ML19312D053: Difference between revisions
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| Line 92: | Line 91: | ||
. BATCH RELEASES . | . BATCH RELEASES . | ||
n~ ; | n~ ; | ||
y | y | ||
- 22 /, '- ;0 ASEOUS ' EFFLUEtlT 14' 14 | - 22 /, '- ;0 ASEOUS ' EFFLUEtlT 14' 14 | ||
| Line 134: | Line 132: | ||
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p.{p't,;. A r +:w - +j; , ;.' | p.{p't,;. A r +:w - +j; , ;.' | ||
n | n 41:a.n :g _ , _ s- _ | ||
41:a.n :g _ , _ s- _ | |||
- _ _ - + - - ..m-.- _ , ,, , . . . . . , _ . . _ , . . . , | - _ _ - + - - ..m-.- _ , ,, , . . . . . , _ . . _ , . . . , | ||
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- 9 e | - 9 e | ||
' '-. / ._ | ' '-. / ._ | ||
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. T w i t h p h a l. f ' ' 1. t v e s g" eater than eight ' . days - d u r.i n g any | . T w i t h p h a l. f ' ' 1. t v e s g" eater than eight ' . days - d u r.i n g any | ||
, j- 1 calendar. quarter shallibe:' , | , j- 1 calendar. quarter shallibe:' , | ||
e 7.-l . t(X : 10 6[oo's +(1. qj x 107 ~ opy\<.1 5 | e 7.-l . t(X : 10 6[oo's +(1. qj x 107 ~ opy\<.1 5 | ||
. pN; ' | . pN; ' | ||
| Line 998: | Line 992: | ||
(3) The installed hvdrogen monitoring systems- shall have- | (3) The installed hvdrogen monitoring systems- shall have- | ||
~ | ~ | ||
d a il,y sensor checks, monthly functional chocks, 'and T quarterly .ca t t b rat ions. The portable hydrogen gas. | d a il,y sensor checks, monthly functional chocks, 'and T quarterly .ca t t b rat ions. The portable hydrogen gas. | ||
analyzer shall be calibrated immediately prior- to installation and shall be subject to daily sensor checks,- monthly functional checks, and . quarterly calibrattons:untti removed from serv.co. | analyzer shall be calibrated immediately prior- to installation and shall be subject to daily sensor checks,- monthly functional checks, and . quarterly calibrattons:untti removed from serv.co. | ||
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: r*N L -f | : r*N L -f | ||
' . ;. 4 | ' . ;. 4 | ||
* q qg6.. (25) I N[$h,e ' ' | * q qg6.. (25) I N[$h,e ' ' | ||
q | q | ||
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(26) | (26) | ||
bL M 0 ,'- ' , | bL M 0 ,'- ' , | ||
= | = | ||
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~ | ~ | ||
~ T.6!:- | ~ T.6!:- | ||
i.7 u ~, . . , | i.7 u ~, . . , | ||
.}} | .}} | ||
Revision as of 19:43, 21 February 2020
| ML19312D053 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/29/1980 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML19312D052 | List: |
| References | |
| PM-80-171, NUDOCS 8003030568 | |
| Download: ML19312D053 (34) | |
Text
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~ Go a a F-OMr C:nLp,1:Fr c rant Ctw.e Hu 4 il l Guojf. etp .t Vi13 i' f6cutu m 912 M 7 7731' 912Q3/ 9444
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<: . Edwin L H: itch Nuciear Plant bCOIhO )WCf
!! v :u294:res o l*v,lt:c !:;Mr str February 29, 1980
4'/
PLANT E. 1. HATCH Semi-Annual Radioactive Effluent Release Report .
Director of Inspection and Enforcement-
% Distribution. Services Branch
- U. S. Nuclear Regulatory Commission Washington, D. C. 20555 l
- Gentlemen
Pursuant to Section 5.7.1.b in Appendix B, Environmental Technical Specifications, of the Plant Edwin I. Hatch Operating Licenses, please find enclosed the Semi-Annual Report for Plant Radioactive Effluent Releases, July 1,1979 through December 31, 1979. -
,/ ~
C 'MT an'ry Plant Manag r
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4 GEORGIA POWER COMPANY
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'l'44 .
PLMIT E. I. HATCil UNITS N0.~1 & 2 SEf11 ANNUAL REPORT
'~
PLANT RADI0 ACTIVE EFFLUENT RELEASES
- JULY.1, 1979 - DECEMBER 31, 1979 l
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PLAN.T.~E. I . ~ H ATCII
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- PLA'lT.RADI0 l ACTIVE EFFLUEtiT RELEASES ytl}ft
?' - LSECTIOff TITLE PAGE
'M 1.= LIQUID EFPLUE!!TS ' 1 -;
- REGULATORY LIMITS 1
, f- ) i.' ic 4 g' 1
, i t'. 2 ' 'HAXIMUM' PERMISSIBLE'CONCEt!TRATIONS a.
w ei ' ,
- 1. 3i 'HEASUREMEllTS AND APPROXIMATIONS OF m- -
.* TOTAL RADI0 ACTIVITY - 4 [
" $d;isi,m ....
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6
. BATCH RELEASES .
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- 22 /, '- ;0 ASEOUS ' EFFLUEtlT 14' 14
' 2 .1'. . R EGUL ATORY LIMITS.
2' 2 . 4 HEASUREMENTS AND APPROXIMATIONS OF ..}
-TOTAL HADI0 ACTIVITY 21
!~ 4: - >
f 7
2.3 -GASEOUS EFFLUEllT RELEASE DATA 29 t
' SOLID WASTE 25.
- T
': x:. .f. : .
y f't .1 ! REG'ULATORY SPECIFICATI0!!S 25
- / -
342
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SOLID WASTE DATA' 29 ,
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PL At!T l E. I. HATCH
. SEMI A!!NU AL REPORT
). PLANT RADIOACTIVE EFFLtlEllT RELEASES
%.J -
FIGURE L,IST OF FIGURES PAGE 1- 1. . METi10DS OF MEETING TABLE II 7 COLUMN'2 MPC LIMITS (10 CFR 20)
- 1-2a, b LIQUID RADNASTE ANALYSIS - UNIT I 8, o 1-3s, b LIQUID RADWASTE ANALYSIS - UNIT II 10, 11 -
1 4' LIQUID RADWASTE DISCHARGE PERMIT 19.
43 . .
1-Sa, b LIQUI'D R ADWASTE D ATA COMPILATION 13, lli TABLE LIST OF TABLES PAGE 1-la, b EFFLU E!!T AtID WASTE DISPOSAL SEMI-
- ANNUAL REPORT, LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 18i, 16 1-Pa, b EFFLUENT AND WASTE DISPOSAL SEMI-A!1NUAL REPORT, LIQUID EFFLUENTS-B ATCl! Oi!LY 17, 18 a =2-1 EFFLUENT AND WASTE DISPOSAL SEMI-(v), ANNUAL REPORT, GASEOUS EFFLUENT- -
SUMMATIO!! 0F ALL RELEASES 26 2-2 EFFLUENT AND WASTE DI9POSAL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-
~
ELEVATED RELEASE 27 _
2-3 ,
. EFFLUENT At!D . WASTE DISPOS AL SEMI-ANNUAL REPORT, GASEOUS EFFLUENTS-
- GROUT!D LEVEL RELEASES 28 3-la, b 2FF LU E!!T AND WASTE DISPOSAL SEMI-A!!NU AL REPORT, SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 20, 10 p .
9qp3
)
ye..._ . _
mm
PLANT. RADIOACTIVE EFFLUENT RELEASES 1- L_IOUID , EFFLUENTS a
)- 1.1. REGULATORY LIMITS l'. The concentration of radioactive mate"ials released in
, liquid vastes from all reactors at the site shall not -
exceed the values soecirted 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 Q.. 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 monito" shall be set to alarm and to initiate -
the automatic closu"e 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 1tne shall be
- demonstrated quarterly. -
6.
n The equipment installed in the liquid radioactive waste V ~
system shall. be maintained and shall be operated to process radioactive liquid wastes prior to their
! discharge. when. the projected cumulative release rate could exceed 1.25 Ci/ceactor/ calendar ' quarter, excluding tritium and dissolved gases.
- 7. The maximum radioactivity to be contained in any liquid radvaste tank that can be discharged directly to , the enviaons shall not exceed 110 C1, excluding tritium and dissolved, gases.
- 3. 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 du"ing Nhich-the release occurred.
4 An unnlanned o". uncontrolled offsite release of a ra d io a c t iv e .. ma t e r i a l. s in . liquid .ef fluents in excess of l< l 0.'5 C1 excluding' dissolved gases shall be reported.
Q c 9m 9g m_m y .
- ..,_.7 * - '
, G-
la ?. M A IIMU'i. P ERMISSIBt,E. CO?!CEt!TR ATIOfiS
~
'The MPC values' used in determining allowable liquid radvaste ael Jase' concentrations are taken from 10 CFR Part 20, Appendix B,.
Table II, Colunn 2. ' Release rate and dilution ratio for each i ): ' batch are: determined by a mixed nuclide MPC calculation performed
-before the release of the batch. To f a c il i. t a t e the measurements z '. and - calcul.ations', . the ' nuclides of Column 2 which can be produced in a fission reactor-hsve been grouped according to MPC value and g tvoe.of radiation as shown in Figure 1-1.
The concentrstion of each of the 24 gamma emitting nuclides a spectrically 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 activitv measurement. For any of the 29 nuclides not detected in the gamma scan, the MDA limit is q,
computed from the measured data for that sample,
/
(Only two pure beta emitters, Sr-89 and Sr-90, have MPC values less than 4 Y 10 -6 uCi/ml. Individual measurements are made
- ' on prooortional comoosite liquid radwaste samples to determine the Sr-80 and 3r-90 concentration er MDA value to be applied to individual batch release calculations. .
Although the '4 P C 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 acceptabl.e tritium measurement. A distillation and liquid scintillation counting technique is used to measure tritium concentration.
A The maximum activity of gamma and beta emitting nuclides with MPC values greater. than 4 X 10 -6 uCi/ml, 7)~ except for the 29 nuclides noted above, is determined by gross gamma and gross beta e measurements. Measurement senst tivity limits of approximately 2-cpm /mi' allow a null measurement to show that the sum,E (Ci/MPC1), is less than 0.1 for gamma and beta nuclides not measured directiv.
The sum of the ratios, I (Ci/MPC1), f or alpha emitters can be shown- to be sless than 0.1 by a null measurement with a sensttivity limit of aporoximately 1 X 10 -2 com/ml. Gas flow counting .is used to achieve the required sensitivity of measurement.
Thus, zexcept for radionuclides produced in negligible quantities
-in. a . fission- reaction (eg. I-125, I-120 etc.), the methods out1.ined a bove. providei a means to assign a quantitatively
. measured or. MDA- value to a l.1 nuclides in Column 2. These
-neasured and - cal.c ula ted concentratton values for each batch are used'to cal.c ulat e ' the - dilu t ion ratio, release rate, and dilution rate ' prior to relcane of-each batch. Both ~ the concentration and- '
release data are stored .on a' computer ' dis c file. The. disc file data 1.3 used to assure ' that quarter 1v and annual relesse limits jare n o t .. e x c e e d e d .' Bases used for the data of Ta ble 1-1 are as-folloss:
~
o s g ygyb ~
(2) et, 4,,
. . A. 7 t sO,on- - and ' ac t i va t i on products -- The total. release tvaluen Inot: .in clu d in g - tritium, . gases, alpha)- are comprised o f.
cthosum of the ' individual-' rad t.onuci tdo activities and include the LLD.. concentration of all isotopes that were not measured
'but. :d td > not i c e t the minimum sensittvity 1.tmit as set forth
'I( .
); .in-the Environmental Tech Specs.~ This sum is for each batch
' released to the r i.v e r for the res oec ti.ve quarter. Percent (
of aop11 cable ilmit is determined from a mixed nucilde MPC he , -
calculation. The average concentration for each ~ nuclide ' !
- summed over .sil batches ~ is divided by the corresponding-(? individual. MFC .valua. The sum over all nuoltdes of the
'E Ci/MPCi' ' ra tios times 100 is the percent of appitcable 1. im i t Q- for effluent releases 'during the quarter.
