HL-1785, Georgia Power Co Plant,Ei Hatch Units 1 & 2 Semiannual Radioactive Effulent Release Rept,Jan-June 1991
| ML20082L905 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/30/1991 |
| From: | Beckham J GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| HL-1785, NUDOCS 9109040457 | |
| Download: ML20082L905 (55) | |
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{i f o'.9Qhd'f1 A.a!,rtia liW1 le:epV . Of; ei7 7 72 lit u a i B cm.m a,, GCOlgill POWCf m ,~n n.+ N o nwn n , ;r ' , HL- 1785 August 26, 1991 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Plant Hatch - Unit I and 2 NRC Docket 50-321 and 50-366 Operating License DPR-57 and NPF-5 Eff2 ANNUAL RADI0 ACTIVE EFFLUEN1 RELEASE REPORT Geatlemen: In accordance with the provisions of Plant Hatch lechnical Specifications Sections 6.9.1.8 and 6.9.1.9, Georgia Power Company (GPC) is providing six copies of the Plant Hatch Unit I and 2 Semiannual Radioactive Effluent Release Report. This report covers the period of January 1, 1991 through Jane 30, 1991. Should you have any questions please advise. Sincerely,
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/J. T. Beckham, Jr.
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U. S. Nuclear Regulatory Conmission Page 2 August 26, 1991 cc: Georaia Poycr Company Mr. H. L, Sumner, Jr. General Manager - Nuclear Plant Mr. W. R. Woodall, Manager Environmental Affairs Mr. C. L. Whatley, Manager Nuclear Insurance and Risk Management NORMS U. S. Nuclear Regulatory Commission. WashinolonAL Mr. K. vabbour Licensing Project Manager - Hatch V. S. Nusjear Reaulatory Commistion. Reaton il Mr. S. D. Ebneter, Regional Administrator Mr. L. D. Wert. Senior Resident inspector 1 l American Nuclear Insurers Mr. M. Marugg State of Georgia Mr. J. Setser, DNR l l-l I r i l
! GEORGIA KMER COMPNJY PLANT E. I. HATO! UNITS to.1 & 2 SEMIANNUAL RADIOACTIVE EFFLUErfI' RELEAS3 REPORT January 1,1991 - June 30,1991 O O
. 4 PLANT E. I . HVICH SEMIANNLAL RADIOACTIVE EFFLUEtC RELEASE REPORT ECTION TITLE PAGE
- 1. LIOUID EFFLUEtES 1 1.1 REGULA'IORY LIMITS 1 1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS 5 1.3 MIASUREMEtES AND APPROXIMATIONS OF TOTAL RADIGACTIVITY 5 1.4 LIQUID EFFLUENT RELEASE DATA 7 1.5 RADIOLOGICAL IMPACT ON MAN DUE TO LIOUID RELEASES 9 2 GASEOUS EFFLUErfrS 19 2.1 REGULA'IVRY LIMITS 19 2.2 MEASUREMEtTTS AND APPROXIMATIONS OP 70TAL RADIOACTIVITY 25 2.3 GASEOUS EFFLUENT RELEASE DATA 30 2.4 RADIOIOGICAL IMPACT DUE 'IO GASEOUS RELEASES 31 3 SOLID WAST'E 47 3.1 REGULATOft' REQUIREMENTS 47 3.2 SOLID WASTE DATA 47 O
A 4 PLAtC E. I. HATOi SEMIANNUAL RADIOACTIVE
,m - - (g) -
EFFLUEtR RELEASE REFORT TABLE LISTT OF TABLES PAGE 1-1 TECHNICAL SPECIFICATION TABLE 3.14.1-1 RADIOACTIVE LIQUID EFFLUEtR MONITORING INSTRUMENTATION 3 1-2a LIQUID EFFLUE!CS - SUMMATION OF ALL RELEASES - UNIT 1 10 1-2b LIQUID EFFLUEtCS - SUMMATION OF ALL RELEASES - UNIT 2 11 1-2c LIQUID EFFLUENTS - SUMMATIONS OF ALL RELEASES - SITE 12 j 1-3a LIQUID EFFLUENTS ~ UNIT 1 13 i 1-3b LIQUID EFFLUEtCS - UNIT 2 14 r 1-3c LIQUID EFFLUE!CS - SITE 15 1-4a INDIVIDUAL DOSES DUE % LIQUID ; .- RELEASES - UNIT 1 16 1-4b INDIVIDUAL DOSES DUE TO LIQUID RELEASES - UNIT 2 17 i-1-5 INER LIMITS OF DETECTION - LIC'!ID , SAMPLE ANALYSES 18 2-1 TECHNICAL SPECIFICATIO1 TABLE [ 3.14.2-1 RADIOACTIVE GASEOUS EFFLUENT MONI'IORING INSTRUMENTATIQ1 21-2-2a GASEOUS EFFLUENTS - SUMMATION OP h
. ALL RELEASES - UNIT 1 32 2-2b GASEOUS EFFLUENTS - SUMMATIO1 OF 33 ALL RELEASES - UNIT 2 2-2c GASEOUS EFFLUENTS - SUMMATIQ1 OF ALL RELEASES - SITE 34 2-3a GASEOUS EFFLUENTS - ELEVATED RELEASES - UNIT 1 35 ,
2-3b GASEOUS EFFLUENTS - ELEVATED [ RELEASES - UNIT 2 36 4 3c GASEOUS EFFLUENTS - ELEVATED PELEASES - SITE 37
TABLES LIST OF TABLES PAGE O 2-4a Gd5DUS EFFLUEIRS - GROUtO-LEVEL RELEASES - UNIT 1 38 2-4b GASDOUS EFFLUEtCS - GROUfC - LEVEL RELEASES - UNIT 2 39 2-4c GASEO'JS EFFLUEtES - GROUND - LEVEL RELEASES - SITE 40 2-5 GASEOUS EFFLUEtES - DOSE RATES - SITE 41 2-6a AIR DOSES DUE 70 tOBLE GASES - UNIT 1 42 , 2-6b AIR DOSES DUE "O NOBLE GASES - UNIT 2 43 2-7a INDIVIDUAL DOSES DUE 'IO RADIOIODINE, TRITIUM, AND PARTICULATES IN CASEOUS RELEASES - UNIT 1 44 3 2-7b INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM, AND PARTICULATES IN CASEOUS
- RELEASES - UNIT 2 45 2-8 IIMER LIMITS OF DETECTION - GASEOUS SAMPLE ANALYSES 46 3-la,b SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 48,49 O
i
RADIOACTIVE EFFLUEtC RELEASE REPORT 1 LIQUID EFFLUEffrS [U'T l.1. REGULA70RY LIMITS
- 1. The Technical Specifications presented in this section are t'or Unit 1. Requirements for Unit 2 are the same as Unit 1; however, the Technical Specification numbers are not the same.
[ TECHNICAL SPECIFICATIONS 3.14.1 The radioactive liquid effluent monitoring instrumentation channels shown in table 3.14.1-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.15.1 are not exceeded. TM alarm / trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION FANUAL (ODCM). (Technica1 Specification-Table 3.14.1-1 is included in this section as Table 1-1). 3.15.1.1 The concentration of radioactive material released at any time from the site to UNRESTRICIED AREAS (figure 3.15-1) shall be limited to the concentrations specified in 10 CPR Part 20, Appendix B,
- Table II (column 2) for radionuclides other than 5
-dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 uCi/ml total activity.
3.15.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, from the site (figure 3.15-1) shall be limited to:
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or
. equal to 5 mrem to any organ.
.. b. During any calendar year to less : ban or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
3.15.1.3 The liquid radwaste treatment system, as described in the ODCM, shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent per Unit from the site (figure 3.15-1) when projected over the calendar quarter would exceed 0.18 mrem to the total body or 0.62 mrem to any organ, o _I_
3.15.1. 4( a ) The contents within vny outride temporary tank shall be ;imited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases,. (a) An outside temporary tank is not surrounded by liners, dikes, or w ils that are capable of holding the tank contents and not having tank overflows and drains connected to the liquid radwaste treatment syatem. 6.9.1.9 states in part: "The Radioactive Effluent Release Report shall include (on a quarterly basis) unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents that were in excess of I Ci, excludina dissolved and entrained cases and tritium for liquid effluents, or those in excess of 150 Ci of noble gases or 0.02 Ci of radiciodines for gaseous releases". O O
TABLE l-1 TECHNICAL SPECIFICATION TABLE 3.14.1-1 (SHEET 1 of 2) RADIOACIVE LIOUID EFFLUEtR MONI MRING INSTRUMEtTTATION Minimum Channels Instrument OPERABLE Applicability ACTIO!!_
- 1. Gross Radioactivity Monitors Providing Automatic Termina-tion of Release Liquid Radwaste Effluent Line 1 (a) 100
- 2. Gross Radioactivity Monitors not Providing Automatic Termination of Release Service Water System Effluent
- Line 1 (b) 10 1 O 3. Flowrate Measure-ment Devices **
Liquid Radwaste Effluent Line 1 (a) 10 2 Discharge Canal 1 (b) (a) 102
- 4. Service Water 1 At all times 103 System to Closed Cooling Water System Differential Pressure,
** Pump curves may be utilized to estimate flow; in such cases, ACTION statement 102 is not required.
(a) Whenever the radwaste discharge valves are not locked closed. ( b )- Whenever the service water system pressure is below the closed cooling water system pressure or differential pressure indication is not available, l j
TABLE 1 1 (COfffINUED) TECHNICAh SPECIFICATION TABLE 3.14.1-1 (SHEET 2 of 2) RADIOACTIVE LICOID EFFLC'NT MONI'IORIrr INSTRUME?TTATION g TABLE FUTATIONS ACTION 100 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be continued, provided that prior to initiating a release:
- a. At least two independent samples are analyzed in ,
accordance with Specification 4.15.1.1.1.
. b. At least two technically qualified individuals independently verify the release rate calculations and discharge valving.
Otherwise, suspend release of radioactive effluents via this pathway. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. , ACTION 101 - With the numbers of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided that once per shift grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a Lower Limit of Detection of at least 10-7 uCi/ml. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. ACTION 102 - With the namber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided the flowrate is estimated at le&st once per 4 hours during actual. releases. If the channel remains increrable for over 30 days, an explanation of the circumstances Mall be included in the next seni-annual effluent release report. ACTION 103 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, assure that the service water system effluent system monitor is OPERABLE. O _1. . _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ - - _ _ ___ _ - _ - - _ _ _ _ - - _ - - - - - - --~ -
G 1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS
} The MPC values used in determining allowable liquid radwaste release rates and concentrations for principal gamma emitters, I-131, tritium, y Sr-89, St-90 and Fe-55 are taken from 10CFR Part 20, Appendix B, Table II, Column 2.
For dissolved or entrained noble gases in liquid radwaste, the MPC is taken from Technical Gpecification 3.15.1.1 (Un.: 1) and 3.11.1.1 (Unit >
- 2) as 2.0E-04 uCi/cd. !
~
For gross alpha in liquid rtdwaste, the MPC is taken from 10 CPR Part 20, hpoendix B, Note 2.b as . 3.0E-08 uCi/ml. Further, for all the above radionuclides or categories of radioactivity, the overall MPC t fraction is deternuned in accordance with 10 CFR Part 20, Appendix B, Note 1. , t The method whereby the MPC fraction is used to determine release rates and liquid radwaste . i effluent radiation monitor setpoints is described- - in Section 1.3 of this report.
