ML20206D654
| ML20206D654 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/31/1998 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20206D644 | List: |
| References | |
| NUDOCS 9905040182 | |
| Download: ML20206D654 (81) | |
Text
r- w III VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 1998 ANNUAL REPORT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l
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VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 & 2 '
1998 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l
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VOGTLE ELECTRIC GENERATING PLANT 1998 ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES SECTION TITLE PAGE 1.0 Liquid Effluents 8 1.1 Regulatory Limits /ODCM 8 1.1.1 Concentration Limits 8 ,
I 1.1.2 Dose Limits 8
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1.2 Effluent Concentration Limit 8 1.3 Measurements and Approximations of Total 9 i Radioactivity 1.4 Liquid Effluent Release Data 10 1.4.1 Tables 10 1.4.2 Total Error Measurement 10 1.5 Radiologicalimpact on Man Due to Liquid Releases 12 1.6 Abnormal Releases 12 l
1.7 River Flow 12 2.0 Gaseous Effluents 34 2.1 Regulatory Limits /ODCM 34 2.1.1 Dose Rate Limit 34
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SECTION TITLE PAGE 2.1.2 Air Dose Due to Noble Gas 34 2.1.3 Dose to Any Organ 34 2.1.4 Total Fuel Cycle Dose Commitment (40CFR190) 35 2.2 Release Points of Gaseous Effluents 35 2.3 Sample Collection and Analysis 35 2.4 Total Quantities of Radioactivity, Dose Rates 36 and Cumulative Doses 2.4.1 Fission and Activation Gas 36 2.4.2 Radiolodines, Tritium and Particulate Releases 36 2.4.3 Gross Alpha Release 37 .
t 2.5 Gaseous Effluent Release Data 37 2.5.1 Methodology 37 2.5.2 Gaseous Batch Data 39 2.6 Radiological Impact Due to Gaseous Releases 39 2.7 Abnormal Releases 39 3.0 Solid Waste 67 3.1 Regulatory Limits /ODCM 67 3.1.1 Use of Solid Radioactive Waste System 67 3.1.2 Reporting Requirements 67 3.2 Solid Waste Data 67 2
SECTION TITLE PAGE 4.0 The Vogtle Electric Generating Plant Offsite 67 Dose Calculation Manual (ODCM) 4.1 Changes to the Vogtle Electric Generating Plant 67 ODCM .
I 4.2 The Radiological Environmental Monitoring 68 Proaram l
4.3 Changes in the Radiological Environmental 68 Monitoring Program j I
5.0 Doses to Members of the Public Inside The 69 Site Boundary >
6.0 Major Changes to the Liquid, Gaseous and 78 .
Solid Radwaste Treatment Systems 1 7.0 Meteorological Data 78 l 8.0 Program Deviations 79 i 8.1 Inoperable Liquid or Gaseous Effluent 79 Monitoring Instrumentation '
8.2 Tanks Exceeding Curie Content Limits 79 l
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VOGTLE ELECTRIC GENERATING PLANT ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES TABLE LIST OF TABLES PAGE 1-2A Liquid Effluents - Summation of All Releases 13 Unit 1 ,
1-2AA Liquid Effluents - Summation of All Releases 14 Unit 1 1-2B Liquid Effluents - Summation of All Releases 15 Unit 2 . <
l 1-2BB Liquid Effluents - Summation of All Releases 16 Unit 2 1-2C Liquid Effluents - Summation of All Releases 17 Site 1-2CC Liquid Effluents - Summation of All Releases 18 Site 1-3A Liquid Effluents - Unit 1 19 1-3AA Liquid Effluents - Unit 1 20 1-3B - Liquid Effluents - Unit 2 21 1-3BB Liquid Effluents - Unit 2 22 1-3C Liquid Effluents - Site 23 1-3CC Liquid Effluents - Site 24 4
TABLE LIST OF TABLES PAGE 1-4A Individuals Doses Due to Liquid Releases 25 Unit 1 1-4AA Individuals Doses Due to Liquid Releases 26 Unit 1 1-4B Individuals Doses Due to Liquid Releases 27 Unit 2 1-4BB Individuals Doses Due to Liquid Releases 28 Unit 2 1-5 Minimum Detectable Concentration - 29 Liquid Sample Analysis 1-6A Batch Release Summary of All Releases 30 Unit 1 -
1-6AA Batch Release Summary of All Releases 31 Unit 1 1-6B Batch Release Summary of All Releases 32 )
Unit 2 ]
1-6BB Batch Release Summary of All Releases 33 Unit 2 2-2A Alrborne Effluents - Summation of All 40 Releases - Unit 1 2-2AA Airborne Effluents - Summation of All 41 Releases - Unit 1 2-28 Airborne Effluents - Summation of All 42 Releases -Unit 2 5
TABLE LIST OF TABLES PAGE 2-2BB Airborne Effluents - Summation of All 43 Releases -Unit 2 2-2C Airborne Effluents - Summation of All 44 Releases - Site 2-2CC Airborne Effluents - Summation of All 45 Releases - Site 2-3A Gaseous Effluents - Mixed Mode Releases 46 Unit 1 2-3AA Gaseous Effluents - Mixed Mode Releases 47 Unit 1 2-3B Gaseous Effluents - Mixed Mode Releases 48 Unit 2 2-3BB Gaseous Effluents - Mixed Mode Releases 49 Unit 2 2-3C Gaseous Effluents - Mixed Mode Releases 50 Site 2-3CC Gaseous Effluents - Mixed Mode Releases 51 Site 2-4A Gaseous Effluents - Ground Level Release 52 Unit 1 2-4AA Gaseous Effluents - Ground Level Release 53 Unit 1 1
2-48 Gaseous Effluents - Ground Level Release 54 l Unit 2 2-4BB Gaseous Effluents - Ground Level Re'4ase 55 Unit 2 l
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TABLE LIST OF TABLES PAGE 2-4C Gaseous Effluents - Ground Level Release 56 Site 2-4CC Gaseous Effluents - Ground Level Release 57 Site 2-6A Air Doses Due to Noble Gases - Unit 1 58 2-6AA Air Doses Due to Noble Gases - Unit 1 59 2-6B Air Doses Due to Noble Gases - Unit 2 60 2-6BB Air Doses Due to Noble Gases - Unit 2 61 l
l 2-7A Individual Doses Due to Radiolodines, 62 Tritium, and Particulates in Gaseous Releases - Unit 1 .
2-7AA Individual Doses Due to Radiolodines, 63 Tritium, and Particulates in Gaseous Releases - Unit 1 2-7B Individual Doses Due to Radiolodines, 64 Tritium, and Particulates in Gaseous Releases - Unit 2 2-78B Individual Doses Due to Radiolodines, 65 Tritium, anci Particulates in Gaseous Releases - Unit 2 2-8 Minimum Detectable Concentration - 66 Gaseous Sample Analyses 3-1 Solid Waste and Irradiated Fuel Shipments 70 4-1 Dose to A Member of the Public Due to Activities 77 Inside The Site Boundary 7
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1.0 - Liquid Effluents 1.1 Regulatory Limits /ODCM 1.1.1 Concentration Limits in accordance with Technical Specifications 5.5.4.b, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited at all times to ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1 E-04 Cl/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 as follows:
- 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 Effluent Concentration Limit (ECL)
ECL values used for determining the allowable liquid radwaste release rates and concentrations for the principal gamma emitters,1-131, tritium, Sr-89, Sr 90 and Fe 55 are taken from 10 CFR Part 20, Appendix B, Table ll, Column 2. A tolerance factor of up to 10 is utilized to allow flexibility in establishing practical monitor set points which can accommodate effluent releases at concentrations higher than the ECL values stated in 10 CFR 20, Appendix B, Table 11, Column 2.
For dissolved or entrained noble gases in liquid radwaste, the ECL is 1 E-04 Cl/ml total activity. 3 For gross alpha in liquid radwaste, the ECL is 2.0E-09 Ci/ml.
For all the above radionuclides or categories of radioactivity, the overall ECL i fraction is determined in accordance with 10 CFR Part 20, Appendix B. !
The method utilizing the ECL fraction to determine release rates and liquid radwaste effluent radiation monitor set points is described in Subsection 1.3 of this report.
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1.3 Measurements and Approximations of Total Radioactivity Prior to the release of any tank containing liquid radwaste, and following the required recirculations, samples are collected and analyzed in accordance with the Offsite Dose Calculation Manual (ODCM) Table 2-3 " Radioactive Liquid Waste Sampling Program".
A sample from each tank which is planned for release is analyzed for principal gamma emitters,1-131, and dissolved and entrained noble gases by gamma spectroscopy.
Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample taken from the tanks which are released. Liquid radwaste sample analyses are performed as follows:
MEASUREMENT FREQUENCY METHOD
- 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 Gamma isotopic measurements are performed using germanium detectors with a resolution of 2.1 kev or lower. A liquid radwaste sample is typically counted for 5400 seconds. A peak search of the resulting gamma ray spectrum is performed by the computer system. Energy and net count data for all significant peaks are determined, and a quantitative reduction or MDC calculation is performed. This ensures that the MDC's are met for the nuclides specified in ODCM Chapter 10 (i.e., Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs 134, Cs 137, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present.
Tritium, Gross Alpha, Sr-89, Sr-90 and Fe-55 are_ in some cases, analyzed offsite.
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The radionuclide concentrations determined by gamma spectroscopic analysis of a sample taken from a tank planned for release and the most current analysis results available for tritium, gross alpha, Sr 89, Sr-90 and Fe 55 are used, along with the corresponding ECL values to determine the ECL fraction. This ECL fraction is used, with appropriate safety factors, tolerance factors, and the minimum assured dilution stream flow to calculate maximum permissible release rates and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the Offsite Dose Calculation Manual (ODCM) 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 setpoint 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 wamings will be displayed on the computer screen. If the release is permissible, it is approved by the Chemistry Department and sent to the Operations Department for approval and release. When the release is completed, the necessary data from the release (i.e., release volume, etc.)~are provided by 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 the actual release rates, release concentrations and quantities, actual dilution flow, and calculated doses to an individual.
1.4 Liquid Effluent Release Data 1.4.1 Tables Regulatory Guide 1.21 Tables 2A,28, and 2-C are found in this report as Tables 1-2A,1-2AA,1-28,1-288,1-2-C, and 1-2-CC. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all four quarters.
1.4.2 Total Error Measurement The total or maximum error associated with the effluent measurement includes the cumulative errors resulting from the total operation of sampling and measurement. Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error is not suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid effluents,
- s. Fission and activation total release was calculated from sample analysis 10
I 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 %
- b. Total Tritium release was calculated from sample analysis results and release point volumes.
I Sampling and statistical errors 10% l Counting equipment calibration 10% i Tank volumes and system flow rate 20 %
TOTAL ERROR 40 %
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- c. Dissolved and entrained gases were calculated from sample analysis results and release point volumes.
Sampling and statistical error 20 %
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l Counting equipment calibration 10%
Tank volumes and system flow rate 20 %
TOTAL ERROR 50 %
- d. Gross alpha radioactivity w,'s calculated from sample analysis results and release point volumes.
Sampling and statistical error 10% j Counting Equipment calibration 10%
Tank volumes and system flowrates 20 % ;
Compositing sample error 5%
TOTAL ERROR 45%
- e. Volume of waste prior to dilution was calculated from level Indicators on the tanks and pump discharge flow rates and times.
Level Indicator error 10%
Operator Interpretation of gauge 10%
TOTAL ERROR 20 %
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- f. Volume of dilution water used was calculated from flow rate indicators and pump discharge flow rates and times.
Flow rate indicator error 10%
Operatorinterpretation 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,1-4AA for Unit 1 and 1-48,1-4BB for Unit 2, for all four cuarters.
1.6 Abnormal Releases 1.6.1 There were no abnormal releases for this reporting period.
1.7 River Flow The average flow rate of the Savannah River at Augusta for the Annual Effluent Report period was obtained from the U.S. Army Corps of Engineers Savannah District Historic Data web page (http://www.sas.usace. army.millen/en h/en-ha/adis.html).
The average flow rate for 1998 was 13865 cubic feet per sec.