B.: . T r i t i.um -
The measured t r i t i.um concentration . in . a composite s am p 1. e - is uned to. calcul.a te the total release and average '
] diluted concentration during each period. Average diluted e concentration d iv i,d e d by the MPC limit, 3 X 10 -3 uCi/ml, a[p . .
-is . converted to ' percent . to give the percent of applicable.
J .-
m Aimit.
~C . - Dissolved - and entrained ganes -
Concentrations of dissolved and-ontrained gases in Itquid offluents are measured on each .
J batch by Go(Lt1 spectroscopy on a one liter sample from each liqutd- radwaste batch. Disnolved and entrained gases for
.which measured or MDA concentrations are determined incl.ude noble. gases with half lives greator than 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s: Xe-135, l 1Xe-193m, Xe-133, and Kr-85. - Iodine radionucitdes in any f or m . a'r e also determined during the isotonic analysis for each batch, therefore a separate anal ~vsts for possible n(,/ gaseous forms-'is ~ not performed because it would not provide a dd i ti. onal ; in f o rma t i on .
- 2 A conservative release limit, the maximum sensitivity limit
.o0.4 .X 10-5 uC1/mi or each dissolved and entratned radionuclido1 as-soecified in Regulatory Guide 1.21, has been applied in determining the percent of applicable Itmit.
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kl5 3 iMEASU3 EME!!TS ' AtID TAPPROXIMATIOfiS OF' TOTAL RADI0 ACTIVITY,
[ , Deta d.A of ^ the 'ansivtical procedures for liqut6 radwaste analysis j-:e . .are contained. (n. operating procedure ' .Ht!P-7 601. The following
.1 b messurements.are'oerforned-as indi.cated-
-+ ./
M E A SU .R.E.M
. = _ --- Ef!_T - --FREQUENCY METHOD U % '
7, l '. 1 Gamma Isotooi.c Rach Batch Ge(Li.) spectrometry with
- 11 '- on-line computer.
4':'lp -
6;, T2. Gross. Gamma- Each Batch 2 X 2 NaI well crystal 9.- counting
.' 3 . - Gross' Beta Each Batch Gas flow proportional .
counting 16:
. f.7 Ji . Sr [ Quarterly. Chemical separation and 49 @ +*
Composite gas flow croportional counting *
, .5. Sr 00 Quarterly Chemical separation and y Comoosite gas flow proportional -
counting 6.- Tritium Monthly Distillation and liquid' Composite scintillation counting 2
- 7. '. Alpha Monthly Gas flow proportional d' 'Conposite c ou n t i.n g (s). .
m 8 .- :Di.ssolved Gases: Each Batch Ge(Li) spectrometry with on-line computer g .':1i
.g 1
Q 4
9 A
9
%g
.' % 'y F. . a
. a ., ,
t
, I t_
"t j Ny -f '
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- an'%
6- . g Qy%-' s
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, w: ~~M -;"; ,.,c , - .- - . . . , - . . . - -. + , ,
-I f ; a
- 1. ig ti td radw tate . tank cannot - ho - roorocessed, a samplo for
' ~ an a l.v h t s is taken from the tank i nf ter the required ' roctreulation time. -The sample is used for ganma-ray spectrosconv, gross gamma and. gross beta counting,' and for preparation of a comoosite
- samole.
.j' The ' Ge(Lt)- . detector consist of a 10% and two 15% efficiency, 2.0
-FWHM. resolution detectors. in 4-inch thick lead shields. A one-liter radwante liquid sample is gelled in a Marinelli beaker '
in preparation for.. a 2000-3000 second Ge(Li) count. A peak f^ search ' o f- the ' resulting gamma ray spectrum is performed by the on-line computer 's y s t e m . Energy and not count data for all significant peaks are determined, and quantitative reduction or
- MD A. calculationn are performed for the 'nuclides Itsted in Figure
. s 1-1. 'The- quantitative calculations include corrections for counting ' time, decay time, sample volume, samole geometry, detector e"f ri c i e n c y , baseline counts, and branching ratto. MDA calculations, including the above corrections, are made based on A. 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 s:an and- from previously stored Sr-8o and -Sr oO values are -
4 .~ used to calculate the dilution ration E (Ci/MPC1) and allowable release parameters. A samolo printout is shown in Figures 1-2 and 1 '4 .
The Liquid Radwaste. Discharge Permit Printout is transferred item by iten to the f t"s t . portion of the release permit (Figure 14) bv a laboratory technician. Although the computer could printout Q[ O
]_ the release permit. and will inform the technician if a batch cannot be discharged as desired, a manual transfer-of calculated
'results to the release permit by the technician was implemented
~
'as.more likely to catch abnormal conditions in tne data. ,
The liquid radwaste monitor setting is calculated by the comouter
- based - on .the gross gamma activity as measured in the sample used for laboratory analysis. A coefficient has been determined which relates laboratory gross gamna counts to the monitor count rate.
If ' the monitor count ruto exceeds the u l c u l a ',e d setting during.
s .. d is c h a r ge , then the- liquid passing through the monitor is not representative of the . sample which was analyzed. in the lab. A
, monitor: reading in oxcess of the calculated setpoint therefore
-results i n't an autoeatic ' termination of the liquid effluent
_ diseM ege. Liq uid . 3ffluent discharge is also automatically terminated if ' the dilution flow rate falls below the - flow rate used.in.the computer calculattor..
, , When the' release permit is returned from Radwaste O'erations p
follouing' discharge, .the d i s c h a .'g e data is combined- with the canalyaic--results on the: compute" disc file. Thc-disc file may be
, , (scanned to display -_ trends in. any recorde- parameter, on may be.
s'un led E rorc roportin 3 nurooses ' as '.shown in Figure 1-Sa and b.
~
7, .
, fjiL m -
- M ' '
~ ~
' Alliotherf radionuclide concentration measurements are performed as indicated'in the table given previously in this section and as de-
'J S'-
-(.r) tailed .in the procedure HNP-7601. The dissolved ~ gases calculation is pe'rformed in the Ge(Li) spectrometry system with computer data
~'
-reduction .using .the Liquid Radwaste Liberty which includes gases.
Several commentr ~are indicative of the success of the HNP liquid
.radwaste progran during this reporting period:
- 1. The' total measured activity released in liquid effluent for both . Units was 1.25 E-2 curie for the third quarter and 6.19 E-3
~
curie for the fourth ~ quarter. These values were approximately 1/1552-for Unit.1 and 1/1655 for Unit 2 for the third quarter
,. s" , and 1/2252 for. Unit-l'and-1/5714 for Unit 2.for the fourth f'
. quarter of the allowed 10. curies per quarter per reactor.
2.' 1The radwaste releases procedure emphasized reprocessing rather than discharge'of liquid radwaste. During this report period 41.8% of- the liquid. radwaste reaching the sample tanks was dis-
/ charged; 58.2% 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 891 discharge batches for both Units.
1.4 BATCH RELEASES '
- ,m .
d%,) . -Regulatory Guide 1.21 Tables 2A and 28 are found in this report Las; Table 1-1 and 1-2. Data is presented on a quarterly basis as per. Regulatory Guide 1.21.
Other; data pertinent to batch releases of radioactive effluent froa.
both units.is as.follows:-
4
. Number of batch 1 releases: 891 Total; time period for releases: 114,493 minutes Maximum' time period for a batch release: 240 minutes-
~
Average 'timelperiod for batch release: 129 minutes Minimum tine period for a batch release: 4 minutes Average strearp flow.during period.e .of release of effluent into.a V- iflowing: stream: 5530 CFS
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FIGUR E ' 1-l'
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FIGURE-1-1' METHODS'OF' MEETING TABLE II,' COLUMN 2 MPC LIMITS tr. ) , ,
',A -
MPCLRANGE - G AMMA- R AY.: -
BETA ALPHA (U.Ci/ml) EMITTERS' EMITTERS EMITTERS Y. I-131,I-132, I-l_33 . ' . Sr-89, Sr 40 J (Soparation &
I-1152_Cs-134
. Gas Flow
<4 X 6 - (ge(Lt). Gamma-Ray Counting) l Soectroscon_y) _
___j ,____
ALL
.a (Gas Flow
'"i , Counting, Sensitivity n, o 0.01 CPM /ml)
Ba'La-140, Ne-24,Cu 64 Tritium
- -6 CO-60, _Fe-90 7
-.n-65
._ >4 XL10 Ag.110m, Mn-54, co-58 (Distillation &
Liquid Scintil-
' Zr-Ub 05,'Cs-Ba-137 As-7 C F-18, Cr-Si~ All Others No-220, Ce-1El IIo-_Te 001_ Ce- P r-.14 4 (Ga s Flow Counti.ng
,q. . (Ge(Li) Gamma-Ray Sensitivity ~2 V. Spectroscopy) CPM /ml
.', All others (Gross Gamma-Well
, Counter; Sensitivity
~ 5 CPM /ml) f' .
4 4
4
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J m
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tSk
$mm :
@ig@pe c :, d . .,,.~ ;
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FIGURE l-2a i 1
FR0CEDURE: Mi1P-7 01 REVIS1011: 7 DATA SHEET 8 ,
. _ . ........e.e.................. .................
) . E. I. Hatch Nuclear P? ant *
\_/
- Liquid Raduast e Analys t s e e..e....ee......*se........eee............ ....
t A -
hD k9 Re ac t or t l' Batcht 605
-Tank: FDSTI Rectre time: 80 minutes 9 \)
Comment: HIGH TURE FIL SQL Run date: 11'11/79 0149 Count start dat e: 11/11/79 0035 Sample volume: 1000.00 mi Clock time: 3000 secs i Geometry codel ILHB-0 -Live time: 3000 secs t i- Detectore 1 MCA8 1 I Library: LKWLB2 Operator: WJH .
Energy (kev)= .46 + 1.000*Che + 0.000E+00.Chea2 + 0.000E+00.Cht^3 : 11/11/79 0001 Efr 1/tt.102E-01 + Ea(-2.4635E+00) + 521.333 . Ea(9.6530E-01)3 : 11/09/79 0001 uhere E = Energ's in tieV.
ISOT0FE ElliRGY CottCENTRAT!Ctl ERROR MPC C/MPC
- ' kev)
(uCleml) (uCleml) (uCl/ml) m ..............................................................................
i Ce-144 133.50 <2.5335-07 1E-05 <2.54E-02 e Tc-99m 140.50 <2.967E-04 3E-03 (9.89E-06 Cc-141. 145.40 <5.610E-08 9E-05 . <d.23E-04 Hp-239 277.90 (2.380E-07
[]
s Cr-51 320.10 <3.017E-07 1E-04 2E-03
<2.33E-03 I-131 <1.51E-04 364.50 <3.747E-02 3E-07 <1.25E-01 2n-6?m~ 433.70- <3.123E-08 6E-05 <5.21E-04 H-187 '4T9.50' (1.112E-07 ' 6E-05 (1.85E-03 -
F-1C 513.55 (3.410E-03 5E-04 (6.32E-05
-I-133 529.50 (3.322E-03 1E-06 <3.32E-02 Ba-140 537.40 (1.!??E-07 2E-05 (5.83E-03 -
As-76 559.20 (6.915E-00 2E-05 <3.46E-03 Cs-134 604.70 (4.205E-03 f 9E-06 <4.67E-03 Cs-137 ~661.64 (4.512E-03 2E-05 (2.26E-03 -
a Mo-99 739.70 <2.713E-07 4E-05 <6.7aE-03 ;
HJ 2r-97 743.50 (3.195E-03 2E-05 <1.6CE-03 i 2r-95 756.90 (6.196E-03 CE-05 <1.03E-03 !
Hb-95 765.80 (3.361E-06 1E-04 <3.36E-04 I-132' 772.60; <3.236E-03 SE-06 <4.04E-03 Co-58 C10.60 <4.468E-03 9E-05
.<4.96E-04 Mn-54 834.30 (3.469E-08 1E-04 (3.47E-04 Ag-110m 984.70 (5.256E-0$ 3E-05 <1.75E-03 2n-65 1115.40 <1.01?E-07 1E-04 <1.02E-03 I-135- 1260.50 -(1.032E-07 4E-06 (2.70E-02 Fe 1291.60 (9.135E-03 . CE-05 -(1.52E-03
'Co-60 1332.60 2.437E-07 4.731E-08 3E-05 0.12E-03 Cu-64~ 1345.90 <5.624E-06 2E-04 (2.31E-02 Ha-24 1368.55 (3.907E-08 3E-05 <1.30E-03 Ca-140- 1596.60 <2.070E-08 2E-05 <1.53E-03 Mn-56 1811.00 (6.36?E-03 .
