View source for ELV-03979, Semiannual Radioactive Effluent Release Rept for Vogtle Electric Generating Plant,920131 Through 920630

{{Adams
| number = ML20114C109
| issue date = 06/30/1992
| title = Semiannual Radioactive Effluent Release Rept for Vogtle Electric Generating Plant,920131 Through 920630
| author name = Mccoy C
| author affiliation = GEORGIA POWER CO.
| addressee name = 
| addressee affiliation = 
| docket = 05000424, 05000425
| license number = 
| contact person = 
| document report number = ELV-03979, ELV-3979, NUDOCS 9209010184
| document type = ENVIRONMENTAL MONITORING REPORTS(&amp;RADIOLOGICAL)-PERIODIC, TEXT-ENVIRONMENTAL REPORTS
| page count = 57
}}

=Text=
{{#Wiki_filter:..                    .        . ..                 .         . . - .
h-            4                                                                                                                    5
       -s,                Georo,a Power Comrwir 401nvemess Cenw Pa%st
                         . PeyJ 0%e Boi 1295 P.wma.gham, A!abama 35201
  ^
Teephore 7 4 877-7122 i     <
  -r
: c. K.' McCoy .                                                            CCOfQl(j' POWCf
                         -. wce Pwident, Otiey Vog'ic Ptcycl                                                           I?V ' Adher?' t** N 5 istem ELV-03979 002186 w
Docket Nos.           50-424 50-425
                     .U. S.- Nuclear Regulatory Commission-ATTN:       Document C'.ntrol Desk Washington, D. C. 20555.
Gentlemen:
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT In' accordance with requirements of:Vogtle Electric Generating Plant Unit I and Unit 2 Technical Specifications, Section 6.8.1.4, please find enclosed the Semiannual' Radioactive Effluent Release Report for January 1,1992 through June ~30,fl992.         Six copies are provided for your use. Two copies of this report are being provided to the-NRC Region II office.
Sincerely, 0 .$1'q C. K. McCoy
.                    i CKM/JLLhmb -
Enclosure N                    :xc: 'Gecraia Power Company T                               Mr_. W. B. F spman-F                             --Mr. M.' Sheibani.
                              -Mr.-M..C.-Nichols-NORMS-U. S. Nuclear' Reaulatory Commission y
Mr. S. D.--Ebneter, Regional Administrator (w/2 encl.)
   '~
                               -Mr. D. S. Hood, Licensing Project Manager, NRR-Mr. B. R. Bonser, . Senior. Resident Inspector, Vogtle State of Gerraia-Mr. J. L.-Setser, DNR
                               " American ' Nuclear Insurers
                              'Mr.;L.-Cross
          ^
                -9209010f-]      e4 920630 EPDR' ADOCK 05000424 7[
L
 ,?'-           : R-                          PDR a           ,                                          _                                                     _

[f l'
l l
l i
l GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 NRC DOCKET NOS,    50-424 AND 50-425 FACILITY OPERATING LICENSE NOS. NPF-68 AND NPF-81 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT POR JANUARY 1, 1992 TO JUNE 30, 1992 i
         ,A l
l 1
                                                                    ?
e                                                                 .J

t VOGTLE ELECTRIC GENERATING PLANT SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES SECTION                                         TITLE                                       PAGE 1.0                          Liquid E*fluents                                               7 1.1                         Regulatory Limits / Technical Specifications                   7 1.1.1                       Concentration Limits                                           7 ,
1.1.2                      Dose Limits                                                    7 1.2                        Maximum Permissible Concentrations                             7 1.3                       Measurements and Approximations of Total                       8 Radioactivity 1.4                      Liquid Effluent Release Data                                  10 1.4.1                    Tables                                                        10 1.4.2                   Total Error Measurement                                       10 1.5                      Radiological Impact on Man Due to Liquid                     11   .s Release                                    -
1.6                     Abnormal Releases                                            11 1.7                    River Flow                                                   11 2
S

u VOGTLE ELECTRIC GENERATING PLANT SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES SECTION                                                                     TITLE                                                                PAGE 2.0                           Gaseous Effluents                                                                                                   23 2.1                            Regulatory Limits / Technical Specifications                                                                       23   _.
2.1.1                           Dose Rate Limit                                                                                                   23 2.1.2                           Air Dcse Due to Noble Gas                                                                                         23 2.1.3                            Dose to Any Organ                                                                                                23 2.1.4                            Total Fuel Cycle Dose Commitment -(40CFR190)                                                                     24 2.2                              Release Points of Gaseous Effluents                                                                               24 2.3                               Sample Collection and Analysis                                                                                   24 2.4                              Determination of Total Quantities of                                                                             25 Radioactivity, Dose Rates and Cumulative Doses 2.4.1                             Fission and Activation Gas                                                                                      25     .
2.4.2                              Radiciodine, Tritium and Particulate                                                                           26 Releases 2.4.3                               Gross Alpha Release                                                                                           27 2.5                                 Gaseous Effluent Release Data                                                                                 27 2.5.1                               Methodology                                                                                                    27 2.5.2                                Gaseous Batch Data                                                                                            29 3

            .   .   .-    .. -                                           . . - - - .   =-   .   .. - - . _       -     . -
VOGTLE ELECTRIC GENERATING PLANT SEMIANNUAL REPORT
: PIANT - RADIOACTIVE EFFLUENT RELEASES SECTION                                    TITLE                                              PAGE 2.6               Radiological Impact Due to Gaseous Releases                  -
29-           !
3.0               Solid Waste                                                                   50 3.1               Regulatory Limits / Technical Specifications                                  50 3.1.1             Use of Solid Radioactive Waste System                                         50 3.1.2             Reporting Requirements                                                        50 3.1.3             Process control Program (PCP)-                                                50 3.2               Solid Waste data                                                             .51 4.0               Changes to the Vogtle Electric                                                51 Generating Plant ODCM 4.1               Changes in the Radiological Environmental                                     52 Monitoring Program 5.0               Doses to Members of the Public Inside The                                     52' Site Boundary 6.0               Major Changes to the Liquid, Gaseous                                         57 and: Solid Radwaste Treatment Systems 7.0               Meteorology                                                                  57 8.0                Inoperable Liquid or Gaseous Effluent                                       57 Monitoring Instrumentation t .-
              .9. 0              Tanks Exceeding Curie Content Limits                                         58 l
l.
L l
L
{-
4 l

r t        ..
VOGTLE ELECTRIC GENERATING PLANT SEMIANNUAL REPORT RADIOACTIVE EFFLUENT RELEASE REPORT l.
TABLE         LIST OF TABLE                            PAGE 1-2a    Liquid Effluents - Summation of All Releases       12 Unit 1 1-2b    Liquid Effluents - Summation of All Releases       13 Unit 2 1-2c    Li4; aid Effluents - Summation of All Releases     14 Site 1-3a    Liquid Effluent, - Unit 1                          15 1-3b    Liquid Effluents - Unit 2                          16 1-3c    Liquid Effluents - Site                            17 1-4a     Individuals Doses Due to Liquid Releases        -18 Unit 1 1-4b     Individuals Doses Due to Liquid Releases          19 Unit 2 1-3'    Lower Limits Of Detection.- Liquid Sample          20 Analysis-
            '1-6a    Batch Release Survey-Summary of \ll Releases       21 Unit 1 6b-   Batch-Release Summary of All Releases              22
                     -Unit 2 a
5
     - u        .. _              _     - _  _ -                      -

4 TABLE           LIST OF TABLES                        PAGE 2-2a    -Airborne Effluents - Summation of All         30 Releases - Unit 1                                  ,
2-2b-    Airborne Ef fluents -- Summation of All       31 Releases - Unit 2 2-2c    Airborne Effluents - Summation of All         32 Releases - Site 2-3a    Gaseous L~fluents - Mixed Mode Releases       33 Unit 1 3b    Gaseous Effluents - Mixed Mode Releases       35 Unit 2 2-3c    Gaseous Effluents - Mixed Mode Releases        37 Site 2-4a    Gaseous Effluents - Ground Level Release       39 Unit 1                                                '
                    '2-4b    Gaseous Effluents - Ground Level Release       41       '
Unit 2 2-4c    Gaseous Effluents - Ground Level Release       43 Site 2-6a    Air Doses.Due to Noble Gases    - Unit 1      45 2-6b    Air Doses Due to Noble Gases    - Unit 2      46 1
2-7a    Individual Doses Due to Radiciodine,          47 Tritium, and Particulates in Gaseous Releases - Unit 1 2-7b)   Individual ~ Doses Due to Radiciodine,         48 Tritium, and Particulates in Gaseous Releases - Unit 2 2    Lower Limits of Detection-- Gaseous Sample     49 Analyses 1     Solid-Waste and Irradiated Fuel Shipments      54 5-1     Basic Data Assumed in Dose Assessments to      56
                             -Members of the Public 6

1.0                   Liquid Effluents 1.1                    Regulatory Limits 1.1.1                    Concentration Limits The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR Part                                                                           20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases,                                                                         the concentration shall be limited to 2.0E-4 microcuries/ml total activity.
1.1.2                    Dose Limits                                                                                                                  _
The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS shall be limited:
: a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and
: b. During any calendar year to less than or equal to 3                                                                     #
mrems to the whole body and to less than or equal to 10 mrems to any organ.
                                                                                                                                                                                             /
1.2                      Maximum Permissible Concentration (MPC)
MPC values used in determining allowable liquid radwaste release rates and concentrations for principal gamma emitters, I-131, tritium, Sr-89, Sr-90, and Fe-55 are taken from 10 CFR Part 20, Appendix B, Table II, Column                                                                       -
2.
For   dissolved or entrained noble gasen in liquid radwaste, the MPC is 2E-04 uCi/ml total activity.
For gross alpha in liquid radwaste, the MPC is obtained from 10 CFR Part 20, Appendix B, Note 2.d as 3.0E-08 uCi/ml.                                                                                                                         <
Further, for all the above radionuclides or categories of radioactivity, the overall MPC fraction is determined in accordance with 10 CFR Part 20, Appendix B, Note 1.
The method whereby the MPC fraction is used to determine release rates and liquid radwaste effluent radiation monitor setpoints is described in Subsection 1.3 of this report.
7

e 1.3         Measurements and Approximations of Total Radioactivity Prior tL release _of any tank containing liquid radwaste, and following the required recirculations, samples are collected- and analyzed in accordance with Technical
                                    -Specification Taole 4.11-1                A sample from each tank-planned for release is analyzed for principal gamma 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 radwaste sample analyses are performed as follows; L
l l
_ MEASUREMENT                         FREQUENCY                                      METi!OD           1
: 1. Gamma Isotopic                         Each Batch                     Gamma Spectroscopy with computerized data-reduction
: 2. Dissolved or entrained                Each Batch                  Gamma Spectroscopy noble gases                                                         with computerized data reduction
: 3. Tritium                                Monthly                         Distillation and Composite                 liquid scintillation counting
: 4. Gross Alpha                            Monthly                Gas flow proportional Composite                             counting
: 5. Sr-89 & Sr-90                          Quarterly               Chemical separation Composite                    and gas flow proportional or scintillation counting
: 6. Fe-55                                Quarterly              Chemical separation Composite      and liquid scintillation counting 7
Gamma isotopic measurements are performed in-house in the radiochemistry lab using germanium spectrometry.                                      This consists of four high purity germanium detectors with resolution of 1.80 kev or lower.                          The detectors are shielded by four inches of ' lead,                      - A liquid radwaste sample is typically counted for . -2000-4000 seconds.                                    A peak search of the resulting_ gamma ray spectrum is
: j.                                   performed by the computer system. Energy and net count data of lall significant peaks are determined, and a                                           i quantitative reduction or MDA calculation is performed.
The procedure ensures that .the LLD's are met for the nuclides specified in Table Notation 3 of Technical Specification Table 4,11-1: Mn-54, Fe-59, Co-58, Co-60, I -

Zn-65, Mo-99, Cs-134, Cs-137. Cc-141 and Ce-144.                                                                                                          The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio, and MDA calculations, are made based on the counts at                                                                                                             the location on the spectrum where the peak for that radionuclide would be located, if present.
Tritiun. Gross Alpha, Sr-89, Sr-90 and Fe-55 are, in some cases, acalyzed offsite.
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, groes alpha, Sr-89, Sr-90 and Fe-55 are used along with the corresponding MPC values to datermine a MPC fraction for the tank planned for release.                                                This MPC fraction is then used,                                                           with appropriate safety factors, along with the minimum e,sured                                               dilution stream flow tu calculate maximum permissible release rate and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of Technical Specification 3.11.1.1 are not exceeded.
A monitor reading in excess of the calculated setpoint results in an automatic termination of the liquid radwaste discharge.                                                                                             Liquid effluent discharge is also automatically terminated if the dilution stream flow rate falls below the minimum assured dilution flow rate used in the' setpoint calculations and established as a satpoint on the dilution stream flow monitor.
Radionuclide concentrations, safety factors, dilution stream flow rate, and liquid effluent radiation monitor calibrations are entered into the computer and a pre-release printout is generated.                                                                                             If the release is not permissible, appropriate warnings will be included on the computer screen.                                                                        If the release is permissible, it is approved by the Chemistry Foreman on duty and sent to the Operations Department for approval and processing. When the release is completed, the necessary data from the release (ex., release volume) are transferred from the Operations Department to the Chemistry Department. These data are input to the computer and a post-release printout is generated.                                                                                              The post-release printout contains                                            actual                                                  release   rates,   actual   release concentrations and quantities, actual dilution flew and calculated doses to an individual.
9

