ML20216B254
| ML20216B254 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/31/1997 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20216B245 | List: |
| References | |
| NUDOCS 9805180012 | |
| Download: ML20216B254 (80) | |
Text
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III VOGTLE ELECTRIC GENERATING PLANT-UNITS 1 AND 2 1997 ANNUAL REPORT - PART 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 9805100012 99050644 ADOCK 050 PDR R
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VOGTLE ELECTRIC GENERATING PLANT ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES SECTION TITLE PAGE 1.0 Liquid Emuents 8
1.1 Regulatory Limits / Technical Specifications 8
1.1.1 Concentration Limits 8
1.1.2 Dose Limits 8
1.2 Effluent Concentration Limit 8
1.3 Measurements and Approximations of Total 9
Radioactivity 1.4 Liqu!d Effluent Release Data 10 1.4.1 Tables 10 1.4.2 Total Error Measurement 10 1.5 Radiological Impact on Man Due to Liquid Release 12 1.6 Abnormal Releases 12 1.7 River Flow 12 2.0 Gaseous Effluents 34 2.1 Regulatory Limits /ODCM 34 2.1.1 Dose Rate Limit 34
SECTION TITLE PAGE 2.1.2 Air Dose Due to Noble Gas 34 2.1.3 Dose to Any Organ 34 2.1.4 Total Fuel Cycle Dose Commitment (40CFR190) 35 2.2 Release Points of Gaseous Effluents 35 j
2.3 Sample Collection and Analysis 35 2.4 Total Quantities of Radioactivity, Dose Rates 36 and Cumulative Doses 2.4.1 Fission and Activation Gas 36 2.4.2 Radiolodines, Tritium and Particulate Releases 36 2.4.3 Gross Alpha Release 37 2.5 Gaseous Effluent Release Data 37 2.5.1 Methodology 37 2.5.2 Gaseous Batch Data 39 2.6 Radiological Impact Due to Gaseous Releases 39 2.7 Abnormal Releases 39 3.0 Solid Waste 70 3.1 Regulatory Limits /ODCM 70 1
3.1.1 Use of Solid Radioactive Waste System 70 3.1.2 Reporting Requirements 70 3.2 Solid Waste Data 70 y
1 2
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SECTION TITLE PAGE 4.0 The Vogtle Electric Generating Plant Offsite 70 Dose Calculation Manual (ODCM) 4.1 Changes to The Vogtle Electric Generating Plant 70 ODCM 4.2 The Radiological Environmental Monitoring 71 Program 4.3 Changes in the Radiological Environmental 71 Monitoring Program 5.0 Doses to Members of the Public inside The 71 Site Boundary 6.0 Major Changes to the Liquid, Gateous and 78 Solid Radwaste Treatment Systems 7.0 Meteorology 78 8.0 Program Deviations 79 8.1 Inoperable Liquid or Gaseous Effluent 79 Monitoring Instrumentation i
8.2 Tanks Exceeding Curie Content Limits 79 l
4 3
VOGTLE ELECTRIC GENERATING PLANT ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES TABLE LIST OF TABLES PAGE 1-2A Liquid Effluents - Summation of All Releases 13 Unit 1 l
1-2AA Liquid Effluents - Summation of All Releases 14 Unit 1 1-28 Liquid Effluents - Summation of All Releases 15 Unit 2 1-2BB Liquid Effluents - Summation of All Releases 16 Unit 2 1-2C Liquid Effluents - Summation of All Releases 17 Site 1-2CC Liquid Effluents - Summation of All Releases 18 Site 1-3A Liquid Effluents - Unit 1 19 1-3AA Liquid Effluents - Unit 1 20 1-3B Liquid Effluents - Unit 2 21 1-3BB Liquid Effluents - Unit 2 22 1-3C Liquid Effluents - Site 23 1-3CC Liquid Effluents - Site 24 4
TABLE LIST OF TABLES PAGE 1-4A Individuals Doses Due to Liquid Releases 25 Unit 1 1-4AA Individuals Doses Due to Liquid Releases 26 Unit 1 1-48 Individuals Doses Due to Liquid Releases 27 Unit 2 l
1-4BB Individuals Doses Due to Liquid Releases 28 Unit 2 1-5 Minimum Detectable Concentration -
29 Liquid Sample Analysis 1-6A Batch Release Summary of All Releases 30 Unit 1 1-6AA Batch Release Summary of All Releases 31 Unit 1 1-6B Batch Release Summary of All Releases 32 Unit 2 1-688 Batch Release Summary of All Releases 33 Unit 2 2-2A Airbome Effluents - Summation of All 41 Releases - Unit 1 2-2AA Airbome Effluents - Summation of All 42 Releases - Unit 1 2-2B Airbome Effluents - Summation of All 43 Releases -Unit 2 5
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 2-2CC Airborne Effluents - Summation of All 46 Releases - Site 2-3A Gaseous Effluents - Mixed Mode Releases 47 Unit 1 2-3AA Gaseous Effluents - Mixed Mode Releases 48 Unit 1 2-3B Gaseous Effluents - Mixed Mode Releases 50 Unit 2 2-3BB Gaseous Effluents - Mixed Mode Releases 53 Unit 2 2-3C Gaseous Effluents - Mixed Mode Releases 52 Site 2-3CC Gaseous Effluents - Mixed Mode Releases 53 Site 2 4A Gaseous Effluents - Ground Level Release 55 Unit 1 2-4AA Gaseous Effluents - Ground Level Release 56 Unit 1 2-4B Gaseous Effluents - Ground Level Release 57 Unit 2 2-4BB Gaseous Effluents - Ground Level Release 58 Unit 2 6
1 TABLE LIST OF TABLES PAGE 2 4C Gaseous Effluents - Ground Level Release 59 Site 2-4CC Gaseous Effluents - Ground Level Release 60 Site 2-6A Air Doses Due to Noble Gases - Unit 1 61 2-6AA Air Doses Due to Noble Gases - Unit 1 62 2-6B Air Doses Due to Noble Gases - Unit 2 63 2-6BB Air Doses Due to Noble Gases - Unit 2 64 2-7A Individual Doses Due to Radiolodines, 65 Tritium, and Particulates in Gaseous Releases - Unit 1 2-7AA Individual Doses Due to Radiolodines, 66 Tritium, and Particulates in Gaseous Releases - Unit 1 2-7B Individual Doses Due to Radiolodines, 67 Tritium, and Particulates in Gaseous Releases - Unit 2 2-788 Individual Doses Due to Radiolodines, 68 Tritium, and Particulates in Gaseous Releases - Unit 2 2-8 Minimum Detectable Concentration -
69 Gaseous Sample Analyses 3-1 Solid Waste and Irradiated Fuel Shipments 73 4-1 Dose to A Member of the Public Due to Activities 77 Inside The Site Boundary 1
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1.0 Liquid Effluents 1.1 Regulatory Limits /ODCM 1.1.1 Concentration Limits in accordance with Technical Specifications 5.5.4.b and 5.5.4.c, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited at all times to ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1 x 10" Ci/mL total l
activity.
l I
1.1.2 Dose Limits The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive l
materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS l
shall be limited as follows:
l a.
During any calendar quarter to less than or equal to 1.5 mrems to the l
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 l
body and to less than or equal to 10 mrems to any organ.
1.2 Effluent Concentration Limit (ECL)
ECL values used for determining the allowable liquid radwaste release rates and concentrations for the principal gamma emitters,1-131, tritium, Sr-89, Sr-90 and Fe-55 are taken from 10 CFR Part 20, Appendix B, Table ll, Column 2. A tolerance factor of up to 10 is utilized to allow flexibility in establishing practical monitor set points which can accommodate effluent releases at concentrations higher than the ECL values stated in 10 CFR 20, Appendix B, Table 11, Column 2.
For disscIved or entrained noble gases in liquid radwaste, the ECL is 1E-04 Ci/mi total activity, For gross alpha in liquid radwaste, the ECL is 2.0E-09 Ci/ml.
For all the above radionuclides or categories of radioactivity, the overall ECL fraction is determined in accordance with 10 CFR Part 20, Appendix B.
The method utilizing the ECL fraction to determine release rates and liquid radwaste effluent radiation monitor set points is described in Subsection 1.3 of this report.
8
1.3 Measurements and Approximations of Total Radioactivity Prior to the release of any tank containing liquid radwaste, and following the required recirculations, samples are collected and analyzed in accordance with the Offsite Dose Calculation Manual (ODCM) Table 2-3 " Radioactive Liquid Waste Sampling Program".
A sample from each tank which is planned for release is analyzed for principal gamma emitters,1-131, and dissolved and entrained noble gases by gamma spectroscopy.
Monthly and quarterly composites are prepared for analysis by extracting aliquots from each semple taken from the tanks which are released. Liquid radwaste sample analyses are performed as follows:
MEASUREMENT FREQUENCY METHOD 1.
Gamma Isotopic Each Batch Gamma Spectroscopy with computerized data reduction.
2.
Dissolved or entrained Each Batch Gamma Spectroscopy noble Oases with computerized data reduction 3.
Tritium Monthly Distillation and Composite liquid scintillation counting 4.
Gross Alpha Monthly Gas flow proportional Composite counting 5.
Sr-89 & Sr-90 Quarterly Chemical separation Composite and gas flow proportional or scintillation counting j
6.
Fe-55 Quarterly Chemical separation Composite and liquid scintillation counting Gamma isotopic measurements are performed using germanium detectors with a resolution of 2.1 kev or lower. A liquid radwaste sample is typically counted for 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-58, Co-60, Zn 65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present.
Tritium, Gross Alpha, Sr-89, Sr-90 and Fe-55 are, in some cases, analyzed offsite.
9
The radionuclide concentrations determined by gamma spectroscopic analysis of l
sample taken from a tank for tanks planned for release and the most current s' ample I
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 effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the Offsite Dose Calculation Manual (ODCM) are not exceeded.
A monitor reading in. excess of the calculated setpoint results in an automatic termination of the liquid radwaste discharge. Liquid effluent discharge is also automatically terminated if the dilution stream flow rate falls below the minimum assured dilution flow rate used in the setpoint calculations and established as a setpoint on the dilution stream flow monitor.
Radionuclide concentrations, safety factors, dilution stream flow rate, and liquid effluent j
radiation monitor calibrations are entered into the computer and a pre-release printout is j
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 l
input to the computer and a post-release printout is generated. The post release printout i
contains the actual release rates, release concentrations and quantities, actual dilution flow, and calculated doses to an individual.
i 1.4 Liquid Effluent Release Data l
1.4.1 Tables l
l Regulatory Guide 1.21 Tables 2A,28, and 2-C are found in this report as Tables l
1-2A,1-2AA,1-28,1-288,1-2-C, and 1-2-CC. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all four quarters.
1.4.2 Total Error Measurement The total or maximum error associated with the effluent measurement includes the cumulative errors resulting from the total operation of sampling and measurement. Because it may be very difficult to assign l
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.
10
Fission and activation total release was calculated from sample analysis a.
results and release point flow rates.
Sampling and statistical error 10%
Counting Equipment Calibration 10%
Tank Volumes and System Flow Rates 20%
TOTAL ERROR 40%
b.
Total Tritium release was calculated from sample analysis results and release point volumes.
Sampling and statistical errors 10%
Counting equipment calibration 10%
Tank volumes and system flow rate 20%
TOTAL ERROR 40%
c.
Dissolved and entrained gases were calculated from sample analysis results and release point volumes.
Sampling and statistical error 20%
l Counting equipment calibration 10%
Tank volumes and system flow rate 20%
i TOTAL ERROR 50 %
I d.
Gross alpha radioactivity was calculated from sample analysis results and j
release point volumes.
i Sampling and statistical error 10%
Counting Equipment calibration 10%
Tank volumes and system flowrates 20%
Compositing sample error 5%
TOTAL ERROR 45%
0.
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%
i Operator Interpretation of gauge 10%
l TOTAL ERROR 20%
j i
i 11 l
)
f.
Volume of dilution water used was calculated from flow rate indicators and pump discharge flow rates and times.
Flow rate indicator error 10%
Operator interpretation of gauge 10%
TOTAL ERROR 20%
1.5 Radiological impact on Man Due to Liquid Releases Doses to an individual due to radioactivity in liquid effluent were calculated in accordance with the Offsite Dose Calculation Manual. Results are presented in Table 1-4A,1-4AA for Unit 1 and 1-48,1-4BB 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 at Augusta for the Annual Effluent Report period was obtained from the U.S. Army Corps of Engineers Savannah District Historic Data web page (http://www.sas.usace. army.millen/en-h/en-ha/adis.html).
The average flow rate for 1997 was 9052 cubic feet per sec.