1E-04 (6.37E-04 Sr-69 (BETA) 5.160E-09 2.230E-09 3E-06 t.72E-03 Sr-90 '(BETA) 1.610E-09 7.740E-10 3E 5.37E-03 '
1 ~ Measured totals 2.504E 4,737E-08 1.52E-02 A LLD.tetsls L(8.020E-06 '<2.83E-01 "Q
' Totals'. . 8.273E-06 2.98E-01 m..
[ ,
.(8)
E FIGuilEl-2b p_lS$0LVI'D GA?ES Xe-133 80.99 (8.509E-08 4E-05 <2.13E-03 V Kr-88 196.10 (6.520E-08 4E-05 (1.63E-03 Xe-133m 233.18 (2.364E-07 4E-05 (7.16E-03 Xe-135 249.60 (2.847E-03 4E-05 <7.12E-04 Kr-85m- 305.00 (1.932E-0? _ 4E-05 <4.83E-03 '
Kr-87 402.70 (4.339E-03 4E-05 (1.08E-03 Xe-138 434.50 <1.157E-08 . 4E-05 (2.89E-04
................. ........... ......... ..... .......__ i Measured gas tos als 0.000E+00 0.000E+00 0.00E+00 !
LLD gas tot als (7.133E-07 <1.78E-02 Total gas '7.133E-07 1.78E-02
.%@ Ac
- cM CROSS ACTIVITY Counter . Gross Bad ground Time vol Het . Error Cou.ts Counts (Hin) ml Ac t i u t t y(c pa./ml ) 1 Sigma,
............. ...... ...... ..... .... ......__ __......i Hell Cryst al 15U8 1491 20.0 2 4.25E-01 1.37E+00 Prop or t i on al 160 160 10.0 2 4.00E-01 9.06E-01 ESTI'llAYE0 WASTE TAHK VOLUMES 9291.00 g al l ons ESTinATED ACTIVITY THIS EATCH. 8.81E-06 Curses ( 8.81E+00 Microcuries)
)
QUARTEALY ACTIVITY RELEASED THROUGH THIS ERTCH (Cl)= 1.56E-03 PERCEliT OF TECH SPEC L!rt!T = 1.56E-02 m /~^ 12 N0HTH ACTIVITY EELEASED THROUGH THIS EATCH (Cl)= 3.34E-02
] .
PERCElli OF TECH SPEC LIMIT =.1.92E-01 r.
Liquid Radutste Rele ase Summaru
- 1) Meas. radio-nuclide cone., excluding gases (uC1/ml): 2.50E-07 +- 4.74E-03
- 2) Calculated LLD concentration, excluding dissolved gases (uct/ml): 8.02E-06 3)Calcul at ed NPC rat io (C/NPC of meas., including gases): 1.52E-02
- 4) Minimum dilution flou cate (;pm): 10000
- 5) Maximum. tank discharge flou rate (gpm): 664085 6)Specified tan 6 flow rat e (gpm): 75 7)Raduaste monitor trip setting: 154 A = 2.50E-07 ,Ge(Lt) uCi/mi 8 = 100 ilonitor BG CPS C = 47610000.00 .Nonttoc CPS per uCi/m1 F = 2 ,Conserv. Factor
'Est imat ed conc. of mess. nuclides at point of relesse (uCi/ml): 1.864E-09
- 8) Monitor maxtmuu to ensure 10CFR20 limits are not exceeded: 1732 e
,j ~ BATCHe-605 DATA SUCCESSFULLY. STORED t
. V} SPECTRUn STORED AS: LPil! -. ? 3
[%B E
o t'
,. (9) .
u
[ ;Q. ,M. -
~
s H'
FIGURE.1-3a
- a
,s PROCEDURE: HHP-7601 REVISION: 7 DATA SHEET S i 1-V- ,
E. I. Hatch tiuc le nr P1 ant Liquid Raduaste Analys t a
. b k' u %e g g&
Reactore 2 Entche 805 ,
Tank: WSTA2 Rectre time: 55 minutes Comment: NA!HTA!!! CST LEVEL jJm il' Run dat e: 12'31/79 1701 Count start d at e: 12/31/79 1603
-Sample volure: 1000.00 ml ,. Clock time: 3000 secs
' Geometry code tLHB-0 Live time: 3000 secs
~ 'Detectore 1 MCA# 1 Library: LKHLE2 Operator: REH 4
Energy (kev)= .34 + 1.000.Che + 0. 000E + 00.Che a2 + 0.000E.00.Ch e a3 : 12/31/79 0123 Err = 1/C4.234E-02 . Ea(-2.3605E+00) + 532.792 . Ea<9.5507E-01)) : 12/13/73 0001 where E . Energy in HeV.
ISOT0FE EllERGY CONCEllTFATION ERROR MPC C/NPC (kev) (uCleml) (uCl/ml) (uCleml)
[ Ce-144 133.50 (2.642E-07
"-(k / Tc-99=
Co-141 140.50 145.40
('. 349E-03
<5.049E-08 1E-05 3E-03 (2.64E-02
<t.12E-05 /
9E-05 (6.50E-04 /
Hp-235 277.90 (2.378E-07 IE-04* <2.33E-03 Cr-51 320.10 <3.160E-07 2E-03 <1.58E-04
'!-131 364.50 <3.41at-08 3E-07 <1.14E-0t ,
2r.-69m ' 439'.70 <2.903E-08 -
6E-O'J (4.85E-04 H-187 479.50 (1.155E-07 6E-05 <1.93E-03 F-18 5i0.75 <3.337E-03 SE-04 (6.67E-05:
1-133. 524.50 (0.504E-08 1E-06 <3.50E-02:
- . , .r.
'~
34-140 537.40 <t.310E-07 2E-05 <6.55E-03j As-76 -559.30 -<7.742E-03 2E-0? <3.87E-03i Cs-134 604.70 (3.208E-08 9E-06 Cs-137 <3.65E-03l
~ 661.64- (4.495E-03 , 2E-05 <2.25E-03; Mo-99~ 739.70 <2.473E-07 '4E-05 (6.18E-03
~2r-97 743.50 <3.309E 2E-05 <1.90E-03 2r-95 -756.90- #5.90AE-08 6E-05 (9.83E-04.
Ht>-9 5 765.80 <3.361E-08 1E-04; <3.36E-04'
.!-132 ??2.60 (4.253E-08 8E-06 (5.32E-03 Co-58 810.60 <3.650E-08 .9E-05 (4.06E-04 Mn-54' .834.80 (4.311E-08 1E-04 <4.31E-04 A0-110m 834.70 <3.626E-08 3E-05 <1.2tE-03 2n-65 1115.40 (8.753E-03' 1E-04 ~ <8.75E-04 1-135 1260.50 (9.337E-03 4E-06 <2.33E-02 Fe 11291.60 (6.278E-03 6E-05 (1.05E-03
, Co-60. -1332.07- 1.464E-07 3.656E-08 3E-05 4.83C-03
.Cu-64 1345.90 <5.041E-06 2E-04 <2.92E-02
'Hs 1360.55: <3.133E-08 3E-05 <1.04E-03
.La-140 1596.60 (3.512E-03 2E-05 -<1.76E-03 Mn-56 -1311.00 <7.110E-08 1E-04 <7.11E-04 p_s $r < BETA) ?.910E-09 1.680E 3E-06 2.64 E-0 3
~( )- Sr-90 <SETA) 1.210E-09 4.830E-10 3E-07; 4.03E-03 4
3/ ............. ... ..........- ......... ..... .........-
1 Measured tot al s 1.555E-07 3.660E-08 1.15E-02
- LLD tot als- (8.~202E-06 -(2.72E-01
' Tot al s =
8.357E-06 2.84E-01 l '
I
.'}fg yW y" (10) -
2..
FIGURE l-3b DISSOLVED CASES
- ( ~T Xe-133 81.48 s 2.500E-07 7.227E-08 4E-05 6.25E-03
.() - .Kr-98 196.10 (6.896E-08 4E-05 <1.72E-03 Xe-133m 233.10 (2.800E-07 4E-05 (7.23E-03 Xe-135 250.13 8.153E-07 4.099E-03 4E-05 2.04E-02 Nr-85m 305.00 (1.925E-07 4E-05 Mc-87 ~ (4.81E-03 '
402.70 * (5.219E-03 4E-05 <1.30E-03
- ~ Me-138e 434.50 (3.063E-08 4E-05 (7.66E-04
'f Measured gas totals 1.065E-06 8.308E-08 2.66E-02
. . LLD g as t ot als (6.334E-07 Total gas-
<1.58E-02 1.699E-06 4.25E-02
- Y .
. , 3
- CROSS ACTIVITY Count 2r Gross B ac k ground Time vol Het Error Counts Counts -(Min) ml Activity (cpm /ml) 1 Sigma Well' Crystal 1620 1240 Proportional 20.0 2 9.50E+00 1.34E+00t 193 181 10.0 2 6.00E-01 9.67E-01 ESTittATED HASTE TANK VOLUME = 9215.00 gallona ESTIMATED ACTIVITY THIS BATCH = 5.42E-06 Curtes ( 5.42E+00 Microcuries)
QUARTERLY ACTIVITY RELEASED THROUGH THIS BATCH (Cl>= 1.74E-03 PERCEtiT OF TECH SPEC LIMIT = 1.74E-02 p
- (,,/ 12 MotiTH ACT!YITY RELEASED THROUGH THIS BATCH (Cl>= 1.5SE-02 PERCErli 0F TECH SPEC LIMIT = 7.88E-02 h
/
Liquid Radunst e Pele ase Summ arv #
D 1)Heas, radio-nuclide conc., excluding gases (uCl/ml): 1. E 7 +- 3. 56E-03
- 2) Calculated LLD concentration, excluding dissolved gases (uC1/ml): 8.20E-06 3)Calcul ated MPC ratio (C/t1PC of meas., including. gases): 3.82E-02
- 4) Minimum dilution (Iou rate (gpm): 10000
- 5) Maximum t ank- di schar ge riow rate (gpm): 264535 6)Specified tsnk flou rate (gpm): 90 '-
'7)Raduaste monitor trip setting: 300 A = 1.22E-06 ,Ge(Lt) uCleml B = 125 , Monitor EG CPS C = 57850000.03 ,ttonttor CPS'per uC1/mi- F = 2 ,Conserv. Factor Estimatad conc. or meas. nuclides at point of. release (uCl/ml): 1.337E-09 8)ttonitor maximum t o ensure ' 10CFR20 'l imi t s are not exc e ede'd: 8076 I '
. v!. ~ BATCHa 305' DATA SUCCESSFULLY STORED SPECTRUrt STORED AS: LRW2 A.
NWA y _m.
(11)
[5?l ~
QM-- -
1 ..
/: , ,
h FIGUPS1-4 ' -
, N. '
( ; -- .- DATA 3HEET .8
- % a/ . ,
A i PLA81T E.T. IIATCII . BATCH NO.
LIQUID'R @ I5T5~lif.sdIIIf6E PERMIT- UNIT # _
~
TANK-70 EE RElliASED . ~ DATE REASON'FOR. NECESSITY'5F DISCHAPGE
, 'RECIRC.'ST/RT TIME _ SA!!PLE Tit!E H56 fed! DtisATf65 MINUTES
' I ,. LABORATORY. ANALYSIS (1) MEASURED R ADIONUCLIDE CONCE!!TR ATIO!! . '~~~ ~+ ~
.E uCi/m1' (2) C ALCUL ATED- LLD LIMIT CONCE!!TR ATIONS ~ ~~ ~ ~
uCi/ml (3) cal *CULATCD MR RATIO: I (Ct/MPC1)~
iC W (4) !!IMI!!Ut! DILUTION Flott R ATE CPM M (5) MAX.-CALCULATED TKNK DISCl!ARGE RATE:7jfE SEC. F.4.rI __ GPM (6) SPECIFIED TANK DISCHARGE RATE: < (5)/2 ~ ~
GPM
~
(7) RADWASTE MONITOR TRIP SETTING: ~ CPS A = Go(Li)(1)
~
, C = !!Of.IT0it . CPS . F cot:SER VATIVE PER Ge(Li) uCi/ml FACTOR ~
e 140NITOR ALARM SETPOIllT THE5I (C X A X F) + n + 575-
. COMPLETED BY DATE COMPOSITE LITEli STORED --
(IMITI ALS) 'IFPK5Vsu aY
. ,. ! _ . (G). RADUASTE M0t!ITOR MAX. CPS TO BE WITHIN 10 CFR 20 LIMITS: .