1 1.4       Liquid Effluent Release Data 1.4.1     Tables Regulatory Guide 1.21 Tables 2A and 2B are found in this Ereport as Table 1-2a and Table 1-3a for Unit 1, Tables 1-
                     -2b and 1-3b for Unit 2.
1.4.2     Total-Error Measurement The total or maximum error associated with the effluent                                i measurement will include the cumulative errors resulting                               !
from the total - operation of-sampling and measurement.
Because it may be very difficult to assign error-terms l
for- each parameter affecting the final measurement,                                    l detailed statistical      evaluation   of        error       is   not                  1 suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid effluents.
1.4.2.1   Fission and activation total release was calculated from sample analysis results and release point flow rates.
Sampling-and statistical error                     10%
Counting Equipment Calibration                     10%
Tank: Volumes and System Flow-Rates               20%
   =
TOTAL ERROR                                        40%
1.4.2.2  - Total tritium rc' ease was calculated from. sample analysis results and release point volumes.
Tank volumes and system flow rate                  20%
Sampling and-statistical errors                    10%
Counting equipment calibration                     10%
TOTAL-ERROR                                        40%
.          1.4.2.3:  Dissolved and entrained gases were calculated from sample 4-analysis results and release point volumes.
Tank volumes and sistem flow rate                 20%
i                          Sampling and statistical error                    20%
b                          Counting equipment calibration                    10%
TOTAL ERROR                                       50%
1.4.2.4:  Gross alpha- radioactivity was calculated from sample analysis results and release point volumes.
Tank volumes and system flowrates                 20%
Sampling and statistical error                    10%
                          -Counting _ Equipment calibration                  10%
Compositing sample error                            5%
l                          TOTAL ERROR                                       45%
10 L

t 4
          ;1.4.2.5  . Volume of waste prior to dilution was calculated from level indicators on the tanks and - 1p discharge flow rates and times.
Level indicator error                                     10%
L                         Operator interpretation of gauge                          10%
TOTAL ERROR                                               20%
          - 1.4.2.6 - Volume of dilution water used was calculated from flow rate indicators'and pump discharge flow rates and times.
Flow rate indicator error                                 10%
Operator interpretation of gauge                          10%
TOTAL ERROR                                               20%
1.5       Radiological Impact on Man Due to Liquid Releases Doses to an individual due to radioactivity in liquid
                    . effluent were calculated in accordance with the Offsite Dose Calculation Manual. Results are presented in Table 1-4a for Unit 1 and 1-4b for Unit 2.
1.6-      Abnormal Releases 1.6.1     There was one - unplanned release                     for- this reporting period.
1.6.1.1_  On  January- 23,   1992, _approximately one gallon of contaminated water spilled into the yard drain from the-Radwaste Solidification Building while personnel were trying to open the valve of.a nitrogen cylinder. Release permit 92005-L under Unit 1 was generated to account for the radioactivity released to the environment.
1.7       River Flow-
                    - The- average - flow ' rate of the Savannah River for this-4                    Semiannual Effluent Report period was obtained from the Clark-= Hill Dam Corp of Engineers Office.                    The-average flow rate is~6009 cubic feet /sec.
11

                           .               _ _ _. __._.            ,_. _ - . ,       .          . _. ~ .                    .m..-. _ _ _ - _ . _ _
d TABLE 12A GEORGIA POWER COMPANY
;                                    VOGTLE ELECTRIC GENERATING PLANT U-1 SEMIANNUAL S'UMMATION OF ALL RELEASES BY OUARTER
                                                     ' ALL LIQUID EFFLUENTS UNIT :1 STARTING : 1-JAN-1992                   ENDING : 30-JUN-1992 TYPE OF EFFLUENT                                        UNITS QUARTER 1 QUARTER 2 EST. TOTAL                                             ;
ERROR %                    l A. FISSION & ACTIVATION PRODUCTS -                                                                                                      1
: 1. TOTAL RELEASE (NOT INCLUDING                        CURIES            1.04E-02               2.21E 02              40 TRITIUM, GASES, ALPHA)
: 2. AVERAGE DILUTED CONCENTRATION                       uCl/ML 4.14 E-08              4.61 E-08 DURING PERIOD
: 3. PERCENTAGE OF APPLICABLE LIMIT                      %                 N/A                     N/A B. TRITIUM
: 1. TOTAL RELEASE-                                      CURIES           6.85E+01               1.33E+02               40
: 2. AVERAGE DlLUTED CONCENTRATION                       uCl/ML            2.72E-04               2.77E-04 i                    DURING PERIOD
: 3. PERCENTAGE OF APPLICABLE LIMIT                      %                    N/A                   N/A C. DISSOLVED AND ENTRAINED GASES 1._ TOTAL RELEASE -                                    CURIES            5.33E-04               1.73E-03              50               ,
               - 2. AVERAGE DILUTED CONCENTRATION                       uCl/ML           2.12E-09                3.61 E-09 DURING PERIOD -
: 3. PERCENTAGE OF APPLICABLE LIMIT                      %                 N/A-                   N/A
_ D. GROSS ALPHA RADIOACTIVITY _-
: 1. TOTAL RELEASE                                       CURIES -         0.00E+00               0.00E+00               45
;-              E. WASTE VOL RELEASED (PRE-DILUTION) - LITRE                           - 4.69C+05               9.00E+05               20
!               F. VOLUME OF DILUTION WATER USED -                      LITRE            2.51 E +08 -    _
4.'. t E+08 _          20
            ' Zeroes in this table indicate that no radioactivity was present above detectable n            -levels. Se_e Table 1-5 for typical LLD for liquid sample aralyses i
i-12 l        -                                              -_                         _

       .- x -
TABLE 128 GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT U-2 SEMIANNUAL SUMMATION OF ALL RELEASES BY CUARTER
                                             ~ ALL LIQUID EFFLUENTS UNIT: 2 STARTING : 1-JAN-1992            ENDING : 30-JUN 1992
          - TYPE OF EFFLUENT                                     UNITS OUARTER1 OUARTER 2 EST. TOTAL ERROR %
           'A. FISSION & ACTIVATION PRODUCTS.
: 1. TOTAL RELEASE (NOT INCLUDING                     CURIES       3.16E-02     2.52E 02        40 TRITlUM. GASES. ALPHA)
           - 2, AVERAGE DILUTED CONCENTRATION                    uCl/ML       4.52E-08     5.17E-08 DURING PERIOD
           - 3. PERCENTAGE OF APPLICABLE LIMIT                   %             N/A          N/A B. TRITIUM                                                                                         .
: 1. TOTAL RELEASE                                    CURIES       1.56E+02    5.25E+01         40
: 2. AVERAGE DILUTED CONCENTRATION - uCl/ML                        2.23E-04     1.08E-04 DURING PERIOD 3, PERCENTAGE OF APPLICABLE LIMIT                   %               N/A        N/A                j
         - C. DISSOLVED AND ENTRAINED GASES
: 1. TOTAL RELEASE                                  . CURIES      - 3.54 E-04   3.60E-04        50
           - 2. AVERAGE DILUTED CONCENTRATION                    uCl/ML       5.06E-10     7.38E-10 DURING PERIOD--
: 3. PERCENTAGE OF APPLICABLE LIMIT                   %             N/A         N/A A
D. GROSS ALPHA RADIOACTIVITY -
: 1. TOTAL. RELEASE                                   CURIES      0.00E+00     0.00E+00         45 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE                       1.00E+06     8.68E+05         20 F. VOLUME OF DILUTION WATER USED                     LITRE       6.98E+08     4.87E+08         20.
Zoroes in this table indicate that no radioactivity was present above detectable levels. See Table 1-5 for typical LLD for liquid sample analyses 13 i.

TABLE 1-20 GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT SITE SEMIANNUAL SUMMATION OF ALL RELEASES BY OUARTER ALL LIQUID EFFLUENTS SITE STARTING : 1 JAN 1992             ENDING : 30-JUN 1992 TYPE OF EFFLUENT                                       UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %      !
A. FISSION & ACTIVATION PRODUCTS                                                                        l
: 1. TOTAL RELEASE (NOT INCLUDING                       CURIES      4.19E-02      4.73E-02           40 TRITIUM, GASES, ALPHA)
: 2. AVERAGE DlLUTED CONCENTRATION                      uCl/ML      4.41 E-08     4.89E-08
,               DURING PERIOD
: 3. PERCENTAGE OF APPLICABLE LIMIT                     %            N/A           N/A B. TRITIUM                                                                                             1
: 1. TOTAL RELEASE                                      CURIES     2.25E+02      1.86E+02            40
: 2. AVERAGE DILUTED CONCENTRATION                      uCl/ML      2.37E-04      1.92E-04 DURING PERIOD '
          . 3. PERCENTAGE OF APPLICABLE LIMIT                     %              N/A          N/A C. DISSOLVED AND ENTRAINED GASES 1
: 1. TOTAL RELEASE                                      CURIES      8 87E-04      2,09E-03           50 i         - 2. AVERAGE DILUTED CONCENTRATION                      uCl/ML      9.33E-10      2.16E-09
               - DURING PERIOD
: 3. PERCENTAGE OF APPLICABLE LIMIT                    -%            N/A'         WA-
        . D. GROSS ALPHA RADIOACTIVITY
          - 1. TOTAL RELEASE                                      CURIES     0.00E+00      0.00E+00            45 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE.                       1.47E+06      1.77E*06            20 F. VOLUME OF DlLUTION WATER USED                       LITRE '    9.49E+08      9.66E+08            20
,.        _ Zeroes in this table indicate that no radn> activity was present above detectable levels. See Table 1-5 for typical LLD for liquid sample analyses f
14

  . - - . -   .     -.-.-         .   =.-               . . .      . - .       .   . .. . . . _               - - - . . . - . - . -       -
TABLE 13A REPORT CATEGORY : SEMIANNUAL LIOUlD CONTINOUS AND BATCH RELEASES
!                                         : TOTALS FOR EACH NUCLIDE RELEASED.
l                 TYPE OF ACTIVITY- :ALL RADIONUCLIDES                                                                                       ;
REPORTING PERIOD : QUARTEF.1 AND OUARTER 2 YEAR 1992                                                                       l
: UNIT 1 -
CONTINUOUS                        BATCH ISOTOPE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 Co-57      CURIES         0.00E+00     ~0.00E+00           4.14E-06             4.33E-05 Co-58      CURIES         0.00E+00      0.00E+00           3.05E-03             1.05E-02 Co-60      CURIES         0.00E+00      0.00E+00           5.14E-04             1.05E-03 Cr 51      CURIES         0.00E+00      0.00E+00           2.85E-05             1.01 E-03 Cs 134     CURIES         0.00E+00      0.00E+00           2.17E-05             8.35E-06 Cs-137     CURIES         0.00E+00      0.00E+00           3.07E-05             4.17E-05
;                 Fe 55      CURIES         0.00E+00      0.00E+00           2.73E-03             3.90E-03 Fe-59      CURIES         0.00E+00      0.00E+00           4.95E-06             1.59E-04 G ALPHA CURIES            0.00E+00- 0.00E+00              0.00E+00             0.00E+00 H.3        CURIES         0.00E+00      0.00E+00          6.85E+01             1.33E+02 1-131     ~ CURIES        0.00E+00      0.00E+00           3.48E-06             1.09E-04 1-133      CURIES         0.00E+00      0.00E+00          0.00E+00            ' 2.10E-06 Mn-54    - CURIES         0.00E+00      0.00E+00           1.18E-04             3.09E-04 Nb-95      CURIES         0.00E+00      0.00E+00 .         7.37E-05             2.17E-04 Nb-97. CURIES         0.00E+00      0.00E+00          0.00E+00              1.84E-05 Sb-124     CURIES         0.00E+00      0.00E+00           1.54E-04             1.13E                   Sb-125     CURIES         0.00E+00      0.00E+00          3.57E-03              1.52E-03 L                 Sn-113     CURIES         0.00E+00      0.00E+00           5.42E-06            0.00E+00 Sr-09      CUR'ES         0.00E400      0.00E+00          0.00E+00             0.00E+00
                - Sr-90    : CURIES         0.00E+00      0.00E+00          0.00E+00             0.00E+00 Tc-99m     CURIES         0.00E+00      0.00E+ 00.        0.00E+00             0.00E+00 Te-125m CURIES            0.00E+00      0.00t +00         0.00"+00              2.93E-03 Te-132     CURIES         0.00E+00      0.00E+00          0.00E+00             0.00E+00 Xe-131m CURIES -          0.00E+00      0.00E+00          0.00E+03             0.00E+00 Xe-133     CURIES         0.00E+00      0.00E+00          5.33E-04              1.72E-03
                -- Xe-135    CURIES         0.00E+00      0.00E+00          0.00700              0.00E+00 Zn-65    _ CURIES         0.00E+00      0.00E+00          0.00E+00             0.00E+00 Zr-95      CURIES         0.00E+00      0.00E+00           4.10E-05             7.55E-05 Zr    CURIES -       0.00E+00      0.00E+00          0.00E+00              2.08E-06 TOTAL CURIES          0.00E+00      0.00E+00          6.85E+ 01            1.33E+02 i:
15

