ELV-00840, Semiannual Rept Plant Radioactive Effluent Releases Jan-June 1989
| ML20246J603 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/30/1989 |
| From: | Hairston W GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ELV-00840, ELV-840, NUDOCS 8909050217 | |
| Download: ML20246J603 (145) | |
Text
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- Georga Powr Corrcany 333 Piedmo*d Avow i'
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sp.n o W. G. Hairstors til Sesot V:ce Neudent Naaea, operas ELV-00840 August 24, 1989 Docket Nos. 50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C.
20555 1
Gentlemen:
V0GTLE ELECTRIC GENERATING PLANT SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT In accordance with the requirements of the Vogtle Electric Generating Plant Unit 1 and Unit 2 Technical Specification 6.8.1.4, please find enclosed the Semi-Annual Radioactive Effluent Release Report for January 1,1989 through June 30,1989. Six copies are provided for your use. Two copies of this report are being provided to the NRC Region II office.
Sincerely, id
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W. G. Hairston, III 4
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Enclosure xc (see next page) 1 l
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e909050217 890630 ADOCK 0500 4
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Georgia Powerd H
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U. S. Nuclear Regulatory Commission ELV-00840 Page 2-xc: Georgia Power Company Mr. C. K. McCoy Mr. G. Bockhold, Jr.
Mr. R. M. Odom Mr. W. R. Woodall, Jr.
Mr. P. D. Rushton NORMS Southern Company Services Mr. J. L. Leamon U. S. Nuclear Regulatory Commission
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Mr. S. D. Ebneter, Regional Administrator Mr. J. B. Hopkins, Licensing Project Manager, NRR Mr. J. F. Rogge, Senior Resident Inspector, Yogtle State of Georgia Mr. J. Setser, DNR Americal Nuclear Insurers Mr. L. Cross E. I.'DuPont'beNemours & Co., Inc (SRS)
Mr. W. G. Winn
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l GEORGIA POWER COMPANY
' NUCLEAR PLANT V0GTLE UNIT 1 & UNIT 2 SEMIAGNIJ AL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES January 1, 1989 to June 30, 1989
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.i DISTRIBUTION OF SEMIANNUAL REPORT
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SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT LOCAL' DISTRIBUTION:
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'G.
Bockhold, Jr.
General Manager Vogtle Nuclear Operations 2.
W.
F.
Kitchens Assistant General Manager 3.
R.
L.
LeGrand Manager.HF* Chemistry 4.
D..F.
Hallman Superintendent of Nuclear Chemistry 5.
J.
B Sills Laboratory Supervisor 6.
R.
C.
Hand Chemistry Supervisor 7.
S.
Sundaram Senior Plant Chemist 8.
Document Control File at least one copy in records 9.
SRS 1412A l
b V0GTLE ELECTRIC GENERATING PLANT SEMIAN1;UAL REPO.RT PLANT ~ RADIOACTIVE EFFLUENT RELEASES l
SECTION TITLE PAGE 1.0
. Liquid Effluents 6
l I-1.1 -
Reguletory Limits /Technica?. Specifications 6
1.1.1 Effluent Radiation Monitoring Syctem 6
1.1.2 Concentration Limits 6
1.1.3 Dose Limits 6
1.1.4 Liquid Prccessing 7
1.1.5 Outside temporary Tanks 7
1.1.6 Reporting of Semiannual Releases (Unplanned) 7 1.2 11aximum Permissble Concentrations 11 1.3 Measurements and Approximations ~ of Total 11 Radioactivity 1.4 Liquid Effluent Release Data 13 1.4.1 Methodology 13 1.4.2 Batch Release Data 15 1
1.5 Radiological Impset on Man Due to Liquid
.15 Release 1.6 Abnormal Releases 15 1.7 River Flow 16 2.0 Gaseoue Effluents 30 2.1 Regulatory Limits / Technical Specifications 30 2.1.1 Process Effluent Monitoring System 30 2.1.2 Dose Rate Limit 30 2.1.3 Air Dose Due to Noble Gas 30 2.1.4 Dose to Any Organ 31 2.1.5 Ventilation Exhaust Treatment System and 31 Gaseous Waste Processing System
p.
..,E E C TI O N TITLE PAGE 2.'1.6 Explosive Gas Mixture 32
'2.1.7 Activity In Gas Decay Tanks 32 2.1.8 Total Fuel Cycle Dose Commitment 32 2.1.9
. Reporting"of Semiannual. Releases (Unplanned) 33 2.2 Release Points-38 2 :. 3 Sample Collection and Analysie 36-l 2.4.
determination of Total-Quantities of 39
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Radioactivity, Dose Rates and Cumulative Doses 2.4.1 Fission and Activation Gas 46 2.4.2 R a dirsa c ti vi t y, Tritium and Particulate 40 Released 2.4.3 Gross Alpha Release 41 2.5 Gaseous Effluent Release Data 41 2.5.1 Methodology 42 2.5.2 Gaseous Batch Data 43 2.6 Radiological Impact Due to Gaseous Relea'ses 44 3.0 So?.id Wacte 66 3.1 Regulatory Limits / Technical Specifications 66 3.1.1 Use of Solid Radioactive Waste System 66 3.1.3 Reporting Requirements 66 3.1.3 Changes to the PCP 66 3.2 Solid Waste Data 67 4.0 Changes to the Vogtle Electric 70 Generating Plant ODCM the Radiolcd cal Environmental 72 i
4.1 Changes in Monitoring Program 5.0 Doses to Members of the Public Inside 72 The Site Boundary w__
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ll PAGE TITLE S EC TIOh,.
6.0 Major Changes to che. Liquid, Gascous and Solid Radwaste Treatment Systems 75 7.0 Meteorology (TO BE INCLUDED.FOR THE REPORT DATED JANUARY 1, 1989).
76 j.
Inoperable Liquid or Gaseous Effluent 8.0 77 Monitoring Instrumentation 9.0 Tanks Exceeding Curie Content Limits 79 1
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4-V0GTLE ELECTRIC GENERATING PLANT l
SEMIANNUAL REPORT RADIOACTIVE EFFLUENT' RELEASE REPORT LIST OF TABLES PAGE LIST OF' TABLES TABLE Technical Specification Table 3.3-9 1-1 Radioactive Liquid Effluent Monitoring 8
' Instrumentation Liquid Effluents - Summation of All Releases 1-2a 17 Unit 1 Liquid Effluents - Summation of All Releases 1-2b 18 Unit 2 Liquid Effluents - Summation of All Releases 1-2c 19 Site 20 1-3a Liquid Effluents - Unit 1 1-3b Liquid Effluents - Unit 2 21 22 1-3c Liquid Effluents - Site 1-4a Individuals Doses Due to Liquid Releases 23 Unit 1 individuals Doses Due to Liquid Releases 1-4b 24 Unit 2 1-5 Lower Limits of Detection - Liquid Sample 25 Istalysis Batch Release Summary of All Releasec -
1-6a 28 Unit 1 Batch Release Summary of All Releases -
1-6b 29 Unit 2 Technical Specification Table 3.3.10 2-1 Radioactive Gaseous Effluent Monitoring 34 Instrumentation 2-2a Gaseous Effluents - Sumeation of All Releases 45 Unit 1
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y TABLE LIST OF TABLES PAGE 2-2b
-Gaseous Effluents - Summation of All Releases Unit 2 46 2-2c Gaseous Effluents - Summation of All Releases Site 47 2-3a' Gaseous Effluents - Mixed Mode Releases Unit 1 48 2-3b Gaseous Effluents - Mixed Mode Releases Unit 2 50 2-3c Gaseous Effluents - Mixed Mode Releases 52 2-4a Gaseous Effluents - Ground Level' Release - Unit 1 54 2-4b Gaseous Eff1 cents - Ground Level Release - Unit 2 56 2-4c Gaseous. Effluents - Ground Level Releases 58 2-5' Gaseous Effluents - Dose Rates Site 60 2-6a Air Doses Due to Noble Gases Unit 1 61 2-6b Air Poses Due to Noble Gases Unit 2 62 2-7a Individual Doses Due to Radioiodine, Tritium, and Particulate in Gaseous
-Releases - Unit 1 63 2-7b Individual Doses Due to Radiolodine, Tritium, and Particulate in Gaseous Releases - Unit 2 64 2-8 Lower Limits of Detection - Gaseous Sample Analyses 65 3-1 Solid Waste and Irradiated Fuel Sbipments 68 5-1 Basic Data Assumed in Dose Assessments to Members of the Public 74
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1.0 Liquid' Effluents 1.1 Regulatory Limits / Technical Specifications The Technical Specifications (T/S) presented in this subsection are for the site.