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TABLE 12 A l
VOGTLE ELECTRIC GENERATING PLANT I
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1997 ALL LIQUID EFFLUENTS UNIT : 1 STARTING : 1-JAN 1997 ENDING : 30 JUN-1997 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
l A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 2.06E-02 5.30E 02 40 TRITIUM,G ASES,ALPH A)
- 2. AVERAGE DILUTED CONCENTRATION uCl/m L 1.58E-07 1.94E 07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT B. TRITIU M
- 1. TOTAL RELEASE CURIES 6.58E+ 01 2.40E+02 40
- 2. AVERAGE DILUTED CONCENTRATION uCl/m L 5.07E-04 8.76E 04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 4.18 E-05 1.19E 03 50
- 2. AVERAGE DILUTED CONCENTRATION uCl/m L 3.22E-10 4.34 E-09 DURING PERIOD
- 3. PERCENTAGF. OF APPLICABLE LIMIT D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 1.32E 06 1.16 E-06 45 E. WASTE VOL RELEASED (PRE DILUTION) LITRE 4.13 E + 0 S 8.94 E + 05 20 F. VOLUME OF DILUTION WATER USED LITRE 1.30 E + 08 2.73 E + 08 20
(
- Applicabk limits are expressed in terms of Dose. SeeTable 14A of this report i
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- I l
TABLE 12AA l
l VOGTLE ELECTRIC GENERATING PLANT j
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 l
ALL LIQUID EFFLUENTS l
UNIT : 1 STARTING ; 1-JUL-1997 ENDING : 31-DEC-1997 l
TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 3.08E-01 7.15E 02 40 TRITIUM, GASES, ALPHA) 1
- 2. AVERAGE DILUTED CONCENTRATION uCi/mL 4.83E-07 2.31 E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT B. TRITIUM
- 1. TOTAL RELEASE CURIES 5.17E+02 1.18 E+02 40
- 2. AVERAGE DILUTED CONCENTRATION uCi/mL 8.11 E-04 3.81 E-04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 4.86E 03 0.00E+00 50
- 2. AVERAGE DILUTED CONCENTRATION uCl/mL 7.62E-09 0.00E+00 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 5.19E 05 3.28E 06 45 E. WASTE VOL RELEASED (PRE DILUTION) LITRE 1.59E+06 8.67E+05 20 l
F. VOLUME OF DILUTION WATER USED LITRE 6.36E+08 3.09E+08 20 l
l
- Apphceble hmits are expressed in terms of Done. See Table 14 of this report 14 l
l l
l TABLE 1-28 VOGTLE ELECTRIC GENERATING PLANT l
ANNUAL RADIOACTIVE EFFLUENT RELE ASE REPORT-1997 ALL LIQUID EFFLUENTS UNIT : 2 STARTING : 1-JAN 1997 ENDING : 30-JUN 1997 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
(
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 1.86E-02 8.53E 03 40 j
TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCl/mL 2.50E-09 1.47E 07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT l
B. TRITIUM
- 1. TOTAL RELEASE CURIES 1.60E+02 7.32E+01 40
- 2. AVERAGE DILUTED CONCENTRATION uCl/mL 2.15E-05 1.26E-03 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 4.03E 04 0.00E+00 50
- 2. AVERAGE DILUTED CONCENTRATION uCl/mL 5.42E-11 0.00E+00 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT
- D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 0.00E+00 3.92E-06 45 E. WASTE VOL RELEASED (PRE DILUTION) LITRE 4.07E+05 2.02E+05 20 F. VOLUME OF DILUTION WATER USED LITRE 7.44E+09 5.77E+07 20
- Appscable wts are expreened in terms of Dose. See Table 1-48 of tNs report 15 -
TABLE 12BB VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 ALL LIQUID EFFLUENTS UNIT : 2 STARTING,1-JUL-1997 ENDING : 31-DEC-1997 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 3.41E 02 3.55E 02 40 TRITIUM. GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCl/mL 1.87E-07 2.27E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT B. TRITIUM
- 1. TOTAL RELEASE CURIES 2.07E+02 6.84E+01 40
- 2. AVERAGE DILUTED CONCENTRATION uCl/mL 1.13E-03 4.37E-04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT C.DISSOLVEL AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1.84E-02 0.00E+00 50
- 2. AVERAGE DlLUTED CONCENTRATION uCi/mL 1.01E 07 0.00E+00 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 2.13 E-05 6.41 E-05 45 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 4.84E+05 4.50E+05 20 F. VOLUME OF DILUTION WATER USED LITRE 1.82E+08 1.56E+08 20
- Apferm Imte are expressed in terms of Done. See Table 1-488 of tNo report 16 -
TABLE 1-2C VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 ALL LIQUID EFFLUENTS SITE STARTING : 1-JAN-1997 ENDING : 30-JUN-1997 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 E ST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 2. AVERAGE DILUTED CONCENTRATION uCl/m L 5.18E-09 1.85 E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT B. TRITlUM
- 1. TOTAL RELEASE CURIES 2.26 E + 02 3.13 E + 02 40
- 2. AVERAGE DILUTED CONCENTRATION uCl/m L 2.98E-05 9.42E-04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 4.45E 04 1.19 E-03 50
- 2. AVERAGE DILUTED CONCENTRATION uCl/mL 5.88E-11 3.59E-09 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 1.32E-06 5.08E-06 45 E.W ASTE VOL RELEASED (PRE-DILUTION) LITRE 8.20 E + 05 1.10 E + 06 20 F. VOLUME OF DILUTION WATER USED LITRE 7.57E+09 3.31 E + 08 20
- Appilcable limits are expreened in terms of Does. See Table 1-4A and 1-48 of tNs report 17 '
I l
TABLE 12CC VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 ALL LIQUID EFFLUENTS SITE STARTING.1-JUL-1997 ENDING : 31 DEC-1997 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 3.42E-01 1.07E-01 40 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCl/mL 4.17E-07 2.29E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT i
B. TRITIUM
- 1. TOTAL RELEASE CURIES 7.24E+02 1.86E+02 40
- 2. AVERAGE DILUTED CONCENTRATION uCl/mL 8.83E 04 4.00E 04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT C.ta!SSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CUR!ES 2.33E-02 0.00E+00 50
- 2. AVERAGE DILUTED CONCENTRATION uCl/mL 2.84E-08 0.00E+00 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 7.32E 05 6.74E-05 45 E. WASTE VOL RELEASED (PRE DILUTION) LITRE 2.07E+06 1.32E+06 20 F. VOLUME OF DILUTION WATER USED LITRE 8.18 E+08 4.65E+08 20
- Apphcable hmits are exproceed in terms of Dooe. See Table 14AA and 1-488 of this report 18 l
i I
TABLE 13A Vogtle Bectric Genemting Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 Uquid Effluents Stating : 1-Jan 1997 Endng : 3Odun-1997 UNIT: 1 CONTINUOUS BATCH NUCUDE UMT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 H-3 CURIES 0.00E+00 6.27E-04 6.58E+01 2.40E+02 FISSION & ACTIVATION PRODUCTS Co 144 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 CURIES 0.00E+00 0.00E+00 1.51E-05 6.16E-05 Cc-58 CURIES 0.00E+00 7.64E-06 1.94E-03 3.41E-03 Co40 CURIES 0.00E+00 3.00E-05 5.59E-03 1.56E-02 Cr-51 CURIES 0.00E+00 0.00E+00 2.20E-04 6.19E-04 Cs 134 CURIES 0.00E+00 0.00E+00 4.16E-05 3.57E-03 Cs 137 CURIES 0.00E+00 0.00E+00 6.62E-05 3.12E-03 Fe 55 CURIES 0.00E+00 1.00E-05 8.14E-03 1.33E-02 l-131 CURIES 0.00E+00 0.00E+00 0.00E+00 9.77E-06 l
MN-54 CURIES 0.00E+00 1.64E-05 1.16E-03 2.67E-03 NB 95 CURIES 0.00E+00 0.00E+00 4.04E-04 4.04E-04 NS 97 CURIES 0.00E+00 0.00E+00 0.00E+00 2.66E-05 SB-124 CURIES 0.00E+00 0.00E+00 8.50E-05 0.00E+00 SB-125 CURIES 0.00E+00 0.00E+00 2.71E-03 1.02E-02 Sn 113 CURIES 0.00E+00 0.00E+00 6.92E-06 0.00E+00 Sr-89 CURIES 0.00E+00 0.00E+00 0.00E+00 1.50E-05 l
Sr-90 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-92 CURlES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZN 65 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZR-95 CURIES 0.00E+00 0.00E+00 2.17E-04 7.64E-06 EIg3 0.00E+00 Lgg-of 2,00E 02 5.30E-02 i
DISSOLVED AND ENTRAINED GASES l
Ar 41 CURlES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe 133 CURIES 0.00E+00 0.00E+00 4.18E-05 1.19E-03 Xe 135 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 0.005+00 0.00E+00 4.18E 05 1.19E-03 G-ALPHA CURIES 0.00E+00 0.00E400 1.32E-06 1.16E-06 i
19
1 TABLE 13AA Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 Liquid Effluents Starting : 1-Jul 1997 Ending : 31 Dec-1997 UNIT : 1 CONTINUOUS BATCH NUCLIDE U NIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 H-3 CURIES 0.00E+00 0.00E+ 00 5.17 E + 02 1.18 E + 02 FISSION & ACTIVATION PRODUCTS:
Ag 110M CURIES 0.00E+00 0.00 E + 00 1.94E-03 7.49E-05 Co 141 CURIES 0.00E+00 0.00E+00 1.29E-05 1.13E-05 Ce-144 CURIES 0.00E+00 0.00 E + 00 0.00E+00 0.00 E + 00 Co-57 CURIES 0.00E+00 0.00 E + 00 4.16E-04 3.88 E-05 Co-58 CURIES 0.00E+00 0.00E + 00 7.60E-03 9.46E-03 Co-60 CURIES 0.00E+00 0.00E+00 7.97E-02 1.17E 02 C r-51 CURIES 0.00E+00 0.00E + 00 1.37E-03 1.05 E-02 Cs-134 CURIES 0.00E+00 0.00E+00 8.82E-04 1.06E-03 Cs 136 CURIES 0.00E+00 0.00E+00 8.03E-06 0.00E+00 Cs 137 CURIES 0.00E+00 0.00E+00 5.98E 04 8.63 E-04 Fe 55 CURIES 0.00E+00 0.00E+ 00 1.50E-01 1.28E-02 Fe-59 CURIES 0.00E+00 0.00E+00 2.97E-04 2.78E-04 1131 CURIES 0.00E+00 0.00E+00 7.72 E-03 6.07E-04 l132 CURIES 0.00E+00 0.00E+ 00 5.27E-03 0.00 E + 00 La 140 CURIES 0.00E+00 0.00E+00 3.94E-04 6.30 E-05 M n-54 CURIES 0.00E+00 0.00E+ 00 1.48E-02 2.53E-03 N a-24 CURIES 0.00E+00 0.00E+ 00 4.85E-06 0.00 E + 00 N b-95 CURIES 0.00E+00 0.00E+00 1.84 E-03 1.39E 03 N b-97 CURIES 0.00E+00 0.00E+00 7.09 E-04