9 TABLE 138
          - REPORT CATEGORY i SEMIANNUAL LIQUID CONTINOUS AND BATCH RELEASES j                              : TOTALS FOR EACH RADIONUCLIDE TYPE OF ACTIVITY :ALL RADIONUCLIDES REPORTING PERIOD :OUARTER 1 AND OUARTER 2 YEAR 1992
: UNIT 2 CONTINUOUS                                    BATCH ISOTOPE UNIT QUARTER 1 QUARTER 2 OUARTER1 QUAR''ER 2 Co-57      CURIES    0.00E+00        0.00E+00                 2.19E-05                    ,E-06 Co-SS      CURIES    0.00E+00        0.00E+00                 1.30E-02                . 50E-02 Co-60      CURIES    0.00E+00        0.00E+00                 2.37E-03                1.35E-03 Cr-51      CURIES    0.00E+00        0.00E+00                 5.25E-03                2.78E 03 Cs-134     CURIES    0.00E+00        0.00E+00                0.00E+00                0.00E+00 Cs-137     CURIES    0.00E+00        0.00E+00                0.00E+00                 1.46E 05 Fe-55    - CURIES    0.00E+00        0.00E+00                 8.24E-03                1.31 E-0S Fe-59      CURIES    0.00E+00        0.00E+00                 4.79E-04               3.19E-04 G-ALPHA CURIES-      0.00E+00       0.00E+00                 0.00E+00                0.00E+00 H-3        CURIES    0.00E+00        0.00E+00                1.56E+02                5.25E+01 1-131      CURIES    0.00E+00       0.00E+00                  4.29E-05                1.01 E-04 l-133      CURIES    0.00E+00        0.00E+00                 M5E-06                 0.00E+00 Mn-54      CURIES    0.00E+00       0.00E+00                  6 44E-04                4.93E-04 Nb-95      CURIES    0.00E+00        0.00E+00                  '. 45E-04             4.82E-04 Nb-97      CURIES    0.00E+00       0.00E+00                  3.24E-06               0.00E+00 Sb-124     CURIES    0.00E+00        0.00E400                 9.63E-05               2.74E-04 Sb-125 '   CURIES    0.00E+00       0.00E+00                  6.58E-04               2.72E-03 Sn-113     OURIES    0.00E+00'      O.00E+00 -               0.00E+00                2.30E-05 Sr-89      CURIES    0.00E+00       0.00E+00                 0.00E +00 -             0.00E+00 -
Sr-901     CURIES    0.00E+00       0.00E+00                 0.00E+00 -              0.00E+00 Tc-99m - CURIES '    O.00E+00       0.00E+00                 0.00E+00                0.00E+00 Tc-125m ' CURIES     0.00E+00       0.00E+00                 0.00E+00                0.00E+00 Te-132     CURIES    0.00E+00       0.00E+00                  2.54E-05               0.00E+00 Xe-131m CURIES . 0.00E+00       0.00E+00.                0.00E+00 -              3.60E-04 Xe-133     CURIES    0.00E+00: - 0.00E+00                     2.63E             0.00E+00 Xe 135     CURIES    0.00E+00       0.00E+00 .                9.05E-05               0.00E+00                      ,
           -Zn-65      CURIES    0.00E+00       0.00E+00                 0.00E+00                6.89E-06 Zr 95      CURIES    0.00E+00       0.00E+00                  2.24E              1.98E-04
          ' Zr-97      CURIES    0.00E+00       0.00E+00                 0.00E+00                0.00E+00 l
TOTAL CURIES     0.00E+00       0.00E,00                 1.56E+02                5.25E+01 l                                                16 l

  . - - . .      -.. -.   -.       .   . . - , ~ . _ . - ~ _ - - - -                                           _. _ _ , - . - - . _ -          . - -~    .
                                                                                                                                                                )
1 TABLE 13C REPORT CATEGORY : SEMIANNUAL LIQUID CONTINOUS AND BATCH RELEASES
: TOTALS FOR EACH RADIONUCLIDE                                                                            l TYPE OF ACTIVITY              : ALL RADIONUCLIDES -                                                                                  _
REPORTING PERIOD :OUARTER 1 AND QUARTER 2 YEAR 1992
: SITE CONTINUOUS                      BATCH ISOTOPE UNIT QUARTER 1 QUARTER 2 OUARTER 1 QUARTER 2 Co-57              CURIES               0.00E+00   0.00E+00       2.60E-05         4.66E-05 Co-58              CURIES               0.00E+00   0.00E+00        1.61 E-02       2.55E-02 Co40               CUllES               0.00E+00   0.00E+00       2.88E-03         2.40E-03 Cr-51              CURIES               0.00E+00   0.00E+00       5.28E-03         3.79E-03 Cs-134             CURIES               0.00E+00   0.00E+00       2.17E-05         8.35E-06 Cs-137             CURIES               0.00E+00   0.00E+00       3.07E-05         5.63E-05                                   ,
Fe            CUF"ES               0.00E+00   0.00E+00        1.10E-02        5.21 E-03 Fe-59              CURIES               0.00E+00   0.00E+00       4.84E-04         4.78E 04 G ALPHA CURIES                          0.00E+00   0.00E+00       0.00E+00        0.00E+00 H-3                CURIES               000E+00    0.00E+00      2.25E+02          1.86E+02 1-131              CURIES               3.00E+00   0.00E+00       4.64E-05         2.10E-04 l-133              CURIES               '.00E+00   0.00E+00       8.55E-06         210E-06 Mn 54              CURIES               0.00E+00   0.00E+00       7.32E-04         8.02E-04
                                - Nb-95          = CURIES                0.00E+00   0.00E+00       5.19E-04         6.99E-04 Nb-97              CURIES               0.00E400   0.00E+00       3.24E-06          1.84E-05 Sb-124 . CURIES                         0.00E+00   0.00E+00      = 2.50E-04        3.87E-04 Sb-125           . CURIES               0.00E+00   0.00E+00 -    l 4.23E-03        4.24E-03 L                                Sn-113             CURIES               0.00E+00   0.00E+00       5.42E-06         2.30E-05 l-                               Sr-89              CURIES               0.00E+00. 0.00E+00       0,00E+00         0.00E+00 Sr90               CURIES               0.00E+00   0.00E400      0.00E+00         0.00E+00 Tc 99m             CURIES               0.00E+00   0.00E +00. 0.00E+00         0.00E+00 Te-125m CURIES                          0.00E+00   0.00E+00      0.00E+00          P 93E-03 Te-132           _
CURIES               0.00E+00   0.00E+00 -     2.54E-05        0 00E+00 Xe-131m CURIES                          0.00E+00 ' O.00E+00      0.00E+00          3.60E-04 l:                               Xo-133             CURIES               0.00E+00   0.00E >00 -     7.96E 04        1.72E-03 E                                Xe-135             CURIES               0.00E400   0.00E+00       9.05E-05       . 0.00E+00 -                                 !
Zn-65              CURIES             ' O.00E+00-- 0.00E+00      0.00c+00          6.89E-06                                   '
Zr 95              CURIES -             0.00E+00   0.00E+00       2.65E-04         2.74E-04 Zr-97              CURIES               0.00E+00   0.00E+00      0.00E+00          2.08E-06 TOl'AL CURIES                       0.00E+00   0.00E+00      2.25E+ 02         1.86E. 02 L
I-l 17'

4
                                                                                                                        ]
i TABLE.1-4A VOGTLE. ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES-l                                        January 1, 1992 through June 30, 1992 UNIT 1
              - Cumulative Dose Per Ouarter                                                              ,
              - Organ.        Tech          Units                Quarter           % of     Quarter            5 o.
Spec                                     1           Tech         2              Tech Limit                                               Limit                       Limit.
Bone           5.0           mrem       2.68E-04                5.36E-03   4.19E-04         8.38E-03 Liver          5.0           mrem       1.34E-03                2.68E-02   3.11 E-0 3       6.22E-02 T_. Body        1.5          urem      -1.25E-03                8.33E-02   2.95E-03         1.97E-01 Thyroid         5.0          mrem       9,60E-04                1.92E-02   2.72E-03         5.46E-02 Kidnev          5.0          mrem       1 ^#E-03                2.16E-02   3.08E-03         6.16E-02 Luno           5.0           mrem       5.40E-03                1.08E-01   4.65E-03         9.30E-02 GI-LLI          5.0          mrem       1.54E-03                3.08E-02   3.73E-03         7.46E-02 Cumulative Dose Per Year                                    .
Organ         Tech          . Units             Year to Date                % of Tech Spec Limit-Spec Limit Bone           10.0           mrem                  6.78E-04                       6.78E-03 Liver          10.0           mrem                  4.45E-03                       4.45E-02 T. Body          3.0          mrem                  4.20E-03                       1.40E-01 Thyroid        10.0           mrem                  3.69E-03                       3.69E-02 l
Kidney       - 10. 0 -        mrem                  4.16E-03                       4.16E-02 l             _Luno-          10.0           myem                  1.01E-02                       1.01E-01 GI-LLI         10.0           mrem                  5.27E-03                       5.27E-02 l.
d 18 l
        ~,                     ._ .            .       - . . _ - .                      -    -       --         _.

TABLE 1-4B VOGTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES T                                January 1, 1992 through June 30, 1992 l
UNIT 2
      -Cumulative Dose Per Ouarter Organ        Tech             Units              Quarter         % of         Quarter                        4 of Spec                                    1           Tech             2                          Tech Limit                                              Limit                                       Limit Bone           5.0            mrem         7.78E-05           1.56E-03     1.44E-04                   -2.88E-03 Liver          5.0            mrem         9.50E-04           1.90E-02     2.47E-03                     4.94E-02  o T. Body        1.5            mrem         8.63E-04           5.75E-02     2.44E-03                     1.63E-01
      -Thyroid         5.0            mrem          7.91E-04          1.L8E-02     2.43E-03                     4.96E-02 Jidnev          5.Q            mrem         7.66E-04           1.53E-02    _2.33E-03                     4.66E-02 Luno           5.0            mrem          1.58E-03       _ L,16E-02 ___7,.07E-03                      1.41E-01 GI-LLI         5.0            mrem          1.58E-03        .3a 16E-02 ,_.4,6;2E=03                     7.64E-02
      ' Cumulative Dose Per Year Organ        Tech             Units             Year to Date                % of Tech Spec Limit Spec Limit-
                                                                                       ~
Bpne         10.0              mrem                2.22E-04                                2 . 2 2 E ') 3 Liver        10.0              mrem                3.42E-03                                3.42E-02 T. Body        3.0            mrem                3.30E-03                                1.10E-01 Thyroid      10.0              mrem                3.22E-03                                3.22E-02
      ~ Kidney-      10.0              mrem                4.00E-03                                4.00E-02
      ' Luna        -10.0              mrem               8.65E-03                                 8.65E-02 GI-LLI       10.0              mrem                5.40E-03                                5.40E-02 r                                                           19

       .       _ _      m.   . _ _ _ _   _.     . . _ .- .. . - _  . . _ -
TABLE 1-5 LOWER LIMITS OF DETECTION - LIQUID SAMPLE ANALYSES                                        ,
VOGTLE ELECTRIC GENERATING PLANT (January 1, 1992 TilROUGH June 30, 1992) i The values in this table represent a priori lower limits of                                            l detection-(LLD) which are typically achieved in laboratory analyses -
of liquid radwaste samples.
RADIOMUCLIDE                                      LLD                           UNITS                  ,
           - Mn-541                                      2.73E-08                            uCi/ml Fe-59                                       8.33E-08                            uCi/ml-Co-58                                       3.78E-08                            uCi/ml
            'Co-60                                       6.-76E-08                           uCi/ml Zn-65'                                      1.32E-07                            uC1/ml Mo-99                                       4.31E-07                            uCi/ml
           - Cs-134                                      3.06E-08                            uCi/ml~
Cs-137                                      4.51E-08                            uCi/ml
.          - Ce-141                                      6.99E-08                            uCi/ml l            Ce- 1 ~4 4                                  2.95E-07                            uCi/ml I-131                                       5.97E-08                            uCi/ml Xe-133                                      9.11E-08                            uCi/ml
.          - Xe-135                                      4.27E-08                            uCi/ml Fe-55                                       1.00E-06                            uCi/ml Sr-89                                       5.00E-08                            uCi/ml-
           - Sr-90                                       7.00E-09                            uCi/ml
           - H-3                                         2.00E-06                            uC1/ml Gross Alpha                                 7.00E-08                            uCi/ml J
1 20