.j-~3 ;
, d 1.3 MEASUREMEtTPS AND APPROXIMATIONS OF TCTPAL RADIOACTIVITY Prior to release of any tank.containing liquid l radwaste, and following the required t recirculation, samples are collected and analyzed , in accordance with Technical Specification Tables l 4.15.1-1 (Unit 1) and 4.11.1-l'(Unit 2). A sample from each tank planned for release is analyzed for ; principal camma emitters, I-131, and dissolved and ) entrained noble gases by gamma spectrometry.
- Monthly and quarterly composites are prepared for .
analysis by extracting aliquots from each sample ; taken from tanks which are released. Liquid F radwaste samole analyses are performed as follows: , Measurenent Frequency Method i
- 1. Gamwi Isotopic Each Batch Gamma spectroscopy with computerized ,
data reduction _. 2. Dissolved or Each Batch Ganna spectroscopy r (N Entrained with computerized ' () Noble Gases data reduction [ II
-S- ,
p
l l Measurement Frequency Method gS (f~
- 3. Tritium Monthly Composite Distillation and liquid scintillation counting
- 4. Gross Alpha Monthly Gas flow proportional Composite counting
- 5. Sr-89 and Sr-90 Quarterly Chemical separation and Composite gas flow procortional counting
- 6. Fe-55 Quarterly Chemical separation and Composite low energy photon detector.
Gamma isotopic measurements are performed in-house in the radiochemistry lab using germnium spectrometry. Three germnium detectors are available: a 20% efficient and two 15% efficient intrinsic germanium detectors, with 2.0 FWHM resolu* ion and housed in 4 inch-thick lead shields. A one liter liquid radwaste sample is poured into a Marinelli beaker in . preparation for a 3000 second count. A peak search of 7, the resulting gamma ray spectrum is performed by the
) conputer system. Energy and net count data for all V significant peaks are determined, and quantitative reduction or LLD calculations are performed for the nuclides specified in Table Notation e of Technical Specification Tables 4.15.1-1 (Unit 11 and 4.11.1-1 (Unit 2): Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. The quantitative calculations include corrections for counting time, decay time, sarple volume, sample geometry, detector efficiency, baseline counts, and branching ratio. LLD 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 radionuclide would be located if present.
The radionuclide concentrations determined by gamma spectroscopic analysis of a sample taken from a tank planned for release and the most current sample analysis results available for tritium, gross alpha, St-89, Sr-90, and Fe-55 are used along with the corresponding MPC values to determine an MPC fraction for the tank planned for release. This MPC fraction is then used, with appropriate safety factors, along with the expected dilution stream flow to calculate a maximum permissible release rate and a liquid effluent f] n/ monitor setpoint. The monitor setpoint is calculated to assure that the limits of Technical Specifications 3.15.1.1 (Unit 1) or 3.11.1.1 (Unit 2 ) are not exceeded. E-
- - - - _ _ - - - w
A monitot reading in excess of the calculated setpoint therefore results in an automatic O- termination of the liquid radwaste discharge. Liquid effluent discharae is also automatically terminated if the dilution stream flow rate falls below the dilution flow rate used in the setpoint calculations and established as a setpoint on the dilution stream flow mcnitor. Radionuclide concentrativns, safety factors, dilution atream flow rate, and liquid effluent radiation monitor calibration factor are entered into the computer and a prerelease printout is aenerated. If the release is not permissible appropriate warnings will be included on the prerelease printout. If the release is permissible it is approved by the Chemistry Foreman on duty. The pertinent inforration is transferred manually from the prerelease printout to a one-page release permit which is forwarded to Radwaste Operations. When the release is completed the release permit is returned from Radwaste Operations with actual release data included. These data are input to the computer and a post release printout is ger.erated. The post release printout contains actual release rates, actual release concentrations and O quantities, actual dilution flow, and calculated doses to an individual. 1.4 LIOUID EFFLUEm' RELEASE DATA Regulatory Guide 1.21 Tables 2A and 2B are found in this report as Table 1-2a for Unit 1, Table 1-2b for Unit 2 and Table 1-2c for the site; and Table 1-3a for Unit 1,1-3b for Unit 2, and Table 1-3c for the site. The values for the four categories of Tables 1-2a
. and 1-2b, and 1-2c are calculated and the Tables completed as follows:
- 1. Fission and activation products - The total release values (not including tritium, gases, and alpha) are comprised of the sum of the measured individual radionuclide activities. This sum is for each batch released to the river for the respective O
-7
( j i quarter. Percent of applicable limit is determined from a mixed nuclide MPC fraction f calculation. The average concentration for : _tS each nuclide over all released batches is
- ( ,) _
divided by the corresponding individual MPC value. The sum over all nuclides of the C/MPC ratios times 100 is the percent of applicable limit for effluent releases during the quarter.
- 2. Tritium - The measured tritium concentrations in the monthly composite samples are used to calculate the total release and average diluted concentration during each period. Average diluted :
concentration divided by the MPC limit, 4 3.0E-03 uCi/ml, is converted to percent to give the percent of applicable limit. ,
- 3. Dissolved and entrained gases - $
Concentrations of dissolved and entrained gases in liquid effluents are measured by , germanium spectroscopy on a one liter sample ; from each liquid radwaste batch. The l average concentration of dissolved or entrained noble gases for all released
- batches is divided by the MPC value stated in Technical Specifications 3.15.1.1 and
( 7 N s'
) 3.11.1.1 ( 2.0E-04 uCi/ml) to determine the MPC fraction. The result x100 is the percent of applicable limit for noble gases in liquid effluent releases during the ;
quarter. Radioisotopes of iodine 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. i
- 4. Gross alpha radioactivity - The measured gross alpha concentrations in the monthly ,
-- composite samples are used to calculate the ,
total release of alpha radioactivity. P
?
1 8. , b u i t i
Other data pertinent to batch releases of i r~~S- radioactive liquid effluent from both units are _ ( ,) as follows: Number of batch releases: 703 Total time period fcr batch releases: 78,332 minutes Maximum time period for a batch release: 250.0 minutes Average time period for batch releases: 111.4 minutes Minimum time period for a batch release: 2.0 minutes Average stream flow during periods of release of liquid effluent into a flowing stceam: 17,840 CFS 1.5 RADIOILGICAL IMPACT ON MAN DUE 'IO LIQUID RELFASES Doses to an individual, due to radioactivity in liquid effluent, were calculated in accordance ' with Technical Specifications 3/4.15.1.2 (Unit 1) and 3/4.11.1;2 (Unit 2) using the methodology presented in the Plant Edwin I. Hatch Offsite-Dose Calculation Manual. As required by the , above Technical Specifications, doses were calculated separately for Unit I and Unit 2.- [J
's Results are presented in Table 1-4a for Unit 1 and Table 1-4b for Unit 2.
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TABLE 1-2a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 g LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 1 Quarter 2 Est. Total Error (%) A. Fission and activation products
- 1. Total re1 9 ase Ci 2.18E-02 5.45E-02 4.70E+01
- 2. Average diluted congentration during period uCi/ml 2.69E-08 3.52E-08
- 3. % of applicable limit % 1.17E+00 1.12E+00 B. Tritium
- 1. Total release Ci 3.72E+00 8.01E+00 3.70E+01
- 2. Average diluted congentration during period uCi/ml 4.58E-06 5.17E-06
- 3. % of applicable limit % 1.53E-01 1.72E-01 C. Dissolved and entrained gases
- 1. Total release Ci 5.69E-03 2.51E-02 1.00E+02
- 2. Average diluted concentration during period
% of applicable uCi/ml 7.01E-09 1.62E-08
( 3. limit % 3.51E-03 8.08E-03 D. Gross Alpha radioactivity
- 1. Total release Ci 0.00E+00 0.00E+00 1.20E+02 E. Volume of waste (prior to dilution) liters 3.69E+06 6.22E+06 1.00E+01 F. Volume of dilution water used liters 8.12E+08 1.55E+09 1.60E+02
- 10 -
}
TABLE 1-2b E. I. HATCH NUCLEAR PLANT - UNIT 2 e~ SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 3991 f(s LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES , i Unit Quarter 1 Quarter 2 Est. Total i Error (%) ; A. Fission and ; activation ! products i
- 1. Total release Ci 1.42E-02 1.23E-01 4.70E+01 2.-Avorage di:.uted concentrat:.on during per;.od uCi/ml 1.98E-08 1.16E-07
- 3. %,of applicable limit % 1.83E-01 2.91E-01 ,
-B. Tritium [
- 1. Total release Ci 2.06E+00 2.50E+00 3.70E+01 '
- 2. Average di:.uted concentrat;.on during por: od uCi/ml 2.88E-06 2.36E-06 i
- 3. % of applicable limit % 9.60E-02 7.87E-02 ;
C. Dissolved and i entrained gases
- t
- 1. Total release C1 1.13E-03 5.65E-04 1.00E+02 :
- 2. Average di:.uted concentrat:,on
/
(,j) during period uCi/ml 1.58E-09 5.33E-10 i
- 3. % of applicable limit % 7.88E-04 2.66E-04 D. Gross Alpha radioactivity
- 1. Total release Ci 0.00E+00 0.00E+00 1.20E+02 E. Volume of waste (Drlor to i dilution) liters 3.18E+06 4.72E+06 1.00E+01 ,
F. Volume of dilution wa.ter used liters 7.15E+08 1.06E+09 1.60E+02 ' t [ k U t a
TABLE 1-2c E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991
;(
) LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES l
Unit Quarter 1 Quarter 2 Est. Total Error (%) A. Fis ion and act vation ; pro ucts 1
- 1. Total rel ase ci 3.60E-02 1.78E-01 4.70E+01 :
- 2. Average d uted -
concentrat on ! during p lod uC1/ml 2.36E-08 6.80E-08 $
- 3. % app cable .
li t % 7.10E-01 7.83E-01 i B. Tritium i
- 1. Total release Ci 5.78E+00 1.05E+01 3.70E+01
- 2. . Average di:.uted .
concentratLon i durno Lod uCi/ml 3.78E-06 4.03E-06 L
- 3. % p cable li t % 1.26E-01 1.34E-01 ;
C. Dissolved and entrained gases
- 1. Total reloa50 Ci 6.82E-03 2.56E-02 1.00E+02
- i
- 2. Average diluted .
con entrat on ! dur n per od -uCi/ml 4.47E-09 9.82E-09 : (_ 3.'% li t pplicable
% 2.235-03 4.91E-03 f
I D. Gro s Al rad oact ty r
- 1. Total release Ci 0.00E+00 0.00E+00 1.20E+02 ,
'[
E. Volyme of waste Prior to ilution) liters 6.87E+06 1.09E+07 1.00E+01 ' FL V lum of d lut on wa.ter used liters 1.53E+09 2.61E+09 1.60E+02 l h t
+
I L ! l 1 p l I l.