1.1.1 Effluent Radiation Monitoring System The radioactive liquid effluent monitoring instrumentation channels shown in T/S Table 3.3-9 shall be OPERABLE with-their Alarm / Trip Setpoints set to' ensure that the limit s of Specification 3.11.1.1 are 'not exceeded.
The ALARM / TRIP Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFF-SITE DOSE CALCULATION MANUAL (ODCM).
Technical Specification Table 3.3-9 is included in this subsection as Table 1-1.
1.1.2 Concentration Limits 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (See Figure 5.1-1 and 5.1-2) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B,
Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble
- gases, the concentration shall be limited to 2.0E-4 microcurie /ml total activity.
1.1.3 Dose Limits 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents
- released, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-1 and 5.1-2), shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrees to any organ, and b.
During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.
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4 1.' 1. 4 Liquid Processing 3.11.1.3 The Liquid Radwaste Treatment System shall be operable and 1
appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unic, to UNRESTRICTED AREAS (See Figure 5.1-1 and 5.1-2) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.
-l 1.1.5 Outside Temporary Tanks 3.11.1.4 i
The quantity of radioactive material contained in each outside temporary tank shdil'te limited to less than or equal cc 10 Curies, excluding tritium and dissolved or entrain 6d noble gaaas.
1.1.6 Report. Arg of Semiannual Releases (Unplanned) 6.8.1.4 states in part:
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The Semiannual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reperting i
period.
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i TABLE 1-1 (FROM TECHNICAL $ SPECIFICATIONS)
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(TABLE 3. 3-' 9 )
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,R,ADIDACTIVE LIQUID ' EFF LUENT MONITORING. INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE
' ACTION-1.
Radioactivity Monitors Providing Alarm and Automatic Termination of Release a.
Liquid Radweste Effluent Line 1
37 (RE-0018) b.
Steam Generator Blowdown Effluent 1
38 Line (RE-0021) c.
Turbine Bldg. (Floor Draias) Sumps 1
38 Effluent Line (RE-0848) 2.-
Radioactivity Monitors Providing Alarm EBut Not-Providing Automatic Termination of Aelease-a.
Nuclear Service Cooling Water 1
39 System Effluent Line (RE-0020A & B) 3.
Flow Rate Measurement Devices a.
Liquid Radwaste Effluent Line 1
40 (FT-0018) b.
Steam Generator Blowdown 1
40 Efficent Line (FT-0021) c.
Flow to Blowdown Sump 1
40 (AFQI-7620, FR-7620, pen 1)
(common) 8
1 TABLE 1-1 (CONTINUED) l ACTION STATEMENTS
' ACTION 37 With the number of channels OPERABLE less than L'
required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that. prior to initiating a release:
o a.
At least' too independent samples are analyzed in accordance with Specification 4.11.1.1.1, and b.
At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.
Otherwise, suspend release of radioactivity effluents vis this pathway.
ACTION 38 With the number of channels OPERABLE less than required by the Minimum Channela OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for radioactivity at a lower limit of detection of no ~ more than 1E-07 microcurie /ml:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than l-0.01 microcurie / gram DOSE EQUIVALENT I-131, or b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-131.
ACTION 39 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue L
provided
- that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, ' grab samples are collected and analyzed for radioactivity L
at a lower limit of detection of no more than 1E-07 microcurie /ml.
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' ACTION'40-
. With the number of channels OPERABLE less than required by ' the Minimum Channel OPERABLE requirement, effluent ' releases
.via
'this pathway-may continue provided the flow rate is estimated ' at least ' once per 4
hours.during actual releases.
Pump performance curves generated',in place may be used to estimate flow.
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U t1.2 Maximum' Permissible Concentration 1
l MPC ' values used in determining allowable liquid radwaste re. lease rates and concentrations for principal gamma emitters, I-133,
- tritium, Sr-89, Sr-90, and Fe-55 are taken from 10 CFR Part 20, Appendix B, Tcble II, Column 2.
For dissolved or entrained noble gases in liquid radwaste, the MPC.is obtained from Technical Specifications 3.11.1.1 as 2.0E-04 uci/ml.
For gross alpha in liquid radwaste, the MPC'is obtained from 10 CFR Part 20, Appendix B, Note 2.d as 3.0E-08 uCi/ml.
- Further, for all the above radionuclides or categories of radioactivity, the overall MPC fraction is determined in accordance with 10 CFR Part 20, Appendix B, Note 1.
The' method wheceby the MPC fraction is used to determine release rates and liquid radwaste effluent radiation moniter setpoints is described in Subrection 1.4 of this report.
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1.3 Measurements and Approximations of Total Radioactivity Prior to release of any tank containing liquid radwaste, and following the required recirculations, samples are collected and analyzed in accordance with Technical Specification Table 4.11.
A sample from each tank planned for release is analyzed for principal gamma emitters, I-131, and diesolved and entrained noble gases by gamma spectrometry.
Monthly and quarterly camposites are prepared for analysis by extracting aliquots from each sample taken from tanks which are released.
Liquid radwaste sample analyses are performed as follows:
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MEASUREMENT FREQUENCY METHOD 1.
Gamma Isotopic Each Batch Gamma Spectroscopy with computerized cata reduction l
2.
Dissolved or entrained Each batch Gamma Spectroscopy l
noble gases with computerized j
data reduction 3.
Tritium Monthly Distillation and Composite liquid scintillation
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counting 4.
Gross Alpha Monthly Gas flow proportional j
Composite counting i
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MEASUREMENT FREQUENCY METHOD 15.
Sr-89 and Sr-90 Quarterly Cnemical separation Composite and gas-flow proportional or scintillation counting 6.
Fe-55 Quarterly Chemical separation Composite and liquid scintillation countf.ng Gamma-isotopic measurements are performed in-house in the radiochemistry lah using germanium spectrometry.
This consists of four high purity germanium detectors with resolution of 1.,80 kev or lower.
The detectors are shielded. by four inches of lead.
A liquid
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radwaste sample is poured into a graduated cylinder to measure out one liter of sample which is then poured into a bottle or into a 1 liter marinelli in preparation for a 2000-9000 second count.
A peak search of the resulting ' gamma ray spectrum is performed by the computer system.
Energy.and net count data of all significant peaks are determined, and a
quantitative reduction or MDA calculation is performed.
The procedure ensures that the LLD's are met for the nuclides specified in Table Notation 3 of Technical Specification Table 4.11-1:
M n-5 4, Fe.59, Co-58, Co-60, Z r, - 6 5, Ho-99, Cs-134, Gs-137, Ce-141 And Ce-144.
The quantitative calculations, corrections
- time, decay
- time, sample
- volume, sample
- geometry, for counting.
detector efficiency, baseline
- counts, branching
- ratio, and MDA calculations, are made based on the counts at the location on the spectrum where the peak for that radionuclides would be located, if presert.
- Tritium, Gross Alpha, Sr-99, Sr-90 and Fe-55 are, in some cases, performed off-site rather than in-house to more efficiently use plant technicians.
The radionuclides concentrations determined by gamma spectroscopic analysis of a sample taken from a tank planned for release and the most current sample analysis results evailable for tritium, gross
- alpha, Sr-89, Sr-90 and Fe-55 are used along with the corresponding MPC values to determine a MPC fraction for the tank planned for release.
This MPC fraction is then used, with appropriate safety
- factors, along with the minimum assured dilution stream flow to calculate maximum permissible release rate and a
liquid effluent monitor setpoint.
The monitor setpeint is calculated to assure that the limits of Technical Specification 3.11.1.1 are not exceeded.
A monitor reading in excess of the calculated setpoint results in an autocatic 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 ficw rate used in the setpoint calculations and established as a setpoint on the dilution stream flow monitor.
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Radionuclides-concentrations,
~$fety
- factors, dilution stream flow rate, and liquid effluent radiation monitor calibrations are entered into the computer and a prerelease printout is generated.
If the release is not permissible, appropriate warnings will be included on the computer screen.
If the release is permissible, it is approved by the Chemistry Foreman on duty and sent to the Operations Department
,for approval and processing.
When the release is completed, the necessary data from the release (ex.,
release volume) is transferred from the Operations Department to the Chemistry Department.
These data are input to the computer and a
post-release printout is generated.
The post-release printout contains actual release rates, actual release concentrations and quantities, actual dilution flow, and calculated doses to an individual.
1.4 Liquid Effluent Release Data Regulatory Guide 1.21 Tables 2A and 2B are found in this report as Table 1-2a and Table 1-3a for Unit 1.
It should be noted that the report covers the period from January 1,
1989 to June 30, 1989.
Unit 2 data is on Tables 1-2b and 1-3b and covers the periof trom February 5, 1989 to June 30, 1989.
1.4.1 Methodology The values for the four i:at eg o rie s of Table 1-2a and 1-2b are calculated and are completed as follows:
1.4.1.1 Fission and activation products The total release values (not including tritium, gases, and alpha) are comprised of the sum of the measured individual radionuclides activities.