- 0. 00 E + 00 R b-86 CURIES 0.00E+00 0.00E + 00 0.00 E + 00 1.86 E-04 Rh-105 CURIES 0.00E+00 0.00E + 00 0.00E+00 0.00 E + 00 Ru 103 CURIES 0.00E+00 0.00 E+ 00 0.00 E + 00 1.11 E-04 Sb 122 CURIES 0.00E+00 0.00 E + 00 0.00E+00 0.00 E + 00 Sb-124 CURIES 0.00E+00 0.00E+00 1.38E-04 3.62E 04 S b-125 CURIES 0.00E+00 0.00E+00 2.57E-02 1.06E-02 Sn-113 CURIES 0.00E+00 0.00E+00 3.68 E-04 3.80E-05 S r-89 CURIES 0.00E+00 0.00E + 00 1.63 E-03 6.55 E-04 Sr90 CURIES 0.00E+00 0.00E+ 00 4.46E-05 0.00E+00 Sr-92 CURIES 0.00E+00 0.00 E + 00 1.09E-04 0.00 E + 00 Tc-99M CURIES 0.00E+00 0.00E+00 3.14 E-06 0.00E+00 Te 125M CURIES 0.00E+00 0.00 E + 00 0.00 E + 00 7.41E 03 Te129M CURIES 0.00E+00 0.00 E + 00 1.19 E-03 0.00 E+ 00 Te-132 CURIES 0.00E+00 0.00E+ 00 4.31 E-03 0.00 E + 00 Y-92 CURIES 0.00E+00 0.00E+00 1.05E-05 0.00 E + 00 Zn-65 CURIES 0.00E+00 0.00E+00 0.00E+00 1.37E-05 Zr.95 CURIES 0.00E+00 0.00E+00 6.86E-04 7.48E 04 Zr-97 CURIES 0.00E+00 0.00 E + 00 0.00 E + 00 0.00E + 00 I,Q,I,M 0.00E+00 0.00 E + 00 3.08 E-01 7.15 E-02 DISSOLVED AND ENTRAINED GASES:
Xe-133 CURIES C.00E+00 0.00E+ 00 4.86E-03 0.00 E + 00 TOTALS 0.00E+00 0.00 E + 00 4.86 E-0J 0.00E+00 G-ALPHA CURIES 0.0DE+00 0.00E+00 5.19E-05 3.28E-06 20
TABLE 1-38 Vogtle Bectric Generating Rant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 Liquid Effluents Starting : 1-Jan-1997 Endng : 30-Jun-1997 UNIT: 2
^
CONTINUOUS BATCH NUCLlDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 H-3 CURIES 0.00E+00 0.00E+00 1.60E+02 7.32E+01 FISSION & ACTIVATION PRODUCT Ce 144 CURIES 0.00E+00 0.00E+00 1.05E-04 1.62E-04 Co 57 CURIES 0.00E+00 0.00E+00 3.50E-06 2.14E-05 Co 58 CURIES 0.00E+00 0.00900 1.88E-03 6.58E-04 Co40 CURIES 0.00E+00 0.00E+00 3.48E 03 3.66E-03 Cr-51 CURIES 0.00E+00 0.00E+00 1.15E-04 0.00E+00 Cs-134 CURIES 0.00E+00 0.00E+00 2.31E-04 1.06E-04 Cs-137 CURIES 0.00E+00 0.00E+00 1.58E-04 7.47E-05 Fe 55 CURIES 0.00E+00 0.00E+00 8.73E-03 2.08E-03 1-131 CURlES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MN-54 CURIES 0.00E+00 0.00E+00 7.78E-04 6.42E46 Nt>95 CURIES 0.00E+00 0.00E+00 3.12E-04 1.40E-04 Nt>97 CURIES 0.00E+00 0.00E400 0.00E+00 0.00E+00 St> 124 CURIES 0.00E+00 0.00E+00 2.70E-05 0.00E+00 St>125 CURIES 0.00E+00 0.00E+00 2.46E-03 9.25E-04 Sn 113 CURIES 0.00E+00 0.00E+00 0.00E+00 1.82E-05 Sr-89 CURIES 0.00E+00 0.00E+00 4.30E-06 2.73E-05 Sr-90 CURIES 0.00E+00 0.00E+00 1.70F-06 0.00E400 Y-92 CURIES 0.00E+00 0.00E+00 1.00E-04 0.00E+00 Zn46 CURIES 0.00E+00 0.00E+00 1.12E-05 0.00E+00 Zr-95 CURIES 0.00E+00 0.00E+00 1.30E-04 1.58E-05 TOTALS 0.00(;199 g.0.,M 1.06E-02 8.53E-03 DISSOLVED AND ENTRAINED GASES Ar-41 CURIES 0.00E+00 0.00E+00 1.14E-06 0.00E+00 Xe-133 CURJES 0.00E+00 0.00EMO 3.90E-04 0.00E+00 Xe 135 CURIES 0.00E+00 0.00E+00 6.31E-06 0.00E400 TOTALS 0.00p+00 0.00E+00 4.03E-04 0.00E900 G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 3.92E-06 21
1 l
l TABLE 1-3BB Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1997 Liquid Effluents Starting : 1-Jul-1997 Ending : 31-Dec-1997 UNIT : 2 CONTINUOUS BATCH NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QU ARTER 4 H-3 CURIES 0.00E+00 0.00 E+ 00 2.07 E + 02
- 6. 84 E + 01 FISSION & ACTIVATION PRODUCT Ag-110M CURIES 0.00E+00 0.00E+00 5.29E-05 0.00E+00 C e-141 CURIES 0.00 E + 00 0.00E+00 0.00 E + 00 5.80E-05 Ce-144 CURIES 0.00E+00 0.00E+00 1.06E-04 2.02E-04 Co-57 CURIES 0.00E+00 0.00E+00 4.54E-05 2.69E 05 Co-58 CURIES 0.00E+00 0.00E + 00 1.15E-03 183E-03 C o-60 CURIES 0.00E+00 0.00E+00 8.70E-03 7.29E-03 C r-51 CURIES 0.00 E+ 00 0.00E+00 9.65E-05 2.51 E-03 Cs 134 CURIES 0.00E+00 0.00E + 00 6.05E-05 2.43E 05 Cs-136 CURIES 0.00E+00 0.00E+00 0.00 E + 00 0.00 E + 00 Cs-137 CURIES 0.00E+00 0.00 E + 00 6.55E-05 2.89E-05 Fe 55 CURIES 0.00E+00 0.00E+00 9.76E-03 9.89E-03 Fe-59 CURIES 0.00E+00 0.00E+00 0.00E+00 3.40E-05 l-131 CURIES 0.00E+00 0.00E+00 4.34E-04 1.34E-04 l-132 CURIES 0.00E+00 0.00 E + 00 1.62E-03 0.00E+00 La-140 CURIES 0.00E+00 0.00E+00 2.34E-05 1.19E-05 M n-54 CURIES 0.00E+00 0.00 E + 00 1.74E-03 9.48 E-04 N a-24 CURIES 0.00E+00 0.00 E + 00 0.00 E + 00 0.00E+00 N b-95 CURIES 0.00E+00 0.00 E + 00 2.33E-04 2.62E-04 N b-97 CURIES 0.00E+00 0.00 E + 00 1.11 E-04 0.00E+00 R b-86 CURIES 0.00E+00 0.00E+00 0.00 E + 00 0.00E+00 Rh 105 CURIES 0.00 E + 00 0.00 E + 00 0.00E + 00 0.00 E + 00 Ru-103 CURIES 0.00E+00 0.00 E + 00 0.00E+00 1.73E-05 S b-122 CURIES 0.00E+00 0.00E+00 0.00 E + 00 0.00 E + 00 S b-124 CURIES 0.00E+00 0.00E+00 0.00 E+ 00 2.53 E-04 Sb-125 CURIES 0.00E+00 0.00 E + 00 6.78E-03 1.02E-02 Sn 113 CURIES 0.00E+00 0.00 E + 00 1.56E-05 0.00 E + 00 S r-89 CURIES 0.00E+00 0.00E+00 3.10E-04 1.11 E-04 S r-90 CURIES 0.00E+00 0.00E + 00 3.82E-06 8.14E 06 S r-92 CURIES 0.00E+00 0.00E+00 2.18 E-05 0.00 E + 00 Tc-99M CURIES 0.00E+00 0.00E+00 0.00 E + 00 0.00E+00 Te-125M CURIES 0.00E+00 0.00 E + 00 0.00 E + 00 1.55E-03 Te129M CURIES 0.00E+00 0.00 E + 00 1.18E 03 0.00 E + 00 Te-132 CURIES 0.00 E + 00 0.00E+00 1.47E-03 2.28E-06 Y-92 CURIES 0.00E+00 0.00 E + 00 0.00E+00 0.00 E + 00 Zn-65 CURIES 0.00E+00 0.00 E + 00 4.72E-05 0.00 E + 00 Zr 95 CURIES 0.00E+00 0.00E + 00 9.01E 05 1.49E-04 Zr-97 CURIES 0.00E+00 0.00E+00 3.76E-06 0.00E+00 TOTALS 0.00E+00 0.00 E + 00 3.41 E -02
- 3. 55 E-0 2 Xe 133 CURIES 0.00E+00 0.00 E + 00 1.84 E-02 0.00 E+ 00 TOTALS 0.00 E + 00 0.00E+00 1.84 E-02 0.00 E + 00 G ALPHA CURIES 0.00E+00 0.00E + 00 2.13E-05 6.41E-05 t
22
TABLE 1-3C Vogtle Oectric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 Uquid ENIuents Starting : 1-Jan 1997 Endng : 30-Jun-1997 SITE CONTINUOUS BATCH NUCUDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 i+3 CURIES 0.00E+00 6.27E-04 2.26E+02 3.13E+Co_
l FISSION & ACTIVATION PRODUCT l
Co 144 CURIES 0.00E+00 0.00E+00 1.05E-04 1.62E-04 Co-57 CURIES 0.00E+00 0.00E+00 1.88E-05 8.30E-05 Co.56 CURIES 0.00E+00 7.64E-06 3.82E-03 4.07E-03 Co40 CURIES 0.00E+00 3.00E-05 9.07E-03 1.93E-02 l
Cr-51 CURIES 0.00E+00 0.00E+00 3.35E-04 6.19E-04 Cs 134 CURIES 0.00E+00 0.00E+00 2.73E-04 3.60E-03 Cs 137 CURlES 0.00E+00 0.00E+00 2.24E-04 3.19E-03 l
Fe-55 CURIES 0.00E+00 1.00E-05 1.09E-02 1.54E-02 l-131 CURIES 0.00E+00 0.00E+00 0.00E+00 9.77E-06 Mn 54 CURIES 0.00E+00 1.64E-05 1.94E-03 3.31E-03 Nb95 CURIES 0.00E+00 0.00E+00 7.16E-04 5.44E-04 Nb97 CURIES 0.00E+00 0.00E+00 0.00E+00 208E-05 St> 124 CURIES 0.00E+00 0.00E+00 1.12E04 0.00E+00 Sb-125 CURlES 0.00E+00 0.00E+00 5.17E-03 1.11E-02 Sn 113 CURIES 0.00E+00 0.00E+00 6.92E-06 1.82E-05 Sr-90 CURIES 0.00E+00 0.00E+00 4.305 06 4.23E-05 Sr-80 CURIES 0.00E+00 0.00E+00 1.76E-06 0.00E+00 Y-92 CURIES 0.00E+00 0.00E+00 1.09E-04 0.00E+00 ZM55 CURIES 0.00E+00 0.00E+00 1.12E-05 0.00E+00 Zr-95 CURlES 0.00E+00 0.00E+00 3.47E-04 2.34E-05 TOTALS 0.00E+00 7.09E45
.42E:03 6.15E 02 DISSOLVED AND ENTRAINED GASES Ar-41 CURIES 0.00E+00 0.00E+00 1.14E-06 0.00E+00 l
Xe-133 CURIES 0.00E+00 0.00E+00 4.38E-04 1.19E-03 Xa 135 CURlES 0.00E+00 0.00E+00 6.31E-06 0.00E+00 TOTALS 0.00E+00 0.00E+00 4,45E44 1.19E45 l
G-ALPHA CURlES 0.00E+00 0.00E+00 1.32E-06 5.08E-06 l
l 23 '
l
TABLE 1-3CC Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 Liquid Effluents Starting : 1-Jul 1997
' Ending ; 31-Dec-1997 SITE CONTINUOUS BATCH NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 H-3 CURIES 0.00E+00 0.00E+00
- 7.24E+02
- 1.86E+ 02 FISSION & ACTIVATION PRODUCT Ag-110M CURIES 0.00E+00 0.00E+ 00 1.99E-03 7.49E-05 C o-141 CURIES 0.00E+00 0.00E+00 1.29E-05 6.93E Co-144 CURIES 0.00E+00 0.00E+00 1.06E-04 2.02E-04 Co-57 CURIES 0.00E+00 0.00E + 00 4.61 E-04 6.57E-05 Co-58 CURIES 0.00E+00 0.00E+00 8.75E-03 1.13 E-02
- Co-60 CURIES 0.00E+00 0.00E+ 00 8.84E-02 1.90E-02 C r-51 CURIES 0.00E+00 0.00E+ 00 1.47E 1.30E-02 Cs-134 CURIES 0.00E+00 0.00E+00 9.43E-04 1.08E-03 Cs-136 CURIES 0.00E+00 0.00E+00 8.03E-06 0.00E+00 C s-137 CURIES 0.00E+00 0.00E+00 6.64E-04 8.92E-04 Fe-55 CURIES 0.00E+00 0.00E+00 1.60E-01 2.27E-02 i
l Fe-59 CURIES 0.00E+00 0.00E+00 2.97E-04 3.12E-04 1-131 CURIES 0.00E+00 0.00E+00 8.15E-03 7.41 E-04 l132 CURIES 0.00E+00 0.00E+ 00 6.89E-03 0.00E+ 00 La-140 CURIES 0.00E+00 0.00E+00 4.17E-04 7.49E-05 L
M n-54 CURIES 0.00E+00 0.00E+00 1.65E-02 3.48E-03 l
Na-24 CURIES 0.00E+00 0.00E+00 4.85E-06 0.00E + 00 N b-95 CURIES 0.00E+00 0.00E+00 2.07E-03 1.65E-03 l
N b-97 CURIES 0.00E+00 0.00E+00 8.20E-04 0.00E+00 R b-86 CURIES 0.00E+00 0.00E+00 0.00E + 00 1.86E-04 Rh-105 CURIES 0.00E+00 0.00E + 00 0.00E+00 0.00E+00 Ru-103 CURIES 0.00E+00 0.00E+00 0.00E+ 00 1.28E-04 Sb 122 CURIES 0.00E+00 0.00E+ 00 0.00E+00 0.00E+ 00 Sb-124 CURIES 0.00E + 00 0.00E+ 00 1.38E-04 6.15E-04 Sb-125 CURIES 0.00E+00 0.00E+00 3.25E-02 2.08E-02 1
Sn-113 CURIES 0.00E+ 00 0.00E+00 3.84E-04 3.80E-05 S r-89 CURIES 0.00E+00 0.00E+ 00 1.94E-03 7.66E-04 Sr-90 CURIES 0.00E+00 0.00E+00 4.84E-05 8.14E-06 Sr-92 CURIES 0.00E+00 0.00E+00 1.31 E-04 0.00E+00 Tc-99M CURIES 0.00E + 00 0.00E+ 00 3.14E-06 0.00E+00 Te 125M CURIES 0.00E+00 0.00E+00 0.00E+00 8.96E-03 Te129M CURIES 0.00E+00 0.00E+ 00 2.37E-03 0.00E+00 l
Te-132 CURIES 0.00E+00 0.00E+00 5.78E-03 2.28E-06 Y-92 CURIES 0.00E+00 0.00E+ 00 1.05E-05 0.00E + 00 Zn-65 CURIES 0.00E+00 0.00E+00 4.72E-05 1.37E-05 Zr-95 CURIES 0.00E+00 0.00E + 00 7.76E-04 8.97E-04 Zr-97 CURIES 0.00E+00 0.00E+ 00 3.76E-06 0.00E+ 00 TOTALS 0.00E+00 0.00E+ 00 3.42E-01 1.07E 01 Xe-133 CURIES 0.00E+00 0.00E+00 2.33E-02 0.00E+00 TOTALS 9.00.E+ 00 0.00E+00 2.33E-02 0.00E+00 G-ALPHA CURIES 0.00E+00 0.00E+00 7.32E-05 6.74E-05 24 "
TABLE 1-4A VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES j
JANUARY,1997 THROUGH JUNE,1997 UNIT 1 l
CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER
% OF QUARTER
% OF LIMIT 1
ODCM 2
ODCM LIMIT LIMIT Bone 5.0 mrom 5.42E-04 1.08E-02 4.67E-02 9.35E-01 Liver 5.0 mrem 2.03E-03 4.06E-02 9.33E-02 1.87E+00 T. Body 1.5 mrom 1.77E-03 1.18E-01 7.21 E-02 4.81 E+00 Thyroid 5.0 mrem 1.15E-03 2.30E-02 7.21 E-03 1.44E-01 Kidney 5.0 mrom 1.42E-03 2.84E-02 3.55E-02 7.10E-01 l