TABLE 1-3a* E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 s LIQUID EFFLUENTS LJ Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 H-3 Ci 3.72E+00 8.01E+00 Fission and activation products: Na-24 C:, 1.94E-03 4.93E-03 Cr-51 C: 2.41E-04 4.35E-04 Mn-54 C:, 4.53E-04 1.74E-03 Mn-56 C: 0.00E+00 2.24E-05 Fe-59 C: 0.00E+00 3.24E-04 Co-58 C 2.88E-04 7.43E-04 Co-60 C:, 2.83E-03 6.32E-03 Zn-65 C: 3.44E-03 9.31E-03 As-76 C:, 5.81E-06 4.3SE-n6 Sr-89 Cn 1.59E-04 0.00E+00 Sr-91 C4 0.00E+00 4.05E-05 Sr-92 C:, 2.21E-06 5.72E-06 Y-91m C:, 0.00E+00 1.99E-05 Nb-95 Ca 2.58E-06 6.30E-06 Nb-97 C4 1.41E-05 4.59E-05 Mo-99 C: 0.00E+00 1.03E-04 Tc-99m CL 1.52E-04 7.48E-04 I-131 C:. 1.89E-03 1.62E-03 I-132 C:. 3.20E-05 8.51E-04
- I-133 C:, 2.38E-03 9.02E-03 I-134 C: 0.00E+00 2.95E-04 I-135 C: 5.30E-04 6.55E-03 Cs-134 C;. 1.23E-03 1.72E-03 C,
[( )T Cs-137 Ba-140 C; 5.71E-03 1.89E-04 9.66E-03 6.38E-06 La-140 C: 2.62E-04 1.44E-05 Ce-141 C: 2.79E-05 0.00E+00 Np-239 C: 7.57E-05 2.20E-05 Zn-69m C;. 0.00E+00 4.68E-06 Total Ca 2.18E-02 5.45E-02 Dissolved and gntrained gases: Kr-85 C1 0.00E+00 1.86E-04 Kr-87 C:. 0.00E+00 2.36E-05 Xe-131m C: 3.77E-04 0.00E+00 Xe-133m C; 1.21E-05 0.00E+00 Xe-133 CL 1.28E-03 1.12E-03 Xe-135m C; 9.89E-04 1.35E-02 Xe-135 C f. 3.03E-03 1.02E-02 Ar-41 C: 1.51E-06 5.18E-05 Total C: 5.69E-03 2.51E-02 Gr-Alpha Ci 0.00E+00 0.00E+00
- Zeroes in this table indicate that no radioactivity wa9 resent above detectable levels See Table 1-5 for t Sowerlimitsofdetectionforliquidsampleanalyses.ypical
**There are no continuous mode radioactive liquid release pathways at Plant Hatch.
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TABLE 1-3b* E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 LIQUID EFFLUENTS (' Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 H-3 Ci 2.06E+00 2.50E+00 Fission and activation products: Na-24 C: 5.53E-04 4.04E-04 Cr-51 C: 4.06E-04 4.69E-03 Mn-54 C: 1.13E-03 1.07E-02 Mn-56 C: 0.00E+00 3.98E-OS Fe-59 C: 3.90E-05 5.85E-04 Co-58 C: 1.19E-03 8.42E-03 Co-60 C:. 3.29E-03 4.39E-02 Zn-6S C1 2.38E-03 3.67E-02 As-76 C: 4.61E-06 2.19E-05 Sr-92 C: 0.00E+00 7.50E-05 Y-91m C: 0.00E+00 4.08E-06 Nb-95 C: 0.00E+00 9.90E-05 Nb-97 C: 1.01E-04 8.09E-04 Tc-99m C: 1.63E-05 '2.01E-05 Sb-125 C:. 4.69E-06 2.54E-04 I-131 C: 1.17E-04 2.19E-06 I-132 C:, 1.84E-05 0.00E+00
- I-133 C: 4.46E-04 3.69E-05 I-134 C; 5.03E-04 1.41E-03
- I-135 C: 1.32E-04 0.00E+00 Cs-134 C:. 7.61E-04 2.68E-03
- Cs-137 C:, 3.06E-03 1.22E-02 .
Ba-140 C; 0.00E+00 6.32E-06 ! f)/ t La-140 Np-239 Total C: C:, C:, 3.40E-06 0.00E+00 1.42E-02 0.00E+00 3.93E-05 1.23E-01 i
?
Dissolved and entrained gases: .
=Xe-133 C:. 1.73E-04 6.76E-05 Xe-135m C 9.58E-05 0.00E+00 -
-Xe-135 C:. 8.58E-04 4.95E-04 ;
Ar-41 C: 0.00E+00 2.34E-06 Total C: 1.13E-03 5.65E-04 i Gr-Alpha Ci 0.00E+00 0.00E+00 ,
-* Zeroes in this table indicate that no radioactivity wa gresentagovedetectabgelevelsts ower 11 of detect on for liquT"d sample analysesee Table 1-5 for typ ca*
**There are no continuous mode radioactive liquid release pathways at Plant Hatch, i
f I h m amh
TABLE 1-3c* E. I.--HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 ; LIQUID EFFLUENTS ("x -(_) Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 H-3 Ci 5.78E+00 1.05E+01 Fission and activation products: Na-24 C: 2.49E-03 5.33E-03 Cr-51 C: 6.47E-04 5.12E-03 Mn-54 C: 1.58E-03 1.25E-02 > Mn-56 C: 0.00E+00 6.21E-05 Fe-59 C: 3.90E-05 9.09E-04 Co-58 C: 1.48E-03 9.17E-03 Co-60 C: 6.11E-03 5.02E-02 s Zn-65 C: 5.82E-03 4.60E-02 : As-76 C: 1.04E-05 2.63E-05 i Sr-89 C:, 1.59E-04 0.00E+00 , Sr-91 C:. 0.00E+00 4.05E-05 l Sr-92 C: 2.21E-06 8.08E-05 Y-91m Cn 0.00E+00 2.40E-05 Nb-95 C4 2.58E-06 1.05E-04 Nb-97 C: 1.16E-04 8.55E-04 Mo-99 C:, 0.00E+00 1.03E-04 Tc-99m C 1.68E-04 7.69E-04 " Sb-125 Cf 4.69E-06 2.54E-04 I-131 C: 2.01E-03 1.62E-03 ; I-132 C: 5.04E-05 8.51E-04
- I-133 C: 2.82E-03 9.06E-03
- I-134 C; 5.03E-04 1.70E-01 i I-135 C: 6.62E-04 6.55E-C~
[\ Cs-134 C: 1.99E-03 4.40E-03 : () Cs-137 Ba-140 Ca C: 8.77E-03 1.89E-04 2.18E-02 1.27E-05 - La-140 C: 2.65E-04 1.44E-05
- Cc-141 C: 2.79E-05 0.00E+00 '-
Np-239 C: 7.57E-05 6.14E-05 Zn-69m C: 0.00E+00 4.68E-06 Total CL 3.60E-02 1.78E-01 Dissolved and entrained gases: I Er-85 C: 0.00E+00 1.86E-04 Kr-87 C: 0.00E+00 2.36E-05 Xe-131m C: 3.77E-04 0.00E+00 Xe-133m C: 1.21E-05 0.00E+00 Xe-133 C: 1.46E-03 1.19E-03 Xe-135m C: 1.08E-03 1.35E-02 Xe-135 C: 3.89E-03 1.07E-02 i Ar-41' ~ C:- 1.51E-06 5.41E-05 i Total C:. 6.82E-03 2.56E-02 i Gr-Alpha ci 0.00E+00 0.00E+00 t
- Zeroes in this table indicate that no radioactivity way L See Table 1-5 for t !
present above detectable levelslower limits of detection for liquid sample analyses.ypical
**There are no continuous mode radioactive liquid ;
release pathways at Plant Hatch. F
~ -.
l TABLE 1-4a I~ l E. 1. HATCH NUCLEAR PLANT - Unit 1 i () SEMIANNUAL RADICACTIVE EFFLUENT RELEASE REPORT 1991 INDIVIDUAL DOSES DUE TO LIQUID RELEASES r F Cumulative Doses per Quarter ' Organ Tech Unit Quarter 1 % of Quarter 2 % of Speg Tech Tech , Limit Spec Spec - Limit L1mit le B ne 5.0 mrem 2.23E-02 4.47E-01 3.30E-02 6.60E-01 ! L ver 5.0 mrem 3.45E-02 6.91E-01 5.11E-02 1.02E+00 i TBody 1.5 mrem 2.38E-02 1.58E+00 3.46E-02 2.31E+00 ! Thyroid 5.0 mrem 1.16E-02 2.32E-01 1.23E-02 2.46E-01 Ki8ney 5.0 mrem 1.20E-02 2.40E-Oi 1.82E-02 3.63E-01 ! Lung 5.0 mrem 3.75E 7.50E-02 5.43E-03 1.09E-01 GILLI 5.0 mrem 2.87E-03 5.73E 5.78E _. .,_____ 1.16E _-01
. __.___________..___..........___..___-02 _________-03 __ >
r t Cumulative Doses This Year -
. Organ Tech Unit Quarters % of !
Snec . 1&2 Tech " Gimit Spec
- Limit +
~ - [T B nb "5b b mrbm b 54b-b2 bI5kE-b5 - ( ,) L var TBody 10.0 mrem mrem 8.57E-02 5.84E-02 8.57E-01 -
3.0 1.95E+00 Thyroid 10.0 mrem 2.39E-02 2.39E-01 Kidney 10.0 mrem 3.02E-02 3.02E-01 Lung 10.0' mrem 9.18E-03 9.18E-02 , GILLI 10.0 mrem 8.65E 03 8.65E 02 - i F 1 N 5 9 l i [ \ : (_) t [
i
-g ll E
TABLE'1-4b I O:- E.-I.-HATCH NUCLEAR PLANT - Unit 2
- SEMIANNUAL RADIOACTIVE EFFLUENT-RELEASE REPORT 1991-
-INDIVIDUAL DOSES DUE TO LIQUID RELEASES -
Cumulative Doses per Quarter
... ....__--_ ...... __ __________ ... _____=-_____,...-_.._.-
Organ Tech Speg-Unit Quarter 1 % of Quarter 2 % of Tech Tech Limit Spec 3 peg- - L1mit Limi ___________....____ ,__________________ .._____ _________t___ l s Bone- 5.0 : mrem '1.62E-02 3.24E 5.97E-02 1.19E+00 Liver 5.0 mrem 2.55E-02 5.11E-01 9.97E-02 1.99E+00
-TBody 1.5- mrem 1.77E-02 1.18E+00 6.77E-02 4.51E+00 l Thyroid--5.0 mrem- 1.29E-03 2.58E-02 6.25E-05~ 1.25E-03 Kianey= 5.0 mrem- 8.87E-03 1.77E-01 3.75E-02 7.50E-01 Lung 5.0 mrem- 2.76E-03 5.51E-02 9.45E 1.89E-01 GILLI .5. 0 _ _ mrem- 3.37E 03 6.74E 3.76E 02 7.52E
______.......__.--........ _ . -________-02 ___... _..__.......__-01__.
~
-Cumulative
......._____________. Doses ___..This Year'.. -_....... ...______________ .__
Organ Tech. Unit- Quarters % of Speg- 1& 2 Tech Limit Speg
- L1mit
-r' Bone 10.0 mrem :7.59E-02 7.59E -
1 Liver 10.0 mrem ~ 1.25E-01 1.25E+00 TBody 3.0 mrem- 8.54E-02 2.85E+00 Thyroid - 140.0- mrem 1.35E-03 1.35E-02
-Kianey-- 10.0- mram --4.64E-02 4.64E-01
' Lung 10.0 mram 1.22E-02 1.22E-01 LGILLI 10.0 mrem 4.09E-01
...__ ..--____'________4.09E-02 __.---________ ...._________.. . ___ ..