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F TABLE 12 A l 1
SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 -
ALL LIQUID EFFLUENTS UNIT : 1 STARTING : 1-JAN 1998 ENDING : 30-JUN 1998 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 7.34E-02 9.22E-02 40 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION UCi/ML 3.36E-07 4.40E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM -
- 1. TOTAL RELEASE CURIES 1.18E+02 1.26E+02 40
' 2. AVERAGE DILUTED CONCENTRATION uCi/ML 5.40E-04 6.01E-04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1.24E-03 2.38E-05 50
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 5.67E-09 1.14E-10 DURING PERIOD -
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 2.15E-06 3.47E-06 45 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 5.82E+05 5.99E+05 20 F. VOLUME OF DILUTION WATER USED LITRE 2.18E+08 2.09E+08 20 l
- Apphcable limits are expressed in terms of Dose. SeeTable 14A of this report 13
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TABLE 12AA SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1998 ALL LlOUlD EFFLUENTS UNIT : 1 STARTING : 1-JUL-1998 ENDING : 31 DEC-1998 TYPE OF EFFLUENT UNITS QUARTER 3 OUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 1.16E-02 2.02E-02 40 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 8.50E-08 8.91 E-08 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM
- 1. TOTAL RELEASE CURIES 1.64E+02 2.32E+02 40 -
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 1.20E-03 1.02E-03 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 5.74E-04 1.11 E-03 50
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 4.21 E-09 4.90E-09
. DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT % l D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 7.40E-07 2.48E-06 45 j l
E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 4.59E+05 6.10E+05 20 F, VOLUME OF DILUTION WATER USED LITRE 1.36E+08 2.26E+08 20 l
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TABLE 128 SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RAD:OACTIVE EFFLUENT RELEASE REPORT 1998 ALL LIQUID EFFLUENTS UNIT : 2 STARTING : 1-JAN-1998 ENDING : 30-JUN 1998 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 2.10E-01 9.60E-02 40 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCl/ML 3.38E-07 2.87E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM ,
- 1. TOTAL RELEASE CURIES 4.20E+02 2.13E+02 40
- 2. AVERAGE DILUTED CONCENTRATION uCl/ML 6.76E-04 6.36E-04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 4.46E-03 7.71 E-04 50
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 7.18E-09 2.30E-09 {
DURING PERIOD l i
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY l
- 1. TOTAL RELEASE CURIES 0.00E+00 6.11 E-06 45 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 1.57E+06 8.93E+05 20 F. VOLUME OF DILUTION WATER USED LITRE 6.20E+08 3.34E+08 20
- Applicable limits are expressed in terms of Dose. See Table 1-48 of this report 15
TABLE 12BB SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1998 ALL LIQUID EFFLUENTS UNIT : 2 STARTING : 1-JUL 1998 ENDING : 31-DEC-1998 TYPE OF EFFLUENT UNITS QUARTER 3 OUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 1.04E-02 3.60E-03 40 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 6.48E-08 6.61 E-08 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM .
- 1. TOTAL RELEASE CURIES 3.10E+02 8.59E+01 40
- 2. AVERAGE DILUTED CONCENTRATION uCl/ML 1.93E-03 1.58E-03 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1.35E-03 3.23E-06 50
- 2. AVERAGE DILUTED CONCENTRATION uCl/ML 8.41 E-09 5.93E 11 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES - 7.37E-06 5.35E-06 45 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 4.46E+05 1.68E+05 20 F. VOLUME OF DILUTION WATER USED LITRE 1.60E+08 5.43E+07 20
- Applicable limits are expressed in terms of Dose. See Table 1-4BB of this report 16
TABLE 1-2C SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1998 ALL LIQUID EFFLUENTS SITE STARTING : 1-JAN-1998 ENDING : 30-JUN-1998 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
' A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 2.83E-01 1.88E-01 40 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCl/ML 3.37E-07 3.46E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM .
- 1. TOTAL RELEASE CURIES 5.38E+02 3.39E+02 40
- 2. AVERAGE DILUTED CONCENTRATION uCL/ML 6.40E-04 6.23E-04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 5.70E-03 7.95E-04 50
- 2. AVERAGE DlLUTED CONCENTRATION uCi/ML 6.78E-09 1.46E-09 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 2.15E-06 9.58E-06 45 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 2.15E+06 1.49E+06 20 F. VOLUME OF DILUTION WATER USED . LITRE 8.38E+08 5.43E+08 20
- Applicable limits are expressed in terms of Dose. See Tab 6e 1-4A and 1-4B of this report 17
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TABLE 12CC l SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT '
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1998 ALL LIQUID EFFLUENTS !
SITE STARTING : 1-JUL-1998 ENDING : 31-DEC-1998 TYPE OF EFFLUENT UNITS QUARTER 3 OUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS l l
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 2.20E-02 2.38E-02 40 TRITlUM GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 7.41 E-08 8.47E-08 )
DURING PERIOD l
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM
- 1. TOTAL RELEASE CURIES 4.74E+02 3.18E+02 40 ,
- 2. AVERAGE DILUTED CONCENTRATION UCi/ML 1.60E-03 1.13E-03 DURING PERIOD l
- 3. PERCENTAGE OF APPLICABLE LIMIT % l l
C. DISSOLVED AND ENTRAINED GASES I
- 1. TOTAL RELEASE CURIES 1.92E-03 1.11 E-03 50
- 2. AVERAGE DILUTED CONCENTRATION uCVML 6.48E-09 3.96E-09 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 8.11 E-06 7.83E-06 45 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 9.05E+05 7.78E+05 20 F. VOLUME OF DILUTION WATER USED LITRE 2.96E+08 2.80E+08 20
- Applicable firMts are expressed in terms of Dose. See Table 14AA and 1488 of this report 18
TABLE 13A Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUANT RELEASE REPORT-1998 Liquid Effluents Starting: 1-Jan-1998 Ending: 30-Jun-1998 UNIT : 1 CONTINUOUS BATCH NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 H-3 CURIES 0.00E+00 0.00E+00 1.18E+02 1.26E+02 FISSION & ACTIVATION PRODUCTS:
Ag 110M CURIES 0.00E+00 0.00E+00 8.62E-05 1.35E-04 Co-57 CURIES 0.00E+00 0.00E+00 4.32E-05 4.20E-06 Co-58 CURIES 0.00E+00 0.00E+00 2.38E-03 1.90E-03 Co-60 CURIES 0.00E+00 0.00E+00 1.62E-02 7.91E-03 Cr-51 CURIES 0.00E+00 0.00E+00 2.01E-03 2.37E-03 Cs 134 CURIES 0.00E+00 0.00E+00 9.59E-04 1.34E-03 Cs-137 CURIES 0.00E+00 0.00E+00 8.99E-04 1.25E-03 Fe-55 CURIES 0.00E+00 0.00E+00 1.83E-02 4.38E 02 1131 CURIES 0.00E+00 0.00E+00 9.67E-05 3.11 E-05 l132 CURIES 0.00E+00 0.00E+00 2.53E 04 0.00E+00 1-133 CURIES 0.00E+00 0.00E+00 4.77E 05 0.00E+00
- La-140 CURIES 0.00E+00 0.00E+00 2.27E-05 7.18E-08 Mn-54 CURIES 0.00E+00 0.00E+00 2.77E-03 1.30E-03 Nb 95 CURIES . 0.00E+00 0.00E+00 5.17E-04 2.72E-04 Nb-97 CURIES O.00E+00 0.00E+00 8.40E 05 2.36E-04 Sb 124 CURIES 0.00E+00 0.00E+00 5.74E 04 1.05E-03 Sb 125 CURIES 0.00E+00 0.00E+00 2.68E-02 2.95E-02 CURIES 0.00E+00 0.00E+00 2.72E-04 1.85E-04 Sr 89 CURIES 0.00E+00 0.00E+00 2.71E-05 1.01E-05 Sr 90 CURIES 0.00E+00 0.00E+00 1.55E-05 0.00E+00 Sr-92 CURIES 0.00E+00 0.00E+00 1.35E 06 0.00E+00 Tc 99M CURIES 0.00E+00 0.00E+00 6.36E-04 0.00E+00 Te-125M .
CURIES 0.00E+00 0.00E+00 0.00E+00 7.82E-04 Te-129M CURIES 0.00E+00 0.00E+00 2.59E-04 0.00E+00 l Te-132 l CURIES 0.00E+00 0.00E+00 2.61E-05 0.00E+00 Y-92 0.00E+00 0.00E+00 1.87E-04 ' 1.15E-04 Zr-95 CURIES 0.00E+00 0.00E+00 7.34E42 9.22E-02 TOTALS CURIES DISSOLVED AND ENTRAINED GASES:
CURIES 0.00E+00 0.00E+00 7.17E-04 0.00E+00 Kr-85 0.00E+00 0.00E+00 1.99E-04 1.52E-06 Xe-133 - CURIES 0.00E+00 0.00E+00 3.28E-04 0.00E+00 Xe-135 CURIES 0.00E+00 0.00E+00 0.00E+00 2.23E-05 Xe-135M CURIES 0.00E+00 0.00E+00 1,24E 43 2.38E-05 TOTALS CURIES 19
r-TABLE 13AA Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1998 Liquid Effluents l
Starting : 1-Jul-1998 Ending : 31 Dec-1998 UNIT : 1 CONTINUOUS BATCH NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 H-3 CURIES 0.00E+00 0.00E+00 1.64E+02 2.32E+02 f
FISSION & ACTIVATION PRODUCTS:
Ag 1'10M CURIES 0.00E+00 0.00E+00 6.88E-05 0.00E+00 Co CURIES 0.00E+00 0.00E+00 0.00E+00 3.37E-06 '
Co-58 CURIES 0.00E+00 0.00E+00 4.30E-04 4.78E-04 Co-60 CURIES 0.00E+00 0.00E+00 4.48E-03 4.82E-03 Cr-51 CURIES 0.00E+00 0.00E+00 5.98E-05 4.88E-04 Cs-134 CURIES 0.00E+00 0.00E+00 6.20E-04 9.78E-04 Cs 137 CURIES 0.00E+00 0.00E+00 6.29E-04 1.04E-03 Fe-55 CURIES 0.00E+00 0.00E+00 2.51 E-03 5.46E-03 Fe-59 CURIES 0.00E+00 0.00E+00 0.00E+00 4.70E-05 l131 CURIES 0.00E+00 0.00E+00 1.17E-05 7.87E-06 l132 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-133 CURIES 0.00E+00 0.00E+00 3.18E-06 0.00E+00 La 140 CURIES 0.00E+00 0.00E+00 1.32E-05 0.00E+00 Mn-54 CURIES 0.00E+00 0.00E+00 6.24E-04 6.32E-04 Nb-95 CURIES 0.00E+00 0.00E+00 3.61 E-06 7.43E-05 Nb-97 CURIES 0.00E+00 0.00E+00 1.46E-04 6.22E-06 j Sb-124 CURIES 0.00E+00 0.00E+00 0.00E+00 1.49E 06 i Sb-125 CURIES 0.00E+00 0.00E+00 2.01 E-03 1.16E-03 i Sr-89 CURIES 0.00E+00 0.00E+00 5.09E-06 1.57E-05 l Sr 90 CURIES 0.00E+00- 0.00E+00 1.44E-06 7.67E 13 Sr-92 CURIES 0.00E+00 0.00E+00 2.15E-05 0.00E+00 I Te-125M CURIES 0.00E+00 0.00E+00 0.00E+00 4.93E 03 !
Zr-95 CURIES 0.00E+00 0.00E+00 0.00E+00 4.95E-05 TOTALS 0.00Et00 0.00E+00 .t18E-02 2.02E-02 DISSOLVED AND ENTRAINED GASES:
Xe-133 CURIES 0.00E+00 0.00E+00 5.67E-04 1,11 E-03 l Xe-135 - CURIES 0.00E+00 0.00E+00 6.84E-06 0.00E+00 TOTALS 0.00E+00 0.00E+00 5.74E-04 1.11 E-03 i
G ALPHA CURIES 0.00E+00 0.00E+00 7.40E-07 2.48E-06 !
