ML20138F093
| ML20138F093 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/31/1996 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20138F075 | List: |
| References | |
| NUDOCS 9705050260 | |
| Download: ML20138F093 (91) | |
Text
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1 IV VOGTLE ELECTRIC GENERATING PLANT- UNITS 1 AND 2 ,
1996 ANNUAL REPORT- PART 2 l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i
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1 9705050260 970428 DR ADOCK 05000424 PDR ,
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VOGTLE ELECTRIC GENERATING PLANT ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES i
i l SECTION TITLE PAGE }
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! 1.0 Liquid Effluents 8 l 1.1 Regulatory Limits / Technical Specifications 8 1.1.1 Concentration Limits 8 I l
1.1.2 Dose Limits 8 1.2 Effluent Concentration Limit 8 1.3 Measurements and Approximations of Total 9 Radioactivity l 1.4 Liquid Effluent Release Data 11 1.4.1 Tables 11 1.4.2 Total Error Measurement 11 1.5 RadiologicalImpact on Man Due to Liquid Release 12 1.6 Abnormal Releases 12 1.7 River Flow 12 2.0 Gaseous Effluents 34 2.1 Regulatory Limits / Technical Specifications 34
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SECTION TITLE PAGE 1
2.1.1 Dose Rate Limit 34 l i
- 2.1.2 Air Dose Due to Noble Gas 34 3
2.1.3 Dose to Any Organ 34 i-
- 2.1.4 Total Fuel Cycle Dose Commitment (40CFR190) 35 i
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! 2.2 Release Points of Gaseous Effluents 35 2.3 Sample Collection and Analysis 35 2.4 Total Quantities of Radioactivity, Dose Rates 36 l and Cumulative Doses l 2.4.1 Fission and Activation' Gas 36 2.4.2 Radiolodines, Tritium and Particulate Releases 36 2.4.3 Gross Alpha Release 37 2.5 Gaseous Effluent Release Data 38 2.5.1 Methodology 38 2.5.2 Gaseous Batch Data 40 2.6 Radiological Impact Due to Gaseous Releases 40 2.7 Abnormal Releases 40 2
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SECTION TITLE PAGE 3.0 Solid Waste 80 3.1 Regulatory Limits /Tschnical Specifications 80 3.1.1 Use of Solid Radioactive Waste System 80 3.1.2 Reporting Requirements 80 3.1.3 Process Control Program (PCP) 80 3.2 Solid Waste Data 81 4.0 Changes to the Vogtle Electric Generating Plant 81 ODCM 4.1 Changes in the Radiological Environmental 82 Monitoring Program 5.0 Doses to Members of the Public Inside The 82 Site Boundary 6.0 Major Changes to the Liquid, Gaseous and 89 Solid Radwaste Treatment Systems 7.0 Meteorology 89 8.0 Inoperable Liquid or Gaseous Effluent 89 Monitoring Instrumentation 9.0 Tanks Exceeding Curie Content Limits 90 3
i VOGTLE ELECTRIC GENERATING PLANT j ANNUAL REPORT l PLANT RADIOACTIVE EFFLUENT RELEASES i
l TABLE LIST OF TABLES PAGE i 1-2A Liquid Effluents - Summation of All Releases 13 i Unit 1 j 1-2AA Liquid Effluents - Summation of All Releases 14 i
Unit 1 l
- 1-2B Liquid Effluents - Summation of All Releases 15 i Unit 2 i
! 1-2BB Liquid Effluents - Summation of All Releases 16 3
Unit 2 i
- 1-2C Liquid Effluents - Summation of All Releases 17
- Site i
i 1-2CC Liquid Effluents - Summation of All Releases 18
- Site
) 1-3A Liquid Effluents - Unit 1 19 1-3AA Liquid Effluents - Unit 1 20 l
j 1-38 Liquid Effluents - Unit 2 21 l 1-3BB Liquid Effluents - Unit 2 22 i
) 1-3C Liquid Effluents - Site 23
- 1-3CC Liquid Effluents - Site 24 e
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'i TABLE -
LIST OF TABLES PAGE 1-4A Individual Doses Due to Liquid Releases 25 Unit 1 1-4B Individual Doses Due to Liquid Releases 26 Unit 2 1-4AA Individual Doses Due to Liquid Releases 27 Unit 1 1-4BB Individual 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 1-6B Batch Release Summary of All Releases 31 Unit 2 1-6AA Batch Release Summary of All Releases 32 l Unit 1 1-6BB Batch Release Summary of All Relerces 33 Unit 2 2-2A Airborne Effluents - Summation of All 42 Releases - Unit 1 2-2B Airborne Effluents - Summation of All 43 Releases -Unit 2 2-2C Airborne Effluents - Summation of All 44 Releases - Site 5
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TABLE LIST OF TABLES PAGE 2-2BB Airborne Effluents - Summation of All 44 Releases -Unit 2 2-2C Airborne Effluents - Summation of All 45 Releases - Site i I
2 2CC Airborne Effluents - Summation of All 46 Releases - Site ;
1 2-3A Gaseous Effluents - Mixed Mode Releases 47 l Unit 1 l 2-3AA Gaseous Effluents - Mixed Mode Releases 49 Unit 1 2-3B Gaseous Effluents - Mixed Mode Releases 51 ;
Unit 2 !
2-3BB Gaseous Effluents - Mixed Mode Releases 53 I Unit 2 2-3C Gaseous Effluents - Mixed Mode Releases 55 Site 2-3CC Gaseous Effluents - Mixed Mode Releases 57 Site 2-4A Gaseous Effluents - Ground Level Release 59 Unit 1 2-4AA Gaseous Effluents - Ground Level Release 61 ,
Unit 1 2-4B Gaseous Effluents - Ground Level Release 63 Unit 2 6
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1 TABLE LIST OF TABLES PAGE l
i 2-488 Gaseous Effluents - Ground Level Release 65 2
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Unit 2 )
j 2-4C Gaseous Effluents - Ground Level Release 67 l
- Site '
i i 2-4CC Gaseous Effluents - Ground Level Release 69
) Site 3 . 2-6A Air Doses Due to Noble Gases - Unit 1 71 2-6AA Air Doses Due to Noble Gases - Unit 1 72 !
j 2-6B Air Doses Due to Noble Gases - Unit 2 73 1
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2-6BB Air Doses Due to Noble Gases - Unit 2 74 i
i 2-7A Individual Doses Due to Radiolodines, 75 ,
! Tritium, and Particulates in Gaseous
! Releases - Unit 1 l
l' 2-7AA Individual Doses Due to Radiolodines, 76 Tritium, and Particulates in Gaseous j Releases - Unit 1 k
l 2-78 Individual Doses Due to Radiolodines, 77 i j Tritium, and Particulates in Gaseous
! Releases - Unit 2 2-7BB Individual Doses Due to Radiolodines, 78 l Tritium, and Particulates in Gaseous Releases - Unit 2 i
~ 2-8 Minimum Detectable Concentration - 79 Gaseous Sample Analyses 3-1 Solid Waste and Irradiated Fuel Shipments 84 4-1 Dose to A Member of the Public Due to Activities 88 Inside The Site Boundary 7
1 1.0 Liquid Effluents 1.1 Regulatory Limits / Technical Specifications 101.1 Concentration Limits 1 The concentration of radioactive material released in liquid effluents
- to UNRESTRICTED AREAS shall be limited to the corscentrations l specified in 10 CFR Part 20, Appendix B, Table ll, Column 2 for l E radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1.0E-4 microcuries/ml total activity.
1 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; j
- 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. i 1.2 Effluent Concentration Limit (ECL) !
ECL values used in determining allowable liquid radweste release ;
l rates and concentrations for principal gamma emitters,1-131, tritium, i Sr-89, Sr-90 and Fe-55 are taken from 10 CFR Part 20, Appendix B, Table ll, Column 2. A tolerance factor up to 10 is selected to allow flexibility in the establishment of a practical monitor set point which
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could accommodate effluent releases at concentrations higher than the ECL values stated in 10 CFR 20, Appendix B, Table 2, Column 2.
For dissolved or entrained noble gases in liquid radwaste, the ECL is 1E-04 pCi/mi total activity.
For gross alpha in liquid radwaste, the ECL is 2.0E-09 pCi/ml. l Further, for all the above radionuclides or categories of radioactivity, the overall ECL fraction is determined in accordance with 10 CFR Part 20, Appendix B.
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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.
i 1,3 Measurements and Appro.wimations of Total Radioactivity Prior to the release of any tank conti:iining liquid radwaste, and following the ;
j required recirculations, samples are collected and analyzed in accordance with
. the Offsite Dose Calculation Manual (ODCM) Table 2-3. A sample from each tank :
j which is planned for release is analyzed for principal gamma emitters,1-131, and I l dissolved and entrained noble gases by gamma spectroscopy. Monthly and )
- quarterly composites are prepared for analysis by extracting aliquois from each I sample taken from the tanks which are released. Liquid radwaste sample l l analyses are performed as follows: )
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! MEASUREMENT FREQUENCY METHOD
- 1. Gamma Isotopic Each Batch Gamma Spectroscopy ;
with computerized ,
data reduction.
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- 2. Dissolved or entrained Each Batch Gamma Spectroscopy ,
l noble gases with computerized 1 data reduction
- 3. Tritium Monthly Distillation and
. Composite liquid scintillation
!- counting
- 4. Gross Alpha Monthly Gas flow proportional Composite counting
- 5. Sr-89 & St-90 Quarterly Chemical separation Composite and gas flow proportional or i
scintillation counting i 6. Fe-SS Quarterly Chemical separation
- Composite and liquid scintillation counting
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Gamma isotopic measurements are performed using germanium detectors with a
> resolution of 1.80 kev or lower. A liquid radwaste sample is typically counted for 2000 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- ;
i 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 l 1 g l .
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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 analysis is done onsite in most cases. Gross Alpha, Sr-89, Sr-90 and Fe-55 are analyzed offsite.
The radionuclide concentrations determined by gamma spectroscopic analysis of sample taken from a tank for tanks planned for release and the most current sample 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 I assured dilution stream flow to calculate maximum permissible release rates and a liquid l 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 .
l 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 l
stream flow monitor.
Radionuclide concentrations, safety factors, dilution stream flow rate, and liquid effluent radiation monitor calibrations are entered into the computer and a pre-release printout is generated. If the release is not permissible, appropriate warnings will be 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.
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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,1-2B,1-2BB,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. l I
1.4.2 Total Error Measurement l The total or maximum error associated with the effluent measurement l includes the cumulative errors resulting from the total operation of l 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.
1.4.2.1 Fission and activation total release was calculated from sample analysis l results and release point flow rates.
Sampling and statistical error 10%
Counting Equipment Calibration 10%
Tank Volumes and System Flow Rates 20 %
TOTAL ERROR 40%
1.4.2.2 Total Tritium release was calculated from sample analysis results and release point volumes.
Sampling and statistical errors 10%
Counting equipment calibration 10%
Tank volumes and system flow rate 20 %
TOTAL ERROR 40%
1.4.2.3 Dissolved and entrained gases were calculated from sample analysis results and release point volumes.
Sampling and statistical error 20 %
Counting equipment calibration 10%
Tank volumes and system flow rate 20%
TOTAL ERROR 50 %
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1.4.2.4 Gross alpha radioactivity was calculated from sample analysis results and release point volumes.
' Sampling and statistical error 10%
Counting Equipment calibration 10%
Tank volumes and system flowrates 20 %
Compositing sample error 5% l TOTAL ERROR 45% l i
1.4.2.5 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%
1.4.2.6 Volume of dilution water used was calculated from flow rate indicators I
and pump discharge flow rates and times.
4 Flow rate indicator error 10%
Operator interpretation of gauge 10%
TOTAL ERROR 20 %
1.5 Radiological Impact on Man Due to Liquid Releases Doses to an individual due to radioactivity in liquid effluent were calculated in accordance with the Offsite Dose Calculation Manual. Results are presented in Table 1-4A,1-4AA for Unit 1 and 1-48,1-48B for Unit 2, for all four quarters.
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 for the Annual Effluent ,
Report period was obtained from the Clark Hill Dam, Corp of Engineers Office. The average flow rate is 9636 cubic feet /sec.