This sum is for each batch released to the river for the respective quarter.
1.4.1.2 Tritium The measured tritium concentrations in the monthly composite samples are used to calculate the total release and average diluted concentration during each period.
1.4.1.3 Dissolved and ent. rained gases Concentrations of dissolved and entrained gasee in liquid effluents are measured by germanium spectroscopy on each one liter sample for each liquid rudwaste batch.
Radioisotopes of iodine in any form are also determined during the isotopic anclysis for each batch; therefore, a separate analysis for possible gaseous forma ia not performed because it would not provide additional information.
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1.4.1.4 Gross alpha radioactivity The measured gross alpha concentrations in the monthly composite samples are used to calculate the total release of alpha radioactivity, 1.4.1.5 Total Error Measurement The total or maximum error associated with the. ef fluent me:curement 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 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.
Estimated errors are based on errors in counting equipment calibration, counting statistics, dilution flow
- rates, sample and tank flow rates.
i 1.4.1.5.1 Fission and activation total release was calculated from sample analysis results and release point flow rates.
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Sampling and statistical error 10%
l Counting Equipment Calibration 10%
Tank Discharge Flow Rate Volumes 20%
l TOTAL ERROR 40%
l 1.4.1.5.2 Total tritium release was calculated from sample analysis results a nd release point volumes.
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Tank volumes or system flow rate 20%
Sampling and statistical errors 10%
l Counting equipment calibration 10%
TOTAL ERROR 40%
1.4.1.5.3 Dissolved and entrained gases were calculated from sample analysis results and release point volumes.
Tank or system flow rate, volume 20%
l Sampling and statistical error 20%
Counting equipment calibration 10%
TOTAL ERROR 50%
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1.4.1.5.4 Gross alpha radioactivity was calculated from sample analysis results and release point volumes.
Tank or system volumes, flowrate 20%
Sampling and statistical error 10%
Counting Equipment calibration 10%
Compositing sample arror 5%
TOTAL ERROR 45%
1.4.1.5.5' Volume of waste prior to dilution was calculated from level ' indicators on the tanks and pump discharge flow rates and times.
Level indicator error 10%
Operator interpretation of gauge 10%
TOTAL ERROR 20%
1.4.1.5.6 Volume of dilution water used was calculated from flow rate indicators and pump discharge flow rates and times.
Flow rate indicator error 10%
Operator interpretation of gauge 10%
TOTAL ERROR 20%
1.4.2 Batch Release Data Other data pertinent to continuous and batch releases of radioactive liquid ef flue nt from Unit 1 are listed in Table 1-6a and Table 1-6b for Unit 2.
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 Technical Specification 3/4.11.1.2 using the methodology presented in the Plant Vogtle Offsite Dose Calculation Manual.
Results are presented in Table 1-4a for Unit 1 and 1-4b for U nit 2.
This is submitted as required by section 6.8.1.4 of Technical Specification.
- 1. 6 Abnormal Releases 1.6.1 Itemization of the Location / Source of the Unplanned Releases J
1.6.1.1 Unit one containment atmosphere Radioactive Gas Release j
(4-17-1989) l 15
5 1.6.2 Description of Unplanned Release (4-17-63) 1.6.2.1 Containment Air On April 17, 1989, Chemistry issued a containment release permit 1-890078-G.
After the pressure relief ended at 9:37 on April 17, 1989, a purge was initiated without a purge permit.
So after the fact, Chemistry initiated and closed a purge ' permit 890080-G.
Using the same source term used ie 890078-G, and this permit was defined as an unplanned release.
No technical specification violation has occurred as far as dose and dose rates.
1.7 River Flow 1.7.1 The average flow rate of the Savannah River for this Semiannual E f f.lue nt Report period was obtained from the Clark Hill Dam Corp of Engineers Office.
The average flow rate is 3567 cubic feet /sec.
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f Tcblo 1-2a Georgia Power Company Vogtle Electric Generating Plant SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER L
ALL LIQUID EFFLUENTS Unit: 1 Starting :
1-Jan-1989 Ending : 30-Jun-1989 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)
CURIES 1.492E-01 3.466E-02 40 2.
AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.795E-07 1.804E-08 3.
PERCENT OF APPLICABLE LIMIT N/A N/A B. TRITIUM
- 1. TOTAL RELEASE CURIES 9.345E+01 1.454E+02 40
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.124E-04 7.566E-05
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A C.
DISSOLVED AND ENTRAINED GASES
____e._______________._,.______________._______..__________________________________
- 1. TOTAL RELEASE CURIES 4.024E-02 2.739E-02 50
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.840E-08 1.425E-08
___________________________________________________+____________________________
3.
PERCENT OF APPLICABLE LIMIT N/A N/A
____r_____________,___,_________________________________________________________
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES
- 0E0
- 0E0 45 E.. WASTE VOL RELEASED (PRE-DILUTION) LITERS 1.967E+06 1.691E+06 20
_______________________________________~________________________________________
F. VOLUME OF DILUTION WATER USED LITERS 8.293E+08 1.920E+09 20
Tablo 1-2b 4
i Georgia Power Company
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Vogtle Electric Generating Plant SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL LIQUID EFFLUENTS Unit: 2 Starting :
1-Jan-1989 Ending : 30-Jun-1989 TYFE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %
' A. FISSION & ACTIVATTON PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)
CURIES 2.574E-03 7.473E-03 40
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 9.832E-09 2.935E-00 3.' PERCENT OF APPLICABLE LIMIT N/A N/A B. TRITIUM
- _ - - _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ - - _. _ _ _ _ _ _ _ _ _ _ _ ~ _ - - - _ _ - _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _
- 1. TOTAL EELEASE' CURIES 2.525E+00 9.596E+01 40
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCi/ML 9.626E-06 3.768E-34
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A C.
DISSOLVED AND ENTRAINED GASES
. -__--________-__-_____--__________------______-_______--_________-y---_____.____
- 1. TOTAL RELEASE CURlES 5.495E-05 7.543E-03 50
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.099E-10 2.962E-08 3.
PERCENT OF APPLICABLE LIMIT N/A N/A D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES
- 0E0
- 0E0 45
-__--__y________-______________________----_-__________,.---.._--____-____________
E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 6.998E+05 8.319E+05 20 F. VOLUME OF DILUTION WATER USED LITERS 2.611E+08 2.538E+08 20
l Table 1-2c i
Georgia Power Company Vogtle Electric Generating Plant SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL LIQUID EFFLUENTS SITE Starting :
1-Jan-1989 Ending : 30_Jun_1989.
TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %
A. FISSION & ACTIVATION PRODUCTS
_.._____ _-____-_-_________--___ __~____.._________________-___-__ ____-________-_
- 1. TOTAL RELEASE (NOT INCLUDING E
TRITIUM, GASES, ALPHA)
CURIES 1.518E_01 4.213E-02 40
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.389E-07 1.936E-08
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A B. TRITIUM
- 1. TOTAL RELEASE CURIES 9.598E+01 2.431E+02 40 l 2. AVERAGE DILUTED CONCENTRATION L
DURING PERIOD uCi/ML 8.784E_05 1.117E-04 i 3. PERCENT OF APPLICABLE LIMIT N/A N/A l _________-___--___--___--_______ -_-__-__-_______________ ______________.-______
l l C.
DISSOLVED AND ENTRAINED GASES
-_____--n_--______-_--_____-_____________-__-_-_---,---____-_--____----___--___
- 1. TOTAL RELEASE CURIES 4.029E_02 3.493E_02 50
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.687E_08 1.605E-08 3.
PERCENT OF APPLICABLE LIMIT N/A N/A l D. GROSS ALPHA RADIOACTIVITY l1.-__-__ ___~_______________________________-__--_____--_________________________-
L1. TOTAL RELEASE CURIES
- 0E0
- 0E0 45 l
______--_-__________-__-__--___-_________-____-_--_______-______---____~_-_-_---
E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 2.667E+06 2.523E+06 20
)
F. VOLUME OF DILUTION WATER USED LITERS 1.090E+09 2.174E+09 20
l La Table 1-3a
'tREPORT. CATEGORY i; SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES i TOTALS FOR EACH NUCLIDE RELEASED.