Lung 5.0 mrom 4.85E-03 9.71 E-02 3.83E-02 7.67E-01 GI-LLI 5.0 mrem 2.22E-03 4.43E-01 1.32E-02 2.65E-01 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE
% OF ODCM LIMIT LIMIT Bone 10.0 mrem 4.73E-02 4.73E-01 Liver 10.0 mrom 9.53E-02 9.53E-01 T. Body 3.0 mrom 7.39E-02 2.46E+00 Thyroid 10.0 mrom 8.36E-03 8.36E-02 Kidney 10.0 mrom 3.69E-02 3.69E-01 Lung 10.0 mrom 4.32E-02 4.32E-01 GI-LLI 10.0 mrom 1.54E-02 1.54E-01 25
- i l
TABLE 1-4AA VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES July,1997 THROUGH December,1997 UNIT 1 CUMULATIVE DOS _E PER QUARTER ORGAN ODCM UNITS QUARTER
% OF QUARTER
% OF LIMIT 3
ODCM 4
ODCM LIMIT LIMIT Bone 5.0 mrem 1.52E-02 3.03E-01 1.57E-02 3.14E-01 Liver 5.0 mrom 3.88E-02 7.76E-01 3.15E-02 6.30E-01 T. Body 1.5 mrom 3.26E-02 2.18E+00 2.45E-02 1.63E+00 Thyroid 5.0 mrem 2.81 E-02 5.62E-01 4.75E-03 9.50E-02 Kidney 5.0 mrom 2.49E-02 4.98E-01 1.39E-02 2.77E-01 Lung 5.0 mrom 8.77E-02 1.75E+00 3.36E-02 6.71 E-01 Gl-LLI 5.0 mrom 4.74E-02 9.47E-01 1.14E-02 2.29E-01 CUMULATIVE DOSE PER YFAR ORGAN ODCM UNITS YEAR TO DATE
% OF ODCM l
LIMIT LIMIT Bone 10.0 mrom 7.81 E-02 7.81 E-01 Liver 10.0 mrom 1.66E-01 1.66E+00 j
T. Body 3.0 mrom 1.31 E-01 4.37E+00 Thyroid 10.0 mrom 4.12E-02 4.12E-01 Kidney 10.0 mrom 7.57E-02 7.57E-01 Lung 10.0 mrom 1.64E-01 1.64E+00 GI-LLI 10.0 mrom 7.42E-02 7.42E-01 i
)
26 1
l TABLE 1-4B VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES JANUARY,1997 THROUGH JUNE,1997 UNIT 2 CUMULATIVE DOSE PER QUARTER j
ORGAN ODCM UNITS QUARTER
% OF QUARTER
% OF LIMIT 1
ODCM 2
ODCM LIMIT LIMIT Bone 5.0 mrom 1.50E-03 2.99E-02 1.55E-03 3.10E-02 Liver 5.0 mrom 4.67E-03 9.35E-02 5.35E-03 1.07E-01 T. Body 1.5 mrom 4.00E-03 2.67E-01 4.65E-03 3.10E-01 Thyroid 5.0 mrom 1.93E-03 3.86E-02 2.42E-03 4.84E-02 Kidney 5.0 mrem 2.82E-03 5.63E-02 3.37E-03 6.74E-02 Lung 5.0 mrom 4.93E-03 9.87E-02 5.36E-03 1.07E-01 GI-LLf 5.0 mrom 2.60E-03 5.20E-02 3.44E-03 6.88E-02 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE
% OF ODCM LIMIT LIMIT Bone 10.0 mrem 3.05E-03 3.05E-02 Liver 10.0 mrem 1.00E-02 1.00E-01 T. Body 3.0 mrom 8.65E-03 2.88E-01 Thyroid 10.0 mrom 4.35E-03 4.35E-02 Kidney 10.0 mrom 6.18E-03 6.18E-02 Lung 10.0 mrom 1.03E-02 1.03E-01 GI-LLI 10.0 mrom 6.04E-03 6.04E-02 27
t TABLE 1-4BB VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES JULY,1997 THROUGH DECEMBER,1997 UNIT 2 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER
% OF QUARTER
% OF LIMIT 3
ODCM 4
ODCM LIMIT LIMIT Bone 5.0,
mrem 2.11 E-03 4.22E-02 1.06E-03 2.12E-02 Liver 5.0 mrem 9.52E-03 1.90E-01 2.95E-03 5.90E-02 T. Body 1.5 mrem 8.80E-03 5.87E-01 2.73E-03 1.82E-01 Thyroid 5.0 mrem 7.32E-03 1.56E-01 2.20E-03 4.39E-02 Kidney 5.0 mrsm 9.63E-03 1.93E-01 2.56E-03 5.11 E-02 Lung 5.0 mrem 2 70E-02 5.40E-01 2.80E-02 5.59E-01 GI-LLI 5.0 mrem 1.47E-02 2.95E-01 6.15E-03 1.23E-01 CUMULATIVE DOSE PER YEAR l ORGAN ODCM UNITS YEAR TO DATE
% of ODCM LIMIT LIMIT Bone 10.0 mrem 6.22E-03 6.22E-02 Liver 10.0 mrem 2.25E-02 2.25E-01 T. Body 3.0 mrem 2.02E-02 6.73E-01 Thyroid 10.0 mrem 1.44E-02 1.44E-01 Kidney
_ 10.0 mrem 1.84E-02 1.84E-01 Lung 10.0 mrem 6.52E-02 6.52E-01 GI-LLI 10.0 mrem 2.69E-02 2.69E-01 28 '
TABLE 1-5 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES VOGTLE ELECTRIC GEN /iRATING PLANT Ji,tvUARY,1997 - DECEMBER 31,1997 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 Ci/mi Fe-59 8.33E-08 Ci/mi Co-58 3.78E-08 Ci/mi Co-60 6.76E-08 Ci/mi Zn-65 1.32E-07 Ci/ml Mo-99 4.31 E-07 Ci/mi Cs-134 3.06E-08 Ci/mi Cs-137 4.51 E-08 Ci/ml Ce-141 6.99E-08 Ci/ml Ce-144 2.95E-07 Ci/ml 1-131 5.97E-0B Ci/ml Xe-133 9.11 E-08 Ci/mi Xe-135 4.27E-08 Ci/mi Fe-55 1.00E-06 pCi/mi Sr-89 5.00E-08 Ci/ml Sr-90 7.00E-09 Ci/ml H-3 2.00E-06 Ci/mi Gross Alpha 7.00E-08 Ci/mi 29
l TABLE 1-6A 1
VOGTLE ELECTRIC GENERATING PLANT-UNIT 1 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JANUARY,1997 ENDING: JUNE,1997 l
i LIQUID RELEASES Number of Releases 29 Total Time For All Releases 6232.33 minutes Maximum Time For a Release 790.00 minutes Average Time For a Release 214.91 minutes Minimum Time For a Release 57.00 minutes GASEOUS RELEASES Number of Releases:
61 Total Ti.ae For All Releases 14699.90 minutes Maximum Time For A Release 6425.00 minutes Average Time For A Release 240.98 minutes Minimum Time For A Release 6.00 minutes 30
TABLE 1-6AA VOGTLE ELECTRIC GENERATING PLANT-UNIT 1 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JULY,1997 ENDING: DECEMBER,1997 LIQUID RELEASES Number of Releases 57 Total Time For All Releases 12277.00 minutes Maximum Time For a Release 455.00 minutes Average Time For a Release 215.39 minutes Minimum Time For a Release 45.00 minutes GASEOUS RELEASES Number of Releases:
100 Total Time For All Releases 55683.67 minutes l
Maximum Time For A Release 6740.00 minutes l
Average Time For A Release 556.84 minutes l
Minimum Time For A Release 3.00 minutes l
31
TABLE 1-6B VOGTLE ELECTRIC GENERATING PLANT-UNIT 2 l
1 1
BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING:
JANUARY,1997 ENDING:
JUNE,1997 LIQUID RELEASES i
Number of Releases 22 Total Time For All Releases 2763.20 minutes Maximum Time For a Release 292.53 '
minutes Average Time For a Release 125.60 minutes Minimum Time For a Release 45.00 minutes GASEOUS RELEASES Number of Releases:
23 Total Time For All Releases 1773.00 minutes Maximum Time For A Release 151.00 minutes Average Time For A Release 77.09 minutes Minimum Time For A Release 10.00 minutes l
l l
32
e TABLE 1-6BB VOGTLE ELECTRIC GENERATING PLANT-UNIT 2 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING:
JULY,1997 ENDING:
DECEMBER,1997 LIQUID RELEASES Number of Releases 38 Total Time For All Releases 4525.00 minutes Maximum Time For A Release 368.00 minutes Average Time For A Release 119.08 minutes Minimum Time For A Release 15.00 minutes GASEOUS RELEASES Number of Releases 44 Total Time For All Releases 4331.00 minutes Maximum Time For a Release 1200.00 minutes Average Time For A Release 98.43 minutes Minimum Time For A Release 30.00 minutes i
i G
33 '
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 i
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.
l 34 -
2.1.4 Total Fuel Cycle Dose Commitment (40CFR190) i 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 Collection and Analysis All of the paths can be continuously monitored for gaseous radioactivity. Each is equipped with an integrated-type sample collection device for collecting particulates and iodines. During this reporting period, there were no continuous radioactive releases through the condenser air ejector and steam packing exhauster system vents. Batch Waste Gas Decay Tank releases are analyzed for noble gases before each release.
The containment atmosphere is analyzed for noble gases prior to each release and for tritium at least on a monthly basis.
Sample analyses results and release flow rates form the basis for calculating released quantities of radionuclide specific radioactivity, dose rates associated with gaseous releases, and cumulative doses for the current quarter and year.
With each release period and batch release, radioactivity, dose rates, and cumulative doses are calculated. Cumulative dose results are tabulated, along with the percent of the ODCM limits for each release for the current quarter and year.
l 35 ~
2.4 Total Quantitles of Radioactivity, Dose Rates, and Cumulative Doses The methods for determining release quantities of radioactivity, dose rates, and cumulative doses cre 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, radioiodines, tritium, and particulates are calculated. Calculated dose rates are compared to the dose rate limits specified in ODCM 3.12 for noble gases, radioiodines, tritium, and particulates. Dose rate calculation methodology is presented in the ODCM.
Beta and gamma air doses due to noble gases are calculated for the location in the unrestricted area with the potential for the highest exposure due to gaseous releases.
Air doses are calculated for each release period and cumulative totals are kept for each unit for the calendar quarter and year. Cumulative air doses are compared with the dose limits specified in ODCM 3.1.3. Current percent of the ODCM limits are shown on the printout for each release period. Air dose calculation methodo:3gy is presented in the 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.
Individual doses due to radioiodines, 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 36
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 calculations.
2.:
Gaseous Effluent Release Data I
2.5.1 Methodology i
Regulatory Guide 1.21 Tables 1 A,1B, and 1C are found in this report as Tables 2-2A,2-2AA, 2-28, 2-2BB, 2-2C, 2-2CC, 2-3A, 2-3AA, 2-38, 2-3BB, 2-3C, 2-3CC, 2-4A, 2-4AA, 2-4B,2-4BB,2-4C, and 2-4CC Data are presented on a quarterly basis as required by Regulatory Guide 1.21.
To complete table 2-2A,2-2AA, 2-2B, and 2-2B8, the total release for each of the four categories (fission and activation gases, iodines, particulates, and tritium) was divided l
by the number of seconds in the quarter to obtain a release rate in Cl/second for each category. However, the percent of the ODCM limits are not applicable because VEGP has no curie limits for gaseous releases. Applicable limits are expressed in terms of dose. Noble gases are limited as specified in ODCM 3.1.2. The other three categories
-(tritium, 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.