~ fN. CXAX _(6) fu)
V ~ .
(6) (3T ___cos pil II. .OPERATIO!1S 6:
I N I,T .
(0)
LIO.UID RADUASTE MONITOR TRIP SET AT:
CPS ~~
. . - (10) CONFIRf4ED DILUTIO!! FLOW RATE ~
GPM (11)' VALVE LINEUP ' CHECKED AS PER !!NP- - - .
TANK dis. INTEGRATOE DIS. ~EATT I~fIL. TOTIL RI V 5!I~E L . M6iifTO DATE TI !F LEVEL -1 R D!:0. GPM CAL PT. CPS
~
e e f.
3 TART
(.
SND- as m--- --. --..-----. .---- ---.
. COMPLETED BY D'A T E j4 . !!IN . CAL.
! ," . DURATION- TOTAL
-RELEASE -----------------------------
8 e 10 HIN'AFTER START.
L.
>- 8 AFTER FLUSilING
~
III . LA fiOR ATORY - ~
L4 (12) 10*AI.l TA!!E L VOLU!!FbDTSC!!f.RGZD C AL. X ~4,7SS m1 b '
. s (13) TOTAL ACTIVITY DISCHARCSD .(1) - X (12) ~~~~ ~~~~~~~~~-~~ uCi
_ (14) hIVER FLOW R ATE -(Fn0:ll FSAR 2.4-6) ~'~ ~~ ~ ~[ -- ,---- CPS i._ g ,
Qt;-+I- ..:]
COMPLETED BY DATM F: .r-
, ,% APPROVED.8Y Q .
- c. .... -
f ,,,sp ka,~? . -
___. ------~~~~~----..
}:?*Qf s w ' - : .
- (12).
n -m Lx s - ~ .:. -
~
7 , -= ' _-
n , ~
4 ;
v n
- -FIGURE.1-Sa-iqold'R4d d sc5Dsta Codpilatfor.'Yor Reg. Guide 1.21 Report !
ms q j +
Q LE. I. Hatch Huclear Pl ant UNIT 1 m _ kb Sg -
<3 Tot al1 Act ivi t y (Curies) -
3 s* J0uarter 5,1979 Quart er 4, 1979
,'g, .s -s
~
E st -he s - 260 theu ~ 4?1.
Batches 482 thru 744 7:e v 3 6 ,1 .Heasurci Error High LLDs T o t. a 1 Heasured Error High LLLs Tots!
M4. ice-144' l.13E-05 6.37E-06 0.00E+00 1.13E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00.
"U
[O Tc-996 'n.00E+00 0.00E+00 0.00E+00 0.00E+00 5.56E-06 1.11E-06 0.00E+00 5.562-06' ice-141! 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Q f p Hp-239, l'.2SE-05 0.00E+00 0.00E+00 1.2SE-05-1.93E-05 7.59E-06 0.00E+00 1.95E-05 (pc.u 7 . Cc-51 -5.53E-05.1.34E-05 0.00E+00 5.5GE-05 2.99E-04 2. 54E-05 0. 00E+00 2. 9 ?E-04'
- U[ Il-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.73E-04 5.44E-06 0.00E+00 1.73E-04 ,
10 7 <
2n-69m" 40.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 11-187 O.00E+00 0.00E+00 0.00E+00 0.00E+00 9.21E-06 4.43E-06'O.00E+00 9.21E-06
- Fk19. ' 1.72E-04:4.92E-0[0.00E+00.1.72E-04 1.06E-04 3.76E-06 0.00E+0C 1.06E-04 "I-133' '4.61E-06 1.21E-06 0.00E+00 4.61E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00
,- Ba-146 2.59E-06 1.35E-06 0.03E+00 2.59E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I* '
[AS-76; '4.50E-06 1.56E-06 0.00E+00 4.50E-06 2.01E-05 5.16E-06 0.00E+00 2.01E-05 i- '
C s'- 134 : 8.56E-04 9.54E-06 0.00E+00 6.56E-04 3.42E-04 7.24E-06 0.00E+00 3.42E-04
-Cs-137 1.30E-03~1.27E-05 0.00E+00 1.30E-03 5.75E-04 1.02E-05 0.00E+00 5.75E-04
- Ho-99 1.57E-05.5.15E-06 0.00E+00 1.57E-05 3.27E-05 1.16E-05 0.00E+00 3.27E-05
', Jr-97' O.00E+00.0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 c :2r-95 2.90E-06 2.00E-06 0.00E+00 2.80E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5m .
.2.10E-05 2.19E-06 0.00E+00 2.10E-05 2.47E-06 7.53E-07 0.00E+00 2.47E-06
'A'-f!-132[^ . Hb-95
. ~ :Co 1 0.00E+00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 0.00E+00'O.00E+00 0.00E+00
- 4. 35E-05 ' 3. 90E-06 0. 00E +00 6. 35E-05 5. 53E-05 3. 91 E-06 0. 00E+00 5. 5 ?E-05 4 s Mn 54- f1J34E-04 S.??E-06 0.00E+00-1.34E-04 4.06E-05 3.48E-06 0.00E+00 4.06E-05 L' -
jag-110ra' 0.00E+00-0.00E+00 0.00E+00 0'.00E+00'5.65E-06 1.49E-06 0.00E+00 5.65E-06
<2n-65, 1.59E-03:2.85E-05 0.00E+00 1.59E-03 S.81E-04 2.42E-05 0.00E+00 8.01E-04 4
~
I-135- 0.00E+00'O.00E+00 0.00E+00 0.00E+00-8.82E-06 2.93E-06 0.00E+00.8.82E-06 lFe-59
- 3. 4 6E-06 3'. 57E- 07 0. 00E+00 3. 46E-06 3. 27E-06 1.17E-06 0.00E+00 3.27E-06 1 ~
Co'-60 : 1.60E-03 1.87E-05-0.00E+00 1.60E-03 1.64E-03 2.25E-05 0.00E+00 1.64E-03; i Cu-64f ;0.00E+00'O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00,
.LHa-24 -5s72E-0419.'27E-06 0.00E+00 5.72E-04 2.04E-04 5.02E-06 0.00E+00 2.04E-041 JLa-140f 0.00E+00 0.'00E+00'O.00E+00 0.00E+00 6.55E-06 1.52E-06 0.00E+00 6.55E-063 g CE'
' i ffn-56 CS-136,
.0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.80E-06.9.03E-07 0.00E+00 2.80E-06 1.92E-06'5.36E-07-0.00E+00 1.92E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 THb 4JS4E-06E1.09E-Of 0.'00E+00 4.84E-06 1.04E-06 3.21E-07 0.00E+00 1.04E-06 chip 65; L1'.05E-05 3.13E-06'O.00E+00 1.05E-05 1.29E-06 4.94E-07 0.00E+00-1.2?E-06
_ ,;;$r-89; 1 0.00E+00 0.00E+00,0.00E+00 0.'00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 JSr 10.00E+00 0.00E+00-0.00E+00 0.00E+00.0.00E+00 0.00E+00 0.00E+00.0.00E+00 ,. 's . . . . . . . .. LTotals' 6.44E-03: 4.29E-05 0.00E+00 6.44E-03'4.44E-03 4.74E-05-0.00E+00-4.44E-03 2Ne' > [b ' + c.ac QF "(Kr-00Xe-133; [1174E-04 3.36E-06 0.00E+00 1'.74E-04;7.'18E-04 1.55E-05 0.00E*00.7.132-04* M '
- 0.00E+00f0'.00E+0010.00E+00'0.00E+0011.05E-05 1.91E-06 0.00E+00.1.05E-05 Xe-103k -0.00E+00~0'.00E+00'O.00E+00=0.00E+00ll.07E-05.5.21E-06 0.00E+00-1.37E-05 Xe-135' 16. 20E-0416 ~.' 41 E-0 6 0. 00E + 00 J '6.20E-04:1.70E-03't.16E-05 0.00E+00 1.70E A ' [ (Nd35r.C [0'.00E+ 00) 0. 00E+00 30. 00E+00. 0. 00E+0011. 86E-05 ;5. 54E-06 0.' 00E+00 1. 36E-05.
R e - s MH 871 l0;00E+00iO.00E+0010.00E+00:0.00E+00 2.77E-06 1.04E-06 0,00E+00 2.77E-OS 9 ek13S
'N]g N p E0J00E+00k0.00E+00=0.00E+00:0.00E+00 0.57E-06 3.20E-07.0.'00E400 2.5'E-06 9
, Q~C l STcf ab > i.94E-04 41. -NE-05[diO0d 0'O M ?4E-04 2. f 46E-03 : 2.10E-05 0. 00E+00 7.WE -0 3 g 3
.a.
.@ w. .,
~
W*A ~~uW PA 4 +a < (13)' o
/hst - ;E 9"o "
w -
-1 h i
4 . , ._ 4 . _. _ . _ _
-g . . ,
- f. ;i; .
my <? o % FIGUREl-5bl 0
' .% - 0 hMuuu ueu E '% Mtdbd%pe .ht a Couril 1 at i on ' f or F:r g. ~ Gui de 1.21-Report '
<' u. _ ,
'^
? q .
E. I. . H st ch fluc l e ar P1 ant Ull!T 2
- k
[. 9 ' Tot al Activity (Curtes)
-Quarter 3, 1979 -Quarter 4, 1979
- 9. -
Batch d '400 t hru 630 Batches 631 thru 805
. liase - Hruured -Errcr .High LLDs Totat Hersured Error High L1.D4 Total L 'Ce-144 0,00E+00'O.00E+00 0,00E+00 0,00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
., tTc-99u 3.07E-0E 7.13E-07 0.00E+00-3.07E-06 1.94E-06 8.40E-07 0.00E+00 1.94E-06) t
,ss. JCe-141 .0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.45E-06 1.26E-06 0.00E+00 2445E-06! -
g(,W:Qttp-239
-Cr-512 0. 00C + 00 0. 00E4 00 0. 00E 600 0. 00E+ 00 2. 75E-05 1. 87E-06 0. 00E+00 2. 75E-05!
