ML19263C899: Difference between revisions
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lease of the batch. To facilitate the measurements and calculations, the nuclides of Column 2 which can be produced in a fission reactor have been grouxd according to MPC value and type of radiation as sho.n in Figure 1-1. | lease of the batch. To facilitate the measurements and calculations, the nuclides of Column 2 which can be produced in a fission reactor have been grouxd according to MPC value and type of radiation as sho.n in Figure 1-1. | ||
(1) | (1) | ||
The concentration of each of the 29 gamna emitting nuelides 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 de tec te d in the gamma scan, the MDA limit is computed from the measured data for that sample. | The concentration of each of the 29 gamna emitting nuelides 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 de tec te d in the gamma scan, the MDA limit is computed from the measured data for that sample. | ||
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TABLE 2-3 | TABLE 2-3 | ||
[. E. I. H at c h thc l e ar Pouer Pl ant SITE EFFLUENT AND HASTE DISPOSAL 5EMIANNUAL PEPORT 1978 l> | [. E. I. H at c h thc l e ar Pouer Pl ant SITE EFFLUENT AND HASTE DISPOSAL 5EMIANNUAL PEPORT 1978 l> | ||
GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE | GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE | ||
- l' CONTINUOU5 NODE EATCH MODE Nuc1 ides Re1eLied Unit Duarter Qu ar t e r Qu art e r Quarter 3 4 5 4 4 | - l' CONTINUOU5 NODE EATCH MODE Nuc1 ides Re1eLied Unit Duarter Qu ar t e r Qu art e r Quarter 3 4 5 4 4 | ||
| Line 1,047: | Line 1,043: | ||
1 (11) Tatal TW. Volu c Dishpd 221. x 3. 7C 5 x 10 ' c:l/ g t l .] | 1 (11) Tatal TW. Volu c Dishpd 221. x 3. 7C 5 x 10 ' c:l/ g t l .] | ||
f:al f | f:al f | ||
(12) 1:tal1:::.ityPi:cr..tr?..[(1)x(11)] UCi | (12) 1:tal1:::.ityPi:cr..tr?..[(1)x(11)] UCi (13) Ri.-:r fica U te (frc.a ill.F. 2.4-6) Cf3 | ||
(13) Ri.-:r fica U te (frc.a ill.F. 2.4-6) Cf3 | |||
{ | { | ||
(c. ,iletcc. L/ : UJte:. | (c. ,iletcc. L/ : UJte:. | ||
| Line 1,400: | Line 1,394: | ||
I gQul0 EFFLUENTS . , | I gQul0 EFFLUENTS . , | ||
1.1. PI . (.JRY LIMITS | 1.1. PI . (.JRY LIMITS | ||
: 1. The concentration of radioactive materials r#ca:,eo in - | : 1. The concentration of radioactive materials r#ca:,eo in - | ||
liquid waste ef fluents from all reactore at the site shall not . . : | liquid waste ef fluents from all reactore at the site shall not . . : | ||
| Line 1,499: | Line 1,492: | ||
.. s | .. s | ||
( . | ( . | ||
(5) ! | (5) ! | ||
i | i | ||
| Line 1,518: | Line 1,510: | ||
I?C R/,' ICE CN:'A-PAY BETA - | I?C R/,' ICE CN:'A-PAY BETA - | ||
/J.NIA - | /J.NIA - | ||
ElllTIERS ElllT T ECS (U Ct/.1) DtiTTFRS I-131.1-13?.!-123 Sr-89.Sr-90 1-135, Cs l? - (SeparatienandChs | ElllTIERS ElllT T ECS (U Ct/.1) DtiTTFRS I-131.1-13?.!-123 Sr-89.Sr-90 1-135, Cs l? - (SeparatienandChs | ||
-5 flos Coun:.ing) | -5 flos Coun:.ing) | ||
| Line 1,713: | Line 1,704: | ||
. ;. .rer W.C.' CFM/=1 Factor . | . ;. .rer W.C.' CFM/=1 Factor . | ||
. . . l H niter Alam Sa.t;cint (CFS) = (C x A x F) + B + 3/T * - | . . . l H niter Alam Sa.t;cint (CFS) = (C x A x F) + B + 3/T * - | ||
J' | J' | ||
. ,' Cccrosi te Liter Stered: | . ,' Cccrosi te Liter Stered: | ||
| Line 1,801: | Line 1,791: | ||
.[ | .[ | ||
1.13E-0" - | 1.13E-0" - | ||
c_ .__: _r_*.i s_ .e: licable_ _ 1_ 1_ti_i t_ _ _ . __._ . _ L. _ _t D. G'u;I hl pie E FadiOi!ti9it') | c_ .__: _r_*.i s_ .e: licable_ _ 1_ 1_ti_i t_ _ _ . __._ . _ L. _ _t D. G'u;I hl pie E FadiOi!ti9it') | ||
^ | ^ | ||
| Line 1,820: | Line 1,809: | ||
_a.m- 4- e i .cr :n .,, 3 * .: . one i iicr- ! . 41 t .: ' L. . _:_ __D_E__ e_ e_l | _a.m- 4- e i .cr :n .,, 3 * .: . one i iicr- ! . 41 t .: ' L. . _:_ __D_E__ e_ e_l | ||
* ,- .a. . , | * ,- .a. . , | ||
(12) | (12) | ||
| Line 1,841: | Line 1,829: | ||
2 GASEOUS EFFLUEtlTS 2.1. REGULATORY LIMITS. | 2 GASEOUS EFFLUEtlTS 2.1. REGULATORY LIMITS. | ||
: a. (1) The release rate limit of noble gases from the site, shall be; | : a. (1) The release rate limit of noble gases from the site, shall be; | ||
{ Q;. 3 1.9 Y + 1.0 TB + Qiv 11 Ey + 44 EB 1I i+n - | { Q;. 3 1.9 Y + 1.0 TB + Qiv 11 Ey + 44 EB 1I i+n - | ||
where Q 3 = Total release rate from main stack for both Units in Ci/sec (elevated release) ' | where Q 3 = Total release rate from main stack for both Units in Ci/sec (elevated release) ' | ||
| Line 1,886: | Line 1,873: | ||
alarm and to initiate the automatic closure of the waste ges i discharge valve prior to exceeding the limits specified ;n Section 2.1.3a above. The operability of the automatic isolation valve . | alarm and to initiate the automatic closure of the waste ges i discharge valve prior to exceeding the limits specified ;n Section 2.1.3a above. The operability of the automatic isolation valve . | ||
shall be demonstrated quarterly. . | shall be demonstrated quarterly. . | ||
: c. If the post-treatment offgas monitor is not operating, a shutdown -; | : c. 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. l 4 | shall be initiated so that the reactor will be in the hot shutdown condition within 10 hours. l 4 | ||
| Line 1,978: | Line 1,964: | ||
: 2. Aver age re1 ease r at e for period uCi/sec 7.19E-07 5.83E-06I | : 2. Aver age re1 ease r at e for period uCi/sec 7.19E-07 5.83E-06I | ||
?. of Technical spc c i fi c at i on l i ra i t . 2.82E-04 1. 5 4 E -- 0 5 ! | ?. of Technical spc c i fi c at i on l i ra i t . 2.82E-04 1. 5 4 E -- 0 5 ! | ||
C. Paa t i c u l at e s | C. Paa t i c u l at e s | ||
: 1. Part i c ul at e s with half-lives >9 dws Ci 4.41E-06I E.39E-06 I I . 0 0 E + 0[ | : 1. Part i c ul at e s with half-lives >9 dws Ci 4.41E-06I E.39E-06 I I . 0 0 E + 0[ | ||
| Line 2,008: | Line 1,993: | ||
TABLE 2-3 E. I. H at c h Huc l ear P c4> e r Plant UNIT 2 PFFLUENT RHD HASTE DISPOSAL 5FMIANNUAL REPORT 1978 GASEOUS EFFLUENT 5-GROUND-LEVEL RELEASE l t | TABLE 2-3 E. I. H at c h Huc l ear P c4> e r Plant UNIT 2 PFFLUENT RHD HASTE DISPOSAL 5FMIANNUAL REPORT 1978 GASEOUS EFFLUENT 5-GROUND-LEVEL RELEASE l t | ||
CONTINUGUS MODE EATCH NODE I huclices Peleazea Uni' Ou ar t e r Quarter Qu ar t e r Quarter j 3 4 3 4 | CONTINUGUS MODE EATCH NODE I huclices Peleazea Uni' Ou ar t e r Quarter Qu ar t e r Quarter j 3 4 3 4 | ||
: 1. F112icn g as e i re-1?' Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ur-0? Ci 0.00E+00 1.59E-01 0.00E+00 0.00E+00 M-1??M Ci 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 | : 1. F112icn g as e i re-1?' Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ur-0? Ci 0.00E+00 1.59E-01 0.00E+00 0.00E+00 M-1??M Ci 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 | ||
Revision as of 06:09, 22 February 2020
| ML19263C899 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/28/1979 |
| From: | Manry M GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML19263C896 | List: |
| References | |
| NUDOCS 7903120318 | |
| Download: ML19263C899 (87) | |
Text
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,t: ,e c:n nk Edwin 1. Hatch Nuclear Plant
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February 28, 1079 PM-79-210 x ._ PLANT E. I. HATCH Semi-Annual Report Director, Office of Inspection & Enforcement 5 Distribution Services Branch, DDC, ADM . U.S. Nuclear Regulatory Commission Washington, D.C. 20555 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, 1978 through December 31, 1978.
-O kN. Manry Y'
Plant Manager WHR/cd s 790312036e
GEORGIA POWER COMPANY PLANT E. I. HATCH UNITS NO. 1& 2 SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JULY 1, 1978 - DECEMBER 31, 1978
. PLAfiT E. I . IIATC11 SEP.IAtitiUAL REPORT PLNIT RADIOACTIVE EFFLUEtiT RELEASES
~
SECTIO:1 TITLE PAGE
.1. LIQUID EFFLUEf!TS . 1 1.1 REGULdTORYLIMITS 1
. . s. -
# MAXIMUM PERMISSIBLE C0:1CEtiTRATIO:15 1.2 1 1.3 MEASUREF.Ef!TS AtiD APPROXIMAT10 iS OF .
TOTAL RADI0 ACTIVITY 4 1.4 BATCli RELEASES 6 2 GASEOUS ""n UEriT 19 2.1 REGULATORY LIMITS , 19 2.2 MEASUREMEllTS AliD APPR0XIfMTIO:15 0F
. TOTAL RADIOACTIVITY -
21 2.3 GASEOUS EFFLUEliT RELEASE DATA 25 3 g SOLID 1.!ASTE 25
, 3.1 -
REGULATORY SPECIFICATI0!iS 25 SOLID l!ASTE DATA 25 3.2s . ej - O g . i 4 1
. t e
f
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' ?' . - . - - . . . . - .
PLAtlT E. I. IIATCil SE!!!ANI;UAL REPORT -
~
. PLAtlT RADI0 ACTIVE EFFLUENT RELEASES LIST OF FIGURES .
FIGURE , PAGE 1-1 ' METil0DS OF MEETING TABLE II COLU:Cl ? MPC LIMITS (10 CFP,20) 7 1-2a, b LIQUID RAD'IASTE ANALYSIS - UNIT I 8, 9 l-3a,'b 10, 11 L QUID RADWASTE AfiALYSIS - UNIT II 12 1 LIQUID RADWASTE DISCHARGE PERMIT 1-Sa, b 13, 14 LIQUID RADUASTE DATA COMPILATIOt i LIST OF TABLES TABLE' PAGE 1-1 EFFLUEitT AND WASTE DISPOSAL SEMI- ' A!!NUAL REPORT, LIQUID EFFLUEi;TS-SUMIMTIOil 0F ALL RELEASEF 15, 16 1-2 , EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT, LIQUID EFFLl'dNTS-
*, - 17, 18
. BATCH CULY ,
2-1 EFFLUEtlT AND WASTE DISPOSAL S.Ei!I- . ANT!UAL REPORT, GASEQUS EFFLUENT-
*
- 26 SUM:GTIO:t 0F ALL RELEASES 2 ,
$FFLUENT AND WASTE ' DISPOSAL' SEMI- ,
ANNUAL REPORT, GASE0US EFFLUENTS- - 27 ELEVATED RELEASc 2-3 EFFLUEllT AMD WASTE DISPOSAL SEMI-
- AttriUAL REPORT,- GASEQUS EFFLUEf!TS-28
- GROUND LEVEL RELEASES .
3-1 - EFFLU.31T A'ID WASTE DISPOSAL SEMI-
- ANNUAL REPORT, SOLID WASTE AND IRRADIATED FUEL SHIPMEilTS 2f, 30 O
e e
- 4
- e O
e
. e 4 0
'l t.il' RADIOnCTIVE EFI LUEUT R.M.'ASES 1 QQUIDLffLUENTS .
1.1. REGULA10RY LIMITS
- 1. The concentration of radioactive caterials released in liquid wastes from all reactors at the site shall net exceed the values specified in 10 CFR Part 20, Appendix 0, Table 11, Colua.n 2, for unrestricted area.
- 2. The release rate of radioactive materials in liquid wastes, excluding tritium and dissolved gases, shall not exceed 10 Ci/ reactor / calendar quarter.
- 3. The release rate of radioactive materials in liquid wastes, -
excluding tritium and dissol','ed 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 closur.e of the waste discharga 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 demonst-rated qu1rterly.
- 6. The equipment installed in the liquid radioactive waste system shall be maintained and shall be oparated to process radioactive liquid wastes prior to their discharge when the projected cumulative release rate w~ill excced 1.25 Ci/ reactor /
. calendar quarter, excluding tritium and dissolved gases.
- 7. The makimum radicactivity to be contained in any liquid radwaste t. ink that can be discharged directly to the environs shall not exceed 10 Ci, excluding tritium and dissolved gases. , .
8.' When the release' rate of radioactiYe materials in liquid wastes, excluding tritium and dissolved gases, exceeds 2.5 Ci/ reactor / calendar quarter, the licensee shall maPe an in-vestigation to identify the causes of such release rates, define and initiate a program of action to reduce such release rates to the design objective levels end report these actions to the Conaission within 30 days from the end of the quarter during which the release occurred. l.2. l'AXIMUM PERMISSIBLE CONCENTRATI0"5 The IIPC values used in.deternining allowable liquid radwaste release concentrations are taken frem 10 CFR Part 20, Appendix 8. Table II, Colua.n 2. Release rate and dilution ratio for each batch are de-ternined by a mixed nuclide W C calculation cerfonned before the re . lease of the batch. To facilitate the measurements and calculations, the nuclides of Column 2 which can be produced in a fission reactor have been grouxd according to MPC value and type of radiation as sho.n in Figure 1-1. (1)
The concentration of each of the 29 gamna emitting nuelides 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 de tec te d in the gamma scan, the MDA limit is computed from the measured data for that sample. Only two pure beta emitters, Sr-89 and Sr-90, have MPC values less than 9X 10-6 uCi/ml. Individual measurements are made the on proportional composite liquid radwaste samples to determine Sr-89 and Sr-90 concentration or MDA value to be applied to individual batch release calculations. Although the MPC limit for tritium is greater than 9 X 10 - 6, a separate measurement is made for tritium since the gross beta technique does not provide an acceptable tritium measurement. A distilation and liquid scintillation counting technique is used to measure tritium concentration. The maximum activity of gamma and beta emitting nuclides with MPC values greater than 9X 10-6 uCi/ml, except for the 29 nuclides noted above, is determined by gross gamma and gross beta Measurement sensitivity limits of approximately 2 measurements. cpm /ml allow a null measurement to shou that the sum E (Ci/MPCi), is less than 0.1 for gamma and beta nuclides not measured directly. The sum of the ration, I (Ci/MPCi), for alpha emitters can be shown to be less than 0.1 by a null measurement with a sensitivity limit of approximately 1 X 10 - 2 cpm /ml. Cas flow counting is used to achieve the required sensitivity of measurement. Thus, except for ra d ionu c li de s produced in negligible quantities in a fission reaction (eg. I-125, I-129 etc.), the methods outlined above provide a means to assign a quantitatively measured or MDA value to all nuclides in Column 2. These measured and calc 21ated concentration values for each batch are used to calculate the dilution ratio, release rate, and dilution rate. prior to release of each batch. Both the concentration and release data are stored on a computer disc file. The disc file data is used to assure that quarterly and annual release limits are not exceeded. Bases used for the data of Table 1-1 are as follows: A. Fission and activation produc ts - The total release values (not including tritium, gases, alpha) are comprised of the sum of the individual ra d ionuc li de 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 Envircnmental Tech Specs. This num is for each batch 9 released to the river for the of applicab1" limit 1: determinod ^ n t 7 respactive "t quarter.
' <ed nuefide Pareent
'fPC r o ,- .i11 n:l e ' '<-
caluulation. T! e a v e r:t r e c o ri e , ri t r - *ini (2)
summed over all batches is divided by the corresponding individual MPC value. The sum over all nuclides of the Ci/MPCi ra t i on times 100 in 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 uct/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 offluents are measured on each batch by Ge(Li) spectroscopy on a one liter sample from each liquid radwaste batch. Dissolved and entrained gases for which neasured or MDA concentrations are determined include nobic 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 analysis for each batch, there fore 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 10 - 5 uC1/ml of each dissolved and entrained radionuclide as specified in Regulatory Guide 1.21, has been applied in determining the percent of applicalbo limit. D. Alpha measurements are taken monthly from the Liquid Radvaste composite. A study was instituted in July to determine if the ratio method, as described in the E.T.S. Table 2.1 ' footnote e could meet the LLD of 10% of the MPC value spectfled in 10 CFR part 20 Appendix B, Table II, Column 2. The lim!t of 3X 10-9 uCi/mi was never excecced tiuring the study. Below is a summary of the study findings. _ _ _ _ _ P.M IO_ PR t1CJ tiOO_ _ __ _ __ --LRW - ------------- r ~01FCC L t?CMUEE'".2iLt%ItfJ0. PRIMARY !t1ARY LRW- - - - - LRW COULNJT COCL/NT COMPO91TC CRO'iG ALPHA CO-Co CROSS ALPHA CO-Co N.PHA
.. t10m t L __ _ UN I L_ _. _lut u ell ____. _ _iu t uull _Iuc dm1L__ . __Iuti be1 L __ iu t1611_ __ ____.______
N.Y hL__ _ L _ __ _ _ 2.13_C:h____ __2dC_C:S____. _S.92_C:7_____ __CJ3 2-10__ I.22 C 9___.___ _ AL" _7ti. __ __1__ _. _1.70 1:d____ __1. 05_C: 10__ _. 1.EL C:C _ ____ _ _1.::9_C:12 .. _ S.S.32:1 L _ LCt!L /d___ __L____ _1.lL E:S__ _ _C.71C:2____ _ L C LC :7_ ___ . ._2. ? L C: '.C_ _ _1.1. _ C :10. . _ _ ___ _ _ . _ _ _ _ . QC L.1_. _ __L___..- _ l d LE: S___._ ._. 3 . 00_ C : 10. .__ _2.0 LC:7_ _ _ _. . S d S. E 13._ _1 / L C : 19_. _ ___ _ _ _ _ _ __ _ _ . NOL I S __._ _ .._1_____ _1 dC_ C:1__.._ _S dO I:0_ _ _2.05 C:L_ _. __L.07_C:lL _ _3.11 C 10_______ __ DCC_7d____ __1- . _1. L ol: L ___ . _!I.91 C:10___ _d.2.22:7 Id!LC:la__ 7d05:1 L .._ ________ J6N 73____ __L___._ _C.30_C:A____ .__5.21C:10___ _2. 3 2_C : L ___. ._C . 21C:13 _ _ U JLC:10 _._ _ J UL._7 d _ . ._ Ad35:10_ AC.0 L E:0__ _. __1. 711:1L_ . 3 . to. E r _ .. _ _ _ _ _. _ .. _ _ _. AUG 78.___ .d___.__b_.Ld0.C:L___ _C____ J . 021 C _ ..__2.011:11 _ _ U d 3.. C: L... .
._ U , 3 L C l a _ 3 . E I. C - 10_ _. _ __. _ _ . _ _ _ _ _ .
'lt!L 7 L._ _ _ . d .. _ _ _ h ? d '.' _ C : 7.' _ _ ~ 1. t LC . _ .l. E . C:7. ____ I' . ' . F : U.c . _ '.1.u.F-!Q._..___ _ _ . _ . . _ _ T Lid. . _ .d..___ h .c.2L k t..___ _...LO_L: 11_ . ._L.27 C-7____._ l . 2 . l: 1 C. . .3._:;1._._..____._.._. CL 7 U __._ _ IdC_C:b!_ _t.__S.Ub l:2__ . d . 39. C . L__ _. _ LIS .E:1L_ ...d. E1..E: 10 ._ _...__ .... ___. . CC_7B____ __d_____4'_d.53 1:5 _. .L__L.123 ' __C_____J U____ ._L1111:0__ l .ML C:10.. _ . 9. ? L C : l C - ..__ _ _ _ _ . . _ _ _ _ _. NJ .ie. _ _..__ _ . . c.L _._ _ 1d uk C: t _ _ _ _ L _ J. 9 ? _ f.210.- . . LCL C:U. _. . _3. F.' l: 13 . L.tJ 1:10. . _ _ . _ . . . _ . . . _ _ .
- "a-(unc i.r.t m.t.a h o t!o no usoim er i n i +i t i t.c t. o i t tuan n af Ilia s .tolv .s usa t t!., r .i l io m. i t -i +, ,.itot.:i.ic a : r!. 's. ;i 3 in l i <;o n d e .e u e s t o ,wlea as at le.t e io a v e l m. t lu 3! dat - i m .a dii? 1e6 ealle><l.
(J
- 1. 3 MEASUR EME!!TS A!!D APPROXIM ATIO!!S OF TOTAL R ADIO ACTIVITY.
Details of the analytical procedures for liquid radwaste analysis are contained in operating procedure IU!P-7601. The following measurements are performed as indicated: ME A SU R EMC:!T FR EQlIE!!CY METHOD
- 1. Ganna Isotopic Each Batch Ge(Li) spectronotry with on-line computer.
- 2. Gross Gamma Each Batch 2X 2 flaI well crystal counting 3 Gross Beta Each Batch Gas flow proportional counting
- 4. Sr-89 Monthly Chemical separation and composite gas flow proportional counting
- 5. Sr-90 Monthly 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 on-line computer (4)
If a liquid raduaste tank cannot be reprocef.[ed, a san.nle for analysis is taken from the tank af ter the required recirculation t irse. The sample is used for ganm-ray spectroscopy, gross ganna and gro',s beta counting, and for preparat icn of a co:.;sosite sample. lhe Ge(Li) detector systems censist of a 10", and two 15% efficiency, 2.0 FUllM resolution detectors in <i-inch thick lead shields. A one-liter raddaste liquid sanale is solidified in a furinelli beaker in prepa-ration f or a 20000000 second Ge(Li) count. A peak search of the resulting gar.na ray spectrum is performed by the on-line cc:rputer systen. Energy and net count data for all significant peaks are Je-termined, and quantitative reduction or MDA calculations are performed for the nuclidos listed in figure 1-1. lhe quantitative calcula-tions inclu& correcticas for counting tina, decay time, sample volume, sample gcometry, detector efficienc.y, baseline counts, and branching ratio. l'DA calculations, including the above corrections, are made ba',ed on the counts in two standard deviations of the baseline count at the location on the spectrum t;here a peak for that nuclide would be located if present. The calculated radionuclide concentrations or MDA values from the gamma scan an:I fro::1 previously s tored Sr-89 and Sr-90 values are used to calculate the dilution ratio t (Ci/MPCi) and allowable release parameters. A sarcple printout is shcain in figures 1-2 and 1-3. The Liquid Radaaste Discharge Permit Printout is transferred item by item to the first portion cf the release pernit (Figure 1 o.) by a laboratory technician. Although the computer could printout the release permit and vill inform the technician if a batch cannot be discharged as desired, a manual transfer of calculated res ults to the release permit by the technician was implemented as moce likely to catch abnermal conditions in the data: The liquid rantaste monitor setting is calculated by the computer based on the gross gama activity es mecsure.d in the sarrple used for laboratory analysis. A coefficient hts been determined which relatcs laboratory gress gam.ca counts to the monitor count rate. If the msnitor count rate e:'ceeds the calculated setting' during discharce, then the liquid possing through the monitor is not Pepresentative of the sanple which was analyzed in the lab. A monitor reading in excess of the cal-culated setpoint therefore results in an culcactic termination of the liquid ef fluent discharge. Liquid effluent discharge is also auto-matically terminated if the dilution flow rete falls belove the flow rate used in the computer calculation. When the release peruit is returned from Rydaaste Operations following discharge, the discharge data is cambined vith the analysis results on the computer disc file. The disc file may be scanned to display trends in any recorded parameter, or my be summed for reparting purposes as shown in Figure 1-5. O m ,
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 computer data reduc tion using the Liquid Radwaste Library which includes gases. Several comments are indicative of the success of the HNP liquid radwaste prog"am during this reporting period:
- 1. The total measured activity released in liquid e f fluen t for both Units was 7.34 E-3 curie for the third quarter and 1.51 E-2 curie for the fourth quarter. These alues were approximately 1/1430 for Unit 1 and 1/2832 for unit 2 for the third quarter and 1/1280 for Unit 1 and 1/1381 for Unit 2 for the fourth quarter of the allowed 10 curies per quarter per reactor.
- 2. The ra d wa s t e releast procedure strongly emphasized reprocessing rather than discharge of liquid radwaste.