I Gross alpha radioactivity is reported in Table 2-2A,2-2AA,- 2-2B, and 2-2BB as curies released in each quarter.
Limits for cumulative beta and gamma air doses due to noble gases are specified in i
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.
l Limits for cumulative individual doses due to radioiodines, tritium and particulates, are l
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.
1 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 l
37 '
i j
measurements of radioactive materials released in liquid and gaseous effluents and solid waste.
Estimated errors are based on errors in counting equipment calibration, counting statistics, vent-flow rates, vent sample flow rates, non-steady release rates, chemical i
yield factors, and sample losses for such items as charcoal cartridges.
e.
Fission and activation total release was calculated from sample analysis results and release point flow rates.
Sampling and statistical error in counting 10%
Counting equipment calibration 10%
Vent flow Rates 10%
Non-steady release rates 20%
TOTAL ERROR 50%
b.
1-131 releases were calculated from each weekly sample:
Statistical error in counting 10%
Counting equipment calibration 10%
Vent Flow Rates 10%
Vent Sample Flow Rates 50 %
Non-Steady release rates 10%
Losses from charcoal cartridges 10%
TOTAL ERROR 100 %
1 c.
Particulates with half lives greater than 8 day releases were calculated from sample and analysis results and release point flow rates.
Statistical error at MDC concentration 10%
Counting equipment calibration 10%
i Vent flow rates 10%
Vent sample flow rates 50%
Non steady release rates 10%
TOTAL ERROR 90 %
d.
Total tritium releases were calculated from sample analysis results and release point flow rates.
i l
Water vapor in sample stream determination 10 %
Vent flow rates "j%
Counting calibration and statistics 10%
Non-steady release rates 10%
TOTAL ERROR 40%
38 '
c.
Gross Alpha radioactivity was calculated from sample analysis results and release point flow rates.
j Statistical error at MDC concentration 10%
Counting equipment calibration 10%
Vent flow rates 10%
Vent sample flow rates 50 %
1 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,14B, and 14BB.
2.6 RadiologicalImpact Due to Gaseous Releases Dose rates due to the release of noble gases were calculated for the site in accordance with ODCM 3.4.1.1 Dose rates due to radioiodines, tritium, and particulates in gaseous releases were calculated in accordance with ODCM 3.4.1.2.
Dose rates were calculated as part of pre-release and post release permits, no limits were exceeded for this reporting period.
Cumulative air doses due to noble gas releases were calculated for each unit in l
accordance with ODCM 3. 4.2.These results are presented in Tables 2-6A, 2-6AA,2-68, and 2-688.
Dose rates and doses were calculated using the methodology presented in the Vogtle Electric Generating Plant Offsite Dose Calculation Manual.
2.7 Abnormal Releases i
There were 3 unplanned gaseous releases in 1997:
A. Permit # 970051 was generated for Unit 1 Gas Decay Tank # 1 which lost approximately 22 psi between 1-31-97 and 2-20-97. A leaking valve was discovered as the cause and the contents of Gas decay tank #1 were transferred to Gas decay tank #5 thereby terminating the release. DC # 1-97-073 was written to address this incident.
Sampling and analysis was performed and this release was verified to be in compliance with the Offsite Dose Calculation Manual limits with 20.6 Curies released.
39 '
2.7 Abnormal Releases cont'd B. Permit # 970119 'was generated on 44-97 following the release of radioactive gases from the Unit 2 Waste Gas system during compressor maintenance. Valve leak by into an isolated waste gas system was determined to be the cause; deficiency 2-97-111 was generated to further address this incident.
~ The area radiation monitor alerted personnel to the leak and samples were pulled.
The duration of the release was determined to be 80 minutes using Plant Computer trends. The source term was permitted and was determined to be in compliance with the Offsite Dose Calculation Manual limits. An estimated 0.014 Curies were released.
C. Permit # 970192 was generated for a release from the Unit 1 Equipment Building on 7-28-97. On 7-28-97 background radiation increases in the unit 1 Equipment Building coupled with primary lab sampling activity and plant vent effluent monitor increases led to the discovery of a sneak release path from the plant vent. This flow path was identified to be originating in the plant vent stack bypassing plant vent effluent monitors and leaking past damper 1-HV-2632B. The path continued out of the housing
)
for the containment mini purge exhaust fan 1-1506-B7-002-H01 and into the Equipment j
Building. Samples obtained in the area were used to generate release permit. Dose and j
dose rates were well within the ODCM limits. An estimated 4.81E-05 Curies were i
released.
Total dose to the public due to mixed and ground mode release for the second half of 1997 was 2.02E-04 mrem. Dose due to Equipment Building release alone was only 5.03E-07 mrem which is only 0.24% of the total dose to the public for the second half. So an estimated 6.53E-05 mrem would have been given to the public for the first half of the i
year. Total gaseous effluent dose for 1997 is 7.17E-04 mrem, which is about 2.39E-03%
of ODCM limit. Therefore only 5.74E-04% of the ODCM dose limit is from the Equipment Building. The increase in dose attributed to the Equipment Building release point is insignificant. Therefore doses from Equipment Building release points will no longer be calculated for routine continuos releases.
i 40
r-l TABLE 2-2A VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 ALL AIRBORNE EFFLUENTS UNIT : 1 STARTING : 1-JAN-1997 ENDING : 30-JUN-1997 l
TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 3.91 E+01 1.00E+ 01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD Ci/Sec 5.03E+00 1.27E + 00
- 3. PERCENTAGE OF APPLICABLE LIMIT N/A N/A l
B. RADIOIODINES
- 1. TOTAL IODINE-131 CURIES 2.23E-06 4.73E-06 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 2.87E-07 6.02E-07 l
- 3. PERCENTAGE OF APPLICABLE LIMIT l
C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS)
CURIES 1.73E-07 0.00E+00 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.22E-08 0.00E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT l
l D. TRITIUM i
- 1. TOTAL RELEASE CURIES 1.37E+01 3.28E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 1.76E+00 4.17E+ 00
- 3. PERCENTAGE OF APPLICABLE LIMIT
- 4. GROSS ALPHA RADIOACTIVITY CURIES 0.00E+00 0.00E+00 90
- Apphcable kmns are expressed in terms of Does. See Tath 2-6A and 2-7A of this report 41 '
TABLE 2 2AA VOGTLE ELECTRIC GENERATING PLANT l
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 l
ALL AIRBORNE EFFLUENTS l
UNIT : 1 STARTING : 1-JUL-1997 ENDING : 31-DEC-1997 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 1.46E+02 1.09E+00 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 1.84E+01 1.37E-01
- 3. PERCENTAGE OF APPLICABLE LIMIT B. RADIOlODINES
- 1. TOTAL IODINE-131 CURIES 1.82E 03 1.74E-04 100 l
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 2.29E 04 2.19E-05
- 3. PERCENTAGE OF APPLICABLE LIMIT C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS)
CURIES 4.92E-06 1.51 E-05 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 6.19E-07 1.90E-06
- 3. PERCENTAGE OF APPLICABLE LIMIT D. TRITIUM
- 1. TOTAL RELEASE CURIES 1.32E+ 01 2.57E+ 01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 1.66E+00 3.23E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT
- 4. GROSS ALPHA RADIOACTIVITY CURIES 9.51 E-10 1.05E-06 90 l
I
- Appicable hmRs are expressed in terms of Done. See Tables 2-6AA and 2-7AA of this report 42 '
l
l l
l TABLE 2-28 l
VOGTLE ELECTRIC GENERATING PLANT l
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 ALL AIRBORNE EFFLUENTS UNIT : 2 STARTING : 1-JAN-1997 ENDING : 30-JUN-1997 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
)
- 1. TOTAL RELEASE CURIES 2.04 E+ 00 2.99E+00 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.62E-01 3.80E-01
- 3. PERCENTAGE OF APPLICABLE LIMlY B. RADIOIODINES
- 1. TOTAL IODINE-131 CURIES 2.49E 06 9.48E 07 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.20E-07 1.21 E-07
- 3. PERCENTAGE OF APPLICABLE LIMIT C. PARTICULATES I
1.PARTICULATES(HALF-LIVES >8 DAYS)
CURIES 1.88E 06 8.06E 08 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 2.42E 07 1.03E-08
- 3. PERCENTAGE OF APPLICABLE LIMIT D. TRITIUM i
- 1. TOTAL RELEASE CURIES 6.97E+00 6.41 E+00 40 I
l
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 8.96E 01 8.15E-01 1
- 3. PERCENTAGE OF APPLICABLE LIMIT
- 4. GROSS ALPHA RADIOACTIVITY CURIES 7.82E-14 2.03E-13 90 i
l l
j
- Apphceblo limas are expressed in terms of Dose. See Tables 2 68 and 2-78 of this report j
43 j
i TABLE 2-2BB VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 ALL AIRBORNE EFFLUENTS UNIT : 2 l
STARTING 1-JUL-1997 ENDING : 31-DEC 1997 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE -
CURIES 2.17E + 01 1.96E+00 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 2.73E+00 2.47E 01
- 3. PERCENTAGE OF APPLICABLE LIMIT B. RADIOlODINES
- 1. TOTAL IODINE-131 CURIES 7.74E 06 4.73E-05 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 9.74E 07 5.95E-06
- 3. PERCENTAGE OF APPLICABLE LIMIT C. PARTICULATES 1.PARTICULATES(HALF. LIVES >8 DAYS)
CURIES 1.67E 06 6.09E 07 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 2.10E 07 7.66E 08
- 3. PERCENTAGE OF APPLICABLE LIMIT D. TRITIUM
- 1. TOTAL RELEASE CURIES 3.46E+00 3.12E+ 00 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 4.35 E-01 3.93E 01
- 3. PERCENTAGE OF APPLICABLE LIMIT
- 4. GROSS ALPHA RADIOACTIVITY CURIES 1.15E-06 1.53E-07 90 l
- Ap=* limde are expressed in terms of Done. See Toth 2488 and 2 788 of tNs report l
44 '
TABLE 2-2C VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 ALL AIRBORNE EFFLUENTS SITE STARTING : 1-JAN-1997 ENDING : 30-JUN-1997 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 4.11 E + 01 1.30E+ 01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.29E+00 1.65E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT B.RADIOlODINES
- 1. TOTAL IODINE-131 CURIES 4.72E-06 5.68E-06 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 6.07E-07 7.225-07
- 3. PERCENTAGE OF APPLICABLE LIMIT C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS)
CURIES 2.05E-06 8.06E-08 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 2.64E-07 1.03E-08
- 3. PERCENTAGE OF APPLICABLE LIMIT D. TRITIUM
- 1. TOTAL RELEASE CURIES 2.07E + 01 3.92E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 2.66E+ 00 4.99E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT
- 4. GROSS ALPHA RADIOACTIVITY CURIES 7.82E-14 2.03E-13 90
- Aph limits are expreseed in terms of Dose. See Tables 2 6A,2-68. 2-7A and 2-78 of this report 45 -
TABLE 2-2CC VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1997 ALL AIRBORNE EFFLUENTS SITE STARTING 1-JUL-1997 ENDING : 31-DEC-1997 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 1,68E+02 3.05E+ 00 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 2.11 E + 01 3.84E-01
- 3. PERCENTAGE OF APPLICABLE LIMIT B. RADlOIODINES
- 1. TOTAL LODINE-131 CURIES 1.83E-03 2.21 E-04 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 2.30E-04 2.78E-05
- 3. PERCENTAGE OF APPLICABLE LIMIT C. PARTICULATES I
1.PARTICULATES(HALF-LIVES >8 DAYS)
CURIES 6.59E-06 1.57E-05 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 8.29E-07 1.98E 06
- 3. PERCENTAGE OF APPLICABLE LIMIT D.TRITlUM
- 1. TOTAL RELEASE CURIES 1.67E+ 01 2.88E+ 01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 2.10 E+ 00 3.63E+00 i
- 3. PERCENTAGE OF APPLICABLE LIMIT j
- 4. GROSS ALPHA RADIOACTIVITY CURIES 1.15E-06 1.20E-06 90 i
i
- Aym hmrts are expressed in terms of Done. See Tab 6es 2-6AA. 2-6BB, 2-7AA and 2-7BB of the report 1
l l
46 1
I TABLE 2-3A (PAGE 1 OF 1)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JANUARY,1997 THROUGH JUNE,1997
\\
UNIT 1 i
NUCLIDES RELEASED
\\
UNIT CONTINUOUS MODE BATCH MODE l
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 1
2 1
2 Ar-41 Ci 0.00E+00 0.00E+00 1.47E-01 4.87E-02 Kr-85 Ci 0.00E+00 0.00E+00 5.45E+00 0.00E+00 j
Kr-85m Ci 0.00E+00 0.00E+00 4.15E-02 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 8.17E-03 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 4.34E-02 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 1.87E-01 3.01 E-03 l
Xe-133 Ci 1.17E+01 7.69E+00 2.08E+01 1.94E+00 Xe-133m Ci 0.00E+00 0.00E+00 2.13E-01 7.14E-02 Xe-135 Ci 0.00E+00 2.17E-01 5.27E-01 2.58E-02 Xe-135m Ci 0.00E+00 0.00E+00 1.60E-03 0.00E+00 TOTAL FOR PER/OD Ci 1.17E+01 7.91 E+00 2.74E+01 2.09E+00 j
- 2. ladine's l-131 Ci 2.23E-06 4.73E-06 0.00E+00 0.00E+00 l-133 Ci 0.00E+00 2.05E-06 0.00E+00 0.00E+00
)
TOTAL FOR PER/OD Ci 2.23E-06 6.78E-06 0.00E+00 0.00E+00
- 3. Particulates Sr-89 Ci 1.73E-07 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PER/OD Ci 1.73E-07 0.00E+00 0.00E+00 0.00E+00 H-3 Ci 1.36E+01 3.27E+01 1.02E-01 6.09-E-02
)
1
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See I
Table 2-8 for typical minimum detectable concentrations.