TABLE 1-6A GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT - UNIT 1 BATCil RELEASE 

==SUMMARY==
OF ALL RELEASES STARTING:                                               JANUARY 1, 1992                                                             ENDING:   JUNE 30, 1992 LIQUID RELEASES                                                                                                           -
Humber of Releases:                                                                                                                                             62 Total Time For All Releases:                                                                                                                                 7999 minutes Maximum-Time For A Release:                                                                                                                                   518 minutes
          = Average _ Time For A Release:                                                                                                                                129 minutes Minimum Time For A Release:                                                                                                                                     38 minutes Average Stream Flow                                                                                                                                             42 GPM GASEOUS RELEASES Number of Releases:                                                                                                                                             73 Total Time For All Releases:                                                                                                                                19276   minutes
          . Maximum Time For A Release:                                                                                                                                 3860   minutes Average Time For A Release:                                                                                                                                    264  minutes Minimum Time For A Release:                                                                                                                                     49  minutes     -
21

ib di2iii.i is 7.,-
TABLE 1-6B GEORGIA POWER COMPANY VOGTLE. ELECTRIC GENERATING PLANT U-2 BATCII RELEASE 

==SUMMARY==
OF ALL RELEASES STARTING:       -JANUARY 1, 1992        ENDING:    JUNE 30, 1992 LIQUID RELEASES
                 ' Humber of Releases:                                  58 Total Time for All Releases:                       13456 minutes
                 - Maximum Time For A Release:                         689 minutes Average 1 Time'For A Release:                        232 minutes Minimum Time For A Release:                            4 minutes         y Average Stream Flow:                                  36 GPM c.
GASEOUS RELEASES Number of Releases:                                   59 Total Time For All-Releases:                      54525   minutes Maximum Time For A Release:                        6106   minutes Average Time For A Release:                         -924  minutes         -
Minimum Time For A= Release:-                          1  minutes 22

4 2.0                     . Gaseous Effluents 2.1                       Regulatory Limits / Technical Specifications-                                                                                   1 1
                                                                                                                                                                            'l The Technical Specifications presented in this section                                                                           )
are for Unit 1 and Unit 2.
i 2 .' 1 .1                 Dose Rate Limit The dose rate due to radioactive materials released in gaseous effluents from the site to. areas at and beyond the SITE BOUNDARY shall be limited to the following:
: a.            For noble gases:                         Less than or equal                    to 500 mrems/yr-to the whole body and less than or equal to 3000 .mrems/yr to the skin, and
: b.             For . !odine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:. Less than or: equal to 1500 mrems/yr to any organ.
2.1.2                    Air Dose Due to Noble Gas The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and-beyond the
                                            -SITE. BOUNDARY shall be limited to the following:
: a.             During .any calendar quarter:                         Less than or equal to 5 mrads for gamma radiation and less than or equal                                                               -
l                                                           to 10 mrads-for beta radiation, and
                                            'b.             During any calendar year: Less than -or- equal to 10 mrads for-gamma radiation and less than or equal to-20 mrads;for. beta radiation._
2.1. 3_                 _ Dose to Any Organ The dose _ to a MEMBER OF - THE .-. PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form _ with half-lives greater i than - 8 days in _ gaseous-b                                            effluents released, from each unit, to areas at and beyond_ the SITE DOUNDARY -shall be limited to the Ll l                                            following:
    =
a.L           During any calendar quarter:                          Less than or equal to 7.5'mrems to any organ and,
: b.            During any calendar-yeat-: .Less than or-equal to 15 lL                                                         mrems to any organ.
23
                        -               -_______.._2__                                           . _      . - _ _             . - . _   . . _ , - . . . _ . . _ _ _

2.1.4      Total Fuel Cycle Dose Commitment - (40CFR190)
The~ annual (calendar year) dose or dose commitment _to any MEMBER OF THE PUBLIC due to releases of- radioactivity and to radiation- from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the_whole body or to any organ, except the thyroid, which shall be
                  -limited to less than or equal to 75 mrems.
2.2        Release Points of Gaseous Effluents C 4seous Ef fluents at Vogtle Electric Generating Plant are currently confined to four paths:     plant vents (Unit 1 and Unit 2), and the condenser air ejector and steam packing exhauster systems (Unit 1 and Unit 2).
Waste gas decay tanks are batch releases and the waste gas decay tanks are released through the Unit 1 plant vent. Containment purges are released through their respective plant vents.
2.3        Sample Collection and Analysis All .of the paths can be continuously monitored- for gaseous radioactivity.       Each is equipped with an integrated-type-sample collection device for collecting particulates-and iodines. Dcring this release period, there were no radioactive releases through the condenser air ejector and steam packing exhauster system vents.
Unless    required    n. ore frequently        under            certain circumstances samples are collected as follows:
: 1. Nc Nle gas samples are' collected by grab sampling monthly,
: 2. Tritium samples are collected by grab sampling
                        -monthly. Since spent fuel was placed-in the spent-o     fuel pool during the .first Unit. 1 refueling, tritium samples are collected weekly on the Unit 1 (Common) Plant Vent.
                  -3. Radiciodine samples are collected from the_ sample stream- through -a charcoal- cartridge over a 7-day period.
: 4. Particulates are collected from the sample stream through=a; particulate filter over a 7-day period.
: 5. _ The - day particulate filters above are analyzed for gross alpha activity .
24 l
g
: 6. Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the quarterly composite sample is analyzed _for Sr-89 and Sr-90.
Batch Waste Gas Decay Tank releases are analyzed for iodines, particulates, and noble gases before each release.          In addition, the containment atmosphere is analyzed for tritium on at least a montbly basis.
Sample analyses results and release flow rates from the 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 normally performed with computer assistance.
With    each             release              period   _and   batch          release, radioactivity, dose rates, and cumulative doses are calculated. Cumulative dose results are tabulated, along with-percent of Technical Specification limits for each release for the current quarter and year.
                     ~2.4     Total Quantities                __of        Radioactivity,   Dose   Rates,          and Cumulative Doses The methods for determining release quantities of radioactivity, dose rates, and cumulative doses follow:
2.4.1  Fission and Activitation Gas The released radioactivity is determined from sample analyses results collected as described above and average release flow rates _ over the period represented by the collected. sample.
                             . Instantaneous dose-rates.due to noble-gases and_due to radiciodines, tritium, and particulates are calculated (with computer assistance).                         Calculated-dose rates are
                             - compared to the dose rate limits specified in 3.11.2.1a for noble gases,                         and 3.11.2.1b of the Technical
;                             Specifications                     for        radiciodine,     tritium,             and t
particulates.                  Doae rate . calculation methodology is presented in-the ODCM.
Beta and gamma                     air doses due to noble gases _ are calculated for the location in the unrestricted area with-Lthe potential for the highest exposure dun to gaseous releases.           Air doses are calculated for each release period and cumulative totals are kept for each unit for                                         ,
the calendar' quarter and year. Cumulative air doses are                                        l
* compared to the dose limits specified in Technical                                              !
Specification 3.11. 2. 2.                     Current percent of the Technical                  i h                             Specification limits are shown on the printout for each lI 25 l

_            . . _ - . _ _ _ . _ . .                       .... _ _~ _.._ ._._ _ _ ____ __.-._ _ _
4 e
1 release period.                        Air : dose calculation methodology is presented in the ODCM.
2.4.2             Radiciodine, Tritium and Particulate Releases Released quantities of radiciodines are determined from                                               ;
the-weekly samples and release flow rates for the two                                                '
release                     points.              Radiciodine                    concentrations  are   ,
determined by gamma spectroscopy..
1 Release quantities of particulates are determined from the weekly (filter) samples and release flow rates for the two release points. Gamma spectroscopy is used to quantify' concentrations of principal gamma emitters.
After each quarter, the particulate filters from each vent are combined, fused, and a strontium separation is                                              .
performed. -If Sr-89 or Sr-90 is not detected, LLD's are calculated. - Strontium concentrations are input to- the composite file of the computer to be used for release dose rate and individual dose calculations.
Tritium samples are obtained at least monthly from each vent by-bubbling the sample stream through a water trap.
The tritium concentration in water is converted to tritium concentration in air and this value is input into the composite file of the computer to be used in release, dose rate, and individual dose calculations.
Dose rates due to radioiodine, tritium, and particulates nre calculated for a hypothetical child, exposed to the inhalation pathway, at the -location in the unrestricted                                            -
brea where the potential dose rate is expected to be the highest.                    Dose rates are calculated for each release
                                   . point, for ecch releave_ period, and the total dose _ rate from both' release points.are-compared to the dose rate limits specified in Technical: Specification 3.11.2.1b.
Individual doses due                                     to- radioiodine,               tritium and .
particulates are calculated for the critical receptor, which for -vogtle Electric Generating Plant is a-child exposed to the inhalation. and ground-plane pathways.
Individual doses are calculated for each release' period, and a .mulative - totals are kept for each unit for the-curr .t calendar quarter and year. Cumulative. individual d o s e.3 _ a r e cotapared to the dose limits specified in Technical Specification 3.11.2.3.
Current percent of technical specification limits are shown on-the printout for each release period.
n                                                                                  26

       . . . . . . . - . - - - - . -. -. ---~ - . - - . . -                                              .. - . - .. - . - . -         . . ~ - . . . . - - ~ _
1 12,4.3                        Gross Alpha Release o
The : gross alpha: release is calculated _each month by counting the particulate filters for each week for gross alpb' activity in a proportional counter by an offsite                                            '
labr ratory.         The four or five weeks' numbers - are then recorded on a data sheet and the activity is summed at the end of the month. This concentration is input to the composite file of the computer and is used for release calculations.
2.5                         Gaseous Effluent Release Data 2.5.1                      ' Methodology Regulatory Guide 1.21 Tables 1 A, 1B, and 1C are found in this report as Tables 2-2a, 2-2b, 2-3a, 2-3b, 2-4a and 2-4b. Data is presented'on a quarterly basis as required by Regulatory Guide 1.21.
To complete table 2-2a and 2-2b, total release for each of the four. categories (fission and activation gases, iodines, particulates, and tritium) was divided _by the number of seconds in the quarter to obtain a release rate in uCi/second for each category for each quarter.
However, the percent of the Technical Specification limits are not applicable because we have no curie limits for gaseous- releases.               Noble gases are limited as specified in Technical Specification 3.11.2.1a.                               The other_ three. categories- (tritium, radiciodines,                              and particulates)__ are limited as a group as specified in
!                                                           T1chnical Specification 3.11.2.1b.
Dose rates due to noble gas- releases and due to radiciodine, tritium, and particulates were calculated as part of the pre-release and post-release permits on individual permits.              No limits were exceeded for this reporting period.
l                                                           Gross alpha radioactivity is reported in Table 2-2a and-2-2b as curies released in each quarter.
Limits for-cumulative beta and gamma air-doses due to noble gases are specified -in Technical Specification L                                                            3.11.2.2. Cumulative air doses are presented in Table 2-6a and 2-6b along with percent of. technical specification l-                                                          limits'.
Limits     'for - cumulative           individual                  doses due      to-radiciodine, tritium, and particulates, are specified in Technical Specification 3.11.2.3. Cumulative individual doses.are presented-in Table 2-7a and 2-7b along with percent of technical specification limits.
27

                    .                                                                                                                           t 4
i Tne total or maximum error associated with the effluent                            l measurement will include the cumulative errors resulting                           l from the total operation of sampling and measurement.
Becaose .t may be very difficult to assign error terms                             ,
for - cach parameter affecting the final measurement, detailed statistical evaluation of error are not suggested                     The objective should be to obtain an overall
* estimate of the error associated with measurements of                              ,
radioactive materials released in liquid and gaseous effluents and solid waste.
Estimated                    errors are     based on errors in counting equipment calibration,                      counting statistics, vent-flow         ,
rates,-vent sample flow                    rates, non-steady release rates,        t chemical: yield-factors                    and sample losses for such items        ,
as charcoal cartridges.
2.5.1.1                      Fission and activation total release was calculnted from sample analysis results and release point flow rates.
,~                                                           Sampling and statistical error In counting                          10%
counting equipment calibration                                      10%
Vent flow rates _                      _ _                         _10%            -
Non-steady release rates                                            20%
TOTAL ERROR                                                         50%
2.5.1.2                       I-131 releases were calculated from each weekly sample:
Statistical error in counting'                                      10%
Counting equipment calibration                                      10%
Vent Flow Rates-                                                     10%
Vent Sample Flow Rates                                               50%
Non-steady release rates _                                          10%
                                                             'oses from charcoal cartridges 10%
TOTAL ERROR                                                        100%
2.5.1.3'                    .Particulates with half lives greater than 8 day releases
;                                                           were calculated from sample analysis results and-release point. flow rates.
Statistical error.at LLD concentration                              10%
Counting equipment calibration                                       10%
I                                                           Vent-flow rates                                                      10%
Vent-sample flow rates                                               50%
l Non-steady release rates                                             10%
TOTAL ERROR                                                          90%
26
[

