lihrery which includes gases. I Several comments are indicative of the success of the HNP liquid radwaste program during this reporting period: 4 4 1. The total measured activity released in liquid effluent for both Units was 1.65 E-1 curies for the third quarter and 3.12 E-1 curies for the fourth quarter. These values were approximately 1/77 for Unit 1 and 1/289 for Unit 2 for the l third quarter and 1/42 for Unit 1 and 1/134 for Unit 2 for !W. the fourth quarter of the allowed 10 curies per quarter per j reactor. 4 2. The radwaste release procedure strongly emphasized reprocessing rather than discharge of liquid radwaste. During this report period 27.75% of the liquid radwaste reaching the sample tanks was discharged; 72.25% was recycled back into both of the reactor water systems. 3. A complete isotopic scan, gross beta, and gross gamma counts and computer analysis were performed prior to the release of each of the 874 discharge batches for both Units. 1.4 LIQUID EFFLUENT RELEASE DATA O Re9ulatory cuide 1.21 Tables 2A and 28 are found in this report i as Table 1-la, b and 1-2a, b. Data is presented on a quarterly basis as per Regulatory Guide 1.21. Other data pertinent to batch releases of radioactive effluent from both units is as follows: Number of batch releases: 874 Total time period for releases: 124,465 minutes j Maximum time period for a batch release: 527 minutes Average time period for batch release: 142 minutes l Minimum time period for a batch release: 24 minutes Average stream flow during periods of release of effluent into a flowing stream: 5,543 CFS 1 i e O. I-i' 6 a . ~

FIGURE l-1 METHODS OF MEETING, TABLE II, COLUMN 2 MPC LIMITS MPC RANGE GAMMA-RAY BETA ALPHA s (U Ci/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 (Gas Flow

Counting, Sensitivity

0. 01 CPM /ml)

Ba-La-140, Na-24,Cu-64 Tritium CO-60, Fe-59, Zn-65 9 x 10-6 Aq-110m, Mn-54, C0-58 (Distillation & ~ Liquid Scintil-lation Counting) i Zr-Nb-95, Cs-Ba-137 As-76, F-18, Cr-51 All Others Np-239, Ce-141 Mo-Tc-99, Ce-Pr-144 (Gas Flow Count-(Ge (Li) Gamma-Ray ing Sensitivity Spectroscopy) 2 CPM /ml All others (Gross Gamma-Well Counter; Sensitivity 5 CPM /ml) 8 e 1 7 e ~ _, _ _ r ~ JZ.. 9 '. i.. . 5

wa w '"*Mb FIGURE l-2 '. ',+. s-

1. 5:

f r. i + I\\ -- ~ y

• • ,-,-*-4********+*****************************

T;.; ^ E. I. H at ch Huc l e ar Plant i [.~ - Liquid Radwaste Analysis I ?"' i _~ ,L t m.

e...

s>M. 3 -- W.- a'e t'o r #. 1 Batch # 700 Ta'rsk: CHSTB1 Recirc time: 65 minutes t--- d-$p,'" NN *~" ' UI6H C0tG TURB F. S. Ru[date: 8/17/S2 0925 Count start date: 8/17/82 0805 i arept e volume: 1000.00 ml Clock time: 3000 secs I i ](feometry code: 1LHE-0 Live time: 3000 secs etector# 2 MCA# 2 ' brary: LRULB2 Operator: AM i '~ n. [. ex5 ' ~ Energy (kev)= .36 + 1.000+Ch# + 0.000E+00*Ch#^2 + 0.000E+00*Ch#^3: 08/17/82 0620 e. ,.g:.. - ~;- Err = 1/[1.180E-02

• E^(-3.7497E+00) + 549.294
• E^(8.4451E-01>3 : 08/09/S2 0107 i

twhere E = Energy in HeV. _, _~~ ~ -~~ \\ .-y,,- . y.,.. I k '~ - G

p. g...

i4e .?,~_ f .e, r-II 2.. I t iI i i lI g 4 L. _..._......%;.4.~. .L-3-..-a-

1 FIGURE l-2 (CONr) /' (U w. de - .......................m............... g T:.b. s- + Ce-144 132.26 2.737E-07 3.634E-07 1E-05 2.79E-02 lj-j.3Tc -99ta 140.50 <8.234E-08 3E-03 <2.74E-05 g g"!MCe-141 145.40 <1.471E-07 9E-05 <1.63E-03 s '"Hp-239 277.90 <6.938E-07 1E-04 (6.94E-03

Cr-51

--*' 32 0.10 w: <8.885E-07 2E-03 <4.44E-04 's. . MI'I-131

• .a : 364. 51

• 1.138E-06 1.201E-07 3E-07 3.79E+00

~ 'M 2 $y.Mn': 69 m --'**4 3 8. 7 0 *'" < 1. 015E-07 6E-05 <1.69E-03 [ .H-187 479.50 <3.733E-07 6E-05 <6.22E-03 k.gg I - 18 510.63 <2.142E-07 5E-04 <4.28E-04 { W I-133 529.50 <1.110E-07 1E-06 <1.11E-01 pa hpBa-140 537.40 <4.048E-07 2E-05 <2.02E-02 .- +t e.d;Y C 2-13 4 g.;- A s -76 559.30 <2.201E-07 2E-05 <1.10E-02

g.f. O.

604.33 6.'88SE-06 1.825E-07 9E-06 7.65E-01 - }{p ?}$ff* C2-137 661.18 1.138E-05 2.392E-07 2E-05 5.69E-01

M...wg?.M.? r. Zr-9 7 f Mo-99 738.59 1.769E-07 3.727E-07 4E-05 4.42E-03 743.50

<8.236E-08 2E-05 (4.12E -03 h W W.Zr-95 756.90 <1.410E-07 6E-05 <2.35E-03 '['M,._.M.Hb-9 5 765.80 <8.478E-08 1E-04 <8.48E-04 I-132 772.60 <?.631E-08 8E-06 <9.54E-03 $ @p Co-58 ( 810.60 <8.401E-08 9E-05 <9.33E-04 k WEHn-54 834.31 7.150E-07 8.400E-08 1E-04 7.15E-03 -enew;J2 Ag-110m 884.70 <1.078E-07 3E-05 <3.59E-03 rn* 'rc.:A.p. .%'ty.$[iZn-65 1114.70 5.58'7E-06 2.774E-07 1E-04

5. 59E- 02

~ A$,7.E;I-135 1260.50 <1.378E-07 4 E-M <3.44E-02 '35p d Z Fe-59 1291.60 <1.194E-07 6E-05 <1.99E-03 ihd,GMe Co-60 1331.46 3.158E-06 1.494E-07 3E-05 1.05E-01 dj.W W Cu-64 -1345.90 <7.620E-06 2E-04 <3.81E-02 @dd d NdLa-140 ~ 3E-05 <1.31E-03 '#O: Ha-24 1368.55 .<3.942E-08 1596.60 <4.035E-08 2E-d5 <2.02E-03 l3?.y ' Hn-56 1811.00 <8.560E-08 1E-04 <8.56E-04 ?;"d';t,.Sr-89 <EETA) <3.000E-08 3E-06 <1.00E-02 [K.G '.Sr-90 (EETA) .1.000E-08 3E-07 <3.33E-02 $(.., H-3 (BETA) 6.830E-03 3'.000E-06 3E-03 2.28E+00 Fe-55 (BETA) <2.000E-06 8E-04 <2.50E-03 M [.;...P-32 ( EC > (1.000E-07 2E-05 <5.00E-03 ,p'gse;-,,_.

e. 4.5 -.. - Heasured totals 6.859E-03 3.079E-06 7.60E+00 7 C LLD totals

<1.400E-05 <3.11E-01 I N YN C Tot'als 6.873E-03 7.91E+00 }$-$.:;; hiff...:.; L. IE!/'f^" ~' ' D I S SOL VED C AS E S c...J ~ X.i-133 80.99 <3.463E-07 4E-05 <8.66E-03 Js~ ' X e - 13 3 ru 233.18 <8.542E-07 4E-05 <2.14E-02 Kr-88 196.10 <1.739E-07 4E-05 <4.35E-03 Xe-135 249.60 <8.355E-08 4E-3 <2.09E-03 i L.u. Kr-85m 305.00 <5.402E-07 4E-05 <1.35E-02

Y Kr-87 402.70

<1.251E-07 4E-05 <3.13E-03 ' N.. Xe-138 434.50 <2.753E-08 4E-05 <6.88E-04 i] Heasured gas totals 0.000E+00 0.000E+00 0.00E+00 q g i l j 7 .1 ..._. a 3

j%.*.y... FIGURE l-2 (CONT) l M,y.M;.LLD gas tot 412 -<2.151E-0C <<5.38E 02,3 { j g gas 2.151E-06

• -4&v#gJ[. To r. a l 5.38E-G2,3 Ti&

7. I.&y:: --Q: W'.W. y

).'.

m.. n, ,,1;k[.]4*d,ffjf[ - CROSS ACTIVITY gg Counter Gross

Background

T i nie vol Het Error . [Mf.& g{ND&m. Counts Counts (Min > ml Activity (cpm / % p), Sigma .ag g.3------------- Crystal 2761 1517 20.0 2 3.11E+01 hNdN, h. Hell 1.64E+00 s "g Proport i on al 491 196 10.0 2 ]~ 1.48E+01 )g 1.31E+00 gam - E5TIMATED HASTE TAHK VOLUME = 7146.00 gal l ons ,3 m.

r. -

. ESTIMATED ACTIVITY THIS BATCH I g g a.. EXCLUDING GASES: - - - 1.86E-01 ' Curies ( 1.86E+05 Microcuriesh rg,3 p g.,s;g M EXCLUDING H-3 AND GASES: 7.93E-04 Curies ( 7.93E+p2 Mi c roc uri es3 yr ;,3 g.. , y puyp>.<w g .,,.N-Nn.. :.~,T[~ACT'I V I TY ^0F TH I S B A TCH (EXCLUDING H-3 AHD GASES)-IS 793.04 u C i),. uCi 5.y,- c.Ldf:%.. T H q .THE MAXIMUM TAHK RELEASE LIMIT IS 300 uCi E b g ~; LAB SUPERVISOH APPROVAL HEEDED FOR THI~S RELEASE h t% ? W.- E k-N hm.NELEASE APPROVED BY: ACC 2 y ,..J. 1 23 es%e = m -> d y.s+n 6 tar.tner:c. ? ~ [*^"'i Q M - l. a g; % s g 4.%, 2h+44.e?.'r.. Liquid Radwaste Rel ease Surumaru T , %c f .m i 4

• M1) Meas. conc., excluding H-3 and dissolved gases (uCi/ml); 2. 93E-05 e.g-Gy:94E-073

- Ed..f.-( M e as. conc., including H-3, excluding gases

6.'86E'-03 M_4pSE-Ci6iy l

(uC i /t.1 ):; 313 pf,-05 Sy -r 2') Calculated LLD concentration, excluding dissolved gases 4 ..si.wgr.. St, pg ' l.ft';*jA,",.,3 ) C a l c u l at e d M P C r at i o (C/MPC of meas., including gases >: 7.60E,+00 .q., 0 0 '4.9 %* ;T 'f %@'32' 4 ) M i n i mum dilution flow rate (gpm): 10000 .T h@'D ' ~ Ik .iffffC: 5) Maximum tank discharge flow rate (gpm): 1514 ii D'W.lE*.,. .? ..If.h.s,d.6) Spe c i f i ed t ank flow rate (gpm): 75 if j- , m.wu. . -JS;. .7)Radwaste monitor trip setting: 9402 i't ' ff.Q ' A = 2.93E-05,uCi/ml 10 ', Mon i t or E,G,,QJjS f. - C = 54050000.00, Monitor CPS per uCi/ml ,Conserv. Faggy p, -e-v . Q~+.;,> Sr-89, Sr-90, H-3, Fe-55, P-32 ~.nd gases but ex g4de,s: 3h c = .s,g.2 --. A includes measured ' selected','other' nuci ,;F.r.p.%~ i

.[.p.,. S.) Es t i niat e d c on c. of meas. nuclides at point of release (uCi/ml)

5.j 0,6E,05

v. ;., -

1

9) Monitor maximum to ensure-10CFR20 limits are not.. exceeded: 27995 27995

./ ih ". 5- ? 2.- uz : .'.n c.. .'.s v. g. a; i ?.h: l -~ i. ' ESTIMATED DOSES THIS BATCH, MREN l - s.,..* .h e. ' T-i r. H. E.od y Eone Liver Thyroid Kidney Lung GI-LLI b! g n .-Isot. ope I ,hm :. :,:. e,9 ..2?.N.;. - 10 .-e. e' -e-

r mcz. 1-2 Bvar ~. Jd.' Ce-144 Qe. [.. 34-1 0

.005-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.73E-09 3.22E-08 1.35E-00 0.00E+00 8.01E-09 0.00E+00 1.09E-OS g.g-1, T c -9 9 r..