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l TABLE 12 A 3
GEORGIA POWER COMPANY
.. VOGTLE ELECTRIC GENERATING PLANT l . ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 1996 ALL LIQUID EFFLUENTS l UNIT : 1 l STARTING : 1-JAN-1996 ENDING : 30-JUN-1996 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR % 4 l A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 1.88E-01 1.66E-01 25 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCl/ML 4.83E-07 4.18E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 8. TRITIUM
- 1. TOTAL RELEASE CURIES 3.00E+02 3.75E+02 25 l
- 2. AVERAGE DILUTED C.ONCENTRATION uCi/ML 7.71E-04 9.46E-04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 2.96E-03 1.15E-02 25
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 7.60E-09 2.90E-08 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 25 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 1.10E+06 1.18E+06 25 F. VOLUME OF DILUTION WATER USED LITRE 3.88E+08 3.95E+08 25
- Apphcable limits are expressed in terms of Dose. See Tabe 1-4A of this report 13
TABLE 1-2AA GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996 ALL LIQUID EFFLUENTS UNIT : 1 STARTING : 1-JUL-1996 ENDING : 31-DEC-1996 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL l ERROR % l A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 1.25E-01 7.37E-02 25 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 6.98E-07 3.63E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- j B. TRITIUM
- 1. TOTAL RELEASE CURIES 5.95E+01 6.74E+01 25
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 3.33E-04 3.31 E-04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1.25E-03 5.52E-05 25
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML '7.00E-09 2.71 E-10 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 1.10E-05 6.96E-06 25 LITRE 5.12E+05 5.92E+05 25 E. WASTE VOL RELEASED (PRE-DILUTION)
F. VOLUME OF DILUTION WATER USED LITRE 1.78E+08 2.03E+08 25
- Applicable hmits are expressed in terms of Dose. See Table 1-4AA of this report 14
TABLE 1-28 GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996 ALL LIQUID EFFLUENTS UNIT : 2 STARTING : 1-JAN-1996 ENDING : 30-JUN-1996 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS )
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 4.12E-02 4.87E-02 25 TRITIUM, GASES, ALPHA) i
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 3.98E-07 4.82E-07 l DURING PERIOD ,
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- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM I
- 1. TOTAL RELEASE CURIES 1.45E+02 1.36E+02 25
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 1.40E-03 1.35E-03 j DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES l
- 1. TOTAL RELEASE CURIES 8.64E-04 4.01 E-03 25
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 8.34E-09 3.97E-08 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 25 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 2.82E+05 2.89E+05 25 F. VOLUME OF DILUTION WATER USED LITRE 1.03E+08 1.01E+08 25
- Applicable hmits are expressed in terms of Dose. SeeTable 1-4B of this report 15
TABLE 1-2BB GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996 ALL LIQUID EFFLUENTS UNIT : 2 STARTING : 1-JUL-1996 ENDING : 31-DEC-1996 TYPE OF EFFLUENT UNITS QUARTER 3 OUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 2.71E-01 5.95E-02 25 TRITIUM, GASES. ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 4.49E-07 2.89E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM
- 1. TOTAL RELEASE CURIES 4.81E+02 7.17E+01 25
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 7.97E-04 3.47E-04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES 4
- 1. TOTAL RELEASE CURIES 2.15E-02 8.38E-04 25
- 2. AVERAGE DILUTED CONCENTRAT80N uCi/ML 3.57E-08 4.05E-09 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 0.00E+00 7.49E-06 25 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 1.72E+06 6.89E+05 25 F. VOLUME OF DILUTION WATER USED LITRE 6.02E+08 2.06E+08 25
- Applicable hmits are expressed in terms of Dose. See Table 1-4BB of this report 16
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l TABLE 1-2C 1
l GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT j ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996 ALL LIQUID EFFLUENTS SITE STARTING : 1-JAN-1996 ENDING : 30-JUN-1996 l 1
TYPE OF EFFLUENT UNITS OUARTER1 OUARTER 2 EST. TOTAL ERROR % l A. FISSION & ACTIVATION PRODUCTS CURIES 2.29E-01 2.15E-01 25 l
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) l
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 4.65E-07 4.31 E-07 l
DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM CURIES 4.45E+02 5.11E+02 25
- 1. TOTAL RELEASE
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 9.02E-04 1.03E-03 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES CURIES 3.82E-03 1.55E-02 25
- 1. TOTAL RELEASE
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 7.75E-09 3.12E-08 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT % ,
D. GROSS ALPHA RADIOACTIVITY CURIES 0.00E+00 0.00E+00 25
- 1. TOTAL RELEASE 1.38E+06 1.47E+06 25 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE LITRE 4.92E+08 4.96E+08 25 F. VOLUME OF DILUTION WATER USED
- Apphcable hmits are expressed in terms of Dose. See Table 1-4A and 1-4B of trus report 17
TABLE 1-2CC GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL. RADIOACTIVE EFFLUENT RELEASE REPORT-1996 ALL LIQUID EFFLUENTS SITE STARTING : 1-JUL-1996 ENDING : 31-DEC-1996 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 3.96E-01 1.33E-01 25 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 5.06E-07 3.25E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM
- 1. TOTAL RELEASE CURIES 5.41 E+02 1.39E+02 25
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 6.91 E-04 3.39E-04 DURING PERIOD
. 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 2.28E-02 8.93E-04 25
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 2.91 E-08 2.18E-09 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 1.10E-05 1.44E-05 25 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 2.23E+06 1.28E+06 25 F. VOLUME OF DILUTION WATER USED LITRE 7.80E+08 4.08E+08 25
- Applicable limits are expressed in terms of Dose. See Table 1-4AA and 1-488 of this report 18
l TABLE 1-3A Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996 Liquid Effluents
-. Starting : 1-Jan-1996 Ending : 30-Jun-1996 UNIT : 1 CONTINUOUS BATCH NUCLlDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 H-3 CURIES 0.00E+00 0.00E+00 3.00E+02 3.75E+02 FISSION & ACTIVATION PRODUCTS:
AG-110M CURIES 0.00E+00 0.00E+00 6.75E-04 0.00E+00 Ce-141 CURIES 0.00E+00 0.00E+00 0.00E+00 2.52E-05 Co-57 CURIES 0.00E+00 0.00E+00 2.46E-04 1.99E-05 Co-58 CURIES 0.00E+00 0.00E+00 2.03E-02 2.48E-02 Co-60 CURIES 0.00E+00 0.00E+00 4.55E-02 1.32E-02 Cr-51 CURIES 0.00E+00 0.00E+00 2.19E-02 1.57E-02 Cs-134 CURIES 0.00E+00 0.00E+00 3.17E-05 4.98E-05 Cs-137 CURIES 0.00E+00 0.00E+00 8.23E-05 1.59E-05 ;
Fe-55 CURIES 0.00E+00 0.00E+00 7.14E-02 5.64E-02 i Fe-59 CURIES 0.00E+00 0.00E+00 2.66E-03 6.86E-04 1 1-131 CURIES 0.00E+00 0.00E+00 0.00E+00 6.70E-03 I l-133 CURIES 0.00E+00 0.00E+00 0.00E+00 9.06E-05 j LA-140 CURIES 0.00E+00 0.00E+00 6.85E-06 2.74E-04 MN-54 CURIES 0.00E+00 0.00E+00 1.04E-02 4.68E-03 NB-95 CURIES 0.00E+00 0.00E+00 3.30E-03 4.15E-03 l NS-97 CURIES 0.00E+00 0.00E+00 1.56E-04 3.65E-05 i SB-122 CURIES 0.00E+00 0.00E+00 0.00E+00 3.77E-04 SB-124 CURIES 0.00E+00 0.00E+00 2.13E-04 1.51E-03 SB-125 CURIES 0.00E+00 0.00E+00 8.64E-03 2.77E-02 SN-113 CURIES 0.00E+00 0.00E+00 1.38E-04 1.01 E-04 SR-89 CURIES 0.00E+00 0.00E+00 0.00E+00 1.71 E-04 SR-92 CURIES 0.00E+00 0.00E+00 2.97E-05 0.00E+00 TC-99M CURIES 0.00E+00 0.00E+00 0.00E+00 2.72E-05 TE-125M CURIES 0.00E+00 0.00E+00 0.00E+00 6.40E-03 TE-129M CURIES 0.00E+00 0.00E+00 2.24E-04 0.00E+00 TE-132 CURIES 0.00E+00 0.00E+00 6.14E-05 3.92E-05 ZR-95 CURIES 0.00E+00 0.00E+00 2.06E-03 2.66E-03 TOTALS 0.00E+00 0.00E+00 1.88E-01 1.66E-01 DISSOLVED AND ENTRAINED GASES:
Xe-133 CURIES 0.00E+00 0.00E+00 2.96E-03 1.15E-02 TOTALS Q&QfiQQ 0.00E+00 2.96E-03 1.15E-02 G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 19
TABLE 1-3AA Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996 Liquid Effluents
.. Starting : 1-Jul-1996 Ending : 31-Dec-1996 UNIT : 1 CONTINUOUS BATCH NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 H-3 CURIES 0.00E+00 0.00E+00 5.95E+01 6.74E+01 FISSION & ACTIVATION PRODUCTS:
Ag-110M CURIES 0.00E+00 0.00E+00 0.00E+00 2.11 E-05 Ce-141 CURIES 0.00E+00 0.00E+00 0.00E+00 6.04E-05 Ce-144 CURIES 0.00E+00 0.00E+00 0.00E+00 1.29E-04 Co-57 CURIES 0.00E+00 0.00E+00 3.00E-04 1.53E-04 Co-58 CURIES 0.00E+00 0.00E+00 1.57E-02 1.44E-02 Co-60 CURIES 0.00E+00 0.00E+00 4.08E-02 1.43E-02 Cr-51 CURIES 0.00E+00 0.00E+00 5.43E-03 7.03E-03 l Cs-134 CURIES 0.00E+00 0.00E+00 3.23E-06 9.50E-05 Cs-137 CURIES 0.00E+00 0.00E+00 1.22E-05 5.12E-05 Fe-55 CURIES 0.00E+00 0.00E+00 3.48E-02 1.67E-02 Fe-59 CURIES 0.00E+00 0.00E+00 1.43E-04 6.24E-04 l-131 CURIES 0.00E+00 0.00E+00 1.31 E-04 1.65E-04 La-140 CURIES 0.00E+00 0.00E+00 0.00E+00 9.45E-06 Mn-54 CURIES 0.00E+00 0.00E+00 8.68E-03 4.49E-03 Nb-95 CURIES 0.00E+00 0.00E+00 4.41E-03 3.38E-03 Nb-97 CURIES 0.00E+00 0.00E+00 1.03E-04 1.08E-04 ;
Ru-103 CURIES 0.00E+00 0.00E+00 0.00E+00 1.12E-04 Sb-124 CURIES 0.00E+00 0.00E+00 1.74E-04 2.77E-04 i Sb-125 CURIES 0.00E+00 0.00E+00 1.16E-02 9.17E-03 Sn-113 CURIES 0.00E+00 0.00E+00 1.68E-04 2.88E-04 Sr-89 CURIES 0.00E+00 0.00E+00 0.00E+00 9.88E-05 Sr-92 CURIES 0.00E+00 0.00E+00 0.00E+00 2.68E-05 2 Zr-95 CURIES 0.00E+00 0.00E+00 2.31E-03 1.99E-03 l TOTALS 0.00E+00 0.00E+00 1.25E-01 7.37E-02 DISSOLVED AND ENTRAINED GASES:
Xe-133 CURIES 0.00E+00 0.00E+00 1.25E-03 5.52E-05 TOTALS 0.00E+00 0.00E+00 1.25E-03 5.52E-05 G-ALPHA CURIES 0.00E+00 0.00E+00 1.10E-05 6.96E-06 20
TABLE 13B Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996 Liquid Effluents
. Starting : 1-JAN-1996 Ending : 30-JUN-1996 UNIT : 2 '
CONTINUOUS BATCH NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 H-3 CURIES 0.00E+00 0.00E+00 1.45E+02 1.36E+02 FISSION & ACTIVATION PRODUCTS:
Co-57 CURIES 0.00E+00 0.00E+00 7.59E-05 2.05E-05 Co-58 CURIES 0.00E+00 0.00E+00 8.76E-04 3.53E-03 Co-60 CURIES 0.00E+00 0.00E+00 1.50E-02 4.47E-03 Cr-51 CURIES 0.00E+00 0.00E+00 0.00E+00 2.89E-03 Cs-134 CURIES 0.00E+00 0.00E+00 2.97E-05 4.31E-05 Cs-137 CURIES 0.00E+00 0.00E+00 3.54E-05 2.80E-05 Fe-55 CURIES 0.00E+00 0.00E+00 2.03E-02 2.65E-02 1-131 CURIES 0.00E+00 0.00E+00 0.00E+00 2.40E-03 1133 CURIES 0.00E+00 0.00E+00 0.00E+00 1.25E-04 ,
La-140 CURIES 0.00E+00 0.00E+00 0.00E+00 6.40E-05 .