h t 4 b i
f TABLE 1-5 ; I.UdER LIMITS OF DETECTION - LIQUID SAMPLE ANALYSES 7-The values in this table represent apriori lower limits of detection (LLD) which are typically achieved in laboratory analyses of liquid radwaste samples. . RADIONUCLIDE LLD UNITS Mn-54 S.38E-08 uC1/ml Fe-59 7.78E-08 Co-58 4.67E 08 Co-60 4.78E-08 In-65 1.31E-07 Mo-99 5.10E-07* Cs-134 7.10E-08 Cs-137 6.05E-08 C e-141 1.41E-07 Ce-144 6.30E-07* I-131 6.51F-08 ' Xe-135 8.45E-08 Fe-55 2.00E-06 Sr-89 5.00E-08 Sr-90 5.00E-08 H-3 1.00E-05 . I) *In accordance with Technical Specification Tables 4.15.1-1 (Unit 1) and \-~ 4.11.1-1 (Unit 2), Table Notation b, the permissible Lower Limit of Detection may be increased inversely proportional to the magnitude of the gamma yield. However, the LLD determined in this manner must not exceed 10 percent of the Maximum Permissible Concentration (MPC) value specified ; in 10 CFR20, Appendix B, Table II (Column 2). L w , r V ,
-lo- ,
t
3 t 2 GASEOUS EFFLUEIRS - f~Y 2.1 REGULA'IORY LIMITS if The Technical Specifications presented in this section f L are for Unit 1. Requirements for Unit 2 are the same as for Unit la however, the Technical Specification : numbers are not the same. .; TECHNICAL SPECIFICATIONS ; 3.14.2 The radioactive gaseous effluent monitoring instrumentation channels shown in table 3.14.2-1 shall be OPERABLE with their alarWtrip setpoints set to ensure that . the limits of Specification 3.15.2.1 (a) are not exceeded. l The alarWtrip setpoints of these channels shall be determined in accordance with the ODCM. (Technical l Specification Table 3.14.2-1 is included in this section as j Table 2-1). ; 3.15.2.1 The dose rate at any time in the UNRESTRICTED AREAS (figure 3.15-1) due to radioactive materials released ~ in gaseous effluents from the site shall be limited to the ! following values: 1
- a. The dose rate limit for noble gases shall be less I than or equal to 500 mrevyear to the total body l and less than or equal to 3000 mrem / year to the OV skin.
6
- b. Tne dose rate limit .for I-131, I-133,- tritium, :
and for all radioactive materials in particulate [ form and radionuclides oth(.ir than rc le gaoes with half-livea-areater than 8 ( shall be less : than or equal to 150u mc re', mar any organ. [ 3.15.2.2 The air- dose in UNRESTRICTED ARaS (figure : _3.15-1) due to noble cases released in gaseous effluents ' from each reactor unit shall be limited to the fotlowinc: '
*~
~
- a. During any calendar quarter, to less than or equal to 5 mrad for gamma radiation and less than ;
or equal to 10 mrad for beta radiation.
- b. During any calendar year, to less than or equal ,
to 10 mrad for gamma t 'iation and less than or equal to 20 mrad for beta radiation. , 3.15.2.3 The dose to any organ of a MEMBER OF THE PUBLIC i from I-131, I-133, tritium , and all radionuclides in . particulate form with half-lives greater than 8 days in gaseous effluents released to UNRESTRICTED AREAS (figure 3.15-1) from each reactor unit shall be limited to the -f following-L
r
~.= .-
r
- a. During any calendar quarter to less than or ;
equal to 7.5 mrem to any oraan. ,
-(.'% +
\~el b. During any ca - aar year to less than or equal to 15 mtem to any organ. l i
3.15.2.4 The GASEQUS RADWASTE TREATPER" SYSTEM-as I described in the ODCM shall be in operation. (Thia l Technical Specification applies whenever the main ! condenser air ejector system is in operation.) l 4.15.2.4 GASEOUS RADWASTE TREATMEtrP SYSTEM ! operability shall be demonc*rv -i ny administrative I controls which assure that the or'fgas treatment system is not bypassed, a 3.15.2.5 The annual (calendar year) dose or dose comitment to any MEMBER OF THE PUBLIC due to releases ! of radioactivity and to radiation fram uranium fuel cycle sources shall be limited' to less than or equal . to 25 mrem to the total body or any organ, except the I thyroid, which shall be limited to less than or equal , to 75 Exem. (With the calculated doses from the release of
- radioactive materials in liquid or gaseous effluents exceeding twice the limits of ;
.i ~
(~% Specifications 3.15.1.2(a), 3.15.1.2(b),
"q )y 3.15.2.2. (a), 3.15.2. 2(b), 3.15. 2. 3( a ), or ,
3.15.2.3(b), calculations shall be nade including ! direct radiation contributions fran the reactor , units and from outside storage tanks to determine whether the above limits of Specification , 3.15.2.5 have been exceeded. ; 3.15.2.6 The concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system shall be limited to less than or equal to 4 ! percent by volume. ; i 3.15.2.7 The gross gamma radioactivity rate of the ; noble gases Xe-133, Xe-135, Xe-138, Kr-85m, Kr-87, and f Kr-88 measured at the main condenser evacuation system pretreatment monitor station shall be limited to less _1 than _or equal to 240,000' uCi/second. 6.9.1.9 states in part:
"The Radioactive Effluent Release Deport shall include (ca a quarterly basis) unplanned releases i from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents that were in excess of 1 Ci, excluding
()
- dissolved and entrained gases and tritium for l' liquid effluents, or those in excess of 150 Ci of noble gases or 0.02 Ci of radioiodines for t gaseous releases." ',
I
- r
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E IAHI1 3. I ts . 2- I { $111 i I I Of is ) H39193El!Yi CAST DOS.lf iltf111L_H9M8 80MlW_!!1sittuMin! A!Ipg M e es s enam Cseas6tse i s ACI_tyg AJp l j f;mts i lj ty Pa r ame te r ( s W L t tesuesit 9flftABi [ I. M.e s es Condestse t' Of'f ga a i s na t swss t Sysie e L aplos sve Cas P40ns toreng s System
** % leydeugest t06 tsyde uncre Moses tur (l)
?. Ste.cc tur Besi id a 99 Vent Stach Monstoring System
- Hadsoactsvety Hate I O's Hoble Cas Actevity Moristor (1) M3a ses s emen t +
a.
- Verify Preserece of 101
- b. todene Sample r Ca s t s s dge (1) Cartridge i .- #
l w
- Ver s f y Pr esence of 807 @
l 8 c. Pts r t 6 c u l a t e Sampler letter (1) finter r4 t'1 l i ra
- d. I f I's eseset System ilowsate
- System itowrate lois e Me.a sse s emes s t Devste (l) Me a sse ressen t e, Sample r i t owra te th .a sur ensent
- Sampler iIowrate I D F.
peysee (;) Mea s se remere t
- 3. Ites s ete s ue r un e lef saag Vent e is t sun Moses tus steg System
- Radior 6.systy Hate 105 Noble Cas Actsysty Hoesstor (l) Mes sees t .* set +
a.
- Verift Ps e *"' Oe ?f 10?
Budene Sampler Castredge (I) Ca r t ridge b.
- Verify PresesKe of 201
- c. $.amples Ieetus (1) ietter P,.s s 1 s c se t a t e
- Samples 8 8 w s .s t e i te8s Nemples itows.te M..s see s ve use t (lJ Mea su s emuest
- d. .
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I Ant E 3.14.2-1 islitiI 2 of 4i H AtH OM ! ! YLUML9're .L !!L9tML M9M.i l9!!1E_1111Ifi'LMLMiaL195 Minimum Ottattf te 0 $ - j flh t f ung;i!L ' Qf'( ftASt { A ep i s catsi QLy l fprameter 6(isOJ
- 4. Main Stacis Monitoriang System
- Radioactivity Hate 10$
- a. Hobie Gas Activity Monitor (1)
Measaarement *
- b. todine Sampler Cartridge (1)
verify Presence of tol Cartridge .
- c. Pa rticula te Sampler f il ter (1)
- Verify Presence or 101 Filter d, I f f latent System Itowrate Messaaring Devices {l)
- System fIowrata 104 Me a saa remen t
- e. Sdampler i Iowra te Measieritay (1)
- Sampler flowrate 104 k3 Measurement ij ro Devace 8 ra
*) , Condeftser Offgah Pfeticathent Hann i t u r Ti Huble G.ss Actavity Monitor {l)
*** Radioactivsty Hate 108 [s Mes sas s emen t ...,
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9
T!aII :-1 (CONT'D) - (] TABLE 3.14.2-1 (SHEET 3 0F 4) RADIOACTIVE GASEOUS EFFtVENT MONITORING INSTRUMENTAT10N Table Notations
+ Monitor must be capable of responding to a Lower 1imit of Detection of 1 x 10-' pC1/ml. '
*0uring releases via this pathway.
"During main condenser off' gas treatment system operation.
"'Ouring narration of the main condenser air ejector.
ACTION 104 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided the flowrate is estimated at least once per 4 hours. If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. ACTION 105 - With the number of. channels OPERACLE less than required by the Minimum Channels OPERABLE requirement, effluent re' eases via this pathway may continue, provided grab samples are taken daily :nd analyzed daily for gross activity within 24 hours. With the nuinber of main stack monitoring system channwis OPERABLE less than required by the Minimum Channels OPERABLE requirement, without delay suspcnd drywell ourge. If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement 'or over 10 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. ACTION 106 - With the number of channels OPERABLE less than j required by the Minimum Channels OPERABLE requirement. l operation of the main condenser offgas treatment system may continue proutdad:
- (a) Gas samples are collected once per 4 hours and analyzed l
1 uithin the ensuing a hours, ce l (b) Using a temporary hydrogen analyzer installed in the i offgas system line downs,trean of the recombiner, l hydrogen concentration readings are taken and logged
- every 4 hours. >
l
-n-
i TABLE 2 1 (cottrep) i TABLE 3.14.2-1 ($HEET 4 0F 4) ; RADIOACTIVE GASEOUS EFFLUENT MON!TORING INSTRUNENTATION t Table Notations (Continued) j
. l If the numoet of channels OPERABLE remains less than !
required by the Minimum Channels OPERABLE requirement for f over 30 days, an explanation of the circumstances shall be l included in the next semi-annual effluent release report. ; I ACf!ON 107 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, i effluent releases via this pathway may continue, provided , samples are continuously collected with auxiliary sampling t eculpment for periods on the order of 7 days and analyzed i within 48 hours after the end of the sampling perioc.. ; If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE reoutrement for over 30 days, an explanation of the circumstances shall be j included in the next semeannual effluent release report. t ACTION 108 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, , release to the environment may continue for up to 72 hours ! Os- provided: l l
- a. The offgas system is not bypassed, and j
- b. The offgas post-treatment monitor (011-V615) or* the main !
stack monitor (011-K600) is ofERABLE. Otherwise, be in at least HOT STANDBY within 12 hours. If the number of channels OPERABLE remains less tha' . > required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be - included in ';he next semi-annual effluent release report. l i i i t O ;
-et. l
[
~w - ~~, -- . , , , _ , _ -
. , , _ _ _ - . . + - .