0.00E-00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .+.n.4 Ce-141 0.00E*00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 f,11% Kr 4? [kgg',Xe-13h 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j 'n.p.- Xe-135 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i p g Up-239 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l 4- T Kr-SS. 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ! di' $ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i s $js;8h.r Cr-51 yl-131 4.33E-07 5.29E-07 7.56E-07 2.48E-04 1.30E-06 0.00E+00 1.99E-07 m..-pKr-87 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 86 Q.hXe-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 p$ M Zn-69m 0.00E+00 0.00E*00 0.00E+00 0.00E+00 'O.00E+00 0.00E+00 0.00E+00 ggH-187 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .W /M.F-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6 i-I - 133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7 Ba-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1,, . - As-76 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F -L- -~ ^,Cs-134 1.37E-03 7.03E-04 1.67E-03

0. 0 0 E + 0,.,

5.42E-04 1.80E-04 2.93E-05 Cs-137 ~1.33E-03 1.49E-03 2.03E-03 0.00E+00 6.92E-04 2.30E-04 3.95E-05 ... y...FMo-99

• • 5.77E-08 0.00E+00 3.04E-07 0.00E+00 6.86E-07 0.00E+00 '7.03E-07 E.d ;. # ~97 ~~~'O.00E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M' RM Zr-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

~0.00E+00 j f h'UQHb-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TM-(I-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M's'."Co-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+^0 0.00E+00 g g Mn-54 1.57E-07 0.00E+00 8.22E-07 0.00E+00 2.44E-07 0.00E+r 2.52E-06 [k b @.i.Ag-110rn S. w 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 3.19E-05 2.21E-05 7.05E-05 0.00E+00 4.72E-05 0.00E+00 4.44E-05 N.1-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 P N p.Fe-594 M.'Co-607.17E-06 0.00E+00 3.25E-06 0.00E+00 0.00E+00 0.00E+00 6.11E-05 pw N M.l'Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M Ha-24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0,.00E+00 ) gyyLa-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 'O.00E+00 0.00E+00 j 1 M --+Mn-56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 h[Sr-39 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 J ~;.{.eSr-90 g 0.00E+00 0.00Et00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 %*7 H-3 1.83E-06 0.00E+00 1.83E-06 1.83E-06 1.85E-06 1.83E-06 1.83E-06 ,1 T*5 M;'t Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Gi % ~..P-32 q q --...- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 g'g.'.To t al 2:74E-03 2.22E-03 3.78E-03 2.50E-04 1.29E-03 4.12E-04 1.90E-04 ..mte, @.M.c ..e.m - &ns '.dgn;./ Cumu l at i ve dos e this YEAR (includes est imate for this batch): f KTK uhole body 5.66E-01 mrem Percent of Tech Spec Limit: 1.89E+01 ~". Bone 4.49E-01 mrem Percent of Tech Spec L i nii t : 4.49E+00 ~ M.% ~, Liver 7.78E-01 mrem Percent of Tech Spec Limit: 7.78E+00 5 $,jfk... Thyroid 1.61E-01 mrera Percent of Tech Spec Limit: 1.61E+00 l As-g[M@h Kidney 2.67E-01 mrem Percent of Tech Spec Limit: 2.67E+00 Lung 8.37E-02 mrem Percent of Tech Spec Limit: 8.37E-01 S GI-LLI 4.50E-02 mrem Percent of Tech Spec Limit: 4.50E-01 .ti m+.... w-a - Cumulative doze this QUARTER (inc ludes estimate for this batch): l .Qg Whole body 6.03E-02 mrem Percent of Tech Spec Limit: 4.02E+00 i Bone 4.SSE-02 mrem ~ Percent of Tech Spec Limit: 9.77E-01 E Liver S.31E-02 mrem Percent of Tech Spec Limit: 1.66E+00 T7[. Thyroid 4.25E-02 mrem Percent of Tech Spec Limit: 8.50E-01 Kidney 2.83E-02 mrem Percent of Tech Spec, Limit: 5.65E-01 Lung 9.06E-03 mrem Percent of Tech Spe-Limit: 1.81E-01 GI-LLI 3.59E-03 mrem Percent of Tech Spec L i rn i t : 7.1SE-02 i l l ,y Projected cumul at ive dose this QUARTER (includes estimate for this batch): l Mk 6 _11 l c . m.--.... ) j h%._.._, m m..._-

...'_.e' FIGURE 1-2 (CONI) gg Whole body 1.17E-01 mrera 4 t

A/ '. /.15 Bone 9.46E-02 mrera x

+.< < m Liver

1..,1,er. - 01 nir e m 9.,.:.Le.v eiv n$r r

Thyroid S.23E-02 mrem 7dk. s?.Y Kidniy

5. 4 TE-02 rier's m

%.AQ.a.n... Lung 1.75E-02 mrem GI-LLI

6. 95E-03 rarem w

.,.c.ip..',,-

.',Jf,t..N.V--' Cun.u l at i ve rae u ur e d activit. this YEAR (inc1udes estimate for-this batch): ll 4,m.-g, 3.699E-01 Curies, exc luci ng H-3 and di ssolved g ues y$, w,0.f.p; s 3 %*;.%ts j

gg.y------------------------------------------------------------------------------

@$ fit.?#EATCH# 700 DATA SUCCESSFULLY STORED Wry Tu.R .:w* f..f y... n.~ y cm. e.-3PECT90t1 STORED AS: LRut M~q. w,N1'D * ^ 8 . -M. n$..s v.- c e ".. u%. u m. u :..- a-s.,s ~e %. l.et y p; m rr m ~.,.-.....,..,..,......e. .-e ,m e. -m ....e ., m - ~. w _ ~S v. N.*> e. - - m ~v u r-z., ~.. -,.e. r.w:Jy.- =.< L s.,y

f. f-

). >g G.W.;n=.'ln< v r,s,.w*.. c; kW.;3aO.-Pbtw&is.1:eW V^ %.-.. j ind,%.<$.5*** M h W~.+ r26.,,Q N , @Tes?ti ti.^

s. 4

.ny;:.':., r.,s, g,1'3" s;,. n. s.. ,..Gofr./$. 4.fnA*.# z ( 4+** tMv s +=am *= ' <1 4 t'.A. Q.[ 4*.""J '1. e~s %' ~.a L. L.D..f.3.f. ?,$.W.l%. "A.

i

[.. mmh.Yp -r - m* IMDd,"'*,. ll I se

e -

- ' N.'.g.c. f O.55a.i-iv:%.,. - f,

--.g t.4Tf.?...llC 4

:%y'.:;. '

• @:~* f.Q.%i '

I dT 'Ap> - - # "ts: A pNb. =- .xcc. r.y'.,,.

. m.~,,

"%.'r. %. e$~'

l, - :.;.*e.. g.h.n.I e'.)[.ke, N. - - % i c* e Q$.f4 e s - a & .&' 4 N.

• v.C1'U M...

.w.a . o.-O =*p;. Ar g %".T-

-~ =".;.

f.nW ' '. ^g..,, y-W3W"y;

• gg

..',y..yx ;*.r.' -~ .a 9f..,.,... ..-*b./-L h *%. .. n ns.x;* e + .2 5J,>Nlc. hk*.'C_, e e o.-e. U. eg g.. g jj ./ x 1I 12 .e -s .g g ee e G .*e**

• e e.

.e. e, e. .eee.. e ..t .o e e e. e gp e.,eoeeeeeee.Deeeeee e. e

FIGURE 1-3 p - 1 J ) i 1 -..*4**=*.. 4-..************************ i I .I E. I. H atch Huclear Pl ant Liquid Radwaste Analysis - ).'4-Q. ~+s-=~s m **ss*==ss**+ m *********** m ******** .d~6-lf x- .'h*,ctau im, : . y y,....4. d 5. i, h s.- Reactor # 2 Batch # 597 'l-N ALY. O 4 Tank: FDST2 Recirc time: 105 minutes 4'- . ~f.<.r-u,,.ma+.... .a.. w:~ .' Comment: -HIGH..COND TURB FS SILICR Run dste: S/2S/82 0950 Count start date: S/23/82 0800 O sn.p l e vo l uta e : 1000.00 ml Clock time: 3000 secs Ge or..s t ry c oce: 1LHB-0 Live time: 3000 secs . Detector # 3 MCA# 3 L i t.r iry: LRWLB2 Operator: JL '[? -i - E r. i r g.; < k e V ) =.18 + 1.000*Ch# + 0.000E+00*Ch#^2 + 0.000E+00*Ch#^3 : 08/23/82 03t R-Efr = 1/C9.520E-02

• E^(-2.2726E+00) + 264.571
• Ea(9.2937E-01>3 : 08/09/82 Ol' f"'N.T where E = Energy in MeV.

i . - ~. g g ,k,.:.".;... s W 3. 3 - -s I -m.

?

I O s I, l 9 O 4 13 '.w% ..".-L-- ~ 3..

FIGURE 1-3 (Cotfr) m, L/ c hdM. [ Y$f ISOT 2M ENERGY C0tICEllTR AT IO!I ERROR MPC C/MPC ll (lev) (uCi/ml) (uCi/ml) (uCi/ml> %, 4[q% - mzaaza=maaaaaua=maa2aaaas=mz=n=an=2maaumaaaummumumaemunnumaaaumaumaaeeaaaaeaaaem f,.. - y aI *=~ N Ce-144 133.50 <9.507E-08 1E-05 <9.51E-03 $ Tc-99r 140.50 <1.277E-08 3E-03 (4.26E-06 Y 'N *.T Ce-141 145.40 <2.233E-08 9E-05 <2.48E-04 k g)M.2'ICr-51y g tip-239 277.90 <7.623E-08 1E-04 <7.62E-04 I4M 320.10 <1.092E-07 2E-03 (5.46E-05 % M..f,I-131 365.00 1.000E-07 1.370E-08 3E-07 3.33E-01 s vP".~. 2n-69 ta 438.70 (9.841E-09 6E-05 <1.64E-04 pJ'f. ~479.50 - <3.338E-08 6E-05 <5.56E-04 W'*'yg H-187 M'

• F-18 511.05

<2.491E-08 SE-04 <4.98E-05 13133 529.50 -'~(1.126E-08 1E-06 <1.13E-02 Z l.-- - ij$i Ba-140 537.40 <4.813E-08 2E-05 <2.41E-03 . 'g M @h i Cs-134 f' 'p[g. As-76 559.33 6.011E-07 4.867E-08 2E-05 3.01E-02 606.30 1.657E-07 2.099E-08 9E-06 1.84E-02 662.01 8.893E-08 1.965E-08 2E-05 4.45E-03 N3y9.y2~, Cs-137 .y'fdj;t. Mo-99 739.70 (6.953E-08 4E-05 <1.74E-03 Sm SlC%. Zr-97 743.50 <1.123E-08 2E-05 <5.61E-04 MNt D* Zr -9 5 756.90 <2.442E-08 6E-05 (4.07E-04 jd ttb-95 765.80 <1.128E-08 1E-04 <1.13E-04 g)#c,W;i-I-132 772.60 <1.193E-08 8E-06 <1.49E-03 Co-58 810.60 <1.319E-08 9E-05 <1.47E-04 "g [gG ag Nn-54 834.30 <1.348E-08 1E-04 <1.35E-04

1. b NffiAg-110m 884.70

<1.714E-08 3E-05 <5.71E-04 4 "U.M F 2n-65 1115.91 8.590E-08 2.755E-08 1E-04 8.59E-04

\\

l M I-135 1260.50 (4.109E-08 4E-06 <1.03E-02 Y ' Of:[ Fe-59 1291.60 <1.959E-08 6E-05 <3.26E-04 l s 2, Co-60 1332.64 5.911E-08 1.927E-08 3E-05 1.97E-03 'y h, f3[.7 Cu-64 1345.90 <1.255E-06 2E-04 <6.27E-03

-I t.

7'4t.~

tia-24 1368.55 <1.511E-08 3E-05 <5.04E-04 35%r - La-140 1596.60 (7.644E-09 2E-05 <3.82E-04 'hf# Hn-56 1811.00 <2.168E-08 1E-04 <2.17E-04 657.77 3.823E-08 1.439E-08 9E-04 4.25E-05 ll h'D7 tib-97 Y4W Sr-89 (EETA) <3.000E-08 3E'-06 <1.00E-02 I6 -MX.. Sr-90 (EETA) <1.000E-08 3E-07 <3.33E-02 C, H-3 (EETA) 2.160E-03 2.000E-06 3E-03 7.20E-01 hi{j s. Fe-55 (EETA) <2.000E-06 8E-04 <2.50E-03 l [. "" P-32 < EC )

1. 1.000E-07 2E-05

<5.00E-03 }-;71;, - ~ fle as ured t ot al s 2.161E-03 2.001E-06 1.11E+00 gi t.M-4.,.. LLD totals <4.115E-06 <9.90E-02 - :;.f . Totals 2.165E-03 .1.21E+00 me..w.. ,r , -[ O-DISSOLVED GASES ~ ... ~ I Xe-133 81.27 1.365E-06 5.148E-08 '4E-05 3.41E-02 I 5.21E-04 Kr-88 196.10 <2.082E-08 4E-05 Xe .0 % 233.18 <1.187E-07 4E-05 <2.97E-03 Xe-tJ5 250.01 1.005E-06 2.786E-08 4E-05 2.51E-02 Kr-85m 305.00 <5.763E-08 4E-05 <1.44E-03 /] Kr-87 402.70 <1.360E-08 4E-05 <3.40E-04 k/ Xe-138 434.50 <2.767E-09 4E-05 <6.92E-05 ll M=asured g as total 5 2.370E-06 5.853E-OS 5.93E-02 LLD gas totals <2.135E-07 <5.34E-03 ll

2. 5 8 4 E' '0 6' 6.46E-02 Total gas I

14 4 iJ

a g :; >~ .W.'.~"

w : a.. -

'oe C. u. d"g3a U FIGURE l-3 (CONI) ..: W 9... W.k ' 4:..w.. GPOS? ACTIVITY -g%p -. Count e r Groa2

Background

Time vol Het Error ' ~;r - 0 Counts Counts (Min) ml Activity (cpm /ml) 1 Sigma.i d.3 } % y ;_____________ f5He11 Cryst al 1875 791 20.0 2 2.71E+01 1.29E+00 Q T R e.roportional W e~ P 203 211 10.0 2 <3.37E+00 .--s,. 9A'.,ria,.. E S T I M A T E D W A S T E T A M K V O L U M E = 9744.00 gallons , rm r g q* .r g ESTIMATED ACTIVITY THIS BATCH X,' EXCLUDING GASES: 7.97E-02 Curies ( 7.97E+04 M'crocuries) E,i C E._XCLUDIHG H-3 AND GASES: 4.20E-05 Curies ( 4.20E+01 Microcuries) c hh. hh:$~,2 ~$$ n:<w 1 Licuid Raduaste Release Summaro j 'm;;;d%: sen-.~..