20
e TABLE 13B Vogtts Eltetric Gantrating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1998 Uquid Effluents 1 Starting : 1-Jan 1998 Ending : 30-Jun-1998 )
UNIT : 2 CONTINUOUS BATCH NUCUDE UNIT QUARTER 1 QUARTM 2 OUARTER1 QUARTER 2 H-3 CURIES 0.00E+00 0.00E+00 4.20E+02 2.13E+02 FISSION & ACTIVATION PRODUCT Ag-110M CURIES 0.00E+00 0.00E+00 3.76E-05 3.75E-05 Ce 14 4 CURIES 0.00E+00 0.00E+00 1.28E-04 0.00E+00 Co-57 CURIES 0.00E+00 0.00E+00 1.04E-04 0.00E+00 Co-58 CURIES 0.00E+00 0.00E+00 8.87E-03 2.37E-03 Co-60 CURIES 0.00E+00 0.00E+00 3.98E-02 9.35E-03 Cr-51 - CURIES 0.00E+00 0.00E+00 7.87E-03 6.18E-03 Cs 134 CURIES 0.00E+00 0.00E+00 3.95E-03 1.87E-03 Cs 137 CURIES 0.00E+00 0.00E+00 3.48E-03 1.87E-03 Fe-55 CURIES 0.00E+00 0.00E+00 3.08E-02 5.30E-03 Fe-59 CURIES 0.00E+00 0.00E+00 1.15E-04 2.05E-05 l131 CURIES 0.00E+00 0.00E+00 4.55E-04 2.28E-04 l132 CURIES 0.00E+00 0.00E+00 1.27E-03 5.54E-05 l-133 CURIES 0.00E+00 0.00E+00 8.76E-06 0.00E+00 La 140 CURIES 0.00E+00 0.00E+00 2.96E-05 0.00E+00 Mn-54 CURIES 0.00E+00 0.00E+00 7.07E-03 1.55E-03 Na-24 CURIES 0.00E +00 0.00E+00 0.00E+00 1.50E-05 Nb-95 CURIES 0.00E+00 0.00E+00 1.70E-03 3.67E-04 I
- Nb-97 CURIES 0.00E+00 0.00E+00 5.16E-04 9.73E-05 Ru 103 CURIES 0.005+00 0.00E+00 2.49E-05 0.00E+00 Sb 122 CURIES 0.00E+00 0.00E+00 2.77E-06 0.00E+00 Sb-124 CURIES 0.00E+00 0.00E+00 1.99E 03 2.26E-03 Sb-125 CURIES 0.00E+00 0.00E+00 9.71E-02 5.58E-02 Sn-113 CURIES 0.00E+00 0.00E+00 1.21 E-04 0.00E+00 Sr-89 CURIES 0.00E+00 0.00E+00 2.96E-04 3.88E-05 Sr-90 CURIES 0.00E+00 0.00E+00 1.70E-05 6.02E-06 Sr-92 CURIES 0.00E+00 0.00E+00 7.84E-05 2.44E-05 ,
Te-125M CURIES 0.00E+00 0.00E+00 0.00E+00 6.72E-03 Te 129M CURIES 0.00E+00 0.00E+00 1.83E 03 1.61 E-03 i Te-132 CURIES 0.00E+00 0.00E+00 1.26E-03 3.97E-05 l Y-92 CURIES 0.00E+00 0.00E+00 0.00E+00 4.93E-05 Zn-65 CURIES 0.00E+00 0.00E+00 2.13E 04 0.00E+00 Zr 95 CURIES 0.00E+00 0.00E+00 6.97E-04 1.25E 04 TOTALS CURIES 0.00E+00 0.00E+00 o inus a ans.no DISSOLVED AND ENTRAINED GASES Ar 41 CURIES 0.00E+00 0.00E+00 2.70E-05 0.00E+00 Xe-133 CURIES 0.00E+00 0.00E+00 4.36E-03 7.71 E-04 Xe-135 CURIES 0.00E+00 0.00E+00 7.67E-05 0.00E+00
~ TOTALS n nas nn n nns nn 4.4 age v 71ua
' G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 6.11 E-06 21
[
TABLE 1-3BB Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1998 Liquid Effluents Starting : 1 Jul 1998 Ending : 31 Dec 1998 UNIT : 2 CONTINUOUS NUCLlDE UNIT QUARTER 3 QUARTER 4 H-3 CURIES 0.00t 00 0.00E+00 3.10E+02 8.59E+01 FISSION & ACTIVATION PRODUCT Ag-110M CURIES 0.00E+00 0.00E+00 . 2.21E-05 0.00E+00 Ce-141 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-144 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co CURIES 0.00E+00 0.00E+00 9.16E-06 0.00E+00 Co-58 CURIES 0.00E+00 0.00E+00 4.36E-04 3.80E-05 Co-60 CURIES 0.00E+00 0.00E+00 3.29E-03 1.50E-03 Cr-51 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-134 CURIES 0.00E+00 0.00E+00 6.53E-04 3.05E-05 Cs-136 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs 137 CURIES 0.00E+00 0.00E+00 6.18E-04 2.78E-05 Fe CURIES 0.00E+00 0.00E+00 2.83E-03 1.50E-03 Fe-59 CURIES 0.00E+00 0.00E+00 9.14E-06 0.00E+00 -
I131 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1132 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1133 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La 140 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 CURIES 0.00E+00 0.00E+00 4.76E-04 1.64E-04 Na-24 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 CURIES 0.00E+00 0.00E+00 4.11 E-05 0.00E+00 Nb-97 CURIES 0.00E400 0.00E+00 1.03E 04 1.28E-05 Rb-86 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-125 CURIES 0.00E+00 0.00E+00 1.92E 03 3.00E-04 Sn 113 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 CURIES 0.00E+00 0.00E+00 1.80E-05 1.78E-05 Sr 90 CURIES 0.00E+00 0.00E+00 1.42E 14 2.13E 14 Sr-92 CURIES 0.00E+00 0.00E+00 7.38E 06 0.00E+00 4 Tc-99M CURIES 0.00E+00 0.00E+00 0.00E+00 3.78E-06 Zr-95 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr 97 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 0.00E+00 0.00E+00 1.04E-02 3.59E-03 Xe 133 CURIES 0.00E+00 0.00E+00 1.34E-03 3.23E-06 l Xe-135 CURIES 0.00E+00 0.00E+00 1.29E-05 0.00E+00 l TOTALS 0.00E+00 0.00E+00 1.35E-03 3.23E-06 G-ALPHA CURIES 0.00E+00 0.00E+00 7.37E-06 5.35E-06 22
TABLE 13C Vogtla Electric G ntrating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1998 Liquid Efflu:nts Starting : 1 Jan 1998 Ending : 30-Jun-1998 SITE CONTINUOUS BATCH NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 H CURIES C.00E+00 0.00E+00 5.38E+02 3.39E+02 FlSSION & ACTIVATION PRODUCT Ag 110M CURIES 0.00E+00 0.00E+00 1.24E-04 1.73E-04 Ce-144 CURIES - 0.00E+00 ' O.00E+00 - 1.28E-04 0.00E+00 Co CURIES 0.00E+00 0.00E+00 1.47E-04 4.20E-06 Co-58 CURIES 0.00E+00 0.00E+00 1.13E-02 4.27E-03 Co-60 CURIES 0.00E+00 0.00E+00 5.60E-02 1.73E-02 Cr 51 CURIES 0.00E+00 0.00E+00 9.88E-03 8.55E-03 Cs-134 CURIES 0.00E+00 0.00E+00 4.91 E-03 3.21 E-03 Cs-137 CURIES 0.00E+00 0.00E+00 4.38E-03 3.12E-03 Fe 55 CURIES 0.00E+00 0.00E+00 4.91 E-02 4.91E-02 Fe-59 CURIES 0.00E+00 0.00E+00 1.15E-04 2.05E-05 l131 CURIES 0.00E+00 0.00E+00 5.52E-04 2.59E-04 l-132 CURIES 0.00E+00 0.00E+00 1.52E-03 5.54E-05 l133 CURIES 0.00E+00- 0.00E+00 5.64E 05 0.00E+00 La 140 CURIES 0.00E+00 0.00E+00 5.23E-05 7.18E-08 '
Mn-54 CURIES 0.00E+00 100E+00 9.84E-03 2.85E-03 Na-24 ~ CURIES 0.00E+00 0.0M+00 0.00E+00 1.50E-05 Nb-95 CURIES 0.00E+00 G 00l!+00 2.22E-03 6.39E-04 Nb-97 CURIES 0.00E+00 0.GGd+00 6.00E-04 3.33E-04 Ru-103 CURIES 0.00E+00 0.00E+00 2.49E-05 0.00E+00 Sb 122 CURIES 0.00E+00 0.00E+00 2.77E-06 0.00E+00 Sb 124 CURIES 0.00E+00 0.00E+00 2.57E 03 3.31E 03 Sb-125 CURIES 0.00E+00 0.00E+00 1.24E-01 8.53E-02 Sn 113 CURIES 0.00E+00 0.00E+00 1.21E-04 0.00E+00 Sr-89 CURIES 0.00E+00 0.00E+00 5.68E-04 2.24E-04 Sr90 CURIES 0.00E+00 0.00E+00 4.41 E-05 1.61 E-05 Sr-92 CURIES 0.00E+00 0.00E+00 9.38E-05 2.44E 05
- Tc-99M CURIES 0.00E+00 0.00E+00 1.35E-06 0.00E+00
' Te 125M CURIES 0.00E+00 0.00E+00 6.36E-04 6.72E-03
- Te-129M CURIES 0.00E+00 0.00E+00 1.83E-03 2.39E-03 Te 132. CURIES 0.00E+00 0.00E+00 1.52E 03 3.97E-05 Y 92 CURIES ' O.00E+00 0.00E+00 2.61E 05 4.93E 05 Zn-65 ' CURIES 0.00E+00 0.00E+00 2.13E-04 0.00E+00
. Zr 95 - CURIES 0.00E+00 0.00E+00 8.84E 04 2.40E-04 TOTALS CURIES 0.00E+00 0.00E+00 2.83E-01 1.88E 01 DISSOLVED AND ENTRAINED GASES -
Ar 41 CURIES 0.00E+00 0.00E+00 ' 2.70E-05 0.00E+00 Kr-85 CURIES 0.00E+00 .0.00E+00 7.17E-04 0.00E+00 Xe 133 CURIES 0.00E+00 0.00E+00 4.56E-03 7.72E-04 Xe 135 CURIES - 0.00E+00 0.00E+00 4.05E-04 0.00E+00 Xe-135M CURIES 0.00E+00 0.00E+00 0.00E+00 2.23E-05 TOTALS- 0.00E+00 0.00E+00 L711-03 7.95E 04 G-ALPHA CURIES 0.00E+00 0.00E+00 2.15E-06 9.57E-06 23 I
J
l TABLE 13CC <
Vogtla El!ctric gen:riting Pitnt ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1998 Liquid Effluents Starting : 1-Jul-1998 Ending : 31 Dec 1998 I
SITE CONTINUOUS BATCH NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 H3 CURIES 0.00E+00 0.00E+00 4.74E+02 3.18E+02 {
I FISSION & ACTIVATION PRODUCT {
Ag-110M CURIES 0.00E+00 0.00E+00 9.09E-05 0.00E+00 l Ce 141 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ;
Co 144 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Co-57 CURIES 0.00E+00 0.00E+00 9.16E-06 3.37E-06 Co-58 CURIES 0.00E+00 0.00E+00 8.66E-04 5.16E-04 Co-60 CURIES 0.00E+00 0.00E+00 7.77E-03 6.32E-03 l 4.88E-04 l Cr-51 CURIES 0.00E+00 0.00E+00 5.98E-05 I
Cs-134 CURIES 0.00E+00 0.00E+00 1.27E-03 1.01E-03 Cs-136 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 CURIES 0.00E+00 0.00E+00 1.25E-03 1.07E-03 Fe-55 CURIES 0.00E+00 0.00E+00 5.34E-03 6.96E-03 Fe-59 CURIES 0.00E+00 0.00E+00 9.14E-06 4.70E-05 l-131 CURIES 0.00E+00 0.00E+00 1.17E-05 7.87E 06 l-132 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ,
1-133 CURIES 0.00E+00 0.00E+00 3.18E 06 0.00E+00 La-140 CURIES 0.00E+00 0.00E+00 1.32E 05 0.00E+00 Mn-54 CURIES 0.00E+00 0.00E+00 1.10E-03 7.96E-04 Na-24 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb CURIES 0.00E+00 0.00E+00 4.47E 05 7.43E 05 Nt>97 CURIES 0.00E+00 0.00E+00 2.49E-04 1.90E 05 Rb-86 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rh-105 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ru-103 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 St>122 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1,49E-06 St>124 CURIES CURIES 0.00E+00 0.00E+00 3.93E-03 1.46E-03 Sb 125 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 an-113 CURIES 0.00E+00 0.00E+00 2.31E 05 3.35E-05 Sr-89 CURIES 0.00E+00 0.00E+00 1.44E-06 7.88E 13 l St-90 '
CURIES 0.00E+00 0.00E+00 2.89E 05 0.00E+00 Sr 92 i CURIES 0.00E+00 0.00E+00 0.00E+00 3.78E 06 Tc-99M CURIES 0.00E+00 0.00E+00 0.00E+00 4.93E-03 Te-125M CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te129M CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-132 CURIES 0.00E+00 0.00E+00 ' O.00E+00 0.00E+00 Y-92 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 CURIES 0.00E+00 0.00E+00 0.00E+00 4.95E-05 Zr 95 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr 97 0,00E+00 0.00E+00 2,21E42 2.38E-02 TOTALS CURIES 0.00E+00 0.00E+00 1.91E-03 1.11E-03 Xe-133
' CURIES 0.00E+00 0.00E+00 1.97E-05 0.00E+00 Xe-135 0.00E+00 0.00E+00 1,91E43 1.11E-03 TOTALS CURIES 0.00E+00 0.00E+00 8.11 E-06 7.83E-06 G-ALPHA 24
TABLE 1-4A VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES JANUARY,1998 THROUGH JUNE,1998 UNIT 1 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 1 ODCM 2 ODCM j LIMIT LIMIT I Bone 5.0 mrom 6.86E-03 1.37E 01 2.19E-02 4.38E-01 Liver 5.0 mrom 1.31 E-02 2.62E-01 4.13E-02 8.27E-01 T. Body 1.5 mrom 1.03E-02 6.86E-01 3.19E-02 2.13E+00 Thyroid 5.0 mrom 1.66E-03 3.33E-02 3.65E-03 7.31 E-02 Kidney 5.0 mrom 5.41 E-02 1.08E-01 1.62E-02 3.24E-01 ;
Lung 5.0 Mrem 3.68E-02 7.35E-01 7.10E-02 1.42E+00 GI-LLI 5.0 Mrem 6.68E-03 1.34E-01 1.23E-02 2.47E-01 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % OF ODCM LIMIT LIMIT Bone '10.0 mrom 2.87E-02 2.87E-01 )