During this report period only ?4.h% of the Itquid radwaste reaching the sample tanks was discharged; 75.6% was recycled back into both of the reactor water systems. 3 A complete isotopic scan, gross beta, and gross gamma counts and ceaputer analysis were performed prior to the release of each of the 566 discharge batches for both Units. 1.4 BATCH RELEASES Regulator" Guide 1.21 Tables 2A and 2B are found in this report as Table 1-1 and 1-2. Data is presented on a quarterly basis as per Regulatory Guide 1.21. If it is requested, a monthly tabulation will be submitted. Other data pertinent to batch releases of radioactive effluent from both units is as follows: Number of batch releases: 566 Total time period for releases: 66875 minutes Maximum time period for a batch release: 227 mi nu te s Average time period for batch release: 121 minutes Minimum time period for a batch release: 18 mi nu tes Average stream flow during periods of release of effluent into a flowing stream: 3705 CFS (6)
r 1igure 1-1 , . 3 ffGURE l-l' !;F_il:0:15 CF !ECTII;G ilmLE II . CCLL'Fli 2 ITC L!!!!TS
' ITC U.';GE Cfd Wi-RAY [iETA -
/.L NI A .
El!IT TE P.S CtilIl tr.S _(l1Ci/::1)_ rit!TTFnS I-131.1-137.!-133 Sr-09.Sr-00
,g _1 -135, Cs 13 * - (Separction and b s
<9 X 10 flow Counting)
(C0(Li)Canaa-Ray Spc:trcsc3py) /.LL
, -(G a s Fl c.u Co.:n t in g .
Sensit vity 0.01
~ C Pli'... i )
fla- t a -l C .'le-? d .Cu-6 4 Tritium .
,00-63,Fe-59.7n-65 (Distillction a.d
. Lic;uid Scintil-
> 9 X 10-0 Ag-i l 0- , I'n - Dt . Co-58 lation Counting) 7r-!!b-S5, Cs-P,a -137
./.s-76. F-18. Cr-51 /.11 others .
!!f-239, C9-141 (Cr.s fica Counting .
Sensitivity s2 - 11-Tc-99. Ce-Pr-ld4 CHt/ct) ( Ge(Li) Gacma-Ray . .
. . Spectrostcpy) ,
/.11 others :
(Gress Camm '.lcll t- - Counter; scr.sitivity .
*.5 CT @.;l.) .
. 4.
e
, = e h 8 e
- a. . .
. O .
, .te e * .
e
'e g
. , g .
(7) .
FIGURE l-2a FFOCLLUkE: HUF -7601 FEVISION: 5 F06 h3 1 A i d+44+++,*++,*++++,+*4++1k.44Mt++.5++++44+++{+++
- E. 1. H at c h 14uc l e ar P l s[lt *
- Liquid F sdv as t e Ar.alys t e ! + ~.
***+4++++++#,+++.+4.s+44+,1.c,.**,+++****+*-**
Pe sc t ort 1 Batch # 430 Tan 11 CW5T9 Oper at or : JDA Co6 Lent: HIGH EVERYTHING - P.4n d at e: 10<25/73 1549 Count start dat e f 10/25/75 1407 Sample vo l u n.c ' 1000. 0 ~. mi Clock tion: 3000 secs Geometry code: 1LHE-0 Live tioc: 3000 secs - lie t e c t or # 3 NCAN 3 ' L i br ar y: LFhlI2 - Ene r gy ( k e v') = .57 + 1. 0 0 0+ C h b + 0.000E+00*Cht^2 + 0.000E+00*Ch#^3 : 10/25/78 0136
.. *d Eff = 1/[6.669E-03
- E^(-3.1278E+00) + 212.484
- E'(9.1062E-01>3 : 10/01/i? 06?6 ubert E*= Energ" in NeV.
150l0FE i EUFRGY CONCENTRATION ERFOR NPC C/MPC (kcV) (uCi/ml) (uCi/ml) (uCi/m1)
== ====.,&=====2==-e============ ===------===============---- ===========.,======-
Ce-144 133.54 (9.,733E-08 1E-05 (9.73E-03 T c -9 9.. ' 140.50 <1.203E-09 3E-0? <4.0?E-06 , Ce-141 -. 145.4_0 <2.330E-08 ~ 9E-05 <2.59E-04 Hp-239 + 27'.60 <1.169E-07 - IF-04 < 1. '17E- 0 3 Cr-51 s 320.26 3.800E-06 1. 8 7'2 E- 0 7 2C-03 1.90E-03 l I-131 i 564.50 <1.707E-03 3E-07 <5.96C-02 - i 2n-69tn 435.50 (1.545E-05 ' 6E-05 <2.5?E-04 ' H-107 479.50 <5.994E-0C 6E 49.99E-04 F-18 511.07 <6.243E-00 . 5E-04 <1.27E-04 1-133 529.50 <1.562E-03 1E-06 <1.06E-02 Es-140 537.40 s7.409E-08 2E-05 <3.'OE-03 As-76 559.10 <4.035E-08 2E-05 (2.02E-03 Cs-154 605.10 6.710E-03 1.558E-03 9E-06 7.46E-03 Cs-137 661.99 1.870E-07 2.628E-03 2E-05 9.35E-03
. Ma-99 739.70 <!.319E-07 -
4E-05 <3.?0E-03 2r-97 743.*O (2.061E-0? 2E-05 <1.03E-03 2r-95 756.87 <3.540E-0? CE-05 <5.50E Ht-95 766.06 7.932E-00 1.601E-08 IE-04 7.93E-04 I-132 772.60 (1.734E-08 _ 6E-06 <2.17E-03 Co-50 810.76 3.133E-07 2.942E-03 9E-05 3.70E-03 Hn-54 E34.?8 1.643E-07 2.e04E-OS 1E-04 1.64E-03 A;-110u 354.70 <3.440E-OP 3E-05 <1.15E-03 2n-65 _1115.63 1.685E-06 9.2SEE-03 1E-04 1.69E-02 1-135 1260.50 < 2. 3 M E-03 4E-06 (5.95E Fe 59 1291.50 (4.15SE-03 6E-05 (6.98E-04 Co-60 1332.53 1.093C-06 5.321E-69 3E-65 3.61E-02 Cu-64 1345.80 s1.703E-06 2E-04 <8.51E-03 9 Ha-24 Lk-140 Mn-56 1362.*5 15 %;.60 1011.20
<!.0i?E-00
<S.561E-09 (2.70;E-OS 3E-05 2E-05 1E-04
<4.*6E-04
-( 4. 2SE-? 4
<2.70E-04 I
Se-8) (1E16) 1.510E-03 4.310E-09 3E.-06 5.0?C-03 Se-90 (EETH) <?.190E-09 3E-07 s2.40E-02 Ne uured t ot al, . 7.415E-06 2.221F-0T L 7.85E-02 , LLD tceals <2.604E-Or <1.45E-01 ! int al s 1.00lE-A" 2.24E-01 l ,
FIGURE l-2b Ll??0LVED CABES
- Xi-13? 60.93 <2.7{2E-08 4E-u5 <(.r0E-04 Vr -38 196.10 s2.595E-03 4E-05 *
(6.49E-04 X e - 13 3 a. 237.13 (i./26E-07 4E-05 < 3. 31 E-03 Xe-135 249.60 (1.422E-03 4E-05 (3.55E-04 ). . Vr-85m 305.00 <S.663E-09 * 'E-05 (2.17E-03 D- - G 7 402.70 (1.255E-OS - 4E-03 <3. 1E Xs-139 434.40 <1.487E-09 4E-0* <3.72E-05 Ma .s a urc d g as t ot al s 0.000E+00 0.000E+00 0 0.00E*00 LLD gas t ot al s <3.010E-07 (7.55E-03 j Tot al g as 9.011E-07 7.53E-03 GPUSS ACTIvlTY Counter Grcas Eackground T i nie vol Het Cerce Counta Counts ( fl i n ) 't1 Acti >i t p( c pe ' ra l ) 1 C i ;ra g He11 Crystal 1731 1570 20.0 2e p 4.0?E+00 1.44E+00 Frcportional- 213 200 10.0 2 6.50E-01 1.0ZE+00 EST! MATED UA5TE T AW YCLUME= 6f6?.00 g ;l l o n's
~
E3TIMATED ACTIv!TY THIs EATCH= 1.84E-04 Curies ( 1.54E+02 fli c r oc ur i + 3 ) i CUARTERLY ACTIVITY FELEASED THFOUGH THIS I'P T C H (Ci>= 2.10E-03 PERCENT CF TECd SPEC LIllIT
- 2.10E-02 12 MONTH AC T 1I TY FELES?ED THPOUGH THIS FATCH (Cf)= 1.57E-02 FEFCEHT CF TECH 5FEC LItt!T = ?.66E-02 THE ACT!v!TY OF THI? EATCH IS 184.42 UCURIES THE IW4 I MU:t YOU LANT TO FELEASE !5 !00 uCi T -iE F E F O R E YOU " eel. (0Uf SUPEEVIiOR TO OM THIS RELEA?E i
+
L ud Psdoiste y celess. Sum r.
- r "
'litteam. r eic-nuclide conc., xc l udi r.g g as e s ( u C i < ta l ) : 7.42E-CZ +- 2.22E-07 2)C hic u14t e d LLD c enc e nt r-at s on, exc luding d' $ 2 cive d g u es cuC*cnt): 2.iOE Oi 2
3 'C-I cui at t c dilut ion r s' i o ' C.'l1PC e i e u.* t LD. inc luding q u e s ): 2.31E-01 4 Minir..um d i l u t t o r, fleu r at e ( Gi n. ) : 10000 5 Hi s < i r u si t ard di s ch ar ge (Icw r s t ii 2 (gr%' 21855 6 i t'a c i f i e d ' v.L flou r at e ( g p s. * : 75 7 ) P 19 u t e m:nitcr trip sitting: 427 6 , 4.2. , ,: e l l e c,un t C F rt '%1 I = 320 . t;c r i ; ' c-r IG Cf5 r t: t o, C = i.(; , ttoni t or CF3 per W.C. CN1 m1 F e. 2 . y: .- 3,c. S Estitated :cn . of *,.i u . nuclides l' rcini ci rile hr e s%C' .1 * " 5 iE-0' IATChe 400 Isin :.00.E:if0LLY STOFED .
<--ten
- e . . . ,eru ,,, f ,}
~
FIGURE l-3a Pli C C E DUPE : HNP-7601 F E V I S,I sm : 5_ F OPN it 1 E. I. Iiat c h fluc I e ar F1 ant i Liquid F adi.r as t . Analysis I i Re ac t or # 2 Esech# 237 ; Th 4: LH3TE-2 Operhtor: AC ' C on.m e rit : 4:GH FIL SCL Run d at e : 9 -10'?s P" Cour.t start date: 9/10.'70 S amp l e "close: 1000.00 r.1 0550 Ge c t.e t r y coce: 1LHF-0 Clect tive: 3000.zect ' Litector# 1 Live t i r. e : 3000 me:4 , MCA> 1 L i tsr ary: LFhLE2 Energp(lev) =
.90 + .999 + Ch# + 0 + Ch#'2 + 0 + Ch#^3 90978 Eff = -9 1/IS.673E-03 < E^(-3.4731E+001 +
413.405 + E^(9.4372E-01)J 80676 where E = Energy in NsV. ISOTOPE , ENEPGY CONCENTFATION ERPOR MPC C/MFC G eV) ( u C i / n.1 ) <uCi/%1)
=============== es==,===u========n===c=====_========<ocieml)
=========u,=============
1 Ce-144 - 153.54 <i.287E-07 Te-99u. 1E-05 <2.29E-02 140.50 <2.604E-08 3E-03 <8.68E-06 Cc-141 145.40 ' < 5. ~3 7 5 E - 0 3 Hp-239
- 9E-05 <5.97E-04 277.60 <2.356E-07 IE-04 < 2. 3 t:E-0 3 Cr 51 320.10 <2.72SE-07 2E-03 j
1-131 (1.35E-04 ' 364.50 43.402E-00 3E-07 <1.13E-01 2n-698 415-50 (2.629E-05 H-107 6E-05 <4.33E-04 479.50 <9.813E-03 6E-05 <1.64E-03 F-18 511.00 < 3. 854E-09 1-133 5E-04 (7.71E-05 529.50 (3.030E-00 L a- 14 0 1E-06 (3.03E-02 537.40 <1.257E-07 2E-05 <6.23E-03 02-76 559.10 <5.168E-08 C3-134 2E-05 <2.58E-03 604.70 (3.159E-03 9E-06 <3.51E-03 ! C's - 13 7 661.64 <3.056E-03 Mo-99 734.70 2E-us (1.53E-03 t l
<2.252E-07 4d-05 (5.63E-03 2r-97 742,50 l
<2.454E-05 2E-05 <1.49E-03 2r-95 756.39 1.000E-07 3.238E-08 6E-05 Hb-95 765.84 1.67E-03 I (3.064E-08 1E-04 <3.0iE-04 I-132 772.60 <2.656E-03 8E-06 Co-53 810.60 < 3. 02E-0 3
<1.613E-03 9E-05 <1.79E-04 Ho-54 C34.60 <3.113E-03 A p l 10n. $?J.'O 1E-04 <3.11E-0J
<3.191E-05 3E-05 -<l.06E-03 2n-65 1115-50 <7.256E-05 I-135 1260.50 1E-04 <?.2EE-04 (G.02iE-03 4E-06 (2.01E-02 Fe-59 1291.53 <7.565E-08 Co-60 6E-05 <1.31E-03 1332.49 c?.935E-08 SE-05 Cu-64 1345,30 <1.31E-93
<4.371E-Oi 2E-04 <2.19r-02 Ha-24 126.i,55 <1.595E-AS 3E-05 s5.10E-04 La-140 15 % .60 (2.750E-0E 2E-05 Hn-Si 1811.20 < 1. 30E-0 3 (3.404E-03 1E-04 s?.40E-04 Sr - G .a (IETA) 56.990E-09 Sr-90 ( f.E 10 3E-06 '.2.33E-02
. . - - . - . - . ~ - - . I.41LE-09 2.050E-09 3E-07 4.70E-02 Hessured '..tgli 1.141E-07 ?.24JE-0? LLD t ot st 3 s6.400E-06
. 2.45E-02 Tot al s
* <2.4EE-01 6.514r-n6
? ??E-01 (1A% <
FIGURE l-3b DI:?OLVED GA0ES Xe-133 CO.99 <?.032E-OC 4E-05 <1.7(E-03 IV-G8 196.10 J5.011E-03 4E-05 <1.25E-03
;4-133N 233.10 < I . 4 0:. C-0 7 4E-05 <i.OIE-03 M4 -- 135 249.(0 <2.670E-0; 4E-05 c6.6.9E-04 it-d5u 005.00 <1.550E-07 4E-05 :3.?GE-03 If-87 404.70 't.060E-03 4E-05 c4.65E-04 de-138 414.40 <7.370E-10 4E-05 '1.?4E-0" Mr a s ur < d 9u t o t a l s. 0.000E*00 0.000E+00 e.00E+00 LLD gas ' c. i a l s <5.623E-07 <1.41E-02 Tot al g hs 5.623C-07 1.41E-02 GF051 6CTIVITY ,
Cour.t er Gross tsciground T i m.e Vol , IIs t Err:r Ccanti Counts t ri ) re.1 fsc t t v i t M c p ..--S il ) 1 Signa
!!c 11 Cepstai 2040 1619 20.0 2 5.53E+00 1.55E+00 Proportior.sl 181 146 10.0 2 1.75E+00 9.04E-ul ES r!r1 ATED t:A5TE 76tF VOLI."iE = 5? 61. 00 gallons E L T IM A T E D r.C T I VI T'. THIS IATCH= 2.53E-Of Curie 2 ( 2. *' 3E ,0 0 ti i c r .,c u r v e s )
OUM:T E PLY 6C T I V I T'e FELE65ED THFOL'CH T H I '. EP'CH (C1)= I.i2E-04 PEPCENT OF TECH SPEC Lis11r = 2.!IE-03 12 f tCr17ti AC T IVI TY PELEfiSEI THP00GH lHIS BATCH ( C i .a = 2.52E-04 F E F.C Erli 0F TECH 5FEC L Ii1I l = :.?!E-03 Liquid Rad.. oste tele as e su.c a sr y 1,3 ?' 4 h i , r sd i o-r.uc l i de ccn:.. ( cludirig g3542 Cuci/mle: 1.14E-07 +- 3.21E-08 2 TC alcu1 st e d LLD conc ent r at ion, < > c t vJ i r.g d i s s o l ve d gs2e1 .ut'.ui): 6.40E-Oi 3 K 11 c u l at e d d i l ut i c.n rat t o (C 11F C of r., a s . 0 L LI', i nc l ud t ng g ia e a . . 2.5C2-01 4 S f16 e r i si oc. dilut i on clou t st e (gr ..: 10000 Snits /i vs t snt di sch ar ge riou rat e 2 ( g p ra ) : 17630 t- ) S p e .: s f i e d t Snt f l oes este ( g p rd : 75
;'
- P g F.e 4 3 v g- n. .n i t o r trip 5ctting: 64 0 s ".51 . ife l l count CDrl/s I 1 = 7 . Mori s t c r IG CP3 C = 4. 4 ? .f teni t or CPC per it. C. C N1 ml F = 2 .Constem. Factor O '. E ' t r. i s .i d c c.n c . .i r.. i s . n t : 1 1.* 41 3' p. . i n ' cf relt st < ' 's C i
. . ..I*. 0.4.".E *0 16TCH4 ?t? DA16 ONCE9c.rOLLY ST0F E D G
FIGl'RE l-4 CATCH NO.
~FC;;i 1 FtANT T C !nTCH 0:gg y j QQU10 Efin ;31E bhCHAf 5E PENIT TIM. TO EE T.ElEMED DATE / / -
REA50!i FOR r.ECE33!TYTOILCW.';L RECIF.C. ST;RT II.ME 5;;th E lime TiG~C. LW.i R:, ' nDiT I. L/JCPATORY ifALYSIS (1) M:asured Radicr.cclide Ccnccntratica E ti E uti/n1 (2) C11culated CA Lir.it Ccnccntrations .:C1/nl (3) CalculatN Diluti ,n P.atic: I(Ci/niC1) . (4) !!!ni.~en Oilutic . Flcw Rate GPM (5) Calcula cd Tank Discharge P. ate: (4T7T3 ) - I cP:t (6) EpNified Pax. Tank Disch:rg.2 T.cte: <(5)/2 GEM (7) F.cdeaste Menitor Trip 5ettin;: CPS A = L' ell Ccunt CPM /nl
- E = Monitor E3 CPS C = Meniter CPS F = Cor.scrvative
.per L'.C. CM/r.1 Factcr
. Monitor Alam Set;:: int (CFS) = (C x A x F) + 0 + 3fs-Congosite Liter Stored: e cocp eted By: Date:
. Inittels)
- 11. OFEFATIONS (8) Lir,uid Rad 6:nte Monitor Trip Set at: CPS
* (9) Ccnfin:cd Cllutico Fimt hte GPM (10) Valve Lincup Ct.ecked as Fcr CP- .
iank D i s . F.a t e Dil. ictal'P.Y n r ii. Y: .ite Date Tfv ? tc . e l . Irrter
"- l~u515.M i.c..
- 3 GM - G l. ft. O .a.s.I mm m._. m m =_m_
start . Fnd "
~
turauen .9"- Cal- Ccc.pfete:: sy:
~Tc T Date:
*0 10 r;in. after start
**Afte- flushiao 11!_ LAEO 'ATORY i (11) Total Tenk Voice Discur;cd .3a1. s 3.725 x 10' cl/g31.] ml (12) Tatti /ctivity Oisr.iry ; [(1) > (II)} ~ uti (13) Ris :r Fica r:a te (f rc a hl'12.4-6) , CFS
, 1
- y ./ 5
-me smma m h
F.'. '- 1 7 i l
.,. i , n .~ a . ,4 4 1-t 6
- 3 i (12) * '
FIGURE l-5 a. L i qui c Radu ast e Dat a Cernp i l at i on for Reg. Guids 1.21 Rsport E. I. Hat c h Nuc l ear Plant UNIT 1 Total Activity (Curies) Ou ar t er 3, 1978 Ouarter 4, 1978 F at c he s 317 thru 404 Fatches 405 thru 496 H au e Measured Error High LLDs Tot al Messured Error High LLDs Tot al Cc-144 Tc-99w 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Np-229 1.19E-06 3.76E-07 0.00E+00 1.19E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 6.00E-e5 3.90E-06 0.00E+00 6.00E-05 1.42E-03 3.03E-05 0.00E+00 1.42E-03 2n-69w 3.10E-06 9.14E-07 0.00E+00 3.10E-06 4.88E-04 6.87E-06 0.00E+00 4.8SE-04 W-187 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-18 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-133 5.70E-04 6.01E-06 0.00E+00 5.70E-04 0.50E-05 4.57E-06 0.00E+00 8.50E-05 Ba-140 7.62E-06 1.?1E-06 0.00E+00 7.62E-06 0.00E+00 0.00E*00 0.00E+00 0.00E+00 As-76 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.70E-06 1.70E-06 0.00E+00 1.70E-06 Cs-134 0.91E-07 1.45E-07 0.00E+00 8.91E-07 2.98E-06 1.23E-06 0.00E+00 2.98E-06 Cs-137 3.73E-04 6.32E-06 0.00E+00 3.73E-04 1.33E-03 1.09E-05 0.00E+00 1.33E-03 Mo-49 6.74E-04 5.56E-06 0.00E+00 6.74E-04 1.5?E-0? 1.27E-05 0.00E+00 1.52E-03 Zr-97 2.67E-05 7.54E-06 0.00E+00 3.67E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr 95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.45E-05 2,13E-06 0.00E+00 1.45E-05 ^
.48E-06 6.55E-07 0.00E+00 3.48E-06 No-95 I-132
- 93E-05 1.68E-06 0.00E+00 3.93E-05 1.58E-05 1.63E-0C 0.00E+00 1.58E-05 Co-50 0.005t00 0.00E+00 0.00E+00 0.00E+00 0-00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 1.97E-04 5.23E-36 0.00E+00 1.97E-04 2.06E-04 5.14E-Oi 0.00E+00 2.06E-04 1 96E-04 5.02E-06 0.00E+00 1.96E-04 1.12E-04 .n' :-06 0.00E+00 1.,12E-04 Ag-110rc 2n-65 5. P3E-07 2.60E-07 0.00E+00 5.?3E-07 3.11E-06 3.97E-07 0.00E+00 3.11E-06 I-135 2.10E-02 2.21E-05 0.00E+00 2.10E-02 1.45E-03 2.05E-05 0.00E+00 1.45E-03 FF-59 0.J0E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60
- .37E-06 1.?SE-06 0.00E+00 3.37E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.09E-03 1 15E-05 0.00E,30 1.09E-03 8.12E-04 1.07E-05 0.00E+00 8.12E-04 Cu-64 Hs-24
- 2. 49E -04 2.69E-05 0.00E+00 2.49E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La-14?
? lie-04 6.48E-06 0.00E+00 3.12E-04 2.01E-04 5.90E-06 0.00E+00 2.01E-04 Mn-56 2.84E-07 1.61E-07 0.00E+00 2.84E-07 0.00E+00 0.00E+00 0.00E400 0.00E+00 Cs-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 Ni-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.29E-04 4.01E-06 0.00E+00 1.29E-04 3r-09 A.00E+00 0.00E+00 0.00E+00 0.00E+00 1.84E-06 1.1GE-06 0.00E+00 1.84E-06 Gr-90 9.01E-04 2.40E-05 0.00E+00 9.81E-04 1.9?E-05 4.16E-06 0.00E+00 1.97E-05 7.26E-05 1.39E-05 0.00E+00 ;.28E-05 3.66E-06 8.43E-07 0.00E+00 3.66E-06 l at als 6.99E-03 4.94E-05 0.00E+00 6.99E-03 7.81E-0? 4: 9E-05 0.00E+00 7.81E-03
- .e-12:
Me-135 4.40E-03 7.01E-06 0.00E400 4.40E-00 3.03E-OS 3.98E-06 0.00E+00 6.03E-05
's - 131 ru 1.21E-05 7.61E-07 0.03E+00 1.21E-05 6.50E-05 2.41E-06 0.00E+0C 6.50E-05 0.OnE+00 0.00E+00 0.00E+00 0.00E+UU 0.00E+00,0.00E+00 0.00E+00 0.00E400 K -G8 M e - 13 ?i..