TYPE OF1 ACTIVITY
- ALL RADIONUCLIDES
' REPORTING PERIOD
. : QUARTER # 1 AND QUARTER # 2 YEAR 1989 UNIT 1 l CONTINUOUS RELEASES l BATCH RELEASES
,------_-----_-------------------------------------_---l UNIT
- QUARTER 1 l QUARTER 2 l QUARTER 1 (QUARTER 2 l l US#IIE------------_----[---------1---_------[---------1------.--1..--------[
l
'ALL NUCLIDES BE-7 CURIES l 0.00E+00 l 0.00EF00 1 1.09E-03 l 0.00E+00 l
) BR-82 l
CURIES l 0.00E+00 l 0.00E+GO l 3.14E-04 1 0.00E+00 l r CO-57 1
CURIES l 0.00E+00 l o.00E+00 l 2.50E-04 l 7.72E-05 l
-CO-58 l
CUR 1ES l 3.43E-05 l 1.27E-04 l 7.56E-02 l 1.45E-02 l CO-60 l
CURIES l 0. 00E4 00 l 5.44E-05 1 7.50E-03 { 3.58E-03 l CR-51 l
CURIES l 0.00E+00 l 0.00EiOO ] 6.96E-03 l 2.27E-04 l CS-134 i
CURIES l 0.00E400 l 0.00E+00 l 1.61E-04 l 3.12E-04 l l CS-137 l
CURIES l 0.00E+00 l 0.00E+00 l 5.78E-04 j 5.21E-04 l FE-55
.]
CURIES l 4.37E-04 l 0.00E+00 ) 3.06E-02 { 9.64E-03 l FZ-59 j
CUElES l 0.00E+00 ; O.00E+00 l 2.12E-03 l 1.10E-04-l G-ALPHA l
CURIES l *0E0 l *0E0 l *0E0
{ *0E0 l
CURIES l 2.77E-03 l 0.00E+00 l 9.34E+01 j 1.45E+02 l
??-181 l
CURIES l 0.00E+00 l 0.00E+00 l 4.11E-05 { 0.00E+00 l I-131 l
CURIES l 0.00E+00 O.00E+00 l 3.08E-04 l 0.00E+00 l I-133 l
CURIES l 0.00E400 ) 0.00E+00 l 3,G4E-04 j 7 43E-06 l l
!.KR-88 l
CURIES l 0.00E+00 l 0.00E+00 l 2.37E-05 l G.00E+00 l IA-140 l
CURIES l 0.00E+00 l 0.00E+00 l 1.54E-05 l 5.35E-06 l MN-54 l
CURIES l 7.95E-06 l 4.853-05 i 1.03E-02 l 3.06E-03 l NA-24
'l CURIES l 0.00E+00 l 0.00E+00 l 5.02E-03 l 3.13E-05 l NB-95 l
CURIES l 0.00E+00 l 1.52E-05 l 2.37E-03 l 6.32E-04 l NB-97 j
CUR 7ES l 0. 00E4 00 l 0.00Et00 l 6.72E-05 l 0 00E+00 l WI-65 l
CURIES
! 0.00E+00 l 0.00E+00 l 1.99E-05 l 0.00E+00 l RU-103 j
CURIES l 0.00E+00 l 0.00E+00 l 2.26E-06 l 5.24E-06 l SB-124 1
CURIES l 0.00E+00 l 0.00E+00 l 8.70E-04 l 2.27E-04 l SB-125 i
CORIES l 0.00E+00 l 0.00E+00 l 2.11E-03 l 1.10E-03 l l SR-89 i
CURIES l *0E0 l *0E0 l *0E0 l *0E0 l
l SR-90
]
CURIES l *0E0 l *0E0 l *0E0 l *0E0 l
l SR-92 j
CURIFS l 0.00E+00 l 0.00E+00 l 1.36E-05 l 0.00E+00 l
' TC-99M i
CURIES l 0.00E+00 l 0.00E+00 l 1.35E-05 l 0.00E+00 {
XE-131M l
CURIES l 0.00E+00 l 0.00E+00 l 8.77E-05 l 0.00E+00 l XE-123 j
CURIES l 0.00E+00 { 0.00E+00 l 3.95E-02 l 2.72E-02 1 XE-133M l
CURIES l 0.00E+00 l 0.00E+00 l 7.92E-05 l 3.43E-05 l XE-135 l
CURIES l 0.00E+00 l 0.00E+00 l 5.40E-04 l 1.31E-04 l ZN-65 f
CURIES l 0.00E+00 j 0.00E+00 l 3.97E-05 l 1.86E-05 l ZR-95 1
CURIES l 0.00E+00 l 0.00E+00 l 1.36E-03 l 3.22E-04 l TOTAL FOR PERIOD l
CURIES l 3.25E-03 l 2.45E-04 l 9.36E+01 l 1.45E+02 l
- Values less than LLO. See table 1.5 for typical LLD.
20
Tablo 1-3b REPORT CATEGORY
- SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES
- TOTALS FOR EACH NUCLIDE RELEASED.
TYPE OF ACTIVITY
- ALL RADIONUCLIDES l REPORTING PERIOD
- QUARTER $ 1 AND QUARTER # 2 YEAR 1989 UNIT 2 l CONTINUOUS RELEASES l BATCH RELEASES
{
UNIT
- QUARTER 1 l QUARTER 2 l QUARTER 1 ] QUARTER 2 l NUCLIDE i
l l
l J
l ALL NUCLIDES BE-7 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 9.S4E-06 l CO-57 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.13E-05 l CO-58 l
CURIES l 0.00E+00 l 0.00E+00 l 5.71E-04 l 3.14E-03 l CO-60 l
CURIES l 0.00E+00 l 0.00E+00 l 1.83E-04 l 1.03E-03 l CR-51 l
CURIES l 0.00E+00 l 0.00E+00 l 2.34E-05 { 4.53E-04 l CS-134 l
CURIES l 0.00E+00 l 0.00E+00 l 1.81E-05 l 4.03E-05 l CS-137
[
CURIES l 0.00E+00 l 0.00E+00 l 5.64E-05 l 4.78E-05 l FE-55 l
CURIES l 0.00E+00 l 0.00L+00 l 1.49E-03 l 1.46E-03 l FE-59 l
CURIES l 0.00E+00 l 0.00E+00 1 0.00E+00 l 5.03E-05 l G-ALPHA l
CURIES l *0E0 l *0E0 l *0E0 l *0E0 l
Ai-3 l
CURIE.E l 0.00E+00 [ 0.00E+00 l 2.52E+00 l 9 59E+01 l
~I-131 l
CURIES l 0.00E+00 l 0. 00E4 00 l 0.00E+00 l 1.56E-05 l I-133 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 2.86E-05 l MN-54 l
CURIES
[ 0.00E+00 l 0.00E+00 l 1,34E-04 l 8.11E-04 l NA-24 l
CURIES l 0.00E+00 l 0.00E+00 l 0. 00E4 00 l 9.44E-04 l NB-95 l
CURIES l 0.00E+00 [ 0.00E+00 l 1.03E-04 [ 5.52E-04 l SR-89 l
CURIES l *0E0 l *0E0 l *0E0 l *0E0 l
SR-90 l
CURIES l *0E0 l *0E0 l *0E0 l *CEO TC-99M l
CURIES l 0.00E+00 j 0.00E+00 l 0.00E+00 l 1.22E-05 l AE-133 l
CURIES l 0.00E+00 l 0.00E+00 l 5.49E-05 l 7.37E-03 l XE-133M l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 3.61E-05 l XE-135 l
CURIES l 0.00E+00 -l 0.00E+00 l 0.00E+00 l 1.36E-04 l ZR-95 l
CURIES l 0.00E+00 l 0.00E+00 l 4.54E-05 l 3.13E-04 l
....------------------~_ --------------------------------------------------
TOTAL FOR PERIOD l
CURIES l 0.00E+00 1 0.00E400 l 2.52E+00 l 9.59E+01 l T
i Table 1-3C i
i REPORT CATEGORY
- SEMIANNUAL LIQUID CO VTINUOUS AND HATCH RELEASES
- TOTALS FOR EACH NUCL7DE RELEASED.
TYPE OF ACTIVITY.