Mn-54 CURIES 0.00E+00 0.00E+00 2.78E-03 1.08E-03 Nt>95 CURIES 0.00E+00 0.00E+00 1.54E-04 6.68E-04 Nb-97 CURIES 0.00E+00 0.00E+00 6.85E-05 4.96E-05 Sb-124 CURIES 0.00E+00 0.00E+00 0.00E+00 3.33E-04 Sb-125 - CURIES 0.00E+00 0.00E+00 1.76E-03 6.00E-03 Sn-113 CURIES 0.00E+00 0.00E+00 0.00E+00 3.13E-05 Sr-90 CURIES 0.00E+00 0.00E+00 0.00E+00 7.60E-07 Sr-92 CURIES 0.00E+00 0.00E+00 3.46E-05 0.00E+00 Zn-65 CURIES 0.00E+00 0.00E+00 1.21E-04 0.00E+00 Zr-95 CURIES 0.00E+00 0.00E+00 0.00E+00 4.50E-04 TOTALS 0.00E+00 0.00E+00 4.12E-02 4.87E-02 DISSOLVED AND ENTRAINED GASES:
Xe-133 CURIES 0.00E+00 0.00E+00 8.64E-04 4.01 E-03 LOTALS 0.00E+00 0.00E+00 8.64E-04 4.01E-03 G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
21
1 i
l TABLE 1-3BB Vogtle Electric Generating Plant !
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996
. Liquid Effluents Starting : 1-Jul-1996 Ending : 31-Dec-1996 UNIT : 2 CONTINUOUS BATCH NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 i H-3 CURIES 0.00E+00 0.00E+00 4.81 E+02 7.17E+01 I FISSION & ACTIVATION PRODUCTS Ag-110M CURIES 0.00E+00- 0.00E+00 9.49E-05 0.00E+00 j Co-57 CURIES 0.00E+00 0.00E+00 3.12E-04 1.52E-05 Co-58 CURIES 0.00E+00 0.00E+00 2.55E-02 9.17E-03 l Co-60 CURIES 0.00E+00 0.00E+00 5.30E-02 7.10E-03 Cr-51 CURIES 0.00E+00 0.00E+00 1.52E-02 7.47E-03 Cs-134 CURIES 0.00E+00 0.00E+00 6.16E-05 2.09E-06 Cs-137 CURIES 0.00E+00 0.00E+00 6.27E-05 3.97E-05 Fe-55 CURIES 0.00E+00 0.00E+00 7.87E-02 1.63E-02 Fe-59 CURIES 0.00E+00 0.00E+00 5.02E-04 5.79E-04 l-131 CURIES 0.00E+00 0.00E+00 6.60E-03 1.40E-03 !
l-132 CURIES 0.00E+00 0.00E+00 1.89E-03 0.00E+00 La-140 CURIES 0.00E+00 0.00E+00 1.99E-04 2.93E-05 Mn-54 CURIES 0.00E+00 0.00E+00 1.04E-02 1.93E-03 Na-24 CURIES 0.00E+00 0.00E+00 6.38E-06 0.00E+00 Nb-95 CURIES 0.00E+00 0.00E+00 5.39E-03 1.90E-03 Nb-97 CURIES 0.00E+00 0.00E+00 1.16E-04 0.00E+00 Ru-103 CURIES 0.00E+00 0.00E+00 6.89E-05 1.65E-04 Sb-124 CURIES 0.00E+00 0.00E+00 1.04E-03 4.05E-04 l
Sb-125 CURIES 0.00E+00 0.00E+00 4.63E-02 1.16E-02 Sn-113 CURIES 0.00E+00 0.00E+00 1.18E-04 2.10E-04 Sr-89 CURIES 0.00E+00 0.00E+00 2.51 E-03 2.07E-05 l Sr-90 CURIES 0.00E+00 0.00E+00 7.08E-05 0.00E+00 Sr-92 CURIES 0.00E+00 0.00E+00 4.44E-05 0.00E+00 Te-125M CURIES 0.00E+00 0.00E+00 1.59E-02 0.00E+00 Te-129M CURIES 0.00E+00 0.00E+00 2.00E-03 0.00E+00 i
Te-132 CURIES 0.00E+00 0.00E+00 1.39E-03 0.00E+00 Zn-65 CURIES 0.00E+00 0.00E+00 3.14E-04 0.00E+0c Zr 95 CURIES 0.00E+00 0*OE+00 3.23E-03 1.19E-03 TOTALS 0.00E+00 0.00E+00 2.71 E-01 5.95E-02 DISSOLVED AND ENTRAINED GASES:
Xe-131M CURIES 0.00E+00 0.00E+00 4.82E-04 0.00E+00 Xe-133 CURIES 0.00E+00 0.00E+00 2.10E-02 8.38E-04 l
TOTALS 0.00E+00 0.00E+00 2.15E-02 8.38E-04 G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 7.49E-06 22
l TABLE 1-3C I Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996 Liquid Effluents
. Starting : 1-Jan-1996 Ending : 30-Jun-1996 SITE CONTINUOUS BATCH NUCLID UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 H-3 CURIES 0.00E+00 0.00E+00 4.45E+02 5.11E+02 FISSION & ACTIVATION PRODUCTS:
Ag-110M CURIES 0.00E+00 0.00E+00 6.75E-04 0.00E+00 Ce-141 CURIES 0.00E+00 0.00E+00 0.00E+00 2.52E-05 Co-57 CURIES 0.00E+00 0.00E+00 3.22E-04 4.04E-05 Co-58 CURIES 0.00E+00 0.00E+00 2.11 E-02 2.84E-02 i Co-60 CURIES 0.00E+00 0.00E+00 6.06E-02 1.77E-02 )
Cr-51 CURIES 0.00E+00 0.00E+00 2.19E-02 1.86E-02 Cs-134 CURIES 0.00E+00 0.00E+00 e 14E-05 9.29E-05 Cs-137 CURIES 0.00E+00 0.00E+00 1.18E-04 4.38E-05 Fe-55 CURIES 0.00E+00 0.00E+00 9.17E-02 8.29E-02 Fe-59 CURIES 0.00E+00 0.00E+00 2.66E-03 6.86E-04 l-131 CURIES 0.00E+00 0.00E+00 0.00E+00 9.10E-03 1-133 CURIES 0.00E+00 0.00E+00 0.00E+00 2.16E-04 La-140 CURIES 0.00E+00 0.00E+00 6.85E-06 3.38E-04 Mn-54 CURIES 0.00E+00 0.00E+00 1.32E-02 5.76E-03 Nb-95 CURIES 0.00E+00 0 00E+00 3.45E-03 4.82E-03 Nb-97 CURIES 0.00E+00 0.00E+00 2.24E-04 8.61 E-05 Sb-122 CURIES 0.00E+00 0.00E+w 0.00E+00 3.77E-04 Sb-124 CURIES 0.00E+00 0.00E+00 2.13E-04 1.84E-03 Sb-125 CURIES 0.00E+00 0.00E+00 1.04E-02 3.37E-02 Sn-113 CURIES 0.00E+00 0.00E+00 1.38E-04 1.32E-04 Sr-89 CURIES 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Sr-90 CURIES 0.00E+03 0.00E+00 0.00E+00 7.60E-07 Sr-92 CURIES 0.00E+00 0.00E+00 6.43E-05 0.00E+00 Tc-99M CURIES 0.00E+00 0.00E+00 0.00E+00 2.72E-05 Te-125M CURIES 0.00E+00 0.00E+00 0.00E+00 6.40E-03 Te-129M CURIES 0.00E+00 0.00E+00 2.24E-04 0.00E+00 Te-132 CURIES 0.00E+00 0.00E+00 6.14E-05 3.92E-05 Zn-65 CURIES 0.00E+00 0.00E+00 1.21E-04 0.00E+00 Zr-95 CURIES 0.00E+00 0.00E+00 2.06E-03 3.11 E-03 TOTALS 0.00E+00 0.00E+00 2.29E-01 2.15E-01 DISSOLVED AND ENTRAINED GASES:
Xe-133 CURIES 0.00E+00 0.00E+00 3.82E-03 1.55E-02 TOTALS 0.00E+00 0.00E+00 3.82E-03 1.55E-02 G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 23
1 TABLE 1-3CC Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996 i Liquid Effluents
. Starting : 1-Jul-1996 Ending : 31-Dec-1996 SITE I CONTINUOUS BATCH NUCLID UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 H-3 CURIES 0.00E+00 0.00E+00 5.41E+02 1.39E+02 FISSION & ACTIVATION PRODUCTS:
Ag-110M CURIES 0.00E+00 0.00E+00 9.49E-05 2.11 E-05 Ce-141 CURIES 0.00E+00 0.00E+00 0.00E+00 6.04E-05 Ce-144 CURIES 0.00E+00 0.00E+00 0.00E+00 1.29E-04 Co-57 CURIES 0.00E+00 0.00E+00 6.12E-04 1.68E-04 Co-58 CURIES 0.00E+00 0.00E+00 4.12E-02 2.35E-02 Co-60 CURIES 0.00E+00 0.00E+00 9.38E-02 2.14E-02 Cr-51 CURIES 0.00E+00 0.00E+00 2.06E-02 1.45E-02 Cs-134 CURIES 0.00E+00 0.00E+00 6.48E-05 9.71 E-05 Cs-137 CURIES 0.00E+00 0.00E+00 7.49E-05 9.10E-05 Fe-55 CURIES 0.00E+00 0.00E+00 1.13E-01 3.30E-02 Fe-59 CURIES 0.00E+00 0.00E+00 6.45E-04 1.20E-03 1-131 CURIES 0.00E+00 0.00E+00 6.73E-03 1.57E-03 1-132 CURIES 0.00E+00 0.00E+00 1.89E-03 0.00E+00 La-140 CURIES 0.00E+00 0.00E+00 1.99E-04 3.88E-05 Mn-54 CURIES 0.00E+00 0.00E+00 1.91E-02 6.43E-03 Na-24 CURfdS 0.00E+00 0.00E+00 6.38E-06 0.00E+00 Nb-95 CURIES 0.00E+00 0.00E+00 9.80E-03 5.28E-03 Nb-97 CURIES 0.00E+00 0.00E+00 2.19E-04 1.08E-04 Ru-103 CURIES 0.00E+00 0.00E+00 6.89E-05 2.76E-04 Sb-124 CURIES 0.00E+00 0.00E+00 1.21 E-03 6.81 E-04 Sb-125 CURIES 0.00E+00 0.00E+00 5.79E-02 2.08E-02 Sn-113 CURIES 0.00E+00 0.00E+00 2.86E-04 4.98E-04 Sr-89 CURIES 0.00E+00 0.00E+00 2.51E-03 1.19E-04 Sr-90 CURIES 0.00E+00 0.00E+00 7.08E-05 0.00E+00 Sr-92 CURIES 0.00E+00 0.00E+00 4.44E-05 2.68E-05 Te-125M CURIES 0.00E+00 0.00E+00 1.59E-02 0.00E+00 Te-129M CURIES 0.00E+00 0.00E+00 2.00E-03 0.00E+00 Te-132 CURIES 0.00E+00 0.00E+00 1.39E-03 0.00E+00 Zn-65 CURIES 0.00E+00 0.00E+00 3.14E-04 0.00E+00 Zr-95 CURIES 0.00E+00 0.00E+00 5.54E-03 3,18E-03 TOTALS 0.00E+00 0.00E+00 3.96E-01 1.33E-01 DISSOLVED AND ENTRAINED GASES:
Xe-131M CURIES 0.00E+00 0.00E+00 4.82E-04 0.00E+00 Xe-133 CURIES 0.00E+00 0.00E+00 2.23E-02 8.93E-04 TOTALS 0.00E+00 0.00E+00 2.28E-02 8.93E-04 G-ALPH CURIES 0.00E+00 0.00E+00 1.10E-05 1.44E-05 24
-p -
n-. .
^
l l
i
- l i
1 TABLE 1-4A i VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
', 1NDIVIDUAL DOSES DUE TO LIQUID RELEASES JANUARY,1996 THROUGH JUNE,1996 4
i UNIT 1 i'
- CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF
! LIMIT LIMIT j Bone 5.0 mrem 1.19E-03 2.37E-02 2.06E-03 4.12E-02 i Liver 5.0 mrem 6.41 E-03 1.28E-01 1.24E-02 2.48E-01 T. Body 1.5 mrom 5.69E-03 3.79E-01 1.17E-02 7.82E-01 f
Thyroid 5.0 mrem 4.60E-03 9.19E-02 2.29E-02 4.57E-01 Kidney 5.0 mrom 5.14E-03 1.03E-01 1.20E-02 2.40E-01 i Lung 5.0 mrem 1.47E-02 2.95E-01 7.09E-02 1.42E+00 I
GI-LLI 5.0 mrom 1.11 E-02 2.23E-01 2.37E-02 4.74E-01 i
CUMU:E*IVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % OF ODCM LIMIT LIMIT Bone 10.0 mrem 3.25E-03 3.25E-02 Liver 10.0 mrom 1.88E-02 1.88E-01 T. Body 3.0 mrem 1.74E-02 5.81 E-01 )
Thyroid 10.0 mrem 2.75E-02 2.75E-01 l Kidney 10.0 mrem 1.71 E-02 1.71 E-01 Lung 10.0 mrom 8.57E-02 8.57E-01 ;
GI-LLI 10.0 mrom 3.49E-02 3.49E-01 i
25 I
i !