Liver 10.0 mrom 5.44E-02 5.44E-01 T. Body 3.0 mrom 4.22E-02 1.41 E+00 Thyroid 10.0 mrom 5.32E-03 5.32E-02 Kidney 10.0 mrom 2.16E-02 2.16E-01 Lung 10.0 mrom 1.08E-01 1.08E+00 GI-LLI 10.0 mrom 1.90E-02 1.90E-01 25
}
TABLE 1-4AA VOGTLE ELECTRIC GENERAT!NG PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES July,1998 THROUGH December,1998 UNIT 1 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 3 ODCM 4 ODCM LIMIT LIMIT Bone 5.0 'mrom 1.02E-02 2.05E-01 1.51 E-02 3.03E-01 {
Liver 5.0 mrom 2.36E-02 4.72E-01 3.34E-02 6.67E-01 T. Body- 1.5 mrom 1.89E-02 1.26E+00 2.65E-02 1.77E+00 ;
Thyroid 5.0 mrom 5.17E-03 1.03E-01 6.70E-03 1.34E-01 {
Kidney 5.0 mrom 1.12E-02 2.24E-01 1.64E-02 3.28E-01 l Lung 5.0 mrom 1.26E-02 2.51 E-01 1.23E-02 2.47E-01 Gl-LLI 5.0 mrom 6.73E-03 1.35E-01 9.18E-03 1.84E-01 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % OF ODCM LIMIT LIMIT Bone 10.0 mrom 5.41 E-02 5.41 E-01 Liver 10.0 mrom 1.11 E-01 1.11 E+00 T. Body 3.0 mrom 8.76E-02 2.92E+00 '
Thyroid 10.0 mrom 1.72E-02 1.72E-01 Kidney 10.0 mrom 4.92E-02 4.92E-01 Lung 10.0 mrom 1.33E-01 1.33E+00 GI-LLI 10.0 mrom 3.49E-02 3.49E-01 l
l 26
TABLE 1-4B VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES JANUARY,1998 THROUGH JUNE,1998 UNIT 2 CUMULA11VE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 1 ODCM 2 ODCM LIMIT LIMIT Bone 5.0 mrom 2.78E-02 5.56E-01 3.27E-02 6.54E-01 Liver 5.0 mrom 5.45E-02 1.09E-01 6.27E-02 1.25E+00 T. Body 1.5 mrom 4.27E-02 2.84E+00 4.88E-02 3.25E+00 Thyroid 5.0 mrom 6.32E-03 1.26E-01 6.66E-03 1.33E-01 Kidney 5.0 mrom 2.28E-02 4.57E-01 2.63E-02 5.25E-01 Lung 5.0 mrom 1.35E-01 2.69E+00 1.45E-01 2.89E+00 GI-LLI 5.0 mrom 2.38E-02 4.77E-01 2.31 E-02 4.63E-01 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % OF ODCM LIMIT LIMIT Bone 10.0 mrom 6.05E-02 6.05E-01 Liver 10.0 mrom 1.17E-01 1.17E+00 T. Body 3.0 mrom 9.15E-02 3.05E+00 Thyroid 10.0 mrom 1.30E-02 1.30E-01 Kidney 10.0 mrom 4.91 E-02 4.91 E-01 Lung 10.0 mrom 2.79E-01 2.79E+00 GI-LLI 10.0 mrom 4.70E-02 4.70E-01 27
TABLE 1-4BB VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQU:D RELEASES JULY,1998 THROUGH DECEMBER,1998 UNIT 2 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 3 ODCM 4 ODCM LIMIT LIMIT Bone 5.0 mrom 1.06E-02 2.11 E-01 4.93E-04 9.86E-03 Liver 5.0 mrom 2.83E-02 5.67E-01 3.66E-03 7.33E-02 T. Body 1.5 mrom 2.3SE-02 1.57E+00 3.45E-03 2.30E-01 Thyroid 5.0 mrom 9.14E-03 1.83E-01 2.7BE-03 5.59E-02 Kidney 5.0 mrom 1.55E-02 3.09E-01 3.07E-03 6.14E-02 Lung 5.0 mrom 1.64E-01 3.28E-01 3.76E-03 7.52E-02 GI-LLI 5.0 mrom 1.06E-02 '
2.12E-01 3.16E-03 6.33E-02 l CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAD TO DATE % of ODCM LIMIT LIMIT Bone 10.0 mrom 7.16E-02 7.16E-01 Liver 10.0 mrom 1.49E-01 1.49E+00 T. Body 3.0 mrem 1.18E-01 3.95E+00 Thyroid 10.0 mrom 2.49E-02 2.49E-01 Kidney 10.0 mrom 6.76E-02 6.76E-01 Lung 10.0 mrom 3.00E-01 3.00E+00 GI-LLI 10.0 mrom 6.07E-02 6.07E-01 ,
1 I
)
28 J
TABLE 1-5 MINIMUM DETECTABLE CONCENTRA TIONS - LIQUID SAMPLE ANAL YSES VOGTLE ELECTRIC GENERATING PLANT JANUARY,1998 - DECEMBER 31,1998 The values in this table represent a priori Minimum Detectable Concentration (MDC) which are typically achieved in laboratory analyses of liquid radwaste samples.
RADIONUCLIDE MDC UNITS Mn-54 2.73E-08 kCVml Fe-59 8.33E-08 Ci/mi Co-58 3.78E-08 Cl/ml .
Co-60 6.76E-08 Cl/ml Zn-65 1.32E-07 Cl/ml Mo-99 4.31 E-07 Cl/mi Cs-134 3.06E-08 Ci/ml Cs-137 4.51 E-08 Cl/ml Ce-141 6.99E-08 CVml Ce-144 2.95E-07 Ci/ml 1-131 5.97E-08 pCi/ml Xe-133 9.11 E-08 C1/ml Xe-135 4.27E-08 Ci/mi Fe-55 1.00E-06 Cl/mi Sr-89 5.00E-08 Cl/ml Sr-90 7.00E-09 Cl/ml H-3 2.00E-06 Cl/mi Gross Alpha 7.00E-08 Cl/ml 29 i
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TABLE 1-6A VOGTLE ELECTRIC GENERATING PLANT- UNIT 1 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JANUARY,1998 ENDING: JUNE,1998 LIQUID RELEASES Numberof Releases 49 Total Time For All Releases 5298.00 minutes Maximum Time For a Release 315.00 minutes ,
Average Time For a Release 108.12 minutes Minimum Time For a Release 4.00 minutes GASEOUS RELEASES Numberof Releases: 54 Total Time For All Releases 5678.00 minutes Maximum Time For A Release 1356.00 minutes Average Time For A Release 105.15 minutes Minimum Time For A Release 30.00 minutes 30
TABLE 1-6AA VOGTLE ELECTRIC GENERATING PLANT- UNIT 1 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JUL Y,1998 ENDING: DECEMBER,1998 LIQUID RELEASES Number of Releases 36 Total Time For All Releases 5040.35 minutes Maximum Time For a Release 385.00 minutes ~
Average Time For a Release 140.01 minutes Minimum Time For a Release 21.00 minutes GASEOUS RELEASES Numberof Releases: 56 Total Time For All Releases 4204.00 minutes Maximum Time For a Release 209.00 minutes Average Time For a Release 75.07 minutes Minimum Time For a Release 8.00 minutes l
l 31 j
TABLE 1-6B VOGTLE ELECTRIC GENERATING PLANT- UNIT 2 BA TCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JANUARY,1998 ENDING: JUNE,1998 LIQUID RELEASES Numberof Releases 62 Total Time For All Releases 11650.98 minutes ,
Maxirnum Time For a Release 363.00 minutes Average Time For a Release 187.92 minutes Minimum Time For a Release 50.00 minutes GASEOUS RELEASES Numberof Releases: 83 Total Time For All Releases 60877.67 minutes Maximum Time For A Release 5267.00 minutes Average Time For A Release 733.47 minutes Minimum Time For A Release 13.00 minutes 32
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1 TABLE 1-6BB 1 VOGTLE ELECTRIC GENERATING PLANT- UNIT 2 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JUL Y,1998 ENDING: DECEMBER,1998 LIQUID RELEASES Number of Releases 19 Total Time For All Releases 2977.00 minutes Maximum Time For A Release 362.00 minutes Average Time For A Release 156.68 minutes ,
Minimum Time For A Release 69.00 minutes GASEOUS RELEASES Numberof Releases 19 Total Time For All Releases 1240.00 minutes Maximum Time For a Release 138.00 minutes Average Time For A Release 65.26 minutes Minimum Time For A Release 14.00 minutes 33 1
2.0 Gaseous Ettluents 2.1 ODCM Specifications The ODCM Specifications presented in this section are for Unit 1 and Unit 2.
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 lodine-131, for lodine-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 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 lodine-131, lodine-133, tritium and all radionuclides in particulate form with half-lives grenter than 8 days in gaseous effluents released, from each unit, to areas at and beyond 'he SITE BOUNDARY shall be limited to the following.
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ,
- b. During any calendar year: Le'as than or equal to 15 mrems to any organ.
34
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 Gaseous Effluents at the Vogtle Electric Generating Piant are currently confined to four paths: plant vents (Unit 1 and Unit 2), the condenser air ejector and steam packing exhauster systems (Unit 1 and Unit 2).
Waste gas decay tanks are batch released through the Unit 1 plant vent. The Containment purges are released through their respective plant vents.
l 2.3 Sample CoIIection 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 lodines. During this reporting period, there were no continuous radioactive releases through the condenser air ejector and steam packing exhauster system vents. Batch Waste Gas Decay Tank releases are analyzed for noble gases before each release.
The containment atmosphere is analyzed for noble gases prior to each release and for tritium at least on a monthly basis.
Sample analyses results and release flow rates 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.
With each release period and batch release, radioactivity, dose rates, and cumulative doses are calculated. Cumulative dose results are tabulated, along with the percent of the ODCM limits for each release for the current quarter and year.
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2.4 Total Quantitles of Radianctivity, Dose Rates, and Cumulative Doses l The methods for determining release quantities of radioactivity, dose rates, and cumulative doses are as fellows:
2.4.1 Fission and Activation 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 I collected sample.
Instantaneous dose rates due to noble gases, radiolodines, tritium, and particulates are calculated. Calculated dose rates are compared to the dose rate limits specified in ODCM 3.1.2 for noble gases, radioiodines, tritium, and particulates. Dose 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 the potential for the highest exposure due 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 compared with the dose limits specified in ODCM 3.1.3. Current percent of the ODCM limits are shown on the printout for each release period. Air dose calculation methodology is presented in the ODCM.
2.4.2 Radiolodines, Tritium and Particulate Releases The released quantities of radiolodines are determined using the weekly samples and release flow rates for the two plant vent release points. ,
The released quantitles of particulates are determined using the weekly (filter) samples and release flow rates for the two release points.
After each quarter, the particulate filters from each Plant vent are combined, for )
strontium analysis. Strontium concentrations are input to the composite file of the q computer to be used for release dose rate and individual dose calculations.
Individual doses due to radiolodines, tritium and particulates are calculated for the controlling 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 cumulative totals are kept for each unit for the current calendar quarter and year. Cumulative individual doses are compared to the dose limits specified in ODCM 3.1.4.