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00EF00 Fr-059 4.95E-05 1.73E-06 0.00E+00 4.95E-05 0.00E+00 0.00E'00 U.00E+00 0.00E+00 tr-67 1.39E-06 5.00E-07 0.00E+00 1.89E-06 0.00E+00 0.00 *00 0.00E+00 0.00E+00 Me-13? 0.00E+00 0.00E+0e 0.00E+00 0.00E+00 0 00E+00 0.00E+0u 0.00F'00 0.00E+00 S: 0.00E+00 0.00E+00 0.00E400 3.00E+00 0.00E+00 0.00E+00 C.UUE+00 0.00E+00 1 01 + i _ _.00E+00 0.00E400 0.00E+00 0.00E+00 0.00i-00 >.0cE*00 0.00E+00 1 , 4. .- .22E-06 0.00E+00 4.4FE-0? 1.45E-04 4.6t;-0: 0.00E+00 1.45E-04 , f%A\
FIGURE l-5 b i Liquid Raduasts Dat a Compi l at i on for Reg. Cuide 1.21 Report E. I. H at c h Nuclear P l ant UNIT 2 , t Total Activity (Curie.s> Ou ar t er 3, 1978 Quarter 4, 1978 l Batches 74 thru 319 Eatches 320 thru 459 I i H ame Mes ured Error High LLIu Tot al Naasured Error High LLDs Tot al Ce-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 T:-99w 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 Ce-141 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+n0 0.00E+00 , Up-233 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ! Cr-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.43E-04 2.17E-05 0.00E+00 7.43E-04 I-131 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.82E-05 2.29E-06 0.00E+00 4.82E-05 Zn-691 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.99E-06 7.47E-07 0.00E+00 5.89E-06 i U-187 0.00E+00 0.00E+00 0.00E+00 0.00E400 3.67E-05 6.59E-06 0.00E+00 3.67E-05 l F-16 1.32E-05 6.85E-07 0.00E+00 1.32E-05 5.53E-04 3.79E-06 6.08E-04 1.16E-03 ; 1-133 0.00E+00 0.00E+00 0.GOE+00 0.00E+0078.'70E-06 E.62E-07 0.00E+00 5.70E-06 I Pa-140 9.75E-06 2.32E-06 0.00E+00 9.75E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I Pi-76 0.00E+00 0.00E*00 0.00E+00 0.00E+00 8.89E-05 5.19E-06 0.00E+00 8.89E-05 Cs-134 1.49E-06 5.05E-07 0.00E+00 1.49E-06 3.38E-04 4.55E-06 0.00E+00 3.38E-04 Cs-137 1.86E-O' 3 06E-07 0.00E+00 1.86E-06 3.64E-04 5.16E-06 0.00E+00 3.64E-04 \ Ma-99 9.11E-06 e.63E-06 0.00E+00 9.11E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- --97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.33E-06 3.32E-07 0.00E+00 1.33E-06 Zr-95 3.46E-06 7.81E-07 0.00E+00 3.46E-C6 6.84E-07 6.14E-07 0.00E+00 6.84E-07 Nb-95 2.31E-06 4.42E-07 0.00Er00 1.31E-06 5.69E-07 2.37E-07 0.00E+00 8.69E-07 ,
1-131 0.00E+00 0.00E+00 0.00E+0V 0.00E+00 4.7tE-07 1.77E-07 0.00E+00 4.'1E-07 t Co-5' 4.: 3E-05 2.19E-06 0.00E+00 4.83E-05 1.95E-04 4.25E-06 0.00E+00 1.95E-04 Mn-54 4.21E-06 7,91E-07 0.00E+00 4.21E-06 2.23E-05 2.43E-06 0.00E+00 2.23E-05 ng-110m 5 30E-07 1.24E-07 0.00E+00 5.80E-07 0.00P+00 0.00E+00 U.00Er00 0.00E+00 Zn-65 2.65E-05 2.4TE-06 0.00E+00 2.65E-05 1.1;E-04 7.95E-06 0.00E+00 1.17E-04 I-135 1,94E-05 2.93E-06 0.0CE+00 1.94E-05 Q ./SE-06 2.51E-06 0.00E+00 9.75E-06 Fe-59 2.00E-0C 9.70E-07 0.00E+00 1.00E-06 1.03E-05 1.91E-06 0.00E+00 1.0$E-05 Co-60 1.55E-04 5.16E-06 0.00E400 1.55E-04 1.35E-04 4.98E-06 0.00E+00 1.35E-04 Cu-64 0.00d+00 0.00E+00 0.00E+00 0.00E+00 1.80E-03 3,99E-04 6.72E-04 2.48E-03 Ha-24 5.31E-06 i,90E-07 0.00E+00 5.31E-06 1.32E-03 1.02E-05 0.00E+00 1.32E-03 La-140 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-56 7.39E-06 1.51E-06 0.00E+00 7.39E-06 1.27E-05 1.57E-06 0.00E+00 1.27E-05 Cs-136 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.10E-05 1.45E-06 0.00E+00 2.10E-05 Cr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.15E-05 2.16E-06 0.00E+00 7.15E-05 3r-90 4.33E-05 6.30E-06 0.00E+00 4.33E-05 5.32E-05 3.34E-06 A.00E+00 5.32E-05 Tm als 3."3E-04 1.02E-05 0.00E+00 3.53E-04 5.96E-03 4.00E-04 1.25E-01 7.24E-02 Me-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.'1E-04 4.29E-06 0.00E+00 2.11E-04 "m-135 6 36E-06 5.69E-07 0.00E+00 6.36E-06 2.79E-04 4.05E-06 0.00E+00 2.78E-04 4-1 31o 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 70 0.00E+00 0.00E+0t. 0.00E400 0.00E+00 4.42E-07 2.15E-05 0.00E+00 4.42u-07 r - 13 3 ra 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.007+00 35i 6.13E-07 2.06E-07 0.00E600 6.03E-a 0.00E'00 0.00E+00 0.00E+00 0.0(_- Q
) - 37 0.00E*00 0.00E+00 0.00E*00 .00E+00 0.00E+00 0.00E-00 0.00E+00 0.0d +a0
-12; 2.GOE-07 6.1?E-OS 0.00E+00 2.80E-e? 0.00E+00 0.00E+00 0.00E+00 0.0tE+PO
-135' 6.75E-12 2.93E-12 0.00E+00 6.75E-11 0.00E400 0.00E+00 0.00E+00 0.00E+00 i
.stal- . 27L-06 A.09E-07 1.00E+00 7.27E-06 4.89E-01 6.39E-06 0.00E+00 4.89E-04 i
TABLE l-1 E. I. H at _ h hucle ar Plant UllI T 1 i _t E f n liN D tlW.l E D I':i 05HL :.Eill fitit h . A!. CCP0gr i L 10V I D LFF LUl t;'S-5UrIt1ftT I Cri GF rtLL P E L ". it i n Unit Ouarter I :' u e t c *{ 2 r T c.1 s1; 2 1 E r or I
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t Fis_ien ::tivation productc H3, i
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(15)
TABLE l-1 (cont.) E. I. H a t. . n th i t y F 1.an t Utill m EFTLWhi ft. ! D U;~1 C T E FISOiBL 5th M H198 L FE?U 2 -' i LIQUIL E FF Li'E N T '_ - 5 U'Mi Ai l O GF ALL i E L E R r. i U r i v r. O u s r t- e r I' O u e_c t. e r - '. E - Ic=.'
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TABLE l-2 E. 1. H at c h fluc l e ar Plant UNIT 1 EFFLUE!IT AND HASTE D I S POSftL SEi1IANNUAL REPORT 197e LIOUID EFFLUEHTS CONTIHUOUS t10DE E ft T C H (10DE Huclides Re le ase d Unit Ousrter Quarter Qu_.rter Qu ar t c r 3 4 3 4 Ce-144 Ci 0.00E+00 0.00E+00 I c - 9 ? ra Ci 0.00E+00 0.00E+00 Ce-141 Ci ~ 1.19E-06 0.00E+00 ; tir-?39 Ci 0.00E+00 0.00E+00 ' Cr-51 Ci I-131 Ci 6.00E-051 1.42E-03
.10E-06] 4.88E-04
'n - 6 9 rn Li 0.00E+UO 0.00E+00
~
H-107 C i_ [ 0.00E+00 0.00E+00 F - 1 :5 . Ci 5.70E-04 5.50E-05 1-133 C i_ ?.62E-06 0.00E*00 U ri 140 Ci 0.00E+00 1.70E-06
-_..- fi s - / .. Ci 8.91E-07 2.98E-06 C5-134 -
Ci 3. .' ? E- 0 4 1.33E-03 CE-137 Ci 6.74E-04 1.52E-03 No-99 Ci _' 3.6?E-05 0.00E+00 Zr-97 Ci 0.09E+00 0_.00E+00 Zr-95 Ci 1.45E-05 3.46E-06 tib-95 Ci ?.93E-05 1.58E d5 ( 1-132 Ci 0.00E+00 0.00E+00 Co-58 Ci 1.97E-04 2.06E-04 Un-54 Ci 1., 9 6 E - 0 4 1.12E-04 O g - 1 10 n. Ci 5.83E-07 3.11E-06
~
2 n - J. 5 C1 ~~ 2.10E-02 1.45E-03 ? 1-13E Ci i 0.00E+00 0.00E+00 l Fe-59 Ci 7.3?E-06 0.00E+00 Co-60 Ci 1.09E-Oi C.12E-04
~
Co-G4 Ci ~ 2.49E-04 0.00E+00 Ha-94 Ci _.12E-04 2.01E-04 L s -14 0 Ci _ 2.84E-07 0.00E+00 fin-56 Ci 0.00E+00 0.00E+00 , C2-136 Ci 0.00E+00 1.29E-04 , Hi-65 Ci 0.OOE+00 1.84E-06 Sr-99 Ci 9.81E-04 1. 97E- 05 Sr-90 Ci I 7.2EE-05 3.66E-06 1 T it ai t or period (sboue) ]_ Ci ~ 6.99E-02 7.81E-0?! c:r-133 Ci 4.40E-03 5.03E-05 e-135 Ci 1.21E-05 6.50E-05 c - 131 ro Ci 0.00E+00 0.OnE+00 l K r - :: .: Ci 0.00E+00 0.00E+00 e n__ -; e - 13 3 ra Ci 4.95E-05 0.00E+00 Er Ci 1.s9E-06 0.00E+00 f L r - t .' Ci [0.00E+00 61.00E+00 4 c-138 C1 0.00E+00' - O.005+'U{
,_ ._. .__ 35n Ci 0.00E+0.0 0,n0E+g q (17)
TABLE 1-2 (cont.) E. I. Hat cl. Iluc l e ar Plant UNIT 2 < EFFLUEllT AllD WASTE DISPOSAL SElIIANNUAL PEPORT 1979 LIQUID EFFLUENTS C ONT lilUOU S l10LE BRTCH l10DE II21 ides Released Unit Q u ar t e r Quarter Quar t e r Qu ar t e r 3 4 3 4 Ce-144 Ci 0.00E+00 0.00E+00____ Tc-99m Ci O.COE+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 Np-239 Ci 0.00E+00 0.OOE+00 Cr-51 Ci O.00E+00 7.43E-04 I-131 Ci _ 0.00E+00 4.52E-OS" Zn-69ra Ci 0.00E+00 5.99E-06 t1-187 C1 0.00E+00 3.67E-05 F-18 Ci 1.32E-05 1.16E-03 ~ I-1'? Ci __ 0.00E+00 5.70E-06 Ba-140 Ci 9.75E-06 0.00E+0i1 Ac-76 Ci 0.00E+00 8 89E-05 C2.-134 Ci 1.49E-06 3.38E-04 Ca.-137 C1 - f- 1.d6E-06 3.64E-04 r10-99 Ci 9.I1E-06 0.00E+00
~ ~ ~
2r-97 Ci 0.00E+00 1.33E-06 ' 2r-95 Ci :.46E-06 6.84E-07 H b -- 9 5 Ci , 2.31E-06 E.69E-07 I I-132 Ci 0.00E+001 4.71E-0__ ? r [_ 4.93E-05I 1.95E-04 Co-5G Ci iln-54 Ci 4.21E-061 2.23E-05 5.98E-07 0.00E+he n g- 1 10 ra Ci 2n-65 Ci ._.65E-05 ,1.1?E-04 , I-135 Ci 1.94E-05 9.78E-06 _ Fc-59 Ci 2.00E-06 1.08E-0 '
~
Co-C0 Ci 1.55E-04 1.?5E-04 Co-64 Ci 0.00E+00 2.48E-03 Ha-24 Ci 5.31E-06 1. 3 2 E-0:_ > L a-- 14 0 Ci 0.00E+00 0.00E+00 fin-56 Ci 7.39E-06 1.27E-OS C2-136 Ci ~ 0.00E+00 2.10E-05 5r-89 Ci 0.00E+00 . 15E-05 Sr-90 Ci 4.33E-05 5.22E-05"
~
Ci j 3.53E-04 7.24E-03 [ 1 :' t 11 for p:.e r i o d (above) _ _ _ _ _ _ _ _ _ _'+-193 Ci 0.00E+001 2.11E-04 A - l '-15 Ci 6.:6E-06 2.78E-04
;;e - 131 ro Ci 0.00E+r10 0.00E+00 6'r -88 Ci 0.OeE+00 4.42E-07 c e - 1.? 3 m Ci 0.00E+001 0_._0._0 E + 0 0 i: r - 05 m Ci 6.33E-07l 0. OE+00 J, .
):r 2'7 Ci 0.00E+04 ' e _OE+00 l
; - *-138 Ci 2.30 -0'ri .OE-00 l 1:5m Ci 6.'5F-l' ' o noE+0e{
(10 .
2 CASEOUS EFFLUErlTS 2.1. REGULATOP.Y LIMITS.
- a. (1) The release rate limit of n'oble gases from the site, shall be; J
{ Qj3 1.9 E + 1.0 EB +Qv i 11 Ey + 44 Eg 11 i+n - where Qs = Total release rate from main stack for both Units in Ci/sec (elevated release) , gy = Total release rate from vent in Ci/sec (ground release) ~- i ? the individual nuclide. n = total nuclides. Yy = the average gar.za energy per disintegration
- 58.= the average beta energy per disintegration (2) The release rate limit of all radioicdines and radio- 'r active materials in particulate forn with half lives greater than eight days, released frcm the site to the environs as part of cne gaseous wastes', shall be. ,-
1 l.0 X 10 5 Qps + 1.5 X 10 5 Qpv i 1 Where Qps= Total release rate from the main stack for both '
. Uni ~ts in Ci/sec (as elevated release) ',
Qpy= Total relecse rate from vents for both Units in - Ci/sec (ground release) '
~
- b. (1) The average release rate of nobic gases frcm t+ site during any calendar quarter shall be: _ _
Qis 12 Ey + 3.0 Eg + Qiy 66 Ey + 140 EB 1I i+n - (2) The average release rate of noble gases during any 12 consecutive months shall be: .
) i+n Qjs 24 Ty + 6.1 Yg
+ Qiy 130 Ey + 270 EB
- 5. I (3) The averare release rate of.all radio . iodines. and radioactive
- materials in parti ulate form from the site with half lives gi-cater than eight days during any calendar quarter shall be:
7 l . 3 X 10' Q.os + 1.9 X 10 Qpv 5 1 -
- (4) The average release rate of all radio iodines and radioactive materials in particulate form from the site with half lives greater than eight day: during any period of 12 consecutive months shall be: .-
n 2.6 X 10 5 Crs + 3 ' X 10 7 O p v 5. 1 (19) 9
(5) The amount of Iodine - 131 re ease uring any ca en-
,. dar quarter shall not exceed 2 Ci/ reactor. 4 s
(6) The, amount of iodine - 131 released during any period ! of 12 consecutive months shall not exceed 4 Ci/ reactor. ,
- c. Should the conditions of 2.1. 3c (1), (2), or (3) listed ' ;
below occur, the licensee shall make an investigaticn to ' j identi'fy the causes of the release rates, define and initiate - a program of action to reduce the release rates to desigr objective levels listed in subsection 2.1 of the fi:iP-ETS ; and report these actions to the Cc=nission within 30 days 3 from the end of the quarter during which the releases occur- ! red in accordance with section 5.7.2. . 3 (1) If the average release rate of ncble gases during any calendar quarter is: , j:
.r _j
. - - y
/ ,Qis - 47 Ey + 12 E__B + Qiv 250 Ey + 540 EB >l 1 i+n - -
~
4 (2) If the average release rate from the site of all radio iodines ) and radioactive materials in particulate form with half lives -; greater than eight days during any calendar quarter is: .; 7 5.0 X 10 5 Ops + 7.2 X 10 Qpy > 1 2 4
~(3) If the amount of Iodine - 131 released during any cal- ".
endar quarter is greater than 0.5 Ci/ reactor. }.
- d. The post-treatrent offgas monitors shall be operating and set to 9 alarm and to inititte the automatic closure of the waste gas *i discharge valve prior to exceeding the limits specified in Section 2.1.3a above. The operability of the automatic isolation valve .]
shall be demonstrated quarterly. J
- )
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. 1
- S
- f. If the release rate of noble gases measured at the pretreatment ,
monitor excecos 2c0,000 uti/sec ; v
~ '
~
for a period greater than 48 hours, notify the Ccmmission in
- writing within 10 d3ys, identifying the causes of activity and in accordance with section 5.7.2.
- < .G,
. g.. The reactor containment for each Unit shall be purged through ;
the standby gas treatment system for that Unit. . 1
- h. (1) Potentially - explosive gas mixtures of hydrogen and oxygen 5 contained in the offgas sys tem downstream of the reco.T biners shall be continuously monitored durir.g reactor powar operation for hydrogen concentration. The hydrogen gis rconitoring
- system shall provide alarms locally and in the control room :-
at a set point of 4", hydrogen concentration by voluma. At - least one continuous gas monitoring system and its associated . alarm ryste:" shall be enerable durino reac tor po. er opera tion. I f but , ,
.. h ,
,,* s n a e ,n . ia t u alarm * .w , a ro i n.w. r. sm. rt - 1r e m;i . a ty m w ti-nued for a period of tir.a not ta exced .' weeb , providm1 that either (a) grab sa:iples 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 concentration readings are taken and logged every 4 hours. (2) The hydrogen concentration in the offgas system downstream of the recombiners shall not exceed 4% concentration by volume. If at any time during reactor power operation, it is determined that the hydrogen concentration limit is being exceeded, action shall be initiated within 4 hours to return the hydrogen concentration to within the prescribed limit. If the hydrogen concentration is not reduced to less than 4% by volume within 24 hours, the offgas system flow shall be stopped. (3) The installed hydrogen monitoring systems shall have daily sensor checks, monthly functional checks, and quarterly calibrations. The portable hydrogen gas analyzer shall be calibrated immediately prior to installation and shall be subject to daily sensor checks, monthly functional checks, and quarterly calibrations until removed from service,
- i. An unplanned or uncontrolled offsite release of radioactive materials in gaseous effluents in excess of 150 C1. of noble gas or 0.02 C1. of radiciodines 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 Waste gas releare at Hatch is confined to four paths. Each of these four gaths is continuously monitored for gaseous concentration and each has an integrating type collection device which concentrates particulates and iodine for each seven day period (Procedures are such that shorter collection times are used where applicable to Technical Specification requirements). Each of these continuous samplers has a flow controller which maintains sample flow within about a 10 percent range over each seven day collection period. The offgas vent (elevated release) and the reactor building vents have flow measurement devices which continuously record the flow rate of the gas released (accuracy of these devices are within 10% of the actual fl.ows as measured during preoperational testing). The recombiner building vent fl ow on Unit One is conservatively assuaed to be constant at 500 CFM. In addition to the gaseous, particulate, and iodine release measurements tritium, gross alpha and gaseous isotopic neasurements of each vent stream are conducted on a monthly schedule. (21)
After each calendar quarter (13 weeks) c summary of waste gas release from the four vents is compiled and as such is designed to meet the requirements for prepa"ation 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 tne 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 cur.e release is determined from the continuously reading gaseous monitors in addition to the vent ow recorders. Activity monitors and vent flow rate reaot.igs are read hourly and input into the computer. From these readings a daily release is calculated. The calibration factors fon the monitors are determined from the monthly isotopics when su"ficient activity allows or by injection of a known amount of off-gas into the sample chambers. The total curie release is calculated by the computer for each of the individual nuclides released. This number _ is multiplied by the average energy per disintignation (ET &
Ep) along with the coe fficien ts in the release limit formula in our Environmental Technical Specifications. All of the nuclides are summed and stored in their respective data files until the end of the quarter. Then the computer divides the sum of the nuclides by the seconds in the quarter to determine the percent of the tech. spec. limit released. T
- 2. R ADI0 IODINE 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 calcul'ted. Since calculated MDA's are below Technical Specification detectable concentrations then 0 (zero) release is used for the weeks with only MDA values. Weekly releases are summarized with the aid of the counting room calculator -
computer system and a quarterly total is prepared from the weekly summaries. The percent Technical Specification for I-131 on Table 2-1 is based on the quarterly Technical Specification limit. 3 PARTICULATE RELEASES Particulate releases are de te rmi ned weekly for each vent. Where signifiennt 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 valtes. Weekly rele,ses are sunmarized uith the aid of the counti.ng room calculator - computer. (22)
After each calendar month the particulate fi 2 ters from each vent are combined, fused, and strontium separation is made. Sinae sample flows and vent flows are almost constant, over each monthly period the filters from each vent can be dissolved togethea. Decay corrections are made back to the middle of the monthly collection period. Again the countin a room calculator - computer is used to aid in the calculation of the Sr-89, 90 release. Where significant strontium activity is not detected MDAs are calculated. In order to eliminate the need for a quarterly composite Sr-89 and Sr-90 activity is calculated for each monthly composite. The percent of Technical Specification was calculated using quarterly average equation.
- 4. GROSS ALPHA RELEASE The gross alpha release is competed each month by counting the particulate filters each week for gross alpha activity in a proportional counter. The four or five weeks numbers are then recorded on a data sheet and the activity is summed at the end of the month.
S. TRITIUM R ELEASE Tritium staples are obtained monthly from each vent by passing the sample stream from a cold trap immersed in a liquid nitrogen or an acetone and ice mixture. The grams of water vapor / cubic foot gas .' s measured upstream of the cold trap in order to alleviate the difficulties in dotermining water vapor collection e f f'ici enc ie s . The tritium samples are analyzed by an independent laboratory. From the uCi/ml tritium ccncentration, the grams water /ft3, and the vent flow ra ce s , the monthly tritium release is calculated for each vent, and the quarterly summary can be generated from the monthly calculation forms. lintch has attempted to maintain all calculated MDAs as low as possible by counting samples longer than what would be nor 111y practical. For example at this time all weekly particualte and iodine counting times are 3000 see and strontium separations are counted for 100 minutes. Regulatory Guide 1.21 requires that estimated total error in analysis techniques be reported. These estimates are required for the total fission and activation gas release, total I-131 release, total particulates with half-lives greater than 8-day release, and total tritium release.
"The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total operation cf s a m p i. i n g and measurement.
Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed , (23)
statistical evaluation of error are not suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste." Estimated errors are based on errors in counting equipment calibration, counting statistics, vent flow rates, vent sample flow rates, non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges.
- 1. Fission and Activation Gas Total Release was calculated from process monitor readings. As 99.2% of the Xc-133 measur d was released from the main stack tne Kr-85 concentration was calculated *o be 1.26 E-ll uci/ml using 0.288 as the fission yield and basing the calculations on the measured release of Xe-133 With this number so far below the MPC limit of 3 X 10'7 the release was reported as 0.
Monitor Error in Calib ra ti on 50% Vent Flow Rate 10% Non-Steady Release Rate 20% H5T
- 2. I-131 Release was calculated from each weekly sample:
Statistical error 60% Counting Equipment Calibration 10% Vent Flow Rates 10T Vent Sample Flow Rates 10% Non-Steady Release Rates 10% Losses From Charcoal Cartridge 10% 115T
- 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:
Statistical Error at MDA concentration 60% Countng Equipment Calibration 10% Vent Flow Rates 10% Vent Sample Flow Rates 10% Non-Steady Release Rates 10% T565 4 Total Tritium Release was dominated by the reactor building vent PEItium release, hence, the larger statistical erroas of the off-gas vent and recombiner building vent tritium re le a s e.s do not affect the error in the total tritium release: (24)
- Water Vapor in Sample Stream Determination 20%
Vent Flow Rates 10% Counting Calibration and Statistics 10%
!!on-Steady Release 50%
90T 2.3. GASEOUS EFFLUE!!T R ELE ASE D ATA Regulatory Guide 1.21 Tables lA, 1B, and 1C are found in this report as Tables 2-1, 2-2, and 2-3 Data is presented on a quarterly basis as per Regulatory Guide 1.21. 3 SOLID WASTE. 3.1 Regulatory Specifications,
- a. Measurements shall be made to determine or estimate the total curie quantity and principal radionuclide composition of all radioactive solid waste shipped offsite.
- b. Solid wastes in storage and preparatory to shipment shall be monitored and packaged to assure compliance with the applicable portions of 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 171-178.
- c. Reports of the radioactive solid waste shipments, volumes, principal radionuclides, and total curie quantity shall be submitted in accordance with subsection 5.6.1 of the Hil P- E T S .