. TABLE 1-4AA VOGTLE ELECTRIC GENERATING PLANT 3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
. INDIVIDUAL DOSES DUE TO LIQUID RELEASES July,1996 THROUGH December,1996 i
UNIT 1 i i :
- l i CUMULATIVE DOSE PER QUARTER I ORGAN ODCM UNITS QUARTER % OF QUARTER % OF l l LIMIT 3 ODCM 4 ODCM i LIMIT LIMIT 4 i Bone 5.0 mrem 9.10E-04 1.82E-02 1.41 E-03 2.82E-02
! Liver 5.0 mrem 3.53E-03 7.05E-02 4.44E-03 8.88E-02 T. Body 1.5 mrem 2.87E-03 1.91 E-01 3.74E-03 2.49E-01 l
j Thyroid 5.0 mrem 2.01 E-03 4.02E-02 2.28E-03 4.56E-02 ;
j Kidney 5.0 mrem 2.09E-03 4.19E-02 2.67E-03 5.33E-02 Lung 5.0 mrom 3.17E-02 6.33E-01 2.57E-02 5.14E-01
{
GI-LLI 5.0 mrem 1.63E-02 3.26E-01 1.02E-02 2.04E-01 i l CUMULATIVE DOSE PER YEAR
' % OF ODCM ORGAN ODCM UNITS YEAR TO DATE l LIMIT LIMIT l Bone 10.0 mrom 5.57E-03 5.57E-02 mrem 2.68E-02 2.68E-01 Liver 10.0 l T. Body 3.0 mrom 2.40E-02 8.01 E-01
- Thyroid 10.0 mrem 3.17E-02 3.17E-01
- Kidney 10.0 mrom 2.19E-02 2.19E-01 Lung 10.0 mrom 1.43E-01 1.43E+00
. GI-LLI 10.0 mrom 6.14E-02 6.14E-01 4
1 4
j 26 i
- - . ~ .
i l
i TABLE 1-4B
. VOGTLE ELECTRIC GENERATING PLANT 1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES JANUARY,1996 THROUGH JUNE,1996 UNIT 2 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 1 ODCM 2 ODCM LIMIT LIMIT Bone 5.0 mrem 4.53E-04 9.06E-03 9.08E-04 1.82E-02 Liver 5.0 mrem 3.36E-03 6.73E-02 4.98E-03 9.96E-02 T. Body 1.5 mrem 3.07E-03 2.05E-01 4.62E-03 3.08E-01 Thyroid 5.0 mrem 2.56E-03 5.11 E-02 8.58E-03 1.72E-01 Kidney 5.0 mrem 2.79E-03 5.57E-02 4.19E-03 8.39E-02 j Lung 5.0 mrem 5.33E-03 1.07E-01 2.09E-02 4.18E-01 l GI-LLI 5.0 mrom 4.46E-03 8.92E-02 7.16E-03 1.43E-01 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % OF ODCM LIMIT LIMIT ,
Bone 10.0 mrom 1.36E-03 1.36E-02 ;
Liver 10.0 mrem 8.34E-03 8.34E-02 T. Body 3.0 mrem 7.69E-03 2.56E-01 J Thyroid 10.0 mrem 1.11 E-02 1.11 E-01 Kidney 10.0 mrom 6.98E-03 6.98E-02 Lung 10.0 mrom- 2.62E-02 2.62E-01 GI-LLI 10.0 mrem 1.16E-02 1.16E-01 !
27
I TABLE 1-4BB VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
, 1NDIVIDUA!. DOSES DUE TO LIQUID RELEASES l JULY,1596 THROUGH DECEMBER,1996 UNIT 2 l CUMULATIVE DOSE PER QUARTER
.i ORGAN ODCM UNITS QUARTER % OF QUARTER % OF
- LIMIT 3 ODCM 4 ODCM i LIMIT LIMIT l Bone 5.0 mrem 6.83E-03 1.37E-01 9.34E-04 1.87E-02 l Liver 5.0 mrem 1.99E-02 3.99E-01 3.17E-03 6.35E-02 l T. Body 1.5 mrem 1.85E-02 1.23E+00 2.85E-03 1.90E-01 l Thyroid 5.0 mrem 2.52E-02 5.04E-01 4.88E-03 9.75E-02 l j Kidney 5.0 mrem 2.12E-02 4.23E-01 2.46E-03 4.92E-02 l 4 Lung 5.0 mrem 1.30E-01 2.60E+00 3.47E-02 6.94E-01 l GI-LLI 5.0 mrem 4.78E-02 9.56E-01 8.74E-03 1.75E-01 l l
i :
~
j CUMULATIVE DOSE PER YEAR !
ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT LIMIT ;
Bone 10.0 mrem 9.12E-03 9.12E-02 Liver 10.0 mrem 3.15E-02 3.15E-01 T. Body 3.0 mrem 2.90E-02 9.67E-01
- Thyroid 10.0 mrem 4.12E-02 4.12E-01 Kidney 10.0 mrem 3.06E-02 3.06E-01 Lung 10.0 mrem 1.91 E-01 1.91 E+00 GI-LLI 10.0 mrem 6.82E-02 6.82E-01 4
28
TABLE 1-5 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES VOGTLE ELECTRIC GENERATING PLANT JANUARY 1,1996 - DECEMBER 31,1996 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 uCi/mi Fe-59 8.33E-08 uCi/mi Co-58 3.78E-08 uCi/ml Co-60 6.76E-08 uCi/ml Zn-65 1.32E-07 uCi/ml Mo-99 4.31 E-07 uCi/ml Cs-134 3.06E-08 uCi/mi Cs-137 4.51 E-08 uCi/ml Ce-141 6.99E-08 uCi/ml Ce-144 2.95E-07 uCi/mi 1-131 5.97E-08 uCi/ml Xe-133 9.11 E-08 uCi/ml Xe-135 4.27E-08 uCi/mi Fe-55 1.00E-06 uCi/mi Sr-89 5.00E-08 uCi/ml Sr-90 7.00E-09 uCi/mi H-3 2.00E-06 uCi/ml Gross Alpha 7.00E-08 uCi/ml 29
TABLE 1-6A GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT- UNIT 1 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JANUARY,1996 ENDING: JUNE,1996 LIQUID RELEASES Number of Releases 50 Total Time For All Releases 10028.00 minutes Maximum Time For a Release 381.00 minutes Average Time For a Release 200.56 minutes Minimum Time For a Release 16.00 minutes GASEOUS RELEASES Number of Releases: 88 Total Time For All Releases 80814.33 minutes Maximum Time For A Release 10047.92 minutes Average Time For A Release 918.34 minutes '
Minimum Time For A Release 1.92 minutes 30
l l
I
^
i l
TABLE 1-6AA l
GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT- UNIT 1 BATCH RELEASE
SUMMARY
OF ALL RELEASES b
STARTING: JULY,1996 ENDING: DECEMBER,1996 l l
l LIQUID RELEASES i Number of Releases 28 Total Time For All Releases 4954.00 minutes Maximum Time For a Release 416.00 minutes Average Time For a Release 176.93 minutes Minimum Time For a Release 51.00 minutes i 4
GASEOUS RELEASES 4
Number of Releases: 53 Total Time For All Releases 5130.92 minutes Maximum Time For A Release 265.00 minutes Average Time For A Release 96.81 minutes Minimum Time For A Release 33.92 minutes
, 31 e
TABLE 1-6B
~
GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT- UNIT 2 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JANUARY,1996 ENDING: JUNE,1996 LIQUID RELEASES Number of Releases 15 Total Time For All Releases 2923.00 minutes Maximum Time For a Release 434.00 minutes Average Time For a Release 194.87 minutes Minimum Time For a Release 49.00 minutes GASEOUS RELEASES Number of Releases: 25 Total Time For All Releases 4278.67 minutes Maximum Time For A Release 1471.00 minutes Average Time For A Release 171.15 minutes Minimum Time For A Release 22.92 minutes 32
'i TABLE 1-6BB
~
GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT- UNIT 2 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JULY,1996 ENDING: DECEMBER,1996 LIQUID RELEASES Number of Releases 43 Total Time For All Releases 10541.40 minutes Maximum Time For A Release 429.00 minutes Average Time For A Release 245.15 minutes Minimum Time For A Release 74.00 minutes GASEOUS RELEASES Number of Releases 66 Total Time For All Releases 41356.00 minutes Maximum Time For a Release 5133.92 minutes Average Time For A Release 626.61 minutes Minimum Time For A Release 2.00 minutes 33
j j
E 2.0 Gaseous Effluents 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 greater than 8 days in gaseous effluents released, 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 7.5 mrems to any organ.
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
34
2.1.4 Total Fuel Cycle Dose Commitment (40CFR1.*0)
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 Plant 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.
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 iodines. 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 tritiurn 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.
35
l l
l 2.4 Total Quantities of Radioactivity, Dose Patos, and Cumulative Doses \
, The methods for determining release que w of radioactivity, dose rates, and cumulative doses are as follows:
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 collected sample.
Instantaneous dose rates due to noble gases, radiciodines, tritium, and particulates are calculated . Calculated dose rates are compared to the dose rate limits specified in i
ODCM 3.1.2 for noble gases, radiciodines, tritium, and particulates. Dose rate i calculation methodology is prasented 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 4
ODCM.
2.4.2 Radiolodines, Tritium and Particulate Releases The released quantities of radiciodines are determined using the weekly samples and release flow rates for the two plant vent release points.
The released quantities 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 computer to be used for release dose rate and individual dose calculations.
36
Tritium samples are obtained at least monthly from each vent by bubbling the sample stream through a water trap. The tritium concentration in water is converted to the tritium concentration in air and this value is used in release, dose rate, and individual dose calculations.'
Dose rates due to radiciodines, tritium, and particulates are calculated for a hypothetical child, exposed to the inhalation pathway, at the location in the unrestricted area where the potential dose rate is expected to be the highest. Dose rates are calculated for each release point, for each release period, and the total dose rate from both release points are compared to the dose rate limits specified in ODCM 3.1.2 individual doses due to radiciodines, 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 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 calcu;ations.
i 37
2.5 Gaseous Effluent Release Data 2.5.1 Methodology
' Regulatory Guide 1.21 Tables 1 A,18, and 1C are found in this report as Tables 2-2A,2-2AA, 2-2B, 2-288, 2-2C, 2-2CC, 2-3A, 2-3AA, 2-38, 2-3BB, 2-3C, 2-3CC, 2-4A, 2-4AA, 2-48,2-4BB,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 2-288, the total release for each of the four categories (fission and activation gases, iodines, particulates, and tritium) was divided by the number of seconds in the quarter to obtain a release rate in uCi/second for each category. 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, radiciodines, and particulates) are limited as a group as specified in ODCM 3.1.2.
Dose rates due to noble gas releases and due to radiciodines, tritium, and particulate releases were calculated as part of the pre-release and post-release permits. No limits were exceeded for this reporting period.
Gross alpha radioactivity is reported in Table 2-2A,2-2AA, 2-28, and 2-28.B 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 radiciodines, tritium and particulates, are specified in ODCM 3.1.4. Cumulative individual doses are presented in Table 2-7A,2-7AA,2-78, and 2-7BB along with 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 materials released in liquid and gaseous effluents and solid waste.
I 38 1
l l
- i i
i
~ l Estimated errors are based on errors in counting equipment calibration, counting ;
- statistics, vent-flow rates, vent sample flow rates, non-steady release rates, chemical i yield factors, and sample losses for such items as charcoal cartridges.
2.5.1.1 Fission and activation total release was calculated from sample analysis j results and release point flow rates. 1 l Sampling and statistical error in counting 10% )
- Counting equipment calibration 10% l 1 Vent flow Rates 10%
Non-steady release rates 20%
TOTAL ERROR 50 %
2.5.1.21-131 releases were calculated from each weekly sample:
l i Statistical error in counting 10% l i Counting equipment calibration 10 % l 1 Vent Flow Rates 10%
l Vent Sample Flow Rates 50 %
! Non-Steady release rates 10%
l Losses from charcoal cartridges 10% i
- j. TOTAL ERROR 100 % l
! 2.5.1.3 Particulates with half lives greater than 8 day releases were calculated
! from sample and analysis results and release point flow rates. I i l l Statistical error at MDC concentration 10%
- Counting equipment calibration 10% ,
! Vent flow rates 10% i l Vent sample flow rates - 50 % l Non steady release rates 10% ;
TOTAL ERROR 90 %
i .
j 2.5.1.4 Total tritium releases were calculated from sample analysis results
- and release point flow rates.
l
! Water vapor in sample stream determination 10% )
- Vent flow rates 10%
4 Counting calibration and statistics 10%
j Non-steady release rates 10%
j TOTAL ERROR 40 %
i l
i 39
2.5.1.5 Gross Alpha radioactivity was calculated from sample 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 %
2.5.2 Gaseous Batch Data 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 1-6BB.
2.6 RadiologicalImpact Due to Gaseous Releases Dose rates due to noble gas release 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.