i 47
- i l
TABLE 2-3AA (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JULY,1997 THROUGH DECEMBER,1997 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gssses QUARTER QUARTER QUARTER QUARTER 3
4 3
4 Ar-41 Ci 0.00E+00 0.00E+00 8.81 E-02 3.21 E-02 Kr-85 Ci 0.00E+00 0.00E+00 5.14E-01 0.00E+00 i
Kr-85m Ci 2.90E-02 0.00E+00 2.07E-04 0.00E+00 Kr-87 Ci 4.09E-02 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 1.42E+00 0.00E+00 Xe-133 Ci 3.01 E+01 1.01 E+00 1.11 E+02 2.52E-02 Xe-133m Ci 0.00E+00 0.00E+00 7.41 E-01 0.00E+00 Xe-135 Ci 1.27E+00 0.00E+00 1.81 E-01 1.57E-03 Xe-135m Ci 4.95E-02 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PER/OD Ci 3.15E+01 1.01 E+00 1.14E+02 5.89E-02
- 2. lodines 1-131 Ci 1.64E-03 5.25E 05 2.04E-10 0.00E+00 1-133 Ci 1.39E-04 8.17E-06 1.14E-13 0.00E+00 TOTAL FOR PER/OD Ci 1.78E-03 6.07E-05 2.04E-10 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.
48
i TABLE 2-3AA(PAGE 2 OF 2) i j
VOGTLE ELECTRIC GENERATING PLANT
}
ANNUAL EFFLUENTS - MIXED MODE JULY,1997 THROUGH DECEMBER,1997 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates QUARTER QUARTER QUARTER QUARTER 3
4 3
4 CO-58 Ci 2.90E-07 1.39E-06 0.00E+00 0.00E+00 CO40 Ci 0.00E+00 7.90E-07 0.00E+00 0.00E+00 CS-134 Cl 1.64E-06 6.83E-06 0.00E+00 0.00E+00 CS-137 Cl 1.31 E-06 5.93E-06 0.00E+00 0.00E+00 1-131 Cl 1.55E-06 0.00E+00 0.00E+00 0.00E+00 SR-89 Cl 1.18E-07 1.36E-07 0.00E+00 0.00E+00 SR-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 4.91 E-06 1.51 E-05 0.00E+00 0.00E+00 G-ALPHA Cl 5.97E-13 1.05E-06 0.00E+00 0.00E+00 I
H-3 Ci 1.31 E+01 2.56E+01 1.21 E-02 5.66E-02
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
1 l
49 -
)
j
TABLE 2-38 (PAGE 1 OF 1)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JANUARY,1997 THROUGH JUNE,1997 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 1
2 1
2 Ar-41 Ci 0.00E+00 0.00E+00 1.69E-02 2.24E-02 Kr-85m Ci 0.00E+00 0.00E+00 4.04E-05 0.00E+00 Xe-135 Ci 0.00E+00 2.58E-01 2.46E-03 2.28E-03 Xe-133m Ci 0.00E+00 0.00E+00 1.92E-04 6.80E-04 Xe-133 Cl 1.89E+00 2.52E+00 1.31 E-01 1.77E-01 TOTAL FOR PERIOD Ci 1.89E+00 2.78E+00 1.50E-01 2.03E-01
- 2. lodine's 1-131 Cl 1.21 E-05 4.66E-06 0.00E+00 0.00E+00 1-133 Ci 2.49E-06 9.48E-07 0.00E+00 0.00E+00 TOTAL FOR PERIOD Cl 1.46E-05 5.61 E-06 0.00E+00 0.00E+00
- 3. Particulates Co-58 Ci 8.05E-07 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 1.02E-06 0.00E+00 0.00E+00 0.00E+00 Sr-89 Ci 5.27E-08 8.06E-08 0.00E+00 0.00E+00 1
TOTAL FOR PER/OD Cl 1.88E-06 8.06E-08 0.00E+00 0.00E+00 G-ALPHA Ci 7.82E-14 2.03E-13 0.00E+00 0.00E+00 H-3 Ci 6.97E+00 6.40E+00 5.01 E-03 9.30E-03 i
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
50 l
l
TABLE 2-3BB (PAGE 1 OF 1)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JULY,1997 THROUGH DECEMBER,1997 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 3
4 3
4 Ar-41 Ci 0.00E+00 0.00E+00 5.02E-02 4.11 E-02 Kr-85 Ci 0.00E+00 0.00E+00 6.73E-01 0.00E+00 Kr-85m Ci 0.00E+00 0.00E+00 4.85E-04 0.00E+00 Xe-133 Ci 2.03E+01 1.34E+00 3.43E-01 1.67E-01 Xe-133m Ci 0.00E+00 0.00E+00 7.03E-04 0.00E+00 Xe-135 Ci 2.02E-01 4.06E-01 1.25E-02 1.73E-03 XE-137 Ci 0.00E+00 0.00E+00 2.37E-02 0.00E+00 TOTAL FOR PERIOD Ci 2.05E+01 1.75E+00 1.10E+00 2.10E-01
- 2. Iodines 1-131 Ci 7.74E-06 4.73E-05 0.00E+00 0.00E+00 1-133 Ci 3.48E-05 3.49E-05 0.00E+00 0.00E+00 l
TOTAL FOR PER/OD Ci 4.25E-05 8.22e-05 0.00E+00 0.00E+00
- 3. Particulates Co 60 Ci 1.67E-06 5.50E-07 0.00E+00 0.00E+00 Sr-89 Ci 6.66E-16 5.86E-08 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 1.67E-06 6.09E-07 0.00E+00 0.00E+00 G-ALPHA Ci 1.15E-06 1.53E-07 0.00E+00 0.00E+00 H-3 Ci 3.45E+00 3.11 E+00 1.27E-02 2.67E-03
' Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
51
i TABLE 2-3C (PAGE 1 OF 1)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JANUARY,1997 THROUGH JUNE,1997 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 1
2 1
2 Ar-41 Ci 0.00E+00 0.00E+00 1.64E-01 7.12E-02 i
Kr-85 Ci 0.00E+00 0.00E+00 5.45E+00 0.00E+00 Kr-85m Ci 0.00E+00 0.00E+00 4.15E-02 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 8.17E-03 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 4.34E-02 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 1.87E-01 3.01 E-03 Xe-133 Cl 1.36E+01 1.02E+01 2.09E+01 2.12E+00 Xe-133m Ci 0.00E+00 0.00E+00 2.13E-01 7.21 E-02 Xe-135m Ci 0.00E+00 0.00E+00 1.60E-03 0.00E+00 Xe-135 Ci 0.00E+00 4.75E-01 5.29E-01 2.81 E-02 TOTAL FOR PERIOD Ci 1.36E+01 1.07E+01 2.75E+01 2.29E+00
- 2. lodines 1-131 Ci 1.21 E-05 6.70E-06 0.00E+00 0.00E+00 1-133 Ci 4.73E-06 5.68E-06 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 1.68E-05 1.24E-05 0.00E+00 0.00E+00
- 3. Particulates Sr-89 Ci 2.25E-07 8.06E-08 0.00E+00 0.00E+00
?
Co-58 Ci 8.05E-07 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 1.02E-06 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PER/OD Ci 2.05E-06 8.06E-08 0.00E+00 0.00E+00 G-ALPHA Ci 7.82E-14 2.03E-13 0.00E+00 0.00E+00 f
H-3 Ci 2.06E+01 3.91 E+01 1.07E-01 7.02E-02
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
i 52
)
\\
TABLE 2-3CC (PAGE 1 OF 2) i VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JULY,1997 THROUGH DECEMBER,1997 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 3
4 3
4 Ar-41 Ci 0.00E+00 0.00E+00 1.38E-01 7.32E-02 Kr-85 Ci 0.00E+00 0.00E+00 1.19E+00 0.00E+00 Kr-85m Ci 2.90E-02 0.00E+00 6.91 E-04 0.00E+00 Kr-87 Ci 4.09E-02 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 1.42E+00 0.00E+00 Xe-133 Ci 5.05E+01 2.35E+00 1.11 E+02 1.92E-01 Xe-133m Ci 0.00E+00 0.00E+00 7.42E-01 0.00E+00 Xe-135 Cl 1.47E+00 4.06E-01 1.93E-01 3.30E-03 Xe-135M Ci 4.95E-02 0.00E+00 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 2.37E-02 0.00E+00 TOTAL FOR PERIOD Ci 5.21 E+01 2.76E+00 1.15E+02 2.69E-01
- 2. Iodines 1-131 Ci 1.64E-03 9.98E-05 2.04E-10 0.00E+00 1-133 Ci 1.74E-04 4.30E-05 1.14E-13 0.00E+00 TOTAL FOR PERIOD Cl 1.81 E-03 1.43e-04 2.04E-10 0.00E+00
- 3. Particulates Co-58 Ci 2.90E-07 1.39E-06 0.00E+00 0.00E+00 Co-60 Ci 1.67E-06 1.34E-06 0.00E+00 0.00E+00 Cs-134 Ci 1.64E-06 6.83E-06 0.00E+00 0.00E+00 Cs-137 Cl 1.31 E-06 5.93E-06 0.00E+00 0.00E+00 1-131 Ci 1.55E-06 0.00E+00 0.00E+00 0.00E+00 Sr-89 Ci 1.18E-07 1.95E-07 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD l
Ci 6.58E-06 1.57E-05 0.00E+00 0.00E+00 53
TABLE 2-3CC (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JULY,1997 THROUGH DECEMBER,1997 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE QUARTER QUARTER QUARTER QUARTER 3
4 3
4 G-ALPHA Cl 1.15E-06 1.20E-06 0.00E+00 0.00E+00 H-3 Ci 1.66E+01 2.87E+01 2.48E-02 5.92E-02
- Zeroes in this mole indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
54
4 TABLE 2-4A (PAGE 1 OF 1)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JANUARY,1997 THROUGH JUNE,1997 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 1
2 1
2 TOTAL FOR PERIOD Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. lodines TOTAL FOR PER/OD Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates TOTAL FOR PER/OD 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.
i 55 '
TABLE 2-4AA (PAGE 1 OF 1)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS GROUND MODE JULY,1997 THROUGH DECEM*2R,1997 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOU3 MODE BATCH MODE
- 1. Fission Gasses QUARTER ' QUARTER QUARTER QUARTER 3
4 3
4 Xe-131m
~
Ci 0.00E+00 0.00E+00 1.29E-02 0.00E+00 Xe-133 Ci 2.19E-01 2.43E-03 7.45E-01 1.79E-02 Xe-133m Ci 0.00E+00 0.00E+00 4.84E-03 0.00E+00 Xe-135 Ci 1.30E-03 3.71 E-04 1.71 E-03 0.00E+00 TOTAL FOR PERIOD Ci 2.20E-01 2.80E-03 7.65E-01 1.79E-02
- 2. lodiras 1-131 Ci 1.33E-05 1.64E-07 1.67E-04 1.21 E-04 l-133 Ci 2.67E-07 4.20E-08 1.14E-06 0.00E+00 TOTAL FOR PER/OD Ci 1.36E-05 2.06E-07 1.68E-04 1.21 E-04
- 3. Particulates Co-58 Ci 2.41 E-09 2.31 E-09 0.00E+00 0.00E+00 Co-60 Ci 1.175-09 2.12E-09 0.00E+00 0.00E+00 Cs-134 Ci 1.35E-09 8.69E-09 0.00E+00 0.00E+00 Cs-137 Ci 1.68E-09 7.44E-09 0.00E+00 0.00E+00 1-131 Ci 9.63E-09 0.00E+00 0.00E+00 0.00E+00 Sr-89 Ci 2.86E-10 2.33E-10 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 1.65E-08 2.08E-08 0.00E+0L 0.00E+00 G-ALPHA Ci 9.50E-10 1.92E-09 0.00E+00 0.00E+00 H-3 Ci 6.05E-02 4.17E-02 0.00E+00 8.83E-03
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical miniman detectable concentrations.
56
TABLE 2-4B (PAGE 1 OF 1)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE l
JANUARY,1997 THROUGH JUNE,1997 UNIT 2 l
NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE I
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 1
2 1
2 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 3.32E-03 Kr-85m Ci 0.00E+00 0.00E+00 0.00E+00 8.85E-05 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 2.29E-05 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 1.44E-04 Xe-133 Ci 0.00E+00 0.00E+00 0.00E+00 8.32E-03 Xe-133m Ci 0.00E+00 0.00E+00 0.00E+00 1.95E-04 Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 1.87E-03 l
Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 1.80E-05
, TOTAL FOR PER/OD Ci 0.00E+00 0.00E+00 0.00E+00 1.40E-02
- 2. lodines TOTAL FOR PERIOD Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates TOTAL FOR PER/OD Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
57 -
TABLE 2-488 (PAGE 1 OF 1)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JULY,1997 THROUGH DECEMBER,1997 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 3
4 3
4 TOTAL FOR PERIOD Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. lodines TOTAL FOR PER/OD Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates TOTAL FOR PER/OD 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.