3.2 Solid Waste Data Regulatory guide 1.21 Table 3 is found in this report as Table 3-1. i , .
- i (25)
TABLE 2-1 (_ EFCLUENT At3D HASTE DISPOSAL set 1I Atir4U AL REPORT 1978 G ASEOUS EFFLLIEtiT 5-5Ut1M AT I0t1 0F ALL RELE6SE5 Unit Quarter Quarter Est Tot al 3 4 Error . E. I. Hatch t4uc l e ar Pouer P l ant SITE , i A. Fission ac t ivat ion gas es Ci 2.59E+0 1 04E+0- ~
.00E+01 l
- 1. T ot al re le as e l uCi/sec 3.30E+0! 1.29E+0i
- 2. Aver ne re le ase r at e for oeriod
- 3.88E-02 2.56E-01 of Technica1 : cec i f i c at i oti 1imit
- 3. I i
- 1. Iodines Ci 1.60E-05 1.44E-v;I1.,10E+02[l
- 1. Tot al iodine-131 '
uCierec 2.04E-06 1.79E-0#
- 2. 9"e r ag e re l e as E rat e for period 3.60E-w '
of T e c hn i c al soec i f i c at i on 1init _
. 4.00E-04 i
C. P a.s t i c u l at .: - !
~~~1. P art i c u l at e s ulth hal f-11'*es >8 d at's Ci 1.47E-C4 }.27F-0?' 1. 0 0E +6fT l I
uCi/sec 1.87E-05 2.52E O;i Auer ag - rel e are r at e for period i
- 2. "
?.01E-Oi 5 20E-01 !
of Technica! soec iii c at i en 1imit 4 . __ C i 5.25E-06 4.83E-06
- 4. Groms al ph a radicactivitv i ;
D. Trition Cr 2.53E+00 2.'2E+ 0! .00E+01l t
- 1. Total rale:se a'eraac r e 1 e ,2 e rate for ::ie r i o d u;1 sec _.22E-01 g? ?E-0.l
- - ( 12 - hni c al = pc c i f i c at i c o l i ra i t
. 0.00E+00l ' . 0_0 E + ( 0 i- )
i l (26)
TABLE 2-2 f E. I. Hatc'n Nuc l e ar Poiier Plant SITE EFFLUENT AND NASTE DISPOSAL SEMIANNUAL REPORT 1978 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTINUOUS MODE ERTCH M O I- E Nuclide3 Re l e as e d Unit Ouart er Quarter 3 4 Quart e r l Quart er R L_ 4
- 1. Fis3iori g as e s Xe-1?? Ci 1.60E+01 6.58E+02 0.00E+00 . 0.00E+00
%e-151H Ci 0.00E400 4.45E+01 0.66Et00 0.00E+00 Kr-88 Ci 7 54EtOO 3.54E+01 0.00E+00 0.00E+00 Je-1?3M Ci 0.00E+00 2.21E+00 0.00E+00 0.00E+00 Xe-135 Ci -. 39E+0G
_ 1.84E+01 0.00E+00 0.00E+00 Er-85M C1 c.66E+01 1.33E+0E 0.00E+00 0.00E-00 I-131 Ci 6.75E-07 0.00E+00 0.00E+00 0.00E&OO Fr-S7 Ci 2.55E+00 9.06E+00 0.00E+00 0.00E+00 Ne-138 Ci 1.40E+01 3.19E+01 0.00E+00 0.00E+00 "e *37 Ci ?.67E-02 0.00E+0a 0.00E+00 0.00E+00 N-1? Ci 4.82E+00 3.03E*01 0.00E+00 0.00E+00 F:r-35 Ci O.00H+00 0.00E+00 0.00E+00 0.00E+00 Ae-135M Ci 5.10E-0? 6.43E+00 0.00E+0e 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-59 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 f_ Ar-41 Ci 3.59E+00 1.16E+01 0.00E+00 0.00E+00 Total Ocr period Ci 2.24E+02 9.81E+02 0.00E+00 0.00E+00
- 2. Iodines I-131 Ci 1.05E-05 5.53E-05 0.00E+00 0.00E+00 I-1?? C1 2.^9E-05 9.19E-05 0.00E+00 0.00E+00 1-135 Ci 1.01E-06 4.?3E-05 0.30E+00 0.00E+00 Total for period Ci 4.03E-05 1.96E-04 0.00E+00 0.00E+00
- 3. Part i c u l at e s ir-99 Ci ~ 2.24E-05 2.10E-05 0.00E+00 0.00E+00 '
Sr-90 Ci 2.71E-07 2.31E-07 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C r -51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 1.42E-08 2.0?E-06l 0.00E+00 0.00E+00 Sn-11? Ci 0.00E+00 0.00E+001 0.00E+00! 0.00E+00 Ba-140 Ci 0.00E400 1.21E-05 0.00E+00 0.00E+00 C2-134 Ci 0. 0FE' 0 0 2.58E-06 0.00E+00 0.00E+00 C .= - 1]j tt 0.00E+00 3.36E-06 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00l 0.00E+00 Zr-95 __ Ci 0.00E+00 0.00E+0a 0.00E+00 i 0.00E+00 Nb-95 Ci O.00E+00 0.OnE+00, 0.00E+00 0.00E+00 Co-5E Ci-- O.00E+00 0.00E 00i 0.00E+00! 0.00E+00 M r, - 5 4 Ci__ 0.00E+00 0.00E+001 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+GOl 0.00E+00 0.00E*00 Ce-60 Ci 6. 3 B E - 0.- c..tE-07 0.00E+00{ 0.00E+00i 1 La-140 _ C _,. . _ _ _7 ._n S_E _- 0 7 3.41E-05,_.3 e r E
- C O .I_0.00E+00 IC* iI f 0t D iOd C1 __n_E.41E-05 7.57E-05 0.0eE+00 0.00E+00 (27)
TABLE 2-3 [. E. I. H at c h thc l e ar Pouer Pl ant SITE EFFLUENT AND HASTE DISPOSAL 5EMIANNUAL PEPORT 1978 l> GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE
- l' CONTINUOU5 NODE EATCH MODE Nuc1 ides Re1eLied Unit Duarter Qu ar t e r Qu art e r Quarter 3 4 5 4 4
- 1. Fission g as e s t 4 -1.33 Ci 5.40E+00 1.0TE+00 0.00E+001 0.00E+00
- se-131P Ci 0.00E+00 0.00E+00 0.00E+00' O.00E+00 Kr-8? C1 2.58E-02 1.2TE+00 0.00E+00 0.00E+00
[ he-1?3M Ci 9.?QE-02 3.86E-02 0.00E+00 0.00E+00 xe-125 Ci 2 . '.i O E + 01 5.97E+00 0.00E+00 0.00E+00 i Kr-85"i Ci 1.92E-03 1.13E-01 0.00E+00 0.00E+00 i I-1 1 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00-Kr-9< t. i 1.21E-02 R.15E-01 0.00E+00 0.00E+00
<e-155 Ci 0.00E+00 1.63E-01 0.00E+00 0.00E+00 -
t Ae-1?? Ci 0.00E+00 0.00E+00 0.00E+00}__0.00E+00 N - 1 :. Ci 4.,99E+00 2.55E+00 0.00E+00! 0 30E+00 Kr-85 Ci O.00E+00 0.00E+00j 0.00E+m s.00E+00 a-135M Ci 0.00E+00 1. 39 E -0.2 0.00E+00 0.00E+00 I-10.3 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
~
Kr-39 Ci 1.10E-01 4.52E+01 0.00E+00 0.00E+00 ( 1-135 Ci 0.00E+00 0.00E+00 0.00E+001 0.00E+00 t Ar-41 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Tctsi for period C1 3.56E+01 5.72E+01 0.00E+00 0.00E+00 ;
- 2. Iodines 1-131 Ci 4.76E-06 9.31E-04 0.00E+00 0.00E+00 1-132 Ci 3.42E-06 2.50E-04 0.00E+00 a.00E+00 I-135 Ci 2.70E-06 2.13E-03 0.00E+00 0.00E+00_ _
Total for period 2_C i 1.0?E-05 1.39E-02 0.00E+00 j .00E+00
- . f' ar t i c u l at e s t
jr-89 Ci 6.44E-06 2.55E-Os[ 0.00E+00 0..0E+00 3r-90 Ci 5.98E-07 3.32E-06 0.00E+00 0.00E+00 Cc-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 3.58E-05 3.46E-04 0.00E+00 0.00E+00 I-131 C1 5.26E-08 4.51E-04 0.00E+00 0.00E+00 , S n - 1 1 :_ Ci 0.00E+00 5.13E-06 0.00E+00 0.00E+00 E k- 14 0 Ci O.00E+0U 0.OOE+00 0.OOE+00 0.00E+00 Cs-134 Ci 1 '3E-08 6.51E-04 0.00E+00 0.00E+00 C s ' ? Ci 4.1rE-10 6.49E-Ol D.00E+00 0.00E+00 Cc-144 Ci 0.00E+00 9.63E-Os(_O.00E+00 0.00E+00 Zr x C; 0.00E400 0.00E*03 0.0UE+00 0.00E+00 ho-95 C1 0.OOE+00 ?.??E-00 0.00E+00 0.00E+00 g Cc . Ci 0.00E+00 1.02E-05l 0.00E+00 0.00E+00 < Mr-54 C1 2.54E-05 0.00E+00f 0.00E+00. 0.00E+00 Fe-99 Ci 0.00E+00 t- 3.18 E-0 T i 0 . 0 0 E + '_: 0 0.00E+00 r.r, C1 _j 5.44E-051 5.06E-05 3 0.00E-00 0.00E+00 U.Ue.+._ _ _ _._a w + u u Li ...20t_-08r-0.00E+1' i >d 1, "' ? E - 0 4 2.19E-0: 0.00E-J0! O.00E+00 __ _n C i a (28)
Table 3-1 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT (YEAR) 1978 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNIT I A. SOLID WASTE SHIFFED OFFSITE FOR SURIAL OR D:0POS AL (Net irradiated fuel) 1 Gme th E st. To ul I. Type of w.ute Wit Peried Error %
- a. Spent r: sins. filter s:tdges, evarers:or m' 1.03 E+2i .
totter s. etc. C: 1.43 ET2i 1.00EC
- b. Dry ccm; rem e w:s:e, cont:r un2::d m' l 7.40 E+11 equ:p. e::- Ci i1 cq E +f 1_ OqE+?
- c. Irt:di2ted ccmponents, contrel -
m' 1 03_ Ell! rods. etc. Ci 10.54 E+1 1.00E+2
- d. Other (desenbe) m' E '
Ci E E
- 2. Estimate of maior nuclide composiden (by typ of v.rste)
ISOTOPE l PERCEf1T l CURIES Zie 5 57 82
- a. C060 15 21
. CS137 c; '8 fib 95 R 11 All Otners 15 21
- b. Zii6 > 57 9 C06' I 15 2 CS137 5 1 51 4 Cr 1 All Others i 19 3
- c. FUEL CHA!ffELS I ZR*" l 75 370 tib* 5 25 123 LPRW s 7lF 5 46 4622 CO' 42 4219 lib'5 6 603 All Others 6 603
- 3. Sclid Waste Disp:sidca Number o f Shi:ments Mede o f Trans:crtation Destinaden 38 Chem-fluclear S3 stems, Barnwell, S.C.
Inc. B. IRRADIATED FUEL SHIP.',1ENTS (Disposidon) ! Number of Shiements Mod: of Trr.:mr:2:fon Des irudon .
. sl
^.
Elt-2.s 8 73
Table 3-1 Cont.' EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)_1978 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UillT II A. SOLID WASTE SHIPPED CFFSITE FOR F.URIAL CR DISFCSAL (f.'ot irradiated fuel)
- 1. Type of wzste un; M cmth E st. To mi W od En x. %
. a. Spent resins, filter sh:d;:s. evaper:. tor rn* i 1.73 E +3 . bo t tom.s. e tc. Ci i 1.o; E 001.00 E+2
- b. Dry cornpresa:1 waste. cont:rmnat:d eqws,etc.
rn i El Ci E I E
- c. Irradicted cc,rapanenu, control m' E rods, et:. Ci E E
- d. Other (desenbe) rn' E Ci E E
- 2. EstIr:ute cf rnaior necEde composition (by type of waste)
ISOTOPE PERCEi1T CURIES
- a. Cr 51 68.10 1.33 C058 11.26 0.22 7N 5 11.87 0.23 All Others 8.77 0.17 b.
c. d.
- 3. SoUd nste Dispostica Numberof Shi cena Mode of Tr2..spettation Destination 15 Chem-Nuclear Systems, Barnwell, S.C.
Inc. C. IRRADIATED FUEL SHIPMENTS (Oisp.sition) Number of Shier ent: Mode of Transmrtation Desti:ution
. . , . , <n 4 I sl = I 'E S ='I (30)
/
GEORGIA POWER COMPANY PLANT E. I. HATCH UNIT NO. 1 SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JULY 1, 1978 - DECEMBER 31, 1978 , .f. . ,
PLAfiT E. I. HATCH
- UNIT I SEMIA!'?iUAL REPORT
. PLNIT RADI0 ACTIVE EFFLUENT RELEASES
~
SECTIO'i TITLE PAGE
.l. LIQUID EFFLUEfiTS . 1 1.1 REGUL TORY LIMITS 1
# IMXIMUM PERMISSIBLE CGIiCENTRATIONS 1.2 1
~
1.3 MEASUREMEf!TS A.iD APPROXIMATIONS OF . TOTAL RADI0 ACTIVITY 4 1.4 BATCli RELEASES 6 2 . GASEGUS EFFLUEitT 14 2.1 . REGULATORY LIMITS 14 2.2 MEASUP,EMEtiTS AfiD APPROXIMATIONS OF TOTAL RADI0 ACTIVITY . 16
- 2. 3 GASEOUS EFFLUEliT RELEASE DATA 19 p SOLID WAS " 19 3 ', .
3.1 - REGULATORY SPECIFICATIONS 19' SOLID HASTE DATA 20 3.2s . e
. . . . - - . - . . . . . ~ . . . . . . -. ,
PLA:IT E. I. HATCH UNI [ I 5Elll A 'NUAL REPORT
- PLAtlT RADICAC,'VE EFFLUEllT RELEASES
( . LIST OF FIGURES . FIGURE , , PAGE l-1 ' METHODS OF MEETit;G TASLE II
' COLU:'Ji 2 M?C LIMITS (10 CFR 20) 7 1-2 LIQUID RAD',iASTE RIALYSIS 8
~ ~ ~
' l-3 LIhJIDRACUASTEANALYSIS 9 1 LIQUID RAD'.!ASTE DISCHARGE PERMIT 10 ,
1-5 -
, LIQUID RADUASTE DATA CCM?ILATION 11 I
LIST OF TABLES
~
- TABLE PAGE 1-1 EFFLUENT AND UASTE DISPOSAL SEMI-AUiiUAL PEPORT, LIQUID EFFLUE:TS-
- SU:G'AT10;i 0F ALL RELEASES 12 1-2 . ' EFFLUEt!T A!iD UASTE DISPOSAL SEMI-( -
*, ANNUAL REPORT, LIQUID EFFLUENTS-BATCH O!;LY ..
13 2-1 EFFLUEt!T A :D WASTE DISPOSAL S.Ei!I- . A!it'UAL PEPORT, GASEGUS EFFLUENT-
' ~
SU:lGTION OF ALL RELEASES 21 2-2 ,
$FFLUE!!T AND WASTE ' DISPOSAL' SEMI- .
ANNUAL REPORT, GASEOUS EFFLUE"TS- -
- ELEVATED FILEASE 22 ,
2-3 EFFLUEt!T Ai:0 WASTE DISPOSAL SEMI-
- - AUi;UAL REPCRT,- GASEQUS EFFLUEt:TS-23 GROU:iD LEVEL RELEASES .
3-1 - EFFLUENT R!D WASTE DISPOSAL SEMI-
- ANiiUAL REPORT, SOLID UASTE AND
' 1RRADIATED FUEL SHIP;;EllTS 24 O
O 9 x - O e
UNIT I P.ADI0 ACTIVE EfflUEil! R.El' EASES 1 QQUID _Lf flue!!TS , , 1.1. REGULA105 LIMITS .
- 1. The concentration of radioactive materials released in
. liquid wastes from all reactors at ti l e site shall not
- exceed the values specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for unrestricted area.
2 ". The release rate of radioactive materials in liquid uastes, excluding tritium and dissolved gases, shall not exceed 10 Ci/ reactor / calendar quarter.
- 3. The release rate of radioactive materials in liquid wastes, -
excluding tritium and dissolved gases, shall not exceed 20 Ct/ reactor in any 12 consecutive conths. ,
- 4. During release of radioactive wastes, the effluent control monitor shall be set to alara and to initiate the automatic closure of the waste discharca valve prior to exceeding the .
limits specified in 1. above. ,
- 5. The operability of the automatic isolation valve in the liquid radioat"ive w :ste discharge line shall be demonst-rated quarterly. .
- 6. The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process radioactive liquid wastes prior to their discharge when the ,
projected cumulative release rate will exceed 1.25 Ci/ reactor /
~
. calendar quartei , excluding tritium and dissolved gases. .
- 7. The makicum radicactivity to be contained in any' liquid radwaste tank that can be discharged directly to the environs shall not exceed 10 Ci, excluding tritium and dissolved
. -gases. . . ,
- L.
- 8. When the release rate of radioactive materials in liquid wastes, excluding tritium and dissolved gases, exceeds 2.5 Ci/ reactor / calendar quarter, the licensee shall. cake an in- '
vestigation to identify the causes of such release rates, define and initiate a program of action to reduce such release . rates to the design objective levels and report these actions to the Cca:nission within 30 days from the end.of the quarter . . . . . ... . - - , during which the release occurred. , 1.2. KulMUM PERMISSIBI.E CO:!CE!!TRATIO::S
' The M?C values used in. determining allowable liquid radwaste release concentrations are taken frcm 10 CFR Part 20, Appendix B. Table II, Column 2. Release rate and dilution ratio for each batch are de-
, termined by a mixed nuclide MPC calculation performed before the re .
lease of the batch. To fat.ili ta te the mdasurements and calcula tions , the nuclides of Column 2 unich can be produced in a fission reactor
- have been grouped according to MPC value and type of radiation as shown in Figure 1-1. - .
e , (1)
The concentration of each of the 20 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 lt att is computed from the ueasured data for that sample. Only two pure beta emitters, Sr-84 and Sr-90, have MPC values less than 9 X 10 6 uCi/nl. Individual measurenents are made on proportional composite liquid radwaste samples to determine the Sr-89 and Sr oD concentration or MDA value to be applied to individual batch release calculations. Although the MPC limit for tritium is greater then 9X 10 - 6 , a separate measurement is made for tritium since the gross beta technique does not provide an acceptable tritium measu"ement. A distilation and liquid scintillation counting technique is used to measure tritium concentration. The maximum activity of gamma and beta emitting nuclides with MPC values greater than 9 X 10-6 uCi/ml, except for the 29 nuclides noted above, is determined by gross gamma and gross beta measurements. Measurement sensitivity linits of approxinately 2 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 measured directly. The sun of the ratios, I(Ci/MPCi), for alpha emitters can be shown to be less than 0.1 by a null measurement with a sensitivity limit of approximately 1 X 10 -2 cpa/ml. Gas flow counting is used to achieve the required sensitivity of measurement. Thus, except for radionuclides produced in negligible quantities in a fission reaction (eg. I-125, I-129, etc.), the methods outlined above provide a means to assign a quantitatively measured or MDA value to all nuclides in Colunn 2. These measured and calculated concentration values for each batch are used to calculate the dilution ratio, release rate, and dilution rate prior to release of each batch. Both the concentration and release data are stored on a computer disc file. The disc file data is used to assure that quarterly and annual relea e limits are not exceeded. Bases used for the data of Table 1-1 are as follows: A. Fission and activation products-The total release values (not including tritium, gases, alpha) are comprised of the sun of the individual "adionuclide activities .nd include the LLD concentration of all isotopes that were not measured but did not meat the mininum sensitivity li mi t as set forth in our Envirannental Tech Specc. This se is for each batch 4 - released to the river for the respective quarter. Percent of applicable limit is determined from a mixed n u e .* i d e MPC cal ci:1 a t t re . ha wc m ca mnecer m'4-- Nr ot* w' 4 (2)
summed over all batches is divided by the corresponding individual MPC value. The sum over all nuclides of the Ci/MPCi ra t i os times 100 is the percent of applicable limit for ef fluent 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 lo - 3 aci/ml, is converted to percent to give the percent 01 applicable limit. C. Dissolved and entrained gases - Concentrations of dissolved and entrained gases in liquid effluents are measured in each batch by Ce(Li) spectroscopy on a one liter sample from each liquid radwaste batch. Dissolved and entrained gases for which measured or MDA concentrations are determined include noble gases with half lives greater than 8 hours; Xe-135, Xe-133m, Xe-133, and Kr-85. Iodine radionuclides in any form are also determined during the isotopic analysis for each batch, therefore a separate analysis for possible gaseous forms is not performed because it would not provide additional information. A conservative release limit, the maximum sensitivity limit of 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. D. Alpha measurements are taken monthly from the Liquid Radwaste composite. A study was instituted in July to determine if the catio method, as described in the E.T.S. Table 2.1-1 footnote e could meet the LLD of 104 of the MPC value specified in 10 CFR part 20 Appendix B, Table II, column 2. That limit of 3 X 10 -9 uCi/ml was never exceeded during the study. Below is a summary of the study findings. PallC_FEIUCD _DIEECI_tS-350.EiE'!1_t'Elt*M FRIMARY PRIMARY LRt4 LRiJ LRt1 COOL /WT COOL /WT CC"PCSITE CROSS (LPHA C O-E.o CPO35 ALPHA CO-E.o ALPHA __t'O' JIB _L*J1I _lutiZull __lutil:1) lutilt-il __lus1Zell___ _IniZolf JLLY_23 1 _E.13_E:C __2 E E _C:3____ _5.?a_E:2 2,EH_E:10__ _2.91_E:9 nUG_70 I J S _r _ m _1.EZ_E:0 __1d LErla__ .hE9_E:11 ict >I_7 d _ __ __1__1____7 1.10_E.-__1.20_E:9 4 2.F '
- 1.El_E-2 _2J1_E:1R_ _1.12_E:10-LCI_2S __1____ I __Lo0_E:10___}_2.eZ_E:2 hcS_E:1.'i__ . _1. 5 3_ E:10.. _ _ _ _ _ __ _ ____ _
tm_ Z S_ __. __1____3__1.CS_E:S 1dC_Cru ..__LE0_E:3 t_C.Ci_E:2 E 07_E 12__ _L 19_C:10.__ ECC_2C . _1 3_1dLE:3 _S.??_E:10___1_2 I2_E:2_____ _1.E9_E:12__ 742_E 11.._ _ J6N_73 __1 J_2.20_C:n ___5 J2_E:10___l_2J9_E 2_ E Jo_EriS__ ._adl r_ m JLLY 23.__. __ f _ J 5.50 5:2____ _hC2_E 10___l1C. 1_E:3_____ __l,?l E:11__ ._3.R E _ ..___ .___.___ 6LC_2S. . __e_____EL E L E C ^___[___L 01_ E 11___ L _ E d i E: L__ _. .. Ba a _E :12__ .:.57.E:11._ _____________. LCI_I L __2_____ h hCi l :12___L__l a _: 2__ __ -_.1. Ihl:2 ___J _L." 2: t t <_1 = c m DC LIo 3 __11L 921.E 4 - 1 Id o_L:10 L 22_ E:2_ _ __._ _L95_E:12__ , _ S.1? _ E: 10.._ _ __ . _____ kW_78 __2___ __111. C 2_ E:5 ? _ L E5_C:L___ _2.32_E:2__ L15.E:ll__ . 2.93_E ' 10_. __.____.._______ M C_liL.___ __2 . ___1_2.t sl:S _ __ L' _ _5.12 C :0__ _ J63_2S 2 ' EJL c ' _ L27_ E:10___L_1.e62:E- _7. l ?_E: S____...__1. 1 E.is_E:1L_ ^ 5_ E - 10_ .. k. . M J " 5 dLE:10_____. _
- conc ect zmted f rom LLn en = or = c m u t .c r pr ivi ttu t is s. , u ', L .* '% ,l. s s e! s n 'l< t . s 2 rad.uwtt a + 1 t' .s .i t it .,t co t a v a l . i ' io il<. farie i i+ m.u i t r .r.* s- '
(3)
1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADI0 ACTIVITY. Details of the analytical procedures for liquid radwaste analysis are contained in . operating procedure HNP-7601. The following measurements are performed as indicated: MEASUREMENT FREQUEllCY MET _ HOD
- 1. Gamma Isotopic Each Batch Ge(Li) spectrometry with on-line computer.
- 2. Gross Gamma Each Batch 2 X 2 NaI well crystal counting 3 Gross Beta Each Batch Gas flow proportional counting
- 4. Sr-89 Monthly Chemical separation and composite gas flow proportional counting
- 5. Sr-90 Monthly Chemical separation and Composite gas flow proportional counting
- 6. Tritiun Monthly Distillation and liquid Composite scintillation counting
- 7. alpha Monthly Gas flow proportional Composite counting
- 8. Dissolved Gases Each Batch Ge(Li) spectrometry with on-line computer O
O "ak (4)
a If a liquid radaaste tank cannot be reproccf. sed, a sar.;ile for cualys i'. is tcLen f rom the tank af ter the required recircnlation t ire 2. The sc71e i used fo:' gr.n-ray s;u cctrasco;n , gross gam cr.d grc;s beta ccanting, and for preparaticn of a co:.gosite scrple. The Ge(Li) detector syste.cs censist of a 135 and two 15% efficiency, 2.0 FD:M resolutica detectors in 4-inch thick lead snields. A ene-liter radaaste lic.uid serale is solidified in e ;Crir. cili beaker in ;,repa-ration for c 200DCC03 second Ce(Li) count. A peak search of the resulting ger a ray spectru::: is perfort.:ed by the en-1ine cerruter systen. Energy cnc net <ount datc for all significant peaks are de-terr.ined, cnd cuantitative reduction or I:'.A calculations are performed fcr the nuclides listed in figure 1-1. The quantitative calcula-tions include correcticas for ccunting ti. 2, cecay tir2, sarple volume, ser.ple scoretry, detector efficiency, baseline ccu:its, and branching ratio. On cciculations, including the above correcticn:;, ere nada based on the ccunts in two star.dard deviations cC the bcseline count at the locatica en the spectre where a paak for that nuclice ecuid be loccted if present. Tha calculated radicduclide concentrctior.s or I'CA values from the crra sccn ard frca previously stored Sr-P.9 cnc Sr-E0 value; are used to caltclate the dilutica ratio T (Ci/PCi) and clle. able release pcrcraters. A scrple printout is shr..a in Figures 1-2 and 1-3. 3 The Liquid P.cdasste Discharge Perr.it Printout is transferred item by i te 1 to tc.e first ::crtica of the release pcrrit (Figure 1-4) by a ~ laboratory technicicn. Altho: p the computer could printout the release pernit cr.d will infcrn the tcchnician if e batch can ::t be dismrgtd as desired, c ranual transfer of calculatcd results to the relecse perait by the technicicn was icpieranted as core likely to catch cbr.crcal ccnditions in the d2.c-The liquid rc
- caste ronitor settini; is cciculated by the cer: uter bcsed er the gross gar /:a cctivity cs measu:e.d in the sur;)le used for laboratory cnclysis. A ccefficient hcs bc:n datcrrir.ed '.hich reictu laboratory grcss gama cc;nts to the renitor count rate. I f the ermi .or count rcte exce:5s the cf.lculcted settin? 'aring dischcr_: 0, than ti e lie. rid mss r *..y "1 ~. ." *M
.. m r. ". .. ". a" #~
o r~d. Pe,m. u . o "m. 's '. m. _ c '. 's .o. . oe .=. . '. a. Which Uas analyced in the lab. I. r ;nitor raidin~ in excess of me cal-culatcd set;:cint therefor - results in cn tuttnatic terrin?tica cf the liquid ef fluev. distn:rg . Licuid ef fluent dischcrce is clso cuto-raticalb tcrmnater if the dilution fic'. rate feils belc; the flat ra '. e used in the cccputer calculation. L' hen the relcasc peri:it is returned frcr, R6as te Operations fcilcenr.g discharge, the discharge dsta is ccmbined with tne analysis results en the corputer disc file. The disc file r:y be scanned to display trends in cny recorded ;, arc ..eter, or av ba sumed for reporting ;.ur;cses cs she.m in figure 1-5. t E
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 cal cula ti on is performed in the Ge(Li) spectrometry system with computer datw reduction using the liquid Radwaste Library which includes gssses. Several comments are indicative of the success of the HNP liquid radwaste program during this reporting period:
- 1. The total measured activity released in liquid effluent was 6.99 E-03 curie for the third quarter and 7.81 E-03 curie for the fourth quarter. These values were approximately 1/1430 and 1/1280 respectively, of the allowed 10 curies per quarter.