-I-131 14.53E-04 2.41E-05 0.00E+00 4.83E-04 4.41E-05 9.00E+00 0.00E+00 4.41E-05 1'.21E-06 4.59E-07'O.00E+00 1.21E-06 2.77E-06 5.?TE-07 0.00E+00 2.77E-06 LO
'_ 12n-69s- 4.92E-06-7.13C-07.0.00E+00.4. 92E-06 3.99E-06 7.54E-07 0.00E+00 2.99E-06
.11- 16: 7 ~
"E-18 6.22E-06 1.82E-06 0 00E+00
~
s 6.22E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.79E-04: 3.4SE-06 1.97E-04 3.67E-04 1. 43E-04 2.79E-06 1.02E-04 2.44E-04
-I-133
+
Ba-140 -0.00E+00 1.?0E-06-5.96E-0? 0.00E+00 1.90E-06 8.93E-06 1.16E-06 0.00E+00 8.93E-06 As-76 0.00E+00'O.00E+00: 0.00Ev00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.06E-04'5.37E-06
!Cr-134 '5.93E-06 1.38E-06 0.00E+00 0.00E+00 1.06E-04 3.06E-05-3.55E-06 0.00E+00 3.06E-05 C1-137' 2.47E-05 2. 3?E-06 0; 00E+00 2. 5.93E-06 3.9?E-05 1.91E-06 0.0GE+00 3.99E-05 47E-05 6. 38E-05 2. 80E-06 0. 00E+00 6. 38E -05 Ho-991 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 f f2r-9Z_ i 0.'00E400 0.00E+00 0.00E+00 0.00E+00 1.13E-06 3.76E-07 0.00E+00 1.13E-06
,_ ' 2r -95. - 14,07E-06 1.41E-06 0.00E+00 4.07E-06 3.36E-06 2.45E-06 0.00E+00 3.36E-06
' 6/~N:llb-95 2.05E-06'4.20E-07 0.00E+00 2.05E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ' ' A t 'I-1321 Co-58'
-6,37E-07 2.57E-07 0.00E+00 6.37E-07 3.62E-06 9.84E-07 0.00E+00 3.62E-06
' ' 1.06E-04 -1.21E-06 0.00E+00 1.06E-04 6.96E-05 ?.30E-06 0.00E+00 6.96E-05
' fin-54 L 1.49E-05 1.95E-06 0.00E+00 1.49E-05 7.36E-06 1.40E-06 0.00Ev00 7.30E-06 1Ag-110m 22n-65' 0.00E+00.0.00E+00 0.00E+00 0.00E+00 2.0SE-06 9.05E-07 0.00E+00 2.0&E-06 '
.I-135-2.13E-04 1.11E-05 0.00E+00 2.13E-04 1.62E-04 9.41E-06 0.00E+00 1.62E-04
-Fe 'O.00E<00 0.~00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00.O.00E+00 0.00E*00 e
>1.'49E<06 5.53E-07'O.00E+00 1.49E-06 1.27E-06'8.12E-07 0.00E+00 1. 2 7 E-Od' ,
Co 6. 04E-04 : 1.19E-05 0. 00E+00 6. 04E-04, 5. 48E-04 Cu 1. 27E-05 0. 00E+00 5. 49E-04 l 'M y"f 'Ha-24. 2.22C-03.2.70E-04 0.00E+00 2.22E-03 1.85E-04 1.26E-04 0.00E+00 1.85E-04. L L'a- 14 0 1.74E-03.1.10E-05'O.00E+00 1.74E-03 2.91E-04 S.91E-06'O.00E+00 2.91E-04i
- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1Mnn56- 3.09E-06 i.52E-06 0.00E+00~3.09E-06 4.51E-06.1.52E-06 0.00E+00-4.51E-06
' Bra 82.
; ~ tib-97j 1.77E-06.7.33E-07 0 00E+00.1.77E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00
.1 2GE-0 7 :4. 03E 0'. 00E +00,1'. 28E-07 2.15E-06 7. 56E-07 0. 00E + 00 2.15E-06
+
Sr-89< .1.17E-04 3.02E-05 0.00E+00 1.17E-04.0.00E+00 0.00E+00'O.00E+00 0.00E+00 _; /Sr 90. z0.00E+00,0.00E+00 0.03E+00 0.00Et00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 o
#: 4Totats- 5.95E-03 2.74E-04'~1.87E-04 6. 04E-03 1. 65E-03 1. 28E-04 '1. 02E-04 1.75E-03 l
?
~L;Kr XO1535 ??.44E-0401.34E-05-0.00ENO 7.44'E-04'7.9'9E-04 1.45E-05 0.00E+00 7.9?E-04 '
m -39h
=0.00E400 0.00E+00 0.00E+00 0.00E+00'O.00E+00 0.00E+00 0.00E+00.0.00E*00 4 v joO133r: 0. 00E+00J0. 00E+00 0. 00E+00 '0. 00E +00 1. 67E-05. 6. 34E-06 0.00E+00 1.67E-05 Xeh135f 12; 05E-03 9.'13E-06. O a 00E+00. 2. 05E-03 1. 32E-03 0. 30E-0610. 00E+00 1. 32E-0 3
, ~ M[f , f Kr Kr'-05m; S 70 ~0.00E+00-0.00E+00-0.00E+00 0.00E+00 0.00E+00=0.00E+00 0.00E+00 0.0
~
uO,6 ] Xe-138) iO.00E+00 0.00E+00 O.00E+00"0.00E+00 0.00E+00 }.00E+00 O.00E+00 O.00E+00
- 6. 22E- 10 ; .1.'82E- 10 0. 00E+ 00 : 6. 20E-10' 0. 00E+ 00 6. 00E +00 0. 00E+00 0. 00E+00 ;
~ jg.f '
' Totals ( .2.79E-03/1;62C-05t0.00E+00'2.79E-03 2.1'4E-03 i t.36E-0510.00E+00 2.14E -
A .. .. b' '~ rm (1h). ,
*AN
- w_::;
- n "Lh- <
, -s-Xgg _
TABLE 1-la
). El. I, il u c h fluc 1 < >2r F1 ant Utili 1 EFFLUErsi 6 TID l1ALTE DISPOS AL SEil! AlltiUAL F EPORT 1979 L IOU I D ' EFFLUEil T S-Sullf! A T I Otl 0F ALL RELEASES Unit Qu art er Guertst' Est Totkl 3 4 Error .
A. Ftssion e, scttvatson produ:ts f, ; - 1.~ f ot al release (not including H3 ' M' ^ q u e r. . ra lph s ) . Ci 6.44E-03 4 . 4 -1 E - 0 3 4.26F+01 t
- 2. 6verage dt lut ed concentrat t on '
during pert 3d _ _ uC i Ma l 3.75E-09 2.50E-09 _
- 3. Percent _ of Epd 1 e sebl e 1 i ratt *: 1.50E-02 4.0?E-02 B. Tr i t t u;n
__1, . Tot al r 417s s . I Ct 1.bSE*00 u 3.85C+00 3.65E+01J
- 2. 6versgc dilut4d concentratton dur t eig pe r i od_ __
___u c i na l 9.010-07 2.17E-06 7.23E-02
- 3. Perce nt of app t c stil e i t en i t _ :. 3.00E-02 C. Dissolved snd entrained gasc2 j 1. Tot al r elc ate Ct 7.94E-04 2.46E-0? 1.01_E?OM O. _ 8verage ciluted concentratton during' period _ _ __ _.
uC i nu l 4.63E-10 1.39E-09 _,_ 3. Percent of sty l i c at;1,.! l i tii t % 1.16E 03 3.47E-03_ D. Gross alpha encioactivity l 1. Total re l e as e l Ci l__2.51E-06l 3.36E-0Cl 1.20E+0d I T5. Volume c r' vut e (prior to dilution >l liters l 8.29E+06) 1.07E+0?l 1.00E+0!T ll [T.' Volume cd dilution c14 t a r' used l l i t e r's j 1.71E+09[ 1.76E+09l 1.COE+00T
.h c s 'hp qv 9
e r i MM i (15) d.
TABl.E 1-lb E. I. Hatch fluc l e se Pl ant UllIT 2
/
EFl*LUEllT 9 TID tlASTE DISPOSAL $Er116tlHUAL REPORT 1979 i L IQUIL. EFFLUEllT3-SUtlt1ATI0tl 0F ALL RELEASES Unit Guarter Ousrter Eat Tet al - 3 4 Error . H. Fisa t on a act t vat ten product S
- 1. Totsl r e l e s s .t (not including fl3, jca), y p cases,51phs) Ct 6.01E-03 1.75E-03 4.59E+01 o . 2. Hver>sge diluted concentratican durino period uCi/m1 3.94E-09 1.46E-09
- 3. P.e rc e n t of applicable limit % 1.07E 5.02E-03 E. Trittua
[1. Totni re l e as e C1 1.5SE+00 2.55E+00 : 2.62E+01]
- 2. eve rage d i l ui,ed concintration oCi/mi 1.0?E-06 2.12E-06_
- 3. _F<tcent during_pariod or spoticsb1e _1imit % 3. 4 3E-02 7.07E-02i C. Isi s sol ved and entrained gazes
,. 1. T o t .a t relense Ci 2.7?E-03 2.14E-03 1.01Et021
<(V : S 2. 6ver.ag e diluted concentration
~
'durino ocriod u C i / r.i l 1.82E-09 1.78E-09
- 3. Perc4nt of appticable 1imit *
. 4.55E-03 4.4SE-03 D. Gross alpha radioact ivi ty l 1. Tots 1 relearc ] C1 l 2.04E-06l 6.11E-0T! 1.20E+021 4 -y
- lE. Volu.ie of wast e (prior to dtlution)l Iiters l 7.39E+06l S.71E+061 1.00E+01l
]F. Vo l u n.e of dilution uster used l literz l 1.53E+091 1.20E+09] 1. 6 0 F. + 0 2 l f
/
e D m._ J. 7
/
~
i[I${{p -(16) a_
_ = s y . A-- 7
,t>
.!: i y
TABl.E 1-2a 3; - ,.
' E. LI.i H at ch iluc l e ar P1 nnt Ull! T 1 O a 't Q <
~
Al . ..
- EFFLUE!!Tf AtlD IM3TE DISPOSAL SEti! AtlNUAL F.EPORT 1979 s.*3 y - ,, . <l,[..
LIQUID EFFLUE!1TS
- , ~' ~
C0tiTINUOUS MODE BATCH MODE
' - Nuclides Releasec Unit Quarter Ouwt er Quarter Q u ar t e r 3 4 3 4 Ce-144 Ci 1.13E-05 O.00E+00--
' Tc-99m Ci 0.00E+00 5.56E-05 Ce-141 Ci 0.00E+00 0.00En.'O Ng-239-C1 1.28E-05 1.98E-05
.,e j C r --51 C1' 5,59E-05 2.99E-04
! i
,W Q '
l-131- Ci 0.00E+00 1.73E-04
"~ Zn-69tn . .
Ci 0.00E+00l 0.00E+00 W-187 Ct 0.00E+30 9.21E F-16 Ci 1.72E-04; 1.06F-04
'I-133 '
Ci 4.61E-06 ' O.COE+00 Ba-140 1 Ci 2.59E-06 0.00E+00
~~
' R .5 - 7 6 Ci 4.50E-06: 2.01E-05 Cs-134 Ci 8.56E-041 3.42E-04i Cz-137 Ci 1.30E-03 5.75E-04!
rio-9 9 Ci-
~~ i 1.57E-05 3.27E-05 r2r Ci 0.00E+00 0.00E+00 Zr-95 Ci 2.80E-06 0.00Ev00
.Nb-95 Ci- 2.!OE-05 2.47E-06 C I-132 Ci 0.00E+00 0.00E+00
, Co-58 C1 6.35E-05 5.53E-05 Nn-54 Ci 1.34E-04' 4.06E-05 Ag-110m C1 0.00E+00 5.65E-06,
, 2n-65 C1 1.59E-03 "S.81E-04 I-135-Fe-5?
Ci 0.00E+001 3.62E-06 Ci 3.46E-06 3.27E-06 10o-60 Ci 1.60E-03 1.64E-03
-Cu-64 Ct 0.00E+00 0.00E+00
'Ns-24 Ci 5.72E-04 2.04E-04 e La-140 Ci 0.00E+00 6.55E-06
- Mn Ci 0.00E+00 2.80E-06
- Cs-136 Ci 1.' 92 E-0 6 0.00E+00 s
Nb-97 C1 4.84E-06 1.04E-061
- ti t -65 'Ci 1.05E-05 ' 1.29E-061
- Sr Ci 0.00E+00 0.00E+00'~
Sr Ci 5'., l l 0.00E+001-O.00E+00~
+
l - To t at -'e' ora pe r i od-- ( above ) - Cl- -l
'v.
l l l 6.44E-03l 4.44E-03l-Xe-133 Ci- 1.74E-04 1'7.1GE-04 Kr-89 'Ci 0.00E*00 - 1.05E-05 X e- 133 ni; _ Ci' O.00E+00 1._3_ iE - 0 5 XA-135 Ci' :6. 20E-04 1.70E-03 l@c ,
-kr-G5a-
- Ci: 0.00E+00 1. 266-0M f .