Current percent of ODCM limits are shown on this report for each release period 2.4.3 - Gross Alpha Release .
36
1
\
The gross alpha release is calculated each month by counting the particulate filters for each week for gross alpha activity. 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 used for release calculations.
2.5 Genaus Effluent Release Data 2.5.1 Afethodology Regulatory Guide 1.21 Tables 1 A,1B, and 1C are found in this report as Tables 2-2A,2-2AA,2-28,2-2BB,2-2C,2 2CC,2-3A,2-3AA, 2-3B,2-3BB,2-3C,2-3CC,2-4A,2-4AA, 2-4B,2-4BB,2-4C, and 2-4CC. Data are presented on a quarterly basis as required by Regulatory Guide 1.21.
To complete table 2-2A,2-2AA,2-2B, and 2-2BB, the total release for each of the four categories (fission and activation gases, lodines, particulates, and tritium) was divided by the number of seconds in the quarter to obtain a release rate in Cl/second for each category. However, the percent of the ODCM limits are not applicable because VEGP has no curie limits for gaseous releases. Applicable limits are expressed in terms of ,
dose. Noble gases are limited as specified in ODCM 3.1.2. The other three categories (tritium, radiolodines, and particulates) are limited as a group as specified in ODCM 3.1.2.
Dose rates due to noble gas releases and due to radiolodines, tritium, and particulate releases were calculated as part of the pre-release and post-release permits. No limits wem exceeded for this reporting period.
Gross alpha radioactivity is reported in Table 2-2A,2-2AA,2-2B, and 2-2BB as curies released in each quarter.
Limits for cumulative beta and gamma air doses due to noble gases are specified in ODCM 3.1.3. Cumulative air doses are presented in Table 2-6A,2-6AA,2-68, and 2-6BB along with the percent of the ODCM limits.
Limits for cumulative individual doses due to radioiodines, tritium and particulates, are specified ire ODCM 3.1.4. Cumulative individual doses are presented in Table 2-7A, 2-7AA,2-7B, and 2-788 along w!!ii' percent of ODCM limits.
The total or maximum error associated with the effluent 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 for each 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 materiels released in liquid and gaseous effluents and solid waste.
37
Estimated errors are based on errors in counting equipment calibration, counting statistics, vent-flow rates, vent sample flow rates, non-steady release rates, chemical yleid factors, and sample losses for such items as charcoal cartridges,
- s. Fission and activation total release was calculated 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 %
- b. 1-131 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%
Losses from charcoal cartridges 10%
TOTAL ERROR 100 %
- c. Particulates with half lives greater than 8 day releases were calculated from sample and analysis results and release point flow rates.
Statistical error at MDC concentration 10%
Counting equipment calibration 10%
Vent flow rates 10%
Vent sample flow rates 50 %
Non steady release rates 10%
TOTAL ERROR 90 %
- d. Total tritium releases were calculated from sample analysis results and release point flow rates.
Water vapor in sample stream determination 10%
Vent flow rates 10%
Counting calibration and statistics 10%
Non-steady release rates 10%
TOTAL ERROR 40 %
- e. Gross Alpha radioactivity was calculated from sample analysis results 38
and release point flow rates.
I Statistical error at MDC concentration 10%
Counting equipment calibration 10%
Vent flow rates 10% ,
Vent sample flow rates 50 % I Non Steady release rates 10%
TOTAL ERROR 90 %
)
I 2.5.2 Gaseous Batch Data l Other data pertinent to batch releases of radioactive gaseous effluent from Unit 1 and Unit 2 are listed in Table 1-6A,1-6AA,1-6B, and 1688.
)
2.6 RadiologicalImpact Due to Gaseous Releases Dose rates due to the release of noble gases were calculated for the site in accordance with ODCM 3.4.1.1 Dose rates due to radioiodines, tritium, and particulates in gaseous releases were calculated in accordance with ODCM 3.4.1.2.
Dose rates were calculated as part of pre-release and post release permits, no limits ~
were exceeded for this reporting period.
Cumulative air doses due to noble gas releases were calculated for each unit in accordance with ODCM 3.4.2. These results are presented in Tables 2-6A,2-6AA,2-68, and 2-688.
Dose rates and doses were calculated using the methodology presented in the Vogtle Electric Generating Plant Offsite Dose Calculation Manual.
2.7 Abnormal Releases There were no unplanned gaseous releases in 1998.
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TABLE 2-2A {
l
- SOUTHERN NUCLEAR OPERATING COMPANY
' VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1998 )
- ALL AIRBORNE EFFLUENTS UNIT : 1 i STARTING : 1-JAN-1998 ENDING : 30-JUN-1998 TYPE OF EFFLUENT UNITS OUARTER1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS ,
-1
- 1. TOTAL RELEASE CURIES 1.09E+01 1.05E-01 50 ,
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.40E+00 1.34E-02
- 3. PERCENTAGE OF APPLICABLE LIMIT % N/A N/A B. RADIOlODINES
- 1. TOTAL IODINE 131 CURIES 2.40E-05 3.33E-06 100 .
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 3.09E-06 4.24E-07 DURING PERIOD
' 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES 1.PARTICULATES(HALF LIVES >8 DAYS) CURIES 1.27E-06 1.09E 10 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 1.63E-07 1.39E-11
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. TRITIUM
- 1. TOTAL RELEASE CURIES 5.89E+01 2.85E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.57E+00 3.62E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 7.31 E-06 0.00E+00 90
- Applicable limits are expressed in terms of Dose. See Tables 2-6A and 2 7A of this report 40
TABLE 2-2AA SOUTHERN NUCLEAR OPERATING COMPANY '
VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1998 ALL AIRBORNE EFFLUENTS UNIT : 1 STARTING : 1-JUL-1998 ENDING : 31-DEC-1998 TYPE OF EFFLUENT UNITS QUARTER 3 OUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS I
- 1. TOTAL RELEASE CURIES 6.60E-01 1.63E-01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.30E-02 2.05E-02
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. RADIOIODINES l
1
- 1. TOTAL IODINE 131 CURIES 3.78E-06 0.00E+00 100 ,
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.76E-07 0.00E+00 DURING PERIOD 1 1
- 3. PERCENTAGE OF APPLICABLE LIMIT %
l C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 3.66E-07 9.43E-08 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.60E-08 1.19E-08
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D.TRITlUM
- 1. TOTAL RELEASE CURIES 2.20E+01 4.37E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.77E+00 5.50E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 0.00E+00 0.00E+00 90
- Applicable limits are expressed in terms of Dose. See Tables 2 6AA and 2 7AA of this report 41
TABLE 2-2B SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1998 ALL AIRBORNE EFFLUENTS UNIT : 2 STARTING : 1-JAN-1998 ENDING : 30-JUN-1998 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 3.25E+02 7.09E-01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.18E+01 9.02E-02
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 8. RADIOlODINES
- 1. TOTAL IODINE-131 CURIES 2.56E-04 5.59E-05 100 .
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.29E-05 7.11 E-06 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 1.20E-05 4.62E-07 90
- 2. AVER AGE RELEASE RATE FOR PERIOD uCl/Sec 1.54E-06 5.88E-08
- 3. PERCENTAGE OF APPLICABLE LIMIT % 4 I
D. TRITIUM l
- 1. TOTAL RELEASE - CURIES 3.11 E+01 2.80E+01 40 !
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 4.00E+00 3.56E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 7.11 E-14 0.00E+00 90
- Apphcable limits are expressed in terms of Dose. See Tables 248 and 2-78 of this report 42 l l
TABLE 2 2BB SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1998 ALL AIRBORNE EFFLUENTS UNIT : 2 STARTING : 1 JUL-1998 ENDING : 31-DEC-1998 TYPE OF EFFLUENT UNITS QUARTER 3 OUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 9.28E-02 1.10E 01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.17E-02 1.38E-02
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. RADIOlODINES
' 1. TOTAL LODINE 131 CURIES 2.82E-06 1.52E-06 100 .
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.55E-07 1.91 E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 5.52E-07 3.52E-07 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 6.94E-08 4.43E-08
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. TRITIUM
- 1. TOTAL RELEASE CURIES 2.64E+01 1.13E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 3.32E+00 1.42E+00
' 3. PERCENTAGE OF APPLICABLE LIMIT %- * -
- 4. GROSS ALPHA RADIOACTIVITY CURIES 0.00E+00 0.00E+00 90 i
- Applicabie limits are egressed in terms of oose. see Tables 2-ess and 2 7ss of this report l
43 1
TABLE 2-2C SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1998 ALL AIRBORNE EFFLUENTS SITE STARTING : 1-JAN-1998 ENDING : 30-JUN-1998 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 3.36E+02 8.14E-01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.32E+01 1.04E-01
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. RADIOlODINES
- 1. TOTAL IODINE-131 CURIES 2.80E-04 5.92E-05 100 .
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.60E-05 7.53E-06 DURING PERIOD l
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 1.33E-05 4.62E-07 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 1.71 E-06 5.88E-08
- 3. PERCENTAGE OF APPLICABLE LIMIT %
4 D. TRITIUM
- 1. TOTAL RELEASE CURIES 9.00E+01 5.65E+01 40 l
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.16E+01 7.19E+00 l
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 7.31 E-06 0.00E+00 90
- Applicable limits are expressed in terms of Dose. See Tables 2-6A . 2-68,2 7A and 2-78 of this report 44
TABLE 2-2CC SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1998 ALL AIRBORNE EFFLUENTS SITE STARTING : 1-JUL-1998 - ENDING : 31 DEC 1998 TYPE OF EFFLUENT UNITS QUARTER 3 OUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 7.53E-01 2.73E-01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 9.47E-02 3.43E-02
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. RADIOlODINES l
- 1. TOTAL LODINE-131 CURIES 6.60E-06 1.52E-06 100 ,
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.30E-07 1.91E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES 1
1.PARTICULATES(HALF LIVES >8 DAYS) CURIES 9.18E-07 4.46E-07 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.15E-07 5.61 E-08
- 3. PERCENTAGE OF APPLICABLE LIMIT % ,
I D. TRITIUM
- 1. TOTAL RELEASE CURIES 4.84E+01 5.50E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCL/Sec 6.09E+00 6.92E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 0.00E+00 0.00E+00 90
- Apphcable hmits are expressed in terms of Dose. See Tables 2 6AA,2-688, 2 7AA and 2-788 of this report 45
TABLE 2-3A VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JANUARY,1998 THROUGH JUNE,1998 ;
UNIT 1 NUCLIDES RELEASED I
__ .UNff CONTINUOUS MODE BATCH MODE
- 1. Fission Gassee , QUARTER QUARTER QUARTER QUARTER h 1 2 1 2 Ar-41 Cl 0.00E+00 0.00E+00 4.65E-02 5.01 E-02 Kr-85 Cl 0.00E+00 0.00E+00 3.41 E+00 0.00E+00 Kr-85m Cl 0.00E+00 0.00E+00 6.32E-05 0.00E+00 Xe-133 Cl 5.39E+00 0.00E+00 1.62E-01 5.07E-02 Xe-135 Cl 1.83E+00 0.00E+00 7.96E-03 3.83E-03 TOTAL FOR PER/OD Ci 7.22E+00 0.00E+00 3.63E+00 1.05E-01
- 2. Iodine's 1-131 Ci 2.38E-05 3.33E-06 0.00E+00 0.00E+00 1-133 ,
Cl 5.01 E 06 3.22E-06 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 2.88E-05 6.55E-06 0.00E+00 0.00E+00
- 3. Particulates Cs-134 Cl 1.19E-06 0.00E+00 0.00E+00 0.00E+00 Sr-89 Cl 6.38E-08 0.00E+00 0.0GE+00 0.00E+00 TOTAL FOR PERIOD Cl 1.26E-06 0.00E+00 0.00E+00 0.00E+00 G-ALPHA Cl 7.30E-06 0.00E+00 0.00E+00 0.00E+00 H-3 Cl 5.88E+01 2.84E+01 3.41 E-02 3.52E-02
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
46
TABLE 2-3AA VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS- MIXED MODE JULY,1998 THROUGH DECEMBER,1998 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 3 4 3 4 Ar-41 Ci 0.00E+00 0.00E+00 5.33E-02 6.69E-02 Kr-85m Ci 0.00E+00 0.00E+00 0.00E+00 2.69E-03 Kr-87 Cl 0.00E+00 0.00E+00 0.00E+00 6.03E-03 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 7.53E-03 Xe-133 Cl 5.45E-01 '0.00E+00 5.73E-02 4.04E-02 Xe-133m Cl 0.00E+00 0.00E+00 0.00E+00 5.03E-04 Xe-135 Cl 0.00E+00 0.00E+00 4.61 E-03 2.42E-02 Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 4.23E-03 Xe-138 Cl 0.00E+00 0.00E+00 - 0.00E+00 1.01 E-02 TOTAL FOR PERIOD Ci 5.45E-01 0.00E+00 1.15E-01 1.63E-01
- 2. lodines 1-131 Ci 3.78E-06 0.00E+00 0.00E+00 0.00E+00 1-133 Cl 9.74E-06 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD Cl 1.35E-05 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates CO-57 Cl 0.00E+00 7.13E-08 0.00E+00 0.00E+00 SR-89 Cl 3.66E-07 2.30E-08 0.00E+00 0.00E+00 SR-90 Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD Cl 3.66E-07 9.43E-08 0.00E+00 0.00E+00 G-ALPHA Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 Cl 2.19E+01 4.37E+01 3.09E-02 3.33E-02
- Zeroes in this table indicate that no radioactivity was present above detectable levels.