2.5.1.4        Total . tritium releases were calculated from     sample analysis results and releasu point flow rates.
Water vapor in sample stream I
determination                      10%
Vent flow rates                                 10%
Counting-calibration and statistics             10%
Non-steady release rates                        10%
TOTAL ERROR                                     40%
2.5.1.5        Gross Alpha radioactivity was calculated from sample analysis results and release point flow rates.
Lcatistical error at LLD concentration          10%
Counting equipment calibration                  10%
Vent ~ flow rates                               10%
Vent sample flow rates                          50%
Non-steady release rates                        10%
TOTAL ERROR-                                    90%
2.5.2          GaseousiBatch Data-Other data pertinent _ to batch releases of radioactive gaseous effluent from Unit 1 and Unit 2 are listed in    ,
Table 1-6L and 1-6b.
2.6-           Radiological Impact Due to Gaseous Releases Dose rates due to noble gas releases were calculated for the site in accordance with Technical Specification 3/4.11.2.la. Dose rates due to radiciodine, tritium, and particulates in gaseous releases were calculated in accordance with Technical Specification 3/4.11.2.1b.
As part of pre-release and post release on individual release permits, these dose rates were calculated. No limits were exceeded for this reporting period.
Cumulative air doses due to noble gas releases were o                        calculated for each unit in_ accordance with Technical o                        Specification 3/4.11.2.3. These results are presented in
                        -Tables 2-7a and.2-7b.
Dose- rates and- doses were calculated' using the u                       methodology presented in the Vogtle Electric Generating Plant Offsite Dose Calculation Manual.
l 29

l i
i TABLE 2 2A                                                                                                                                    ,
GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT U 1 SEMIANNUAL GUMMATION OF ALL RELEASES RY OUARTER ALL AIRBORNE EFFLUENTS UNIT : 1                                                                                                                                       ;
STARTING : 1 JAN 1992                     ENDING : 30-JUN 1992 1YPE OF EFFLUENT                                                           UNITS          OUARTER1 QUARTER 2 EST. TOTAL ERROR %                                           ;
A. FISSION & ACTIVATION PRODUCTS
: 1. TOTAL RELEASE                                                         CURIES                  7.98E+00                                1.42E+01              50
: 2. AVERAGE RELEASE RATE FOR PERIOD uCl/See                                                       1.03E+00                                1.79E+00
: 3. PERCENTAGE CF APPLICAGLE LIMIT                                        %                       N/A                                t#A f
         - B. RADIOlODINES
: 1. TOTAL LODINE 131                                                      CURIES                   1.02E-05                                4.64E-04           100
: 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec                                                        1.31E 00                                5.84 E-05 DURING PERIOD
: 3. PERCENTAGE OF APPLICl BLE LIMIT                                       %                          t#A                                     N/A t
C. PARTICULATES 1.PARTICULATES(HALF LIVES >8 DAYS)                                       CURIES                   9.86E-06                                5.01 E-06            90
: 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec                                                        1.27E-00                                0.30E-07
: 3. PERCENTAGE OF APPLICABLE LIMIT--                                      %                        N/A                                     N/A D. TRITIUM
: 1. TOTAL RELEASE                                                         CURIES                  5.99E+01                                2.26E+01              40                                        >
: 2. AVERAGE RELEASE RATE FOR PERf00 uCl/Sec                                                       7.71 E+00                              2.84 E@
3.PEr1CENTAGE OF APPLICABLE LIMIT                                        %                       N/A                                  N/A
: 4. GROSS ALPHA RADIOACTIVITY                                             CURIES                  3.41E 07                                 3.80E-07             90 Zeroos in this table indicate that'no radioactivity was present above detectable levet See Table 2 8 for typical LLD for gaseous sarnple anahses.
30 e "-4m *        -+-.- . -,w  c,,,,.,,..,,,-r.,,,,       _,-,m..,,v., ,.    ,-,mm..,e-                .,,,-.w, y..m..,r..~,,-,..,_,.-~,,--,-.,,.,e,._,,.mv..w._        ..,.,m. .+-,.,,-,,...m , , , , - , , . , =

9 e
TABLE 2 2B
                                                     . GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT U 2                                                     .
SEMIANNUAL SUMMATION OF ALL RELEASES BY OUARTER ALL AIRBORNE EFFLUENTS UNIT : 2                                                        l STARTING : 1 JAN 1992                  ENDING : 30-JUN 1992 TYPE OF EFFLUENT                                              UNITS OUARTER1 OUARTER 2 EST. TOTAL ERROR %
A. FlSSION & ACTIVATION PRODUCTS
: 1. TOTAL RELEASE                                            CURIES           2.12E401         1.80E+00        50
: 2. AVERAGE RELEASE RATE FOR PERIOD uCl/ Soc                                   2.73E+00         2.26E-01
: 3. PERCENTAGE OF AFPLICABLE LIMIT                            %               N/A             N/A B. RADIOIODINES
: 1. TOTAL IODINC 131                                          CURIES            7.69E 04        4.90E 05       100   ,
: 2. AVERAGE RELEASE RATE FOR PERIOD UCl/Sec                                     9.88E45         6.16E 06 DURING PERIOD 3 PERCENTAGE OF APPLICABLE LIMIT                             %                   N/A            N/A C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS)                          CURIES           3.98E-03         5.00E 04         90
: 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec                                     5.12E 04        6.29E-05
: 3. PERCENTAGE OF APPLICABLE LIMIT                            %                 N/A             N/A                  !
D. TRITIUM I                1. TOTAL RELEASE                                            CURIES           2.78E+01         2.03E+01        40
: 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec                                    3.58E+00         2.55E+00
: 3. PERCENTAGE OF APPLICABLE LIMIT                            %           N/A               N/A
: 4. GROSS ALPHA RADIOACTIVHY                                  CURIES           3.44E 07         3.77E-07         90-Zeroes in this table indicate that no radioactivity was present above detectable level. See Table 2-8 for typical LLD for gaseous sample analyses.
31
    . . , _      m ,_ . _ _ _ , _ _ _ _ __ _. _ .. _ _ _ . _ _ _ _ _ .. _ _ ._..~. , _ _ _ - _ _ _ _ _ . ,

                                   -      -      .. - _ . _ . . .~ _ -               _._ - . - - - . - . -                       .. _- .c. ..
l l
l TABLE 2 2C l
GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT SITE SEMIANNUAL SUMMATION OF ALL RELEASES BY OUARTER ALL AIRBORNE EFFLUENTS SITE STARTING : 1 JAN 1992                   ENDING : 30-JUN 1992 TYPE OF EFFLUENT                                           UNITS    OUARTER1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
: 1. TOTAL RELEASE                                          CURIES        2.92E401               1.00E+01           50
: 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec                              3.75E+00               2.01 E4 00                     ,
l
: 3. PERCENTAGE OF APPLICABLE LIMIT                         %            t#A                   N/A                              i l
O. RADIOIODINES
: 1. TOTAL LODINE 131                                       CURIES         7.79E-04              5.13E-04          100 t
: 2. AVERAGE RELEASE RATE FOR PERIOD uCl/ Soc                              1.00E-04              6.46E-05                       !
DURING PERIOD
: 3. PERCENTAGE OF APPLICABLE LIMIT                          %                N/A                 t#A C. PARTICULATES 1.PARTICULATES(HALF LIVES >8 DAYS)                        CURIES         3.99E 03               5.05E-04          90
: 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec                               5.13E 04              6.35E-05
: 3. PERCENTAGE OF APPLICABLE LIMIT                          %              N/A                  N/A D. TRITIUM
: 1. TOTAL RELEASE                                          CURIES -      8.77E+01               4.20E+01           40
: 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec                              1.13E+01               5.38E400
: 3. PERCENTAGE OF APPLICABLE LIMIT                          %       N/A                     N/A
: 4. GROSS ALPHA RADIOACTIVITY                              CURIES         6.85E-07              7.57E-07           90-Zeroes in this table indicate that no radoactivity was present above detectable                                                >
level. See Table 2 8 for typical LLD for gaseous sample analyses.
32 5

TABLE 2-3A (Page 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - MIXED MODE January 1, 1992 through June 30, 1992 UNIT 1 Continuous Mgde                               Hatch Mode Nuclides                        Unit        Quarter              Quarter            Quarter       Quarter Heleased                                        1                   2                   1             2
: 1. Fission Gases Xo-131M                         Ci           0.00E400             0.00E+00           4.66E-02     6.62E-02 Xo-133                          C1           1.35L                1.05E+00           6.38E+00     1.15E+01 Xe-133M                         Ci           0.00E+00             5.08E-01           7.90E-02     1.75E-01 Xo-135                          Ci           0.00E+00             0.00E400           7.52E-02     5.48E-01 Ar-41                           Ci           0.00E600             0.00E400           3.78E-02     1.95E-01 Kr-85M                          Ci           0.00E+00             0.00E+00           4.52E-03     8.16E-02 Kr-85                           C1           0.00E+00             0.00E+00           1.85E-03     0.00E+00 217 PAL FOR PERIOD              C1           1.35E+00             1.56E+00           6.63E+00     1.26E+01
: 2. Iodines I-131                           C1           1.02E-05             4.64E-04           0.00E+00     0.00E+00 I-132                           Ci           0.00E+00             0.00E400           0.00E+00     0.00E+00 1-133                           C1           1.30E-05             3.84E-05           0.00E+00     0.00E+00 TOTAL FOR PERIOD                C1           2.32E-05              5.02E-04          0.00E+00     0.00E+00 0 Zeroes in this table indicate that no radioactivity was present above detectable levels.                 See Table 2-8 for typical lower limits of detection for
: gaseous samples analyses.
33

e TABLE 2-3A (Page 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - MIXED MODE January 1, 1992 through June 30, 1992 UNIT 1 Continupua Mode                     llaLgh Mode Nuclides                  Unit                Quarter            Quarter  Quarter            Quarter Released                                          1                    2        1                2
: 3. Particulates**
    "Be-7                     C1                  2.36E-06           0.00E+00 0.00E+00            0.00E+00 Co-57                     Ci                  0.00E400           0.00E+00 0.00E+00            0.00E+00 Co-58                     C1                  4.54E-06           4.00E-06 0.00E+00            0.00E+00 Co-60                     Ci                  0.00E+00           0.00E+00 0.00E400            0.00E400 Mn-54                     C1                  2.66E-07           0.00E+0D 0.00E+00            0.00E+00 Cs-134                    C1                  1.45E-06           0.00E+00 0.00E+00            0.00E+00 Cs-137                    C1                  1.24E-06           1.01E-06 0.00E+00            0.00E+00 Cr-51                     Ci                  0.00E400           0.00E+00 0.00E+00            0.00E+00 Na-24                     Ci                  7.94E-OS           0.00E+00 0.00E+00            0.00E+00 G-Alpha                   C1                  3.41E-07           3.81E-07 0.00E400            0.00E+00 11 - 3                    Ci                  S.98E+01           2.24E+01 7.70E-02            1.63E-01 TOTAL FOR PERIOD          Ci                  5.98E401           2,24F+01 7.70E-02            1.63E-01 i
* Zeroes in this table indicate that no radioactivity was present above detectable levels.           See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
    ** IIalf lives greater than 8 days.
i
(
L                                                         34

i TAllLE 2-3B (Page 1 OF 2)
VOGTLE ELECTRIC CENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUEff1'S - MIXED MODE January 1, 1992 through June 30, 1992 UNIT 2 Conj;_inuous  i       Mode                            Datch Mcxle Nuclides                         Unit           Quarter                Quarter             Quarter                       Quarter                                    ,
Holeased                                                1                    2                   1                                  2
: 1. Fission Gases Xe-131M                          Ci              000E400                  0.00E+00          0.00E+00                          0.00E+00 Xe-133                           C1              1.93E+01                 1.40E+00          1.39E+00                          3.34E-01 Xs-133M                          C1              0.00E400                 0.00E+00          0.00E+00                         0.00E+00 Xe-135                           C1              0.00E+00                0.00E+00           3.12E-02                          0.00E+00 Ar-41                            Ci              0.00E+00                0.00E400           4.80E-01                          5.52E-02 Kr-SSM                           Ci              0.00E+00                0.00E+00           0.00E+00                          0.00E+00 Kr-87                            Ci              0.00E+00                0.00E400           0.00E400                         0.00E+00 TOTAL FOR PERIOD                 Ci              1.93E+01                  1.40E+00          1.90E400                        3.89E-01 5
: 2. Iodines I-131                            C1              7.68E-04                 4.88E-05           0.00E+00                        0.00E400 I-132                            Ci              0.00E+00                 0.00E+00           0.00E+00                        0.00E+00 I-133                            C1              1.17E-04                 4.68E-05           0.00E400                        0.00E+00 TOTAL FOR PERIOD                 Ci              8.65E-04                9.56E-05            0.00E400                        0.00E+00 0 Zeroes in this table indicate that no radioactivity was present above detectable levels.                  See Table 2-8 for typical lower limits of detection for gaseous samples analyses.
35 i-l    -      -         . . . .                            _ _ , - _ .       .   .-       _                .--               - _.          -   . . _ . .        .-