- 2. The radwaste release procedure strongly emphasizes reprocessing rather than discharge of liquid radwaste.
During this report period only 17.3% of the liquid radwaste reaching the sample tanks was discharged: 82.7% was recycled back inte the reactor water system.
- 3. A complete isotopic scan, gross beta, and gross gamma counts and computer analysis were performed prior to the release of each of the 180 discharge batches.
1.4 BATCH RELEASES Regulatory Guide 1.21 Tables 2A and 2B are found in this report as Table 1-1 and 1-2. Data is presented on a quarterly basis as per Regulatory Guide 1.21. If it is requested, a monthly ta b ula ti on will be submitted. Other data pertinent to batch releases of radioactive effluent is as follows: Nrmber of batch releases: 180 Total time period for releases: 22885 minutes Maximum time period for a batch release: 198 minutes Average time period for batch release: 127 minutes Minimum time period for a batch release: 18 minutes Average stream flow during periods of release of effluent into a flowing stream: 3583 CFS .~ , - (6)
a
.
- l-Igure 1-1 g
FIGURE l-l' !;ET!:005 CT !;ECTI:;G ibtE II, CCLL'P.i 2 ITC L! itTS
' (;PC FA';CE Ca? ?'.A-RAY
[iETA . -
/J.PHA .
E11111EP.S Efil TI ECS JU Ci/r.Q__ Eft 1TTERS
]__131.I-13?.!-l'33 ' Sr-09,5r-90
-6 1-135, Cs 13' - (Separatien and $s
<9 X 10 Flow Countin.3)
, ( Ce(Li) Cam::a-Ray -
Spectroscopy) /J.L
-(G a s Fi c.'.! C0: n t ir.g ,
Sensiti.ity 0.01
. , , CPli/r.:1)
Pa-t a -140.*h-2 4.Cu-C
- Tritium .
,C_0-60,Fe-59 Z,-65 (Distillatien cr.d Lic;uid Scintil-
._ 6 X 10'0 Aa-110.7, l',- E d . Co -5!) lation Countir.g) 2r-l'b-SS . Cs .D 2 -137
./s-76, F-18. Cr-51
[.11 others . (Cr.s Flc.. Ccentir.g
!!n-239, Cc-lfi Sensitivity -2 -
l'.o-Te- 09, Cr-Pr-l a 4 CH:/.r.1 ( Ge (ii) Ca.:.rA-P.2y .
. . _ Spectrosccpy) .
/sil_ ethers t
'(Gross Cura '.lcil 1 -
Counter; car.s i t i vi ty -
% CP:V:.:i .)
e
. O g * . . .
3 (7) -
FIGURE l-2 Ps.ctorm 1 Estcha 420 [ Tsnt: C.: 3 T 5 Orerator: JLA C o r..ru n t : HIGH EVE'YTHING Ran dste: 10.'25/72 1549 Count Itsrt d at e: 10/25/7. Sample 4 31 >..ra : 10 00. 0 3 ra l 1407 Ge o i.e t r y code: ILHE-0 C1cct t i na : 3000 zect Live time: 3000 sec; D=tectock 9 f tC A s 3 L i br se p: L.O.ill E 2 Ernrgy(k e V)= .57 + 1.000+Chk + 0.000E-00*Ch4^2 + 0.000E+00-Ch4"3 : 10/25/75 0136 E t' f = 1/C6.669E-03 + E^( '.1275E+00) + 212.424 + E^<9.1062E-01)] : 10/01/76 06?6 uhere E= Energy i n fle V. ISOTOFE ENERGY CONCENTPATION ERRGR H?C Citt: C (kev) ( uC i /ra l ) ( u C i / nil )
=============,============== ========= ==============<uci/nt) ==_========================
Ce-144 133.54 (9.73?E-05 Tc-99m 14_T . 5 0 ~ IE-05 <9.~2E-07
- 1.203E-09 3E-03 Ce-141 145.40 f.4 . O ! E -0 6
< 2. 3 ?0 E-0:: *7 t - 0 3 Np-239 ~277.60 (2.592-04
<1.169E-07 ~1E-04 <1.17E-03 Cr-51 320.26 3.300E-0E 1.672E-07 I-131 P_6 4 . 5 0 2E-03 1.90E-03 (1.787E-05 3E-07 (5.96E-02 2n-69a. 435.50 <1.545E-05 W-1?? 6E-05 <2.5?E-04 479.50 <5.994E-03 6E-05 <9.99E-04 F-12 511.07 (6.243E-02 I-133 529.50 SE-04 <1.27E-04
<1.862E-08 IE-06 (1.36E-02 Ea-140 537.40 <7.409E-05 2E-05 As-76 559.10 <3.70E-0?
<4.035E-03 .
OE-05 <2.02E-03 C2-134 605.10 6.718E-05 1.55SE-03 C3-137 9E-06 7.4fE-03 661.99 1.870E-07 2.62?E-03 2E-05 No-99 9.35E-03 739.70 <1.319E-07 4E-05 <3.20E-05 2r-97 743.50 <2.061E-05 Zr-95 2E-05 <1.CIE-03 756.87 <3.540E-09 Hb-95 6E.-05 (5.90E-04 766.06 7.932E-03 1.601E-03 1E-04 7.98E-04 I-132 772.60 <1.734E-02 Co-50 SE-06 <2.17E-03. 010.76 3.333E-07 2.942E-03 9E-05 tin-54 634.99 3.70E-03 1.643E-07 2.SO4E-OS 1E-04 1.64E-02 A ;- 110 ra 954.70 <3.440E-OS 2n-65 3E-05 :1.15E-0? 1115.63 1.635E-06 9.282E-08 1E-04 1.69E-02 1-135 1260.50 <2.391E-05 4E-06 <5.95E-0? Fe-59 1291.58 (4.15GE-OS Co-60 6E-05 '6.95E-04 137: 2.53 1.033E-06 5.321E-OS 3E-05 C..-64 2.51E-02 1 ? 4 5. C-: 0 :1.70?E-06 2E-04 Hs-24 ' i' . 51 E - 01 I?65.55 :1.369E-05 3E-05 <!4.565-04 Ls-140 159i.60 '3.561E-09 2E-05 <4.IBE-3, Mn-56 1811.20 :2.702E-03 1E-04 !2.70E-04 c.r -:: : e. E E T A i 1.510E-05
? -90 4.?40E-09 3E-06 5.0iE-02 (EETA) :7.190E-0? 3C-07 '
'2.40E-02 M e u u r + .* tor +14 7.415E-06 2.;21E LLD t c 113
. . : 'c E '- -
,I.604E-Oi Tot al s < 1. 4 t E -01 1.001E-05 2.24E-01 (8)
~
J
ol:;0t.VED GiiEl FIGUhE 1-3 M -t?? 63.99 ' 2. 76 2E-0:2 4E-05 <: 6 790E- 04 V. -:30 19i.10 s 2. 5 M E-03 ' .. a ' .
^ ' ~
.4E-05 -
- 6.49E-04 X s - 13 3.. 2.;3.11 1.326E-07 ~4 E'- 0 5 <3.11E-02
': -125 I + '.4 . 6 0 ;1.422E-0? 4E-05 s3.5tE-04 K r -8 5 a) 305.00 . 8. 6 6 ?.E-0;i 4E-05 :2.17E-02 f ? - S .' 407. 70 <!.235E-05 4E-05 43.21E-04
'c-132 434.40 1.4??E-09 4E-05 (3.72E-05 Mea 2ured g as
- ot al s 0.000E+00 0.000E+00 0.00E+00 LLD gas t tal2 <3.012E-07 (7.53E-03 T .t al g al 3.013E-07 7.53E-03 i
t l GPG35 ACTIVITY l Countir Grcas 2ackground T i ru e voi tie t Error i Cc mt2 Coun*,5 (fli n) ra l A c t i v i t y ( c p r; / m l ) 1 Si;rs' a Will Crys t al 1731 1570 20.0 2 4.0?E+00 1.44E+CO: P r c.pe r t i on al 213 200 10.0 2 6. 5 0 E-0.1 1.02E+Ca; I m. E 5 T I fl A T E D 'J A 5 7_ T AtiV. VCLU lE= 6563.00 g al 1 :<ns E3'IMATED ACTIVITY THIS LATCH = 1.84E-04 Curies ( 1.84E+0- fli c r c.c ur i es .s ! QUARTERLY A C T I V I T'. RELEASED THF.Ov0H THIS LATCH (Ci)= 2.10E-03 PEi!CEliT OF TECH ?.:-EC L IllI T = 2.10E-02 12 M0llTH ACTIVITY EELEASE3 THPCUCH THIS E6TCH (Ci>= 1.57E-02 l P ER C Elli CF TECH ?PEC LlflIT = 7.86E-02 THE ACTIVITY OF THIS ERTCH IS 184.42 UCURIES THE ri A X IilU t1 YOU UAtiT TO RELEASE 19 100 uCi THEFEFORE YCU IJEEL YOUF S UF ERV I:i OR TO OK THI5 RELEASE i I Liquid P a d u a 2.t e Pe 1e ase i.u nce, ar.i 1 ) fl.r as . r ad i o-nuc l i de conc., e:x c l ud i ng g a s .r 2 ( uC i ,'n t ) : 7. 4 2 E -- 0 6 +- 2.22E-07 2 ) C al c u l a* .E d LLD c on e nt r at i on. .xcluding dissolved gase2 ( u C i < ra l ) : 2.60E-Oi 3 )C al cul at e d dilution r at i o ( C,' t1P C o f' ru s a s . 2 L L D , i nc l ud i ng g as s t .' : 2.~1E-01 4 y lli n i r..e ra dii.ition i' l o n r t' at e ( g r. rn ) : 10000 S i rl s ..u a t a n.' dischargs t'!cs r a t .E 2 ( g c i .' : 21355
/
6)ip+cified t v.t. ( i t.) r at e ( g p i.. * : 75
? >P id in r e c.. . n i e o r trip 3 *t ing: 427 -
A = 4 - ...i i1 c i i r. t C F r* .1 I = ..I . : r. *:r IG i C = 6. . s . t: i :r 'T pir 11. C . C F:' . . ' F = . , . . , - .
. F . . r .i 3
- L t i t. a' i d : . .n : . . o' .s.
. r.uc l i di s at pstr' :( 41 + a; ' ...I'
. .il: 5 %iC-03 In\
FIGURE l-4 ~ EATCH ti0.
-FC i 1 F L *.';T 't'. I. HATDI tl NIT /
L tr[jto ?; g_;ii Lists;.g ,: E:uiT T/..';X TO EE T.ELEMED .. D? 'E / / RfA'Cri FM ?.ECE35ITYlI'5fb:! GL RECIF.C. SI'RT TIME 5/ Pii I IME F.ECir.C. LutJIL:4 :iti .
- 1. LAC 0F',iCU ?MLYSIS (1) F:etsured bdicr.uclide Cenccntraticn E + t cCi/nl (2) Ca.lculated CA Li..it Ccnctntrati:ns tCi/al (3) Calculate: Dilutisn Ratic: I(Ci/MFCi) ~
(4) flini. rt Oilutio 1 Flev Eate GP:4 (5) Calculated Tank Dischar;2 RU.t. (41/ (3 ) - 1 GP:( (C) $; acifie ' Max. Tank Ci::h:r;c Rate: <(5)/2 GIF. (7) F.civaste Menitcr Trip Setting: CPS A = k' ell Ccunt CFH/nl ' E = Mcnitor ES CPS C = Mcniter CFS F = Conservative
, .per k'.C. CF?./ril Facter Maniter Alarn Sc.trair.t (CFL) = (C x -A x F) + B + 3[f Co.mcsite Liter Stered:
c;gpjg ca ;,y gate:
.Tinitials)
~
II. CFEF.ATIC:;S IMIT. is) Lic;uid Phaste 5'enitcr Trip Set at: CPS - (9) Ccnfiracd Ciluticn Fic.tF.:te GFM (10) _ Valve Lineup Cted.ed as scr i:." P- _ *
, . g
.e ar..K vis. c;- D i s . r'e t e io s . i c a .r i u, v . c :.
Datt r N: cite:y T i.. +_ _ leva.l
._m . ~t __r :c e ~ in.- c .
-=_.__
0 7 . C _.el. __._-=m._-ft. US - Start ' End ..I, i
~
Durcticn "' - ic tar C I- Cc p Etcd 6y: D[te:
*0 10 ein. after start
";. f t e - flufnie.n III. LtsCCRATOP.Y .
1 (11) Tatal TW. Volu c Dishpd 221. x 3. 7C 5 x 10 ' c:l/ g t l .] f:al f (12) 1:tal1:::.ityPi:cr..tr?..[(1)x(11)] UCi (13) Ri.-:r fica U te (frc.a ill.F. 2.4-6) Cf3 { (c. ,iletcc. L/ : UJte:.
-}
}
K'i?-1 7.QI l
, ,w. w.: s c,. i. e:m a !
(10) , i
FIGURE 1-5 tiquid R adu. as t e D at a Compi 1 at i on for Reg. Guide 1.21 Report E. I. Hatch Nuclear P1 ant UNIT 1 Tot al Activity (Curies) Qu art e r 3, 1978 Quarts-r 4 1978 Eatches 317 thru 404 Eat c hes 405 thru 496 H am e Me as w e d Error High LLDI Total Me azured Etrcr Higi- LL0s Total , Ce-144 0.00E+v0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0(E+00 0.00E+00 0.00E+00 Tc-99a 0.COE+00 0.00E+00 0.00E+00 0.00E+00 0.00E400 0.0tE+00 0.00E+00 0.00E+00 Ce-141 1.19E-06 3.76E-07 0.00E+00 1.19E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Np-23? 0.00E+00 0.00E+00 0.00E+00 0.00Ev00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 6.00E-05 3.00E-06 0.00E+00 6.00E-05 1.42E-03 3.03E-05 0.00E+00 1.42E-03, I-131 5.10E-06 9.14E-07 0.00E+00 3.10E-06 4.88E-04 6.97E-06 0.00E+00 4.68E-04 2n-691 P.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00l U-187 6 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 F-13 5.70E-04 6.01E-06 0.00Ev00 5.70E-04 S.50E-05 4.57E-06 0.00E4 00 8.50E-05, I-133 7.62E 3i 1.31E-06 0.00E+00 7.62E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba-140 0.0CE+00 0.00E+00 0.00E+00 0.00E+00 1.70E-06 1.70E-06 0.00E+00 1.70E-06 As-76 9.91E-07 1.45E-07 0.00E+00 8.91E-07 2.98E-06 1.23E-06 0.00E+00 2.98E-06, Cs-134 3.73E-04 6.32E-06 0.00E+00 ?.73E-04 1.33E-03 1.09E-05 0.00E+00 1.33E-03i Cs-137 6.74E-04 3.56E-06 0.00E+00 6.74E-04 1.52E-03 1.27E-05 0.00E+00 1.52E-03' Ho-99 3.67E-05 7.54E-06 0.00E+00 3.67E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2r-97 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2r-95 1.45E-05 2.13E 06 0.00E+00 1.45E-05 3.48E-06 6.55E-07 0.00E+00 3.43E-06 Hb-95 3.93E-05 1.6SE-06 0.00E+00 3.93E-05 1.58E-05 1.63E-06 0.00E400 1.58E-05 ( I-132 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 1.97E-04 5.23E-06 0.00E+00 1.97E-04 2.06E-04 5.14E-Of 0.00E+00 2.06E-04 Mn-54 1.96E-04 5.02E-Of 0.00E+00 1.96E-04 1.12E-04 4.04E-06 0.00E+00 1.12E-04 A;-110m 5.83E-07 2.60E-07 0.00E+00 5.,83E-0? 3.11E-06 6.97E-0 0.00E+00 3.11E-06 2n-65 2.10E-0? 2.?!E-05 0.00E+00 2.10E-03 1.45E-03 2.05E-05 0.00E+00 1.45E-03 I-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 Fe-59 3.37E-06 1.3EE-06 0.00E+00 3.??E-06 0.00E+00 0.00E+00 0.00E*00 0.00E+00 Co-60 1.09E-0: 1.15E-05 0.00E+00 1.09E-02 E,12E-04 1.07E-05 0.00Et00 8.12E-04 Cu-64 2.4?E-04 2.69E-05 0.00E+00 2.4?E-04 0.00E*00 0.00E+00 0.00E+00 0.00E+00 Ha-24 3.12E-04 6.45E-06 0.00E+00 3.12E-04 2.01E-04 5.90E-06 0.00E+00 2.01E-04 La-140 2.646-07 1.61E-07 0.00E+00 2.e4E-07 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.P'E+00 0.00E+00 0.00E+00 0.00E+00 C5-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.c9E-04 4. 01 E- 0 6 0.00E+0? 1.29E-04 Hi-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.84E-06 1.15E-06 0.00E+00 1.?4E-06 3r-G? 9.31E-04 2.40E-05 0.00E+00 9.31E-U4 1.97E-05 4.18E-06 0.00E+00 1.97E-05 Sr-90 7.28E-05 1.39E-05 0.00E+00 7.28E-05 3.66E-06 8.43E-07 0.00E+00 3.66E-06 Totils 6.99E-03 4.94E-05 0.00E+00 6.99E-03 7.31E-03 4.SSE-05 0.00E*00 7.81E-03 se-133 4.40E-03 '.01E-06 0.00E+00 4.40E-0? O.03E-05 3.9GE-06 0.00E+00 8.03E-05
<-135 1.21E-05 7.61E-07 0.00E+00 1.21E-05 6.50E-05 2.41E-Of 0.00E+00 6.50E-05
' r- 131 : 0.00E*00 0.00E+00 0.00E*00 0.00E+00 0.0aE+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 "2-1330 4.95E-05 1.73E-06 0.00E+00 4.95E-05 0.00E+00 0.00E+00 0.03E+00 0.00E+00 L -85, 1.5?E-06 5.09E-07 0.00E+00 1,59E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 K -87 0.00E+00 0.00E+00 0.00E+00 0.00E*00 0.00E+00 0.00E+00 0.00E-00 0.00E+00
(. de-17.? 0.00E*00 0.00E*00 0.00E+00 0.00Et00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
-: e - 13 5 m .OJE+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 T: _ _ ;t. -
7.28E-06 0.00E+00 4.46E-Oi 1.45E-04 4.65E-Oi 0. 0 2 E + < _ 1.45E-04 (10
TABLE l-1 i
/ E. I. Hatch fluc 1 c ar P 1 a r,t UtilT 1 l j
E F F LUEtiT AtlD 11ASTE DISPOSAL SEIII Atit4U AL REPORI 1978 LIQUID EFFLIJEt4 f S-SUtitl AT I Oti 0F ALL ?ELEASES Unit Guarter Guartcr Est Tot al 3 4 Error . A. Fis2 ion '. ac t i vat i on products t
- 1. Tot al re l e as e (not including H3 p a s e s , a l r.h a ? Ci 6.99E-09 7.81E-02 4.24E+01
- 2. #eerage diluted c onc ent r at i on 1
durir.c ceriod u C i ',i l 8.62E-09 1.14E-08
- Oer c e nt of arip l i c ab l e limit :. 9.11E-0? 2.A2E-01, B. Tritium :
- 1. Tot al release Ci 1.22E+00 1.60E+00 :.22E+01I
- 2. Average diluted c onc e nt r at i on !
during neriod u C i / ra l 1.51E-06 I.34E-06 l __ ? Dercent of applicable linit " f-
. 5.02E-02 7.81E-02, C. Dissolved and e nt r ai ned gases
- 1. Tot al release Ci 4.46E-03 1.45E-04 1.9aE-011 I 2. :tve r age diluted concentration I during period u C i / ru l 5.50E-09 2.!?E-10 n
- 2. ercent of appl i c ao I c 1imit 1.37E-02 5.??E-04 D. Gross al pha r adi o ac t i vi t y
- 1. Tct al r e l e a s .= Ci 3.06E-06 1.25E-06 1.20E+01]
[E . ' 31un,e or uaste < prior to di1ution) Iiter1 5.07E+06i 3.2SE+06l 1.00E+01 1r ",1un2 of di1ution mater used 1iters I 8.08E+0C 6.E'E+I l 1.60E+0i ( (12)
.4
TABLE l-2 E. I. H at c h Nuclear Plant UNIT 1 i EFFLUENT AND WASTE DISPOS AL SEMI A!'HUAL REPORT 1978 ! I t i LIQUID EFFLUENTS j l CONTINUGUS MODE EATCH MODE Hsclide3 Fe l e as e d Unit Ouarter Guarter Quarter Quarter 3 4 3 4 Ce-144 Ci 0.00E+00 0.00E+00 T c - 9 9 rn ci 0.00E+un 0.00E+00 Ce-141 Ci 1.19E-06l 0.00E+00 Np-239 Ci O.00E+001 0.00E+00 Cr-51 Ci 6.00E-05 i.42E-03 I-131 Ci 3.10E-06' 4.98E-04 Z n ~ 6 9:n Ci 0.00E+00 0.00E+00 W-187 Ci 0.00E+00 0.00E+00 F-18 Ci o.70E-04 8.50E-05 I-133 Ci r.62E-06 0.00E+00 Ea-140 Ci 0.00E+00 1.70E-06 As-76 Ci 9.91E-07 1.98E-06 Cs-134 Ci : 73E-04 1.33E-03 Cs-137 Ci 6.74E-04 1.52E-03 t?o-99 Ci "O I 3.67E-05 0.00E+00 Zr-97 Ci 0.00E+00 0.00E+00 Zr-95 Ci 1.45E-05 ?.48E-06 Hb-95 Ci 3.90E-05 1.58E-05 ( I-132 Co-58 Ci Ci 0.00E400 1.9?E-04 0.00E+00 c.06E-04 fin-54 Ci 1.96E-04 1.12E-04 Ag-110m Ci 5.83E-0? 3.11E-06 Zn-65 Ci 2.10E-03 1.45E-03 1-135 Ci 0.0eE+00 0.00E+00 Fe-59 Ci 3.37E-06 0.00E+00 Co-60 C1 1.09E-OS e,12E-04 Cu-64 Ci 2.49E-04 0.00E+00 Ha-24 Ci :.12E-04 2.01E-04 La-140 Ci 1.94E-07 0.00E+00 Mn-56 Ci 0.00E+00 0.00E+00 C5-136 Ci 0.00E+00 1.29E-04 Ni-E5 Ci 0.00E+00 1.34E-06 Sr-89 Ci 9.B1E-04 1.97E-05 Sr-90 Ci _ 7.28E-05 :.66E-06_ T T at al for period (above) Ci I 6. 99E-03F7. 81 E-O::- Xe-13? Ci [4.40E-03 9.03E-05_ Xe-135 Ci l ___ l 1.01E-05 6.50E-05 Xe-131m Ci 0.00E+00 0.00E+00 Ur-80 Ci 0.00E+00 0.00E+001 Ae-133m Ci 4.95E-05 0.00E+00 - Kr-85m Ci 1. '3 9 E - 0 6 0.00E+00
~ ~ ~ - Er-87 Ci 0.00E+00 0.OOE+00 l u-1 : Ci [_3_ 0E+00 0.00E+00 3 D, Ci ' O.00E*iO4 0.00E+00 (13) .
2 GASEQUS EElll!i.'ITS . 2.1. REGULATORY LIMITS.
- a. (1) The release rate limit of noble gases shall be; UQ is .9 E + 1.0 Eg 4 Qjy 11 Ey + 44 ED 11 i+n - - -
where Qs = release rate from main stack in Ci/sec (elevated release) Qy = release rate from vents in Ci/sec (ground release) i = the individual nuclide. n = total nuclides. g Ey = the averr.;e garca energy per disintegration Eg = the s 'a beta energy per disintegration , (2) The release rate limit of all radioicdines and radio-active materials in particulate form with half lives greater than eight days, released to the environs as part of the gaseous wastes, shall be: 2.7 X 10 Qs : 3.9 X 105 Qy 51 Uhere Qs = release rate from the main stack in Ci/sec (as elevated release) Qv = release rate from vents in Ci/sec (ground release)
- b. (1) The average rclease rate of nobie gases during any calendar quarter shall be:
'~~ ~ ~
+ h j'y
, , Qis 12 Ey + 3.0 Eg 66 Ey + 140 Eg i1 1 -> n ,
(2) The average release rate of noble gases du' ring any 12 consecutive months shall be: .-
- \
,> ;Qi3 p24 '
Ey + 6.1 Eg._ 4 Qiy 130 Ey ,i .270 Eg <1
. i -> n - -
(3) 1he average release rate of all Iodines ar.d radioactive raaterials in particulate form with half lives greater than cight days during any calendar quarter shall be: 3.3 X 105 Q3 + 4.9 X 105 0y 51 (4) The average release rate of all. Iodines and radioactive materials in particulate form with half lives greater than eight days during any period of 12 consecutive t.anths shall be: . , 6.7 X 10 5Qs 4 9.7 X 10'Qy 1 1 , , (14)
(.,Uancunt of lodine - 131 released during'any calen-dar quartar shall not excced 2 Ci. (6) The amount of lodina - 131 rele.' sed during any period of 12 consecutive n:caths sh)11 not exceed 4 Ci.
- c. Should the conditions of 2.lc (1), (2), or (3) listed belc.t exist, the licensee shall make an investigati'on to identify the causes of the release rates,. define and initiate a progren of actica to reduce the release rates to design
' ebjective levels listed in subsection 2.4, of the IDP-ETS and report these.ac,tions to the Commission within 30 days from the end of the quarter during unich the rdicases occur-red.
(1) If the average release rate of nc51e gases during any
. calendar quarter is:
.) Qis ' G Ey + 12 Eg + Qiy 260 Ey + 500 Eg >1 1+n -
(2) If the averare release rate of all Icdines ar.d radio-active materials in particulate form with half lives greater than eight days during any calendar quarter is:
- 1. 3 X 105 Qs + 1.9 X iC Qy >1 (3) If the a:Junt of Iodine - 131 released during e.ny cal-endar quarter is greater than 0.5 Ci.