-erMTW 1 ) M e as. conc., excluding H-3 and dissolved gases (uCi/ml): 1.14E-06 +- 6.87E-03

?N M:# Ate.ar - Me as. conc., including H-3, excluding gases

2.16E-03 +- 2.00E-06 s_N@'NW ) Cal c ul at ed LLD c onc ent rat i on, g.a*.s.? 2 excluding dissolved gases (uCi/ml): 4.12E-06 m +.: u.

sn,- 3)Calcul ated MPC rat t o (C/MPC of meas., including gases): 1.17E+00 -f n;p '., a. x. - - { M%:. % 4) Minimum dilution flou rate (gpm): 10000 5- $~gn-

5) Maximum tank discharge flou rate (gpm): 59380

1. 3/25.

.E.E.,' 6)Specified tank flou rate (gpm): 75 g h. ".7)Raduaste monitor trip setting: 969 W -M ' A = 3.51E-06,uCi/mi E = 550, Monitor EG CPS .hl['* C = 49670000.00, Monitor CPS per uCi/ml F=2,Conserv. Factor l ~~ "g-i A inclu' des measured ' selected','other' nuclides and gases but excludes: -Q - Sr-39, Sr-90, H-3, Fe-55, P-32

v.. +..e.,,

e S)Est i tuat ed conc. of meas. nuclides at point of release (uCi/ml): 1.609E-05 . W.s . 2..

9) Monitor maximum to ensure 10CFR20 limits are not exceeded: 20039 4

.~ ":. ?_.. v r. ~: ESTIMATED DOSES THIS BATCH, MREM I s c t op.a

u. Body Bone Liver Thyroid Kidney Lung CI-LLI Xe-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C.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 (g)

T c -99 ta 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0'O 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-33 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133m 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hp-23? 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0,.00E400 0.00E+00 0.00E+00 15 J*S ... ~ ...a,'.

Ib6 FIGURE l-3 (GNr) idbS' Ec - 3 S. 3.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C' Cc-!: 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-::: 5.;9E-05 6.34E-08 9.06E-08 2.97E-05 1.56E-07 0.00E+00 2.39E-08 K:-3' O.00E-00 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 0.00E+00

N.::

0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-i P 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 U-117 0.00E-00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F-ti 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00ll I-10:3 9.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 As-76 5.59E-09 0.00E+00 5.87E-09 0.00E+00 1.10E-08 0.00E+00 0.00E+00 Cs-134 4.49E-05 2.31E-05 5.48E-05 0.00E+00 1.78E-05 5.90E-06 9.60E-07 Cs-137 1.42E-05 1.59E-05 2.17E-05 0.00E+00 7.37E-06 2.45E-06 4.21E-07 Mo-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i..- Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00C+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 . e.: Hb-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ihPEb'e-~ 1-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ' CU"""?UECo-58 0.00E+00 0.00E+00 0.'00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ff.d$$CEEEMn-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ag-110m - 0. 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2n -65 6.68E-07 4.64E-07 1.48E-06 0.00E+00 9.89E-07 0.00E+00 9.30E-07;; I-135 0.00E+00 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 0.00E+00 0.00E+00ll 3 Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cc-60 1.83E-07 0.00E+00 8.29E-08 0.00E+00 0.00E+00 0.00E+00 1.56E-06 Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ha-24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-56 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00-Hb-97 ,3.92E-20 4.25E-19 1.07E-19 0.00E+00 1.25E-19 0.00E+00 3.96E-16 Sr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00, Sr-90 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 7.88E-07 0.00E+00 7.88E-07 7.88E-07 7.88E-07 7.88E-07 7.88E-07 (9;'f Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00;j Su* P-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l -~ ________1 Total 6.CGc-05 3.95E-05 7.89E-05 3.05E-05 2.71E-05 9.14E-06 4.68E-06 Cumul at ive dose this YEAR (includes estimate"for this batch): a {j Whole-body 1.42E-01 mrem Percent of Tech Spec.Li.uit: 4.72E+00 Bone 1.13E-01 mrem Percent of Tech Spec Limit: 1.13E+00 Liver 1.96E-01 mrem Percent of Tech Spec Limit: 1.96E+00 Thyroid 4.37E-03 mrem Percent of Tech Spec Limit: 4.37E-02 Kidney 6.71E-02 mrem Percent of Tech Spec Limit: 6.71E-01 Lung 2.10E-02 mrem Percent of Tech Spec Limit: 2.10E-01 CI-LLI 1.12E-02 mrem Percent of Tech Spec L i m i't : 1.12E-01 1i Cu.vu l at i ve dose this QUARTER (includes estimate for this batch): Whole body 4.20E-02 mrem Percent of Tech Spec Limit: 2.80E+00 Eone 3.40E-02 mrem Percent of Tech Spec Limit: 6.80E-01 Liver 5.79E-02 mrem Percent of Tech Spec Limit: 1.16E+00 Thyroid 2.49E-03 mrem Percent of Tech Spec Limit: 4.99E-02 Kidney 1.96E-02 mrem Percent of Tech Spec Limit: 3.92E-01 ~ Lung 6,33E-03 mrem Percent of Tech Spec Limit: 1.27E-01 il GI-LLI 2.20E-03 mrem Percent of Tech Spec Limit: 4.40E-02 8 I Projec ted cumul at ive dose this OUARTER < includes estimate for this batch): Whole body 6.59E-02 mrem Bone 5.33E-02 mrem (,s), Liver 9.08E-02 mrem Thyroid 3.91E-03 mren j j Kidney 3.07E-02 mrem Lung 9.94E-03 mrem GI-LLI 2 3.46E-03 mrem 16 a2

~'5-> FIGURE 1-3 (CONT) .y,.s -', Cu iu s 'i.4 m u red activity this YEAR (includes es t i nat e f or-this batch):

Q;-

1. HI.E-01 C:..c i i 2. excluding H-3 and dissolved g ues er w(e,).%..

M * ,m l;'g d BRICHw 597 DATA SUCCE?SFULLY' STORED ..m,<.. :.e,. - / -..

J. ~ ~ ~.. SPECTRU!1 STOPED A?

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FIGURE 1-4 ELU.E_fL.L._UATC.U DATCH NO. LIGUI_D_R(QMSTC O_1gClynCC PrRMIT UNIT 48 TAN *.( TO CE RELEACCD =__ DATE RCASN FCR isCCCECITY CF DIGCHARGE RECIRC. STNIT tit'E SAMPLE TIME RECIRCIDURATICN MItJUTCS A-" I. UsSCRATCTtY ANALYSIS g (1) MEASURED RADICffdCLIDE CCNCENTRATICN .E + .E uCi/ml (2) CALCULATED LLD LIMIT CCNCCNTRATIONS (3) CALCULATED MPC RATIO: 2 (Ci/MPCi) uCi/ml 8 (4 ) MINI!C1 DILUTION FLOW RATE CPM ^ (5) MAX. CALCULATED TANM DISCHARCE RATE: (EEE SEC. F. 5. J) CPM ~ (G) SPECIFIED tat:( DISCHARCE RATE: 6 (5 )'/E CPM (7) RADWASTE MONITOR TRIP SETTINC: _,._ CPS '4ed.VL '.7W6" A = Ce(LI)(1) uCL/ml B = MONITOR DG CPS ' W.E C = MCNITOR CPS F = CONSERVATIVE j.. PER Ge(Li) uCi/mi FACTOR' MONITGR ALARM SETPOINT (CPS) = (C X A X F) +B+3@ l COB'PCSITE LITER STCRED (INITIALS) LAB FURE*1AN APPROVED (S) RADWASTE MONITOR MAX. CPS TO BE WITHIN 10 CFR 20 LIMITS: CXAX (G)+(4) (G) (3) cps

4. 9, II. OPERATIONS l,jDIS$

I 'h INIT. ~ (9) LIQUID RADWASTE MONITOR TRIP SET AT: CPS I (10) CCNFIRBED DILUTION FLOW RATE CPM j (11) VALVE LINEUP CHECKED AS PER HNP-TAF'.'M DIS. INTEGRATOR DIS. RATE D1L. TOTAL RIVER EL. MCNITt: f DATE* TIME LEVEL -% RONC. CPM CAL FT. CPG 3 TART TNO 1 l COMPLETED BY DATC l MIN. CAL. l DURATICN TOTAL SHIFT FOREMAN API'ROVCD t RELEASE l'

• O 10 MIN AFTER START

. ** AFTER FLUSHINC III.LACORATCRY t (12) TOTAL TANI( VOLUME DISCHARCED (CAL. X 3,705) ml (13) TOTAL ACTIVITY DICCitARCED ((1) X (12)] _ uCi (14) RIVER FLOW RATE (FROM FSAR 2.4-G) CFS COMPLETED OY DATC g I

e. -

a.a ... 18 ~

FIGURE 1-Sa y z--- L iqui d R aduast e Dat a Compil at i on for Reg. Guide 1.21 Report E. I. Hat ch Huc l e ar Pl ant UNIT 1 Total Activity (Curies) l Quarter 3, 1982 Quart er 4,

1982, Batches 578 thru 846 Bat'che4 847 thru 1083 P*77 H am e Measured Error High LLD2 Total Me as ured Error High'LLDs Total I r.

Ce-1-4 5.93E-04 6.15E-05 1.36E-05 6.06E-34 1.78E-04 7.08E-05 0.00E+00 1'.78E-04 Tc-99m 2.22E-04 4.50E-06 2.22E-04 1.24E-03 1.02E-05 4 1.24E-03

• f Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.47E-06 1.08E-06 0.00E+00 3.47E-06 Hp-209 3.92E-04 1.98E-05 3.92E-04 0.00E+00 0.00E+00 4

6.00E+00 I h_ E Cr-51 9.38E-04 3.33E-05 9.38E-04 7.94E-03 9.56E-05 ' 4 7; 94E-03 jrf;;r,;.L-131 2.00E-02 3.70E-05 0.00E+00 2.00E-02 3.20E-02 5.40E-05 Oe00E+00 3.20E-02 pj77;;;J:Zn-69m 0.00E+00 0.00E+00 0.00E+00 1.04E-05 1.84E-06 '4 s'_1.04E-05 i t-'NV-* ru-187 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4 'O,00E+005 i t J18~ 6.57E-04 1.06E-05 6.67E-04 1.96E-04 5.86E-06 4 J'96E-04 2h22E-0 33 4.10E-03 1.99E-05 4.10E-03 2.22E-03 1.47E-05 4

0. ODE +d i

.Ba-1c0 7.57E-06 1.95E-06 7.57E-06 0.00E+00 0.00E+00 '4 t s 65-76 1.38E-04 7.84E-06 1.88E-04 1.84E-04 9.39E-06 4 '1.M 4 E-0 4 ~\\ C2-134 1.24E-02 3.20E-05 0.00E+00 1.24E-02 2.27E-02 5.10E-05 0.00E+00,2.2FE-02' _(~ Cz-107 2.05E-02 4.18E-05 0.00E+00 2.05E-02 3.15E-02 6.32E-95 0.00E+00'3.'2;E-02 flo -99 1.26E-04 2.59E-05 0.00Ev00 1.26E-04 4.71E-04 4.90E-05 0.00E+,00:4.7tE-04; [ "" Zr-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4 0.00E+00 N 7-2r-95 6.73E-05 1.50E-06 6.73E-05 2.91E-04 1.532-05 4 2'. 91 E-O++ ' "^' T ' Hb-95 2.49E-05 2.09E-06 2.49E-05 8.89E-04 1.39E,-05 ,+ 8.89E-DA'% -2 S 1-132 1.09E-04 6.10E-07 1.09E-04 0.00E+00 0.00E+00 4 (0.00E+00' s ,EL' Co-59 4.12E-05 3.12E-06 0.00E+00 4.12E-05 5.16E-04 1.4fE-05 Os00E+00 5.16E-04 { (l.. G tin-5; 3.67E-04 8.33E-06 0.00E+00 3.67E-04 2.46E-03'2.17E-05 0.00E+00 2.46E-03 fs-Ag-110m 1.94E-05 2.64E-06 1.94E-05 5.12E-05 4.57E'-06 4 5.12E-0 ;,' r ""F" - - 2n-65 7.94E-03 5.12E-05 0.00E+00 7.84E-03 2.72E-02 9.38E-05 0.00E+00 2.72E-0 ' I'~" 1-135 1.13E-04 7.90E-06 1.13E-04 2.50E-05'3.52E-06 4 2.50E-0 re-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.01E-04 1.74E-05 0.00E+00 6.01E-04 Co-60 4.27E-03 2.59E-05 0.00E+00 4.27E-03 1.33E-02 (4.67E-05 0.00E+00 i 33E-02 f Cc-6c 3.19E-03 4.11E-04 3.19E-03 3.09E-03 4.'11E-04 4 3.09E-03 Hs-2c 2.09E-03 1.49E-05 2.09E-03 3.36E-04 6.55E-06 9 3.'36E-04 La-1c0 1.50E-04 5.33E-06 1.50E-04 4.74E-04.1.12E-05 4 4.,74 E-04 i ; '._ ttn-56 0.00E+00 0.00E+00 0.00E+00 0.00E+00,0.00E+00 0.00E+00 4 1 ~.' Cs-106 4.64E-02 1.52E-02 4.64E-02 1.29E-04 3.46E-06 4 1.29E-04 Cs-106 2.95E-04 7.06E-06 2.95E-04 7.67E-02 2.23E-02 4 7.67E-02 3 Rb-68 1.97E-05 1.58E-06 1.97E-05 9.61E-05 3.97E-06 4 9.61E-05 'c-104 2.29E-06 1.25E-06 + 2.29E-06 0.00E+00 0.00E+00 4 0.00E+00 J Sb-115 1.76E-05 2.19E-06 1.76E-05 3.65E-04 1.14E-05 4 3.65E-04 Ag-111 7.44E-05 2.08E-05 7.44E-05 7.99E-04 4.89E-05 4 7.99E-04 Te-131 1.29E-04 1.50E-05 1.29E-04 0.00E+00 0.00E+00 4 'O.00E+06 s La-1c3 7.85E-06 1.28E-06 7.85E-06 0.00E+00 0.00E+00 4 0.00E+00 134 2.86E-05 3.45E-06 2.86E-05 0.00E+00 0.00E+00 4 0.00E+00 Te-e 1016 6.44E-05 6.57E-06 6.44E-05 0.00E+00 0.00E+00 4 0.00E+b0 Ti~105 8.73E-08 6.53E-09 8.73E-08 0.00E+00 0.00E+00 4 0.00E+00 Te-132 4.18E-06 6.12E-07 4.18E-06 0.00E+00 0.00E+00 4 0.00E+06 Sr-91 4.77E-07 1.45E-06 4.77E-07 0.00E+00 0.00E+00 4 , 0. 00 E +l06