-(i Kr-87 __
_ ._ _ Ci. _ 0.00E+00 2.77E-06 ] AL 74-1,38' C i- 0.00E+00 -2.57E-06 _- g
.) y 'd4 ,g I
e- / 1
.r hf
. . . - ac
.v' -
'(17))
a.w. . . ._ - - -
, . . .~ . . . .. . . .- - . -. - ,
"h ' TABLE 1-2b ,
E. I. H at c h' iluc l e ar . P l ant UllIT 2 [ EFFLUEtiT AtID llA3TE DISPOSAL SEflIAlillUAL REPORT 1979 a: ;, . 2 - 4
,. LIQUID EFFLUEllTS
: CollT!tlVOUS f10DE EATCH t100E ficclides Reltazed Unit Quarter Qu art er Quarter -Quarter
- 1 3 4 3' 4 Ce-104- Ct 0.00E+00 0.003+00._,
i T- '
- T c -9 9 ta Ci 3.07E-06 1.94E-06 '
Ce-141 Ci 0.00E+00 2.45E-06 "3 ' M gA tip-2 39 - Ci O.00E+00 ' 2.75E-05_, 4.83E-04, 4.41E-05 17 Cr-51 Ci
#C I-131 Ci 1.21E-06 2.77E-06 '
d 2n-69tn C1 4.92E-06 6.22E-06 3.99E-06 j' 0.00E+00 W-187 C g F-18 C1 3.67E-04 2.44E-04 I-133- Ci 1.90E-06 l-8.93E-06 . xcr Dis- 14 0 Ct O.00E+00t O.00E+00l 85-76 Ci i 1.06E-041 3.06E-05 C5-134 Ci 5.93E-06 3.99E-05 4
'Cs-137 C1 2.47E-05 6.3?E-05 ,
rio-99 Ci 0.00E+00 0.00E+00 '
~
-Or-97 Ci 0.00E+00 1.13E-06 Zr-95 Ci 4.07E-06 3.36E-06' tib-95 Ci 2.05E-06 0.00E+00 5(s D -
..' 1-132 Ci 6.37E-07 3.62E-06 Co-$8 C1 1.06E-04 6.96E-05
. - fin Ci 1.49E-05 . 7.3EE-06 Ag-110m Ci 0.00E+00 . 2.08E-06 l 2n-65 Ci 2.13E-04 1.62E-04 I-135 Ci 0.00E+00 0.00E+00 Fe-59' C1 1.49E-06 1.27E-06l Co-60 Ci 6.04E-04 5.4?E-04 Cu Ci 2.22E-03 1.85E-04
- 4:.r. fla-24 Ci 1.74E-03 2.91E-04 V La-140 Ci 0.00E+00 0.00Et00
=
Mn-56 C1 3.09E-06 4.51E-06 $(i f Er-82 Ci 1.77E-06 0.00E+001,
- J tio Ci 1.2CE-07 2.15E-06 ,
Se-89 C1 1.17E-04 0.00E+00 45 ' :Sr-90 Ci- 0.00E+00 ' O.00E+00
-l-' . Tor g ror-period ( at.c ve ) -l Ci l -l l 6.04E-03l 1.75E-031 2
~
^ ~
Xe-133 Ci4 1 7.44E-04 7.99E-04
, ' ~ ~~
Kr-SS. Ci- 0.00E+00 0.00E+90 Xs - 13 3a.
- Ci 0.00E+00 't.67E-05 :.
J ,
-C Mc-135 'Ci 2.0$E-03 1.30E-03 1
, .. ! Kr-35ta Cs O 00E+00 0.e0E400 j 3
re-87 - Ci 0.00E+001 0.00C+057) j[fm., j e-139'~ Ct 6.22E-10l-0.002,001-
,, l _
+^ - 4. /
I [I., ; c .,;
.r,...w.,. c ~
gyr -
,y 1
_ . .m ( 18) .~ w ,,_,. .; 4 _.-- , . 3 b ...i' q .
~
- v(%<+; , __ ; ; , , 3, ,. ,, ,_
s y
~ -
7 L2/ JGASEOUS EFFLUENTS
~
- 2.-l . I R F.GUL ATORY JLIMITS ~ ,
Si,(x;,I ;a. . '( U " T h e E r'e l e a s e ' r a t e limit of nobl.o gases from the site T ~ , shal.1 be: '
;g - ; , -
, 2, ~ Q t3- '
- 1. 9 E 1. 0 E3 -+ Qyi 11 Ey. + % En $1 '
i - +' n .
- where-Q 3 = Total release ra te . f rom m a i. n stack for both Units in'01/sec (elevated release)
Q v =: Total release r a t'e from vent in Ci/sec (ground release)
,, i =' The individual nuclide n = total nuclides X;4s '
,j~ E y = The : average gamma x energy per disintegration
~
97 E 3 =: .The average beta energy per disintegration (2 ) The release rate limit of all radiotodines and radioactive materials 1n- particulate form with half lives greater than eight days, released from the site to.the environs as part of the gaseous wastes, shal.1 be.
~
- 1. 0 X 106 Qos + 1.5 X 106 gpy <1 Where Q p3 = Total release rate from the main stack-for both Units in Ci/sco (as elevated
]b s -
release) Qyp = Total release rate from vents for b'oth Units in Ci/sec (ground releases) _ (1)' The - average release rate of noble gases from the site
~
b. o during any calendar quarter shall be:
~~ *
- 5;i 4Q..n s'- i L-
- 1. 2 E y + 3. 0' E 3 A
.+ Qv i
66-E + 140 E B I1 (2) lThe average f release cate or . noble - gases during any 19. ' consecutive _ months'shalt be: c -; -
! >j t 9 Ey + 5.1~ Eg- _+-Q i y 130' .Ey+ 270 Eg . < : 1.
' T +?. .n. Q '3-: .
~
f 7o- ' ' E (M ) . ;The;;averde _ release rato! or' all rad io ' todines and u rndioactive~ materials in Joarticulato form : from the . site
;.g^
. T w i t h p h a l. f ' ' 1. t v e s g" eater than eight ' . days - d u r.i n g any
, j- 1 calendar. quarter shallibe:' ,
e 7.-l . t(X : 10 6[oo's +(1. qj x 107 ~ opy\<.1 5
. pN; '
d4) ;TheiJaverage release sea te. o ry L all ' radio todines. and p( . Jrad.toac h t.ve mater tals in'oart t.cul.a te .' f orm from' the' site: m m m g^ %-1 m 1 4
- T Y
wg , , g .- D** -
.f. x ,
f.
, .W@ D ""I '
g y ,
. !(19)' ,.
. with? hair lives - greater than. eight . days during any
'{' ,
period.or 121 consecutive months shall'bo: 2'.6'X 106 gpn + 3,*r x 10 7 goy g 1
"" [ ') 5) .The-am'ount of' Iodine - 131 released during any calendar quarter shall.not. exceed 2 Ct/ reactor.
n w (6) The ' amount of Iodine - 131 released during any period :
.~ of 12 consecutive months ~sha u not exceed 4 Ct/ reactor.
..- Should the conditions of 2.1.3c (1), (2), or (3) . listed below occur,' the Itcensee shall make an - investigation .to
" ':/ 7 identir.y. the- causes of- the release estos, define and initiate a proganm of action to reduce the release rates to levels itsted in subsection 2.1 or the design objective
!!!!P-ST9 ' a nd report these actions to the Commission within 30
,51 days. from the end,' or the. quarter during wh ich . the reinases f . occurred in accordance with section 5.7.2.
-(1) If the average release rate of noble gases during any '
cal.endar quarter is: j -
- 4Qin 4 'T EY + I? RD' + Qiv- 260 EY + 5810 En >l t .i n -
(2) If the average release rate from the site of all radio iodines and radioactive materials in particulate form w i. t h hair Itves greater than eight days during any calendar quarter is:
;r t
, j. 5.0 X 106 Qps + 7.7 X 107 Qpy > 1 ~ (3) Ir .the amount of. Iodino - 131 released during any calendar quarter is greater than 0.5 Ci/ reactor.
- d. -The post-treatment ;ortgas monitors shall be operating and set to -alarm and to initiate the automatic closure of the
. ' waste gas discharge valve prior to exceeding the -limits-spectried in Section 2.1.3a above. The operability of the automatic isolation valve shall be demonstrated quarterly.
- e. -T T the oost-treatment offgas - monitor is not operating,- a shutdown shall. be initiated so - tha t t h'c - r ea c to r will be.in the. hot.-shu tdown condit t'on within 10 hours.
..r .- If the~ release cate of noble gases- measured . a ti the pretreatment moniton ' exceeds 260,000 uct/sec for a period!
greaterf than . !I8 f hours, nottry 'the Constasion -in writing w i.t h i n 10; days' :t dentt rying the causes or- activity and in iaccordance'vi.th section 5.7.2. '
' g. The. reactor _ containment- for each Unit; . s h'a l l be purged
<- g, chbrough .the~'standbv; gas-treatment-sys em for.thatLUnit.
>)
- f ;- .
6 , y N ~ ' s <- i 4 7, . '( 20) ' gqv
.m m e '
$f -
- ;h. (R Dotent t1My - oxplosivo . gas . ' mixtures of- ' hyd rogen and oxygen contained'in tho of fgas system downstream 'or the
<~
recombtneas s ha M . be . continuously ' monitored during t reactor power operation for hydrogen .concentrition. , 7- Tho: hydrogen gas monito"ing system'shall provide alarms 1 1 . locally and in- the control room at. a set point of 4%
'# ~
. hydrogen. concentratton by volume. At least one ,
f _.
... continuous ga s monitoring system and its associated
._- alarn system 'shs11 be operable during reactor power s e
- operation. 'If both. o f the- hydrogen ga s - monitors or
^ .
both of the a s's o c i a t e d al. arm systems are inocerable,
-reactor operation may .be continued for a period'of timo '
- not- to exceed' 2 wooks, orovided that either (a) grab samples. -are and analyzed 4
.taken for hydrogen concentration once overv- 4 hours, or (b) using a
, T .tomporary'hydrogon gas nnalyzer i n s t a l.1, o d in the offgas system Itno 'dounstream or the recombiner, hydrogen
- f. - g) concentration, readings are- taken ' and logged .every 4 .
- 97 ,m
' hours.
(2)~ Tho~ h'vdrogen concentration in the orrgas system-
-downstream of the recombiners. shall not exceed 44 concentratton hv volume. If at any time during reactor.
power operation, it is determined that the hydrogon conoontration limit is being~ exceeded, action shall be initia ted '. within 4- hours to return the hydrogon
' concentration to within the prescribed limit. If the hydrogen concentration is not reduced -to less than 4T 9! ' bv .vol.ume within-24 hours, t h'n offgas system fl.ow shall .
{- bo1 stopped.
- y,~
(3) The installed hvdrogen monitoring systems- shall have-
~
d a il,y sensor checks, monthly functional chocks, 'and T quarterly .ca t t b rat ions. The portable hydrogen gas. analyzer shall be calibrated immediately prior- to installation and shall be subject to daily sensor checks,- monthly functional checks, and . quarterly calibrattons:untti removed from serv.co. i.- ' An unolanned or' uncontrolled of fsite release or~ radioactive materials in.Gasoous effluents in-exooss of 150 Ct. or noble gas or 0.02 C t. -or radiciodines in gaseous form shall be reoorted to the NRC within 30 -days- in accordance with soction-9.7.2.
, 2. 2 'ttE ASUREME'!TS A!!D APPROXIMATI0il9 0F TOTAL-RADIOACTIVITY I Waste gas t ecleaso at' Hatch is confined to 'rour paths. 'Each or '
'those f 'ou r. . ' paths is~ conttnuousiv . monitored for gaseous
, c o n c e n t ** n t i o _n :: a n d aach han ' an integrating : typo _ collection devico wh t ch iconcentes ton - pa"t ton 1.a tot and tiodino
~
00" each ' sovon . day - M speriod- ( Proco.tu re s '. m ro ' in uch that
, shorter collection times: are us td where 'appi tca bl.o ~ to' Techn ical' Spec t rication frequirements ) .
e-k [ t
.. a
,b Nf y .
np
Each of' those continuous samp1'ers 'has a flow controller which
, .maintatna sample flow within about a 10 oorcent range over each seven day collection period.- The offgas vent (elevated release) and the reactor butidtog vents have flow measurement devicco which continuously record the flow rate of the gas released
'O v ~
faccuraov of these devices are within -10% of the actual flows as measured during precoerational testing). The recombiner building vent flow on Unit One is conservatively assumed to be constant at 500 C F'4. In addition to the gaseous, particulate, and iodine s
+
release measurements trittum, gross alpha and gaseous isotooto n measurements of- each vont stream are conducted on a monthly schedule. After each calendar quarter (19 weeks) a summary of waste gas release from the four vents is compiled and as such is designed to meet thn requirements for preparation of the 6-month report as specified in Regulatory Guide 1.21. Unit one and two releares
,. _ were ca lc u l.a t e d 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 A!!D ACTIVATION GA3 The total curie release is determined from the continuousiv ~~
reading gaseous monitors in addition to the vont 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 in.iection of a known amount of off-gas into the samole chambers. The w( total' curie release is ca lc ul.a t e d by the computer for each . of the individual nuclides released. This number is mq1.ttplied by thethe along with average enengv per disintigration (5g&
- 59) coefftetents in the release limit formula in our Environmental Techntcal Spectrications. All of the nucildes are summed and stored in their respective data files until the end of the quarter. Then the computer divides the sum of the nuclides by the seconds t r. the quarter to determine the percent of the tech. spec. . limit released.