As part of pre-release and post release on individual release permits, these dose rates were calculated. No limits were exceeded for this reporting period.
Cumulative air doses due to noble gas releases were calculated for each unit in accordance with ODCM 3.4.2.These results are presented in Tables 2-6A,2-6AA,2-6B, and 2-6B8.
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 three unplanned releases for this reporting period. Permit # 960290 was generated to account the dose and activity for inadvertent release of U-1 gas decay tank
- 4 when release of gas decay tank # 3 was in progress. A total of 1.59 Ci was released.
-Permit # 960356 was generated to account the loss of 4 psig from the U-1 inservice waste gas decay tank #1. A total of 7.68 Ci was released due to this incident. Permit #
960357 was generated to account the loss of 4 psig due to inadvertent opening of gas analyzer drain valve. A total of 5.80 Ci was released due to this incident. A total of 15.1 Ci was released from these three unplanned releases. All these releases were monitored by the plant vent monitor. No ODCM limits were exceeded due to these events.
40
._ . - -.. - - . - _ _ - - - - . - _ _ - . . - - . - - . . - ~ ,- - . - . . _-
l J
l I
TABLE 2-2A l
)
GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996 ALL AIRBORNE EFFLUENTS l UNIT : 1 STARTING : 1-JAN-1996 ENDING : 30-JUN-1996 l TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
l A. FISSION & ACTIVATION PRODUCTS
! 1. TOTAL RELEASE CURIES 1.53E+00 1.56E+01 - 25
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.94E-01 1.98E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
l i B. RADIOlODINES l
l 1. TOTAL LODINE-131 CURIES 9.64E-07 1.06E-05 25 )
i
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.23E-07 1.34E-06 )
- DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
l l C. PARTICULATES l 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 4.04E-05 2.10E-04 25
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.14E-06 2.67E-05 i
- 3. PERCENTAGE OF APPLICABLE LIMIT %
l D. TRITIUM i 1 TOTAL RELEASE CURIES 1.50E+01 1.49E+01 25 l
l 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.90E+00 1.89E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 0.00E+00 0.00E+00
- Applicable hmits are expressed in terms of Dose. See Tables 2-6A and 2-7A of this report i
41
-. _. _ _ _ . _ _ _ . . _ _ __ . _ . ~ _ _ . _ . _ __ _. ._ -- . . _ _ _ __
TABLE 2-2AA 3
GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996 ALL AIRBORNE EFFLUENTS UNIT : 1 l STARTING : 1-JUL-1996 ENDING : 31-DEC-1996 TYPE OF EFFLUENT UNITS QUARTER 3 OUARTER 4 EST. TOTAL ERROR %
- A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 7.45E+01 3.31E+01 25
- 2. AVERAGE RELEASE RATE FOR PERIOD UCi/Sec 9.38E+00 4.16E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 8. RADIOlODINES ;
- 1. TOTAL IODINE-131 CURIES 3.88E-05 5.49E-05 25
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.88E-06 6.91E-06 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %'
C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 2.76E-06 1.23E-06 25
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.48E-07 1.54E-07
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. TRITIUM
- 1. TOTAL RELEASE CURIES 1.41 E+01 4.76E+01 25
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.77E+00 5.98E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA "" OlOACTIVITY CURIES 0.00E+00 0.00E+00
- Applicable limits are expressed in terms of Dose. See Tables 2-6AA and 2-7AA of this report 42
TABLE 2-28 GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996 ALL AIRBORNE EFFLUENTS UNIT : 2 STARTING : 1-JAN-1996 ENDING : 30-JUN-1996 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL i ERROR %
A. FISSION & ACTIVATION PRODUCTS ,
- 1. TOTAL RELEASE CURIES 9.74E+00 3.77E+01 25
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.24E+00 4.80E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
l B. RADIOIODINES l l
- 1. TOTAL IODINE-131 CURIES 1.17E-06 4.81 E-05 25
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.49E-07 6.11 E-06 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 3.38E-07 0.00E+00 25 1
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.30E-08 0.00E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. TRITIUM
- 1. TOTAL RELEASE CURIES 8.69E+00 1.93E+01 25
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.10E+00 2.45E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 0.00E+00 0.00E+00
- Applicable limits are expressed in terms of Dose. See Tables 2-68 and 2-78 of this report 43
- -- - - . - . _ _ . . _ . . . . - . _ - . . . - - ~ . . . . - . - . . . . _ - - . - . .
TABLE 2-2BB GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1996 2 ALL AIRBORNE EFFLUENTS UNIT : 2 STARTING : 1-JUL-1996 ENDING : 31-DEC-1996
- TYPE OF EFFLUENT UNITS OUARTER3 OUARTER 4 EST. TOTAL ERROR %
! A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 1.64E+03 2.03E+01 25 l 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.06E+02 2.56E+00
! 3. PERCENTAGE OF APPLICABLE LIMIT %
i i B. RADIOIODINES i
- 1. TOTAL IODINE-131 CURIES 5.16E-03 5.38E-04 25
{
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 6.49E-04 6.77E-05 j DURING PERIOD l 3. PERCENTAGE OF APPLICABLE LIMIT %
! l l C. PARTICULATES ;
O . l 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 6.23E-05 1.86E-05 25 i
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.84E-06 2.34E-06 i
- 3. PERCENTAGE OF APPLICABLE LIMIT % )
. D. TRITIUM 1
2
- 1. TOTAL RELEASE CURIES 4.24E+01 1.06E+01 25 1
4 l 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.34E+00 1.33E+00 l I * *
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 3.56E-06 0.00E+00
- Applicable limits are expressed in terms of Dose. See Tables 248B and 2-7BB of this report i
j a
l 44 i
i l
l TABLE 2-2C GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RAQlOACTIVE EFFLUENT RELEASE REPORT-1996 ALL AIRBORNE EFFLUENTS SITE STARTING : 1-JAN-1996 ENDING : 30-JUN-1996 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL j ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 1.13E+01 5.33E+01 25
. 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.44E+00 6.78E+00 3
- 3. PERCENTAGE OF APPLICABLE LIMIT %
5 B. RADIOlODINES
- 1. TOTAL LODINE-131 CURIES 2.13E-06 5.87E-05 25 i i 2.AV.ERAGE PILtiASE RATE FOR PERIOD uCi/Sec 2.71 E-07 7.46E-06 i DURING PERIOD 4 3. PERCENTAGE OF APPLICABLE LIMIT %
1 C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 4.04E-05 2.10E-04 25 4 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.14E-06 2.67E-05
- 3. PERCENTAGE OF APPLICABLE LIMIT %
4 j D. TRITIUM
- 1. TOTAL RELEASE CURIES 2.37E+01 3.42E+01 25
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.01 E+00 4.35E+00 4
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 0.00E+00 0.00E+00
,
- Applicable limits are expressed in terms of Dose. See Tables 2-6A . 2-68. 2-7A and 2-7B of this report 4
(
45
..- - - - - - . . . ~ ~ . . = . - . . _ . - - . _ . - - - - - . _ - _ - . . -
TABLE 2-2CC GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL F.AQlOACTIVE EFFLUENT RELEASE REPORT-1996 ALL AIRBORNE EFFLUENTS SITE STARTING : 1-JUL-1996 ENDING : 31-DEC-1996 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ERROR %
! A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 1.71E+03 5.34E+01 25
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.15E+02 6.72E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. RADIOlODINES j 1. TOTAL IODINE-131 CURIES 5.20E-03 5.93E-04 25 l
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 6.54E-04 7.46E-05 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 6.51 E-05 1.99E-05 25
- 2. AVERAGE RELEASE RATE FOR PERIOD UCi/Sec 8.19E-06 2.50E-06
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. TRITIUM
- 1. TOTAL RELEASE CURIES 5.65E+01 5.82E+01 25 l
! 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.11 E+00 7.32E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 3.56E-06 0.00E+00
- Applicable hmits are expressed in terms of Dose. SeeTables 2 6AA. 2-6B8, 2-7AA and 2-78B of this report i
i 46 1
)
l TABLE 2-3A (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT :
ANNUAL EFFLUENTS - MIXED MODE JANUARY,1996 THROUGH JUNE,1996 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission <
gg QUARTER QUARTER QUARTER QUARTER Gasses es e N 1 2 1 2 Ar-41 Ci 0.00E+00 0.00E+00 4.60E-01 1.26E-01 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 6.15E-01 Kr-85M Ci 0.00E+00 2.77E-01 0.00E+00 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 0.00E+00 6.87E-02 Xe-133 Ci 8.87E-01 1.60E+00 1.65E-01 1.27E+01 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 9.73E-02 Xe-135 Ci 0.00E+00 0.00E+00 5.25E-03 2.61 E-02 TOTAL FOR Ci 8.87E-01 1.87E+00 6.30E-01 1.37E+01 PERIOD
- 2. lodine's 1-131 Ci 9.39E-07 1.06E-05 0.00E+00 0.00E+C 0 1-133 Ci 4.30E-06 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 5.24E-06 1.06E-05 0.00E+00 0.00E+00 PERIOD
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
j 47
4 4
i l TABLE 2-3A (PAGE 2 OF 2)
- VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE
\ JANUARY,1996 THROUGH JUNE,1996 h UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates a:%. QUARTER QUARTER QUARTER QUARTER l ' *? 1 2 1 2 Co-58 Ci 2.50E-07 9.83E-07 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 7.83E-08 0.00E+00 0.00E+00 TOTAL FOR Ci 2.50E-07 1.06E-06 0.00E+00 0.00E+00 PERIOD H-3 Ci 1.49E+01 1.49E+01 1.54E-02 ' 3.09E-04
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
48
l TABLE 2-3AA (PAGE 1 OF 2) l l VOGTLE ELECTRIC GENERATING PLANT 1
\
- ANNUAL EFFLUENTS - MIXED MODE
- JULY,1996 THROUGH DECEMBER,1996 i l l UNIT 1 l
- 1 l NUCLIDES i RELEASED UNIT CONTINUOUS MODE BATCH MODE :
4 i 1. Fission s@% QUARTER QUARTER QUARTER QUARTER 1 l Gasses $ in 3 4 3 4 :
- Ar-41 Ci 0.00E+00 0.00E+00 4.16E-02 5.30E-02 l Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 4.72E-01 ,
! Kr-85m Ci 0.00E+00 1.22E-01 7.25E-05 1.28E-02 l Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 1.69E-03 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 1.12E-02 l Xe-131 m . Ci 0.00E+00 0.00E+00 0.00E+00 1.61 E-01 Xe-133 Ci 7.37E+01 1.77E+01 1.55E-01 1.28E+01
{
i Xe-133m Ci 0.00E+00 0.00E+00 0.00E+00 1.28E-01 I Xe-135 Ci 6.03E-01 1.41 E+00 2.98E-03 1.56E-01
! TOTAL FOR Ci 7.43E+01 1.92E+01 2.00E-01 1.38E+01
. I d nes
! l-131 Ci 3.88E-05 5.49E-05 0.00E+00 0.00E+00
- l-133 Ci 0.00E+00 9.87E-06 0.00E+00 0.00E+00 TOTAL FOR Ci 3.88E-05 6.48E-05 0.00E+00 0.00E+00 l'
PERIOD I i
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
49 l
l
TABLE 2-3AA(PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JULY,1996 THROUGH DECEMBER ,1996 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates g
~ WGyn QUARTER QUARTER QUARTER QUARTER
< sw 3 4 3 4 Ce-144 Ci 0.00E+00 3.63E-07 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 7.44E-07 0.00E+00 0.00E+00 Sr-89 Ci 2.76E-06 1.19E-07 0.00E+00 0.00E+00 TOTAL FOR Ci 2.76E-06 1.23E-06 0.00E+00 0.00E+00 PERIOD H-3 Ci 1.41 E+01 4.73E+01 1.10E-02 2.87E-01
- Zeroes in this table indicate that no radioactivity was present above detect'able levels. See Table 2-8 for typical minimum detectable concentrations.