-134 2.36E-08 8.86E-08 2.86E-08 0.00E+00 0.00E+00 4

0.00E+00 Or-92 0.00E+00 0.00E+00 O.00E+00 2.97E-06 8.12E-07 4 2.97E-06 PA-151 0.00E+00 0.00E+00 0.00E+00 3.29E-05 5.77E-06 3.29E-0T 1 Us-109 0.~00E+00 0.00E+00 0.00E+00 1.47E-04 2.83E-05 4 4.47E-04 As-7: 0.00E+00 0.00E+00 0.00E+00 3.90E-06 9.06E-07 /- 0.00E+00 4.10E-06 9.'03E-07 i.O.90E-06 j'] 1 Hb-97 0.00E+00 0.00E+00 4.10E-06 s N-Ga-151 0.00E+00 0.00E+00 0.00E+00 5.94E-06 9.82E-07 4 5.94E '06 Sb-124 0.00E+00 0.00E+00 0.00E+00 7.14E-05 4.35E-06 4 7.14E-05' Gr-29 3.74E-03 0.00E+00 0.00E+00 3.74E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 g Sr-90 3.71E-04 0.00E+00 0.00E,+00 3.71E-04 0.00E+00 0.00Z+00 0.00E+00 0.00E400 .Fe-55 0.00E+00 0.00E+00 1.29E-02 1.29E-02 1.05E-02 4.90E263 0.00E+00 1.85E-02 4J m. -->--a

r. FIGURE 14'Sa (CONT). t c T-02

.00E+00 0.00E+00 0.00E+00 d.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

' : ai t' 1.30E-01'1.52E-02 1. 29 E--02 1.43E-01 2.37E-01 2.28E-02 0.00E+00 2.37E-01 s 3 g it - 1 ? ! 3.08E-02 1.77E-04 0.00E+00 3.0SE-02 2.8SE-02 6.09E-05 0.00E+00 2.88E-02 w/, t.' - i i 2.55E-05 3.10E-06 0.00E+00 2.55E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ' F.e - 1 ? % i4.34E-04 2.67E-05 0.00E+00 4.84E-04 4.24E-04 3.04E-05 0.00E+00 4.24E-d4 .. M 't - r.. .1.37E-02 2.85E-05 0.00E+00 1.87E-02 6.29E-03 1.73E-05 0.00E+00 6.29E-03 5 kr'-3 S 2.12E-05 6.00E-06 0.00E+00 4.12E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 'M r 47 - 2.362-05 1.97E-06.0.00E+00 2.36E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 f -' - X+-12T 1.00E-06 1.59E-07 0.00E+00 1.00E-06 0.00E+00 0.'00E+00 0.00E+00 0.00E+00

['

M-155t! 6.50E-07 1.92E-07 0.00E+00 6.50E-07 0.0CE+00 0.00E+00 0.00E+00 0.00E+00 L -131n 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.20E-03 1.11E-04 0.00E+00 3.20E-03 'r (:;-. s ~ "ot al s 5.31E-02 1.82E-04 0.00E+00 5.01E-02 3.87E-02 1.32E-04 0.00E+00 3.37E-02 v i.'.:. H~sm.. w;g e -? r .?- O'T4%* Ho.LLD requirement in Tech Spec F l W ;'- e ). h . \\- - 3. < L N .b.9;) i f t t + v.,

• . *.e..

s Y h x / 4..

x.

i '( \\, I Ig\\ j \\-, af.,( N ) 1 6" h I s r) L, j g s k i h I. 'y i, [h 3 \\., f 4 t, 20 l %. ? T 4J 3 .s. % . ~., -._. _- -

s + .,r 3 FIGURE l-5b' ,f ,s p .r if Liquid Psdweste Dat a Compil at ion fof Reg., Guide 21 R.rport E. I. Hatch ucles" P'Isnt UNIT 2 ...rg

• .Y e

s E Tot al Actlf ty (Curies) '? i I s f Ouarter 3, 1982 7 Quarter 4, 1982 Tj Bktches 434 thru (59 s E st c he.s 640, thru 851 4,- ~, (ij? Huw Messured Error High uLDs Tot al MeEsured Error Hiah LLDs. Tot al. it.. Cd-164 1.61E-05 1.89E-05 0.00E+00j1.61E-05 1.42E-04 5.15E-05 ?(00E+00 1. 42E-34 !]7J "c-99ta 1.21E-04 2.50E-06 1.21E-04 1.43E-03 9.48E-06 1.t3E-D3 4

^,-1; "

C4-!c1 0.00E+00 0.00E+00 0.00E+00 0.00E+00ji.74E-06 5.21E-06 0.00E+00 1.34E-06 2.;;, Hr:-20 9 3.78E-05 6.04E-Os 3.78E-05 0.0,0E+00 0.00E+00 4 0.00E+00 .ct Cc-51 1.30E-03 4.44E-05 1.80E-03 4.97E-03 8.23E-05 4 4.97Ec93 {3((5((Cl,:.-131 8.01E-04 8.37E-06 0.00E+00 8.01E-04 1.98E-02.3 50E-05 0.00E+00 1.98E-02 a v??* 2n-69ta 1.75E-05 1.61E-06 1.75E-05 4.66E-06 7.79E-07 '4 4.66E-06 l' H W N -187 * ~3.31E-06 0.00E+00 3.31E-06 6 00E+00 9. 00E+00 4 0.00E+00. H 1 -- FTT5 - 4.34E-04 7.42E-06 ~

• 4.34E-04~1.11E-03 9.06E-06 4

1.11E :-1?? 2.16E-04 4.25E-06 2.16E-04 1.67E-03 1.04E-05 ~ 1.67E-0), 7 4 .ht-l'O 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.'00E+00 4 0.00E+0 f. As 76 3.21E-03 2.06E-05 3.21E-03 1.87E-03 2.05E-05 4 1.87E-03 I" 7 ' ~ " Cs-104 5.43E-03 2.29E-05 0.00E+00 5.48E-03 3.63E-03 2.19E-05 0.00E+00 3.63E-03 Cs-137 9.06E-03 3.06E-05 0.00E+00 9.06E-03 6.06E-03 2.84E-05 0.00E+00 6.06E-03 ' re. Ho-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.12E-04 3.49E-05 0.00E+00 6.12E-04 !^ 2r-97 0.00E+00 0.00E+00 0.00E+00 6.05E-06 4.38E-07 4 6.05E-06 ! ~~ '. Cr-?S 1.64E-05 2.17E-06 1.64E-05 3.97E-04 1.02E-05, 4 3.97E-04 ~ ~7 '~ Hb-95 ?.23E-05 3.55E-06 7.23E-05 4.74E-04 8.15E-06 4 4.74E-04 '7

-132 1.79E-05 3.89E-06 1.79E-05 4.76E-06 6.85E-07 4,

4.76E-06 3 '? Co-59 1.56E-04 4.49E-06 0.00E+00 1.56E-04 8.66E-05 4.86E-06 0.00E+00.8.66E-05 1/~'t Hn 8.27E-05 4.57E-06 0.00E+00 8.27E-05 1.24E-04 5.99E-06'O.00Et0.0.1.24E-04 fyf" Ag-110m 5.52E-05 4.78E-06 5.52E-05 2.92E-04 8.35E-06, .6 2.92E-0j

Jrc On-65 4.03E-03 3.70E-05 0.00E+00 4.03E-03 4.59E-03 4.09E-05.0.00E+00 4.59E-03

, k:

-135 3.28E-05 5.94E-06 3.28E-05 3.86E-06 1.10E-06 4

3.86E-06 ~ Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.34E-05 2.79E-06 0.0.0E+00 1.34E-05 Co-60 1.48E-03 1.72E-05 0.00E+00 1.48E-03 2.26E-03 2.15E-05 0.00E+00 2.26E-0$ Cu-6e 5.35E-03 3.82E-04 5.35E-03 2.29E-02 7.97E-04 4 2.29E-02 H a-24 1.26E-03 1.10E-05 1.26E-03 1.0AE-03 8.85E-06 4 1.00E-03 r-1.&-1c0 1.05E-05 1.28E-06 1.05E-05 3.99E-05 2.83E-06 4 3.99E-05 i -jf-Un-56 8.34E-06 1.29E-06 8.34E-06 0.00E+00 0.00E+00 4 0.00E+00 1E HD-97 7.94E-05 1.96E-06 7.94E-05 1.29E-04 3.51E-06 4 1.29R-04 Cs-133 7.14E-05 6.52E-06 7.14E-05 1.04E-04 2.62E-06 4 1.04E-04 Rb-88 8.31E-06 8.22E-07 8.31E-06 8.04E-05 3.29E-06 4 8.04E-05 v - 131 ra 3.08E-06 8.21E-07 3.0SE-06 0.00E+00 0.00E+00 4 0.00E+00 e 1 Sb-118m 7.24E-06 9.77E-07 7.24E-06 0.00E+00 0.00E+00 4 0.00E+00 Br-82 1.79E-05 1.09E-06 1.79E-05 0.00E+00 0.00E+00 4 0.03E+00 - U-42 7.58E-05 6.67E-06 7.58E-05 0.00E+00 0.00E+00 4 0.00Ev06 .. Co-57 9.49E-06 5.90E-07 9.49E-06 0.00E+00 0.00E+00 4 0.00E+00 Ce-139 9.51E-06 6.92E-07 9.51E-06 0.00E+00 0.00E+00 4 0.00E+00 -Cr-88 1.38E-0G 9.99E-07 1.38E-05 0.00E+00 0.00E+00 4 0.00E+00 ~c' '105 2.47E-15 3.35E-16 2.47E-15 0.00E+00 0.00E+00 4 0.00E+00 Y-91M 3.27E-06 7.59E-07 3.27E-06 0.00E+00 0.00E+00 4 0.00E+00 Cs-106 7.13E-06 1.55E-06 7.13E-06 7.30E-04 1.01E-05 4 7.30E-04 1: a-1 ' 1 1.03E-06 3.17E-07 1.03E-06 0.00E+00 0.00E+00 4 0.00E+00 Oc-92 0.00E+00 0.00E+00 O.00E+00 2.20E-06 5.24C-07 + 2.20E-06 Lu-174m 0.00E+00 0.00E+00 0.00E+00 1.22E-04 1.46E-05 4

1. 2 2 E-04' Gd-151 0.'00E+00 0.00E+00 0.00E+00 5.16E-06 1.55E-06 4

5.16E-06 Sr-89 5.14E-04 2.36E-04 0.00E+00 5.14E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 / Sr-PO 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 7.80E-03 7.80E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+0g l i P-32 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

• ct al s 3.46E-02 4.56E-04 7.80R-03

.24E-02 7.47E-02 8.08E-04 0.00E+00 7.47E-0 1 21 i A J -- S E. . mw . _.. =

FIGURE 1-5b (CONT) C~.

a - t '.c 1.20E-03 1.35E-05 0.00E+00 1.20E-03 1.53E-02 4.74E-05 0.00E+00 1.55E-02 r.r -1.:

0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.25E-06 1.39E-06 0.00E+00 8.25E-06 % -: :O

• 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.52E-04 1.47E-05 0.00E+00 1.52E-04 N.'

1.2SE-03 7.91E-06 0.00E+00 1.2SE-03 2.32E-03 1.24E-05 0.00E+00 2.82E-03 -A tr-it-0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 , _ D 5:r -i r 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I': - : H 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i 4 "otala 2.49E-03 1.56E-05 0.00E+00 2.49E-03 1.84E-02 5.12E-05 0.00E+00 1.84E-02 4 y. 3

i -.g. -

y.y. e *

• Ho LLD requireu nt in Tech Spec Y,

$ st*tA e. ,y,- g s:.. ev.m. ~. . ~..... Jade 4 'f ~ nj. e e49@- f.* e. 9 w i. \\p'. 3 2;.** L...~ +

• :.g. }::;.:..+

.a. .n.v e ...g y i & I

,, p

-

..~. .9 I s .e 4 m w, I O-t l 5 22 ~~,.rff; 42 cm* .c-. " ' " ' ' ~ * * ' m, . ~ __. _ -. _. - -_.~._..:.... - _ _. _. -.. _ - - -.,,. -. ' - ' - -

TABLE 1-la Q E. I. Hatch Huclear Plant UNIT 1 p) EFFLUEHT AtID WASTE DISPOSAL SEMI AHilUAL REPORT 1982 LIQUID EFFLUEllTS-SUMMATIOH OF ALL RELEASES . f.R. 7 hs.s ; i Unit Quarter Quarter E2t Tota 1 3 4 Error % ) %.. v.. u.

• Y,7.". ~

A. Fi ss ion f act ivat ion produc *,s ,2,

2. n:,.