See Table 2-8 for typical minimum detectable concentrations. l 1
47
TABLE 2-3B VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JANUARY,1998 THROUGH JUNE,1998 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QU.4RTER 1 2 1 2 Ar-41 Cl 0.00E+00 0.00E+00 2.20E-02 6.78E-02 Kr-85 Ci 0.00E+00 0.00E+00 2.68E+01 0.00E+00 Kr-85m Cl 0.00E+00 0.00E+00 0.00E+00 9.70E-05 Xe-135 Cl 1.03E+00 0.00E+00 5.32E-03 1.12E-02 Xe-133m Cl 0.00E+00 0.00E+00 1.47E+00 0.00E+00 Xe-131m Cl 0.00E+00 0.00E+00 7.06E+00 0.00E+00 Xe-133 Cl 4.12E+01 0.00E+00 2.47E+02 5.92E-01 TOTAL FOR PERIOD Cl 4.22E+01 0.00E+00 2.82E+02 6.71 E-01'
- 2. lodine's ,
1-131 Cl 1.90E-04 1.50E-06 0.00E+00 0.00E+00 I l-133 Cl 1.32E-04 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD Cl 3.22E-04 1.50E-06 0.00E+00 0.00E+00 l
- 3. Particulates Co-58 Cl 2.18E-06 1.08E-07 0.00E+00 0.00E+00 Co-60 Cl 6.18E-06 3.54E-07 0.00E+00 0.00E+00 1 Cr-51 Cl 3.27E-06 0.00E00 0.00E+00 0.00E+00 1-131 Ci 2.00E-07 0.00E+00 0.00E+00 0.00E+00 Mn-54 Cl 1.71 E-07 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD Cl 1.20E-05 4.62E-07 0.00E+00 0.00E+00 G ALPHA Ci 7.11 E-14 0.00E+00 0.00E+00 0.00E+00 H-3 Ci 2.70E+01 2.78E+01 3.90E+00 2.35E-01
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations. ,
48
TABLE 2-3BB VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS- MIXED MODE JULY,1998 THROUGH DECEMBER,1998 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 3 4 3 4 Ar-41 Cl 0.00E+00 0.00E+00 1.37E-02 1.65E-02 Kr-85m Cl 0.00E+00 0.00E+00 3.81 E-05 0.00E+00 Xe-133 Ci 0.00E+00 0.00E+00 7.70E-02 9.05E-02 Xe-133m Cl 0.00E+00 0.00E+00 4.31 E-04 0.00E+00 Xe-135 Ci 0.00E+00 0.00E+00 1.58E-03 3.22 E-03 l TOTAL FOR PERIOD Cl 0.00E+00 0.00E+00 9.28E-02 1.10E-01
- 2. lodines \
I-131 Ci 2.82E-06 1.07E-05 0.00E+00 0.00E+00 1-133 Cl 2.35E 05 1.52E-06 0.00E+00 0.00E+00 TO7AL FOR PERIOD Cl 2.63E-05 1.22E-05 0.00E+00 0.00E+00
- 3. Particulates Co-60 Ci 4.31 E-07 0.00E+00 0.00E+00 0.00E+00 Sr-89 Cl 1.21 E-07 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 5.52E-07 3.52E-07 0.00E+00 0.00E+00 G ALPHA Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 Cl 2.64E+01 1.13E+01 4.66E-03 2.21 E-02 '
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
1 49
i f
TABLE 2-3C i
VOGTLE ELECTRIC GENERATING PLANT i l
ANNUAL EFFLUENTS- MIXED MODE JANUARY,1998 THROUGH JUNE,1998 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 1 2 1 2 <
Ar-41 Ci 0.00E+00 0.00E+00 6.85E-02 1.18E-01 Kr-85 Cl 0.00E+00 0.00E+00 3.02E+01 0.00E+00 Kr-85m Ci 0.00E+00 0.00E+00 6.32E-05 9.70E-05 Xe 131m Ci 0.00E+00 0.00E+00 7.06E+00 0.00E+00 Xe-133 Cl 4.65E+01 0.00E+00 2.47E+02 6.43E-Of Xe-133m Cl ' O.00E+00 0.00E+00 1.47E+00 0.00E+00 Xe-135 Cl 2.85E+00 0.00E+00 1.33E-02 1.50E-02 TOTAL FOR PERIOD Cl 4.94E+01 0.00E+00 2.86E+02 7.76E-01
- 2. ladines 1-131 Cl 2.14E-04 4.83E-06 0.00E+00 0.00E+00 1-133 Cl 1.37E-04 3.22E-06 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 3.51 E-04 8.05E-06 0.00E+00 0.00E+00
- 3. Particulates Sr-89 Cl 6.38E-08 0.00E+00 0.00E+00 0.00E+00 !
Mn-54 Cl 1.71 E-07 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 3.27E-06 0.00E+00 0.00E+00 0.00E+00 Cs-134 - Cl 1.19E-06 0.00E+00 0.00E+00 0.00E+00 1-131 Cl 2.00E-07 0.00E+00 0.00E+00 0.00E+00 Co-58 Ci 2.18E-06 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 6.18E-06 0.00E+00 0.00E+00 0.00E+00 i TOTAL FOR PERIOD Cl 1.33E-05 4.62E-07 0.00E+00 0.00E+00 G-ALPHA Cl 7.30E-06 0.00E+00 0.00E+00 0.00E+00 H-3 Cl 8.58E+01 5.62E+01 3.94E+00 2.70E-01
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
50
TABLE 2-3CC VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JULY,1996 THROUGH DECEMBER,1998 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 3 4 3 4 Ar-41 Cl 0.00E+00 0.00E+00 6.70E-02 8.34E-02 Kr-85m Cl 0.00E+00 0.00E+00 3.81 E-05 2.69E-03 Kr-87 Cl 0.00E+00 0.00E+00 0.00E+00 6.03E-03 Kr-88 Cl 0.00E+00 0.00E+00 0.00E+00 7.53E-03 Xe-133 Ci 5.45E-01 0.00E+00 1.34E-01 1.31 E-01 Xe-133m Cl 0.00E+00 0.00E+00 4.31 E-04 5.03E _04 Xe-135 Cl 0.00E+00 0.00E+00 6.18E-03 2.74E-02 Xe-135M Ci 0.00E+00 0.00E+00 0.00E+00 4.23E-03 Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 1.01 E-02 TOTAL FOR PERIOD Ci 5.45E-01 0.00E+00 2.08E-01 2.73E-01
- 2. lodines 1-131 Ci 6.60E-06 1.52E-06 0.00E+00 0.00E+00 1-133 Ci 3.32E-05 1.07E-05 0.00E+00 0.00E+00 TOTAL FOR PERIOD Cl 3.98E-05 1.22E-05 0.00E+00 0.00E+00
- 3. Particulates Co-57 Cl 0.00E+00 7.13E-08 0.00E+00 0.00E+00 Co-60 Cl 4.31 E-07 0.00E+00 0.00E+00 0.00E+00 Sr-89 Ci 4.87E-07 2.30E-08 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 9.18E-07 4.46E-07 0.00E+00 0.00E+00 G-ALPHA Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 Cl 4.83E+01 5.50E+01 3.56E-02 5.54E-02
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations. ,
l l
l 51 i
TABLE 2-4A VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS- GROUND MODE JANUARY,1998 THROUGH JUNE,1998 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gssses QUARTER QUARTER QUARTER QUARTER 1 2 1 2 Xe-135 Cl 3.72E-03 0.00E+00 0.00E+00 0.00E+00 Xe-133 Cl 4.07E-02 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 4.44E-02 0.00E+00 0.00E+00 0.00E+00
- 2. lodines 1-131 Cl 1.91 E-07 3.57E-10 0.00E+00 0.00E+00 l-133 Cl 1.21 E-07 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD Cl 3.12E-07 3.57E-10 0.00E+00 0.00E+00
- 3. Pstticulstes Co58 Cl 1.85E-09 1.09E-10 0.00E+00 0.00E+00 Co40 Cl 5.49E-09 0.00E+00 0.00E+00 0.00E+00 1-131 Cl 1.81 E-10 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 2.83E-09 0.00E+00 0.00E+00 0.00E+00 Sr-89 Ci 8.23E-11 0.00E+00 0.00E+00 0.00E+00 Mn-54 Cl 1.55E-10 0.00E+00 0.00E+00 0.00E+00 Cs-134 Cl 1.85E-09 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD Cl 1.24E-08 1.09E-10 0.00E+00 0.00E+00 _ )
H-3 Cl 1.19E-01 9.54E-03 0.00E+00 0.00E+00
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
52
TABLE 2-4AA VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS GROUND MODE JULY,1998 THROUGH DECEMBER,1998 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gssses QUARTER QUARTER QUARTER QUARTER 3 4 3 4 TOTAL FOR PERIOD Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. lodines TOTAL FOR PERIOD Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulstes TOTAL FOR PERIOD Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00~
H-3 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations, 4
53
l l
l TABLE 2-4B VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE i
JANUARY,1998 THROUGH JUNE,1998 l UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 1 2 1 2 Ar-41 Cl 0.00E+00 0.00E+00 4.63E-02 0.00E+00 Xe-133 Ci 0.00E+00 0.00E+00 6.96E-01 3.81-02 TOTAL FOR PER/OD Cl 0.00E+00 0.00E+00 7.42E-01 3.81 E-02
- 2. lodines 1-131 Cl 0.00E+00 0.00E+00 6.62E-05 5.44E-05
- l-133 Ci 0.00E+00 0.00E+00 4.11 E-07 0.00E+00 TOTAL FOR PER/OD Cl 0.00E+00 0.00E+00 6.66E-05 5.45E-05
- 3. Particulstes TOTAL FOR PER/OD Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 Ci , 0.00E+00 0.00E+00 1.59E-01 1.68E-03
- Zeroes in this table indicate that no ra& activity was present above detectable levels. See Table 2-8 for typical minimum detectable cecentrations.
I 54
TABLE 2-4BB VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JULY,1998 THROUGH DECEMBER,1998 UNIT 2 1
NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
]
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER \
3 4 3 4 {
TOTAL FOR PERIOD Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Iodines TOTAL FOR PERIOD Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates l TOTAL FOR PERIOD Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See f Table 2-8 for typical minimum detectable concentrations.
1 l
l 55
i I
l TABLE 2-4C VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS- GROUND MODE I JANUARY,1998 THROUGH JUNE,1998 l SITE NUCLIDES l
RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER \
1' 2 1 2 l Ar-41 Cl 0.00E+00 0.00E+00 4.63E-02 0.00E+00 Xe-135 Cl 3.72E-03 0.00E+00 0.00E+00 0.00E+00 !
Xe-133 Cl 4.07E-02 0.00E+00 6.96E-01 3.81 E-02 l TOTAL FOR PERIOD Ci 4.44E-02 0.00E+00 7.42E-01 3.81 E-02
~
- 2. IODINES \
l-131 Cl 1.91 E-07 3.57E 10 6.62E-05 5.44E-05 l-133 Cl 1.21 E-07 0.00E+00 4.11 E-07 0.00E+00 TOTAL FOR PERIOD Cl 3.12E-07 3.57E-10 6.66E-05 5.45E-05
- 3. PARTICULA *rES l-131 Cl 1.81 E-10 0.00E+00 0.00E+00 0.00E+00 Cr-51 Cl 2.83E-09 0.00E+00 0.00E+00 0.00E+00 Sr-89 Cl 8.23E-11 0.00E+00 0.00E+00 0.00E+00 Mn-54 Cl 1.55E-10 0.00E+00 0.00E+00 0.00EA00 Cs-134 Cl 1.85E-09 0.00E+00 0.00E+00 0.00E+00 Co-58 Cl 1.85E-09 1.09E-10 0.00E+00 0.00E+00 Co-60 Ci 5.49E-09 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD Cl 1.24E-08 1.09E-10 0.00E+00 0.00E+00 H-3 Cl 1.19E-01 9.54E-03 1.59E-01 1.68E-03
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
i 56
TABLE 2-4CC VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JULY,1998 THROUGH DECEMBER,1998 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE ____ BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 3 4 3 4 TOTAL FOR PERIOD Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Iodines TOTAL FOR PERIOD Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates TOTAL FOR PERIOD Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See l Table 2-8 for typical minimum detectable concentrations.