- d. The offgas monitor shall be operating and set to alarm and to i
initiate the aupcatic closure of the waste cas discharce ' valve prior to exceeding the limits specified in 2.la (1) above. The operability of the automatic isolatica valve shall ' be demons trated quarterly. -
- e. If the offgas monitor is.not operating, a shutdown shall be
" initiated so that the reacter will be in the hot shutdown
, condition within 10 hours.
, f. If the release rate of noble gases frc:a the main condenser vacuum system is: ~
/ ,Qis 24 Ey + 6.1 Eg >1 1+n 4__ _
~ for a period of greater than 48 hours, notify the Conm.ission in . writing within 10 days, identifying the causes of activity. Tac report should includ2 the flcu rate of the offgas frc:: the m2in condenser vacuum system and the activity ceasured downs tream of the main condcnser vacuu:a syste:a prior to holdup and at a point upstream of the point of release. : 9 The reactor containa:ent shall be purged through the s tandby gas treatment system. , .
,h. A hydrogen n:cnitor in the of fgas line downs trea:a <. the recombiners ,,
shall be opeiable during pwer eperation. If the hydrogen concen-
, tration reaches an alarm set point of four percent by volume. the o f fm f M.i .211 le . te,. . by c'o:in ; .. 1- <
<...mi. i at tht. rt cc:.Q ; :rs .
'(15) _. . . ... -.-. _ ~ .- .4
Whenever the hydrogen monitor is inoperable during power operation, grab samples shall be operable during power operation. If the hydrogen concentration reaches an alarm set point of four percent by volume, the offgas flow shall be stopped by closing the valves downstream of the recombiners. Whenever the hydrogen monitor is inoperable during power operation, grab samples shall be taken and analyzed for hydrogen concentration each shift. Calibration check of the monitoring system shall be performed weekly. 2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Waste gas release at Hatch I is confined to three paths. Each of these three paths is continuously monitored for gaseous concentration and each has an integrating type collection device which concentrates particulates and iodine for each seven day period (Procedure, are such that she tar collection times are used where applicabls to Technical Specification requirements). Each of these continuous samplers has a flow controller which maintains sample flow within about a 10 percent range over each seven day collection period. The offgas vent (elevated release) and the reactor building vent have flow measurement devices which continuously record the flow rate of the gas released (accuracy of these devices are within 10% of the actual flows as measured during preoperational testing). The recombiner building vent flow is conservatively assumed to be constaat at 500 cfm. In addition to the gaseous, particulate, and iodine release measurement; tritium, gross alpha, and gaseous isotopic measurements of each vent stream are conducted on a monthly schedule. After each ca .1 e n d a r quarter (13 weeks) a summary of waste gaa release from the three vents is compiled and as such is designed to meet the "cquirements for preparation of the 6- month recort as specirted in Regulatory Guide 1.21. The methods for compilation of the quarterly releases are as follows:
- 1. Fission and Actvation Gas The total curic release is determined from t'.e 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 in .i e c t io n of a known amount of off-gas into the sample chambers. The total curie release is calculated by the computer for each of the individual nuelides releaned. This number is multiplied by the average energy per Jisintegration (5 r &
Eg) and the coefficients in the release limit formula. All the nuclides are summed and stored in their respective dat'a fil e s until the end of the quarter. Then the computer - (16)
divides the sum of the nuclides by the seconds in the quarter to determine the percent of the tech, spec. limit releases.
- 2. RADIOIODINE RELEASES
_ Iodine releases are determined weekly for I-131, I-133, and 1-135, for each vent. Where significant activity is not measured MDA releases are calculated. Since calculated MDA's are below Technical Specification detectable concentrations then 0 (zero) release is used for the weeks with only MDA values. Weekly releases are summarized with the aid of the counting room calculator-computer system and a quarterly total is prepared from the weekly summarios. The percent Technical Specification for I-131 on Table 2-1 is based on the quarterly Technical Specification limit. 3 PARTICULATE RELEASES Particulate release are determined weekly for each vent. Ehere sig3ificant activity is not measured MDA rel_ ease is calculated. Since calculated MDA's are below Technical Specification detectable concentrations, then 0 (zero) release is used for weeks with only MDA values. Weekly releases are summarized with the aid of the counting room calculator - computer. After each calendar month the particulate filters from each vent are combined, fused, and strontium separation is made. Since sample flows and vent flows are almost constant over each monthly period the filters from each~~ vent-~ can be dissolved together. Decay corrections are made back to the middle of the monthly collection period. Again the counting room calculator - computer is used to aid in the calculation of the Sr-89, 90 release. Where significant strontium activity is not detected MDAs are calculated. In order to eliminate the need for a quarterly composite Sr-89 and Sr-90
~
activity is calculated for each monthly composite. The percent of Technical Specification was calculated using the quarterly average equation. 4 GROSS ALPHA RELEASE The gross alpha release is computed each month by counting the particulate fil t e rs each week for gross alpha activity in a proportional counter. The four or five weeks numbers are then recorded on a data sheet and the activity is summed at the end of the month.
- 5. TRITIUM R ELEASE Tritium samples are. obtained monthly from each vent by
pa ssing the sample stream from a cold trap immersed in a .
(17)
liquid nitrogen or an acetone and ice mixture. The grams of water vapor / cubic foot gas is measured upstream of the cold trap inorder to alleviate the difficulties in determining water vapor collection efficiencies. The tritium samples are analyzed by an independent laboratory. Fcom 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 calcualtlon forms. Hatch I has attempted to maintain all calculated MDAs as low as possible by counting samples longer than what would be normally practical. For example at this time all weekly particualte and iodine counting times are 3000 see and strontium separations are counted for 100 minutes. Regulatory Guide 1.21 requirrs 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.
"The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total ope"ation of sampling and measurement. Because it may be very difficult to assign error terms for each pacameter affecting the final measurement, detailed stattstical evaluations of error are not suggested. The object've should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste."
Estimated errors are based on errors in counting equipment calibration, counting statistics, vent flow rates, vent sample flow rates, non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges.
- 1. Fission and Activation Gas Total Release was calculated from process EoniEoE readings. -~
Monitor Error in Calibration 50% Vent Flow Rate 10% Non-Steady Release Rate 20% E0%
- 2. I-131_ Release was calculated from each weekly sample:
Statistical error 60% Counting Equipment Calibration 10% Vent Flow Rates 10T Vent Sample Flow Rates 10% , ,, , , , , ., ~ , . > - (18)
Non-Steady Release Rates 105 Losses Froa Charcoal Cart.idge 10% IIOJ
- 3. Particulates with half-lives creater than 8 days release was dominated by the MDA calculations for I-131 and Ba-La-140 hence the errors in the strontium determinations and gross alpha had negligible affects On the estimated err or in the-total particulate release:
Statistical Error at MCA concentration 60% Countng Equipment Calibration 10% vent Flow Rates 10% Vent Sample Flow Rates 10% Non-Steady Release Rates 30% I56J 4 Total Tritium Release was dominated by the reactor building veat' tritium Felease, 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% Vent Flow Rates 10% Counting Calibration and Statistics 10% Non-Steady Release 50% 96T 2.3.GASE003 EFFLUENT RELEASE DATA Regulatory Guide 1.21 Tablos lA, IB, and 1C are found in this report as Tables 2-1, 2-2, and 2-3. Data is presented on a quarterly basis as per Regulatory Guide 1.21. 3 SOLID WASTE 3.1 Regulatory Specifications.
- a. Measurements shall be made ta determine or estimate the total curie quantity and principal radionuclide cocposition of all radioactive solid waste shipped offsite.
- b. Solid wastes in storage and preparatory to shipment shall be monitored and packaged to assure compliance with the applicable portions of 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 171-178.
- c. Reports of the radioactive solid waste s h i on an i-a , f ol u wn ,
p ri nc i p al radionu'lides, and total curie quantity shall .be.
' submitted in accordence with subsection 5.6.1 of the HNP-ETS.
(19)
3.2 solid wante Data Regulatory guide 1.21 Table 3 is round in this report as Table 3-1. , ., , , . s .. . .s., -- .r-i ., (?O)
TABl.E 2-1
, EFr LUENT AND HASTE DIEPOSAL SEff! ANNUAL REPORT 197-GH5EOUS EFFLUENTS-SUrlt1ATION OF ALL PELEA'EEE '
Unit Quarter Ouartet Est Tot 11
- j. I, Hatch Nuclear P cr e r Pl ant UNIT 1 3 4 Error
- H. F i -; 2 i c. n ac t i o st i on g ase s 1< Total r c 1 c 13 e cj 2.5cE+c;
- 2. :h4 e r a g e releaze rat e for period 9,7;g,g;i g , o .3 E + a l J ;
u C t .- z e c 3.25E+01 1.21Ed O2' 1 ;. o f- Technical 2 pe c i(ic at ion l i rn t t
- 3.86E-02 6.34E-02l l
t F. Iodines
- 1. Total iodine-131 C1 1.04E-05 1.41E-03 i,,10E+02f
- 2. Overaw rclea e rate for neriad uCi-acc 1.32E-06 1.75E-04
~
of T echni c al apec i f ic at ion l i ra i t 5.18E-04 T.05E-02 C. Pa^t icul at e s
~
1 , F art i c u l at e a uith hal f -1 i ue - t O dav: C1 1.43E-04l 2.26E-u-[1.0dEt02
- . :o ie r a a e r e 1 e =.2 .r e at e f' o r period uC1/zec 1.81E-05l i.~;1E g 1 o f' Tac hn i c al syc 1 f i c a t i o n 11 rii t ?,51E-03l 1. 24 E-01 [ ,
i 4 Groza al oha radi cac t i ui t o ,, b;i 4.57E-06l 4.46E-061 l D. T r i t i u r. ( _1. Tot al relesse Ci 2.22EJ00 2.54E+ee[[9.00E+01[
? A u e r = ,: e r ,- 1 < a = 9 rate for
- r. . . r i o d oCi/2ec 2.E:2E-03 3 .16 E - 0__1_i c r Te_ 1,. a l spe c i f'i c at i on 1 i rii t
- 4 . 7 9 E + 0 0_i 4.94F+00i I
( (21) .
TABLE 2-2 E. I. H at ch th.c l e ar P cm e r P l an t- UNIT 1 EFrLUEHT AND URSTE DISPOSAL 3EMIANNUAL FEFORT 1975 GASEOUS EFFLUENTS-ELEVATED FELEASE CONTINUOUS MODE FATCH MODE Huciides Pel t az ed Unit Qu ar t e r Ou art er Ou art er Qu art e r 3 4 3 4
- 1. Fission g am e s Me-1 : C1 1.59E+02 6.45E+02 0.00E+00 0.00E+00
'e-131n Ci 0.00E+00 4. 36 E + 01 0.c0E+00 0.00E+00 Fr-88 C1 7.42E+00 3.47E+01 0.00E+00 0.00E+00 a-123H Ci 0.00E+00 2.16E+001 0.00E+00 0.00E+00 W-135 Ci 3.93E+00 1.80E+01 0.00F+00 0.00E+00 Vr-55M Ci 2.62E+01 1.30E+02T 0.00E+00 0.00E+00 1-131~ Ci 6.64E-07 0.00E+00l 0.00E+00 0.00E+00 Er-87 Ci 2.51E+00 9. 66E +0 JI 0. 00E + 00 --.0 00E+00
<(-130 C1 1.38E+01 2.13E+01l 0.00E+00- U.00E+00 1-137 C1 3.61E-02 0.00E+00! 0.00E+00 0.00E+00 H-13 Ci 4.75E+00 2.97E+0 Q 0.00E*00 0.00E+00 K r -:E 5 Ci O . uni!+ 0 0 0.00E+001 0.00E+00 0.OnE+00 4-135M C1 5.02E-03 6.30E+00 0.00E400 0.00E*Un
' 0.00E+00 0.00E+00 0.00E+00 1 Ci O.00E+00 Fr-S9 C1 0.00E+00 0.00E+00_1 0.00E+00 0.00E+00 I-125 Ci 0.00E+00 0.00E+00 0.03E+03 0.00E+00
{_ Ar-41 Ci _ .54E+00 1.14E+01 0.00Ew00 0.00E+00 Total for p.riod Ci 2.20E+02 9.62E+02 0.00E+00 0.OCE+00
- 2. Iodines 0.00E+00' I-131 C1 1.03E-05 5.47E-05 0.03E400 I-133 Ci I.34E-05 9.00E-05 0.00E+00 0.00E+00 I-135 Ci 9.90E-07 4.73E-05 0.00E+00 0.00E+00 Tot al rcr period Ci ?.97E-05 1 1. 92E -04 0.00E+00 0.00E+00
- 3. P-ar t i c u l at e 2 Sr-89 Ci 2.21E-05 2.05E-05 0.00E+00 0.00E+ne Sr-90 Ci 2.66E-07 2.27E-07 0.00E+00 0.00E+00 Cc-141 ~ Ci OT00E+00 0.00E+001 0.00E+00 0.00E400 Cr-51 Ci 0.00E400 0.00E+00 0.00E+00 0.fs0E+00 1-121 Ci 1.35E-08 2.05E-06l 0.00E+00 0.00E+00 c.1- 1 10 C' O.00E+00 0.00F+UO 0.00E+00 0.00E+00 la-140 Ci 0.00E+00 1.18E-05 0.00E+00 0.00E+00 C1-134 Ci O.00E+00 2.52E-Ot.! 0.00E+00 0.UOE+00 Cs-1?? Ci 0.00E+00 3.2 E-06 0.00E+UO 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E400
-' r - 9 5 Ci O.00E+00 0.00E+00 0.00E+00 0.00E+00
{ 0.0aE+00 g 0.00E+00 0.30E+00 Mb- M Ci 0.00E+00 Co-5. Ci 0.00E+00 0.00E+C01 0.0'E+00 0.00E+00 ( Mn-54 Ci O.00E+UO 0.00E+001_0.00t+00 0.00E+0m Fe-59 Ci 0. eut:+0 0 g 0.00E+00 0.00F+00 0.0DE+00 C c -- 6 0 Ci 6. 27E-07} 2.71E-07 0 0E+00 L1-11o Ci 6.97F-0; : . :. 4 E - 0 5 ; O . m'E + 0 0 0.00E+004 0.00E+00 l l T:' ! fa r + j Ci 2.27E-05 7.4 E-05! ' 00E+00I 0.A0E+00 (22)
TABLE 2-3 t_ . 1. H at c h fluclesr Pcmer P1 ant UtlI T 1 EFFLUEttT At4D UR5TE DISPOSAL set 116ttt4URL FEPO?T 197E i GA3EOUS EFFLUEt4Ti-GROUtiD-LEVEL FELEASE I C0t4 tit 400U5 II D I' E EATiH MODE tluc l i de s Fx ! ( Ai e d Unit Ouirter Qu ar t er Cu ar t e r 'u rter
? 4 ? 4
- 1. Fission g ase 2
_ ._ Tc - 1_3. :_ Ci 5_. 4 U E v 0 0 1. 0 7 E + 0 A I, _ 0. 0 0_E_+ 0 01 0 . 0 0 E + 0_ .0___ e-131h Ci e.UOE+00 0.00E+0Ul 0.00Ee00 0.00E+00 1.11E+0c._4 0.00E+UU tr-t'._ Li 2.5_Ec -U3 _. U.UOc+00 __ . < - 1 : 3_M Ci _ 9 . 7 2__E. - 0 2 3.56E-02 0,00E+00 0.03E-00 _
;e-125 l C' I_. 4 9 E + 01 5.?9E+00 0.60E+00 0.0+00, Er-5., i C1 1.92E-03 1.13E-01 0.00E+001 0.00E4 001 I-1_1 2 l C1 U.10
_ .- :+C0 0 . e_ u. -t+UO 0. __s0 e- U Uq e.00c+Un I r :, C1 1.21E-03 7.13E-01 0.00E+001 0.00E+00
<.-1:E Ci 0.00E400 1. 6'I E - 01 0.00E+00 0.00E+00
- e - 13 7 Ci 0._Cp3 E r 0 0 0.00E+00l 0.00E+001 0.00E+00_
r ^
- h-13 Ci 4.9%E+00 55E+001 0.0?E+0C 0.00E+00 Ur-5' 0.30E+00 0 . 0 0 E + 0 0 1 0 . 0 0 E + 0 '_' O.00E+00
.e - 12 5 :
( C1 Ci U .'0 0 E + 0 0 1.39E-02 " UeE-00 0.00E+00 ___I - 19 : Ci 0.00E+00 0.00E+00; 0.30E+00 _ _ _ _ t 0 . 0 0_E + 0_0_ t r - {: 9 Ci 1.19E-01 0.00E+00j 0.00E+C01 0.00E+00 I-135 C1 0.00E+na 0.00E+00! 0.00E4 00 0.00E+00 M-41 T Ci 0.00E+00 0.00E+00i 0.00E+00 0.00E+00 ( l Tctal fcr osriod l Ci_ 3.55E+01 1.11E+01 0.00E+0C 0.00E+00
- 2. 10dinc:
I-131 C1 4.76E-061 9.29E 141 0 . _' 0 E + 0 0 0.00E+00l I-13. Ci 3.42E-06 2.18E-04' O . .* 0 E + 0 0 0. 0E + 00 [ I-135 Ci 0.00E+00 6.29E-05 v.00E+0C 0.30E+00_ Tcs si for per od Ci 8.1: E-06 1.11E-02 0.00E+C0 0.00E+00
;. T ar t iculste; ]_ _ : - E
- l Ci *
. 44E-06 2.19E-05l J.00E+00 0.00E+0C]
- . r - 9 0 I Ci 8.10E-07 ?.94E-06j 0.OOE+0a 0.00E+00
_ Ce-141 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 3.50E-05 :.46E-04 0.00E+00 0.00E400 I-131 _ C1 3.t 1E-09 4.51E-04 0.00E+00,_e.00E*00 in-11: C1 0.30E+00 5.1?E-06! 3.00E+00l 0.00E+00 E4-14C C1 C.00E+00 0.00E+001 0.00E+C- 0.00E+00 C 5-1 ? Ci 0.00E+00 6.51E-04! 0.00E+001 0.0'E+00 C -!_. Ci 4.12E-10 6.49E-04 0.00E-U0i 0.00E+00 C.-194 Ci j 0.00E+00 9.C3E-0; 0.00E+0af0.00E400 Jr -95 { Ci l 0.00E+00 0.00E+C- 0.00E+00 1 0.C3E+00 ~ Nt-95 i C- i 0.00E+00 3 . E T E : 1 0.00E+00' ..
.00E*[0 Co=: Ci -7 0.00E+00 00E-0C- 0.00E+30 nn-54 Ci Z.54E-a5 1.02:E-05h0 0.00E+00J ._ - -?- u- -E+ + 0 _' t 0.00E+0 ic
__F .E_ _5 9 _ . _ _ ___ _C_i _ _0 . 0 0 E + C _0,i 7.00E+C01 0.00E+Ce O . 0 0__E__4 0__0_ _ _ _ _ _ . C_ _c_- 6 0 _ _ _ __ __ _ _ _ _ _ _ _ _ _ . . _ _ _ C i_ _ 5._15E-05 4.E3E-0"l 0 .'C"Dai 0.00 , , ,_, _
+00 l '
T. r. l Ci 1.19E-04 2.19E- 0 3 + - - ; 00E+00 (23)
Table 3-1 . EFFLUENT AND WASTE DISTOSAL SEf.11 ANNUAL REPORT (YEAR) 1978 SC L!D WA5TE ANO IRHADIATED FUEL SHIF.M ENTS FOR U.' LIT I A. SOLIO WZTE SHIPPEO oTFSITE FOR EURIAL OR D:SNSt.L (,'ut irradia:4d fuel) w,;t Ce " 3 F s'. To =1
- 1. Ty,7e of wiste h. .co E :,. s
- a. S; ent resins. ti. iter s'u.i.;es. e .:per :or n/ 1,03 E + p; }
- tot oru. e::. Ci , QE + PIT 7(Tfyi
- b. Dry corn. es.ic:e was: . coctatruna; 1 rn' equip. e tc. . Ci il 11[40 E41!Effff-)TT7~
- c. Irr:d.sted ec:apenenu. conual F 1 01 Edl__.
r M s. ct:. I Ci 10,3 E 4 3 1.00Ed_ rn' i E i
- d. O:hcr (des.:noe) _
Ci El E 2_Esti:-_:te of c sicr ec:iid: compositica (by tyy of was:4) ISOTOPE I PERCEf;T I CU. RIES l 82 l lE?_ 57 15 21 . _j
- a. C050 __!
5- 0 i
. L523/ 1 fiin5 a ~I 1,1 ATI'Others 13 21 o
- b. ZM5 57 ~
C5c 15 i 7 , CS1 37 5 1 _ _} 4 1 1 C r l ~ lo 3 ~~l All Others l
- c. FUFL Ch/W!El S 76.T' ~
75 __370 fib" P,5 123 L PPI1's 7If" t- 6 ' 46?? C0' t.2 Qlc 603 j file 6 6 ,61 3 1 All Others
' 3. Said Mste Dir;cd:ica .
Made of Trans:cr:2eion Destin: don
. Number of Shi: men:s Chera-fluclear Systens , Barnwell, S.C. 9 38 .
< Inc. g C. IRRADIATED FUEL SHiFMENTS (Dispzi:ico)
Numter of Shi mect.s M:4e e f Tunereruifo.. - Ce:i 2 den
~
I4 4M- 3-14. 3 (24)
GEORGIA POWER COMPANY PLANT E. I. HATCH UNIT NO. 2 SEMIA!!!!UAL REPORT PLANT RADIOACTIVE EFFLUE!!T RELEASES JULY 1, 1978 - DECEMBER 31, 1978 e' e s 4" F F
?.., , . - .. ,
...v. >. - . .
- . . .~^
PLAf1T E. I. liATCil , SEMIA!:tiUAL REPORT U:11T 2 RADI0 ACTIVE EFFLUE!iT RELEASES
~
SECTIOt TITLE PAGE
.1. LIQUID EFFLUEliTS . I REGULATORY LIMITS 1 1.1 >, -
# MAXIMUM PERMISSIBLE C0!iCEi!TRATIC:15 1 1.2 1.3 f:EASUREfiEf!TS AtiD APPROXD',ATI0t:5 0F .
4 TOTAL RADICACTIVITY 1.4 BATCil RELEASES 6 2 GASEOUS EFFLUEllT, 14 2.1 REGULATORY LIMITS 14 2.2 MEASUREMEllTS A:1D APPROXIMATI0ftS OF
- TOTAL RADI0 ACTIVITY 2.3 GASEOUS EFFLUEliT RELEASE DATA 19 3' '
p SOLID WASTE . 20 3.1 - REGULATORY SPECIFICATI0:'S 20 SOLID UASTE DATA 20 3.2s . of = ee<
, T e
O g
. , , ee = i g f
.i d ., ,
. s :. . .
., ., s .
s . 0 A
PLAIT E. I. HATCH ' SEMINitlUAL REPORT - U: TIT 2 RADI0 ACTIVE EFFLUEllT RELEASES ( m W FIGURE
- LIST OF FIGURES .
PAGE, 1-1 EETHODS OF MEETit;G TACLE II
' COLU:i'l 2 t:?C LIMITS (10 CFR 20) 7 1-2 ,
LIQUID RAD'IASTE AliALYSIS
'l-3
' 8 LIQJID PAD'!ASTE A?IALYSIS 9
l LIQUID PADilASTE DISCHARGE PERMIT 10 1-S - LIQUID RAD',IASTE DATA C0:-:PILATIO:t 11
~
_ LIST OF TABLES TABLE EE l-1 .
. EFFLUEllT AfiD UASTE DISPOSAL SEMI-M!NUAL REPORT, LIQUID EFFLUEt;TS-SUF2ATIO:i 0F ALL RELEASES 12 1-2
(
- EFFLUEi!T A? D WASTE DISPOSAL SEMI-
*, A!!:lUAL REPORT, LIQUID EFFLUE!TS-
. BATCH CJ;LY -
' . . . 13 2-1 EFFLUEt!T N;D WASTE DISPOSAL SE!!I-
'
- Afii!UAL REFORT, GASEQUS EFFLUE!!T-SUPU'ATIO:; 0F ALL RELEASES 21 2-2
$FFLUENT A?;D WASTE ' DISPOSAL SEMI-
~
L E LEdS: 22 2-3 EFFLUENT M D WASTE DISPOSAL SEMI- '
- AM!;UAL REPCRT,- GASEGUS EFFLUEt:TS-GROU:iD LEVEL RELEASES 3-1 -
23 EFFLUEffT NID NASTE DISPOSAL SEMI-N!NUAL REPORT, SOLID UASTE A :D IRRADIATED FUEL SHIPI:EilTS 24 9 1 g .
'4 8
. 1
- 8 'i
. ,, . p
, _e.
4
dP. 7RD .L - u
~
I gQul0 EFFLUENTS . , 1.1. PI . (.JRY LIMITS
- 1. The concentration of radioactive materials r#ca:,eo in -
liquid waste ef fluents from all reactore 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 waste :
cffluents excluding tritium and dissolved gases, shall not exceed 10 Ci/ reactor /callendar quarter.
- 3. The cumulative release of radioactive materials in liquid waste
,cffluents, excluding tritium and dissolved gases, shall not exceed 2,0 Ci/ reactor in any 12 consecutive months. .
- 4. During release of radioactive wastes, the liquid radwaste '
effluent radiation monitor shall be set to alarm and to initiate the automatic closure of the waste discharge valve prior to ex-ceeding the limits specified in section 2.1.la of Tech Specs. .,
- 5. The operability of the automatic discharge valve in the liquid radioactive waste discharge line shall. be demonst-rated quarterly. , ,
, 6. The equipment installed in the liquid radioactive waste .
system shall be maintained and shall be operated to prccess ' radioactive liquid wastes prior to their discharge when the '
- projected cumulative release could exceed 1.25 Ci/ reactor /
calcndar quarter, excluding tritium and dissolved gases.