_1. Tot al release (not including H3,

3.,

53 . i f u.: 1,lil case s, al pha) C1 1.30E-01 2.37E-01 5.35E+01 N "?T 2. Average diluted concentration INN"5" during period uC i na l 6.85E-08 1.44E-07 E= f_ _ 3. Percent of applieable 1imit 4.40E+00 7.19E+00,, 2c.. ,'d.,.., - B. Teitium ',. ~. ~ Y[ ~ 1. Totsi re1 ease Ci 6.52E+01 2.44E+01 3.20E+011 . ep, 2. Average diluted concentration E' during period uCi/ml 3.45E-05 1.4SE-05 ~ ?* 3. Parcent of applicable limit /. 1.15E+00 4.93E-iE w- ^ - - ~ " L C. Iiissolved and entrained gases gu' I' E 1. Total release C1 5.01E-02 3.87E-02 1.00E+02l IA)A.uk f  !' 2. Average diluted concentration during period uC1/ml 2.65E-08 ~2.35E-08 ( D *,'"f..." t 3. Percent of applicable Itmit 6.62E-02 5.87E-02

jr.G. ~ '

~.... D. Gross alpha radioactivity ).... 1. Total release l-Cs l 8.80E-05l 7.77E-04l 1.20E+021 , - : s.&. - j.:r.rr. . n. ,' 5',Z lE. Volume of waste (prior to dilution)l liters l 9.27E+06l 8.88E+06l 1.00E+011 ,U 'I lF. Vo l u riee. o f dilution uater used l liters l 1.88E+091 1.64E+09l 1.60E+02l b. 5 -- e p. .q-g &37* '. 23 a.;lt n w a.: j.....

TABLE l-1b G?. t . 'a .M ..e . [~ E. I. Hatch Huclear Plant UNIT 2 EFFLUENT AHD WASTE DISPOSAL SEMIAHHUAL REPORT 1982 I x-e

f.,,

LIQUID EFFLUENTS-SUMMAT!0tl 0F ALL RELEASES o

. ?4..

8 YW.- Unit Quarter Quarter Est Totall EQ* 3 4 Error % l

3p.

..;& W.. A. Fission C. act ivat ion products - (A$ S .M, ' .W' 1. Tot al release (not including H3, '144.: s. e l gas e s, alpha) Ci 3.46E-02 7.47E-02 4.68E+01 .g re--:-:t 2. Average diluted concentration rI.3%1Y1M ' durino period uCi/ml 1.29E-08 4.76E-08 3.-Percent'of applicable 1imit 1.70E-01 4.39E+00 B.. Tritium i sw'..A.- '. " ~ Tct al release Ci 1.62E+01 1.28E+01 3.20E+01i 7. Average diluted concentration '1.~ du-ino period uCi/ml 6.03E-06 8.16E-06 ';ya - ?. Percent of apr> I t c ab l e limit 2.01E-01 2.72E-01 sc..w C. Dissolved and entrained gases . p:,.y 1 .c.; ; 1. Total release C1 2.49E-03 1.84E-02 1.00E+021 i N;. 2. Average diluted concentratton I 4 ? ,,,,4 5 7 'I durino peciod uCi/m1 9.26E-10 1.17E-08 g .& Crit.I - 3. Percent of applicable limit 2.32E-03 '2.94E-02 ry,*.e ~ ~ ..ew D. Cross alpha radioactivity .+ + 1. Tot al release l Ci l 1.11E-04l 3.34E-05l 1.20E+021 ~L%:. ^ we t,; J' dy.. '. E. \\'olume of waste (prior to dilution)l liters l 5.77E+06l 6.23E+061 1.00E+011

5. \\'ol ume, of di l ut i on wat er used l liters l 2.68E+091 1.56E+09l 1.60E+021 e

b. e I

~ i e e I 24 l u L _",$7 Y,1 .....,,...---_:-.-__~.__.,~-

CA TABLE 1-2a , ~. f(eN E. I. H atch flucl ear Plant UtlI T 1 ) EFFLUEllT AtID WASTE DISPOSAL set 11 AtitlUAL REPORT 1982 l LIQUID EFFLUEllTS 2[ * "' C0tiTIllUOUS MODE EATCH MODE ji iluc l ides Released Unit Quarter Quarter Quarter Quarter p v. 3 4 3 4 Q" Ce-144 Ci 5.93E-04 1.7SE-04 i' T:-99tn C1 2.22E-04 1.24E-03 .4-- Ce-141 Ct 0.00E+00 3.47E-06 i L Hp-239 C1

3. 92E -04 0.00E+00 Cr-51 Ci 9.38E-04 7.94E-03

..-NIMU - I-131 C1

2. 00E -02 3.20E-02 9

l Zn-69m Ci 0.00E*00 1.04E-05 L1 - 1.7 7 Ci 0.00Ew00 0.00E+00 F-18 Ct 6.67E-04 1.96E-04 I-133 Ci 4.10E-03 2.22E-03 ~ "~ Ba-140 Ci

7. 57E -06 0.00E+00 As-76 Ci

1. 88 E--04 1.84E-04 CE-134 C1

1. 24E -02 2.27E-02 Cs-137 Ci

2. 05E -02 3.15E-02

^ ~ MS-99 C1

1. 26E -04 4.71E-04 m,_

' Ze-97 Ci 0.00E400 0.00E+00 Zr-95 Ci 6.73E 05 2.91E-04 i lib-95 Ci 2.49E-05 8.89E-04 .h.:.. '. I-132 C1

1. 09E -04 0.00E+00 M7 '

Mn-54 Ci

3. 67E -04 2.46E-0)

Co-58 C1 4.12E-05 5.16E-04 [y;.', Ao-110ra Ci

1. v4E -05 5.12E-0$

26-65 C1 7.84E-03 2.72E-02 I-135 Ci 1.13E 04 2.50E-05 T-~ Fe-59 Ci 0.00E+00 6.01E-04 Co-60 C1 4.27E-03 1.33E-02 I Cu-64 Ci 3.19E-03 3.09E-03

3. ' #-5 8

lla-24 Ci

2. 09E -03 3.36E-04 La-140 C1

1. 50E -04 4.74E-04

~ Mn-56 Ci 0.00E+00 0.00E+00 E. Cs-133 Ci 4.64E-02 1.29E-04 Cs-136 C1 2.95E-04 7.67E-02 4 i Rb-88 Ci

1. 9?E -05 9.61E-05

~ Tc-104 Ci 2.29E-06 0.00E+00 Sb-125 C1 1.76E-05 3.65E-04 Ag-111 Ci 7.44E-05 7.99E-04 Te-131 Ci 1.29E-04 0.00E+00 ~* Lk-143 Ci 7.85E-06 0.00E+00 I Te-134 C1

2. 86E -05 0.00E+00 i

Te-131m Ci 6.44E-05 0.00E+00 Tc-105 Ci 8.73E-08 0.00E+00 Te-132 Ci 4.18E-06 0.00E+00 Sr-91 C1 4.77E-07 0.00E+00 1-134 Ci 2.86E-08 0.00E+00 'Sr-92 Ci 0.00E+00 2.97E-06 Pa-151 Ci 0.00E+00 3.29E-05 O T~~ Ba-139 Ci 0.00E+00 1.47E-04 b ~- As-71 Ci 0.00E+00 3.90E-06 14o-97 Ci 0.00E+00 4.10E-06 i Gd-151 Ci 0.00E+00 5.94E-06 i Sb-124 Ci 0.00E+00 7.14E-Ot 4,' Se-89 Ci 3.74E 03 0.00E+00 4.:3

TABLE 1-2a (CONT) .c~ Sr-90 Ci

3. 71 E -04 0.00E+00

~ Fi-55 Ci 0.00E*00 1.0$E-02 P-32 Ci 0.00E+00 0.00E+00 .f s 1: ai for period (above) l Ci l l l 1.30E 01l 2.37E-01l e \\v) o Xe-133 Ci

3. 08E -02 2.8SE-021 Kr-68 Ci 2.55E-05 0.00E+00

.s e - 133 ra Ci 4.34E 04 4.24E-04 ..N. ~. Xe-135 Ci

1. 87E -02 6.29E-03

~... K a-8 5 tu Ci 4.12E 05 0.00E+00 s

e,/..

Ke-87 Ci

2. 36E -05 0.00E+00 Xe-133 C1

1. 00E -06 0.00E+00

• -.7 -

X e-135 f1 Ci

6. 50E -07 0.00E+00 Xe-131m Ci 0.00E+00 3.20E-03 g : 1 v:

_e_ _ y. J.aaAmkw4 r..L,w e A+. p u:. s. :.; > p.ewyus;.:, 4. -u=. ee,.w.n_.. w'g _ ? .,g .a' .w. .p.. 9 e MhM* 4. . war.

2.

.),b, S. - I. J:._;. f%,_s I ~ sq e

• a a :a.u:.,.

l ~ $.'E. : 1 .m. _ q., s 3 .V I i. 26 ,_____....~...... ~.. ......._____._________a....__..

TABLE 1-2b A .p E. I. Hitch fluc l ear Pl ant UtlIT 2 EFFLUEllT At:D WASTE DISPOSAL SEMI AtitlUAL REPORT 1982 i LIQUID EFFLUEtiTS CollTIHUOUS MODE BATCH MODE j g g. Huc lides Released Unit Quarter Quarter Qu art err Quarter ~- - 3 4 3 4 ',N ~ Ce-144 Ci

1. 61 E -05 1.42E-04_,

.i'. Tc-99ta C1 1.21E-04 1.43E-03 i (d.~-~%AM Ho-239 Ci 3.78E 05 0.00E+00 Ce-141 Ct 0.00E+00 1.34E-06 '. Q"i.,.?'.UJ Cr-51 C1 1.80E-03 4.97E-03 ? "wa>-. I-131 Ci 8.01E-04 1.98E-02 ~ i Zn-69m C1 1.75E-05 4.66E-06 W-137 C1 3.31E-06 0.00E+00 F-18 C1 4.34E-04 1.11E-03 [ I-133 C1 2.16E-04 1.67E-03 Ba-140 Ci 0.00E600 0.00E+00 Aa-76 Ci 3.21E-03 1.87E-03 Cs-134 Ci 5.48E-03 3.63E-03 Cs-137 Ci 9.06E-03 6.06E-03

• l,, ~

M3-99 Ci 0.00E+00 6.12E-04 ' Z r-97 Ci 0.00E+0C 6.05E-06 Zr-95 Ci 1.64E-05 3.97E-04 l,,,. Hb-95 Ci

7. 23E -05 4.74E-04 I-132 Ci 1.79E 05 4.76E-06 j^)f.,;;.-.'.

k. I C3-59 C1 1.56E-04 8.66E-05 C'.'l Mn-54 Ci

8. 27E -05 1.2eE-04 1-..-

t Ag-110m Ci

5. 52E -05 2.92E-04 26-65 C1 4.03E-03 4.59E-03 I-135 Ci 3.28E-05 3.86E-06 Fe-59 Ci 0.00E+00 1.34E-05 Co-60 Ci 1.48E-03 2.26E-03 Cu-64 Ci

5. 35E -03 2.29E-02 S 1Y.

ifh-24 C1 1.26E-03 1.00E-03 i I~ - La-140 Ci 1.05E-05 3.99E-05 T Mn-56 Ci 8.34E-06 0.00E+00 i N5-97 Ci 7.94E-05 1.29E-04 i Cs-138 Ci 7.14E-05 1.04E-04 'j Ro-88 Ci 8.31E-06 8.04E-05 + j_ Te-131m C1

3. 08E -06 0.00E+00

.i SD-118m Ci 7.24E-06 0.00E+00 s Br-82 Ci - 1.79E-05 0.00E+00 1 l K-42 Ci 7.58E-05 0.00E+00 j ' Ce-139 Ci 9.51E-06 0.00E+00 Co-57 Ci 9.49E-06 0.00E+00 J Zr-88 Ci 1.38E-05 0.00E+00 T -105 Ci

2. 4 7E -15 O.00E+00 Y-91M Ci

3. 27E -06 0.00E+00 Cs-136 Ci 7.13E-06 7.30E-04 1

Bi-141 C1 1.03E-06 0.00E+00 'Sr-92 Ci 0.00E+00 2.20E-06 Lu-174m Ci 0.00E+00 1.22E-04 p Gd-151 Ci Oc00E600 5.16E-06 V 50-89 Ci 5.14E-04 0.00E+0Q Sr-90 Ci 0.00E400 0.00E+00 } Fe-55 Ci 0.00E+00 0.00E+00 P-32 Ci 0.00E+00 0.00E+0d

i.