57
TABLE 2-6A VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES JANUARY,1998 THROUGH JUNE,1998 UNIT 1 CUMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF RADIATION LIMIT 1 ODCM 2 ODCM LIMIT LIMIT BETA 10.0 mrad 2.55E-04 2.55E-03 3.33E-06 3.33E-05 GAMMA 5.0 mrad 8.93E-05 1.79E-03 7.20E-06 1.44E-04 CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM UNITS YEAR TO DATE % OF ODCM LIMIT RADIATION LIMIT l BETA 20.0 mrad 2.59E-04 1.29E-03 GAMMA 10.0 mrad 9.65E-05 9.65E-04 .
l l
58
l l
TABLE 2-6AA VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEAGE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES JULY,1998 THROUGH DECEMBER,1998 UNIT 1 CUMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF RADIATION LIMIT 3 ODCM 4 ODCM LIMIT LIMIT BETA 10.0 mrad 1.20E-05 1.20E-04 6.78E-06 6.78E-05 GAMMA 5.0 mrad 1.05E-05 2.10E-04 1.38E-05 2.77E-04 CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM UNITS YEAR TO DATE % OF ODCM LIMIT RADIATION LIMIT BETA 20.0 mrad 2.77E-04 1.39E-03 GAMMA 10.0 mrad 1.21E-04 1.21E-03 1
59
TABLE 2-6B VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES JANUARY,1998 THROUGH JUNE,1998 UNIT 2 CUMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF RADIATION LIMIT 1 ODCM 2 ODCM LIMIT LIMIT BETA 10.0 mrad 5.45E-03 5.45E-02 1.60E-05 1.60E-04 GAMMA 5.0 mrad 1.61E-03 3.21E-02 1.37E-05 2.74E-04
- 1 CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM UNITS YEAR TO DATE % OF ODCM LIMIT RADIATION LIMIT BETA 20.0 mrad 5.47E-03 2.73E-02 GAMMA 10.0 mrad 1.62E-03 1.62E-02 60
TABLE 2-688 VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES JULY,1998 THROUGH DECEMBER,1998 UNIT 2 CUMULA11VE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF RADIATION LIMIT 3 ODCM 4 ODCM } '
LIMIT LIMIT BETA 10.0 mrad 1.91E-06 1.91E-05 2.30E-06 2.30E-05 ,
GAMMA 5.0 mrad 2.31E-06 4.63E-05 2.81E-06 5.61E-05
- 1 CUMULATIVE DOSES PER YEAR (YEAR TO DATE) i TYPE OF OOCM UNITS YEAR TO DATE % OF ODCM LIMIT RADIATION LIMIT l BETA 20.0 mrad 5.47E-03 2.74E-02 l GAMMA 10.0 mrad 1.62E-03 1.62E-02 l
J 61
TABLE 2-7A VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JANUARY,1998 THROUGH JUNE,1998 UNIT 1 1
CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 1 ODCM 2 ODCM LIMIT LIMIT Bone 7.5 mrom 2.26E-07 3.01 E-06 4.09E-09 5.45E-08 GI-LLI 7.5 mrom 3.80E-04 5.06E-03 1.83E-04 2.44E-03 Kidney 7.5 mrom 3.80E-04 5.07E-03 1.83E-04 2.44E-03 Liver 7.5 mrom 3.80E-04 5.07E-03 1.83E-04 2.44E-03 Lung 7.5 mrom 3.80E-04 5.06E-03 1.83E-04 2.44E-03 T. Body 7.5 mrom 3.80E-04 5.07E-03 1.83E-04 2.44E-03 Thyroid 7.5 mrom 3.88E-04 5.18E-03 1.84E-04 2.46E-03 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT LIMIT Bone 15.0 mrom 2.30E-07 1.53E-06 GI-LLI 15.0 mrom 5.63E-04 3.75E-03 Kidney 15.0 mrom 5.63E-04 3.75E-03 Liver 15.0 mrom 5.63E-04 3.75E-03 Lung 15.0 mrom 5.63E-04 3.75E-03 T. Body 15.0 mrom 5.63E-04 3.75E-03 Thyroid 15.0 mrom 5.73E-04 3.82E-03 l
l 62
TABLE 2-7AA VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JULY,1998 THROUGH DECEMBER,1998 UNIT 1 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 3 ODCM 4 ODCM LIMIT LIMIT Bone 7.5 mrom 7.91 E-08 1.05E-06 5.43E-09 7.24E-08 i GI-LLI 7.5 mrom 1.41 E-04 1.88E-03 2.81 E-04 3.75E-03 Kidney 7.5 mrom 1.41 E-04 1.88E-03 2.81 E-04 3.75E-03 Liver 7.5 mrom 1.41 E-04 1.88E-03 2.81 E-04 3.75E-03 Lung 7.5 mrom 1.41 E-04 1.88E-03 2.81 E-04 3.75E-03 T. Body 7.5 mrom 1.41 E-04 1.88E-03 2.81 E-04 3.75E-03 Thyroid 7.5 mrom 1.43E-04 1.90E-03 2.81 E-04 3.75E-03 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT LIMIT Bone 15.0 mrom 1.56E-07 1.04E-06 GI-LLI 15.0 mrom 9.85E-04 6.57E-03 Kidney 15.0 mrom 9.86E-04 6.57E-03 Liver 15.0 mrom 9.86E-04 6.57E-03 Lung 15.0 mrom 9.85E-04 6.57E-03 T. Body 15.0 mrom 9.85E-04 6.57E-03 Thyroid 15.0 mrom 9.97E-04 6.64E-03 1
63 l l
TABLE 2-7B VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JANUARY,1998 THROUGH JUNE,1998 UNIT 2 CUMULATIVE DOSE PER QUARTER 1 ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 1 ODCM 2 ODCM LIMIT LIMIT Bone- 7.5 mrom 1.21 E-06 1.61 E-05 1.61 E-07 2.15E-06 )
GI-LLI 7.5 mrom 2.02E-04 2.69E-03 1.80E-04 2.41 E-03 Kidney 7.5 mrom 2.02E-04 2.70E-03 1.81 E-04 2.41 E-03 l Liver 7.5 mrom 2.02E-04 2.70E-03 1.80E-04 2.41 E-03 Lung 7.5 mrom 2.02E-04 2.69E-03 1.80E 04 2.41 E-03 !
T. Body 7.5 mrom 2.02E 04 2.69E-03 1.80E-04 2.41 E-03 Thyroid 7.5 mrom 3.11 E-04 4.15E-03 2.14E-04 2.86E-03 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT LIMIT _
Bone 15.0 mrom 1.37E-06 9.14E-06 GI-LLI 15.0 mrom 3.82E 04 2.55E-03 Kidney 15.0 mrom 3.83E-04 2.55E-03 Liver 15.0 mrom 3.83E-04 2.55E-03 Lung 15.0 mrom 3.82E-04 2.55E-03 T. Body 15.0 mrom 3.82E-04 2.55E-03 Thyroid 15.0 mrom 5.25E-04 3.50E 03 !
l 64
TABLE 2-7BB VOGTLE ELECTRIC GENERATlNG PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JULY,1996 THROUGH DECEMBER,1998 UNIT 2 CUMULATIVE DOSE PER QUARTER ORGAN ODCM- UNITS QUARTER % OF QUARTER % OF LIMIT 3 ODCM 4 ODCM LIMIT LIMIT Bone 7.5 mrom 9.39E-08 1.25E-06 2.39E-09 3.19E-08 GI-LLI 7.5 mrom 1.70E-04 2.26E-03 7.28E-05 9.70E-04 Kidney 7.5 mrom 1.70E-04 2.26E-03 7.28E-05 9.70E-04 Liver 7.5 mrom 1.70E-04 2.26E-03 7.28E-05 9.70E-04 Lung 7.5 mrom 1.70E-04 2.26E-03 7.28E-05 9.70E-04 T. Body 7.5 mrom 1.70E-04 2.26E-03 7.28E-05 9.70E-04 Thyroid 7.5 mrom 1.71 E-04 2.28E-03 7.34E-05 9.79E-04
' CUMULATIVE DOSE PER YEAR
. ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT LIMIT i Bonc 15.0 mrom 1.47E-06 9.78E-06 GI-LLI 15.0 mrom 6.25E-04 4.17E-03 Kidney 15.0 mrom 6.25E-04 4.17E-03 Liver 15.0 mrom 6.25E-04 4.17E-03 Lung 15.0 mrom 6.25E-04 4.16E-03 T. Body 15.0 mrom 6.25E-04 4.17E-03 Thyroid 15.0 mrom 7.70E-04 5.13E-03 l
1 65
[
1 TABLE 2-8 MINIMUM DETECTABLE CONCENTRATIONS - GASEQUS SAMPLE ANALYSES VOGTLE ELECTRIC GENERATING PLANT JANUARY,1998 THROUGH DECEMBER,1998 I
l The values in this table represent a prioriMinimum Detectable Concentration (MDC) which are l typically achieved in laboratory analyses of gaseous radwaste samples. l RADIONUCLIDE MDC UNITS l Kr-87 1.82E-08 CVcc Kr-88 2.53E-08 CVcc Xe-133 2.05E-08 CVcc Xe-133m 8.63E-08 pCVcc -
Xe-135 7.12E-08 CVcc Xe-138 1.05E-07 pCVcc I-131 7.93E-15* pCVcc Mn-54 3.94E-14
- CVcc Fe-59 2.45E-14
- pCVcc Co-58 1.39E-14
- CVcc Co-60 1.75E-14
- pCVcc Zn-65 2.82E-14
- pCVcc Mo-99 9.57E-14
- pCVcc St-89 1.00E-13 pCVcc Sr-90 1.00E-13 pCVcc H-3 9.00E-08 pCVcc Gross Alpha 1.00E-13 pCVcc Based on an estimated sample volume of 5.7E+08 cc.
66
3.0 Solid Waste 3.1 Regulatory Limits /DDCM l The ODCM Limits presented in this section are stated in part for Unit 1 and Unit 2.
3.1.1 Use of Solid Radioactive Waste System 10.2.1 Process Control Program Radioactive wastes shall be solidified or dewatered 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 12.1 (PCP) states in part:
The Annual Radioactive Effluent Release Report, submitted in accordance with Technical Specifications 5.6.3, shallinclude a summary of the quantities of solid radwaste released from the units, as outlined in Regulatory Guide 1.21.
3.2 Solid Waste Data Regulatory Guide 1.21, Table 3 is found in this report as Table 3-1.
4.0 The Vogtle Electric Generating Plant Offsite Dose Calculation Manual (ODCM) l 4.1 Changes to the Vogtle Electric Generating Plant Offsite Dose Calculation Manual (ODCM) 7.2.2.5 of ODCM There were no changes to the Vogtle Electric Generating Plant ODCM for the period January 1,1998 through December 31,1998.
67
4.2 The Radiological Environmental Monitoring Program 4.0 of ODCM The Radiological Environmental Monitoring Program (REMP) shall be conducted as specified in Table 4-1.
Section 4.1.1.2.3 states in part:
If adequate samples of milk, or during the growing season, grass or leafy )
vegetation, can no longer be obtained from one or more of the sample !
locations required, or if the availability is frequently or persistently wanting, j efforts shall be made: to identify specific locations for obtaining suitable replacement samples; and to add any replacement locations to the REMP given in the ODCM within 30 days.
Pursuant to Technical Specification 5.5.1, documentation shall be submitted in the next Radioactive Effluent Release Report for the change (s) in the ODCM, including revised
. figure (s) and table (s) reflecting the changes to the location (s), with supporting informdtion identifying the cause of the unavailability of samples and Justifying the selecticn of any new location (s).
4.1.2 of ODCM states in part: ,
-1 "A Land Use Census shall be conducted . . . . ."
The Action Statement for this requirement states in part:
i l
- a. ." With a Land Use Census identifying a location (s) that yields a ca!culated dose or {'
dose commitment greater than values currently being calculated in accordance with Section 3.4.3, identify the new location (s) in the next Radioactive Effluent Release Report ".