~
- 7. The maximum radioactivity to be contained in any liquid radwaste tank that can be discharged'directly to the environs -
shall not exceed 10 Ci, excluding tritium and dissolved . gases. -
~
- 8. If the cumulative release of radioactive materials in liquid ef-fluents excluding tritium and dissolved gases, exceeds 2.5
- Ci/ reactor / calendar cuarter, the licensee shall make an in- -
vestigation to identify the causes of such releases, define and initiate a program of action to reduce such releases to - the design objective levels listed in'section 2.1 and report . these actions to the Comission within 30 days from the end of the quarter during which the release occurred in accordance
. .. with section 5.7.2 of Tech Specs. ,
1.2. FAXIMUM PERMISSIBLE CONCENTRATIONS ' '. The FPC 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 de-termined by a mixed nuclide ??C calculation performed before the re- .
. lease of the batch. To facilitate the measurements and calcula tions, the nuclides of Column 2 which can be produced .in a fission reactor ,...
'.. ', have been grouped accor' ding to PPC value and type of radiation as shown in Figure 1-1. .
(1) . -
The concentration of each of the 29 gamma emitting nuclides lhI' specifically noted in figure 1-1 is measured individually because of interest in that nuclide or be ause of inadequate sensitivity for the nuclide from a gross activity measurement. For any of the 29 nuclides not de tec te d in the gamma scan, the MDA limit is computed from the measured data for that sample. Only two pure beta emitters, Sr-89 and Sr-90, have MPC values less than 9X 10-6 uCi/ml. Individual measurements are made on proportional composite liquid radwaste samples to determine the Sr-89 and Sr-90 comcentration or MDA value to be applied to individual batch release calculations. Although the MPC limit for tritium is greater than 9X 10 -6 , a separate measurement is made for tritium since the gross beta technique does not provide an acceptable tritium measurement. A distilation and liquid scintillation counting technique is used to measure tritium concentration. The maximum activity of ganna and beta emitting nuclides with MPC values greater than 9 X 10-6 uCi/ml, except for the 29 nuclides noted above, is determined by gross gamma and gross beta measurements. Measurement sensitivity limits of approxinately 2 cpm /ml allow a null measurement to show that the sum E (Ci/MPCi), is less than 0.1 for gamma and beta nuclides not
.casured directly.
The sum of the ratios, E (Ci/MPC1), for alpha emitters can be shown to be less than 0.1 by a null measurement with a sensitivity limit of approxinately 1 X 10 - 2 cpm /mi. Gas flow counting is used to achieve the required sensitivity of measurement. Thus, except for radionuclides produced in n e g li g i b l.e quantities in a fission reaction (eg. I-125, I-129, etc.), the methods outlined above provide a means to assign a quantitative measured or MDA value to all nuclides in Column 2. These measured and calculated concentration values for each batch are used to calculate the dilution ratio, release rate, and dilution rate prior to release of each batch. Both the concentration and release data are stored on a computer disc file. The disc file data is used to assure that quarterly and annual release limits are not exceeded. Bases used for the data of Table 1-1 are as follows: A. Fission and activation products - The total release values (not including tritium, gases, alpha) are comprised of the . , s . - . . (2)
sum of the individual ra d i. so u c li d e activities and include the LLD concentrationof all isotopes that were not measured but did not meet the m '. n im u m sensitivity limit as set forth in our Environmental 'ech. Specs. This sum is for each batch released to ti a river for the respective quarter. These values represent t ,. 2 activity known to be present in the liquid radwaste effluent. Percent of applicable limit is determined from a mixed nuclide MPC calcualtion. 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 in each batch by Ge(Li) spectroscopy on a one liter sample from each liquid radwaste batch. Dissolved and entrained cases for which measured or MDA concentrations are determined include noble gases with half lives greater than 8 hours; Xe-135, Xc-133m, Xe-133, and Kr-35. Iodine radionuclides in any form are also determineu d aing the isotopic analysis for each batch, therefore a separate analysis for possible gascous forms is not performed because it would not provide additional information. A conservative release limit, the maximum sensitivity limit of 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. D. Alpha measurements are taken conthly from the Liquid Radwaste composite. A study was instituted in July to determine if the ratio method, as described in the E.T.S. Table 2.1-1 footnote could meet the LLD of 10% of the MPC value specified in 10 CFR part 20 Appendix B, Table II, Column 2. The limit of 3X 10-9 uci/ml was never exceeded during the study. Below is a summary of the study findings.
,s: . r u .s. g. ,, - . . e. .
.c .s._. ,,
(3)
.. _ __ _ _ _ _ _ E 6 I I O_ h. It*2O_ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ D F T t E*P.C P: m L t'O L_'2.
PR IWR Y PR IWRY LRW _ _ . _ _ _ _LFW LhW C OO'_N J T COCL /.NT COtPO311 E CPOM /.LHM C O-E.o GF05S N PH% CO-Co /iLPHA __tEUltf___. _ L*J I I____ iu ulell____ __lut i/ mil ___ . _lu;ih"1) __ !u u ta ll ___ _1uu M11._______ ____
"> Y_1 d __ _ __1____~ _2.13_ E25_. __. __3. EC _E :9_ __ _. _5.22_E:7 2, C ?..E:10__ _ L 29..E 9__ _ _....______.__.
E _ W _ ___. __I f_1.20_Ere_____ __1.U5 1.-10 __ _1,27_E:L__.___ ._1.W E-1R__ . ^ . 5 9 _ C 1 1 _ _ _ _ _ _ _ _ ._ _ _ _ _ __ _ _ _ eEt' I _7 d _ __. __1_____.l_1.li_C:A_- __2.2 d_E 9___ __ _1.21_E:7 2.91_E-1B__ -_1.13 E :10_ ._ _ ___ . ._ _ _. _.___ _ __ 0C1_75____ _ _1___ __ _' _1. C 3_ Erd ___ _ _2 CO_E-10___ __2.67_E:7 4 $2_.E:1?__ _1.L'_ErlO___________ ... t lCN_ Z d__ _ __ __1______ _1.td_C:S____ .__ d E 0_E u ._2.C5_C:7 S.C7_E:12__ .V.12_E-10_______ EEC_73____1__1_____. _1.E C _E:0__.__. .__E.22_E:10___ ._2.'d Er7 _1. C L E : 12___ ._L L ( _F.21 ] _ ___ __ ._, _ _ _ , JNL12 i__1____ _2.20_E:4 ___5.09_E:10___ __2.32_E:7 0.20_E 13__ ._2. ?! _ E r l ?_ _..__ _ _ _ .. JL'Y_7S___!__2_____l_L.50E:1____ .__d.52_E 10___ 12.07_E:2 1.21_E:11__ . _ 3
- I O E f . _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ _
6UC _7 E_ _ __ .__2___ __lf.3.2 3_ E:L __ _ .___9.Cl_Erll___ _2.52_E:2- ~' If_E:12__ _ 3 . 5 7 E: 10_ __ _____ _____
- .EEI_ Z L __ _. __2 li? Ct _E:22__ __1 ES E 9___L_1 ZE_F.27_____ __ Z.? ? _ C 10__. $_1.5. E 10.._ __ _ __ ______.
OCI_70____4__2_____119.95_E:E2 1.50_E:10_. 5.97_E:7 L M Erl2__. _E.l?_EclO______________._ . kHL73 __2 111. C2_E:50 __ ___S SS E 9___. .- _2.29_E:1____.. _,1.!C.E:11__ _. 2 . 9d _ E : l O __ _ __ _ _ __ _ _._ __ ___ LEC_IS____.{__2 l 2.5 3_ E:5____L__5.12_E:?____ L_1.1 E_ E.- 2_ _ __ __1 ? . 2 L E: 10_ _ _ _ _ ___ _____ _ J U63_Z2____1__2 ' E.E5_Erc ' d 97_Erl0___L_1.as_E:2_____L_2.!S M _Erl2__ E: 10_ _1.__5 . E 3_E: 10______ _.J _
- conc estinuted f rom LLD un 'CF" computer printout The cunclusion of this study is that the ra tio m e thud for calcula ting alpha activity in l i c:u i d radwaste unvlet is at least equivalent to the direct measuremcnt methud.
1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADI0 ACTIVITY. 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. Gamma Isotopic Each Batch Ge(Li) spectrometry with on-line computer.
- 2. Gross Gamma Each Batch 2 X 2 NaI well crystal counting 3 Gross Beta Each Batch Gas flow proportional counting II . Sr-89 Monthly Chemical separation and composite gas flow proportional counting
- 5. Sr-90 Monthly Chemical separation and Composite gas flow proportional i counting ,
- 6. Tritium Monthly Distillation and liquid Composite Scintillation counting i
- 7. alpha Monthly Gas Flow proportional Composite counters
- 8. Dissolved Gases Each Batch Ge(Li) spectrometry with on_line compute"
. .3 .
(4)
If a liquid radwaste tank cannnt he reprocessed, a sample for analysis is taken from the tank af ter the required recirculat ion time. The sample is used for gaao-ray spectroscopy, gross gar::ia and gross beta (nunting, and for preparatien of a composite sar ple. The Ge(Li) detector systems consist of a 10% and two 15% efficiency, 2.0 s fuiM resolution detcctors in 4-inch thick lead shields. A one-liter rad.vaste liquid sarale is solidified in a furir.elli beaker in prepa-ration for a 2000-3000 second Ge(Li) count. A peak search of the resulting garca ray spectrum is perfort.:ed by the on-line co:rputer systen. Energy and net <ount data for all significant peaks are de-termined, and quantitative reduction or MDA calculations are perforrr.ed for the nuclic'es listed in Figure 1-1. The quantitative calcula-tions include correcticas for counting tire, decay time, sample volume, sample gec: retry, 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 loccted if present.
~
The calculated radionuclide concentrations or l'CA values from the gamma scan and frca previcusly stored Sr-C9 and Sr-90 values are used to calculate the dilution ratio Y (Ci/MPCi) and allowable release parameters. A sample printout is shcwn in figures 1-2 and 1-3. The Liquid Radwaste Discharge Permit Printout is transferred item by itera to the first portion of the release permit (Figure 1-4) by a laboratory technician. Although the computer could printout the release permit and will inform the technician if a batch cannot be discharged as desired, a manual transfer of calculated results to the release permit by the technician was implemented as more likely to catch abnormal s conditions in the data. The liquid rah:aste monitor setting is calculated by the ccmputer based on the gross gamma cctivity as measure.d in the sa:rple used for laboratory analysis. A coefficient has been determined which relates laboratory gross gann counts to the ranitor count rate. If the monitor courit rate exceeds the calculated settinq during discharge, then the liquid passing th. rough the monitor is not Fepresentative of the sangle which 'as analyzed in the lab. A monitor reading in excess of the cal-culatcd setpeint therefore results in an autcutic ter:rination of the liquid effluent discharge. Liquid effluent _discharce is also auto-matically terminated if the dilution flow rate falls belo- the flow rate used in the computer calculation. 1.' hen the release peruit is returned from Ra'dwaste Operations following discharge, the discharge data is combined uith the analysis results on the computer disc file. The disc file may be scanned to display trends in any recorded para:.;eter, or mTV be summed for reporting purposes as shown in Figure 1-5.
. s -
.. s
( . (5) ! i
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) spectronotry system with conputer data reduction using the Liquid Radwaste Library which includes gases. Several conments are indicative of the success of the HNP liquid radwaste program during this reporting period:
- 1. The total measured activity released in liquid effluent was 3.53 E-4 curie for the third quarter and 7.24 E-3 curie for the fourth quarter. These values were approximately 1/2832 and 1/1381 respectively of the allowed 10 curies per quarter.
- 2. The "adwaste release procedure strongly emphasized r e p r o c e s s i n:, rather than discharge of liquid radwaste.
During this report period only 32.42% of the liquid radwaste reaching the sample tanks was discharged: 67.58% was recycled back into both of the "eactor 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 386 discharge batches for both Units. 1.4 BATCH RELEASES Regulatory Guide 1.21 Tables 2A dnd 2B are found in this report as Table 1-1 and 1-2. Data is presented on a quarterly basis as per Regulatory Guide 1.21. If it is requested, a monthly tabulation will be submitted. Other data pertinent to batch releases of radioactive e f fl u er. t from both units is as follows: humber of batch releases: 386 Total time period for releases: 43990 minutes Maximum time period for a batch release: 227 minutes Average time period for batch release: 115 minutes Minimum time period for a batch release: 42 minutes Average stream flow during periods of release of effluent into a flowing stream: 3826 CFS , , , , ,, o - + -
. ,: < - ac (6)
. FIGURE 1-1 1: Ell!OCS OF l'.ECTIt:G T/.0LE II . CCLU:'ll 2 !*J'C LIli!TS .
I?C R/,' ICE CN:'A-PAY BETA -
/J.NIA -
ElllTIERS ElllT T ECS (U Ct/.1) DtiTTFRS I-131.1-13?.!-123 Sr-89.Sr-90 1-135, Cs l? - (SeparatienandChs
-5 flos Coun:.ing)
<9 X 10 (Cc(Li) Canna-Ray Spectrostc;y) ill ,
(Cas Ficu Cour: ting. Sensitivity C.01 CM'/ml) f a-La-140.fh-?a .Cu-C Tritica .
- CO-00,Fe-E9.!n-55 (Distillction and Li:;uid 5:intil-
> S X 10~ 0 /.a-ll C-* , i',- 5 2 . Co - E!) lation Countir.g) 7r-!:b-95. Cs-h-137
/.s-76. F-18, C r-51 All others .
. !lp-739, Ce-lal (C:s Flo.. Countir.g .
~
Sensitivi ty -2 l'.o-T c- 9 9 . C c - T r-1.:
- CFil/r.1
( Cc(Li) Carr.-Tay - . Spectrcs::;y) .
~
' 11 I others i
' (Cros s Cr. 3 '..':Il
. Ccunter; Sensitivity -
s5 CP:i/:;l) O *
- e g . .
. . s
= .
. (z) .
Licuid F sos aa t 4 Ans!'ais
. n FIGURE.1-2
( P e. ac t or d 2 B at c h# 237 Tank: Clli T E -2 Operator: Ft C C :ura e n t : HIGH FIL SOL F.4n dit4: U 10 ' 7.i 07*5 C o u r. t 2 t ar t d.at e : 9e 10.-75 0 5 =. 0 ( 5 arn p 1e o o l u cc e : 1000.00 rai C1ock t i ra e : 3000 ec3 i G orcie t r y code: 1LHB-0 Livt t i r:4e : 3000 sec; Detector # 1 MCA# 1 l Li br ar' : LFl.LB2 I E n e r g 5"J c V ) = .90 + 999
- Ch# + 0
- Chn^2 +0
- Ch#^3 90978 l Eff = leC5.6.73E-03 + E^<-3.4731E+00) + 413.405 + E^(9.4372E-01)] 80678 where E = Energy in ilsV.
IS0 TOPE ENERGY CONCENTFAT:0N EPROP T1P C C/MPC (lev) (aci/n 1) ( u C i / ra l ) ( uC 1/ ru l )
=======_= _==== ==_===================-================_-==== ========_=========
Ce-144 133.54 <2.287E-07 1E-05 (2.2?E-02 T c - 9 9 e.i 140.*0 <2.604E-08 3E-03 <8.68E-06 Ce-141 145.40 <5.375E-08 9E-05 <5.97E-04 [ Hp-239 277.60 <2.356E-07 1E-04 (2.36E-03 Cr-51 320.10 <2.72SE-07 2E-03 <:1.36E-04 I-131 364.50 (3.402E-08 3E-07 <1.13E-01 2n-69ni 438.50 <2.629E-08 6E-05 (4.33E-04 j H-197 479.50 <9.815E-08 6E-05 <1.64E-03 i F-18 511.00 <3.854E-08 5E-04 (7.71E-05 I-133 529.50 <3.030E-08 1E-06 <3.03E-02 ! Ea-140 537.40 <1.257E-07 2E-05 (6.19E-03 l 82-76 559.10 <5.168E-08 2E-05 <2.58E-03 ! C3-134 604.70 <3.159E-03 9E-06 <3.51E-02 C2-137 661.64 <3.056E-05 2E-05 <1.53E-03 Mo-99 739.70 <2.252E-07 4E-05 <5.63E-03 Zr-97 743.50 <2.954E-06 2E-05 <1.48E-03 l I 1.67E-03 2r-95 756.89 1.000E-07 3.238E-08 6E-05 HD-95 765.84 <3.064E-08 1E-04 <3.06E-04
'I-132 772.60 <2.656E-08 SE-06 <3.32E-03 Co-58 810.60 <1.613E-08 9E-05 <1.79E-04 Mn-54 834.80 <3.113E-08 1E-04 <3.11E-04 i A;-110u. 884.70 <3.191E-08 3E-05 <1.06E-03 26-65 1115.50 <7.256E-05 1E-04 (7.26E-04 I-135 1260.50 (9.028E-08 4E-06 <2.01E-02 l Fe-59 1291.53 < ? . 96 5 E- 0:5 6E-05 1.31E- : i 3E-05 <1.31E-0: !
C:-60 1332.49 3.935E-05 (4.371E-06 2E-04 <2.19E-0; Cu-64 1345.30 Na-24 1345.55 <1.5?5E-Oi 3E-05 (5.12E /*4 L a- 14 0 1596.60 ( 2. 75 0 E-0:5 2E-35 s 1.17 E - . - Flo-56 1311.20 . : . 4 0 4 E - 0.? 1E-04 .40E-04 ( Sr -G9 (EETA) C6.950E-09 3E-06 . I . A - 0. (EETA) 1.410E-Od 2.050E-09 3E-07 4.70E-02 Br-?O ----- --------- 1.141E-07 1.24tE .: 2.4N -~- . It
- 3 3 n r e ..' tces12 (6.400E-06 ' 2. 4.il-01 LLD eet313 A.".14F-na ~ 7 F' - J' ?
Tot-12 (8)
FIGURE l-3
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g (9)
FICURE l-4 . EATCil h0. F_Ce.M i .. . . PLA'? F. I. WTC4 . U(!T f * .
.- 0".rGru FE:.wtT
- , .-LIQtJto FJu S _
I : TAM 70 *~ FELGCEO
- OATE / /
F.E;.50tl FC3 f ICI55:TY LF CISC.%i.E W:;LT'II.Mi RECIF.C. ST; .! TIMI F.icinc7Cs,.gic:6 is;;t , I. LASCRAf a;Y "faLYSIS (1) Pelwred Ea d!:m.clide C:r.cr.ntra tien (2) Calculated I::A Lini Cce.:<ntrattens [._ : + i i,Ct/nl
.g l, 31 (3) Calculated Ciletica Ratio: I(Ci/MFCI) :
(4) l'inic.cn Oilut ten Ficw F. ate crM l (5) Calculated Tank Di::Parga F.ne. ( )/ L3) - 1 C;:1 (6) S;e:ified Mat. Tar.k Cis:.ta ;e Eate: <(5)/2 l CM .
, (7) Eadeaste renitor Trip Settfrg: CPS I
~A = Well Ccunt CPM /:11 S
- Ponitor SG CPS
'C = Mor.it:r CTS i
F = Conservative .. -. 3
. ;. .rer W.C.' CFM/=1 Factor .
. . . l H niter Alam Sa.t;cint (CFS) = (C x A x F) + B + 3/T * -
J'
. ,' Cccrosi te Liter Stered:
i scap!cte.. ty: Cate: ?
. Initials m_ . . . . .
II. - CFEF.ATIC G -
'i ,.- ItilT.
. . 8) Liciufd Radete Moniter Trip 5et at: ' CPS
- 9) Ccnfirmed Oilutien Flow F. ate CPM (10) Valve Lir.eup Che:ked as pcr khP- ~~ '
. j. .
T a r k. . t l 'i i s . In:e;- Gis r.a te c.:y Oil. ic:E Ttver -aj N:ni: rp
._O i te .. T i . ta_ve t _ _. - -...e.
;r=*.:r h
- - ~ - . =
G il , I. re.,. - .l m c s ! w g . i
, Start I -l ,
t ^
. End
. ! - i
~
* * $ 1* CCCdi dEdd C/; 04Ed; Durat1cn ~To ta l
. Release !
*G 10 cit n. af ter start !
**Af ter fluelne i I
. . . g
. i 111. LABCRATORY . . .
I
- 11) Total Tank 'lole.e Disch2rged [;al. x 3.785 x 10' :-7/ gal.] ml
- 12) Tet'l 4:tivity 01sch.irged ((1) x (11}} _ uci '
- 13) River fic r Ene (feca F Ai 2.4-6) CFS ';
Cceple c: d:
. . / i Oatc;
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FIGURE 1-5 Ltquid Padw ar t s D at a Conip i l at i on t' c r Peg. Guide 1.21 FTrort ( E. I. Hatch Nuc l e ar Plant UNIT 2 Tot al Activitv (Curies) , t i Ouarter 3, 1978 Quarte- 4, 197:5 E at che: 74 thru 319 Eatchcs 320 t hr u 459 H an.e Heasured Error High LLDs Tot al De uured Error High LLD3 Tot al Ce-144 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1c-993 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0C 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 0.00E+00 Hp-239 0.00E+00 0.00E+00 0.00E+00 0.00E+0A 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 T.43E-04 2.1TE-05 0.00E+00 7.43E-04 I-131 0.00E+00 0.00E+00 0.00E+00 0.00E+0e 4.12E-05 2.29E-06 0.00E+00 4.8EE-05 2n-69; O.00E+00 0.00E+00 0,00E+00 0.00E+00 5.09E-06 7.4TE-07 0.00E+00 5.99E-06 H-197 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.6?E-05 6.5?E-06 0.00E+00 3.6TE-05 F-15 1.32E-05 6.85E-07 0.00E*00 1.32E-05 5.53E-04 3. 79E-06 6. : ::E -04 1.16E-03 I-133 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.70E-06 S.62E-07 0.00E+00 5.70E-06 ba-140 9.75E-06 2.32E-OC 0.00E+00 9.75E-06 0.00E+00 0.00E+00 0.00E+00 0.0eE+00 A1-76 0.00E+00 0.00E+00 0.00E+00 0.00E+00 S.G9E-05 5.19E-06 0.00E+00 ?.89E-05 Cr-134 1.49E-06 5.05E-07 0.00E+00 1.49E-06 3.33E-04 4.55E-06 0.00E+00 3.38E-04 Cz-13T 1.06E-06 3.06E-07 0.00E+00 1.36E-06 3.64E-04 5.16E-06 0.00E+00 3.64E-04 Us-99 9.11E-06 2.6SE-06 0.00E+00 9.11E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2r-?T 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.33E-06 3.32E-07 0.00E+00 1.33E-06 2r-95 3.46E-06 .'. ele-07 0.00E+00 3.46E-Ot 6.84E-07 6.14E-07 0.00E+00 6.84E-07 Ha-95 2.31E-06 4.42E-07 0.00E+0C 2.31E-06 8.69E-07 2.37E-07 0.00E+00 S.69E-07
- -13; 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.71E-07 1.77E-07 0.00E+00 4.71E-07 C3-tb d.33E-05 .19E-Of 0.00E+00 4.9?E-05 1.95E-04 4.25E-06 0.0CE+00 1.95E-04 Un-54 4.21E-06 7.91E-07 0.00E+00 4.21E-06 2.23E-05 2.43E-06 0 TOE +00 2.23E-05 A,-TIT. 5. 5:3E-0 7 2.24E-07 0.00E+00 5.5SE-07 0.00E+00 0.00E+0C O.00E+00 0.00E+00 2n-65 2.65E-05 2.4TE-06 0.00E+00 2.65E-05 1.1TE-04 T.95E-06 0.00E+00 1.1?E-04 I-135 1.94E-05 2.93E-06 0.00E+00 1.94E-05 Q.78E-06 2.51E-Oi 0.00E+00 9.78E-06 Fs-59 2.00E-06 9.70E-07 0.0eE+00 2.00E-0G 1.00E-05 1.91E-06 0.00E+00 1.08E-05 Co~60 1.55E-04 5.16E-06 0.00E+00 1.55E-0, 1.35E-04 4.90E-06 0.00E+'0 1.35E-04
. Cu-64 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.80E-03 3.99E-04 6.72E-04 2.42E-03 Ha-24 5.31E-06 2 .90E-07 0.00E+00 5.31E-06 1.32E-03 1.02E-05 0.00E+00 1.32E-03 L a-14 0 0.00E+00 0.00E+00 0.00E+0n 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hn "t 4 .39E-06 1.51E-06 0.00E+00 T.39E-06 1.2?E-05 "TE-06 0.00E+00 1.2TE-05 C -136 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.10E-05 1.455-06 0.00E+00 2.10E-05 Gr-89 0.00E+00 0.00E+00 0.00E400 0.00E+00 7.15E-05 2.16E-06 0.00E+00 7.15E-05 Se-90 4.33E-05 6.30E-06 0.00E+00 4.33E-05 5.32E-05 3.34E-06 0.00E+00 5.32E-05 Tot ai r 3.53E-04 1.02E-05 0.00E+0C 3.53E-04 5.96E-03 4.00E-04 1.28E-03 7.24E-03 Ne-12" 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.11E-04 4.29E-06 0.00E+00 2.11E-04 ne-135 6.36E-06 5.69E-07 0.00E+00 f.36E-06 2.?3E-04 4.35E-06 0.00E400 2.??6-04
.' e - 131 r. 0.00E400 0.00E+00 0.00E*00 0.00E+00 0.00E+00 0.00E-00 0.00E+00 0.00E+00 F r - C"E 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.42E-07 2.15E-06 0.00E+00 4.42E-07 Ne-13En 0.00E+00 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0GE+00 V -:15 w 6.:3E-07 2.v6E-07 0.00E+00 6.33E-0T 0..:0E+00 0.00E+0 0.00E+00 0.00E+00 V"-G 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+0C 0.00E+0C 0..:0E+00 0.00E+00 ne-13' 2.30E-0? 6.4?E-05 0.00E400 2.E3E-07 0.00E+00 0.00E+00 0.00E*00 0.00E+00 g g Xe-13.s 6.75Z-12 2.93E-12 0.00E+00 6.75E-12 0.00E+00 0.00E+0: 0.00E+00 0.00E+00 T3- ? E-06 6.09E-07 0.00E+00 7.2TE-06 4.39E-04 6.33E-06 0.03E+00 4.93E-04 (10
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TABLE l-2 E. I. Hat ch tiuc l e ar P l c.n t Ut1I T 2 EFFLUEllT AtID WASTE DISPOSAL SEMI Atit4UAL REPORT 1975 LIOUID EFFLUEt4TS __ C 0 tit I t1U OU S f1GDE EATCH MODE l1.4 c l i de s Re l e ase d Unit G u a r t. e r Quarter Guarter l Ou ar t e r 3 4 3 I 4 Ce-144 Ci 0.00E+00 0.00E+00 T c - 9 9 re Ci 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 tip-239 Ci 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 7.43E-04 I-131 Ci 0.00E+00 4.82E-05 Zn-69n, Ci 0.00E+00 5.89E-u6 W-187 Ci 0.00E+00. 3.67E-05 F-18 Ci 1.32E-05 1.16E-03~ I-135 Ci 0.00E+00 5.70E-06 DE-140 Ci 9.75E-06 0.00E+00 ns-76 Ci 0.00E+00 .89E-05 C2-134 Ci 1. 4 9 E'-06 3.38E-04 Cr-137 Ci q 1.86E-06 5.64E-04 Mo-99 Ci 9.11E-06 0.00E+00 2r-97 Ci 0.00E+00 1.33E-06
~
Jr-95 Ci ~I-~ _ . 4 6 E - 0 6 6,94E-07 uh- i5 Ci [2.i1E-06 :.69E-07 [ _ I-1 2 Ci L Q.00E+001 4.71E-07 C 3 - 5 :i Ci ! 4 . ::: 3 E - 0 5 1., y 5 E - u 4 firi-54 Ci _j 4.21E-06 2. c 3E-Of Ag-110n. Ci 5 . 8 8 E - 0 ,' O.00E+0_0 2n-65 Ci 2.65E-05 1.17E-04 I-135 Ci 1.94E-05 9.78E-06 Fe-59 Ci 2.00E-06 1.08E-05 Co-60 Ci 1.55E-04 1.35E-04 Cu-64 Ci 0.00Ev00 2.48E-03 - tia-24 Ci 5.31E-06 1.32E-03-- LF-140 Ci 0.00E+00 0.00E+00 fin-56 Ci c.39E-06 1.27E-05 Cs-136 Ci ~ 0.00E+00 2.10E-05 Sr-89 Ci 0.00E+00 7.15E-05 Sr-90 Ci _ 4.33E-05 5.32E-05 1_, T ai al for period (above) Ci _ 3.53E-04 7.24E-0'[ i.e-133 Ci 0.00E+00 2.11E-04 N4-135 Ci 6.36E-06 2.78E-04 M.-13ini Ci 0.00E+00 0.00E+00 K r - O ':' Ci 0.00E+00 4.42E-07 "e-1?3n, Ci 0.00E+00 0.00E+00 Vr-85m Ci 6.,33E-07 0.00E+00 Lr-87 Ci 0.00E+00 0.00E+00
-1:: Ci 2.30E-07 0.00E+00
( o e-1 +.4 Ci e.75E-1m 00E+e0L (13)