~a .w .w s M -er e w+- >+> e-esi'sen
2.2 MEASUREMEtIP AND APPROXIMATIONS OP 'IOTAL RADIOACTIVITY . Waste e s release at Plant Hatch is confined to l O four m that min stack (also called the offgas vent), Unit i reactor building vents Unit 2 reactor building vent, and the recombiner building vent. Each of these four paths is ; contin 90usly nonitored for gaseous i radioactivity. Each is equipped with an l integrating-type sample collection device for l collecting particulates and iodines. Sample ; collection is in accordance with Technical Specification Tables 4.15.2-1 (Unit 1) and i 4.11.2-1 (Unit 2). Unless required note frequently under certain circum tances specified in Table Notations to the above mentioned tables, camples are collected as in11ows:
- 1. Noble gas samples ate collected by orab campling monthly.
- 2. Tritium samples are collected by grab sampling monthly.
- 3. Radiolodine samles are collected by pulling the sample stream through a charcoal ,
cartridge over a 7-day period. O 4. Particulates are collected by pulling the sample stream through a particulate filter over a 7-day period.
- 5. The 7-day particulate filters above are arulyzed for gress alpha activity.
- 6. Quarterly composite camp 4es are prepared from the particulate filters collected over l
the previous quarter and the quarterly composite sample is analyzed for Sr-89 and Sr-90. Sample analyses restits and release flow rates from the four release points form the basis for calculating released quantities of radionuclide-specific radioactivity, dose rates associated with gaseous releases, and cumulative doses for the current quarter and year. This task is normily performed with computer assistance. I 1 f The noble gas grab sanple analysis results are l used along with mximum expected release flow ;
^
rates from each of the four vents to calculate :
\ monitor setpoints for the gaseous effluent monitors serving the four release points, to l assure that the limits of Technical !
Specifications 3.15.2.1.a (Unit 1) or 3.11.2.1.a i (Unit 2) are not exceeded. Calculation of : monitor setpaints is described in the Plant Hatch ODCM.
)
With each release period released radioactivity, i dm e rates, and cumulative doces are calculated. Cumulative dose results are tabulated along with percent of Technical Specification limits ( 3.15.2.2 and 3.15.2.3 (Unit 1); 3.11.2.2 and ; 3.11.2.3 (Unit 21 for each release, for the l current quarter and year, i After each calendar quarter (13 weeks) a summary v of waste gas releases from the four vents is ! compiled for preparation of the Semiannual ! Effluent Release Report required by Technical l Specifications 6.9.1.8 and 6.9.1.9 and described ; in NRC Regulatory Guide 1.21. The methods for determining released quantities of radioactivity, dose rates and cumulative doses are as , follows: j O-
- 1. PISSION AND ACTIVATION GAS The radionuclide-specific released radioactivity is determined from sample analyses results ,
collected as described above and average release , flow rates over the period represented by thu ! collected sample. Instantaneous 6ose rates due to noble gases and due to radioiodines, tritium, and particulates are calculated (with computer assistance). '
~
Calculated dose rates are compared to the dose rate limits specified in 3.15.2.1.a (Unit 1) and > I.11.2.1.a (Unit 2) for noble gases; and 3.15.2.1.b (Unit 1) and 3.11.2.1.b (Unit 2) for radiciodine, tritium, and particulates. Dose , ! rate calculation methodology is presented in the ! Plent Hatch ODCM. 1 . l T l O :
.tc.
.. . -- -- -. - -. . . .. -.[
[ Beta and gamma air doses due to noble gases are ; calculated for the location in the unrestricted i area with the potential for the hiahest expasure O
, due to gaseous releases. Air doses are calculated for each release period and cumulative totals are kept for each unit for the current j
i calencht quarter and year. Cumulative air doses ! are compared to the dose limits specified in . Technical Specifications 3.15.2.2 (Unit 1) and ! 3.11.2.2 (Unit 2). Current percent of technical ! specification limits are shown on the printout i for each release period. Air doce calculation i methodology is presented in the Plant Hatch ODCM. l
- 2. RADIOIODINE, 'IBITIUM, AND PARTICULATE RELEASES !
Released quantities of radiolodines are ; d2termined from the weekly samples and release i flow rates for the four release points. Radiotodine concentrations are determined by i ganma spectroscop/. Released quantities of particulates are ! determined from the weekly (filter) samples and ' release flow rates for the four release points. Gama spectroscopy is used to quantify - concentrations of principal gamna emitters. ' ( ( After each calendar quarter the particulate filters from each vent are combined, fused, and ; strontium separation is performed. Since sample ; flows and vent flows are alnost constant over each quarterly period the filters from each vent ' can be dissolved together. Decay corrections are , made back to the middle of the quarterly l collection period. Where significant Sr-89 or i St-90 is not detected, LLD's are calculated. -- Strontium concentrations are input to the t camposite file of the computer to be used in ; releaue, dose rate and individual dose calculations. Tritium sanples are obtained nonthly frm each i' vent by passing the sample stream through a cold trap. The grams of water vapor / cubic foot. gas is l ! measured upstream of the cold trap in order to ! ! alleviate the difficulties in determining water -; vapor collection efficiencies. The tritium ! sanples are analyzed by an independent laboratory i and results are t'arnished in uCi/ml of water. The tritium concentration in water is converted to tritium concentration in air and this value is ! l- inp3t into the composite file of the computer .to ' I be used in release, dose rate, and individual dose calculations. l l
,-v , + . - m, -,,- e--- .- ,,,-. -,e- -,,,-.en-- . . , . , , . -r c.~,---e,-- - _ , - - - - ..-- --,,e- .-,-a w , . ,
j i Dose rates due to radiotodine, tritium, and particulates are calculated for a hypothetical ! child, exposed to the inhalation mthway, at the
/_ location in the unrestricted area where the i
\
potential dose rate is expected to be the ' highest. Dose rates are calculated for each release point, for each release period, and the total dose rate from all four release points are ; conpared to the dose rate limits specified in : Technical Specifications 3.15.2.1.b (Unit 1) or i 3.11.2.1.b (Unit 2). j Individual doses due to radiolodine, tritium, and . partic11ates are calculated for the critical '
> een@ r, which is described in the Plant Hatch t LbN. .~'1"'.6a1 doses are calculated for each !
t elease der d od and cumulative totals are kept for , eaeb I W ror the current calendar quarter and yeat. t umulative individual doe,e are compared ' to the dose limits specified in Technical i Spe.ifications 3.15.2.3 (Unit 1) and 3.11.2.3 i (Unit 2). Current percent of technical i specification limits are shown on the printout J for each release period. !
- 3. CROSS ALPHA RELEASE
- i A The gross alpha release is computed each nonth by i V counting the particulate filters each week for gross alpha activity in a scintillation counter.
i [ The four or five weeks' nunbers are then recorded ; on a data sheet and the activity is sumed at the ! end of the month. This concentration is input to F the composite file of the computer and is used : for release calculations.
- 4. ERROR ESTIMATES i Regulatory Guide 1.21 requires that estimated '
total error in analysis techniques be reported. i
._ These estimates are required for the total l
. fission and activation gas release, total I-131 i release, total particulates with half-lives l greater than 8-day release, and total tritium :
release. ! i h
)
v L l i 26 I
e -
"The total or n.aximum error associated with the ef fluent measurement will include the cumulative f- errors resulting fran the total operation of
( sampling and neasurement. Decause it nay be very difficult to assign error terne for each parameter af feeting the final measurement , detailed statistical evaluation of error are not suggest ed. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in , liquid and caseous effluents and solid waste." ' Estimated errors are based on errors in countinq equipnent calibration, counting statistics, vent flow rates, vent sample flow rates, non-steady release ! rates, chemical yield factors, and sample losses for such itema as charcoal cartridges. (1) Fission and Activation Total Release was calculated from sample analysis results and release point flow rates. l Statistical Error 60% t Counting Equipment Calibration 10% Vent Flow Rates 10% Non-Stead / Release Rates 20% 100s (2) I-131 Release was calculated from each weekly ()T
\s- sample: ,
Statistical Error 60% Counting Equipment Calibration 10 % i Vent Flow Rates 10% i Vent Sample Flow Rates 10 % l Non-Steady Release Rates 10% Losses From Charcoal Cartridge 10% 110% (3) Particulates with half-lives greater than 8 days i release was calculated from sample analysis results and release point flow rates. ! Statistical Error at LLb concentration 60% , Counting Equipment Calibration 10 % ! Vent Flow Rates 10% ', Vent Sample Flow Rates 10 % l Non-Steady Release Rates 10% 100% l , I 1 f \ (- / t 1
(4) Total Tritium Release ma dominated by the i reactor building vent tritium releaser hence, the : larger statistical errors of the off-gas vent and O recombiner building vcsit tritium releaces do not affect the error in the total tritium release: Water Vapor in Suple Stream Determination 20% i Vent Plow Rates 10 % ! Counting Calibration and Statistics 10 % . Non-Steady Release 50% l 90s i 2.3 GASDXE EFFLUENT RELEASE DATA ! Regulatory Guide 1.21 Tables lA,18, and 1C are found r in this report as Tables 2-2a-c, 2-33-c, and 2-4a-c. Data are presented on a guarterly basis as required by . Regulatory Guide 1.21. l To complete Tables 2-2a-c, total release for each of ; the four categories (fission and activation gasest : iodines; particulates; and tritium) was divided by the i number of seconds in the quarter to obtain a release + rate in uCi/second for each category. I However, the applicable Technical Specification limits are not in terms of release rate in uCi/second but in ; h b terrrn of dose rate in mreWyear, as presented in Technical Specifications 3.15.2.1 (Unit 1) and ? 3.11.2.1 (Unit 2) . Noble gases are limited as ; specified in 3.15.2.1.a and 3.11.2.1.a. The other three categories (tritium, radiciodines, and i particulatts) are limited as a group as specified in 3.15. 2.1.b and 3.11. 2.1.b. Further the limits L specified in Technical Specifications 3.15.2.1 and 3.11.2.1 are site limits, not unit limits. Dose rates due to noble gas releases and due to radioiodine, tritium, and particulates are presented in Table 2-5 t alcog with percent of technical specification limits. Gross alpha radioactivity is reported in Tables 2-2a, 2-2b, and 2-2c as curies released in each quarter. - Limits for cumul. tive beta and camma air doses, due to ncble gases, are specified in Technical Specifications 3.15.2.2 (Unit 1) and 3.11.2.2 (Unit 2). These limits are unit limits. Cumulative air doses are presented in Tables 2-6a and 2-6b, along with percent of : technical specification limits. ; q ! O 30-i r
,+-w w w .- -,p -
-..-w-. # 3 ,-~as q.g. m , ,.i .- p- --- c- e..