4.3 Changes in the Radiological Environmental Monitoring Program For this reporting period, there have been no changes to the Radiological Environmental ;
Monitoring Program. j 5.0 Doses to Members of the Public Inside the Site Boundary
-7.2.2.3 states in part:
68
"The report shall also include assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period; this assessment must be performed in accordance with Chapter 6. All assumptions used in making these assessments ( i.e.,
specific activity, exposure time, and location) shall be included in the report".
The location of concern within the site boundary is the Visitors Center. The activities at the Visitor Center consist of occasional attendance at meetings and/or short visits for informational purposes.
There will be no radiation dose at this location due to radioactive liquid effluents.
Delineated in Table 4-1 for this location are the values of the basic data assumed in the dose assessment due to radioactive gaseous effluents. Listed in this table are distance l and direction from a point midway between the center of Unit 1 and the Unit 2 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.
The source term is not listed in Table 41. The source term is listed in Tables 2-3A,2-3AA,2-38, and 2-3BB for the mixed mode releases. Similarly, it is listed in Tables 2,4A, 2-4AA,2-48, and 2-4BB for the ground level releases.
The maximum doses in units of mrem to an individual MEMBER OF THE PUBLIC due to their activities inside the site boundary during the reporting period were assessed to be ,
as follows- !
I VISITOR CENTER Ouader l and 2 Quader 3 and 4 Total Body 9.98E-07 1.95E-08 (Direct Radiation from Plume)
VISITOR CENTER Ouader1 Quader 2 Quader 3 Quader 4 Maximum Organ 2.17E-06 7.09E-07 5.67E-07 5.91 E-07 (Thyroid)
(Inhalation Ground Plane) l 69
TABLE 31 Page 1 of 7 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1998)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY 1,1998 THROUGH JUNE 30,1998 A. 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, evaporator m3 1.877E+01 bottoms, etc. Cl 2.773E+05 1.0E+01
- b. Dry compressible waste, contaminated m3 1.064E+01 equip. etc. Cl 2.902E+00 4.0E+01
- c. Irradiated components, control m3 5.409E-01 rods, etc. Cl 2.71 E+02 1.0E+01
- d. Other(describe) m3 j Ci NONE N/A l
- 2. Estimate of mejor nuclide composition (by type of waste).
- d. N/A % N/A N/A % N/A 1
70 j
Table 3-1 Cont'd Page 2 of 7 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1998)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY 1,1998 THROUGH JUNE 30,1998
- 3. Solid Waste Disposition Number of Mode of Shlomonts Transoortation Destination i Chem-Nuclear Systems, Inc. ]
5 Tractor / Trailer / Cask Barnwell, SC '
Scientific Ecology Group, 9 Tractor / Trailer Oak Ridge TN.
American Ecology Recycle 4 Tractor / Trailer Center, Oak Ridge TN.
B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Mode of Shlomonts Transportation Destination None None None I
l 71
l TABLE 3-1 cont'd Page 3 of 7 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1998)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY 1,1998 THROUGH JUNE 30,1998 ADDITIONAL INFORMATION REQUIRED BY ODCM:
' Shipments Directly to disposal:
VOLUME j Shioment No. Waste Class Tvoe Container Shinoina Class Solidification Acent (direct to disoosal ontv) )
RWS-98-001 BSTABLE TYPE A LSA 2 NONE 135.8 l RWS-98-002 A STABLE TYPE A LSA 2 NONE 19.1 RWS-98-003 BSTABLE TYPE A ' LSA 2 NONE 135.8 RWS-98-004 8 STABLE TYPE A LSA 2 NONE 195.7
]
RWS-98-005 BSTABLE TYPE A LSA 2 NONE 195.7 )
Shipments to a Waste Processor Shioment No. Waste Class Tvce Container Shiocina Class Solidification Aaent RVRS-98-001 A UNSTABLE STRONG TIGHT LSA 2 NONE RVRS-98-002 A UNSTABLE STRONG TIGHT LQ NONE RVRS-98-003 A UNSTABLE STRONG TIGHT LQ NONE RVRS-98-004 A UNSTABLE STRONG TIGHT LQ NONE RVRS-98-005 A UNSTABLE STRONG TIGHT LSA 2 NONE I RVRS-98-006 A UNSTABLE STRONG TIGHT LSA 2 NONE RVRS-98-007 A UNSTABLE STRONG TIGHT LSA 2 NONE RVRS-98-006 A UNSTABLE STRONG TIGHT LSA 2 NONE RVRS-98-009 A UNSTABLE STRONG TIGHT LSA 2 NONE l RVRS-98-010 A UNSTABLE STRONG TIGHT LSA 2 NONE
]
RVRS-98-011 A UNSTABLE STRONG TIGHT LSA 2 NONE
)
RVRS-98-012 A UNSTABLE STRONG TIGHT LQ NONE RVRS-96-013 A UNSTABLE STRONG TIGHT LQ NONE l
72 l
TABLE 3-1 page 4 Of 7 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1996)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JULY 1,1998 THROUGH DECEMBER 31,1998.
A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)
- 1. Type of waste Unit 6-month Est. Total
- a. Spent resins, filter sludges, evaporator m3
- bottoms, etc. Cl NONE N/A b.. Dry compressible waste, contaminated m3 6.424E+00 equip, etc. Cl 1.284E+01 4.0E+01 - I
- c. Irradiated components, control m3 rods, etc. Cl NONE N/A
- d. Other(describe) m3 Ci NONE N/A
- 2. Estimate of major nuclide composition (by type of wasto). ,
)
a.NONE % N/A ]
NONE % N/A NONE % N/A NONE- % N/A
- b. H 3 % 6.037E+01 Ni-63 % 1.668E+01 Co-58 % 3.578E+00 All others % 1.937E+01
, c. N/A % N/A N/A % N/A N/A % N/A N/A % N/A
- d. N/A % N/A N/A % N/A N/A % N/A
.i l
l 73
TABLE 3-1 cont'd Page 5 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1998)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 1
JULY 1,1998 THROUGH DECEMBER 31,1998. l I
- 3. Solid Waste Disposition Number of Mode of l
i Shipments Transportation Destination 5- Tractor / Trailer Scientific Ecology Group, Oak Ridge TN.
5 Tractor / Trailer American Ecology Recycle Center, Oak Ridge TN.
1 Tractor / Trailer Diversified Scientific Services, Inc. OoKRidge, TN i 3 Tractor / Trailer Allied Technology, Richland '
Washington 1 Tractor / Cask / Allied Technology, Oak ,
Trailer Ridge, TN l 2 Tractor / Trailer Manufactured Sciences Inc. !
Oak Ridge, TN B. IRRADIATED FUEL SHIPMENTS '
(Disposition)
Number of Mode of Shloments Transportation Destination None None None 1 i
I 1
l l
74 l
TABLE 3-1 Cont'd Page 6 of 7 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1998)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS )
J JULY 1,1998 THROUGH DECEMBER 31,1998.
ADDITIONAL INFORMATION REQUIRED BY ODCM:
1 Shioment No. Waste Class Tvoe Container Shiocino Class Solidification Acent I RVRS-98-014 A UNSTABLE STRONG TIGHT LO NONE RVRS-98-015 A UNSTABLE STRONG TIGHT LO NONE i RVRS-98-016 A UNSTABLE STRONG TIGHT LSA 2 NONE RVRS-98-017 A UNSTABLE STRONG TIGHT LO NONE !
RVRS-98 018 A UNSTABLE STRONG TIGHT LQ NONE j RVRS-98-019 A UNSTABLE STRONG TIGHT LSA 2 NONE RVRS-98-020 A UNSTABLE STRONG TIGHT LSA 2 NONE ,
RVRS-98-021 A UNSTABLE STRONG TIGHT LSA 2 NONE RVRS-98-022 A UNSTABLE STRONG TIGHT LSA 2 NONE RVRS-98-023 A UNSTABLE STRONG TIGHT LSA 2 NONE RVRS-98-024 A UNSTABLE STRONG TIGHT LSA 2 NONE RVRS-98-025 A UNSTABLE STRONG TIGHT LSA 2 NONE I RVRS-98-026 A UNSTABLE STRONG TIGHT LO NONE RVRS-98-027 A UNSTABLE STRONG TIGHT LO NONE l RVRS-98-028 A UNSTABLE STRONG TIGHT LSA 2 NONE ]
RVRS-98-029 A UNSTABLE STRONG TIGHT LSA 2 NONE J RVRS-98-030 A UNSTABLE STRONG TIGHT LO NONE 1
i l
75 4
I l
TABLE 3-1 Addendum Page 7 of 7 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1998)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Container volumes for years 1996 and 1997 Shioment No. VOLUME in ft3 l
RWS-96-001 174.3 l
RWS-96-002 132.4 )
RWS-96-003 174.3 i RWS-96-004 195.2 RWS-96-005 195.2 Shloment No. VOLUME in ft3 RWS97-001 135.8 RWS-97-002 135.8 RWS-97-003 26.2 76
1 Table 4-1 ,
Vogtle Electric Generating Plant i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 i DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Starting: 01-Jan 1998 Ending: 31-Dec-1998 l 1
Location Name Visitor Center Distance (meters) 4.47e+02 Sector SE X/O(sec/m3) (1) 5.93E-06 Depleted X/Q(sec/m3) (2) 5.58E-06 D/O(nf2) (1) 2.28E-08 X/Q(Sec/m3) (2) 7.12E-07 Depleted X/Q(sec/m3) (2) 6.74E-07
' D/Q(m2) (2) 5.77E-09 Occupancy Factor 0.00046(4hr/yr)
Age Group Child VISITOR CENTER
~
UNITS OTR 1 QTR2 Total Q1 OTR3 QTR4 Total O3 l
& O2 & O4 ,
Total mrem 9.85e-07 1.32e-08 9.98e-07 8.34e-09 1.12e-08 1.95E-08 Body Dose l Organ Bone mrem- 1.03E-06 1.50E-08 1.05e-06 9.05E-09 1.11 E-08 2.02E-08 Liver mrem 2.04E-06 6.36E-07 2.68E-06 5.65E-07 5.90E-07 1.16E-06 Tbody mrem 2.04E-06 6.36E-07 2.68E-06 5.65E-07 5.90E 07 1.16E-06 Thyroid mrem 2.17E-06 7.09E-07 2.88E-06 5.67E-07 5.91 E-07 1.16E-06 Kidney mrem 2.04E-06 6.37E-07 2.68E-06 5.65E-07 5.90E-07 1.16E-06 Luna mrem 2.04E-06 6.36E-07 2.68E-06 5.65E-07 5.90E-07 1.16E-06 GI-LLI mrem 2.04E-06 6.36E-07 2.68E-06 5.65E-07 5.90E-07 1.16E 06 I
77 l w- . . . . .
N
q l
l 6.0 . Major Changes to Liquid, Gaseous, or Solid Radweste Treatment Systems ODCM 7.2.2.7 states in part:
As required by Sections 2.1.5 and 3.1.6, licensee initiated MAJOR CHANGES TO j RADIOACTIVE WASTE TREATMENT SYSTEMS (liquid and gaseous) shall be reported i to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report ;
covering the period in which the change was reviewed and accepted for implementation. '
Note 1: In lieu of inclusion in the Radioactive Effluents Release Report, this same l Information may be submitted as part of the annual FSAR update.
Gaseous Radwaste System There were no ma 'r changes to the gaseous radwaste system in 1998.
Liquid Radwasco System There were no major changes to the Liquid Radwaste Treatment System in 1998. ,
i PCP 12.1 states in part:
Licensee major initiated changes to the solid radioactive waste treatment system shall be reported to the Nuclear Regulatory Commission in the Annual Radioactive Effluent Release Report for the period in which the change was implemented.
Solid Radweste System There were no major changes to the solid radwaste system in 1998.
7.0 Meteorological Data ODCM 7.2.2.2 states in part:
l The Radioactive Effluent Release Report shallinclude an annual summary of hourly meteorological data collected over the previous year. This annual summary may be ,
either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape; or in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.
I in lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
78
1 8.0 Program Deviations
{
ODCM 7.2.2.6 states in part that:
8.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation l
The report shall include deviations from the liquid and gaseous effluent monitoring !
instrumentation operability requirements included in Sections 2.1.1 and 3.1.1, j respectively. The report shall include an explanation as to why the inoperability of liquid '
or gaseous effluent monitoring instrumentation was not corrected within the specified time requirement.
The inoperability of liquid and gaseous effluent monitors was corrected within the specified time for this reporting period.
8.2 Tanks Exceeding Curie Content Limits The report shall include a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specifications 5.5.12.
~
There were no outdoor liquid hold-up tanks used for radioactive liquids during this reporting period. Limits for the gas storage tanks were not exceeded during this reporting period.
h 79 k