• JO ~~~ L.O' 27 4

~.. TABLE 1-2b (CONT) T o t 4.1 for oertod ( abovo') 1 Ci l l l 3.46E-071 7.47E-02l p. 3 Xe-133 Ci 1.20E 03 1.55E-02 s tr-se Ct 0.00E+00 8.25E-06

• " '~'

x, - 1 3 3 r,i Ct 0.00E+00 1.52E-04 N

[d

~ ' ~ ~ ~ ' ~ Xe-135 Ct 1.28E 03 2.82E-03 ~~ ~~ g,- -8 51,. Ci 0.00E+00 0.00E+00 4 ij ~~ he-97 Ct 0.00E*00 0.00E+0d ~ Xe-138 C1 0.00E+00 0.00E+00 .! y;;y - f -.~. a n' :.. 5 ,e g - . u;.a..- 't. e '.'..;S..:.,. i 3&w~+ p t. g m e r:. 1 v,4,. ~.., ~... w..w.t-i

i. _. - - _- -

1 0 .w.~..,4-s.,, [ W *>. < a .i, .L 3 4 -e / .J :c.. t. e 3, $.*&., c,a. r-. \\ 4. r q.'...w .g. e s ,3. h j ' e s 3 l .t ~% r <7-t l. I ^ m. nm.. e

• @=ep-

2 GASEOUS EFFLUENTS 2.1. REGULATORY LIMITS a. (1) The release rate limit of noble gases from the site shall be: ,I Qis [ 1. 9 56+ 1. 0 E l I1 l B l + Oiv [ 11 E 6 + 44 EB 1+ n Total release rate from main stack for both Units where Q = 3 j in Ci/sec (elevated release) m Total release rate from vent in Ci/sec (ground release) Qy = i= The individual nuclide n = total nuclides i E6 = The average gamma energy per disintegration EB= The average beta energy per disintegration ~ (2) The release rate limit of all radioiodines and radioactive materials in particulate form with half lives greater than eight days, relea'ed from the site to the environs as part of the gaseor; wastes, shall be. 1.0 X 105 6 Ops + 1.5 x 10 gpy $1 Where Ops = Total release rate from the main stack for both Units in C1/sec (as elevated release) O t Total release rate from vents for both Units I Oy = p in Ci/sec (ground releases) b. (1) The average release rate of noble gases from the site I during any calendar quarter shall be: ~ 1 i1 l l +Ov [66 E O + 140 EB I Q s. [ 12 E 6 + 3. 0 EB i i ~ i+ n i (2) The average release rate of noble gases during any 12 consecutive months shall be: E + 270 E 1 il i B l+Ov [130 IQ s [24 E6 + 6.1 E 6 B i i+n i (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 Opv i 1 1 Ops + 1.9 X 10 (4) The average release rate of all radio iodines and radioactive materials in particulate form from the site O i l 29 d

with half livas greater than eight days during any period of 12 consecutive months shall b2: 2.6 X 106 Qps + 3.7 x 107 Qpv,1 1 (5) O 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 consec"'ive 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 report these actions to the Commission within 30 r

days from the end of the quarter during which the releases occurred in accordance with section 5.7.2. ~. (1) If the average release rate of noble gases during any calendar quarter is: IQ s [ 47 E 6 + 12 EB] + Q v [ 260 E 6 + 540 E i i B l> 1 i+ n (2) If the average release rate from the site of all radio j iodines and radioactive materials in particulate form with half lives greater than eight days during any calendar quarter is: 5.0 X 106 Ops + 7.2 X 107 Qpv > 1 (3) If the amount of Iodine 131 released during any calendar quarter 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 tho waste gas discharge ~ valve prio'r to exceeding the limits specified in Section 2.1.3a above. The operability of the auto;aatic 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 hours. f. If the release rate of noble gases measured at the pretreatment monitor exceeds 260,000 uci/sec for a period l greater than 48 hours, notify the Commission in writing within 10 days, identifying the causes of activity and in accordance with section 5.7.2. 9 The reactor containment for each Unit shall be purged through the standby gas treatment system for that Unit. 1 l 30 ~ 2 a. x. m. -.-r . -, _. -. - _ - -,.,, _.. - _,, - - - _. - - -.. -,. - -. ~

h. (1) Potentially explosive gas mixtures of hydrogen end oxygen contained in the offgas system downstream of the recombiners shall be continuously monitored during reactor power operation for hydrogen concentration. The hydrogen gas monitoring system shall provide alarms (~ locally and in the control room at a set point of 4% 5 hydrogen concentration by volume. At least one continuous gas monitoring system and its associated l alarm system shall be operable during reactor power operation. If both of the hydrogen gas monitors or both of the associated alarm systems are inoperable, reactor operation may be continued for a period of time not to exceed '2 weeks, provided that either (a) grab samples are taken and analyzed for hydrogen concentration once every 4

hours, or (b) using a

temporary hydrogen gas analyzer installed in the offgas system line downstream of the recombiner, hydrogen ,n-concentration readings are taken and logged every 4 hours. (2) The hydrogen concentration in the offgas system l downstream of the recombiners shall not exceed 4% concentration by volume. If at any time during reactor power operation, it is determined that the hydrogen concentration limit is being exceeded, action shall be initiated within 4 hours to return the hydrogen concentration to within the prescribed limit. If the hydrogen concentration is not reduced to less than 4% by volume within 24 hours, the (Efgas system flow shall be stopped. O (3) The installed hydrogen monitoring systems shall have daily sensor

checks, monthly functional

checks, and I

v quarterly calibrations. The portable hydrogen gas analyzer shall be calibrated immediately prior to installation and shall be subject to daily sensor i

checks, monthl y functional

checks, and quarterly calibrations until removed from service.

I 1. An* unplanned or uncontrolled of fsite release of radioactive 6 materials in gaseous effluents in excess of 150 Ci. of noble gas or 0.02 Ci. of radioiodines in gaseous form shall be reported to the NRC within 30 days in accordance with section 5.7.2. 2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY I 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 4 period (Procedures are such that shorter collection times are used where applicable to Technical Specification requirements). i i O i l 4 .~ ..,. _. - _ _ _ _ _ _ _. _ -.. ~. -~

Each of these continuous samplers has a flow controller which maintains sample flow within about a 10 percent range over each seven day collection period. The offgas vent (elevated release) and the eactor building vents have flow measurement devices which tcontinously record the flow rate of the gas released (accurary of these devicec are within 10% of the actual flows as measured during preoperational testing). The recombiner building vent flow on Unit One is conservatively assumed to be constant at 500 CFM. In addition to the gaseous, particulate, and iodine release measurements tritium, gross alpha and gaseous isotopic measurements of each vent stream are conducted on a monthly schedule. After ecch calendar quarter (13 weeks) a summary of waste gas release f om the four vents is compiled and as such is designed to meet the requirements for preparation of the 6-month report as specified in Regulatory Guide 1.21. Unit one and two releases were calculated together because the Tech. Specifications for the two reactors are identical in this respect. The methods for compilation of the quarterly releases are as follows: 1. FISSION AND ACTIVATION GAS The total curie release is determined from the continuously reading gaseous monitors in addition to the vent flow recorders. Activity monitors and vent flow rate readings are read hourly and input into the computer. From these readings a daily release is calculated. The calibration factors for the monitors are determined from the monthly isotopics when sufficient activity allows or by injection of O a kn wn amo nt of off-gas into the sample chambers. The total curie release is calculated by the computer for each of the individual nuclides released. This nunber is multiplied by the average energy per disintegration (E & 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 3 divides the sum of the nuclides by the seconds in the quarter to determine the percent of the tech. spec. limit released. 2. RADIOIODINE RELEASES Iodine releases are determined weekly for I-131, I-133, and I-135, for each vent. Where significant activity is not measured MDA releases are calculated. Since calculated MDA's are below Technical Specification detectable concentrations then 0 (zero) release is used for the weeks with only MDA values. Weekly releases are summarized with i the aid of the counting room calculator - computer ' system and a quarterly total is prepared from the weekly ) summaries. The percent' Technical Specification for I-131 on Table 2-1 is based on the quarterly Technical Specification limit. ? 32 ..l a .c

3. PARTICULATE RELEASES . Particulate releases' are determined weekly for each vent. D 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. heekly releases are summarized with the aid of the counting room calculator - computer. After each calendar month the particulate filters from each vent are combined, fused, and strontium separation is made. Since sample flows and vent flows are almost constant over each monthly period the filters from each vent can be disselved together. Decay corrections are made back to the middle of the quarterly collection period. Again the computer is used to aid in the counting room calculator calculation of the Sr-89, 90 release. Where significant strontium activity is not detected MDAs are calculated. The percent of Technical Specification was calculated using quarterly average equation. 4. GROSS ALPHA RELEASE The grose alpha release is computed each month by counting the parti.culate filters each week for gross alpha activity ) in a proportional counter. The four or five weeks numbers are then recorded on a data sheet and the activity is summed -at the end of the month. l 5. TRITIUM RELEASE l Tritium samples are obtained monthly from each vent by l passing the sample stream from a cold trap immersed in a liquid nitrogen or an acetone and ice mixture. The grams of j water vapor / cubic foot gas is measured upstream of the cold trap in order to alleviate the diffic'ulties in determining wa' ar vapor collection efficiencies. The tritium samples I ara analyzed by an independent laboratory. From the uCi/ml tritium concentration, the grams water /ft3, and the vent flow rates, the monthly tritium release is calculated for each vent, and the quarterly summary can be generated from the monthly calculation forms. 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 release, total particulates with half-lives greater than 8-day release, and total tritium release. e -0. tl h ~ 33 c.

"The total or maximum error associated with the offlusnt measurement will include the cumulative errors resulting from the total operation of s.ampling and measurement. Because it may be very dif ficult to assign error terms for - O eeca veremeter ettecetas ene einet meesureme#e, aete11ed 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 count ' ng 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 83.39% of this release was from the main stack the MDA release values of the ground level release points were small to the total release. Monitor Error in Calibration 50% Vent Flow Rate 10% Non-Steady Release Rate 20% 80% 2. I-131 Release was calculated from each weekly sample: Statistical error 60% Counting Equipment Calibration 10% Vent Flow Rates 10% ,O vene Semg1e F10w Reees 10% Non-Steady Release Rates 10% Losses From Charcoal Cartridge 10% IID% 3. Particulates with half-lives greater _ than-8 days release was dominated by the MDA calculations for I-131 and Ba-La-140 hence the errors in the strontium determinations and gross alpha had negligible affects on the estimated error in the total particulate release: St'atistical Error at MDA concentration 60% Countng Equipment Calibration 10% i Vent Flow Rates 10% Vent Sample Flow Rates 10% Non-Steady Release Rates 10% 100% u ._o ?- 34 un.

4. Total Tritium Relense was. dominated by the reactor buildiny vent tritium release, hence, the larger statistical errors of the off-gas vent and recombiner building vent tritium releases do not affect the error in the total tritium release: Water Vapor in Sample Stream Determination 20% g Vent Flow Rates 10% Counting Calibration and Statistics 10% Non-Steady Release 50% i 90% 5 2.3. GASEOUS EFFLUENT RELEASE DATA } Regulatory Guide 1.21 Tables lA, 1B, and 1C are found in this j report as Tables 2-la-c, 2-2a-c, and 2-3a-c. Data is presented on a quarterly basis as per Regulatory Guide l.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 o. all radioactive solid waste shipped offsite. b. Solid wastes in storage and preparatory to shipment shall be monitored and packaged to assure compliance with the -O ee911 cad 1e voretone of 10 C,R rare 20, 10 c,R rare 71, and i 49 CFR, arts 171-178. I c. Reports of the radioactive solid waste shipments, volumes, principal radionuclides, and total curie quantity shall be submitted in accordance with subsection 5.6.1 of the HNP-ETS. 3.2 SOLID WASTE DATA g Regulatory guide 1.21 Table 3 is found in this report as Table 3-la, b. i l O i I

?

35 id .-a, ., 4 ,c ,.. - - - - - - - - - - -, = -., - - - - - -

TABLE 2-la' C-UNIT 1.: EFFLU;tlT AtlD 1ASTE DISPOSAL SENIAHilVAL REPORT 1982 ) GASEQUS EFFLUEllTS-SUtir1ATI0tl 0F ALL RELEASES n Unit Quarter Quartite Est T o t a l'1 E. 1. H st c h fluc l e ar Powe r Pl ant UllIT 1 3 4 Error % 6,., F.- fl. Fission t. ac t i vat i on gases p e. e. ' _. Tot al release Ci 3.21E+03 1.36E+02 8.00E+01l 1. .3-- j 2. Ann rag e re l e ase rat e f or period uCi/sec 4.08E+02 1.71E+01

• ;-{.

3. . of Technical specification limit 4.41E-01 4.94E-02 t. h..',,..' .11 . Mab. 10 dines

%ws.a -...

I h$~.,N ~ t 1. Total iodine-131 C1 4.99E-02 2.04E-02 1.10E+02l i- -2.-Average release rate for period uCt/sec 6.35E-03

2. 56E -03 3.

.of T ec hni c al s nec i f i c at i on limit 2.49E+00 1.02E+00 -/. ~C. F u t i c ul at es .. z. 1. ParticJ11tes with half-lives >8 davs Ci 6.27E-031 9.53E-04n 1.00E+02l n 'IT ~ ~E Ave rage rel ease rate for period uCi/sec 7.98E-04 1.20E-04 JE.- 3. 1 o t' T ec hni c al spec i fi c at t on limit 1.26E+00 2.23E-01 ve. 4. Gross al pha r.adi o ac t i vi t v Ci 6.42E-05 4.42E-05 '. ~, D. Tr i t ium 1. Total release Ci 6.35E+01 7.11E+00 9.00E+011 ,g;db U 2. Average release rate for period uCi/sec 8.07E400

8. 95 E--01

,b.g, 3. % of Technical specification 1imit 6.51E+01 6.63E+00 ], a- ,. m...

• i' l

l O k j.k,*X:.; - ..a r-t l e l f I O 4 l t + 3._..-,.. '~ 36

J. '

D x.: ..a.. _;...,_..-..=.- .=

g TABLE 2-lb + UNIT 2 + -J EFFLUElli AtID MASTE DISPOSAL SEMI AtHlUAL REPORT 1932 GASEOUS EFFLUENTS-SUMMATIOli 0F ALL RELEASES s

a..

Unit Quart, er Quarter Est Total '. ~ 'E.

1. H at.: h Huclear Power Plant UNIT 2 3

4 Error 4* 5 Ft. Fission t acttvation gases v 4. f;d 1. Tot al re1 ease Ci 7.48E+01

9. 63E t02 8.00E+011 74.s.