Limits for cumulative individual doses, due to radioiodine, tritium, and particulates, are specified in Technical Specifications 3.15.2.3 (Unit 1) and O 3.11.2.3 (Unit 2 ) . These limits are also unit limits. Cumulative individual doses are presented in Tables 2-7a and 2-7b, with percent of technical specification limits. 2.4 RADIOIDGICAL IMPACP DUE 70 GAS!DUS RELEASES Dose rates due to noble gis releases were calculated for the site in accordance with Technical Specifications 3/4.15.2.1.a (Unit 1) and 3/4.11.2.1.a (Unit 2). Results are presented in Table 2-5. Dose rates due to radioiodine, tritium, and particulates in gaseous releases were calculated in accordance with Technical Specifications 3/4.15.2.1.b (Unit 1) and 3/4.11.2.1.b (Unit 2). These results are also in Table 2-5. Cumulative air doses due to noble gas releases were calculated for each unit in accordance with Technical Specification 3/4.15.2.2 (Unit 1) and 3/4.11.2.2 (Unit 2). These results are presented in Tables 2-6a and 2-6b. , Cumulative doses to an individual due to radiolodine, _f' \ tritium , and particulates were calculated for each unit in accordance with Technical Specifications 3/4.15.2.3 (Unit 1) and 3/4.11.2.3 (Unit 2). These results are presented in Tables 2-7a and 2-7b. Dose rates and doses were calculated using the methodology presented in the Plant Hatch Offsite Dose calculation Manual. g l l 2 TABLE 2-2a E. I. IIATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 i O GASEOUS EFFLUENTS - SUKMATION OF ALL RELEASES Unit Quarter 1 Quarter 2 Est. Total __________________________________________________EEEoE_!*1__ A. Fission and Activation Gases
- 1. Total Ci 3.16E+01 5.66E+01 1.00E+02 Release
- 2. Average uCi/sec 4.02E+00 7.20E+00 Release Rate For Period
*3. % of Tech %
Spec Limit B. Iodines
- 1. Total Ci 9.77E-04 3.59E-04 1.10E+02 Iodine-131
- 2. Averace Release uCi/sec 1.24E-04 4.56E-05 Rate For Period
*3. % of Tech %
Spec Limit 0 i C. Particulates
- 1. Particulates C1 2.81E-04 2.63E-04 1.00E+02 w:.th half-
; 1;,ves > 8 days
- 2. Average uC1/sec 3.57E-05 3.34E-05 Release Rate For Period
*3. % of Tech %
Spec Limit
- 4. Gross Alpha Ci 2.16E-05 5.74E-07 Radioactivity D. Tritium
- 1. Total Ci 1.88E+00 2.45E+00 9.00E+01
'2. Average Release uCi/sec 2.40E-01 3.12E-01 Rate For Period
- 23. % of Tech %
Spec Limit
- Technical Specification limits are in terms of dose rate (mrem 2-7a,/yr) and dose (mrem). See Tables 2-5, 2-6a, 2-6b, and 2-7b.
-32=
i. J
t TABLE 2-2b E. I. HATCH NUCLEAR PLANT - UNIT 2 -
-C\ SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991
(_) GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES , Unit Quarter 1 Quarter 2 Est. Total l Error (%) i f A. Fis lon and I Act$vation Gases
- 1. Total C1 1.92E+01 1.00E+01 1.00E+02 Release
- 2. Average Release uCi/sec 2.44E+00 1.37E+00 i Rate For :
Period i
*3. % of Tech %
Spec Limit D. Iodines
- 1. Total C1 1.27E-03 5.08E-04 1.10E+02 Iodine-131
- 2. Average Release uci/sec 1.62E-04 6.46E-05 Rate For Period
*3. % of Tech %
Spec Limit C. Particu:.ates PartLculates Ci O 1. WLth half-1Lves > 8 days 1.06E-04 4.83E-05 1.00E+02
- 2. Average Release uCi/sec 1.35E-05 6.14E-06 Rate For Period
*3. % of Tech %
Spec Limit
- 4. Gross Alotus C1 1.06E-05 4.26E-07 Radioactivity 4 D. Tritium 4 1. Total Ci 8.24E+00 3.07E+00 9.00E+01
- 2. Average Release uCi/sec 1.05E+00 3.91E-01 Rate For Period
*3. % of Tech %
Spec Limit
- Technical S farem/grgangecificationlimitsareintermsofdoserate q
dose (mrem). See Tables 2-5, 2-6a, 2-6b, i l l l
- u. . . _ _
i TABLE 2-2c E. I. HATCH NUCLEAR PLANT - SITE O SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 1 Quarter 2 Est. Total ! Error (%) i A. Fission and i Activation ! Gases
- 1. Total Ci 5.08E+01 6., 7 4 E + 01 1.00E+02 Release
- 2. Average Release uCi/sec 6.46E+00 8.57E+00 Rate For Period
*3. % of Tech %
Spec Limit i B. Iodines l
- 1. Total C1 2.25E-03 8.67E-04 1.10E+02 Iodine-131 t
- 2. Average Release-uCi/sec 2.86E-04 1.10E-04 5 i
Rate For ! Period '
*3. % of Tech. %
Spec Limit ( C. Particulates
/'"g 1. Particulates Ci 3.87E-04 3.11E-04 1.00E+02 j WLth half-
\-) 1.ves > 8 days t
- 2. Avbrage Release uCi/sec 4.92E-05 3.96E-05 Rate For i Period }
*3. % of Tech %
S ec Lirit
- 4. G$ossAloha Ci 3.22E-05 1.00E-06 5 Radioactivity D. Tritium '
- 1. Total C1 1.01E+01 5.53E+00 9.00E+01
- 2. Average uC1/sec 1.29E+00 7.03E-01 l Release e Rate For Period !
*3. % of Tech % i Spec Limit
- Technical Specification limits are in terms of dose rate
}mrom/grg and See Tables 2-5, 2-6a, 2-6b, 2-7bdose (mrom).
-7a,
! I L l t 1
-3h-i l +
1 r
i i 9 TABLE 2-3a l E. I. HATCH llUCLEAR PLANT - UllIT 1 : SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE HEPORT 1993 i GASEQUS EFFLUENTS - ELEVATED RELEASES
- j
(_ , Continuous Mode Batch Modo ** - Nuclidos Released Unit Quarter 1 Quartor 2 Quarter 1 Quarter 2 .
- 1. Fission Gases 5 Kr-85m C: 4.27E-01 5.12E-01 Xo-133 C: 0.00E+00 1.52E400 i fo-135m C: 3.92E+00 3.46E+00 !
ho-135 C: 1.75E+00 1.62E+00 Xo-138 C: 6.32E+00 6.64E+00 t Ar-41 C:, 0.00E+00 2.00E-01
- Total For '
Porlod C1 1.24E+01 1.40E+01 e 2.lodines . l I-131 C: 9.06E-04 2.73E-04 ; 1-133 C: 1.36E-03 1.40E-03 1 I-135 C: 1.32E-03 1.96E-03 i
........___. _......................... ..____............... j Tot 1 For . !
Por od Ci 3.58E-03 3.63E-03 _________......_____................__...... ___.............. t
- 3. Particulatos -
Co-60 C: 0.00E+00 7.03E-08 + Sr 89 C: 2.01E-05 0.00E+00 , Sr-90 CL 2.39E-07 0.00E+00 t Cs-137 C: 1.15E-06 6.43E-08 i Ba-140 C: 5.62E-05 4.34E-05 i La-140 C: 9.00E-05 8.23E-05 ' I-131 C:, 1.60E-96 8.90E-07 Total For : Period Ci 1.69E-04 1.27E-04 ; t i i
*Zoroes i this table r nd cate that no ra loactivity wa '
resent a ove detectab..o evols. See Tab o 2-8-for ty ower lim ts of detect:,on for gaseous sample analysos.p cal
**There are no batch mode radioactive gaseous releaso i pathways at Plant natch. l I
[ l ( * (s / : L
+
TABLE 2-3b E. I. HATCli NUCLEAR PLANT - UNIT 2 SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 GASEOUS EFFLUENTS - ELEVATED RELEASES
- Continuous Mode Batch Mode **
Nuclides Beleased Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2
- 1. Fission Gases Kr-85m CL 1.36E-01 3.70E-01 Xe-133 C: 0.00E+00 2.97E-01 Xc-135m C; 2.72E+00 0.00E+00 Xc-135 C: 9.38E-01 2.40E-01 Xo-138 C: 7.78E+00 0.00E+00 Ar-41 Ch 0.00E+00 3.07E-01 Total For Period C1 1.16E+01 1.22E+00 2.lodines I-131 C:. 1.20E-03 5.01E-05 1-133 C: 1.06E-03 2.55E-04 I-135 C: 7.59E-04 3.90E-04 Tot 1 For Per od Ci 3.02E-03 6.94E-04
- 3. Particulates Co-60 Cn 0.00E+00 7.03E-08 Sr-89 C: 1.35E-05 0.00E+00 Sr-90 C: 1.61E-07 0.00E+00 Cs-137 C: 1.15E-06 0.00E+00 Ba-140 C: 2.88E-05 8.70E-06 La-140 C: 4.91E-05 1.61E-05 I-131 C: 8.69E-07 9.26E-08 Tot 1 For Per od Ci 9.37E-05 2.49E-05
- Zeroes in this table indicate that no radioactivity was nresent lower limitsabove detectablefor of detection levels. Sco Table 2-8 for ty gaseous sample analyses.pical
**There are no batch modo radioactive gaseous release pathways at Plant Hatch.
-- .- - - - . - - . ~ . . _ _ _ , . _ _ _ _ _ _ _ _ . , , , . _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ , _
4 TAllLE 2-3c E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 GASEOUS EFFLUENTS - ELEVATED RELEASES
- Continuous Mode Datch Mode **
Nucliden Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2
- 1. Fission Gases Kr-85m C: 5.63E-01 8.82E-01 Xo-133 C: 0.00E+00 1.82E+00 Xe-135m C: 6.64E+00 3.46E+00 Xe-135 C 2.69E+00 1.86E+00 Xe-138 C: 1. 4 ?. E+ 01 6.64E+00 Ar-41 C;. 0.00E+00 5.87E-01 Total For Period C1 2.40E+01 1.53E+01
- 2. Iodines I-131 C: 2.11E-03 3.23E-04 I-133 C 2.42E-03 1.65E-03 I-135
.......................__-03 C: 2.08E-03 2.35E Tot 1 For Per od Ci 6.60E-03 4.32E-03
(
- 3. Particulates Co-60 C:, 0.00E+00 1.41E-07 Sr-89 C: - 3.36E-05 0.00E+00 Sr-90 C:, 4.00E-07 0.00E+00 Cs-137 C: 2.30E-06 6.43E-08 Ba"140 C: 8.50E-05 5.21E-05 La-140 C: 1.39E-04 9.83E-05
........ ___...--....... _-06 1-131 C: 2.47E 9.82E-07 Total For Period Ci 2.63E-04 1.52E-04
- Zeroes'i this table ..ndicate that no radioactivity was present a ove detectab:,e levels. See Table 2-8 for ty lower lim ts of detect:.on for gaseous sample analyses.pical
**There are no batch mode radioactive gaseous release pathways at Plant Hatch, l.
l f~ t
l TABLE 2-4a ; E. I. HATCH NUCLEAR PLANT - UNIT 1 , SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPnRT 1991 . GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES * '
?