50
TABLE 2-3B (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLAN
, ANNUAL EFFLUENTS - MIXED MODE JANUARY,1996 THROUGH JUNE,1996
} UNIT 2 i NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE l
- 1. Fission QUARTER QUARTER QUARTER QUARTER Gasses ~ 1 2 1 2 ;
Ar-41 Ci 0.00E+00 0.00E+00 6.29E-02 4.09E-02 )
Kr-85 Ci 0.00E+00 0.00E+00 4.39E-02 7.59E-01 l Kr-85m Ci 6.27E-02 9.91 E-01 5.01 E-05 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 5.66E-02 1.07E-01 Xe-133 Ci 6.39E+00 2.55E+01 2.35E+00 5.59E+00 Xe-133m - Ci 0.00E+00 0.00E+00 2.59E-02 3.38E-02 Xe-135 Ci 7.41 E-01 4.65E+00 4.89E-03 6.19E-03 TOTAL FOR Ci 7.20E+00 3.12E+01 2.54E+00 6.54E+00 PERIOD
- 2. Iodine's 1-131 Ci 1.17E-06 4.81 E-05 0.00E+00 0.00E+00 1-133 Ci 4.49E-06 3.18E-06 0.00E+00 0.00E+00 TOTAL FOR Ci 5.66E-06 5.12E-05 0.00E+00 0.00E+00 PERIOD 1
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
5.1 1
1 4 I
4 i
J ,
i i
1 TABLE 2-3B (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT
- ANNUAL EFFLUENTS - MIXED MODE 4
} JANUARY,1996 THROUGH JUNE,1996 I l UNIT 2 b NUCLIDES
- RELEASED UNIT CONTINUOUS MODE BATCH MODE l 3. Particulates -'7 > QUARTER QUARTER QUARTER QUARTER sm ' $W N 1 2 1 2
- Co-60 Ci 3.38E-07 0.00E+00 0.00E+00 0.00E+00 i
? TOTAL FOR Ci 3.38E-07 0.00E+00 0.00E+00 0.00E+00 PERIOD l H-3 Ci 8.68E+00 1.93E+01 1.03E-02 1.54E-02 4
l
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations. l l
52
)
l 1
l TABLE 2-3BB (PAGE 1 OF 2) i VOGTLE ELECTRIC GENERATING PLANT l
4 ANNUAL EFFLUENTS - MIXED MODE i JULY,1996 THROUGH DECEMBER,1996
!, UNIT 2 i
I NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission n ; : QUARTER QUARTER QUARTER QUARTER Gasses % 3 4 3 4 Ar-41 Ci 0.00E+00 0.00E+00 2.86E-01 1.47E-02 Kr-85 Ci 0.00E+00 6.98E+00 1.42E+01 2.95E+00 Kr-85m Ci 0.00E+00 0.00E+00 1.37E-02 2.72E-04 Xe-131m Ci 1.25E+01 0.00E+00 7.79E+00 5.58E-01 Xe-133 Cl 1.19E+03 5.51E+00 3.96E+02 1.90E+00 Xe-133m Ci 1.02E+01 2.00E+00 3.76E+00 2.06E-03 Xe-135 Cl 1.08E+00 0.00E+00 3.85E-01 8.63E-03 TOTAL FOR Ci 1.21 E+03 1.45E+01 4.22E+02 5.44E+00 PERIOD
- 2. lodinas 1-131 Ci 5.16E-03 1.65E-04 0.00E+00 0.00E+00 1-133 Ci 2.52E-04 1.55E-05 0.00E+00 0.00E+00 TOTAL FOR Ci 5.41 E-03 1.80E-04 0.00E+00 0.00E+00 PERIOD
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
53
l
\
)
TABLE 2-3BB (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT l 1
ANNUAL EFFLUENTS - MIXED MODE JULY,1996 THROUGH DECEMBER ,1996 l UNIT 2 l
NUCLIDES }
RELEASED UNIT CONTINUOUS MODE BATCH MODE 1
- 3. Particulates x, QUARTER QUARTER QUARTER QUARTER SM '
3 4 3 4 Co-58 Ci 2.39E-05 8.06E-06 0.00E+00 0.00E+00 Co-60 Ci 8.78E-06 2.30E-06 0.00E+00 0.00E+00 Cr-51 Ci 1.70E-05 6.39E-06 0.00E+00 0.00E+00 -
l-131 Ci 4.47E-06 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 2.22E-06 5.12E-07 0.00E+00 0.00E+00 Nb-95 Ci 2.05E 5.78E-07 0.00E+00 0.00E+00 Zr-95 Ci 2.06E-06 7.80E-07 0.00E+00 0.00E+00 OTHER Ci 1.87E-06 0.00E+00 0.00E+00 .'0.00E+00 TOTAL FOR Ci 6.23E-05 1.86E-05 0.00E+00 0.00E+00 ;
PERIOD G-ALPHA Ci 3.56E-06 0.00E+00 0.00E+00 0.00E+00 H-3 Ci 4.19E+01 1.03E+01 4.64E-01 1.95E-01 1
- Zeroes in this taale indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations, i
54 I
i ,
i i
l 1
l TABLE 2-3C (PAGE 1 OF 2) .
l VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE :
I i l JANUARY,1996 THROUGH JUNE,1996 SITE I !
NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission >~
QUARTER QUARTER QUARTER QUARTER Gasses % 'd 1 2 1 2 -
Ar-41 Ci 0.00E+00 0.00E+00 5.23E-01 1.67E-01 Kr-85 Ci 0.00E+00 0.00E+00 4.39E-02 1.37E+00 Kr-85m Cl 6.27E-02 1.27E+00 5.01 E-05 0.00E+00 ,
Xe-131m Ci 0.00E+00 0.00E+00 5.66E-02 1.76E-01 l Xe-133 Ci 7.28E+00 2.71 E+01 2.51 E+00 1.83E+01 1 Xe-133m Ci 0.00E+00 0.00E+00 2.59E-02 1.31 E-01 l Xe-135 Ci 7.41 E-01 4.65E+00 1.01 E-02 3.23E-02 TOTAL FOR Ci 8.09E+00 3.30E+01 3.17E+00 2.02E+01 1 PERIOD l
- 2. lodines 1-131 Ci 2.11 E-06 5.86E-05 0.00E+00 0.00E+00 1-133 Ci 8.79E-06 3.18E-06 0.00E+00 0.00E+00 TOTAL FOR Ci 1.09E-05 6.18E-05 0.00E+00 0.00E+00 PERIOD
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
55
I i
. 1 TABLE 2-3C (PAGE 2 OF 2)
, VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE
> JANUARY,1996 THROUGH JUNE,1996 ,
SITE NUCLIDES j RELEASED UNIT CONTINUOUS MODE BATCH MODE 1
- 3. Particulates , QUARTER QUARTER QUARTER QUARTER
- 1 2 1 2 '
Ce-141 Ci 0.00E+00 7.83E-08 0.00E+00 0.00E+00
] Co-58 Ci 2.50E-07 9.83E-07 0.00E+00 0.00E+00 Co-60 Ci 3.38E-07 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 5.88E-07 1.06E-06 0.00E+00 0.00E+00 PERIOD H-3 Ci 2.36E+01 3.42E+01 3.39E-02 1.57E-02
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
56
Y j
l i
i i l
TABLE 2-3CC (PAGE 1 OF 2) .
\
~
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE i
- JULY,1996 THROUGH DECEMBER,1996 i
- SITE i
i NUCLIDES i RELEASED UNIT COWTINUOUS MODE BATCH MODE 1 1. Fission .au QUARTER QUARTER QUARTER QUARTER Gasses N 3 4 3 4 l
^
Ar-41 Ci 0.00E+00 0.00E+00 3.27E-01 6.77E-02 Kr-85 .Ci 0.00E+00 6.98E+00 1.42E+01 3.42E+00 i Kr-85m Ci 0.00E+00 1.22E-01 1.38E-02 1.31 E-02 l Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 1.69E-03
! Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 1.12E-02 l Xe-131m Ci 1.25E+01 0.00E+00 7.79E+00 7.19E-01 I
! Xe-133 Ci 1.26E+03 2.32E+01 3.96E+02 1.47E+01
!~ Xe-133m Ci 1.02E+01 2.00E+00 3 76E+00 1.30E-01 Xe-135 Ci- 1.68E+00 1.41 E+00 3.88E-01 1.65E-01 1
- TOTAL FOR Ci 1.29E+03 3.37E+01 4.23E+02 1.93E+01
- PERIOD i 2. lodines i 1-131 Ci 5.20E-03 2.20E-04 0.00E+00 0.00E+00
! l-133 Ci 2.52E-04 2.54E-05 0.00E+00 0.00E+00 l TOTAL FOR Ci 5.45E-03 2.45E-04 0.00E+00 0.00E+00 3 PERIOD i
i j ..* Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
4 f
i i
i l 57 a
_ _ _ . . . . _ _ _ _ . _ ~ . _ . . _ _ _ _ . _ _ _ _ . - _ _ . _ _ _ _ . . _ . . . _ _ _ _ , -
1-l l
i l
i -
TABLE 2-3CC (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT b ANNUAL EFFLUENTS - MIXED MODE i
l JULY,1996 THROUGH DECEMBER ,1996 f
- SITE NUCLIDES I
RELEASED UNIT CONTINUOUS MODE BATCH MODE ^
j 3. Particulates <~ QUARTER QUARTER QUARTER QUARTER y %w .
3 4 3 4 i
i f: Ce-144 Ci 0.00E+00 3.63E-07 0.00E+00 0.00E+00 Co-58 Ci 2.39E-05 8.81 E-06 0.00E+00 0.00E+00 i
- . Co-60 Ci 8.78E-06 2.30E-06 0.00E+00 0.00E+00 1 i Cr-51 Ci 1.70E-05 6.39E-06 0.00E+00 0.00E+00
. 1-131 Ci 4.47E-06 0.00E+00 0.00E+00 0.00E+00 l Mn-54 Ci 2.22E-06 5.12E-07 0.00E+00 0.00E+00 ;
- Nb-95 Ci 2.05E-06 5.78E-07 0.00E+00 0.00E+00 l i
l Sr-89 Ci 2.76E-06 1.19E-07 0.00E+00 0.00E+00
- Zr-95 Ci 2.06E-06 7.80E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 OTHER Ci 1.87 E-06 0.00E+00 TOTAL FOR Ci 6.51 E-05 1.99E-05 0.00E+00 0.00E+00
< PERIOD
- G-ALPHA Ci 3.56E-06 0.00E+00 0.00E+00 0.00E+00 H-3 Ci 5.60E+01 5.76E+01 4.75E-01 4.82E-01 1
\
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
I 1
I 4
58 Y
n , - , ,_- -. .- - - - -
. _ _ = - - . . - .. ..-.. - ---.- _ . . - - - . . . . - . . . - - . . . - - . - . .
i i
1 1
i
~
l TABLE 2-4A (PAGE 1 OF 2) j VOGTLE ELECTRIC GENERATING PLANT i
ANNUAL EFFLUENTS - GROUND MODE JANUARY,1996 THROUGH JUNE,1996 l
UNIT 1 i NUCLIDES 1 RELEASED UNIT CONTINUOUS MODE BATCH MODE l 1. Fission :, a :, QUARTER QUARTER QUARTER QUARTER Gasses ':' 1 2 1 2 l
Xe-133 Ci 0.00E+00 0.00E+00 9.76E-03 2.89E-02 TOTAL FOR Ci 0.00E+00 0.00E+00 9.76E-03 2.89E-02 l PERIOD
- 2. lodines BR-82 Ci 0.00E+00 0.00E+00 1.98E-07 0.00E+00 1-131 Ci 0.00E+00 0.00E+00 2.45E-08 2.14E-09 TOTAL FOR Ci 0.00E+00 0.00E+00 2.23E-07 2.14E-09 ,
PERIOD
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
l 59
TABLE 2-4A (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JAN,1996 THROUGH JUNE,1996 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates gfg;QQg QUARTER QUARTER QUARTER QUARTER
.m 1 2 1 2 Nb-95 Ci 0.00E+00 0.00E+00 0.00E+00 5.58E-05 Co-58 Ci 0.00E+00 0.00E+00 4.01 E-05 1.53E-04 TOTAL FOR Ci 0.00E+00 0.00E+00 4.01 E 2.09E-04 PERIOD H-3 Ci 0.00E+00 0.00E+00 1.19E-02 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.
60
l l
l i
1 TABLE 2-4AA (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JULY,1996 THROUGH DECEMBER,1996 UNIT 1 NUCLIDES l RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission CD w QUARTER QUARTER QUARTER QUARTER Gasses n <
3 4 3 4 Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 Xe-133m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Xe-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PERIOD
- 2. lodines 1-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-82 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 0.00E+00. 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PERIOD
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
61
i TABLE 2-4AA (PAGE 2 OF 2) s
! VOGTLE ELECTRIC GENERATING PLANT l
l ANNUAL EFFLUENTS - GROUND MODE 1
JULY,1996 THROUGH DECEMBER ,1996 l
l UNIT 1 I NUCLIDES l RELEASED UNIT CONTINUOUS MODE BATCH MODE l 3. Particulates
- L
QUARTER QUARTER QUARTER QUARTER
., 3 4 3 4 I
NB-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PERIOD G-ALPHA Ci 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.