- ALL RADIONUCLIDES
' REPORTING PERIOD
- QUARTER # 1 AND QUARTER # 2 YEAR 1989 SITE l CONTINUOUS RELEASES l BATCH RELEASES l
UNIT
- QUARTER 1 l QUARTER 2 jQUARTER 1 l QUARTER 2 i NUCLIDE l
l l
l l
l ALL NUCLIDES BE-7 l
CURIES l 0.00E+00 l 0.00E+00 1 1.09E-03 l 9.54E-U6 l BR-83 l
CURIES l 0.00E+00 l 0.00E+00 l 1.14E-04 l 0.00E+00 i CO-57 l
CURIES l 0.00E+00 l 0.00E+00 l 2.50E-04 l 8.85E-05 l CO-58 l
CURIES l 3.43E-05 l 1.27E-04 l 7.62E-02 l 1.76E-02 l CO-60 l
CURIES l 0.00E+00 l 5.44E-05 l 7.68E-03 l 4.61E-03 [
CR-51 l
CURIES l 0.00E+00 l 0.00E+00 l 6.98E-03 l 6.80E-04 l CS-134 l
CURIES l 0.00E+00 l 0.00E+00 j 1.79E-04 l 3.S2E-04 l CS-137 l
CURIES l 0.00E+00 l 0.00E+00 1 6.34E-04 l 5.69E-04 j FE-55 l
CURIES l 4.37E-04 l 0.00E+00 1 3.21E-02 l 1.11e-02 l l FE-59 l
CURIES l 0.00E+00 l 0.00E+00 1 2.12E-03 l 1.60E-04 l l G-ALPHA l
CURIES l *0E0 l *0E0 l *0E0 l *0E0 l
CURIES l 2.77E-03 [ 0.00E+00 l 9.S9E+01 l 2.41E+02 l HF-181 l
CURIES l 0.00E+00 l 0.00E*00 l 4.11E-05 l 0.00E+00 (
I-131 l
CURIES l 0.00E+00 l. 0.00E+00 l 3.08E-04 l 1.56E-06 l I-133 l
CURIES l 0.00E+00 l 0.00E+00 l 3.64E-04 l 3.60E-05 l KR-88 l
CURIES l 0.00E+00 l 0.00E+00 l 2.37E-05 l 0.00E+00 l LA-140 l
CURIES l 0.00E+00 l 0.00E+00 l 1.54E-05 l 5.35E-06 l MN-54 l
CURIES l 7.95E-06 l 4.85E-05 l 1.04E-02 l 3.87E-03 i NA-34 l
CURIES l 0.00E+00 l 0.00E+00 l 5.02E-03 l 9.75E-04 l NB-95 l
CURIES l 0.00E+00 l 1.52E-05 l 2.47E-03 l 1.18E-03 l NB-97 l
CURIES l 0.00E+00 l 0.00E+00 l 6.72E-05 l 0.00E+00 l NI-65 l
CURIES l 0.00E+00 l 0.00E+00 l 1.99E-05 l 0.00E+00 l RU-103 l
CURIES l 0.00E+00 l 0.00E+00 l 2.26E-06 l 5.24E-06 l SB-124 l
CURIES l 0.00E+00 l 0.00E+00 l 8.70E-04 l 2.27E-04 l SB-125 l
CURIES l 0.00E+00 l 0.00E+00 l 2.11E-03 l 1.10E-03 l SR-89 l
CURIES l *0E0 l *0E0 l *0E0 l *0E0 l
SR-90 l
CURIES l *0E0 l *0E0 l *0E0
- *0E0 l
TC-99M l
CURIES l 0.00E+00 l 0.00E+00 l 1.35E-05 l 1.22E-05 l XE-131M l
CURIES l 0.00E+00 l 0.00E+00 l 8.77E-05 l 0.00E+00 l i
XE-133 l
CURIES l 0.00E+00 l 0.00E+00 l 3.96E-02 l 3.46E-02 l l XE-133M l
CURIES l 0.00E+00 l 0.00E+00 l 7.92E-05 l 7.04E-05 l XE-135 l
CURIES l 0.00E+00 l 0.00E+00 l 5.40E-04 l 2.67E-04 l ZN-65 l
CURIES l 0.00E+00 l 0.00E+00 l 3.97E-05 l 1.86E-05 l 2R-95 l
CURIES l 0.00E+00 l 0.00E+00 l 1.41E-03 l 6.35E-04 l TOTAL FOR PERIOD l
CURIES l 3.25E-03 l 2.45E-04 l 9.61E+01 l 2.41E+02 l 0 Values less than LLD. See table 1.5 for typical LLD.
22 i
R____.__
I l
TABLE 1-4A
{
l VoGTLE ELECTRIC GEPERATING PLANT I
SE'IANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l
A INDIVIDUAL DOSES DU2 TO LIQUID RELEASES January 1, 1989 Through June 30, 1989 UNT T 1 f
Cumulativ,e'Dore Per Qunrter organ Tech-
'J nf t s Quarter
% of Quarter
% of Spec Tech Tech Limit 1
Limit 2
I.imit
'~
Tone 5.0 mres 4.68E-03 7756E-02 5.81E-03 1.16E-01 Liver 5.0 mrem 6.06E-03 1.21E-01 1.39E-02 2.78E-01 T.
B ody 1.5 mena 4.49E-03 2.99E-01 1.11E-02 7.40E-01 Thyroid 5.0 mrem 1.84E-03 3.68E-02 3.91E-03 7767E 07
- Kidney, 5.0 are.m 2.962-03 5.92E-02 7.19E-03 1.44E-01 Lung 5.0 mrem 2.90E-03 5.80's-02 5.65E-03 1.13E-01 U1-LLI 5.0 arem o ~7hA-03__ _~
.l.35E-01 6.731-03 1.35E-01 Cumulative' Dose'Fer Year Organ Tech Units
Year to Date
% of Tech Spec Limit Spec Limit Bone
' 10.0 mrem 1,. 9 5 E- 0 2 1.05E-01 liver 10.G
~
mrem 2.00E-02 2.00E-01 T
Body 3.0 mrem 1.56E-02 5.20E-01 Thyroid 10.0
~
mrem S,75E-03 5.75E-02 Kidney 10.0' aiEE' ~
1.02E-02 1.02E-01
~~
lung 107D mrem 8.55E-03 8.55E-02 GI-LLI 10.0___
parem 1.35E-02 1.35E-01 23
4 TABLE 1-4b TOGTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES February $. 1989 Through June 30, 1989 UNIT 2 Cumulative Dose Per Quar.ter Organ Tech Unite Quarter
% of Quarter
% of Spec Tech Tech Limit 1
Limit 2
Limit Bone 5.0 mrem 2.975-04 5.94E-03 6.22E-04 1.24E-02
, Liver 5.0 3 rem
- 5. 0 5ET{T~~~
1.02E-UZ 2.85E-03 5.70E-02 T.
Body 1.5 nrem 3.63Fa04 2,,42E-02 2.59E-03 1.73E-01 6.861 4 7 "~,1.36E-03 1.91E-03 3.82E-02
~
2hyroid 5.0 mrem Kidney 5.0 mrew 1.93E-6%
3.86E-03 2.19E-03 4.38E-02 Lung 5.0 arem
~T~WCW' 2.92E-03 1.98E-03 3.96E-02 GI-LL1 5.0 meer J. F7E-64'=
,2.54E-03 2.35E-03 4.70E-02
~
Cumulative Dose Per Year Organ Tech U di.t s Year to Date
% of Tech Spec Limit Spec Limit
~~
Bone 10.0 mrem 9.19E-04 9.19E-03 3.36E-02 Liver 10.0 mrem 3.36E-03 ~
~
T.
Body 3.0 aren 2.95E-03 9.84E-02
^
~~
Thyroid 10.0 m rera 1.98E-03 1.98E-02 Kidney 10.0 a rem 2.30E-63 2.38E-02
~
Lung 10.0 mrem 2.08E-03 2.08E-02 GI-LLI 10.0 gfem 2.48E-03 2.48E-02 I
l l
l I
i 24 i
I.
l TABLE 1-5 (Page 1 ot' 3)
LOWER LIMITS OF DETECTION - LIQUID SAMPLE ANALYSES V0GTLE ELECTRIC GENERATING PLANT (JANUARY 1, 1989 Through JUNE 30, 1989)
'The values in this table represent apriori lower limits of detection (LLD) which are typically achieved in laboratory analyses of liquid radwaste samples.
RADIONUCLIDES LLD UNITS Mn-54 9.87E-09 uCi/mi L
Fe-59 7.91E-10 uCi/mi Co-58 1.12E-08 uCi/mi Co-60 1.03E-08 uCi/ml Zn-65 2.35E-08 uCi/mi Mo-99 6.94E-08 uCi/ml Cs-134 1.35E-08 uCi/ml Cs-137 1.18E-08 uCi/ml Ce-141 1.73E-08 uCi/ml I
Ce-144 7.37E-08 uCi/ml l
I-131 1.21E-08 uCi/ml Xe-133 2.93E-08 uCi/ml Xe-135 1.052-08 uCi/ml Fe-55 1.00E-06 uCi/ml Sr-89 5.00E-08 uCi/mi Sr-90 7.00E-09 uCi/ml H-3 2.00E-06 uCi/ml Gross Alpha 7.00E-08 uCi/ml 1412A 25 l
TABLE 1-5 (Page 2 of 3)
LOWER LIMITS OF DETECTION - LIQUID SAMPLF ANALYSES V0GTLE ELECT'RIC GENERATING PLANT January 1, 1989 Through June 30, 1989 The values in this table represent apriori lower limits of detection (LLD) which are typically achieved in laboratory analyses of liquid radwaste samples.