Continuous Mode Batch Mode ** 1
'p Nuclides Reicased Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 i t
- 1. Fission Gases !
Kr-85m C; 0.00E+00 9.35E-03 i Kr-85 C 0.00E+C0 1.23E+01 6 Xe-133 C: 1.92E+01 2.71E+01 Xo-135 C:. 2.50E-02 3.17E+00 i Ar-41 C1 0.00E+00 7.76E-03 Tot 1 For Per od C1 1.92E&O1 4.26E+01 i
- 2. Iodines 1-131 C:, 7.12E-05 8.60E-05 1-133 C: 4.23E-04 6.18E-04 .
1-135 Ca 0.00E+00 0.00E+00 ', Total for Period Ci 4.94E-04 7.04E-04 ,
....................._........-_..............--._ .......... t I
- 3. Particulates (D)
Cr-51 C: 4.50E-06 0.00E+00 Mn-54 C: 2.66E-05 2.34E-06 ! Co-58 C: 1.42E-06 4.89E-06 Co-60 C: 1.91E-05 2.33E-05 Zn-65 C: 3.28E-05 1.02E-04 - Sr-89 C: 3.97E-06 0.00E+00 ' Mo-99 C: 6.15E-06 0.00E+00 Cs-137 C: 9.88E-07 0.00E+00 : Ba-140 C: 7.32E-06 0.00E+00 f La-140 C: 4.57E-06 3.67"-06 : I-131 C: 4.08E-06 0.00c+00 r
.... ---............. __-.........___ _. .--__--............. t
' Tota For
- Peri d C1 1.12E-04 1.36E-04 i
- Zeroes i this tab.o indicate that no radioactivity was l present a ove detectable levels. See Table 2-8 for ty !
lower lim ts of detection for gaseous sample analyses.pical !
**There are no batch mode radioactive gaseous release pathways at Plant Hatch. .
i I i
~s L
J
TABLE 2-4b E. I. HATCH NUCLEAR PLANT - UNIT 2 i SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 i ( GASEOUS EFFLUENTS - GROUMD-LEVEL RELEASES * , i Continuous Mode Batch Mode ** ! Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 i j
- 1. Pission Gases !
..... .......__... ___...__........................___....... r e-133 C: 0.00E+00 7.60E-01 l e 135 C; 7.62E+00 8.80E+00
~
Total For Period Ci 7.62E+00 9.56E+00 l ______............_______....__________.______...........___. 3 2.lodines l I-131 C: 6.89E-05 4.58E-04 . I-133 C; 3.50E-04 4.99E-03 i I-135 C: 0.00E+00 8.34E-03 ! __.. ...._..._____........................___................. t Tot 1 For , Ci Per od 4.19E-04 1.38E-02
- 3. Particulates l Co-60 C: 0.00E+00 1.23E-06 I
[s ( Zn-65 Sr-89 C: C: 0.00E+00 1.02E-05 1.25E-06 0.00E+00 , Cs-137 C: 8.10E-07 0.00E+00 t Ba-140 C: 8.35E-07 1.10E-05 ! La-140 Ch 0.00E+00 7.89E-06 - I 131 C;. 5.01E-07 ___ _____ .--. ......... ........___-06 1.94E Tot 1 For i Per od C1 1.23E 05 2.33E-05 A I
- Zeroes i this table .ndncate that no radioactivity was :
present a ove detectab: e :,evels. See Table 2-8 for ty T lower-lim ts of detect:.on for gaseous sample analyses,pical i
**There are no batch mode radioactive gaseous release pathways'at Plant Hatch. I
?
r i i 5
/"' !
l ( I l
TABLE 2-4c t E. I. HATCH NUCLEAR PLANT - SITE l r' SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1991 : ( GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES * ! Continuous Mode Batch Mode ** Nuclides ; Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 l
- 1. Fission Gases
...........__.............................................___ 3 Kr-85m C: 0.00E+00 9.35E-03 !
Kr-85 C: 0.00E+00 1.23E+01 Xe-133 C: 1.92E+01 2.79E+01 , Xe-135 C: 7.64E+00 1.20E+01 Ar-41 C; 0.00E+00 7.76E-03 Tota For ! Peri d Ci 2.68E+01 5.22EF01 ! 7 i 2.lodines [ I-131 C: 1.40E-04 5.44E-04 , I-133 C: 7.73E-04 5.61E-03 ! 1-135 C:. 0.00E+00 8.34E-03 !
... ........-_.....__.___...............--______ _-_........ t Tot 1 For !'
Fer od Ci 9.13E-04 1.45E-02
- f I
.f~ 3. Particulates y' ,
Cr-51 C: , 4.50E-06 0.00E+00 i Mn-54 C: 2.66E-05 2.34E-06 ; Co-58 C: 1.42E-06 4.89E-06 " Co-60 C: 1.91E-C5 3.45E-05 Zn-65 C: 3.28E-05 1.03E-04 Sr-89 C: 1.42E-05 0.00E+00 'i Mo-99 C: 6.15E-06 0.00E+00 Cs-137 C: 1.80E-06 0.00E+00 Ba-140 C: 8.16E-06 1.10E-05 La-140 C: 4.57E-06 1.16E-05 I-131 C: 4.58E-06 1.94E 06 r
' Total For .
Ci Period....__...__.............__-04 1.24E
......__.._-041.60E i
I
- Zeroes in this table indicate that no radioactivity was i nresent above detectable levels. See Table 2-8 for ty lower limits of detection for gaseous sample analyses.pical .
I **There are no batch mode radioactive gaseous release [ l pathways at Plant Hatch. ; i
.LO. i P
I b t l ? I t
Table 2-5 O E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 GASEOUS EFFLUENTS - DOSE RATES Dose Rates Due to Noble Gases Organ Tech Unit Quarter 1 % of Quarter 2 % of Cpec Tech Tech Limit Spec Speg Limit L1mit TBo y 500 mrem / r 2.21E-02 4.42E-03 3.28E-02 6.56E-03 Ski 3000
. .../..r mrem 4.04E-02 1.61E-03 9.02E-02 3.01E-03 Dose Rates Due to Radiolodine, Tritium, and Particulates Organ Tech Unit Quarter 1 % of Quarter 2 % of Spec Tech Tech '
L1mit Spec Spec Limit Limit Bone 1500 mrem r 3.48E-05 2.32E-06 1.33E-04 8.84E-06 Liver 1500 mrem r 1.21E-02 8.04E-04 6.09E-03 4.06E-04 TBody 1500 mrom r 1.20E-02 8.03E-04 6.00E-03 4.00E-04
- Thyroid 1500 mrem r 1.78E-02 1.19E-03 3.84E-02 2.56E-03 xianey 1500 mrem r 1.21E-02 8.05E-04 6.18E-03 4.12E-04 Lung 1500 mrom r 1.23E-02 8.20E-04 6.25E-03 4.17E-04 O GILLI 1500. . .
mrem r 1.20E-02 8.03E-04 5.97E-03 3.98E-04 4
)
s i N bl- f L i !
f t TABLE 2-6a ) E. I. HATCH IJUCLEAR PLA11T - Ul1IT 1 t SEMIAllNUAL RADIDACTIVE EFFLUEllT RELEASE REPORT 1991 r AIR DOSES DUE TO 110BLE GAS DELEASES I i t
^
Cumulative Doses per Quarter T pe Tech Unit Quarter 1 % of Quarter 2 % of . o Tech Tech t Radi- Sna"lt Llm Spec Spec ation Limit L1mit Gamma 5.0 mrad 1.98E-03 3.96E-02 4.42E-03 8.83E-02 i Beta 10.0 mrad 5.41E-03 5.41E-02 1.60E-02 1.60E-01 !
}-
1 Cumulative-Doses-This Year T pe Tech Unit Quarters 4 of I o Spac 1 f: ?, Tech ! Radi- Limit Spec t ation Limit !
.. . . . . . .. . . . ... . . __.. . . __ .. t Gamma 10.0 mrad 6.402-u) 6.40E-02 {
Beta 20.0 mrad 2.262-0$ 1.07E-01 . (
'f !
t i I I i , s
?
?
.I t
3 I i - 12 iO , i t I
?
r t i
TABLE 2-6b i E. I. IIATCH llUCLEAR PLAllT - Uli1T 2 SEMIAll!(UAL RADIOACTIVE EFFLUE!1T RELEASE REPORT 1991
- AIR DOSES DUE TO 110BLE GAS RELEASES Cumulative
.........-u-. M,ast .Y.o.r Quartet ..___........________ ..... ...
i Type q(A , Quartetr 1 % of Quarter 2 % of j of 1.j p . ' $ti- Tech Tech t Radi- .py Spec Spec i ation Limit Limit i Gamma 5.0 mrad 4.J7E-03 8.13E-02 4.57E-03 9.13E-02 Beta 10.0 mrad 5.03E-03 5.03E-02 5.96E-03 5.96E ; i s Cumulative Doses This Year TV,pe Tech Unit Quarters % of f 01 Speg 1&2 Tech ! Radi- Limit Spec ', ation Limit 6 Gamma 10.0 mrad 8.63E-03 8.63E-02 : Beta 20.0 mrad 1.10E-02 5.49E _ 02 , t hV
- i. i, i
.?
i i t l - . . k3-L. if l l I'
-+ _= t. < . - , . . . - -- w
.. f I
TABLE 2-7a ! O E. I. HATCH NUCLEAR PLANT - Unit 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 INDIVIDUAL DOSES DUE TO RADIO'ODINE TRITIUM, AND PARTICULATES IN GASEOUS REL$ASES ; i
?