62
i i
i l TABLE 2-4B (PAGE 1 OF 2) >
, VOGTLE ELECTRIC GENERATING PLANT i
ANNUAL EFFLUENTS - GROUND MODE JANUARY,1996 THROUGH JUNE,1996 UNIT 2 I
^ NUCLIDES I RELEASED UNIT CONTINUOUS MODE BATCH MODE !
l 1. Fission at, 4""
QUARTER QUARTER QUARTER QUARTER
- Gasses 1 2 1 2 ;
- Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
! Xe-133m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
! Xe-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l . Xe-131m Ci . 0.00E+00 0.00E+00 0.00E+00 'O.00E+00 I
Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l PERIOD i 2. lodines
!- I-132- Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
- l-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I j BR-82 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I l-131 Ci 0.00E+00. 0.00E+00 0.00E+00 0.00E+00 l TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '
l PERIOD i
!
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See
! Table 2-8 for typical minimum detectable concentrations.
9 63
.-. ..- . .- -. . .- .- - . . = . _-
i TABLE 2-4B (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JAN,1996 THROUGH JUNE,1996 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates ,>-
QUARTER QUARTER QUARTER QUARTER 1 2 1 2 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PERIOD G-ALPHA Ci 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.
64
~ . . _ _ _ _ _ _ _ _
TABLE 2-488 (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JULY,1996 THROUGH DECEMBER,1996 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission em . QUARTER QUARTER QUARTER QUARTER Gasses w ' !#c.; 3 4 3 4 Xe-135 Ci 0.00E+00 0.00E+00 7.48E-03 0.00E+00 Xe-133 Ci 0.00E+00 0.00E+00 6.01 E-01 2.17E-01 Xe-131m Ci 0.00E+00 0.00E+00 2.56E-03 1.67E-01 TOTAL FOR Ci 0.00E+00 0.00E+00 6.11 E-01 3.85E-01 PERIOD
- 2. lodines' l-133 Ci 0.00E+00 0.00E+00 6.36E-05 0.00E+00 BR-82 Cl 0.00E+00 0.00E+00 3.66E-06 0.00E+00 1-131 Ci ,
0.00E+00. 0.00E+00 4.18E-04 3.73E-04 TOTAL FOR Ci 0.00E+00 0.00E+00 4.85E-04 3.73E-04 PERIOD
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
65
l TABLE 2-4BB(PAGE 2 OF 2) \
1 VOGTLE ELEC TRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JULY,1996 THROUGH DECEMBER,1996 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates o ~ QUARTER QUARTER QUARTER QUARTER 3 4 3 4 Be-7 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.005+00 Co-60 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PERIOD H-3 Ci 0.00E+00 0.00E+00 7.43E-02 4.05E-02
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
66
TABLE 2-4C (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JANUARY,1996 THROUGH JUNE,1996 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission QUARTER QUARTER QUARTER QUARTER Gasses : n~ " M .
~
1 2 1 2 Xe-133 Ci 0.00E+00 0.00E+00 9.76E-03 2.89E-02 TOTAL FOR Ci 0.00E+00 0.00E+00 9.76E-03 2.89E-02 PERIOD
- 2. lodines BR-82 ' Ci 0.00E+00 0.00E+00 1.98E-07 0.00E+00 1-131 Ci 0.00E+00. 0.00E+00 2.45E-08 2.14E-09 TOTAL FOR Ci 0.00E+00 0.00E+00 2.23E-07 2.14E-09 ,
PERIOD I
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations. ;
67
TABLE 2-4C (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JAN,1996 THROUGH JUNE,1996 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates .
QUARTER QUARTER QUARTER QUARTER 1 2 1 2 Nb-95 Ci 0.00E+00 0.00E+00 0.00E+00 5.58E-05 Co-58 Cl 0.00E+00 0.00E+00 4.01 E-05 1.53E-04 TOTAL FOR Ci 0.00E+00 0.00E+00 4.01 E-05 2.09E-04 PERIOD H-3 Ci 0.00E+00 0.00E+00 1.19E-02 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.
68 i
i 1
TABLE 2-4CC (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT l l ANNUAL EFFLUENTS - GROUND MODE
- JULY,1996 THROUGH DECEMBER,1996 i
J i SITE i
NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE i 1. Fission : QUARTER QUARTER QUARTER QUARTER I Gasses S*>~ 3 4 3 4 Xe-135 Ci 0.00E+00 0.00E+00 7.48E-03 0.00E+00
- Xe-133 Ci 0.00E+00 0.00E+00 6.01 E-01 2.17E-01 i Xe-131m Ci 0.00E+00 0.00E+00 2.56E-03 1.67E-01 l TOTAL FOR Ci 0.00E+00 0.00E+00 6.11 E-01 3.85E-01 l PERIOD l 2. lodines j 1-133 Cl 0.00E+00 0.00E+00 6.36E-05 0.00E+00
- Br-82 Ci 0.00E+00 0.00E+00 3.66E-06 0.00E+00 l-131 Ci 0.00E+00. 0.00E+00 4.18E-04 3.73E-04 l TOTAL FOR Ci 0.00E+00 0.00E+00 4.85E-04 3.73E-04 PERIOD I
.
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
I I
g.
e 1
i 69 4
i 4
! \
l i
i
- i. TABLE 2-4CC (PAGE 2 OF 2)
\ VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JULY,1996 THROUGH DECEMBER ,1996 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates QQ ' W. QUARTER QUARTER QUARTER QUARTER se , M 3 4 3 4 Nb-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PERIOD H-3 Ci 0.00E+00 0.00E+00 7.43E-02 4.05E-02
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
70
a.L- _ - . - _ , _ A,.- s ~._
k TABLE 2-6A
- VOGTLE ELECTRIC GENERATING PLANT 8 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES
} JANUARY,1996 THROUGH JUNE,1996 l
UNIT 1 CUMMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF RADIATION LIMIT 1 ODCM 2 ODCM
\ LIMIT LIMIT i GAMMA 5.0 mrad 6.85E-05 1.37E-03 9.85E-05 1.97E-03 BETA 10.0 mrad 3.93E-05 3.93E-04 2.58E-04 2.58E-03 CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM LIMIT UNITS YEAR TO DATE % OF ODCM RADIATION LIMIT GAMMA 10.0 mrad 1.67E-04 1.67E-03 BETA 20.0 mrad 2.9BE-04 1.49E-03 71
. - - . _ . .- .- _ - _ . - - . _ - . - ~ . . _ _ _ . ... . ._. . - _ . -
d i
TABLE 2-6AA i
- VOGTLE ELECTRIC GENERATING PLANT i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES JULY,1996 THROUGH DECEMBER,1996 3
UNIT 1 4
l l
CUMMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF RADIATION LIMIT 3 ODCM 4 ODCM LIMIT LIMIT GAMMA 5.0 mrad 4.05E-04 8.09E-03 2.15E-04 4.31E-03 BETA 10.0 mrad 1.16E-03 1.16E-02 5.52E-04 5.52E-03 CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM LIMIT UNITS YEAR TO DATE % OF ODCM RADIATION LIMIT GAMMA 10.0 mrad 7.87E-04 7.87E-03 BETA 20.0 mrad 2.01E-03 1.01E-02 72
~
TABLE 2-6B VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES JANUARY,1996 THROUGH JUNE,1996 UNIT 2 CUMMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF RADIATION LIMIT 1 ODCM 2 ODCM LIMIT LIMIT GAMMA 5.0 mrad 7.61E-05 1.52E-03 3.16E-04 6.32E-03 BETA 10.0 mrad 1.69E-04 1.69E-03 7.01E-04 7.01E-03 CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM LIMIT UNITS YEAR TO DATE % OF ODCM RADIATION LIMIT GAMMA 10.0 mrad 3.92E-04 3.92E-03 BETA 20.0 mrad 8.70E-04 4.35E-03 73
M TABLE 2-6BB i
VOGTLE ELECTRIC GENERATING PLANT
- ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i AIR DOSE DUE TO NOBLE GAS RELEASES i JULY,1996 THROUGH DECEMBER,1996 i UNIT 2 4
)
CUMMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF RADIATION LIMIT 3 ODCM 4 ODCM i
LIMIT LIMIT i GAMMA' 5. 0 - mrad 8.42E-03 1.68E-01 6.23E-05 1.25E-03 BETA 10.0 mrad 2.56E-02 2.56E-01 4.85E-04 4.85E-03 4
4 l CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
. TYPE OF ODCM LIMIT UNITS YEAR TO DATE % OF ODCM
- RADIATION LIMIT GAMMA 10.0 mrad 8.87E-03 8.87E-02 BETA 20.0 mrad 2.69E-02 1.35E-01 1
f 74 4
I I
t i
j TABLE 2-7A VOGTLE ELECTRIC GENERATING PLANT i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1 l INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM l JANUARY,1996 THROUGH JUNE,1996
- i l UNIT 1 CUMULATIVE DOSE PER QUARTER l ORGAN ODCM UNITS QUARTER % OF QUARTER % OF l LIMIT 1 ODCM 2 ODCM l LIMIT LIMIT l Bone 7.5 mrem 3.18E-06 4.24E-05 5.88E-06 7.84E-05 Liver 7.5 mrom 7.12E-05 9.49E-04 7.33E-05 9.77E-04 j T. Body 7.5 mrem 7.12E-05 9.49E-04 7.33E-05 9.77E-04 Thyroid 7.5 mrom 7.13E-05 9.51 E-04 7.40E-05 9.86E-04 Kidney 7.5 mrom 7.12E-05 9.49E-04 7.33E-05 9.77E-04 Lung 7.5 mrem 7.27E-05 9.70E-04 7.73E-05 1.03E-03 I GI-LLI 7.5 mrom 7.12E-05 9.49E-04 7.34E-05 9.79E-04 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT LIMIT Bone 15.0 mrom 9.05E-06 6.04E-05 Liver 15.0 mrom 1.44E-04 9.63E-04 T. Body 15.0 mrom 1.44E-04 9.63E-04 Thyroid 15.0 mrom 1.45E-04 9.68E-04 ;
Kidney 15.0 mrom 1.44E-04 9.63E-04 ;
Lung 15.0 mrom 1.50E-04 1.00E-03 GI-LLI 15.0 mrom 1.45E-04 9.64E-04 i
75
1 i
TABLE 2-7AA VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT j INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JULY,1996 THROUGH DECEMBER,1996 UNIT 1 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF ,
LIMIT 3 ODCM 4 ODCM I LIMIT LIMIT Bone 7.5 mrem 3.51 E-08 4.68E-07 6.15E-08 8.20E-07 Liver 7.5 mrom 6.37E-05 8.50E-04 2.15E-04 2.87E-03 T. Body 7.5 mrom 6.37E-05 8.50E-04 2.15E-04 2.87E-03 Thyroid 7.5 mrem 6.63E-05 8.84E-04 2.19E-04 2.92E-03 Kidney 7.5 mrom 6.37E-05 8.50E-04 2.15E-04 2.87E-03 Lung 7.5 mrem 6.38E-05 8.50E-04 2.15E-04 2.87E-03 GI-LLI 7.5 mrem 6.37E-05 8.50E-04 2.15E-04 2.87E-03 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT LIMIT Bone 15.0 mrom 9.15E-06 6.10E-05 Liver 15.0 mram 4.24E-04 2.82E-03 T. Body 15.0 mrom 4.24E-04 2.82E-03 Thyroid 15.0 mrem 4.31 E-04 2.87E-03 Kidney 15.0 mrom 4.24E-04 2.82E-03 Lung 15.0 mrom 4.29E-04 2.86E-03 GI-LLI 15.0 mrem 4.24E-04 2.83E-03 76
i i
l
)
i 1
TABLE 2-7B VOGTLE ELECTRIC GENERATING PLANT l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM l JANUARY,1996 THROUGH JUNE,1996
- UNIT 2 1
i CUMULATIVE DOSE PER QUARTER ORGAN O M UNITS QUARTER % OF QUARTER % OF LIMIT LIMIT Bone 7.5 mrem 2.30E-07 3.06E-06 3.57E-08 4.76E-07 Liver 7.5 mrem 3.96E-05 5.28E-04 8.75E-05 1.17E-03 i T. Body 7.5 mrem 3.96E-05 5.28E-04 8.75E-05 1.17E-03 l Thyroid 7.5 mrem 3.97E-05 5.29E-04 9.07E-05 1.21 E-03 l Kidney 7.5 mrem 3.96E-05 5.28E-04 8.75E-05 1.17E-03 Lung 7.5 mrem 3.96E-05 5.28E-04 8.75E 1.17E-03 l
i GI-LLI 7.5 mrem 3.96E-05 5.28E-04 8.75E-05 1.17E-03 l
l CUMULATIVE DOSE PER YEAR l ORGAN ODCM UNITS YEAR TO DATE % of ODCM
- j. LIMIT LIMIT j Bone 15.0 mrem 2.66E-07 1.77E-06
- Liver 15.0 mrem 1.27E-04 8.47E-04
- T. Body 15.0 mrem 1.27E-04 8.47E-04 Thyroid 15.0 mrem 1.30E-04 8.69E-04 l Kidney 15.0 mrem 1.27E-04 8.47E-04 Lung 15.0 mrom 1.27E-04 8.47E-04 j GI-LLI 15.0 mrom 1.27E-04 8.47E-04 i
i 4
l 4
l I
77
TABLE 2-78B VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JULY,1996 THROUGH DECEMBER,1996 UNIT 2 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF-LIMIT 3 ODCM 4 ODCM LIMIT - LIMIT Bone 7.5 mrem 1.12E-05 1.50E-04 2.73E-06 3.64E-05 Liver 7.5 mrem 2.05E-04 2.73E-03 5.13E-05 6.84E-04 T. Body 7.5 mrem 2.04E-04 2.72E-03 5.12E-05 6.82E-04 Thyroid 7.5 mrem 6.83E-04 9.10E-03 1.81 E-04 2.41 E-03 ;
Kidney 7.5 mrem 2.06E-04 2.74E-03 5.16E-05 6.88E-04 Lung 7.5 mrem 2.04E-04 2.72E-03 5.11 E-05 6.81 E-04 GI-LLI 7.5 mrem 2.03E-04 2.71 E-03 5.10E-05 6.80E-04 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT LIMIT Bone 15.0 mrem 1.42E-05 9.48E-05 Liver 15.0 mrem 3.83E-04 2.55E-03 T. Body 15.0 mrem 3.82E-04 2.55E-03 Thyroid 15.0 mrem 9.94E-04 6.63E-03 Kidney 15.0 mrem 3.84E-04 2.56E-03 Lung 15.0 mrom- 3.82E-04 2.55E-03 GI-LLI 15.0 mrem 3.81 E-04 2.54E-03 78
TABLE 2-8 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANALYSES VOGTLE ELECTRIC GENERATING PLANT JANUARY 1,1996 THROUGH DECEMBER 31,1996 The values in this table represent a priori Minimum Detectable Concentration (MDC) 'vhich are typically achieved in laboratory analyses of gaseous radwaste samples.