TA3LE 2-3B (Page 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - MIXED MODE January 1, 1992 through June 30, 1992 UNIT 2                                                                     i
__ Continupys Mode                            Batch Mode Nuclides            Unit       Quarter             Quarter     Quarter                      Quarter Heleased                           1                       2          1                              2
: 3. Particulates**
Fe-59               C1         4.20E-05            6.66E-06        0.00E400                      0.00E+00 Nb-95               Ci         3.30E-05            7.30E-05        0.00E+00                      0.00E+00 Zr-95               C1         1.60E-05            4.90E-06        0.00E+00                      0.00E400 Co-144              Ci         0.00E+06             1.05E-06       0.00E+00                      0.00E+00 Co-58               C1         2.9BE-03            2.76E-04        0.00E+00                      0.00E+00 Co-60               Ci         1.20E-04            2.70E-05        0.00E+00                      0.00E+00 Mn-54               C1         5.84E-05            1.27E-05        0.00E+00                      0.00E+00 Co-57               C1         3.16E-06            7.62E-07        0.00E400                      0.00E+00 Cr-51               Ci         7.28E-04            6.78E-05        0.00E+00                      0.00E+00 Na24                Ci         0.00E+00            5.80E-05        0.00E+00                      0.00E400 G-Alpha             Ci         3.44E-07            3.77E-07        0.00E+00                      0.00E+0d"~
H-3                 Ci         2.74E+01            1.95E401         3.56E-01                     6.76E-01 TOTAL FOR PERIOD    Ci         2.74E+01            1.95E+01         3.56E-01                     6.76E-01
* Zeroes in this table indicate that no radioactivity was present above                                        !
detectable levels. See Table 2-8 for typical lower limits of' detection for gaseous samples analyses.
  ** Half-lives greater than 8 days.
36 i

TABLE 2-3C (Page 1 OF 2)
VOGTLF. ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - MIXC) MODE January 1, 1992 through June 30, 1992 SITE Continuous i           Mod 1              Ha(ch Mode Nuclides                                Unit         Quarter              Quarter     Quarter     Quarter Herensed                                                   1                  2          1         2
: 1. Fission Gases Xe-131M                                 C1           0.00E+00              0.00E400   4.66E-02      6.62E-02 Xc-133                                  Ci            2.07E+01             2.45E+00   7.77E+00      1.18E+01
                                                     ~                               ~
Xc-133M                                 Ci            0.00E+00             5.08E-01   7.90E-02      1.75E-01 Xo-135                                  C1            0.00E+00             0.00li+00  1.06E-01      5.48E-01 Ar-41                                   Ci             0.00E400            0.00E+00   5.18E-01      2.50E-01 Kr-85M                                  Ci             0.00E+00            0.00E400   4.52E-03      8.16E-02 Kr-85                                   Ci              0.00E400           0.00E+00   1.85E-03      0.00E+00 TOTAL FOR PERIOD                        C1              2.07E+01           2.96E400   8.52E400      1.30E+01
: 2. Iodines I-131                                   Ci             7.78E-04             5.13E-04 0.00E400     0.00E+00 T-T32                                   Ci             0.00E+00             0.00E+00 0.00E+00     0.00E+00 1-133                                   C1             1.30E-04             U.52E-05  0.00E+00    0.00E400 TOTAL FOR PERIOD                        Ci             9.08E-04             5.98E-04  0.00E400    0.00E400 O Zeroes in this table indicate that no radioactivity was present above
      'detectabl e levels.                      See Table 2-8 for typical lower limits of detection for gaseous samples analyses.
37 m_..u

TABLE 2-3C (Page 2 OF 2)                                                                        ~
VOGTLE ELECTRIC GENEllATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - MIXED MODE January 1, 1992 t.hrough June 30, 1992 SITE Continpous Mode                                                Batch Mode Nuclides                  Unit            Quarter                        Quarter     Quarter                  Quarter Released                                                          1          2                1                   2
: 3. Particulates**
Bo-7                      C1                2.36E-06                     0.00E400    0.00E+00                  0.00E+00 Co-57                     Ci                 3.16E-06                    7.62E-07    0.00E+00                  0.00E+00 Co-58                     C1                  2.98E-03                   2.80E-04    0.00Ee00                  0.00E+00 Co-60                     C1                   1.20E-04                  2.70E-05    0.00E400                  0.00E+00 MN-54                     Ci                   5.87E-05                  1.27E-05    0.09E400                  0.00E+00 Cc-134                    C1                    1.45E-06                 0.00E+00     0.00E+00                 0.00E400 Cs-137                    C1                     1.24E-06                1.01E-06      0.00E400                0.00E+00 CR-51                     Ci                    7.28E-04                 6.78E-05      0.00E+00                0.00E+00 da-24                     Ci                    7.94E-06                5.80E-05      0.00E400                0.00E+00 G-Alpha                   Ci                     6.85E-07               7.58E-07      0.00E+00                0.00E+00 Fe-59                     Ci                     4.20E-05                6.66E-06     0.00E+00                 0.00E+00 Nb-95                     Ci                      3.30E-05               7.30E-05     0.00E+00                 0.00E+00 Zr-95                     C1                        1.60E-05             4.90E-06     0.00E400                 0.00E+00
                          ~
Co-144                    Ci                       0.00E400              1.05E-06     0.00E+00                 0.00E+00 11 - 3                    Ci                       8.72E+01              4.14E+01     1.13E+00                 8.39E-01 TOTAL FOR PERIOD          Ci                        8.72E+01             4.19E+01      1.13E+00                8.39E-01
* Zeroes in this table indicate that no radioactivity was present above detectable levels.        See Table 2-8 for typical lower limits of detection for gaseous samples analyses.
        ** Half lives greater than 8 days.
38

1 I
t TABLE 2-4A (Page 1 OF 2)                                         t VOGTLE ELECTRIC GENERATING PLANT                                                     i SEMIANNUAL RADIOACTIVE EFFLUENT REPORT                                                   l GASEOUS EFFLUENTS - GROUND LEVEL January 1, 1992 through June 30, 1992 UNIT 1 1
1 Con _tinuous Mode                          Untch Mode Nuclides            Unit                       Quarter
* Quarter
* Quarter
* Quarter
* Released                                          3                 4                  3            4
: 1. Fission Gases Xo-131M             Ci                        0.00E+00          0.00E+00            0.00E+00    0.00E+00 Xc-133              Ci                        0.00E+00          0.00E+00            0.00E+00    0.00E+00 Xo-133M             Ci                        0.00E+00          0.00E+00            0.00E+00    0.00E+00 Xe-135              Ci                        0.00E+00          0.00E+00            0.00E+00    0.00E400 Ar-41               Ci                        0.00E+00          0.00E+00            0.00E+00    0.00E+00 Kr-85M              Ci                        0.00E+00          0.00E+00            0.00E+00    0.00E+00
                                                                                                               ~~
Kr-87               Ci                        0.00E+00          0.00E+00            0.00E+00    0.00E+00 TOTAL FOR PERIOD    Ci                        0.00E+00          0.00E+00            0.00E+00    0.00E+00     l
: 2. Iodines I-131               Ci                        0.00E+00          0.00E+00            0.00E+00    0.00E+00 1-132               Ci                        0.00E400          0.00E+00            0.00E+00    0.00E+00 I-133               C1                        0.00E+00          0.00E+00            0.00E+00    0.00E+00 TOTAL FOR PERIOD    Ci                        0.00E+00          0.00E+00            0.00E+00    0.00E+00
* No Releases during this period.
i 39 l
l

TABLE 2-4A (Page 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - GROUND LEVEL                                                         i January 1, 1992 through June 30, 1992                                                            I UNIT 1 1
1 Continuous Mode                           Bat _glLMode                        !
g   Nucliden             Unit                 Quarter
* Quarter
* Quarter
* Quarter
* Released                                      1               2              1                                 2
: 3. Particulates**
Co-58                C1                    0.00E+00     0.00E+00       0.00E+00                       0.00E+00
                                                                                                                           ^
Co-60                Ci                    0.00E+00     0.00E+00       0.00E400                       0.00E+00 Mn-54                C1                    0.00E+00     0.00E400       0.00E+00                       0.00E+00         ;
Hb-95                Ci                    0.00E+00     0.00E+00       0.00E+00                       0.00E+00 G-Alpha              C1                    0.00E+00     0.00E+00       0.00E+00                       0.00E+00 11 - 3               Ci                    0.00E+00     0.00E+00       0.00E400                       0.00E+00 Kr-87                Ci                    0.00E+00     0.00E+00       0.00E+00                       0.00E+00 TOTAL FOR PERIOD     Ci                    0.00E400     0.00E+00       0.00E+00                       0.00E*00 0 No Releases during this period.
00 llalf lives greater than 8 days.
l l
l 1
40

TABLE 2-4H (Page 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - GROUND LEVEL January 1, 1992 through June 30, 'l992 UNIT 2 Continugus Mode                                                            Hajch Mode Nuclides                      Unit       Quarter
* Quarter
* Quarter
* Quarter Released                                            1                            2                            1               2
                                                                                                                                         ~
: 1. Fis51on Gases Xe-131M                       Ci         0.00E+00                            0.00E+00            0.00E+00                 0.00E+00
                                                                                                                           ~
Xe-133                        Ci         0.00E+00                            0.00E400            0.00E400                 5.13E-03 Xe-133M                       Ci         0.00E+00                            0.00E+00            0.00E+00                 0.00E+00 Xe-135                        Ci         0.00E400                            0.00E+00            0.00E+00                 0.00E+00 Ar-41                         Ci         0.00E+00                            0.00E+00            0.00E400                 0.00E+00 Kr-SSM                        Ci         0.00E+00                            0.00E400            0.00E+00                 0.00E+00 Kr-87                         Ci         0.00E+00                            0.00E+00            0.00E+00                 0.00E+00
     'f0TAL FOR PERIOD             Ci         0.00E+00                            0.00E+00            0.00M400                 5.13E      2. Iodinen I-131                         Ci         0.00E+00                            0.00E+00            0.00E+00                 2.22E-07 I-132                         CI"        0.00E+00                            0.00E+00            0.00E+00                 0.00E+00 I-133                         Ci         0.00E+00                            0.00E+00            0.00E+00                 0.00E+00 TOTAL FOR PERIOD              Ci         0.00E400                            0.00E400            0.00E+00                 2.22E-07 C No Releases during this period.
l l-l l                                                                      41 l

TABLE 2-411 (Page 2 OF ?,)
VOGTLE ELECTRIC GENERATING PLANT SrMIANNUAL RADIOACTIVE EFFLUENT REPORT                               F GASEOUS EFFLUENTS - GROUND LEVEL January 1, 1992 through June 30, 1992 UNIT 2 ContiDuous flode                        11atch Mode Nuclides             Unit        Quarter *'   Quarter
* Quarter
* Quarter Iteleased                           1             2                    1            2
                                                                                          ~~
(              3. Farticulates**
Co-58                Ci          0.00E400     0.00E+00    0.00E+00              2.95E-05 r
l Co-60                Ci          0.00E400      0.00E+00   0.00E+00              0.00E+00 Mn-54                Ci          0.00E400      0.00E400   0.00E+00              0.00E+00 Hb-95                C1          De00E+00      0.00E+00   0.00E+00               0.00E+00 G-Alpha               ci         0.00E400      0.00E+00   0.00E+00               0.00E+00 11 - 3                Ci         0.00E+00      0.00E+00'  O.00E+00               8.85E-02 Kr-87                 Ci         0.00E+00      0.00E+00   0.00E+00               0.00E+00 TOTAL FOR PERIOD      Ci         0.00E+00      0.00E+00   0.00E+00               8.86E-02
* No Releases during this period.                                                          -
                ** Italf lives greater than 8 days.
- i E
m 42

l TABLE 2-4C (Page 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - GROUND LEVEL January 1, 1992 through June 30, 1992 SITE ContinuouD Mode                                 IlALCh Mode Nucliden                    Unit         Quarter
* Quarter
* Quarter
* Quarter Heleased                                          1                       2            1            2
: 1. Fission Gases Xe-131M                     Ci           0.00E+00                     0.00E+00    0.00E+00      0.00E+00 Xe-133                      C1           0.00E+00                     0.00E+00    0.00E400      5.13E-03 Xe-133M                     Ci           0.00E+00                     0.00E400    0.00E+00      0.00E+00
    -Xc-135                      C1           0.00E+00                     0.00E+00    0.00E+00      0.00E+00 Ar-41                       Ci           0.00E+00                     0.00E+00    0.00Et00      0.00E+00 Kr-OSM                      Ci           0.00E+00                     0.00E+00    0.00E+00      0.00E+00 Kr-87                       Ci           0.00E+00                     0.00E+00    0.00E+00      0.00E+00 TOTAL FOR PERIOD            Ci           0.00E400                     0.00E+00    0.00E+00      5.13E-03 l
l
: 2. Iodines I-131                       Ci           0.00E+00                     0.00E+00    0.00E+00      2.22E-07 I-132                       Ci           0.00E+00                     0.00E400    0.00E+00      0.00E+00 I-133                       Ci           0 . 0 0 E + li )             0.00E+00    0.00E+00      0.00E+00 TOTAL FOR PERIOD            Ci           0.00E+00                     0.00E400    0.00E+00      2.22E-07
       ~
C No Releases during this period.
1 l
l 43