2. Aoerage release rate for period uCt/sec 9.52E+00 1.21E*02 f,

3. of T ec hni c al spec i fi c at i on Itmit 6.40E-02 9.52E-01 ( 3 :.'. [$6t h P; J.odine$ . m, n s v. -- ~#fQn',%l. 1. Total i odtne-131 C1 1.04E-03 6.44E-02 1.10E+02l

-2.-- Auerage re l ease rate for peri od uCi/sec 1.32E-04 8.10E-03 3.

or Technical specirteatton Iimit 5.19E-02 3.22E*00 O. Particulates

1. P.ar t i c.s i st es with half-lives >8 davs C1 1.61E-04

4. 76E -04 1.00E+02l h_ _ 2. Average release rate for period uCi/sec 2.05E-05

5. 99E -05 l

'I 3. % of Technical specification limit 3.88E-02 7.37E-02 1 Gros 2 a1pha radioactivitv Ci 2.80E-06

4. 97E -06

• • 7.~

[$ D. Tr i t i um l 4 i 1. Total release c# ..i ; 2. C1 1.14E*01 8.98E+00 9.00E+0 d

• p Average release rate for period uCi/sec 1.45E+00 1.13E+00 1

2 u,.

3. % of' Technieal specification 1imit 1.10E+01 9.78E+00

.n:m-6,. L..'. a .\\ f.; * ^. w" s. n.. S.f_ ?- b. \\ l e YP 4 t O g. / 4 w - 37 4' -n ..m , _ - _. _, _. ' - - ~, ~ _ ~ -- -,. - _, ~ - ' _ ' * * '. ~ - - ~ ~ ~. _. _ _ _ _ _. _ - - -,.. - - -.. - -

c,9 TABLE 2-1c. SITE EFFLUEtlT AIID WASTE DISPOSAL SEMIAtitlUAL REPORT 1982 O CASEOUS EFFLUEtiTS-SUllMATI0tl 0F ALL RELEASES A i Unit Quarter Quart tr Est Total 4: 'E. 1. H at c h flur. l e ar Power Plant SITE 3 4 Error % h-fl. Fi ssion t ac t ivation gases y?- I-1. Tot al release Ci-3.29E+03 1.10E+03 8.00E+011 i;.>- 2. Average release rate for period uCt/sec 4.18E+02 1.38E+02 3.

• of Technical specification limtt 5.05E-01 1.00E+00 f '.[O; t c ?'1-

.B. Iodines 1L g g*t.w - 3'i'i't.MSt 1. Total iodine-131 Ci 5.09E-02

8. 47E -02 1.10E+02l i 1

- ' -2. Average release rate for period uCi/sec 6.48E-03

1. 07E -02 3.

• of T te hn t c al specification 1imit 1.27E+00 2.12E+00 C.

Peticulates

71. P art ic ul ates wi th half-Itves>8 davs C1 6.43E-03 1.43E 03 1.00E+02l 2.

Pograce release rate for period uCi/sec S.18E-04

1. 80E -04

~ 3. S. cf T ec hn t c al specification limit 1.30E+00

2. 96E -01

. 4 Gross alpha radioactivito Ci 6.70E-05

4. 92E -05 3

Lt. Tr i t i u't.n j. E1. Total release Ci 7.49E+01 1.61E+01 9.00E+01l d Average release rate for period uCt/sec 9.52E+00 2.02E+00 ._i2. t 3.

• of T e c hni c al specification 11mit 7.61E+01 1.64E+01 l

j..-y. i... ! fRil. y i \\ l me e. l..'a !.:3. l T -s O l r. 38 a3 7 ].

TABLE 2-2a C5e 4 x E. I. Hatch fluclear Pouer Pl ant UllIT 1 f,) l k~# EFFLUEtli AtID tlASTE DISPOSAL SEMIAHilVAL PEPORT 1982 .p. II GASEGUS EFFLUEllTS-ELEVATED RELEASE s i' C0tiTIHUOUS MODE EATCH MODE 4- ' luc la de s Relessed Unit Quarter Quarter Qu art err Quarter .,$,1 3 4 3 4 34 j__ w 4 "i- - 1. F ssion gases t Xe-133 Ci 1.36E+03' 4.54E+00 0.00E+00 0.00E+00 .h,M f Xe-131M C1 1.27E+02 1.95E-01 0.00E+00 0.00E+00 Kr-68 C1 1.94E+02 7.18E-01 0.00E+00 0.00E+00 ,U[;pyJ,y-G' F -

• te -t' Xe-133M Ci 1.18E+00 0.00E+00 0.00E+00 0.00E+00
• Xe-135 Ci 3.46E+01 9.00E-01 0.00E+00 0.00E+00 e r-151 Ci 5.52E+02 5.50E-01 0.00E+00 0.00E+00

~~ [~_ I-131 Ct 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fr-?T Ci 2.37E+01 5.64E-01 0.00E+00 0.00E+00! I ':4 - 13 ? Ci 1.02E+02 1.91E+00 0.00E+00 0.00E+00 Ci 7.64E+01 3.27E-02 0.00E+00 0.00E+00 [,... ((_(( M4-137 Cl 1.20E+02 1.47E+01 0.00E*00 0.00E+00 1 ti-13 Fr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E*00 Me - 13 5i1 C1 1.07E+02 9.40E-01 0.00E+00 0.00E+00 1-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ~ ~ ~ ~ ~ Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 _ _l-135 Ar-41 C1 2.70E+01 5.61E+00 0.00E400 0.00E+00 - a s'.y...'-8 s j'~ ~ l -A-'-- , Tot al fo period Cf 2.73E+03 3.07E+01 0,00E+00 0.00E+00 g a l .h.w._. 4-- 5 2. Iodines [ I-131 C1 3.62E-02 7.29E-03 0.00E+00 0.00E+00 1 I-133 Ci 7.95E-03 1.54E-03 0.00E400 0.00E+00 1-135 C1 1.5SE-03 3.57E-05 0.00E+00 0.00E+00 7-i . r: - ! Tot al for period C1 4.57E-02 8.87E-03 0.00E+00 0.00E+00 ! f.P.' ? 3. Part i c ul at es s' [~ Se-89 Ci 7.82E-04 1.07E-05 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 0.00E+00 0.00E400 0.00E+00 I-131 Ci 5.49E-05 1.96E-06 0.00E400 0.00E+00 Sn-113 Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 s,_* Ea-140 Ci 9.48E-05 2.66E-06 0.00E+00 0.00E+00 C2-134 Ci 3.14E-06 4.96E-07 0.00E+00 0.00E+00 j Cs-137 Ci 7.22E-06 1.10E-06 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 2.32E-07 0.00E*00 0.00E+00 Cr-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 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 _Co-58 Mn-54 Ci 0.00E+00 0.00E+00 0.00E400 0.00E+00 ~N Fe-59 Ci O.00E+00 0.00E+00 0.00E400 0.00E+00 . ' _ _ _ _ Co-60 Ci 5.83E-07 4.85E-OS 0.00E+00 0.00E+00 La-140 Ci 2.04E-04 5.93E-06 0.00E400 0.00E+0.0; ( 1 1_ f ot al for period Ci 1.15E-03 2.31E-05 0.00E+00 0.00E+00 i i a $ 1 a..- 39 ' %.t. ~- - - ~ ~ e = m

CST TABLE 2-2b 4 E. I. H at.ch Huc l ear Pouer Pl ant UNIT 2 EFFLUENT AND HASTE DISPOSAL SEMIAHHURL REPORT 1982 GASEOUS EFFLUENTS-ELEVATED RELEASE j. CONTINUOUS NODE BATCH MODE j eu-

Huclices Released Unit Quarter Quarter Quarttr Quarter i 3 ',.

I 3 4 3 4 l.* 1 j.,,.,. 1. Fission gases

• Q

~ .;Tdf Xe-131M Ct 8.03E-02 1.51E+00 0.00E+00 0.00E+00 Xe-133 Ct 8.636-01 3.53E+01 0.00E+00' O.00E+00 . TAW pige. . $$_f'"7.Ti

• Kr-88 Ci 1.23E-01 5.58E+00 0.00E+00 0.00E+00 Idj.'j;,1;p d Xe-133M Ct 7.49E-04 0.00E+00 0.00E+00 0.00E+00 er? -

L-- -. Xe-135 C1 2.19E-02 6.99E+00 0.00E+00 0.00E+00 F r - 6 5 '1 C1 3.50E-01 4.27E+00 0.00E+00 0.00E+00 I I-131 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ~ t Kr-87 Ci 1.50E-02 4.38E+00 0.00E+00 0.00E+00 .a.. X4-133 Ci 6.44E-02 1.49E+01 0.00E+00 0.00E+00 i Me-137 Ci 4.84E-02 2.54E-01 0.00E+00 0.00E+00 f ti-13 Ci 7.61E-02 1.14E+02 0.00E+00 0.00E+00 Le-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133M Ci 6.79E-02 7.30E+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 l 1-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 C1 1.71E-02 4.35E+01 0.00E+00 0.00E+00 j (_Q..r-( [f.~.e.e i Y ' Tot al for period C1 1.73E+00 2.38E+02 0.00E400 0.00E+00 !N 2. Iodines 2.. ~~ 1-131 C1 2.29E-05 5.67E-02 0.00E+00' O.06E+00 1-133 Ci 5.03E-06 1.20E-02 0.00E+00 0.00E+00 1-135 C1 1.00E-06 2.77E-04 0.00E+00 0.00E+00

g. ; e__;

.n

. Tot al for period Ci 2.89E-05 6.89E-02 0.00E+00 0.00E+00 3. Part..i c ul at es g Sr-89 Ci 4.95E-07 0.33E-05 0.00E+00 0.00E+00 Sr-90 Ct 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 Ci 3.47E-08 1.52E-05 0.00E+00 0.00E+00 Sn-113 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t Ba-140 Ci 6.00E-08 2.07E-05 0.00E+00 0.00E+00 l j Cs-134 Ci 1.99E-09 3.86E-06 0.00E+00 0.00E+00 e i Cs-137 Ci 4.57E-09 8.56E-06 0.00E+00 0.00E+00 l Ce-144 Ci 0.00E+00 1.80E-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 0.00E+00 0.00E+00 0.00E+00 l Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hn-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 s (,) Co-6C Ci 3.69E-10 3.77E-07 0.00E+00 0.00E+00 La-140 Ci 1.29E-07 4.60E-05 0.00E*00 0.00E+00 Tot al for period Ci 7.26E-07 1.80E-04 0.00E+00 0.00E+00 .~ 40 5.-.. 4.2 7 m.m.t:: mu .. r r;-.~

l TABLE 2-2c E. It H a't ch huc l e ar Pouer 'Pl ant SITE

f~\\

(-) EFFLUENT AHD WASTE DISPOSAL SEMIAHHUAL REPORT 1982 GASEQUS EFFLUENTS-ELEVATED RELEASE I f 3 I. '- CONTIHUOUS MODE BATCH MODE i!,, Nuc i nde s Re le ased Unit Quarter Quarter Quart tr Quarter i A.u 3 4 3 4 5$L II f~# 1. Fission gases 3 '. 4 *.d. + 1 ' : v., ' i_ >: e - 13 3 C1 1.36E+03 3.98E+01 0.00E+00 0.00E+00 ,.3. ( ~ fr... Xe-131M Ci 1.27E+02 1.71E+00 0.00E+00 0.00E+00 j 37AEC2232' Kr-88 C1 1.94E+02 6.29E+00 0.00E+00 0.00E+00 j^C[C.l!.l i 1" Xe-133M Ci 1.18E+00 0.00E+00 0.00E+00 0.00E+00 ~**" # ']' Xe-135 Ci 3.46E+01 7.89E+00 0.00E+00 0.00E+00 Mr-85M Ci 5.52E+02 4.82E+00 0.00E+00 0.00E+00 1-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ~ rr-?7 Ci 2.37E+01 4.95E+00 0.00E+00 0.00E+00 'i-13? Ci 1.02E+02 1.6SE+01 0.00E+00 0.00E+00 .;e-137 Ci 7.65E+01 2.87E-01 0.00E+00 0.00E+00 H-13 C1 1.20E+02 1.29E+02 0.00E+00 0.00E+00 Fr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E400 X+-135H C1 1.07E+02 8.24E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-39 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i ~ Ar-41 Ci 2.70E+01 4.92E+01 0.00E+00 0.00E+00 i /~N.. l j(-(( ! Tot al for period C1 2.73E+03 2.69E+02 0.00E+00 0.00E+00; m:~-

b4-2.