RADIONUCLIDES LLD UNITS Au-198 9.77E-09 nCi/ml Ba-140 4.86E-08 uCi/ml Be-7 8.27E-08 uCi/mi Co-57 7.46E-09 uCi/mi Cr-51 9.18E-08 uCi/mi Cs-138 5.37E-08 uCi/ml I-133 1.32E-08 uCi/ml I-135 4.59E-08 uCi/ml La-140 8.97E-09 uCi/ml Mn-55 7.32E-08 uCi/ml Na-24 1.35E-08 uCi/ml Nb-95 1.15E-08 uCi/ml Nb-97 1.23E-08 uCi/ml Np-239 2.62E-08 uCi/ml Ru-106 5.24E-08 uCi/ml Sb-122 1.79E-08 uCi/ml Tc-99m 8.93E-09 uCi/ml Te-132 1.01E-08 uCi/ml l
l l
l l
26
/7FR P
1 l ~-
4 l
1 TABLE-1-5 (Page 3 of 3) n LOWER LIMITS OF DETECTION - LIQUID SAMPLE ANALYSES 1 '
V0GTLE ELECTRIC GENERATING PLANT January 1, 1989 Through June 30, 1989 1
The values in this table represert spriori lower limits of detection.
l (LLD) which are typically achieved'in laboratory analyses of liquid l
radwaste samples.
RADIONUCLIDES LLD UNITS W-187 4.39E-08 uCi/mi Xe-131m 3.57E-07 uC1/ml Xe-133m-7.39E-08 uCi/ml Zr-95 2.37E-08 uCi/mi Zr-97 9.73E-09 uCi/ml Sb-124 1.79E-08 uCi/ml 27
Tcblo 1-6a Georgia Power Company Vogtle Electric Generating Plant h.
BATCH RELEASE
SUMMARY
OF ALL RELEASES Otarting :
1-Jan-1989 Ending :
30-Jun-1989 Unit 1
.____________________+.__________________ ________________________________________
LIQUID RELEASES NUMBER OF RELEASES 181 8'
TOTAL TIME FOR ALL RELEASES :
11081.00 MINUTES MAXIMUM TIME FOR A RELEASE 167.00 MINUTES AVERAGE TIME FOR A RELEASE 61.22 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES
' AVERAGE STREAM FLOW 70.11 GPM GASEOUS RELEASES NUMBER OF RELEASES 129 TOTAL TIME FOR ALL RELEASES :
9149.00 MINUTES MAXIMUM TIME FOR A RELEASE 1454.00 MINUTES AVERAGE TIME FOR A RELEASE 70.,92 MINUTES MINIMUM TIME FOR A REEASE 6.00 MINUTES
..______________________________________________i.________________________________
28
~,
g,,. '
Tablo11-6b Georgia Power comptny Vogtle Electric Generating' Plant' BATCH RELEASE
SUMMARY
OF ALL RELEASES-Starting :
5-Feb-1989 EndingL:
30-Jun-2989 l'
UNIT-2 l
l~
1';
i-LI
}-------------QUID RELEASES
w ---------------------
hNUMBEROFRELEASES 67.
' TOTAL TIME FOR ALL RELEASES :
5765.00 MINUTES MAXIMUM TIME FOR A RELEASE.::
242.00 MINUTES AVERAGE TIME FOR A RELEASE
-86.04 MINUTES
,iMINIMUM TIME FOR A RELEASE 2.00 MINUTES.
l--AVERAGE STREAM FLOW 68.59 GFM 1
e-------------------------------
GASEOUS RELEASES:
l -<.-------- ------_----------_------ --------_-------_------------_-__--.----
NUMBER OF RELEASES:
8
- c. TOTAL TIME.FOR ALL RELEASES :
158354.00 MINUTES I MAXIMUM TIME FOR A-RELEASE 42540.00 MINUTES U AVERAGE TIME FOR A RELEASE 19794.25 MINUTES
' MINIMUM TIME'FOR A. RELEASE 33.00 MINUTES 1
l 1
1 29 1
2.0 Gaseous Effluents-2.1 REGULATORY LIMITS / TECHNICAL SPECIFICATIONS-The Technical Specifications presented in this section are for U nit 1 and Unit 2.
The instrumentation required may be found in Table 2-1 of this report.
2.1.1 Effluent Monitoring Syst.em 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-10 shall be OPERAELE 'vith their Alarm / Trip Setpoints set to ensure that the limics of Specifications 3.11.2.la and 3.11.2.5 are not exceeded.
The Alarm / Trip Setpoints of these channels meeting Specification 3.11.2.la shall be f.etermined and adjusted in accordance with the methodology.
and parameters in the ODCM.
2.1,2 Dose Rate Limit l
3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-land
'.1-2) shall be limited i
to the following:
a.
For noble gases:
Less than or equal to.500 mrems/ year to the whole body and less than or equal to 3000 mrems/yr to the skin, and l
l b.
For Iodine-131 for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8
days:
less than or equal to 1500 mrems/yr to any organ.
l l
2.1.3 Air Dose Due to Noble Gas 3.11.2.2 The air dose due to noble gas released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-land 5.1-2) shall be limited to the following:
1 1
30
l.
h a.
During any calendar quarter:
Less than.or equal to 5
~
l-mrads. f or 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 mrada for beta radiation.
2.1.4 Dose to Any Organ 3.11.2.3 The dose to a
MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium,. and all radionuclides in particulate form with half-lives greater than 8
days in gaseous effluents released, from ear.h unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-land 5.1-2) shall be limited to the following:-
a.
During any calendar quarter:
less than or equal to l
7.5 mrems to any organ and, l
b.
During any calendar year:
Less than or equal to 15 mrems to any organ.
2.1.5 Ventilation Exhaust Treatment System and Gaseous Waste l
Processing System 3.1L1.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the GASEOUS WASTE PROCESSING SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (See Figure 5.1-land 5.1-2) would exceed:
a.
0.2 mrad to air f rom gamma radiation, or b.
0.4 mrad to air from beta radiation, or c.
0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
31
2.1.6 Explosive Gas Mixture 3.11.2.5 The concentration of oxygen in the GASEOUS WASTE PROCESSING SYSTEM shall be limited to less than or equal to 2%
by volume wbenever the hydrogen concentration exceeds 4% by volume.
1 2.1.7 Activity in Gas Tanks 3.11.2.6 l
The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 2.055.
curies of. noble gases (considered as Xe-133 equivalent).
2.1.8 Total Fuel Cycle Dose Commitment 3.11.4 The annual (calendar year) dose Lr 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 i
body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
APPLICABILITY ACTION:
1 At all times a.
With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, I
or 3.11.2.3b calculations shall be made including l
direct radiation contributions from the units (including ontside storage tanks etc.)
to determine whether the above limits of specification 3.11.4 have been exceeded.
i 6.8.1.4 States in part:
l The Semiannual Radioactive Effluent Release Report to be l
submitted within 60 days after January 1 of each year shall also include an assessment of radiation doses eo the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other uranium fuel cycle resources within 8 i
l km, including doses from primary effluent pathways and for the previous calendar year to show direct radiation,40 CFR i
with part 190, " Environmental Radiation conformance Protection Standards for Nuclear Power Operation".
Acceptable methods for calculating the dose cont ri butio n from liquid and gaseous effluents are given in Regulatory
]
Guide 1.109, Rev.
1, October 1977.
32
)
i a_
i
,.2.1.9
-Reporting of Semiannual Releases (Unplanned)
-6.8.1.4 states in part:
The Semiannual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gassous and liquid effluents made during the reporting period.
VEGP unplanned releases are described in section 1.6 of this report.
32 I
u______.-_
TABLE 2-1 (Sheet 2 of 4)
/~^
(From Technical Specifications)
'(,j)
(T.ABLE 3.3-10)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENTS OPERABLE APPLICABILITY ACTION
- 4. PLANT VENT A. Noble Gas Activity Monitor (RE-12442C or RE-12444C) 1 47, 48
- b. Iodine Sampler / Monitor (RE-12442B or RE-12444B) 1 51
- c. Particulate Samplar/
Monitor (RE-12442A or RE-12444A) 1 51
- d. Flow Rate Monitor (RE-12442) 1 46
- e. Sampler Flow Rate
/]
Monitor (FI-12442 or
~
\\_/
FI-12444) 1 46 TABLE NOTATIONS At all times.