TABLE 2-4C (Page 2 OF 2)
VOGTLE ELECTRIC GENERATING PLAlff 6"MIANNUAL RADIOACTIVE EFFLUElfr REPORT GASEOUS EFFLUENTS - GROUND LEVEL January 1, 1992 through June 30, 1992 SITE Continuous Mode                 Hatch tiode Nuclides             Unit      Quarter
* Quarter
* Quarter
* QLtrter Released                          1               2         1            2
: 3. Particulates**
Co-58                C1        0.00E+00       0.00E+00  0.00E+00       2.95E-05 Co-60                C1        0.00E400       0.00E+00  0.00E400       7.90E-06 Mn-54                Ci        0.00E+00       0.00E+00  0.00E+00       0.00E+00 Nb-95                C1        0.00E+00       0.00E+00  0.00E+'9       0.00E400 G-Alpha              Ci        0.00E400       0.00E+00  0.00E400       0.00E+00 11 - 3               Ci        0.00E+00       0.00E+00  0.00E400       8.85E-02 Kr-87                C1        0.00E+00       0.00E+00  0.00E+00       0.00E400 TOTAL FOR PERIOD     C1        0.00E+00       0.00E+00  0.00E+00      8.86E-02 0 !!o Releases during this period.
00 Half lives greater than 8 days.
44

4 TABLE 2-6A VOGTLU ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE HEPORT AIR DOSE dud TO NO11LE GAS RELEASES January 1, 1992 through June 30, 1992 UNIT 1
    -Type of                                                                                     Tech                          Units      Quarter              % of     Quarter   % of Rrdintion                                                                                    Spec                                        1                Tech        2      Tech Limit                                                        Limit              Limit Gamma                                                                                                5.0                 mrad      4.79E-05         9.68E-04      1.36E-04 L22X-D),   -
Beta                                                                                        10.0                         mrad      1.26E-04         1.26E-03      2.iSE-04 2.48E-03 e
Cumulative Doses Per Year (Year to Date) _ _ . .
Gamma                                                                                 10.0                                mrad      1.84E-04                               1 84E-Ql    .
peta                                                                                  20.0                                mrad      3.74E-04            _ _ _ .            1.87E_02 f

I A
TABLE 2-6B VOGTLE ELECTRIC GENERATING PLANT                                                                                      ,,
SEMIANNUAL RADIOACTIVE EFFLUluff RELEASE REPORT                                                                                        '
AIR DOSE DUE TO NOBLE GAS RELEASES January 1, 1992 through June 30, 1992 UNIT 2                                                      ,-
s
                                                                                                                                                         'd Type of         Tech          Units                                          Quarter                          % of     Quarter    % of Rcdiation       Spec                                                                                     3    Tech        4       Tech Limit                                                                                         Limit               Limit
        ~Ghmma           5.0          mrad                               1.74E-04                                   3.48E-03   1.67E-05 S.34E-04            2 Bcta          10.0           mrad                               3.43E ,04                                  3.43E-03   2.98E-05 2.98E-03 i
v Cumulative Doses Per Year (Yqpr to Date)                                                                                        ,
1 9arima         10.0           mrad                                                         1.91E-04                            1.91E-03 Beta           20.0        __ mrad                                                         3.73E-04                            .1.86E-03 h
46
                             - .        _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ - _ - -            -                  -______1

TAILLE 2-7A VOGTLE ELFCTRIC GENERATING PLANT SEMIANNUAL IGDIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM AND PARTICULATES IN GASEGUS RELEASES January 1, 1992 throogh June 30, 1992 UNIT 1 CMaldiVe DoSD_3Lur_ Quar.LGE-Orenn'            Tech            Unita          Quarter           % of                Qnarter                      % of Spec                               1             Tech                    2                        Toch Limit                                           Limit                                            Lirit
                                                                       ~
      'Djiie             7.5             mrenL _   1.70E-06       _ L 32J:-05             1.51E-06                    2.02fc_Q1 Elver               7.5            mtem      2.73E-04        3.64F-03               1.04E-04                    1.38E-Q1 T. Body            75 .
mrem. _2.73E-04        3.64E-03               1.03E-04                    1.38E-03 ThyrQld            7.5            mrem      2.74E-04        3.60c;-03            .1. 3 4 E- 0 4                1.79E-03 Kidr.ev            7.5            mrem      2.73E-04        3 64E-03               1.04E-04                    1.38E-03 surgg _            7.5             mrem      22 73E-04       j.64E-03              1 03E-04                     1.38E-03 GI-LLI             7_.5           mrem      2.73E-04      _3.64E-03                1.03E-04                    1.38E-QJ Qumulptive Doge Per Year Organ             Tech            Units       Year to Date                            % of Tech Spec Limit Spec Limit Done              15.0             mrem          3.29E-06                                   2.19E-05 Liver             15,0             mrrm          3.77E-04                                   2.51E-03 T. Body         15.0             mrem          3.76E-04                                   2.51E-03 Thyroid           15.0             mrem          4.08E-04                                   2.72E-03 Kidney            15.0             mrem          3.77E-04                                  _2.51E-03 Luna              15.0             mIra_-        3.76E-04                                   2.51E-03 GI-LLI            15.0             grem          3.76E-04                                   2.51E-03                            ,
47 f
                      .g   -
                                ,---                                             . , ,          -       w -. e,~.             -&, a

_ . _ _         _ . . _ _     m___.   . _ _ _ _ . . _ . _ _ _ .         __ _ _ ___         _   _ . _      _ _ _ . .m
         ,-                                                                                                                             J l
l
                                                       '"ABLE 2-7D VOGTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM AND PARTICULATES IN GASEOUS RELEASES January 1, 1992 through June 30, 1992 UsiIT 2 Cumulative Dose Per Ouarter Organ               Tech                Units        Quarter                       % of             Quarter                   % of
,                       Spec                                       1                   Tech                 2                    Tech Limit                                                         Limit                                  Limit Ege                   7.5               mrem       13 4E-04                    1. 71E- QL         2.66E_05          3.55E-04 Liver _               7 u5               mrer      2.60E-Q4                    3.47E-03           1.20E-04          1.60E-01 T , _Bgd v            7.5               mrem       2.6.0E-04                   3.47E-03           1.20E-0_4         1.60E-03 Thyroid               7.5                mrem      3.11E-04                    4.15E-03           1.24E-Q,4         1.65E-03        ;
Kidnev                7J                 mrem. 2.60E-04                    3.47E-03           1.20E-34          1.60E-03 Luna                  7.5               mrem       2.77E-04                    3.69E-03           1.23E-04          1. 6 4Fc_Q1 GI-LLI                 7.5               mrem      2.60E-04                    3.47E-03           1.20E_pi          1.60E-03 Citmg)litive Dose Per Year Organ              Tech               Units         Year to Date                                   % of Tech Spec Limit Spec Limit Bone                15.0                 mr.gm            1.61E-04                                      1.07E-03 Idver               15 u0                mrem             3.80E-04                                      2.53E-03 T. Body          15.0                 mreal            3.80E-04                                      2.53E-03 Thyroid             15.0                 mrem             4.35E-04                                      2.90E-03 Kidnev       _
15.0                 mrem             3.80E-04                                      2.53E-03 Luna                15.0                 mrem             4.00E-04                                      2.67E-03 GI-LLI              15.0                 mrem             3.80E-04                                      2.53E-03 48

   - . . - - -        _ ~ - - . -   -   . . . . . - -          . - - - . - - - -        . . - - - - -
1 TMILU 2-8 LOWER LIMITS OF DETECTION - GASEOUS SAMPLE ANALYSES VOGTLE ELECTRIC GENERATING PLANT January 1, 1992 - June 30, 1992 The values in this table represent a priori                 lov 'r limits of detection (LLD) which are typically achieved in laboratory analyses of gaseous radwaste samples.
RADIONUCLIDE                              LLD                        UNITS Kr-87                                   1.82E-08                     uC1/cc Kr-88                                   2.53E-08                     uCi/cc Xe-133                                  2.05E-08                     uCi/cc Xe-133m                                 8.63E-08                     uCi/cc Xe-135                                  7.12E-08                     uCi/cc Xe-138                                  1.05E-07                     uCi/cc 1-131                                   7.93E-15*                    uC1/cc Mn-54                                   3.94E-14*                    uCi/cc Fe-59                                   2.45E-14*                    uCi/cc Co-58                                   1.39E-14*                    uCi/cc Co-60                                   1.75E-14*                    uC1/cc "n-65                                   2.82E-14*                    uCi/cc Mo-99                                   9.57E-14*                    uC1/cc Cs-134                                  1.12E-14*                    uCi/cc Cs-137                                  8.71E-15*                    uCi/cc Co-141                                  8.62E-15*                    uCi/cc           -
Ce-144                                  2.77E-14                     uCi/cc Dr-89                                   1.00E-13                     uCi/cc Sr-90                                   1.00E-13                     uCi/cc H-3                                     9.00E-08                     uC1/cc Gross Alpha                             1.00E-13                     uCi/cc
* Based on an estimated sample volume of 5.7E+08 cc's.
l.
l l
l 49
~

3.0          Solid Waste 3.1          Regulatory Limits / Technical Specification The Technical Specifications presented in this section are for Unit 1 and Unit 2 and are stated in part.
3.1.1        Use of Solid Radioactive Waste Sys tem 3.11.3 Radioactive _ wastes shall be solidified or dowatered in accordance with the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.
3.1.2        Reporting Requirements 6.8.1.4 The Semiannual Radioactive Ef fluent Release Reports-shall include a summary of the quantities of radioactive liquid and gaseous offluents and solid waste-released from the units as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and                                                       i Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.            For-solid wastes, the format for Table 3 in-Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFP Part 61), type of container (e.g., LSA, Type A, Type B, Large Quantity) and SOLIDIFICATION agent or absorbent (e.g., cement urea formaldehyde).
3.1'. 3      Process Control Program (PCP) 6.12.2 Licensee - initiated changes'to the PCP r                                          Shall be- submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made.
For this reporting period, there was no revision.to the PCP.
                  = 3 . .!      -Solid Waste Data Regulatory Guide 1.21, Table 3 is found in this report as g                                Table 3-1 50

4.0 Changes to the Vogtle Electric Generating Plant ODCM 6.13.2 Technical Specification 6.13.2 requires, in part, that changes to the Offsite Dose Cr'culation Manual (ODCM) be reported to the Commission        a  the  ext Semiannual Effluent Release Report.
There have been no changes       to the Vogtle Electric Generating Plant ODCM during the reporting period.
3.12.1 The Radiological Environmental Monitoring Program shall be conducted as specified in Technical Specification Table 3.12.-1.
Table Notation (1) states in part:
It is recognized that, at times, it may not be possible or practicable to continue to obtain sampics of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions, if available, will be made within 30 days in the Radiological          Environmental Monitoring Program given in the ODCM.
Pursuant to specification 6.13, submit in the next Semiannual    Radioactive    Effluent   Release     Report documentation for a change in the ODCM including a revised figure (s) and Table for the ODCM reflecting the new location (s), if any, with supporting information       -
ident.ifying the cause of tne unavailability of samples 2or the pathway and justifying the selection of the new location (s) for obtaining samples, or the unavailability of suitable new locations.
3.12.2 states in part A land Use Census shall be conducted.   . . .
The Action Statement for this requirement states in part:
: a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the value currently being calculated in    specification     4.11.2.3,    pursuant      to specification 6.8.1.4, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report.
51