2 GASEOUS EFFLUEtlTS 2.1. REGULATORY LIMITS.
- a. (1) The release rate limit of noble gases from the site, shall be;
{ Q;. 3 1.9 Y + 1.0 TB + Qiv 11 Ey + 44 EB 1I i+n - where Q 3 = Total release rate from main stack for both Units in Ci/sec (elevated release) ' gy = Total release rate from vent in Ci/sec (ground release) , i = the individual nuclide. n = totai nuclides. EY = the average ga=a energy per disintegration EB = the average beta energy per disintegration (2) The release rate limit of all radioicdines and radio-active materials in particulate forn with half lives greater than cicht days, released from the site to the environs as part of the gcscous wastes, shall be. 1.0 X 10 5 Qps + 1.5 X 10 5 Qpv 51 l!here Qps= Total release rate from the main stack for both Units in Ci/sec (as elevated release) Qpy= Total release rate from vents for both Units in Ci/sec (ground release)
- b. (1) The average release rate of noble gases from the site during any calendar quarter shall be: -
Qis 12 Ey + 3.0 EB + Qiv 66 fy + 140 fB 1I i+n - - (2) 'he average release rate of noble gases during any 12 consecutive months shall ba-
) i+n Qis -
24 5y + 6.1 Eg 4 Qiy 130 fy + 270 fB 1I
. (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 10 5 Qps + 1.0 Y ]Q 7 gy g ] . (4) 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 period of 12 consecutive . c . . months shall be: 7 2.6 X 10 5 Qps + 3.7 X 10 Qpy < 1 (14)
(S) T e amoun t o lo ine - 3 re case uring any calen-
, ,. dar quarter shall not exceed 2 Ci/ reactor. :
i (6) The, amount of iodine - 131 released during .'ny period of 12 consecutive months shall not exceed 4 i / reactor,
- c. Should the conditions of 2.1. 3c (1), (2), or (3) listed ' ;
below occur, the licensee shall make an investigation to ' identi~fy the causes of the release rates, define and initiate a program of action to reduce the release rates to desige objective levels listed in subsection 2.1 of the H:iP-ETS and report these actions to the Comission within 30 days _ from the end of the quarter during which the releases occur- , red in accordance with section 5.7.2. , [ (1) If the average release rate of noble gases during any - calendar quarter is: , ,
) ,Qis" 47 5Y + 12 fB + Qiv 250 Ty + 540 TB >1 ~.
i+n - -
~ _ ,
, (2) If the average release rate from the site of all radio iodines _
and radioactive materials in particulate form with half lives - greater than eight days during any calendar quarter is: , 7 5.0 X 10 8
@s+'/.2X10 @>1 :
~.
'(3) If the amaunt of Iodine - 131 released daring any cal-endar quarter is greater than 0.5 Ci/ reactor. ?
- d. The pos t-treatment offges monitors shall be operating and set to -
alarm and to initiate the automatic closure of the waste ges i discharge valve prior to exceeding the limits specified ;n Section 2.1.3a above. The operability of the automatic isolation valve . shall be demonstrated quarterly. .
- c. 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. l 4
- f. If the release rate of noble gases measured at the pretreatment ,
monitor exceeos 260,000 uci/sec e
. for a period 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. .
.L
. g. The reactor containment for each Unit shall be purged through i
. the standby gas treatment system for that Unit. 3 9
- h. (1) Potentially - explosive gas mixtures of hydrogen and oxygen a contained in the offgas system downstream of the recombiners shall be continuously monitored during reacter power operation for hydrogen concentration. The hydrogen gas monitoring system shall provide alarms locally and in the control room 7 at a set point of 43 hydregen concentration by volume. At .
~. . , ~ , . . -least one continuous gas monitoring system and.its associated . alarm system shall be operable during reactor power operation. ]-
~
If both of the hydrogen gas monitors or both of the assoc iated alar, syc tm a~ 'e m ble w wr im v 9 conti-nued for a period 0: tu no t to "- 'd 2 .;0eks , prov ided that either (a) grab sanples are taken and analyzed for hydrogen (15)
concentration once everv 4 hours, or (b) using a temporary hydrogen gas analyser installed in the offgas system line downstream of the recombiner, hydrogen concentration readings are taken and logged f>ery 4 hours. (2) The hydrogen concentration in the offgas system downstream of the recombiners shall not exceed 4% concentration by volume. If at any time during reactor power operation, it is determined that the hydrogen concentration limit is being exceeded, action shall be initiated within 4 hours to return the hydrogen concentration to within the prescribed limit. If the hydrogen concentration is not reduced to less than 4% by volume within 24 hours, the offgas system flow shall be stopped. (3) The installed hydrogen monitoring systems shall have daily sensor checks, monthly functional checks, and quarterly calibrations. The portable hydrogen gas analyzer shall be calibrated inmediately prior to installation and shall be subject to daily sensor checks, monthly functional checks, and quarterly calibrations until removed from service.
- i. An unplanned or uncontrolled offsite release of radioactive materials in gaseous effluents in excess of 150 C1. of noble gas or 0.02 C1. of radiciodines in gaseour form shall be reported to the NR C within 30 days in accordance with section S.7.2.
2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Waste gas release at Hatch II is confined to two paths. Each of these two paths is continuously monitored for gaseous concentration and each has an integratirq tyne collection device which concentrates particulates and iodinc for each seven day period (Procedures are such that shorter collection times are used where applicable to Technical Specification requirements). Each of these continuous samplers has a flow controller which maintains sample fl ow within about a 10 percent range over each seven day collection period. The offgas vent (elevated release) and the reac tor building vent have fl ow measurement devices which continuously record the flow rate of the gas released (accuracy of these devices are within 10% of the actual flows as measured during preoperational testing). In addition to the gaseous, particulate, and iodine release measurements tritium, gross alpha, and gaseous isotopic measurements of both vent streams are conduc te d on a monthly schedule. After each calerdar quarter (13 weeks) a summary of waste cas release from the two 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 (16)
were calculated separately because of the difference in the Tech. Specifications for the two reactors. However in the future we hope to combine both units into one report. The methods for compilation of the quarterly releases are as follows:
- 1. Fission and Activation Gas Total Release 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 c-- datermined from the monthly isotopics when sufficient activity a: lows or by injection of a known amount of off-gas into the sample chambers. The total curic release is calculated by the computer for each of the individual nuclidcs released. This number is multiplied by the average energy per d i s i n t ig r a t i. on (Ey &
Ep) and the coefficients in the release limit formula in our Environmental Technical Specifications. All of the nuclides are summed and stored in their respective data files until the end of the quarter. Then the computer divides the sum of the nuclides by the seconds in the quarter to determine the percent of the tech. spec. limit released.
- 2. E ADI0 IODIN E RELEASES Iodine releases are determined weekly for I-131, I-133, and IZI35, 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 sunmarized with the aid of the counting room calculator -
computer system and a quarterly total is prepared from the weekly summaries. The percent Technical Specification for I-131 on Table 2-1 is based on the quarterly Technical Specification limit. 3 PARTICULATE RELEASES Particulate release are determined weekly for each vent. Ehere s IgnIficant activity is not measured MDA release is calculated. Since calculated MDA's are below Technical Specification detectable concentrations, then 0 (zero1 release is used for weeks with only t'D A values. Weekly releases are summarized with the aid of the counting room calculator - computer. After each c a l e r. d a r month the particulate filters from each
- vent are combined, fused, and strontium separation is made.
Since sampic fl ows and vent flows are almost constant over (17)
cach monthly period the filters from each vent can be dissolved together. Decay corrections are made back to the middle of the monthly collection occiod. Again the counting room calculator - computer is used to aid in the calculation of the Sr-89, 90 release. Where significant strontium activity is not detected MDAs are calculated. In order to eliminate the need for a quarterly composite Sr-89 and Sr-90 activity is calculated for each monthly composite. The percent of Technical Specification was calculated using the quarter 2.y average equation.
- 4. GROSS ALPHA R EL E A SE The gross alpha release is computed each month by counting the particulate filters each week for gross alpha activity in a proportional counter. The four or five weeks numbers are then recorded on a data sheet and the activity is summed at the end of the month.
- 5. TRITIUM R ELEASE Tritium samples are obtained monthly from each vent by passing the sample stream from a cold trap immersed in a liquid nitrogen or an acetone and ice mixture. The grams of water vapor / cubic foot gas is measured upstream of the cold trap in order to alleviate the difficulties in determining water vapor collection efficiencies. The tritium samples are analyzed by an independent laboratory. From the uCi/ml tritium concentration, the grams water /ft3, and the vent flow rates, the monthly tritium release is calculated or each vent, and the quarterly summary can be generated from the monthly calculation forms.
Hatch 2 has attempted to maintain all calculated MDAs as low as possible by counting samples longer than what would be normally p ra c ti cal . For example at this time all weekly particualte and iodine counting times are 3000 see and strontium separations are sounted for 100 minutes. Regulatory Guide 1.21 requires that estimated total error in analysis techniques be reported. These estimates are required for the total fission and activation gas release, total I-131 release, total particulates with half-lives greater than 8-day release, and total tritium release.
"The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total operation of sampling anc measurement.
Because it may be very difficult to assign ert'or terms for each parameter affecting the final measuf;aent, detailed atatistical evaluation of error are not suggested. The obj ec tive should be to obtain an ove ra ll estimate of the ~
- error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste."
(18)
Estimated errors arc based on errors in counting equipnent calibration, counting statistics, vent flow rates, vent sample flow ra t e s , non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges.
- 1. Fission and_ Activation Gan_ Total _ Release was calculated from process monitor readings.
Monitor Error in Calibration 50% Vent Flow Rate 10% Non-Steady Release Rate 20% 50$
- 2. I-131 Release was calculated from each weekly sample:
Statistical error 60% Counting Equipment Calibration 105 Vent Flow Rates 101 Vent Sample Flow Rates 10% Non-Steady Release Rates 10% Losses From Charcoal Cartridge li' 1157 3 Particulates with half-lives greater than 8 days release was doainated by the MDA calculations for I-131 and Ba-La-140 hence the errors in the strontium determinations and gross alpha had negligibic affects on the estimated error in the total particulate release: Statistical Error at MDA concentration 60% Countng Equipment Calibration 10% Vent Flow Rates 10% Vent Sample Flow Rates 105 Non-Steady Release Rates 10% 106{
- 4. Total Tritium Release was dominated by the reactor building vent tritium release, hence, the larger statistical errors of the off-gas vent and recombiner building vent tritium releases do not affect the error in the total tritium release:
Water Vapor in Sample Stream Determination 20% Vent Flow Rates 10% Counting Calibration and Statistics 10% Non-Steady Release 50% 55T 2.3. GASEOUS EFFLUENT RELEASE D ATA Regulatory Guide 1.?1 Tables lA, 1B, and 1C are found in this repo.rt.as Tables.2-1,,2-2, jnd 2-3.. r . . , u ,. (19)
Data is presented on a quarterly basis as per Regulatory Guide (gf 1.21. 3 40 LID WASTE 3.1 Regulatory Specificationa.
- a. Measurements shall be made to determine or estimate the total curie quantity and principal radionucliue composition
. of all radioactive solid waste shipped offsite.
b. Solid wastes in storage and preparatory to shipment shall monitored be and packaged to assure compliance with the applicable portions o f 10 CPR Part 20, 10 CPR Part 71, and 49 CFR Parts 171-178.
- c. Reports of the radioactive solid waste shipments, volumes, principal radionuclides, and total curie quantity shall be submitted in accordance with subsection 5.6.1 of the H!!P-ETS.
3.2 Solid Waste Data Regulatory guide 1.21 Table 3 is found in this report as I ' '- l e 3-1.
.,.,. .> - .x ,, . - . . , . ~ ' .- s. ,~ ,
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(20)
TABLE 2-1 EFFLUENT AHD HASTE DI SPOS AL SE!1I Atit4U AL REPORT 1978 GGSECUS EFFLUENTS-SUllMATION OF ALL RELEASES Unit Quarter Quarter Est Total 4 Errcr l E. I. Hat.-h Huclear Power Plant UNIT 2 3 l R. Fiz2 ion 0 ac t i o at i on gases j
- 1. Tot al releisc Ci 3.6?E+00 6.56L+01 8.02'E+01J !
- 2. herage release rat e fcr period uCi sec 4.67E-01 9.1TE+00 3.
of Te c hni c al spec i fi c at i on l i rii t % 2.54E-04 1.93E-01 B. Iodine 3
- 1. Tot al iodine-131 Ci 5.65E-06 ?.08E-05l 1,,10 E + 0 - [
- 2. Aver age re1 ease r at e for period uCi/sec 7.19E-07 5.83E-06I
?. of Technical spc c i fi c at i on l i ra i t . 2.82E-04 1. 5 4 E -- 0 5 !
C. Paa t i c u l at e s
- 1. Part i c ul at e s with half-lives >9 dws Ci 4.41E-06I E.39E-06 I I . 0 0 E + 0[
5.61E-0? 1.04E-06! _ _2. Averac_e_re1e u e rat e for period uCi<sec 9.80E-04 1.65E-031
's
, . of Tec hni c al 3 pe c i f i c at i on l i ra i t .
- 4. Grosr alpha radi c ac t i v i t o Ci 6.80E-07 3.69E-07J D. Tritiuu. '
( 1. Total re 1e ese Ci 3.09E-01 1. 7 9E-01 I ' 9. 0 -J E + 01 I
- 2. R'>e r a,e reieas- rat- for period oCi/sec 3.93E-02 2 . 2 2 E - 0.:.a
~.
- o_f_ Te c hni c al s pe c i f i : at ion linit
. 1.67E+00 5.??E-01!
( (21)
TABLE 2-2 g E. I. Hatch Nuc l e ar Pouer Pl ant UNIT 2 EFF '; tit RHD HASTE DISPOSAL SEMIRHHUAL REPORT 1978 GASEOUS EFFLUENTS-ELEVATED RELEASE CONTIHUOUS 110 D E EATCH MODE Huc1 ides Re l e as e d Unit Quarter Qu ar t er Quarter Qu ar t e r 3 4 ? 4
- 1. Fission gases se-137 Ci 2.54E+00 1.31E+011 0.00E+001 0.00E+00 Xe-131M Ci 0.00E+00 8.85E-01 0.00E+00 0.00E+00 Lr-58 C1 1.19E-01 7.04E-01 0.00E+00 0.00E+00 a -133M Ci 0.00E+00 4.39E-02 0.00E+00 0.00E+00 Xc-135 Ci 6.16E-02 3.E5E-01 0.00E+00 0.00E+00 Kr-85M Ci 4.21E-01 2.64E+00 0.00E+00 0.00E+00 I-131 Ci 1.07E-02 0.00E+00 0.00E+00 0.00E+00 Br-97 C1 4.04E-02 1.96E-01 0.00E+00{ 0.00E+00 Xe-13E Ci 2.22E-01 6. 34E-01 0.00E+001 0.00E+00 Xe-137 Ci 5.80E-04 0.00E+00 0.00E+00 0.00E+00 H-12 Ci <.t.4E-02 6.02E-01 0.00E+00 0.00E+00 Kr-85 Ci O.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135M C1 E. 05E-05 1.2?E-01 0.00E+00 0.00E+00 I-123 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-59 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 5.69E-02 2.30E-01 0.00E+00 0.00E+00 Tot al for ceriod Ci 3.54E+00 1.95E+01 0.00E+00 0.00E+00
- 2. lodines I-121 Ci 1.66E-07 1.11E-06 0.00E+00 0.OnE+00 I-133 C1 4.56E-07 1.93E-06 0.00E+00 0.00E+00 I-135 Ci 1.59E-09 9.60E-0? 0.00E+00 0.OOE+00
_ T ot al fer period Ci 6.38E-07 3.89E-06 0.00E*00 0.00E+00
- 3. F ar t i c u l at e s
'_ Tr-89 Ci 3.55E-07 4.17E-07 0.00E+00 0.00E+00 Sr-90 __C i 4.2SE-09 4.60E-09 0.00E+00 0.00E+00 Ce-141 Ci O.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci O.00E+00 0.00E+00 0.00E+00 0.00Et00 1-131 Ci 2.24E-10 4.16E-OS 0.00E+00 0.00E+00 -
Sn-11: Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ea-140 Ci 0.00E+00 2.40E-07 0.00E+00 0. ODE +00 C1-1la Ci 0.00E+00 5.13E-Oi 0.00E+001 0.00E+00 C4-137 Ci 0.00E+00 6.67E-0E 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00_ 0.00E+00 0.a0E 00 0.00E+00 Er-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hb -95 Ci 0.00E+00 0.00E+00 0.00E+00} 0.00E+00 _ Co-5E - Ci 0.00E+00 0.00E+00 0.00Et006 0.00E+00 T Mn-54 Ci 0.00E+00 0.00E+05I 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00i 0.'30E+00 0.00Et00 Co-60 Ci 1.11E-09 5.49E-0? IO 00E+00 0.00E+00 Ls-140 ! Ci 1.12E-n3 6.7aE-07I 0.00E+00 0.30E+00 t + t-1 i l
! T c. t At f .: r reri,, Ci 3.?2E-07 1 50E-0 ! - W +noI 0.00E+00 (22)
TABLE 2-3 E. I. H at c h Huc l ear P c4> e r Plant UNIT 2 PFFLUENT RHD HASTE DISPOSAL 5FMIANNUAL REPORT 1978 GASEOUS EFFLUENT 5-GROUND-LEVEL RELEASE l t CONTINUGUS MODE EATCH NODE I huclices Peleazea Uni' Ou ar t e r Quarter Qu ar t e r Quarter j 3 4 3 4
- 1. F112icn g as e i re-1?' Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 M-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ur-0? Ci 0.00E+00 1.59E-01 0.00E+00 0.00E+00 M-1??M Ci 0.OOE+00 0.00E+00 0.00E+00 0.00E+00
<c-135 Ci 1.30E-01 5.97E-01 0.00E+001 0.00E+00 Er-85M C1 0.00E+00 0.00E+00 0.00E+001 0.00E+00 T-131 Ci 0.00E+00 0.00E+00 0.00E+00j 0.00E+00 Fr-57 Ci O.00E+0ai 1.02E-01 0.00E+00 0.00E+00 W -13S Ci 0.00E+001 0.00E+00 0.00E+00 0.00E+00 se-107 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l H-13 Ci 0.00E+00 0.00E+00 IO.00E+001 0.00E+00 i t
Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 !
"c-125n Ci 0.00E+00, 0.00E+00 0.00Er00 0.00E+00 I-13: Ci (f.'~0 0 E + 0 0 1 0.00E+00 0.00E+00 0.00E+00 v r -:E ; Ci 0.00E+00 4.52E+01 0.00E+00 0.00E+00 I-135 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
-_-_r-4T A
Tet at tor ceriod Ci 1.30E-01 4.61E+01 0.00E+00 0.00E+00
- 2. Iodines ,
I-1 31 Ci 0.00E+00 1.85E-06l O.00E+00 0.00E+00 1 - 1.: Ci 0.00E+00 ?.20E-05! 0.00E+00 0.00E+0F I-135 Ci 2.70E-06 1.50E-04 0.00E+00 0.00E+00 Ci 2.70E-06 1.G4E-04 0.00E+00 0.00E+00 Tctal r o. r -nm: r i o d i
- 3. Part 1 c ul at e s
~ 5 -:% Ci ~ 1.00E-06? 3.61E-06 0.00E+00 0.00E+00 ,
9r-90 Ci 8. 7 3E-0:E 3.30E-07 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-31 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-131 Ci 4.90E-08 0.00E+00 0.00E+00 0.00E+00
- Sn-11? Ci 0.00E+00 0.00E+0:' O.00E110 0.00E+0CL 1: a- 14 0 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
~
C2-124 Ci 1.25E-OS 0.00E+00 0.00E+00 0.00E+00
.2-137 Ci 0.UOE+00 0.00E+00l 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+0 ' O.00E+00 0.00E+00 2r r5 Ci 0.00E+00 0.00E+0C 0.00E*00i 0.00E+00 Ci 0.00E+00 0.00E*00 0 0.00E+00 0.00E+0e.b 0.00E+GO
.00E+00 0.00E+00 Nb-95 C 3-% Ci 0.30E+00 Un-50 4- Ci 0.00E+00 0.00E+00,1 0.00E+00 0.00E+00 F e -Y I Ci 0.00E+00 3.18E-07 P.00E+00 0.00E+00 2.57E-Oi 0.00E+C0 0.00E400
\ Co-60 I Ci 2.54E-06 0.00E+00 0.00E+ 6* 3.00E+00 T' , Ci 3.30E-0E ,
" 0.00E+00 Tor i Ci 4.00E-06 6.80E-0: __.---_--a '>I (23) o-
Table 3-1 Lont. EFFLUENT AND V/ASTE DISPOSAL SEMI ANNUAL REPORT (YEAR) 1978 -_ SOLID V/ASTE AND IRRADIATED FUEL SHIPMENTS FOR Ut!IT II A. SOLID WASTE SHIPPED OFFSITE FOR SUR!AL OR O!SFCS
- L (Not insdUtzd fuel) ur.it Ceco E u. To of
- 1. " Cyp. ef wnte err'a Enx. s
- a. Spent resins. fet:r site.:; 2 evn rstor m 2
- 1. 73 E +3 .
to t te r".:, e ::. Ct 1.os; E GOEOiT fC
- b. Dry compteuiole was:c, contar:un.i: d rn' E equip, c:c- Ci E 't
- c. feradic.ted comp:neau, coacral . ct' _
E tods. etc. Ci E E
- d. Other (de. nbe) m' E_
Ci El E
- 2. Edimst- el maior nectide competition (by tm of was:e)
ISOTOPE l PERCEiii l CURIES
- a. Cr" 68.10 1.33
~
C068 11776 0.22 ZtM 11.87 0_.23 All Others 8.77 0.17
- b. ~~
c. d. 1 l
- 3. Sond W.ute Dhpnitica Number o r shi:ments Made o f Tr:ns:odation Destin2tio i Chem-Nuclear Systems, Barnwell, S.C.
15 Inc. C. IRRADIATED FUEL SHIP?.1ENTS (Oispc:Itien) Nur W :or nieme-ti M3d: ef Trrmart::ien D-tiraden
> ~ ' - ' -
r- .- -- . f GM-215 7 8 (24) .
gw Jersey Central Power & Light Company
- J -
(I" ( ) Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 (201)455-8200 March 5, 1979 Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 c/o Distribution Services Branch DDC, ADM
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Reactor Building Integrated Leak Rate Test - November 1978 Enclosed are twelve (12) copies of a technical summary report of the " Reactor Containment Building integrated Leak Rate Test" performed in November 1978 at the Oyster Creek Nuclear Generating Station. This report is submitted in accordance with Technical Specifications, paragraph 6.9.3.b. Ver-y truly yours, I Q s ~~. Donald A. Ross, Manager Generating Stations-Nuclear cs Enclosures
\
V 7903120$G Jersey Central Power & Light Company is a Member of the General Pubhc Utikties System
,~ PREFACE This Semiannual Report is divided into three sections. The first la a complete report of the releases for the two unit plant (site) using the current Technical Specification reporting requirements. The other two sections are semiannual reports for each unit separately. These last two sections are presented only as an extra assurance that all requirements for reporting, as specified in the Environmental Technical Specifications, are met. l 1 l 1}}