Iodines 4 '~ j I-131 Ci 3.62E-02 6.40E-02 0.00E+00

0. 00 E + 0 0-I-133 Ci 7.95E-03 1.35E-02 0.00E+00 0.00E+00 7~

I-135 C1 1.59E-03 3.13E-04 0.00E+00 0.00E+00 .r - f f; I Tot al foF period Ci 4.57E-02 7.78E-02 0.00E+00 0.00E+00 3. Part i c ul at es I Sr-39 Ci 7.83E-04 9.40E-05 0.00E+00 0.00E+00 I~ Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i 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 3 - J 1-131 Ci 5.49E-05 1.72E-05 0.00E-e00 0.00E+00 l [,, Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Ba-140 Ci 9.48E-05 2.33E-05 0.00E+00 0.00E+00 Cs-134 Ci 3.14E-06 4.35E-06 0.00E*00 0.00E+00 i CA-137 Ci 7.22E-06 9.66E-06 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 2.03E-06 0.00E+00 0.00E+00 2r-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 No-95 Ci 0.00E+00 0.00E+00 0.00E 00 0.00E+00 Co-58 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hn-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 5.83E-07 4.25E-07 0.00E+00 0.00E+00 [_ L a-14 0 Ci 2.04E-04 5.20E-05 0.00E 00 0.00E+00; Tot al for period Ci 1.15E-03 2.03E-04 0.00E+00 0.00E+00 N 4.3 ne.... :.; 41

TABLE 2-3a r,, E. I. Hatch Huclear Pouer P1 ant UllIT 1 EFFLUEllT AtID !!ASTE DISPOSAL SEMIRtitlVAL REPORT 1982 GASEOUS EFFLUEllTS-GROUND-LEVEL RELEASE C0tlTItlVOUS MODE BATCH MODE tiuc 1i ce2 ::t l e as ed Unit Quarter Quarter Quart err Quwter I 3 4 3 4 .g..,... 1. Fission gases ,., f., . ly. xM- ~i Xe-133 Ci 8.05E+01' 6.00E+01' O.00E+00 0.00E+00 Xe-131M Ci 0.00E+00 2.65E+01 0.00E+00 0.00E+00 Kr-88 C1 2.03E-01 1.65E+00 0.00E+00 0.00E+00 ww-6. -i ~ Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 [/ __j Xe-135 Ci 1.57E+02 1.47E+01 0.00E+00 0.00E+00 Mr-95M C1 1.64E-01 5.89E-01 0.00E+00 0.00E+00 1-1?1 Ci 0.00E+00 2.99E-03 0.00E+00 0.00E+00 t:r-87 Ci 3.64E-01 1.97E+00 0.00E400 0.00E+00 'e-133 Ci 3.99E-01 0.00E+00 0.00E+00 0.00E+00 Y.4 - 13 7 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M-13 Ci 3.98E-02 0.00E+00 0.00E+00 0.00E+00 6r-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ye-135M C1 2.45E+02 0.00E+00 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 J 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 O.00E+00 0.00E+00 0.00E+00 0.00E+00 ' 0;: ~ '.l, Total for period Ci 4.84E+02 1.05E+02 0.00E+00 0.00E+00 .. ~ _ ' w... J-2. Iodines I-131 Ci 1.20E-02 1.28E-02 0.00E400 0.00E+00' I-1?3 Ci 8.18E-03 6.00E-03 0.00E+00 0.00E+00 '8 I-135 C1 2.93E-03 2.11E-03 0.00E+00 0.00E+00 . s., 9 1[ ~ Tot al for" period Ci 2.31E-02l 2.09E-02 0.00E+00 0.00E+00 3. Particulates C1 4.96E-05 5.02E-05 0.00E+00 0.00E+00 Sr-39 t Sr-90 Ci 0.00E+00 0.00E+00 0.00E*00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E400 0.00E+00

• f Cr-51 Ci 2.18E-04 9.58E-05 0.00E+00 0.00E+00 i

1-131 Ci 1.70E-03 2.65E-04 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 C1 1.61E-04 5.27E-05 0.00E+00 0.00E+00 s { Cs-134 Ci 9.74E-04 1.24E-04 0.00E+00 0.00E+00 C5-137 Ci 1.53E-03 1.86E-04 0.00E+00 0.00E+00 Ce-144 Ci 2.73E-08 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ci O.00E+00 0.00E+00 0.00E+00 0.00E+00 i4b-35 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-5S Ci 1.93E-05 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci S.12E-06 6.07E-07 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

r. o - 6 0 Ci 9.98E-05 9.04E-05 0.00E+00 0.00E+00 L a-14 0 Ci 3.65E-04 6.57E-05 0.00E+00 0.00E+00

Tot al for period Ci-5.13E-03 9.30E-04 0.00E+00 0.00E+00

$h 42 ,i. -. ~ ~...... _. _ ,.u..

ETs TABLE 2-3b E. I. Hat ch Huc lear Power Pl ant UllIT 2 -+ EFFLUENT AND HASTE DISPOSAL SEMIAHHUAL REPORT 1982 v] ..[ GASEOUS EFFLUENTS-CROUND-LEVEL RELEASE g i. CONTIHUOUS NODE BATCH MODE , g. Huc i t dts Re l e as e d Unit Quarter Quarter Q u ar t et r Quarter 3 4 3 4 e *-> 1..: j E.w.'.+ 1. Fission gases

. w

.e..., ?" Xe-133 Ci 2.70E+00 6.27E+01 0.00E+00 0.00E+00 Y J.". Xe-131H Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 g . I Vr-SS Ci 0.00E+00 1.67E+01 0.00E+00 0.00E+00 g@* y*@**?lO l f Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2,yI2$7.*;1 j Xe-135 Ci 4.46E+01 1.34E+02 0.00E+00 0.00E+00 w- ! ---- K r - 8 5 ?1 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ~ Fr-67 Ci 5.32E-01 2.67E+01 0.00E+00 0.00E+00 Me-133 Ci 2.48E+00 8.95E+01 0.00E+00

0. 0 0 E + 0 0' Ae-137 Ci 0.00E+00 7.15E-01 0.00E+00 0.00E+00 ti-13 Ci 9.46E+00 2.75E+02 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M C1 1.34E+01 1.17E+02 0.00E+00 0.00E+00 I-133 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 g

I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t Ar-41 Ci 0.00E+00 2.44E+00 0.00E+00 0.00E+00 l Tot al ? J 'J R: for period Ci 7.31E+01 7.25E+02 0.00E+00 0.00E+00 f.k. :.,_.. '.j' "--*e-2. Iodines I j' I-133 Ci 8.18E-04 1.64E-03 0.00E+00 0.00E+00 1-131 Ci 9.66E-04 7.f4E-03 0.00E+00 0.00E+00 I-135 C1 2.47E-04 1.36E-04 0.00E+00 0.00E+00 l Tot al for period Ci 2.03E-03 8.82E-03 0.00E+00 0.00E+00 a.4

• ?l:.

?u e 3. Particulates ~ I Sr-89 Ci 7.65E-05 7.73E-05 0.00E+00 0.00E+00 Sr-90 Ci 7.00E+00 0.00E+00 0.00E+00 0.00E+00 i Ce-141 Ci 3.00E+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-1?' Ci 4.81E-05 6.79E-05 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ' l Ba-140 C1 1.19E-05 3.29E-05 0.00E+00 0.00E+00 ) C2-134 C1 4.96E-07 1.88E-05 0.00E+00 0.00E+00 Cs-137 C1 2.42E-06 2.86E-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 0.00E+00 0.00E+00 0.00E+00 l (( tib-95 Ci 0.00E+00 8.78E-06 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 C1 6.96E-OS 2.16E-07 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 g j Co-60 Ci 2.23E-06 2.06E-05 0.00E+00 0.00E+00 La-140 C1 1.86E-05 4.11E-05 0.00E+00 0.00E+00 i i Total for period C.i 1.60E-04 2.96E-04 0.00E+00 0.00E+00 l 3 2-l 43 ! J1 _________________________g_____________- .~

r.h, f.E TABLE 2-3c f E. It Hat ch Huc lear Pouer Plant SITE EFFLUENT A!!D WASTE DISPOSAL SENI'AHHUAL REPORT 1982 D(_) CASEOUS EFFLUENTS-GROUND-LEVEL RELEASE CONTINUOUS MODE BATCH MODE . Nuc l ides Re l e ased Unit Quarter Quarter Quarttr Quarter 3 4 3 4 ) 1. Fission gases f, arn. e c-133 Ci 8.32E+01 1.23E+02 0.00E+00 0.00E+00 g. Xe-131M C1 0.00E+00 2.65E+01 0.00E+00 0.00E+00 Fr-38 Ci 2.08E-01 1.83E+01 0.00E+00 0.00E+00 ,dh;,_,, 'i m Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 , ww.m.~ t Xe-135 Ci 2.01E+02 1.49E+02 0.00E+00 0.00E+00 .[](( _j{.fi Kr-85M C1 1.64E-01 5.89E-01 0.00E+00 0.00E+00 l I-131 Ci 0.00E+00 2.99E-03 0.00E+00 0.00E+00 Vr-87 Cl 8.95E-01 2.87E+01 0.00E+00 0.00E+00 Xe-133 C1 2.88E+00 8.95E+01 0.00E+00 0.00E+00 A4-137 C1 0.00E+00 7.15E-01 0.00E+00 0.00E+00 H-13 Ci 9.50E+00 2.75E+02 0.00E+00 0.00E+00 Er-35 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M C1 2.59E+02 1.17E+02 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 m 1-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ar-41 Ci 0.00E+00 2.44E+00 0.00E*00 0.00E+00 l Tot al for period Ci 5.57E+02 8.31E+02 0.00E+00 0.00E+00 ?[k <hA.T: 7 2. Iodines '. G.. I ~. 'M ' i I-131 Ci 1.29E-02 2.04E-02 0.00E+00 0.00E+008 I-133 C1 9.00E-03 7.05E-03 0.00E+00 0.00E+00 1_ I-135 Ci 3.17E-03 2.25E-03 0.00E+00 0.00E+00 I Tot al for period Ci

2. 5.1 E-0 2 2.97E-02 0.00E+00 0.00E+00 u:x -

3. Particulates 8 Sr-89 C1 1.26E-04 1.27E-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 l 1 Cr-51 Ci 2.18E-04 9.58E-05 0.00E+00 0.00E+00 l I-131 Ci 1.75E-03 3.33E-04 0.00E+00 0.00E+00 -} Sn-113 Ci 0.00F.+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 Ci 1.73C O4 8.566-05 0.00E+00 0.00E+00 l Cs-134 Ci 9.75E-04 1.43E-04 0.00E+00 0.00E+00 t Cs-137 Ci 1.53E-03 2.14E-04 0.00E+00 0.00E+00 i Ce-144 C1 2.73E-08 0.00E+00 0.00E+00 0.00E+00 t Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ) Hb-95 Ci 0.00E+00 8.78E-06 0.00E400 0.00E+00 Co-58 Ci 1 93E-05 0.00E+00 0.00E+00 0.00E+00 A_ Hn-54 Ci E.19E-06 8.24E-07 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 1.02E-04 1.11E-04 0.00E+00 0.00E+00 La-140 Ci 3.84E-04 1.07E-04 0.00E+00 0.00E+00 {%- N I Tot al for period Ci 5.29E-03 1.23E-03 0.00E+00 0.00E+00 ~ 1 : ..__.___.___.....____.____._________,_________________4_4_____________.___ ___________________ J3h

• net

-j..y { -. __d -

TABLE 1-3a s EFFLUENT AND VIASTE DISPOSAL SE.'.t! ANNUAL REPORT (YEAR) 1982 7/1/82 to 12/31/82 ] SOLID VIASTE AND 1RRADIATED FUEL SHIPT.1ENTS FOR UNIT 1 i A.SCt.!D V,'ASTE SHIPPED OFFSITE FOR BURIAL OR O!SPOSAt.(Notirradiated fuell l

1. Typ of waste

ung, 6*noath E st. To ol Period Error. %

~

a. Spent r: sins rdter stud;:s, enporator

~ m' 1.55 E2 Mttor s. ete. Ci 6.16 E2 1.0 El i

b. Dry compresasic waste, contar:unsted m*

2.40 E2 ,c o f, e q::ip..e te-Cl 6.L3 E0 1.0 El ' ~~ d + r C. Irradisted comp)nents, conuoi re 1.(2 El rods, ete. F.W. SPARGERS C1 4.07 E-2 1.0 E1 ~.

d. O:her (des:nbe) m' l.49 El ABSORBED OIL Ci 4.38 E-2 1.0 El e

2. Estir:=te of maior nuclide composi: ion (by type of w=ste)

ISOTOPE l PERCENT CURIES

a. Zn-65 26.76 164.87 i

[, Cs-137 20.21 124.51 I-131 18.19 112.07 OTHERS 34.84 214.65 ~ b. Zn-65 49.00 3.15 ~d.N Cs-137 23.60 1.52 l V' Cs-134 12.40 0.80 \\ ) OTHERS 15.00 0.97

c. Co-60 36.24 0.015

~~ Zn-65 12.80 0.005 j Zr-95 17.49 0.007 urut.xS 33.47 0.014 ~

d. Cs-137 40.43 0.01R l

~ I ts-134 23.83 0.010 i j* 2n-65 16.31 O.007 r OPHFRg 19.43 0.009 i .a 3. So!Id Y/aste Disposition i Number of Shi::ments Mode of Transportation D::tination I i i 31 CASK Barnwell, S.C. 8 VAN Richland, WA. [ ^ 8. InftADIATED FUEL SHIPMENTS (Disposition) I Number of shfor-ents MoJe of Trsr.:cortation Estfrution l e .\\ I' i 4s l d.' - -. - - -. -. =.

TABLE 1-3b EFFLUENT AND WACTS DISPOSAL SE.'.11 ANNUAL REPORT (YEAR) 1982 7/1/82 to 12/31/82 h SOLID WASTE AND IRRADIATED FUEL SHIPT.1ENTS FOR Ut!!T 2 g A.SOLIO WASTE SHIPPED OFFS!TE FOR BURIAt. OR DIS'POSA1. INot irradiated fuell

1. Type of waste unt Geneath EH.Tomi P cioe Error. s

~ ~

a. Spent t: sins. t'ilter studses, enporator d

1.64 E2 inttor s. c!c. Ci 4.56 E2 1.0 E1 ~'

b. Dry cornpresa:ie waste, centsr:unsted m*

2_ on E2 equip. ete-Ci ' 6.63 E0

1. 0 t: 1

-N

c. Irt:Jisted componen:s. control W

-- E I rods, etc. Cl E E

d. 0:her (desenbe) m' 1.49 El ABSORBED OIL Ci 4.38 E-2 1. 0 E

2. Estim:t of maior nuclide composi: ion (by t)y of waste)

IS0TODE 1 PERCENT CURIES ' ~ a. 2n-65 42.93 195.60 rn-117 16.17 73.67 z_ rn-60 14.37 65.47 mHFRA 26.53 120.88 b. 7n-69 49.00 3.15 _d,$ re-117 23.60 1.52 i /T cs-134 12.40 0.80 I 01HERS 15.00 0.97 l c. i [ { d. Cs-137 40.43 0.018 l 'Cs-134 23.83 0.010 16.31 1 0.007 2n-65 [ mvFR9 19.43 0.009 l 3. Solid Wsste Disposition l Number of Shipments Mode ofTnnsportation D:stination I l 27 CASK Barnwell, S.C. I 3 CASK Richland, M. 8 VAN Richland, E. .. ' EL IRRADIATED FUEL. SHIPMENTS (Disposition) e Number of Shior-ents Mode of Tran:cortation Destfrution ~ t ,i e I 46 ~" n..,. ,}}