4 4.1                Changes in the Radiological Environmental Monitoring Program                                                                                                                                    )
i' For this semiannual period, there has been no change to the Radiological Environmental Monitoring Program.
I                  5.0                Doses to Members of the Public Inside the Site Boundary 6.8.1.4 states in part:
2 This same report shall also include assessment of the
:"                                     radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their-1 activities inside the Site Boundary (Figure 5.1-1 of the
.                                      Technical Specifications) during the report period. All assumptions used in making these assessments,                                                               i.e.,                          l 2                                      specific _ activity, exposure time, and location shall be-included in these reports.
The locations of concern within the site boundary are the Visitors Center and Plant Wilson. The activities at the Visitor Center consists of the cecasional attendance at inectings and/or short visits for informational purposes.
l' The        activity            at -Plant                        Wilson       censists           of      regular employment.             There will be no radiation dose at these locations -due                            to         radioactive                liquid          effluents.
Delineated in Table 5-1 for eacn of these locations are                                                                                   -
the values- of the basic data assumed in the dose assessment due to radioactive gaseous effluents. Listed                                                                                   j in this table are:                               The distance and directions from a
,                                      point' midway between the center of Unit 1 and the Unit ?                                                                                 !
;                                      reactors;~the dispersion and deposition factors for any releases from the plant vent (mixed mode) and from the turbine building (ground level); and the estimated                                                                                        *
[                                     maximum . occupancy ' factor for an individual and the assumed age group of this individual.
                                      ' lot listed in Table 5-1 is tne source term.                                                      Listed in Tables 2-4a and 2-4b for the ground level releases and in i                                     Table 2-3a and 2-3b for the mixed mode releases are the noble - gases, radiciodines, and particulates with half j                                      lives greater than eight-days; these are tabulated by radionuclidaLand by quarter.                                             The tritium releases in units of curies-were as follows:
QUARTER                                                              1                                  2 Mixed Mode                                                       8.77E+01                        4.27E+01 h                                     The maximum doses in units of mrem accumulated by an C                                     individual MEMBER OF THE PUBLIC due to their activities l,                                     inside the site boundary during the reporting period were
;-                                    assessed to be as follows:
i l
52
    . . ,     &.1 ,  _,y_,.m,-y m ,.._,.--,.M___,_.~. .
                                                        , , . , , . , , , , . . . - . , .,m  ,,3ym,.,      ~,,m   ,.._.d.,,,...,w--h,,    .gm   ,._w,.y ., , , , . , . _ - . , -

          -.i .
VISITORS CEliTER PL ANT WILSOli Total Body   .
2.17E-07      2.66E-05 (direct radiation from plume)
Maximum Organ (Thyroid - Inhalation and
                        -ground-plane)               1.97E-06       2.85E-04 u
N 53 1

4' TABLE 3-1 (Page 1 of 2)
VOGTLE ELECTRIC GENERATING PLANT EFFLUENT hND WASTE DISPOSAL SEMIANNUAL REPORT SOLID AND IRRADIATED FUEL SIIIPMENTS January 1, 1992 through June 30, 1992 Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)
: 1.      Type of Waste                                                                          Unit            6 month     Est. Total Period        Error %
: a.       Spent resins, filter sludges                                                           m' ~           5.34E+01 Evaporator bottom, etc.                                                                Ci             9.11E+02     1.00E+01      -
: b.       Dry compressible waste,                                                                m3             3.2SE+01 Contaminated equf.pment, etc.                                                          C1              1.26E+01    4.00E+01
: c.       Irradiated components,                                                                 m3 Control rod, etc.                                                                      Ci             NONE            4/A
: d.       Other (describe) oily trash                                                            m3 Speedi-dry mix equipment, etc.                                                         Ci              NONE           N/A Solidified oil, CRD filters 2, Estimate of Maior Nuclide Composition (Ev type of waste)
ISOTOPE                                                                              PERCENT                        CURIES      ,,_
: a. Ni-63                                                                                  5.35E+01                     4.87E+02 Fe-55                                                                                1.91E+01                     1.74E+02 Co-60                                                                                1.42E+01                     1.29E+02          '-
All Others                                                                           1.30E+01                     1.18E+02
: b. Fe-55                                                                                  1.65E+01                     2.09E+00 co-58                                                                               5.96E+01                     7.54E+00 NI-63                                                                               1.20E+01                     1.51E+00 All Others                                                                          1.17E+01                     1.49E+00 54

                                                                                                                                                                                             'A11LE 3-1 (Page 2 of 2)
VOGTLE ELECTRIC GENERATING PLANT                                           i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT                                     !
SOLID AND IRRADIATED FUEL SNIPMIGTS                                         .
January 1, 1992 through June 30, 1992 Isotopy                                                                                  Percent                       curies
: c.                                   None shippsd this period
: d.                                   None shipped this opJiod                                                                                                                    __
: 3.                                   Solid Waste Disposition                                                                                                                                                                              :
lAlptber of ShiomeDIR                                                                                                     Mode of Tru. DER 9I_tilliOD                DeatinatiRD 6                                  Tractor / Trailer / Shielded Cask            Chem Nuclear Barnwell, SC 9                                  Tractor / Trailer                            Scientific Ecology Oakridge, TN 7                                  Tractor / Trailer                            Chem Nuclear Barnwell, SC
: 4.                                   Irradiated Fuel Shipments (Disposition)
Num12Cr of Shipments                                                                                                      11 ode of Tr,4ngportpliga                  ngstinption 0                                                               N/A                          N/A Additional Information Required by Tech Specs:
Shipment                                                                                                                                            Waste                  Type                  Shipping       Solidification Agent No. -                                                                                                                             Class                  Container               Class RWS-92-001                                                                                                                                           A Unstable             Strong Tight             LSA                   N/A RWS-92 002                                                                                                                                           A stable               Type A                   LSA                   N/A RWS-92-003                                                                                                                                           A stable               Type A                   LSA                   N/A RWS-92-004                                                                                                                                           C Unstable             Type B               Radioactive               N/A Material, n.o.s.
HWS-92-005                                                                                                                                           A Unstable             Strong Tight             LSA                   N/A RWS-92-006                                                                                                                                           A Stable               Type A                   LSA                   N/A RVRS-92-001                                                                                                                                          A Unstable             Strong Tight             LSA                   N/A RVRS-92-002                                                                                                                                           A Unstable            Strong Tight             LSA                   N/A RVRS-92-003                                                                                                                                          A Unstable             Strong Tight             LSA                   N/A RVRS-92-004                                                                                                                                          A Unstable             Strong Tight             LSA                   N/A RVRS-92-005                                                                                                                                          2 Unstable             Strong Tight             LSA                   N/A RVRS-92-006                                                                                                                                          A Unstable             Strong Tight             LSA                   N/A RVRS-92-007                                                                                                                                          A Unstable             Strong Tight             LSA                   N/A RVRS-92-008                                                                                                                                          A Unstable             Strong Tight             LSA                   N/A RVRS 009                                                                                                                                         A Unstable             Strong Tight             LSA                   N/A RVRS-92-010                                                                                                                                          A Unstable             Strong Tight             Exempt                N/A RVRS-92-011                                                                                                                                          A Unstable             Strong Tight             Exempt                N/A RVRS-92-012                                                                                                                                          A Unstable             Strong Tigh';            Exempt                N/A RVRS-92-013                                                                                                                                          A Unstable             Strong Tight             Exempt                N/A
                 .RVRS-92-014                                                                                                                                               A Unstable             Strorn Tight             Exempt                N/A RVRS-92-015                                                                                                                                          A Unstable             Strong Tight             Exempt                N/A RVRS-92-016                                                                                                                                         A Unstable              Strong Tight             Exempt                N/A
                  -NOTES:                                                                          Vogtle Electric Generating Plant performed thirteen (13) shipments to Chem Nuclear, Barnwell, 50 and nine (9) shipments to Scientific Ecology Group, Inc. in Oak Ridge, TN.                                                                                                                                             During this reporting period, the waste volume und activity on this report reflects only that volume of waste and activity which was processed and disposed of as radioactive waste at Chem Nuclear Systems, Inc.,
Barnwell Waste Management Facility, or by Scientific Ecology Group, Inc., during this reporting period.
l l
55 l-                                                                                                                                                                                              --            __      .  .          .--               - _ . - - -

p*
                                          -TABLE 5-1 BASIC uATA ASSUMED IN DOSE ASSESSMENTS TO MEMBER OF TIIE PUBLIC January 1, 1992 through June 30, 1992 ITEM                        VISITOR CENTER                     PLANT WILSON Dictance (meters)                 447                                1420 Sector                             SE                                 ESE X/Q (sec/m3)           (1)      5.93E-06                          9.45E-07 Depleted X/Q (sec/m3) (1)       5.58E-06                          8.34E-07 D/Q (m-2)              (1)      2.28E-08                          4.20E-09 X/Q (sec/m3)           (2)      7.12E-07                          1.76E-07 Depleted X/Q (sec/m3) (2)       6.74E-07                          1.59E-07 D/Q (m-2)              (2)      5.77E-09                          2.07E-09 Occupancy Factor              0.00046 (4 hr/yr)                0.228 (2000 hr/yr)
Agn Group                       CHILD                             ADULT (1)-Ground Level Release (2) Mixed Mode Release VISITOR CENTER                       PLANT WILSON Quarter 1    Quarter 2       TOTAL     Quarter 1   Quarter 2      TOTAL mrem        mrem          mrem        mrem         mrem         mrem TOTAL BODY 1.37E-07     7.98E-08      2.17E-07   1.68E-05   9.78E-06      2.66E-05 ORGAN DOSE Bone        3.63E-07   2.08E-08      3.84E-07    6.44E-05   1.30E-05      7.76E-05 Liver       1.34E-06   5.01E-07      1.84E-06    1.92E-04   7.59E-05      2.68E-04 TBody       1.34E-06   5.01E-07      1.84E-06    1.92E-04   7.58E-05      2.68E-04 Thyroid     1.46E-06   5.07E-07      1.97E-06    2.03E-04   8.22E-05      2.85E-04 Kidney     _1.34E-06   5.01E-07      1.84E-06    1.92E-04 s.59E-05     2.68E-04 Lung        1.38E-06   4.97E-07      1.88E-06    1.97E-04   7.66E-05      2.74E-04 GI          1.34E-06   5.01E-07      1.84E-06    1.93E-04   7.59E-05      2.69E-04 l
l l
56

  .         ,.        -        .-   --~.-.       -  . . ~ .   - - .      . . - - ,     -.- - . - . -    .--- -
j,, N -
6.0      Najor changes to Liquid,               Gaseous or Solid Radwaste Treatment Systems 6.8.1.4 states in part:
The Semiannual Radioactive Ef fluent Release Report shall include . . . _ . any major change to liquid,. gaseous, or                            ,
solid    radwaste         treatment        systems          pursuant        to        !
Specification 6.14.
6.1      Gaseous Radwaate System There were no major changes to the gaseous radwaste
,                        system in the first half of 1992.
.                        Solid Radwaste System There were-no major changes to the solid _radwaste system l_                       in the first half of 1992.
.                        Liquid Radwaste System.                                                               ,
There were no major changes to the Liquid Radwaste Treatment System in the first half of 1992.
7.0       Meteorological Data 6.-8.1.4 states in part:
The Semiannual Radioactive Effluent Release Report to be submitted . within 60 days after January 1 of each year
                        .shall include an annual summary of hourly meterological data collected over the previous year.                        This. ~ annual summary may be either in the form of-an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured),
or in-the form-of joint frequency-distributions of wind speed, wind direction and atmospheric-stability.
In lieu of submission - with Semiannual Radioactive Effluent Release Report,_the licensee has' retained __this summary of required meteorological data on site in a file that:shall be provided to the.NRC upon request.
: 8. 0 -    Inoperable        Liquid-    or'   Gaseous    Effluent           Monitoring Instrumentation
                       '6.8.1.4 states in_part that:
The Semiannual Radioactive Ef fluent Relf 'se Reports shall also include the following: an explanat2on as to why the inoperability of liquid or gaseous effluent monitoring 57-

a '' v y
l instrumentation' was not corrected within         the   time
                    -specified       in  Specifications   3.3.3.9  or   3.3'.3.10 respectively.
Inoperable Tech - Spec monitors are tracked on Limiting         l Condition of Operation (LCO) Forms.          The operators declare equipment operable'and inoperable and monitors are considered inoperable if there are open LCO's for that monitor.
8.1.1  The LCO's initiated do not have to be reported for this report period since the LCO's initiated were closed before 30 day period.
9.0    Tanks Exceeding Curie Content Limits L
6.8.1.4' states in part:
!                    The Semiannual Radiaoctive Effluent Release Reports shall       I also include the following, "and description of the events -_ leading to liquid holdup tanks cr gas storage
                    . tanks exceeding the limits.of specification 3.11.1.4 or 3 .11. 2 . 6 ', respectively"..
There were no outside temporary liquid tanks for radioactive liquids during this reporting period.        The    j radioactive material contained in each wcste gas decay          1 tank did not exceed 2E5 curies of noble gases (considered as Xe-133 equivalent).
l l-l-
i 58
_.                         .}}