- 2. RADI0 IODINE RELEASES ,
Iodine releases arc determined weekly for I-191, I-191, and I-135, for each vent. Whero ~significant activity is not measured f4D A' releases are calculated. Since calculated itDA's are b e l.o w Technical Spectrication detectable concentaattons then 0 (zero)- release is used for the weeka with ' only , t1D A values. Weekly releases are summartzed with l the aid of the counting room . calculator - comonter system and! a- q u a r t e r 1. y. total ~is prepared from- 'tha week 1v-summartes. The cercent Te ch n t. c a l Spectrication for I-111 on Ta ble 21 is' banc 3- on the quarterly ' Technical Spectrication ; y Ltimit l
,b '
-Q)
=
.m (22):
aff' s Uv- _
- 3. PARTICULATE RELEASRS:
- :PNeticulate- roloases. are. determtned wecktv for each vent.
1'ihere signtricant. activity is not measured MDA release is s calcul.ated. Since calculated MDA's are below Technical j '); Specification detectable concentrations, then 0 (zeroi rolesse is used :for weeks wi.th oniv MDA values. Weekiv L
- releases are; summarized with sthe aid of the counting room calculator . computer. -
- A r t e r. each:. calendar month the particulate filters from each vent- are D combined, fdsed, and strontium separation is made.
Since namole flows and vent flows are almost constant over each monthly period- the filters from each vent can be dissolved . together. Decay correctionn are made back to the middle of the monthly collection period.' Again the counting room calculator - computen ts used'to aid in the calculation
'.. of the .Sr-89, 90 release. Where signiftcant strontium D'T activity is ' not detected HDAs are calculated. In order to Y- eliminate the need for_a quarterly composite Sr-84 and Sr-90 c -
. activity is ca l.c ul a t e d for each monthly composite. The
' percent' of Technical Specification was calculated using quarterly nyera rte eq ua tion.
>. li . GROSS ALPIIA RELEASE w
The - groos alpha ~ release is computed each month by co un t i. n g
+
the particulate ft.lters 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 sunmed at the end of the month.
;,9 (g -
. 5 .- TRITIt!M RELEASE -*
4 Tritium samples. are obtained monthly from each vent by e passing tho sample stream from a cold trao immersed in a
' liquid nitrogen or an acetone and ice mixture. The grams of water vapor / cubic foot gas is measured upstream 'of the cold trap ^ tn ordor to alleviate. the difficulties in _ determining
-water vapor- collection. e f fi c i en c ie s '. The tritium samples are analyzed by an. independent laboratory. From the uCt/ml
,trittum concontration, the grams waten/ft3,. a n d _. the vent flow. rates, th e - monthly -tritium release is calculated for ench vent, and the quarterly summary cant be genera'ted from-the monthly ~ calculation forms.
~ lla t c h has ' attempted to maintain al E calcul.a ted MDAs as 1.ow
'as possible by : counting. samples. longer than- what would be' normnllyx practical.- For . example. ~at this time-au ' weak 1v particualte/ and todino counting times are;.3000' sec and-Stronttum"separattonn.are counted for 100 minutos.
~
Regulatory _; Guide; 1. n requires.- that estimated total' error in-l a n417 9 ts G tec hn iq ue s :be reoonted. 'These estimates are . required
.for$the : total. fission and activation gas release, total . I-131-
'l L )%
.s i% :5. ,
* ^
8 P. A
, tj ' , ,
Q3),
;f w, i'
, r NM E ': 1.-
release, totai particulatos with hal.f-lives grectG" than S-day releano, and total tritium release.
"The total or maximum caror associated with the effluent measurement v111 include the cumulative errors resulting from the total oce-ation of sanoling and neasurement.
Because 4. t may be very difficult to assign error terms for each paramotea affecting the final measurement, detailed statistical evaluation of error are not suggested. Tha - ob,jective should be to obtain an overan estimate of t, w er"or a ssocia ted with measurements of radioactive materials released in Itquid and gaseous effluents and solid waste." Estimated errors are based on errors in counting equipment calibration, counting s t a t i s t i. c s , vent flow rates, vent sample flow rates, non-stendv release rates, chemical yield factors, and sample losses for such items as charcoal cartridges.
~
- 1. Fission and Activation Gas Total Release was ca:culated from process monito" readings. As 98.3% o f this release was from the main stack the !!D A release values of the ground level release points were insignificant to the total release.
?!on ito r Error in Calibration 50%
Vent Flou Ra te 10% Non-Steady Relence Rate 20% 66?
- 2. I_- l_11 Release was calculated from each weekly sample:
Statistical error 60% ~ ' , Counting Eq u ipm e n t Calibration 10% Vent Flow Rates 10% vent Sample Flow Rates 10% Non-Steady Relcace Rates 10% Losses From Chercoal Cartridge 10% IIOT 3.* Particulates with half-lives greater than 8 days relaase was dominated by the MDA c a lc u l.a t i o n s for I-111 and Ra-La-140 hence the errors in the strontium determinations and gross alpha had negligible affects on the estimated error in the total particulate release: Stattstical. Enror at t:DA concentration 60% Countng Equipment Calibration 10% Vent Flow Rates 10% Vent Sample F1.ow Rates 10% Mon-Steadv Release Rates 10%
. T005 4
Total Tattium R e 1. e a s e was dominated by the reactor building vent t a t t i.u m release, hence, the large" statistical errors of the off ,Tas vent and recombiner building vent tritium i releases do not affect the error in the total ' Lum release.
- s(g c kgh
= M -
i=-(, JaterIVaoon -in Sample Stream Deteamination 201 Vent Flow Rates . . 10% Countinyt Cs11bratton and Statisti.cs 10% y Hon-Steady Release 50%
}l
~
i 00T- _ s
'-" 2. 3.G ASE00S' EFFLUE!!T T R ELR ASE'_ D AT A
, ; .9 ' Re gula torv '- Gu ide -l . 21 ' Ta bl.e s ' 1 A , 1. B , and 1C are found i n' this fe,#2
. reo ort . a s' . Table s ' 2-1, 2-2,.and 2 'i .
; [ .
jData ts presented on a' quarterly . basis 'as oce Regulatory Guide
'l.21.
N* 3. 50 LID-WASTE -
- _c:
,3.1 Regulatory Specifications..
xr [Q ,. . .
.fij . .a. Measurements shall be made to determine or estimate the total curie quantity 'and ortnotoal radionuclide composttion
.or all radioactive ~ sol.id waste shipoed offsito.
4 .t. Solid.' wastes in storage and oreparatory te shioment shal.1 be monitored and : packaged to assure comoltance with 'the aoolicable portions of 10 CFR Part 20, 10 CFR Part 71, and fl o CFR Parts 171-178.
- c. Reoorts of the radioactive soltd waste 351.o m e n t s , volumes, ortncioal "a d i o nu cl i d e's , and total curie quantity shall be
~ri submitted'in accordance with subsection 5.6.1 of the HNP-ETS.
lO.
.3.RESolid Waste. Data m .
Regulatory guide 11. 21 Table '4 ts found. in this report 'a s Tabl.e 3-la, b. c p.
.=
g s e @,
+
f
- r*N L -f
' . ;. 4
- q qg6.. (25) I N[$h,e ' '
q
, y y ;, ; -
ib.6-!k 1. _i u . _ . . _ 1i _%. , L .. - ,. , ._ , . . . , 4
~. ._. _ -
'I"aBLE 2-1 I-i' oy.a %
-. Q.. .EFFLUsHT HilD llR3TE DISPOSAL SEf11 AtillURL' REPORT 1979 GASEOUS EFFLUEtlTS-SUrir1RTION OF ALL RELERSES Unit Quarter Quarter Est Tot al E. lI7 Hat c h flucle ar Power Plant ' SITE 3 4 Error ".
A. Ti fs f on t ac t i v at i on g as e s
'rs= ,
^
'!*'U E 1. Total r e l eas e C1 1.32E+02 5.46E+01 8.00E+011
!@ a
- 32. .Ruerage rel ease rat e for period
~
uCi/sec 1.69E+01 6.79E+00 '
. gs#A .
3.' % eof"Tec hni c al spec i fi c at i on 1imit *: 2.46E-02 1.40E-02 E . ~. l od i ne s e -*w , J. Tot al iodine-131 Ci 4.15E-05 5.63E-05 1.10E+02[
- 2. Rueraae release rate for neriod uCi/sec 5.28E-06 7.01E-06
- 3. *
. o' Technieal spec i eic at ion 1 i r.. i t % 1.04E-03 1.41E-03 i
C."Particulates
. T 1. Particutatee ',s i t h half-1ives>S daus Ci 2.61E 1.72E-04 1.00E+02l.
' . . Fuerage - t i c a >. ** a t e for period uCi/sec 3.32E-05 2.13E-05
~3. *
. of Technicsi spe c i f i c at i on 1 i rn i t :. 5.36E-02 2.31E-02 -
-4. Grosa al pha r adi oac t i vi t v Ci l 4.35E-06 5.22E-06 D. Tr t t iun i
- 1. Tot al t e le a2 e Ci 6.13E+00'i 4.60E+00 9.00E+01l
- 2. Aver age release r at e for period UCi/sec 7.79E-01 5.73E-01 s 3. *: o f' Technisal s p_e c i f i c at i on 1 t r,i i t : 0.00E+00 0.00E+00
\
V 9 NW 9
\
9 i r
& 9 r
(26)
bL M 0 ,'- ' ,
=
? ,r
.; ._y - ,
][q : /
f._ i , , t
%g:3 -
~.
. - !' .- r[ygg2 2_2
" h,, .
J.
&*w ,
~
E. 18. H .t c h Huc l e ar ' Powe r P l ant SITE-ud [ . 9
' ' D s w .
. EFFLUENT AHD: HASTE' DISPOSAL;SENIANNUAL REPORT 1979
, Mw ' :
.&fEf. . 9 (n,ysk,, r -GASEOUS: EFFLUENTS-ELEVATED RELEASE ..
e WpJi ; w . COHTINUOUS MODE BATCH NODE M.rf C 3 Qutrter _. Qearter Quarter Quarter. Mf . ~ 'cf t des Re l ease d - Unit-3 4
-4 12% ~ ' '3
?:% b n .
[ k dis"kission. gases '
.jh4 3 d Q y;; Q W ;y % Q ' ~
0.00E+00"5 pQgyge-133: 9.05E+00 2.63E+00 0.00E+00-Q%%$ d i;myRe-131H-Ci Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 X . EJsg" "@'L' # N D Kr~89' , C i- 1.23E+01 1.33E+00 0.00E+00 030E+00 JW ^ VX e- 13381 2 Ci 0.00E+00 0.00E+00 : 0.' 0 0 E + 0 0 0.00E+00 J C m dy n g Ci 2.30E400 2.76E+00 -0.00E+00 0.00E+00 m %Xe-135 44ye.n+~ ~ Kr-8W ~ 7 : Ci 1.46E+01 1.25E+00 0.00E+00 0.00E+00 if I-131 - Ci 0.-00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-e7 Ci 4.00E+00 2.05E+00 0.00E+00 0.OeE.00 C [: 5.89E+00 0.00E+00 0.00E+00 + mn Xe-139 C1 1.02E+01
; 3 7 -. , . 0.00E+00 0.00E+00 -0.00E+00 0.00E+00
.-w7w % __ _ Ci-0.00E+00
.Md H-13 Ci 5.89E+01 2.13E+01 0.00E+00
" Cf 0.00E+00 0.00Et00 0.00E+00 0.00E+00
. EM fr-85 2.2SE+00 0.00E+00 0.00E+00 Xe- 13511 Ci 2.42E+00 " d.y: m. ;9 c .< c-.