58 '
TABLE 2-4C (PAGE 1 OF 1)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS GROUND MODE JANUARY,1997 THROUGH JUNE,1997 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 1
2 1
2 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 3.32E-03 Kr-85M Ci 0.00E+00 0.00E+00 0.00E+00 8.85E-05 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 2.29E-05 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 1.44E-04 Xe-133 Ci 0.00E+00 0.00E+00 0.00E+00 8.32E-03 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 1.95E Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 1.87E-03 Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 1.80E-05 TOTAL FOR PERIOD Ci 0.00E+00 0.00E+00 0.00E+00 1.40E-02
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
59
TABLE 2-4CC (PAGE 1 OF 1)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JULY,1997 THROUGH DECEMBER,1997 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses QUARTER QUARTER QUARTER QUARTER 3
4 3
4 Xe-131m Ci 0.00E+00 0.00E+00 1.29E-02 0.00E+00 Xe-133 Ci 2.19E-01 2.43e-03 7.45e-01 1.79e-02 Xe-133m Ci 0.00E+00 0.00E+00 4.84E-03 0.00E+00 Xe-135 Ci 1.30E-03 3.71 E-04 1.71 E-03 0.00E+00 TOTAL FOR PERIOD Ci 2.20E-01 2.80E-03 7.65E-01 1.79E-02
- 2. lodines 1-131 Ci 1.33E-05 1.64E-07 1.67E-04 1.21 E-04 l-133 Ci 2.67E-07 4.20E-08 1.14E-06 0.00E-00 TOTAL FOR PER/OD Ci 1.36E-05 2.06E-07 1.68E-04 1.21 E-04
- 3. Particulates Co-58 Ci 2.41 E-09 2.31 E-09 0.00E+00 0.00E+00 Co-60 Ci 1.17E-09 2.12E-09 0.00E+00 0.00E+00 Cs-134 Ci 1.35E-09 8.69E-09 0.00E+00 0.00E+00 Cs-137 Ci 1.68E-09 7.44E-09 0.00E+00 0.00E+00 1-131 Ci 9.63E-09 0.00E+00 0.00E+00 0.00E+00 Sr-89 Ci 2.86E-10 2.33E-10 0.00E+00 0.00E+00 TOTAL FOR PERIOD Cl 1.65E-08 2.08E-08 0.00E+00 0.00E+00 G-ALPHA Ci 9.50E-10 1.92E-09 0.00E+00 0.00E+00 H-3 Ci 6.05E-02 4.17E-02 0.00E+00 8.83E-03
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
60
I TABLE 2-6A VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES JANUARY,1997 THROUGH JUNE,1997 UNIT 1 CUMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER
% OF QUARTER
% OF RADIATION UMIT 1
ODCM 2
ODCM LIMIT UMIT BETA 10.0 mrad 6.93E-04 6.93E-03 1.61E-04 1.61E-03 GAMMA 5.0 mrad 2.17E-04 4.34E-03 6.36E-05 1.27E-03 CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM UNITS YEAR TO DATE
% OF ODCM UMIT RADIATION UMIT BETA 20.0 mrad 8.54E-04 4.27E-03 GAMMA 10.0 mrad 2.80E-04 2.80E-03 l
61
l TABLE 2 6AA l
VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES JULY,1997 THROUGH DECEMBER,1997 UNIT 1 CUMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER
% OF QUARTER
% OF RADIATION UMIT 3
ODCM 4
ODCM UMIT UMIT BETA 10.0 mrad 2.37E-03 2.37E-02 1.93E-05 1.93E-04 GAMMA 5.0 mrad 8.24E-04 1.65E-02 1.04E-05 2.08E-04 l
I l
CUMULATIVE DOSES PER YEAR (YEAR TO DATE) l TYPE OF ODCM UNITS YEAR TO DATE
% OF ODCM LIMIT RADIATION UMIT BETA 20.0 mrad 3.25E-03 1.62E-02 GAMMA 10.0 mrad 1.12E-03 1.12E-02 l
l 62
i i
l TABLE 2-6B 1
VOGTLE ELECTRIC GENERATING PLANT i
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l
AIR DOSE DUE TO NOBLE GAS RELEASES JANUARY,1997 THR JUGH JUNE,1997 UNIT 2 CUMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER
% OF QUARTER
% OF RADIATION UMIT 1
ODCM 2
ODCM l
LIMIT UMIT l
BETA 10.0 mrad 3.20E-05 3.20E-04 5.36E-05 5.36E-04 l
GAMMA 5.0 mrad 1.28E-05 2.57E-04 2.50E-05 5.01E-04 l
CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM UNITS YEAR TO DATE
% OF ODCM UMIT RADIATION UMIT l
BETA 20.0 mrad 8.56E-05 4.28E-04 GAMMA 10.0 mrad 3.79E-05
- 3. 79E-04 l
63 ~
l
i TABLE 2-6BB VOGTLE ELECTRIC GENERATING PLANT l
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l
AIR DOSE DUE TO NOBLE GAS RELEASES JULY,1997 THROUGH DECEMBER,1997 UNIT 2 CUMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER
% OF QUARTER
% OF RADIATION UMIT 3
ODCM 4
ODCM UMIT UMIT BETA 10.0 mrad 3.52E-04 3.52E-03 3.99E-05 3.99E-04
, GAMMA 5.0 mrad 1.21E-04 2.41E-03 2.49E-05 4.97E-04 l
l t
I 1
l CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM UNITS YEAR TO DATE
% OF ODCM LIMIT RADIATION UMIT l
BETA 20.0 mrad 4.77E-04 2.39E-03 GAMMA 10.0 mrad 1.83E-04 1.83E-03 i
TABLE 2-TA VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l
INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM l
JANUARY,1997 THROUGH JUNE,1997 UNIT 1 l
l CUMUL.ATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER
% OF QUARTER
% OF LIMIT 1
ODCM 2
ODCM LIMIT LIMIT Bone 7.5 mrem 4.35E-08 5.79E-07 5.66E-09 7.55E-08 GILLI 7.5 mrem 8.81 E-05 1.17E-03 2.11 E-04 2.81 E-03 Kidney 7.5 mrom 8.81 E-05 1.17E-03 2.11 E-04 2.81 E-03 l
Liver 7.5 mrom 8.81 E-05 1.17E-03 2.11 E-04 2.81 E-03 Lung 7.5 mrom 8.81 E-05 1.17E-03 2.11 E-04 2.81 E-03 i
T. Body 7.5 mrom 8.81 E-05 1.17E-03 2.11 E-04 2.81 E-03 Thyroid 7.5 mrom 8.88E-05 1.18E-03 2.12E-04 2.83E-03 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE
% of ODCM LIMIT LIMIT Bone 15.0 mrom 4.91 E-08 3.27E-07 GI-LLI 15.0 mrom 2.99E-04 1.99E-03 Kidney 15.0 mrom 2.99E-04 1.99E-03 Liver 15.0 mrom 2.99E-04 1.99E-03 Lung 15.0 mrom 2.99E-04 1.99E-03 T. Body 15.0 mrom 2.99E-04 1.99E-03 Thyroid 15.0 mrom 3.01 E-04 2.01 E-03 65
(
l l
TABLE 2-7AA VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JULY,1997 THROUGH DECEMBER,1997 UNIT 1 l
l CUMULATIVE DOSE PER QUARTER ORGAN ODCM J
UNITS QUARTER
% OF QUARTER
% OF LIMIT 1
ODCM 4
ODCM LIMIT LIMIT Bone 7.5 mrem 2.87E-06 3.82E-05 2.82E-06 3.76E-05 j
l GI-LLI 7.5 mrem 8.58E-05 1.14E-03 2.01 E-04 2.68E-03 i
Kidney 7.5 mrem 8.92E-05 1.19E-03 2.02E-04 2.70E-03 Liver 7.5 mrem 8.82E-05 1.18E-03 2.03E-04 2.71 E-03 l
Lung 7.5 mrem 8.57E-05 1.14E-03 2.01 E-04 2.68E-03 l
T. Body 7.5 mrem 8.69E-05 1.16E-03 2.02E-04 2.69E-03 Thyroid 7.5 mrem 7.77E-04 1.04E-02 2.94E-04 3.93E-03 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE
% of ODCM i
LIMIT LIMIT Bone 15.0 mrem 5.74E-06 3.83E-05 GI-LLI 15.0 mrem 5.86E-04 3.90E-03 Kidney 15.0 mrem 5.90E-04 3.93E-03 Liver 15.0 mrem 5.90E-04 3.94E-03 Lung 15.0 mrem 5.86E-04 3.90E-03 l
T. Body 15.0 mrem 5.87E-04 3.91 E-03 l
Thyroid 15.0 mrem 1.37E-03 9.15E-03 y
l i
1 i
I i
TABLE 2-7B VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JANUARY,1997 THROUGH JUNE,1997 UNIT 2 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER
% OF QUARTER
% OF LIMIT 1
ODCM 2
ODCM J
LIMIT LIMIT l
Bone 7.5 mrem 2.56E-07 3.41E 86 2.04E-08 2.72E-07 GI-LLI 7.5 mrem 4.51 E-05 6.01 E-04 4.12E-05 5.50E-04 j
Kidney 7.5 mrern 4.51 E-05 6.01 E-04 4.12E-05 5.50E-04 Liver 7.5 mrem 4.51 E-05 6.01 E-04 4.12E-05 5.50E-04 j
Lung 7.5 mrem 4.51 E-05 6.01 E-04 4.12E-05 5.50E-04 T. Body 7.5 mrom 4.51 E-05 6.01 E-04 4.12E-05 5.50E-04 Thyroid 7.5 mrom 4.61 E-05 6.14E-04 4.16E-05 5.55E-04 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE
% of ODCM LIMIT LIMIT Bone 15.0 mrem 2.76E-07 1.84E-06 GI-LLI 15.0 mrem 8.63E-05 5.75E-04 Kidney 15.0 mrem 8.63E-05 5.75E-04 Liver 15.0 mrem 8.63E-05 5.75E-04 I
Lung 15.0 mrem 8.63E-05 5.75E-04
)
T. Body 15.0 mrom 8.63E-05 5.75E-04 l
Thyroid 15.0 l
mrom 8.77E-05 5.85E-04 i
l 67
TABLE 2-7BB VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JULY,1997 THROUGH DECEMBER,1997 UNIT 2 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER
% OF QUARTER
% OF LIMIT 3
ODCM 4
ODCM LIMIT LIMIT Bone 7.5 mrem 3.10E-07 4.14E-06 1.46E-07 1.95E-06 GI-LLI 7.5 mrem 2.26E-05 3.01 E-04 2.23E-05 2.97E-04 Kidney 7.5 mrom 2.26E-05 3.01 E-04 2.23E-05 2.97E-04 Liver 7.5 mrom 2.26E-05 3.01 E-04 2.23E-05 2.97E-04 Lung 7.5 mrom 2.26E-05 3.01 E-04 2.22E-05 2.96E-04 T. Body 7.5 mrom 2.26E-05 3.01 E-04 2.23E-05 2.97E-04 Thyroid 7.5 mrom 2.56E-05 3.42E-04 3.93E-05 5.24E-04 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE
% of ODCM LIMIT LIMIT Bone 15.0 mrom 7.32E-07 4.88E-06 GI-LLI 15.0 mrom 1.31 E-04 8.75E-04 Kidney 15.0 mrom 1.31 E-04 8.75E-04 Liver 15.0 mrom 1.31 E-04 8.75E-04 Lung 15.0 mrom 1.31 E-04 8.75E-04 T. Body 15.0 mrem 1.31 E-04 8.75E-04 Thyroid 15.0 mrom 1.53E-04 1.02E-03 68
i TABLE 2-8 l
MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANALYSES l
VOGTLE ELECTRIC GENERATING PLANT JANUARY,1997 THROUGH DECEMBER,1997 l
The values in this table represent a priori Minimum Detectable Concentration (MDC) which are l
typically achieved in laboratory analyses of gaseous radwaste samples.
l RADIONUCLIDE MDC UNITS Kr-87 1.82E-08 CVcc Kr-88 2.53E-08 CVcc Xe-133 2.05E-08 CVcc Xe-133m 8.63E-08 CVcc l
Xe-135 7.12E-08 pCVcc l
Xe-138 1.05E-07 CVcc l
I-131 7.93E-15*
pCVcc Mn-54 3.94E-14
- CVcc l
Fe-59 2.45E-14
- CVcc i
Co-58 1.39E-14
- pCVcc l
Co-60 1.75E-14
- CVcc l
Zn-65 2.82E-14
- CVcc Mo-99 9.57E-14
- CVcc Cs-134 1.12E-14
- CVcc Cs-137
- 8. 71E-15*
CVcc Ce-141 8.62E-15*
CVcc Ce-144 2.77E-14
- nCVcc Sr-89 1.00E-13 CVcc Sr-90 1.00E-13 CVcc H-3 9.00E-06 CVcc Gross Alpha 1.00E-13 CVcc Based on an estimated sample volume of 5.7E+08 cc.