During GASEOUS WASTE PROCESSING SYSTEM operation During radioactive releases via this pathway During Emergency Filtration 4
I
)
34
I f-s TABLE 2-1 (Sheet 1 of 4)
(
)
(From Technical Specifications)
(TABLE 3.3-10)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS
, INSTRUMENT OPERABLE APPLICABILITY ACTION
- 1. GASEOUS WASTE PROCESSING
- a. Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release (ARE-0014) 1 45
- b. Effluent System Flow Rate Measuring Device 1
46 (AFT-0014)
- 2. GAbEOUS WASTE PROCESSING SYSTEM - Explosive Gas Monitoring System r'
- a. Hydrogen Monitor 1/recombiner 50 4
- b. Oxygen Monitor 2/recombiner 49
- 3. CONDENSER AIR EJECTOR AND STEAM PACKING EXHAUSTER SYSTEM
- a. Noble Gas Activity Monitor (RE-12839C) 1 47 b.
Iodine Sampler (RE-128398) 1 51
- c. Particulate Sampler (RE-12839A) 1 51
- d. Flow Rate Monitor.
1 46 (FT-12839) (FIS-12362)#
- e. Sampler Flow Rate 1
46 Monitor (FI-13211) 35
a
]
C 'p u
. TAB *E 2-1 (Sheet 3 of 4)
,P'y (From Technical Specifications) o V C"ABLE 3.3-10) i ACTION STATEMENTS ACTION 45 with the number of channels OPSRABLE less than required
' by. the Minimum Channels OPERABLE requirement,'.the-contents of the tank (s) may be released to the environment provided that prior to initiating the-
~ release:
a.
At least two independent samples of the tank's.
1 contents are analyzed, and b.
At least two technically qualified members of the facility staff independently verify.the release rate calculations'and discharge valve lineup.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTIbN 46 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 houro.
ACTION 47 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity within'24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..
ACTION 48 With the number of channels OPERABLE less than required by the Minimum Channels 6PERABLE requirement, immediately suspend containment. purging of radioactive effluents via this pathway.
ACTION 49 a.
With the outlet cxygen monitor channel inoperable, operation of the system may continue provided grab samples are taken and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the oxygen concentration remains less than 1 percent.
b.
With the inlet oxygen monitor inoperable, operation may continue if inlet hydrogen monitor is operable.
)
i 36 I
i
I TABLE 2-1 f3heet 4 of 4) l fly (From Technical Specifications)-
Nj (TABLE 3.3-10)
TABLE NOTATIONS (Continued) c.
With both oxygen' channels or both of the inlet oxygen and inlet hydrogen monitors inoperable, suspend. oxygen supply.to the recombiner.. Addition of: waste gas to the system may continue 'provided grab samples are taken and analyzed at least once per 4
hours during degassing operations or at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations
-l and theioxygen concentration remains less than l'-
percent.
' ACTION 50 With the number of channels OPERABLE one less, than required by-the Minimum Channels OPERABLE requirement',
suspend oxygen supply to the recombiner.
Addition of waste' gas to the system may. continue.provided -grab' samples are Ltaken and analyzed =at'least once per-4 hours during degassing operation or at least once per' 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations and the oxygen concentration remains less than 1 percent.
~('.
ACTION 51' With the number of channels operable less than required' by the' Minimum Channels OPERABLE requirement, effluent-releases via the affected pathway may continue provided samples are continuously collected with auxiliary-sampling equipment as required in Table.4.11-2.
O 37 i
2.2 Release Points of Gaseous Effluents Gaseous Effluents at Vogtle Electric Generating Plant are currently confined to four paths:
plant vents (Unit 1 and Unit 2), and the condenser air ejector and steam packing exhauster systems (Unit 1 and Unit 2).
Waste gas decay tanks are batch releases and the waste gas decay tanks are released through the Unit l' plant vent.
Containment purges are released through their respective plant vents.
2.3 Sample Collection and Analysis All of the paths can be continuously monitorgd for gaseous radioactivity.
Each is equipped with an integrated-type sample collection device for collecting particulate and iodines.
Sample collection is in accordance with Technical Specification Table 4.11-2.
During this release period, there were no radioactive releases through the condenser mir ejector and steam packing exhauster system vents.
Unless required more frequently under certain circumstances specified in Table Notations tu the above mentioned tables, samples are collected as follows:
1.
Noble gas samples are collected by grab campling monthly.
2.
Tritium samples are collected by grab - sampling monthly.
3.
Radioiodine samples are collected from the sample stream thr:ough a charcoal cartridge. over a 7-day period.
4.
Particulate are collected from the sample stream through a particulate filter over a 7-day period.
5.
The 7-day particulate filt.e rs above are analyzed for gross alpha activity.
6.
Quarterly composite samples ale prepared from the particulate filters collected over the previous quarter and the quarterly composite sample is analyzed for Sr-89 and Sr-90.
38
t 1
1 L
Batch Waste Gas Decay Tank releases are analyzed for
- iodines, particulate and noble gases before each release.. In addition, the containment atmosphere is l -
analyzed for tritium on at.least a monthly basis, 1
l Sample. analyses results and release flow rates from the release points form the basis for calculating released quantities of radionuclides specific radioactivity, dose rates associated with gaseous releases and cumulative doses for the current quarter i
and year.
This task is normally performed with computer assistance.
l'
- The noble gas grab sample and analysis (from principal l
gamma emitters) results are used along with maximum I
expected release flow rates from each of the vents to.
l calculate monitor setpoints, for the gaseous effluent monitors-serving the two release points, to l assure that the limits of Technical Specifications 3.11.2.la are not exceeded.
Calculation of monitor setpoints is p
described in the Vogtle Electric Generating Plant ODCM, With each release period and batch
- release, radioactivity, dose-rates and cumulative dosea are calculated.
Cumulative dose results are tabulated, along with percent of Technical Specification limits l
(3'.11.2.2 and 3.11.2.3),
for each release for the current quarter cod year.
After each calendar quarter (13 weeks), a summary of waste gas releases from the two vents and batch processes is compiled for preparation of the Semiannual Radioactive Effluent Release Report required by Technical Specifications 6.8.1.4 and NRC Regulatory Guide 1.21, 2.4 Determination Of Total Quantities of Radioactivity, Dose Rates and Cumulative Doses The methods for determining release quantities of radioactivity, dose rates and cumulative doses are as follows:
l 39 1
'L
____._m__._._.__
2.4.1 Fission and Activation Gas The radionuclides-specific released radioactivity is determined from sample analyses results collected as described above and average release flow rates over the period represented by the collected sample.
Instantaneous dose rates due to noble gases and due to radioiodines, - tritium, and particulate are calculated (with computer assistance).
Calculated dose rates are compared to the dose rate limits specified in 3.11.2.la for noble gases; and 3.11.2.lb for radioiodine,
- tritium, and particulate.
Dose rate i
calculation methodology is presentad 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 to the dose limits specified in Technical Specificat'on 3.11.2.2.
Current percent of the technical specification limits are shown on the princout for each release period.
Air dose l
calculation methodology is presented in the ODCM.
2.4.2 Radioiodine, Tritium and Particulate Releases Released quantities of radioiodines are determined from the neekly samples and release flow rates for the two release points.
Radioiodine concentrations are determined by gamma spectroscopy.
Release quantitles of particulate are determined from the weekly (filter) samples and release flow rates for the two release points.
Gamma spectroscopy is used to quantify concentrations of principal gamma emitters.
After each calendar
- month, the particulate filters from each vent are combined, fused, and a strontium separation is performed.
If Sr-89 or Sr-90 is not
- detected, LLD's are egiculated.
Strontium concentrations are input to the composite file of the computer to be used for release dose rate and I
individual dose calculations.
l 40 a
nr,,--- ---- -
A t
ll
^
!m l*
Tritium samples are obtained monthly from each vent by bubbling the sample stream through a" water trap.
The tritium concentration in water is converted to tritium-concentration in air end this value is input into the composite file of the computer.to be used in release, dose rate, and individual dose calculations.-
l Dose' rates due to radioiodine,
'and particulate are calculated for a hypothetical child, exposed to the inhalation pathway..at the location in the unrestricted area where the potential dose. rate is expected to'be the highest.
Dose rates are calculat6d for each release point,, f or each release period, and the total dose rate from both release points are~
compared to-the dose rate limits specified in Technical Specification'3.11.2.lb.
Individual doses due to radiciodine, tritium and l
particulate are calculated for the critical receptor, l
which f or 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 Technical Specification 3.11.2.3.
Current percent of technical specification limits are shown on the prietout for each release period.
2.4.3 Gross Alpha Release The gross alpha release is computed each month by counting the particulate filters offsite for each week i
I for gross alpha activity in a proportional counter.
The four or five weeks' numbers are then recorded on a data sheet and the activity is summed at the end of the month.
This concentration is input to the composite file of the computer and is used for release calculations.
2.5 Gaseous Effluent Release Data
]
l l
t 41 a----__.-_a.__.-
2.5.1 Methodology
' Regulatory. Guide 1.21 Tables 1A, 1B, and 1C are found in this report as Tables 2-2a, 2-2b, 2-3a 2-3b, 2-4a and 2-4b.-
Data is presented on a quarterly basis as required by Regulatory Guide 1.21.