f 1 Cumulative Dosos per Quarter ! l Organ Tech Unit Quarter 1 % of Quarter 2 % of l Spec Tech Tech i Limit Spec Spec Limit L1mit ne 7.5 arem 2.73E-04 3.64E-03 2.20r-04 2.93E-03 ! B$ver L 7.5 mrom 1.15E-03 1.54E-02 1.27E-03 1.69E-02 . TBody 7.5 mrem 1.14E-03 1.52E-02 1.24E-03 1.65E-02 l 7.5 mrem 4.52E-03 6.02E-02 3.64E-03 4.85E-02 Thbroid Ki ney 7.5 mrom 1.14E-03 1.52E-02 1.24E-03 1.66E-02
' Lung 7.5 mrem 1.13E-03 1.51E-02 1.21E-03 1.61E-02 GILLI 7.6 mrem 1.13E-03 1.51E 1.21E-03 1.62E-02
.__.... .......___.._______...._______-02 ....___.............___
Cumulative Doses This Year Organ Tech Unit Quarters % of Spec 1 &2 Tech-Limit Spec Limit Bone 15.0 mrem 4.92E-04. 3.20E-03 Liver 15.0 mrem 2.42E 1.61E-02 ' TBody 15.0 mrem 2.38E-03 1.59E-02 Thyroid 15.0 mrem 8.15E-03 5.44E-02 Kidney 15.0 mrem 2.38E-03. 1.59E-02 Lung 15.0 mrem 2.34E-03 1.56E-02 GILLI 15.0 mrem 2.35E 03 1.56E 02 4 4 e l-L 1 V u_
TABLE 2-7b E. I. HATCH NUCLEAR PLANT - Unit 2 . SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 INDIVIDUAL DOSES DUE TO RADIOIODINE TRITIUM, AND PARTICULATES IN GASEOUS RELkASES E95ula!!!!.92828.ESE.9"*E!!E.................................. ' organ Tech Unit Quarter 1 % of Quarter 2 % of Spec Tech Toch Limit Sneg Spec Limit Limit Bone 7.5 mrem 1.70E-04 2.27E-03 6.04E-05 8.05E-04 Liver 7.5 r. rem 4.27E-03 5.70E-02 1.63E-03 2.17E-02 TBody 7.5 mrem 4.27E-03 5.69E-02 1.61E-03 2.15E-02 Thyroid 7.5 mrem 8.19E-03 1.09E-01 1.25E-02 1.67E-01 Kianey 7.5 mrem 4.28E-03 5.70E-02 1.66E-03 2.21E-02 Lung 7.5 mrem 4.26E-03 5.68E-02 1.59E-03 2.12E-02 GILLI 7.5 mrem 4.26E-03 5.68E-02 1.60E-03 2.13E-02 E2591a!!!!.9eSSSIh{sfga{,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, Organ Tech Unit Quarters % of I Sg 1 &2 Tech
.S$$t Bone 15.0 mrem 2".31E-04 1.54E-03 v Liver 15.0 mrem 5.90E-03 3.94E-02 TBody 15.0 mrem 5.88E-03 3.92E-02 Thyroid 15.0 mrem 2.07E-02 1.38E-01 Kianey 15.0 mren 5.93E-03 3.96E-02 Lung 15.0 mrem 5.85E-03 3.90E-02 GILLI 15.0 mrem 5.86E-03 3.91E-02 t
b i l 45-1 I s_/ . .
t l TABLE 2-8 ! LOWm LIMITS OP DETECTIOtt - GASDOUS SAMPLE AtMLYSES l The values in this table represcnt apriori lower limits of : detection (LtD) which are typically achieved in laboratory , ana ysec of gaseous radsaste sanples. ' l RADIO!UCLIDE LLD tNtTS I Kr-87 1.31E-07 uCUm1 i Kr-88 2.10E-07 ' Xe-133 1.62E-07 i Xe 133m 6. 07E-0 8 i Xe-135 5.77E-08 : Xe-138 2.8SE-06 3 i I -131 4.37E-14 ! I-133 6.16E-13 i Mn-54 2.78E-14 t Fe-59 4.6 2E- 14 i Co-58 2.46E-14 : Co-60 2.8BE-14 ! Zn-65 7.51E-14 . Mo-99 6.02E- 13 i Ca-134 3.64E-14 , l Cs-137 2.88E-14 ! Ce-141 4.94E-14 i O Ce-144 Sr-89
-St-90 2.02E-13 1.00E-11
- 1. 00E-11 H-3 1.00E-06 !
i i t P 1 t 1 i O l i [ L6 ! 1
i
- 3. SOLID WAST.E l
3.1 REWLAIORY REQUIREMDlIS fi (q 1 The Tuchnical Specifications presented in this ! section are for Unit 1. Requirements for Unit ' ' are the came as for Unit 1; however, the Technical Specification nurbers tre not the same. l i TEONICAL SIECIFICATIOfS j 3.15.3.1 The solid radsaste system shall be used in ' accord'ince with the IHOCESS 00trIROL PROCRAM to provide - for the SOLIDIFICATION of wet soU d wastes and for the SOLIDIFICATION and psekaging of other radioactive I Wastes, as required, to ensure the meeting of the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shinnent of radioactive wastes fram the site. ? 3 6.9.1.9 states in part: The Radioactive Effluent Release Report shall include l the following informtion for each type of solid waste ' shipped offsite during the report periods i
- a. Container volume ,
- b. Total curie quantity (specify whether determined {
by masurement or estimte) *
- c. Principal radionuclides (specify whether "
determined by ncasurement or estimte)
- d. Type of waste, e.g., spent resin, compacted dry waste, evaporator bottoms
- e. Type of container, e.g., IEA, type A,. type B, large quantity !
- f. Solidification agent, e.g., cement. ~
3.2 SOLID WASTE DATA Regulatory guide 1.21 Table 3 is found in this report i as Table 3-la, and .3-lb. 5 ( f 5 l
'V .
l t k7 ! i
i TFFLUEt(T AND WASTE DISKISAL SEMIANNUAL REP 0irr 1991 January 1,1991 - June 30,1991 p SOLID WARTL AND IRRADI ATED FDEL SHIPMEt(TS tj ICR UNITS I AND II TABLE 3-1A A. SOLID WASTE SHIPPED Off SITE F0k HURI AL OR DISPOSAL (Not irradiated fuel) l 1. Type of waste l UNIT l 6 month lEst. Totall i l ,, I l period l ERRORt_l l a. Spent resins, filter sludges, evaporator m3 1.93 G0d ,, l ; l bottoms, etc. I Ci 3 39E+0d 1.0 Egg],,l
- l b. Ory compressible waste, contaminated l m3 l 2 .27 EA0j ,__l Cl l 1 3 0 D 0d 1.0 l_ equip. etc. I LOl l
- c. Irradiated components, control rods, l. mI l 9 17 D 0d l E l
_ C4 1 4,.3 5 p 0 d 2 .0 hl ; l d. Control Rod Drive ritters l m* 0 .0J h 0(t _l l l Cl 0 ,00 D gd E _] !
- e. Other (describe) k'et and Oily Trach l _,[ l 3 .73 E 011 _
l l equip. etc, (Liquid 011) l CJ, l 2.69 Doll 2.0 E4 01 l .
- 2. Estimate of major nuclide comoosition (by type of waste) !
~ ~
l, ISOTOPE l PERCENT l CURI,ES l i l a. Zn-65 l 3.30E+01 l 1.12E+02 j
- l Ee-55 ,,_,
l 1.95E+01 1 6.61E+01 l l [ CO 60 l 2.19 5'+ 01 1 7.19E+ 01. _l b [$ Cs_-137 1 3. 99E+ OQ,,_,,,[ 1.15E+ 01 l l Other l 2. 2 h E+ 01 1 7.59E+01 l ! l b. g 65 1. 160E+0i 1 196E 01 ,_ l , l _ Fe-55 l 4 3 E+00 1 5.07E 02__.l , l Co 60 _l L16E+01 l t h8E 01 l l l 9.26E 02 i l Cn 137 l 8.42E+00 l Other 1.9hE+01 2.13E-01 l l c. Zn 65 5.00E+00 ,'L O 1E+ 01 l i l Fe-55. l .4.26E+01 l 2.58E+02 l l 00-60 I h.00E+01 1 2. 4 2Et,92,_,,,1 l Ce 1'47 1 3. $ E 02 l 2.23E-01 l l Other i 1.2hE401 1 7.50E+01 l l d. 2n 65 _ , , _ l 0.00E+00 0.00E+00 l l Fe.99 _ l 0.00P+00 i
,Q,,00E+00 l cn 60 l ._ l O_00T+00 1 0. 00It 00... ... l l c. 1 17 J, 0_00r+00 1 0 QQEt.QQ_,,_l l l 1 n% i n_nnv40n I n_nnr+nn ,1 l l e. m 6s i t ssr401 1 1_ptr+00 l
( l_ Fe 5E l t 76F+00 l 1.01E 01 1 l Oc-10 1 2.ShE+01 1 6.8hE.01 l , j l C -137 1 6.79I100 1 1.831_QL,,1 , l _.Qira.r i 1. 86E4 01 l S.01F-01 l >
- 3. Solid Waste Disposition hugbg _of Sht)ments Mode of 7ransportation Destination s - 22 Tractor Trailer Barnwell, SC
- 8. IRRADIATED FUEL SHIFM(51b (Oisposition) r Number of Shipments t%fe of Transportation Destinattorg N/A , ?i/A w/A i 1
h&- ,
)J .
EFFLUEttr AND WASTE DISIOSAL SEMIANff)AL REIORT 1991 January 1, 1991 - June 30, 1991 SOLID WASTE AND IRRADIATED FUEL SHIPMEffrS O O FCH UNITS I AND II TABLE 3-1B l TYPt l Cuelt i Pe14CIPLE l SValaL INUNetIor VOLUME or l TYPE l Sot!DirtCatl6El or igunw111Y /t wuctiots / l cxw1 Arwin Icxwtalkt es tacw cowrnikte isnientNT /l act wt I I surpato Iggelc rtti ut niconta1NLe 1 I wattL lociten1 Epi otte.matto= 1 otscerPTisw i lDevatere1l98.6 I:'n.6 ' 5, Co-60 I High l1 l 132.L l l Resins IMeasured l Cs.137, Fe-Mi I ntegrity l l lTYPEB lN/A l CACE g i
. I l l Container I i 1 10-lL2 l 1 I measured l---..---4-..-...+.---....---y.-----------y....----g.-----------.g------n---------.-;
1 I l l l l g t 1 i l i I i i l lDevatered i s35.83 lZN 65,Co 60 l High l 30 l 202.1 l TYPE A ll ; I Resins (Measured ICs-137, Ze-551 Integrity l l l CACK l N/A i l i i l Ccntainer l
..-...--..----.-----.......--.i-----........--{
measured { {14.210 .- - l l Torus I 7.1 I I High I3 1 202.1 1 TYPE A { l b ileanup l Measured ln.65,Co.60Cs-137,Fe-55l Integrity Container l 1 N/A ! k )11ters l l g l l measured l l l l--.--...p..----.4..........-p-..----.-----t.-...---t--------------t-------1----~~----I lCAEK IL-210 l l I I I I I l 1 i lRscire. l 98.3 lZn 65,Fe-55 l Carbon l2 g 95.7 l TYPE B lI l Pump IMeasured10o 60 l Steel l l l CASK l Concrete ; l {Limr l l l 8-120 1 1 l Inter'nalcl.----.] measured lZn-65,Co.60 lStrong
. - - - . . . -- - - L . . . - - -- { . - - - . .- - . . f -- - . J -- - . . -- . .
lDAV 11.10 i 87 l 92 i Strong i ! l(DRY) lEstimatefCs-137,Fe-55lT1ht 6 l l Tight N/A I ! l Cont. l l g Boxes ; ; l((ACTIVE)l I UASTE) l
- l. Estimated lB-25 I l 1925 l i 1-.-....!...--.....t..-....--.--l-....----------l--------l---.----------4.-.-----4.--------.--l I l .I I I I I I lCRD Velo-l507 12n-65,Co 60 lHigh 11 1 132.4 1 TYPE B lI 1 lcity i l l l CASK l N/A 1 l Limiters lEstimatedCs-137,Fe-55lIntegrity l Estimated j Container l l l 10-1L2 i !
l........7-.--...t----------~-T'---~~~~~~~~~~I-~~~~~~~T~~~~~~~~~~~~~~~~~~~~7 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ' I I I l Strong I l I SEO Zn Unknown l to l2.69Estimatches.65,Co.60-137Fe-55l Estima,ted Tight li Unknovn(Variesh lTightStronglI Container (Varies) N/A l lBarnvall ! I i i i Cont, i l SEG = Scientific Ecology Group O L 9..}}