~ ,-
I-133 Ci- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-69' Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MQ.i 1 -Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 T y't F^
- 1-135
.Ar-41 .Ci 3.73E+01 1.30E+01 0.00E+00 C. 00E+0 L ,~ k <
- S '
0.00E+00 'O.00E+00l M -Totil for per iod - Ci 1.31E+02 '5.25E+01 l%$$ jf4@ l 12.; Iodines-
- mm 2% ^w I-131- Ci' 3.05E-05 5.42E-05 0.00E+00 0.00E+00 il ' I-133 Ci 4 99E-05
. 1.13E-04 0.00E+00 0.OOE+00 I-135 Ci 1.05E-05 2.37E-05 0.00E+00 0.00E+00
- . we
}7 .
\hh ' 0.00E+00 -0.00E+00
~
- Ci 9.09E-05 1.91E-04 p ,TTot al f or1per i od, fa !3. . Part icul at es t, : u
- 1 sr-89 .. 'Ci -1.54E-05 4.53E-06 0.00E+00 'O.00E+00 a.O
~
. r -53~~~ ~
Ci 9.30E-08 7.51E-08 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
' ~ Ci 0.00E+00 -0.00E+00 0.00E+00 0.00E+00
~I-131
.1[ isn-113, Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
'2 ' , ~
ita-140 >Ci Ci-8.32E-06 2.46E-05 0.00E+00 0.00E+00 3.81E-08 0.00E+00 0.00E+00 0.00E+00
. , C S - 13 4. -
%- Cs-13? Ci 6.72E-07 _1.32E-07 -0.00E+001 0.00E+00 11 . Ce -14 4 ' -
Ci 0.00E+00 0.00E+00 0.00E+00' O.00E+00 M
~
Zr-95 Ci. -0.00E+00 -0.00E+00 0.00E+00 0.00E+00 i N 4 ut C i' O.00E+00 0.00E+00 0.00E+00 0.00E+00 l W; . . _ , m w Cc49: Ci 0.00E+00 0.00E+00 0.00E+00 -0.00E+0i Vry E.e :nn-54. - -Ci: 0.00E+00 0.00E+00 -0.00E+00 0.00E+00 m . 0.00E+00 0.00E+00 O.00E+00 0.00E+00 ,I X/- m' V- Fe -591 >- ..- m. Ci' j go,,;g - , Ci' 2.57E-06 2.06E-06 0.00E+00 0.00E+00 l M d-h , L a- 14 0 c Ci 1.54E-05 4 79E-05 0.00E+00 0.'00E+00 l
).[hb y ? T6: diL ro'r :. pdr i od ! i di i 4.26E-05 7.' 9 3 E'- 05 O.00E+00 'O.OOE+00
&.hY$yl aw. . ~' , . ,.
' - 'l
' , - " 3:.N' Nyg ,
r
..ff^
W - . , 4sGid. . -s g e- ~ -'. . y ;. 4 j z
; 4 .- s ..
m whw . _ 1
~ .c , . , r -
- 96 W. ,
s b'.-:X , ..._y
- w cn
%g _.
q:q , . j -2c
'IABLE 2-3 "
'~
ypy ; .- - h ' 1- ...
. E. ?It Hat ch tiuc 1'eir Poue'r"Pl ant ~ SITE m, ; ,
.n .
b 1979
'dh.e+f..,i mg _
r [CFFLUEHTArdWN3TE-DISPOSAL'SEMIAHHUAL. REPORT st. - % , phE9 . ,N .SEOUS EFFLUEHTS-GROUND-LEVEL RELEASE w pm - . y' gp !" - W CONTINUOUS T10DE BATCH MODE l i der. Rel e ased v Unit -Quarter Quarter Quarter Quarter ME QW d) ,, 3 4 3 '4
.L nx. ?
F y v: r -. .. , ,. p ,
- m. ,
1,,pt3sjon:g33,. 3
.LJb.3:mn>f+ g=yyv- -
~
-99NTM% % %j m p ,. 1.19E-02
~ -
0.00E+00 :; 0. 00E + 00
;M
. Menssis yW99Xe6133- Ci 5.54E-03 ., chggg _EC
- y ther"131M w . C1 0.00E+00 0.00E+00 0.00E+00 'O.WOEtDO 471*=
g g g3 KN 88 _, Ci- -0.00E+00 0.00E+00 0.00E+00 0.00E+00 . 0.00E+00 0.00E+00 'h md Wi{.z 'Xs-133M Ci 0.00E+00 0.00E+00
,,JM 9 W ,' ..u cXe-135 -
Ci -4.39E-01 9.52E-01 0.00E+00 0.00E+00 < dM ~
'Kr-05M- ___ C i 0.00E+00 -0.00E+00 0.00E+00
'O.00E*00 0.00E+00 0.00E+00 0.00E+00 kg -I-131 Ci 0.00E+00 ,
,jf - Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 W P" Xe-138- Ci- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 N[ ' '
Xe-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
,iTS.1 H-13 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 s ('< m Kr-35 Ci- 0.00E+00 0.00E+00 0.00E+00 0.00E+00 dM!% . Me-135f t Ci' 'O.00E+00 0.00E+00 0.00E+00 0.00E+00
.S~e -I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M, -Kr-83 Ci 5.28E-01 1.14E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
' 2@
h}<. - Or-41
~
Ci O.00E+00 0.00E+00 0.00E+00 0.00E+00 1. r y47e ^ grg/ . ' Tot al' for period ~ Ci -9.73E-01 2.10E+00 0.00E+00 0.00E+00 V.* j.;y - t ; p#{r
- e. ,
1 ,22.HIodines
' ^2M i - 0.00E+00
'"s +. - 'I !?! Ci 1.10E-05 2.15E-06 0.00E+00
'1 11-133 Ci 1.06E-06 2.33E-05 0.00E+00 0.00E+00
< n -I-135' -
C1 1.76E-07 0.00E+e0 0.00e+00 0.00E.00 hh .. . Tot al for pertod' 9 Ci 1.22E-05 2.54E-05 0.00E+00 0.00E+00
, [f, f s ..
_.~, , -y3. " P ar's l. .culatez yp . 1:W - sr.ca- ~'i 5.90E-06 9.13E-06 0.00E+00 0.00E+00 ' Sr-90 Ci 1.14E-06 1~.90E-06 0.00E+00 0.00E+00 V.W, ;:e ,' Ce 2141- Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M Cr-51' Ci 0.00E+00 0.00E+00 0.00E+00 -0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00~ ud I-131' Ci' lI44YR ~
'$n-113- Ci 0.00E+00 -0.00E+00 0.00E+00 -0.00E+00
;h "B a- 140 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E*00 WG' 'Cs-134 Ci 2.14E-05 0.00E+00 0.00E+00 0.00E+00 j.f}} {;i' Cs-137L Ci- ~3.09E-05 5. 0 0 E--0 6 0.00E+00 -O.00E+00 ,
,WN
~~
,Ce-144- :Ci 0.00E+00 0.00E+00 0.00E+00 'O.00E+00 d@. Zr-95 Ci -0.00F+00 0.00E+00 0 00E+00 0.00E+00
..tW : Ht; - Ct. -0.00E+00 0.00E+00 -[00E+00 0.00E+00 ffP$[9' .Co-53' Ci" '2.23E-05 0.00E+00 0.'00E+00 0.00E+00
*i Mn-54c Ci 1.02E-05 0.00E+00 'O.00E+00 0.00E+00
'g e -
'Fe Ci' cl.77E-05 0.00E+00 0.00E+00 - 0. 0 0E + 0iJ-
, j[k
- Co-60" -r eC1 1.09E-04 7.62E-05 0.00E+00 0.00EA00 E _La-140'
- +
Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .c:fW
.m ,L ~ .
j7 ga,},. UT dt%1 YfrN period'I ^ NbC 2.19E-04 '9.22E-05 3 0.- 00E +00 0.00E+00 i RQ yMl% - s < ~ - , g:gg g wwe} , ".,'. 2 [% .m [' E I2 O' x,
7
+
4 34 TABLE 3-1a- .. Pjf.NT-E. I. HATCH r ~ b EFFLUENT AND WASTE DISPOSAL set.11 ANNUAL REPORT (YEAR)1979 ' b
- SOLID WASTE AND 1RRADIATED FUEL SHIPMENTS FOR Ui!IT July through Decmber -
A. SOLID Y.'ASTE SHIPPED OFFSITE FOR. BURfAL OR OlSPOSAL NJot irradiated fuel)
- 1. Ty}e of W.ute Unit
{ j' "8 , bb
-a.. Spent resins, ft!ter sludges, ew;forator -/
n 1.10E+2
. Inttor-.s. etc. Ci 9 . (6EMT 0 E +2
, . b. Dry compressio.e waste. contarmnated m' 1 .90E+2.
equip. etc. Cl 1.98E+0 10 E +2
- c. Irradiated components,' control -
W- -.6 .40E-1 rods. etc. 3.60E-2 1. 0 E +2 C1 ~ 3
- d. Other (desenbe) m . E Ci . E . E
- 2. EstL=t of maior nuclide composition (by type of vaste) - .
ISOTOPE PERCEfiT CURIES Zn-65 37% 3.54 E+1
, ,n a. Cs-134 & 137 -33% 3.12 E+1
- t C/ ' Co-60 9% 8.48 E+0
-Others 21% 1.95 E+1
- b. Zn-65 39% -7.65 E-1 Cs-134 &_137 33% 6.59 E-1 Co-60 11% _2.15 E-1 Others 17% 3.41 E-1
- c. Zn 40% 1.44 E-2_
Cs-134 & 137 34% 1.21 E-2 Co-60 13% 4.60 E-3 Others 13% 4.90 E-3 d .^
- 3. SoUd Y.'arte Dispodtion , . , .
'.. Number of S*d ments Mode of Tr2nsportation D:stination
- 38 ,- ' Chem fluclear Truck , Barnwell, S.C. .
], ~ D. IGRADIATED FUEL $H!PMCJTS (Disposition)
. [7 Number of Shinmenis Mode of Tran rortstion D:stirution :
$t . . -
# $-f [
I?
)b/ ' ir-
_,, , , . , , , , ,. m ,, . . . , . . ,, m . -
~~
. , , .3-u
' TABLE 3-lb- i o .
.v _ ;
'pg,ggy;g,;I. IT A T +'.1 '
g ' EFFLUENT AND V!A"lTE DICPOSALyE!.!! ANNUAL REPORT (Y CAR)_1979 4
~
" ' SOLID t/ASTE AND 1RRADIATED TUEL SHIPMENTS
- i
, FOR UMITe 2 ,.
. July through Doc mber -
. A. SOLID Y!ASTE SHIPPED OFFEITE FOR DURIAL OR DisrO5AL (Notinadiated fuel)
- 1. Type of were ' uni 6* *" "' E5' T ui
~
r,aoa enor.1 4- a. Spent resins. rdrer s!cdges, en;forator m 2 2 .03 E +2
% bottor u. etc.
~
CF T.5TE +1 1.0EW j; b. Dry com; ressible waste, contstmnated m' equip. ete. J~.33 E+1 ci 2 15~B7 I. o E+z
- c. Irradated comronents. contral
- rmh. e tc.
. l'_ .
E_ Ci . E . E
- d. Other (desenoe) m' . E Ci . E . E
- 2. EstLmte oI maior nuclide composition (by tp: of msre)
ISOTOPE PERCENT CURIES Zn 45% 6.84 E+0 yy I a. Cr-51 4% 5.50 E-1
- A. / Cg-6J 13% ,1.93 E+0
, _ Cp _53 -14% 2.20 E+0 Others~ -24% 3.68 E+0
- h. Zn -43% 1.02 E-1
'Cr-51 5% 1.29 E-2 Co-60_ 12% 2.86 E-2 Co-58 13% 3.05 E-2
- c. Others 27% 6.09 E-2
-d.
..s
.9
. 3. ' SoUd Y.*aste D sposition . . .
. Hu:r.her of Shipments Made o f Transportaticn - D:stination 24 .
Chem Nuclear. Truck ,- Barnwell, S.C. 8.;3RRADIATED FUEL Sh1PMENTO (Disposition)
./ 'E
- Numter of Sh!crnents Mode of Tran:oortation . D:stfrution
'Ql
^
'i J
g a
~ ~ T.6!:-
i.7 u ~, . . ,
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