69
3.0 Solid Waste 3.1 Regulatory Limits /ODCM The ODCM Limits presented in this section are stated in part for Unit 1 and Unit 2.
3.1.1 Use of Solid Radioactive Waste System 10.2.1 Process Control Program Radioactive wastes shall be solidified or dewatered in accordance with the Process Control Program to meet shipping and transportation requirements during transit and disposal site requirements when received at the disposal site.
3.1.2 Reporting Requirements 12.1 (PCP) states in part:
The Annual Radioactive Effluent Release Report, submitted in accordance with Technical Specifications 5.6.3, shall include a summary of the quantitics of solid radwaste released from the units, as outlined in Regulatory Guide 1.21.
3.2 Solid Waste Data Regulatory Guide 1.21, Table 3 is found in this report as Table 3-1.
4.0 The Vogtle Electric Generating Plant Offsite Dose Calculation Manual (ODCM) 4.1 Changes to the Vogtle Electric Generating Plant ODCM 7.2.2.5 of ODCM There were changes to the Vogtle Electric Generating Plant ODCM for the period January 1,1997 through December 31,1997. These changes are being submitted with The Annual Radioactive Effluent Release Report in the form of a complete legible copy of the entire ODCM in accordance with Technical Specification 5.5.1.c 70
4.2 The Radiological Environmental Monitoring Program 4.0 of ODCM l
l The Radiological Environmental Monitoring Program (REMP) shall be conducted as i
specified in Table 4-1, 1
Section 4.1.1.2.3 states in part:
l If adequate samples of milk, or during the growing season, grass l
or leafy vegetation, can no longer be obtained from one or more of the sample j
locations required by, or if the availability is frequently or persistently wanting, efforts shall be made: to identify specific locations for obtaining suitable replacement samples; and to add any replacement locations to the REMP given in the ODCM within 30 days.
Pursuant to Technical Specification 5.5.1, documentation shall be submitted in the next l
Radioactive Effluent Release Report for the change (s) in the ODCM, including revised figure (s) and table (s) reflecting the changes to the location (s), with supporting information identifying the cause of the unavailability of samples and justifying the selection of any new location (s).
4.1.2 of ODCM states in part:
"A Land Use Census shall be conducted....."
The Action Statement for this requirement states in part:
a.
" With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than values currently being calculated in accordance with i
Section 3.4.3, identify the new location (s) in the next Radioactive Effluent Release Report ".
l 4.3 Changes in the Radiological Environmental Monitoring Program
- For this reporting period, there have been no changes to the Radiological Environmental Monitoring Program.
I 5.0 Doses to Members of the Public inside the Site Boundary 7.2.2.3 states in part:
"The report shall also include assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the 71
l SITE BOUNDARY during the report period; this assessment must be performed in accordance with Chapter 6. All assumptions used in making these assessments ( l.e.,
I specific activity, exposure time, and location) shall be included in the report" The locations of concern within the site boundary is the Visitors Center. The activities at the Visitor Center consist of occasional attendance at meetings and/or short visits for informational purposes.
There will be no radiation dose at this location due to radioactive liquid effluents.
Delineated in Table 4-1 for this ' ; cation are the values of the basic data assumed in the dose assessment due to radi active 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, 2-38, and 2-388 for the mixed mode releases. Similarly, it is listed in Tables 2-4A, 2-4AA,2-48, and 2-48B for the ground level releases. The tritium releases in units of curies were as follows:
QUARTER 1
2 3
4 Mixed Mode 2.07E+01 3.92E+01 1.66E+01 2.88E+01 Ground Mode 0.00E+00 0.00E+00 6.05E-02 5.05E-02 The maximum doses in units of mrem to an individual MEMBER OF THE PUBLIC due to their activities inside the site boundary during the reporting period were assessed to be as follows:
VISITOR CENTER Quader 1 and 2 Quader 3 and 4 Total Body 1.94E-07 5.93E-07 l
(Direct Radiation from Plume) l l
VISITOR CENTEl?
Quader 1 Quader 2 Quader 3 Quader 4 Maximum Organ 3.69E-07 4.86E-07 1.27E-06 5.95E-07 (Thyroid) j (Inhalation Ground Plane) j l
^
72 J
Table 3-1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1997)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY 1,1997 THROUGH JUNE 30,1997 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)
- 1. Type of waste Unit 6-month Est. Total Period Error. %
- a. Spent resin, filter sludges, evaporator bottoms, m'
NONE NONE etc.
Ci NONE
- b. Dry compressible waste, contaminated m*
1.001E+01 equipment Cl 6 248E-01
- 4. 0E+ 1
- c. Irradiated components, control rods, etc.
m*
Cl NONE NONE
- d. Other(Desenbe) m' Ci NONE NONE
- 2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (by type of waste),
- s. NONE SHIPPED N/A
- c. None Shipped N/A
- d. None Shipped N/A
- 3. Solid Waste Disposition Number of Mode of Transportation Destination Shioments 7
Tractor / Trailer Scientific Ecology Group, Oak Ridge TN.
8 Tractor / Trailer American Ecology Recycle Center, Oak Ridge TN.
B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination NONE NONE NONE f
73 -
t i
Table 31 (continued)
ADDITIONAL INFORMATION REQUIRED BY ODCM:
Shiornent No Waste Class Tvos Container Shlopino Class Golidification Aaent RVRS-97-001 A - UNSTABLE Strong Tight
< D.O.T.
NONE RVRS-97-002 A - UNSTABLE Strong Tight
<D.O.T.
NONE l
RVRS-97-003 A - UNSTABLE Strong Tight
< D.O.T.
NONE-RVRS-97-004 A - UNSTABLE Strong Tight
<D. O.T.
NONE RVRS-97-005 A - UNSTABLE Strong Tight
< D. O.T.
NONE RVRS-97-006 A - UNSTABLE Strong Tight
<D.O.T.
NONE RVRS-97-007 A - UNSTABLE Strong Tight LSA NONE RVRS-97-008 A - UNSTABLE Strong Tight LSA NONE RVRS-97-009 A - UNSTABLE Strong Tight LSA NONE RVRS-97-010 A - UNSTABLE Strong Tight
<D.O.T.
NONE RVRS-97-011 A - UNSTABLE Strong Tight LSA NONE RVRS~C7-012 A - UNSTABLE Strong Tight LQ NONE RVRS-97-013 A-UNSTABLE Strong Tight
<D.O.T.
NONE RVRS-97-014 A - UNSTABLE Strong Tight
<D.O.T, NONE RVRS-97-015 A - UNSTABLE Strong Tight LSA NONE 74
Table 3-1 (continued)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
SOLIO WASTE AND IRRADIATED FUEL SHIPMENTS JULY 1,1997 THROUGH DECEMBER 31,1997.
A SOLID < ASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fue,'
- 1. Type of weste Unit 6-month Est. Total Period Error. %
- a. Spent resin, filter sludges, evaporator bottoms, m'
6.949E+00 etc.
Cl 9.987E+01 1.0E+1
- b. Dry compressible waste. contaminated m'
8.320E+00 eouipment Cl 6.183E+00 4 OE+1
- c. Irradiated components, control rods, etc.
m' 7.419E-01 Cl 9 640E+01
- 1. 0E+ 1
- d. Other(Desenbe) r l' Cl NONE NONE
- 2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (by type of weste).
- a. Cs-137 3.639E+00 Co40 1.906E+01 N643 3.571E+01 All others 4158E+01 r Mn-54 4.121E+00 Fe 59 1.740E-01 Ni43 9.365E+00 All others 8.634E+01
- d. N/A N/A
- 3. Solid Waste Disposition Number of Mode of Transoortation Destination Shioments i
3 Tractor / Trailer / Shielded Cask Chem-Nuclear Systems, Inc. Barnwell, S.C.
6 Tractor / Trailer Scientific Ecology Group, Oak Ridge TN.
5 Tractor / Trailer American Ecology, Oak Ridge TN.
B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination j
NONE NONE NONE 1
1 75
Table 3-1 (continued)
ADDITIONAL INFORMATION REQUIRED BY ODCM:
Shloment No Waste Class Tvoe Container Shiocina Class Solidification Aaent RWS-97-001 A - STABLE TYPE A LSA NONE USED RWS-97-002 8 - STABLE TYPE A LSA NONE USED RWS-97-003 8 - UNSTABLE TYPEO YELLOW - 11 NONE USED RVRS-97 016 A - UNSTABLE Strong Tight LSA NONE USED RVRS-97-017 A - UNSTABLE Strong Tight LSA NONE USED RVRS-97418 A - UNSTABLE Strong Tight
<D.O.T.
NONE USED RVRS-97-019 A - UNSTABLE Strong Tight
<D.O.T.
NONE USED RVRS-97-020 A - UNSTABLE Strong Tight LSA NONE USED RVRS-97-021 A - UNSTABLE Strong Tight LSA NONE USED RVRS-97-022 A - UNSTABLE Strong Tight LSA NONE USED RVRS-97-023 A - UNSTABLE Strong Tight
<D.O.T.
NONE USED RVRS-97-024 A - UNSTABLE Strong Tight
< D.O.T.
NONE USED RVRS-97-025 A - UNSTABLE Strong Tight
<D.O.T.
NONE USED RVRS-97-026 A - UNSTABLE Strong Tight LSA NONE USED 76 '
l l
Table 41 Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1997 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY l
Starting: 014an-1997 Ending: 31-Dec-1997 i
Location Name Visitor Center i
Distance (meters) 4.47e+02 Sector SE i
X/Q(sec/m3)
(1) 5.93E-06
)
Depleted X/Q(sec/m3)
(2) 5.58E-06 D/Q(m2)
(1) 2.28E-08 l
X/Q(Sec/m3)
(2) 7.12E-07 Depleted X/Q(sec/m3)
(2) 6.74E-07 D/Q(m2)
(2) 5.77E-09 Occupancy Factor 0.00046(4hr/yr)
Age Group Child l
VISITOR CENTER UNITS QTR 1 QTR2 Total Q1 &
QTR3 QTR4 Total Q3 &
Q2 Q4 l
Total Body mrom 1.39E-07 5.50E-08 1.94e-07 5.70E-07 2.28E-08 5.93E-07 Dose
_ Organ done mrom 1.41E-07 5.42E-08 1.95e-07 5.78E 07 3.56E-08 6.14E-07 liver mrom 3.68E-07 4.85E-07 8.52E 07 7.66E 07 4.19E 07 1.18E-06 Tbody mrem 3.68E-07 4.85E-07 8.52E-07 7.65E 07 4.19E-07 1.18E 06 l
Thyroid mrem 3.69E-07 4.86E 07 8.55E-07 1.27E 06 5.95E-07 1.86E 06 l-Kidney mrem 3.68E 07 4.85E-07 8.52E-07 7.67E-07 4.19E 07 1.19E 06 Lung mrem 3.68E-07 4.85E-07 8.52E-07 7.64E-07 4.18E-07 1.18E-06 GI-LLI mrem 3.68E-07 4.85E-07 8.52E-07 7.64E-07 4.18E-07 1.18E 06 l
l 77 -
6.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems ODCM 7.2.2.7 states in part:
{
l As required by Sections 2.1.5 and 3.1.6, licensee initiated MAJOR CHANGES TO RADIOACTIVE WASTE Tr.EATMENT SYSTEMS (liquid and gaseous) shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report covering the period in which the change was reviewed and accepted for implementation.
]
Note 1: In lieu of inclusion in the Radioactive Effluents Release Report, this same
{
information may be submitted as part of the annual FSAR update.
Gaseous Radwaste System There were no major changes to the gaseous radwaste system in 1997.
Liquid Radwaste System There were no major changes to the Liquid Radwaste Treatment System in 1997.
PCP 12.1 states in part:
q Licensee major initiated changes to the solid radioactive waste treatment system shall be reported to the Nuclear Regulatory Commission in the Annual Radioactive Effluent Release Report for the period in which the change was implemented.
Solid Radwaste System There were no major changes to the solid radwaste system in 1997.
7.0 Meteorological Data ODCM 7.2.2.2 states in part:
The Radioactive Effluent Release Report 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 of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape; or in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.
In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
78
- 8.0 Program Deviations ODCM 7.2.2.6 states in part that:
l 8.1 Inoperable Liquid or Gaseous Effluent Monitoring instrumentation The report shall include deviations from the liquid and gaseous effluent monitoring i
instrumentation operability requirements included in Sections 2.1.1 and 3.1.1, respectively. The report shall include an explanation as to why the inoperability of liquid l
or gaseous effluent monitoring instrumentation was not corrected within the specified time requirement.
l The inoperability of liquid and gaseous effluent monitors was corrected within the specified time for this reporting period.
3.2 Tanks Exceeding Curie Content Limits The report shall include a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specifications 5.5.12.
There were no outdoor liquid hold up tanks used for radioactive liquids during this reporting period. Limits for the gas storage tanks were not exceeded during this reporting period.
l i
79
/