RADIONUCLIDE MDC UNITS Kr-87 1.82E-08 uCi/cc Kr-88 2.53E-08 uCi/cc Xe-133 2.05E-08 uCi/cc Xe-133m 8.63E-08 uCi/cc Xe-135 7.12E-08 uCi/cc Xe-138 1.05E-07 uCi/cc I-131 7.93E-15' UCi/cc Mn-54 3.94E-14
- uCi/cc Fe-59 2.45E-14
- uCi/cc Co-58 1.39E-14
- uCi/cc Mo-99 9.57E-14
- uCi/cc Cs-134 1.12E-14
- uCi/cc Ce-144 2. 77E-14' uCi/cc Sr-89 1.00E-13 uCi/cc Sr-90 1.00E-13 uCi/cc H-3 9.00E-08 uCi/cc Gross Alpha 1.00E-13 uCi/cc Based on an estimated sample volume of 5.7E-08 cc's.
79
3.0 Solid Waste 3.1 Regulatory Lintits/ODCM The ODCM Limits presented in this section are stated in part for Unit 1 and Unit 2. I 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 the transit, 1 and disposal site requirements when received at the disposal site.
3.1.2 Reporting Requirements j 6.8.1.4 The Annual Radioactive Effluent Release Report covering the operation of the units during the previous calendar year shall be submitted before May 1 of each year. The report shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP, and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix 1 to 10 CFR, Part 50.
3.1.3 Process Control Program (PCP) 6.12.2 Licensee - initiated changes to the PCP shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the change (s) was made.
Following t.hanges were made to PCP for this reporting period:
Section 3.1.2: Updated the 10 CFR 20 Reference (from 10CFR20.311, to 10CFR20,2006)
Section 3.1.8: Updated to the new Branch Technical Position Paper on Radioactive Waste Classification (to the May 1993, rev 0 version)
Section 3.4, 3.5, 3.7.1: Updated the PCP to reflect the new resin dewatering system from SEG. This includes new reference data, topical reports, and SEG procedures.
Section 7.1: Updated the reference to the Vendor topical report.
80
~Section 7.2 and 7.3: Updated the reference to 10CFR20.2006. l 1
Section 9.2: Updated the reference to the Branch Technical Position Paper.
Section 12.1: Changed " SEMI-ANNUAL EFFLUENT REPORT" to " ANNUAL EFFLUENT REPORT" 3.2 Solid Waste Data Regulatcry Guide 1.21, Table 3 is found in this report as Table 3-1.
1 4.0 Changes to the Vogtle Electric Generating Plant ODCM 6.13.2 There were changes to the Vogtle Electric Generating Plant ODCM for the period January 1,1996 through December 31,1996. The changes are attached as Attachment l I
1.
4.0 of ODCM The Radiological Environmental Monitoring Program shall be conducted as specified in ODCM 4.1.1 and 4.1.2. l Table Notation (1) states in part-
"It is recognized that, at times, it may not be possible or practicable to continue to obtain i samples of the media of choice at the most desired location or time. In these instances, i suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions, if available, will be made within 30 days in the Radiological Environmental Monitoring Program given in the ODCM."
Pursuant to specification 6.13, submit in the next Radioactive Efflucnt Release Report documentation for a change in the ODCM including a revised figure (s) and Table for the l ODCM reflecting the new location (s), if any, with supporting information identifying the
- cause of the unavailability of samples for the pathway and justifying the selection of the new location (s) for obtaining samples, or the unavailability of suitable new locations.
4.1.2 of ODCM states in part:
"A Land Use Census shall be conducted . . . .
The Action Statement for this requirement states in part:
81
)
- a. "With a Land Use Census identifying a location (s) that yields a calculated l dose or dose commitment greater than the value currently being l calculated in ODCM 4.12.1 pursuant to specification 6.13. Identify the new location (s) in the next Annual Radioactive Effluent Release Report".
4.1 Changes in the Radiological Environmental Monitoring Program For this reporting period, there has been no changes to the Radiological Environmental Monitoring Program.
J 5.0 Doses to Members of the Pubilc Inside the Site Boundary 6.8.1.4 states in part:
"This same report shall also include assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the Site Boundary during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and location shall be included in these reports".
The locations of concern within the site boundary is the Visitor Center. ,
The activities at the Visitor Center consist of occasional attendance at meetings and/or short visits for informational purposes.
1 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 j basic data assumed in the dose assessment due to radioactive gaseous !
effluents. Listed in this table are distance 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 4-1. The source term is listed in Tables 2-3A,2-3AA,2-3B and 2-3BB for the mixed mode releases.
Similarly, it is listed in Tables 2-4A,2-4AA,2-4B and 2-4BB for the ground level releases. The Tritium releases in unito of curies were as follows:
QUARTER 1 2 3 4 Mixed Mode 2.36E+01 3.42E+01 5.65E+01 5.81E+01 Ground Mode 1.19E-02 0.00E+00 7.43E-02 4.05E-02 82
J i The maximum doses in units of mrem to an individual MEMBER OF THE PUBLIC due to 1
- - their activities inside the site boundary during the reporting period were assessed to be as follows
VISITOR CENTER
. Quarter 1 and 2 Quarter 3 and 4 Total Body 3.57E-07 5.37E-06 (Direct Radiation from Plume) 4 VISITOR CENTER Quaderi Quader 2 Quader 3 Quader 4 I (Inhalation Ground Plane) 3.63E-07 6.71 E-07 7.24E-06 1.34E-06 Maximum Organ (Lung) (Thyroid) l l
83
__ . _ _ _ . _ _ _ _ _ _ . . . _ _ . . . . - - - _ . _ . _ . . _ . - . . - . _ . - _.__.._....____.__.____._,.m..-_,
i ADDITIONAL INFORMATION REQUIRED BY TECH SPECS: i
' Shioment No Waste Clan Tvoe Container Shiocina Class Solidification Aaent
- RWS-96-001 ' B - Stable Type A LSA None Used ,
RWS-96-002 A - Stable Type A LSA None Used '
RWS-96-003 , A . Stable . Type A - LSA None Used RVRS-96-001 A - Unstable Strong Tight LSA None Used i RVRS-96-002 A - Unstable Strong Tight LSA None Used l RVRS-96-003 A - Unstable Strong Tight LQ None Used i RVRS-96-004 A - Unstable Strong Tight LSA None Used ;
RVRS-96-005 A - Unstable Strong Tight LSA None Used i l
s e
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l l
1 .
! l
. i
- r l
f I
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e i
i i
85 l
1
ADDITIONAL INFORMATION REQUIRED BY TECH SPECS:
Shioment No Waste Class Type Container Shippina Class Solidification Aaent RWS-96-004 C - STABLE TYPE A LSA NONE USED RWS-96-005 B - STABLE TYPE A LSA NONE USED RVRS-96-006 A - UNSTABLE Strong Tight LSA NONE USED RVRS-96-007 A - UNSTABLE Strong Tight <D0T. NONE USED RVRS-96-008 A - UNSTABLE Strong Tight <D 0.T. NONE USED RVRS-96-009 A - UNSTABLE Strong Tight < D O.T. NONE USED RVRS-96-010 A - UNSTABLE Strong Tight < DOT. NONE USED RVRS-96-011 A - UNSTABLE Strong Tight LSA NONE USED RVRS-96-012 A - UNSTABLE Strong Tight LQ NONE USED RVRS-96-013 A - UNSTABLE Strong Tight LSA NONE USED RVRS-96-014 A - UNSTABLE Strong Tight LSA NONE USED RVRS-96-015 A - UNSTABLE Strong Tight LSA NONE USED i
i j
4 1
I
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1 1
4 87 i
Table 4-1 Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 1996 DOSE TO A MEMBER OF THE PUBLIC
. DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Starting: 01-Jan-1996 Ending: 31-Dec-1996 i Location Name Visitor Center j Distance (meters) 4.47e+02 i Sector SE
, X/Q(sec/m3) (1) 5.93E-06 i Depleted X/Q(sec/m3) (2) 5.58E-06 i D/Q(m2) (1) 2.28E-08 X/Q(Sec/m3) (2) 7.12E-07 j Depleted X/Q(sec/m3) (2) 6.74E-07 i D/Q(m2) (2) 5.77E-09 Occupancy Factor 0.00046(4hr/yr)
, Age Group Child VISITOR CENTER I UNITS QTR1 QTR2 Total Q1 & QTR3 QTR4 Total Q3 &
Q2 Q4 j Total Body mrem 9.90E-08 2.58E-07 3.57E-07 5.18E-06 1.87E-07 5.37E-06 !
j Dose l
Organ j Bone mrem 9.82E-08 2.79E-07 3.78E-07 5.21 E-06 1,77E-07 5.39E-06 Liver mrem 3.59E-07 6.55E-07 1.01E 06 5.84E-06 8.19E-07 6.66E-06 Tbody mrem 3.59E-07 6.55E-07 1.01 E-06 5.84E-06 8.19E-07 6.65E-06 Thyroid mrem 3.60E-07 6.64E-07 1.02E-06 7.24E-06 1.34E-06 8.58E-06 l Kidney mrem 3.59E-07 6.55E-07 1.01 E-06 5.84E-06 8.20E-07 6.66E-06 Lung mrem 3.63E-07 6.71 E-07 1.03E-06 5.83E-06 8.18E-07 6.65E-06 j GI-LLI mrem 3.59E-07 6.56E-07 1.01 E-06 5.83E-06 8.18E-07 6.65E-06 I
I 88
6.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems 6.8.1.4 states in part:
The Annual Radioactive Effluent Release Report shall include " any major change to liquid, gaseous, or solid radwaste treatment systems pursuant to Specification 6.14 "
Gaseous Radwaste System
, There were no major changes to the gaseous radwaste system in 1996.
Solid Radwaste System There were no major changes to the solid radwaste system in 1996.
Liquid Radwaste System There were no major changes to the Liquid Radwaste Treatment System in 1996.
7.0 Meteorological Data 6.8.1.4 states in part:
The Annual Radioactive Effluent Release Report to be submitted by May 1 of each year, shall include 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 on magnetic tape of wind speed, wind direction, atmosphere stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.
4 in lieu of submission with Annual Radioactive Effluent Release Report, the licensee has retained this summary of required meteorological data on site in a file that will be provided to the NRC upon request.
6 8.0 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 6.8.1.4 states in part that:
The Annual Radioactive Effluent Release Report shall also include the following:
. .an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the specified time requirement.. "
89
The inoperability of liquid and gaseous effluent monitors was corrected within the l specified time for this reporting period, j 9.0 Tanks Exceeding Curie Content Limits The Annual Radioactive Effluent Release Reports shall also include the following:
1
. ..and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specifications 3.11.1.4 or 3.11.2.6, respectively . ..
There were no temporary liquid hold up tanks for radioactive liquids or gas storage !
tanks during this reporting period.
I 90