To complete Table 2-2a and 2-2b, total release for each of the four categories (fission and activation
- gases, iodines, particulate, and tritium) was divided by the number of seconds in the quartet to obtain a-release rate in uCi/second for each category for
~ each quarter.
- However, the percent of the applicable Technical Specification limits are not applicable because we have no curie limits for gaseous relcases.
Noble gases are limited as specified in-3.11.2 la..
The other three' categories (tritium, radioicdines, and particulate) are limited as a group as specified in 3.11.2.lb.
Dose rates due to noble gas releases and due to radioiodine,
- tritium, and particulate are presented La Table 2-5 along with percent of technical specification limits.
Gross alpha radioactivity is reported in Table 2-2a and 2-2b as curies released in each quarter.
Limits for cumulative beta and gamma air doses due to noble gases are specified in Technical Specification 3.11.2.2.
Cum 21stive air doses are presented in Table 2-6a and 2-6b along with percent of technical specification limits.
Limits for cumulative individual doses due to radioiodine, tritium, and particulate, are specified in Technical Specification 3.11,2,3.
Cumulative individual doses are presented in Table 2-7a and 2-7b along with percent of technical specification limits.
The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total operation of sampling and measurement.
Pecause it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of l
error are not suggested.
The objective should be to l
obtain en overall estimate of the error associated I
with measurements of radioactive materials released in liquid and gaseous effluent.s and solid waste.
1 42
4 Estimated errors ~are based on errors in counting equipment calibration, counting statistics, vent-flow rates,_
vent sample flow
- rates, non-steady release i
- rates, chemical yield factors and sample losses for l
such items as charcoal cartridges.
l l
2.5.1.1 Fission and activation ' total release was calculated from somple analysis results and release point flow rates.
Sampling and statistical error 10%
Counting equipment calibration 10%
Vent flow rates 10%
Non-steady release rates 20%
TOTAL ERROR 50%
2.5.1.2 I-131 releases were calculated from each weekly sample:
Statistical error 10%
Counting equipment calibration 10%
Vent flow rates 10%
Vent sample flow rstes 50%
Non-steady release rates 10%
Losses from charcoal cartridges 10%
TOTAL ERROR 100%
2.5'.1.3 Particulate with half lives greater than 8
day releases were calculated from sample analysis results and release point flow rates.
Statistical error at LLD concentration 10%
Counting equipment calibration 10%
Vent flow rates 10%
Vent sample flow rates 50%
Non-steady release rates 10%
TOTAL ERROR 90%
2.5.1.4 Total tritium releases were calculated from sample analysis results and release point flow rates.
Water vapor in sample stream determination 10%
Vent flow rates 10%
Counting calibration and statistics 10%
Non-steady release rates 10%
TOTAL ERROR 40%
2.5.2 Gaseous Batch Data I
Other data pertinent to batch releases of radioactive gaseous effluent from Unit 1 and Unit 2 are listed in i
4 Table 1-6a and 1-6b.
43
l-
.n 2.6 Radioiugical Impact Due to Gaseous Releases j
Dose rates due to noble gas. releases were calculated for the site in accordance with Technical Specification. 3/4.11.2.la.
Results are presented in Table 2-5.
Dose rates due to radioiodine, tritium, and particulate in gaseous releases were calculated in accordance with
_ Technical S pecif ic ation 3/4.11.2.lb.
These results are also in Table 2-5.
Cumulative air doses due to noble gas releases were calculated for each unit in accordance with Technical Specification-3/4.11.2.2.
These results are presented in Tables 2-6a and 2-6b.
Cumulative doses to an individual due to radioiodine,
- tritium, and particulate were calculated in accordance with Technical Specification 3/4.11.2.3.
These results are presented in Tables 2-7a and 2-7b.
Dose rates and doses were calculated using the methodology presented in the Vogtle Electric Generating Plant Offsite Dose Calculation Manual.
44
~
i g
=,
Table 2-2a Georgia Power Company Vogtle Electric Generating Plant SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL AIRBORNE EFFLUENTS Unit: 1 Starting :
1-Jan-1989 Ending : 30-Jun-1989 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %
__--_-___---__--____--___--__------___r___---_-__----___--___
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 2.278E+01 2.138E+01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.930E+00 2.719E+00
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A B.
RADIOIODINES
- 1. TOTAL IODINE-131 CURIES 1.646E-05 3.407E-07 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.117E-06 4.333E-08 3.
PERCENT OF APPLICABLE LIMIT N/A N/A C. PARTICULATE
- 1. PARTICULATE (HALF-LIVES >8 DAYS)
CURIES 1.065E-04 9.793E-05 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.369E-05 1.246E-05
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A
- 4. GROSS ALPHA RADIOACTIVITY CURIES 5.758E-07 2.706E-07
- D. TRITIUM
- 1. TOTAL RELEASE CURIES 7.176E+02 4.154E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 9.228E+01 5.283E+00
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A
A js o'
Yable 2-2b Georgia Power Company Vogtle Electric Generating Plant SEMIANNUAL SUMMATION GF ALL RELEASES BY QUARTER ALL AIRBORNE EFFLUEETS Unit: 2 Starting :
.5-Jab-1989 Ending : 30-Jun-1989 TYPE CF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %
' A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 1.386E-03 3.198E+02 50
,2.
AVERAGE REIEASE RATE FOR PERIOD uCi/Sec 2.865E-04 4.067E+01 3.
PERCENT OF APPLICABLE LIMIT N/A N/A
_________.___________________u____________________________._____________________
B. RADIOIODINES
- 1. TOTAL IODINE-131 CURIES 1.373E-08 0.000E+00 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.837E-09 0.000E+00 3.
PERCSNT OF APPLICABLE LIMIT N/A N/A C.
PARTICULATE
- 1. PARTICULATE (HALF-LIVES >8 DAYS)
CURIES
&DEO 9.676E-04 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec
- 0E0 1.230E-05 3.
PERCENT OF APPLICABLE LIMIT N/A N/A l 4:.
GROSS ALPHA RADIDACTIV7TY CURIES
- 0E0 9.039e-09
____________,.______________,_a________________-_________________________________
D. TRITIUM
- 1. TOTAL RELEASE CURIES 8.200E-01 2.380E+00 40
- 2. AVERAGE RELEASE RATE TOR PERIOD uCi/Sec 1.760E-01 3.030E-01
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A
-e Table 2-2c Georgia Power Company Vogtle Electric Generating Plant SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL AIRBORNE EFFLUENTS SITE Starting :
1-Jan-1989 Ending : 30-Jun-1989 TYPE OF FFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RFLIASE CURIES 2.278E+01 3.411E+02 50 2.
AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.930E+00 4.339E+01
__________._m..___________________________________________________________
3.
PERCENT OF APPLICABLE LIMIT N/A N/A
'B.
RADIDIODINES
- 1. TOTAL IODINE-131 CURIES 1.647E-05 3.407E-07 100
- 2. AVERAGE RELEASE RATE FOR PERIOD. uCi/Sec 2.119E-06 4.3332-08 3.
PERCENT OF APPL 1 CABLE LIMIT N/A N/A C.
PARTICULATE 1.
PARTICULATE (HALF-LIVES >8 DAYS)
CURIES 1.065E-04 1.065E-03 90
_________________.3______________________________________________________________
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.369E-05 2.476E-05
- 3. PERCENT OF APPLICABLE LIMIT t
N/A N/A
- 4. GROSS ALPHA RADIOACTIVITY CURIES 5.758E-07 2.796e-07 D. TRIT 1UM
- 1. TOTAL RELEASE CURIES 7.184E+02 4.392E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 9.245E+01 5.5SGE+00 3.
PERCENT OF APPLICABLE LIMIT N/A N/A
4
. o 4
TABLE 2-3a (Page 1 of 2)
V0GTLE ELECTRIC CENERATING PLA*iT SEMIANNUAL RADI0 ACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - MIXED MODE January 1, 1989 Through June 30, 1983 UNIT 2 Continuous Mode Batch Mode Nuclides Unit Quarter Quarter Quarter Quarter Released 1
2 1
2 1.
Fission Gases Kr-05 Ci
- 0E0
- 0E0
- 0E0 1.65E-01 Xe-133 C1 2.24E+01 1.44E+01 3.06E-01 5.80E+00 Xe-135 C1 1.13E-02 1.26E-01 8.08E-04 7.82E-03 Ar-41 Ci
- 0E0 4.70E-Oi 7.04E-02 3,00E 61
~
Xe-131n__
Ci
- 0E0
- 0E0
- 0E0 9.36E-02 Xe 133m Ci
- 0E0
- 0E0 1.09E-03 5.!JECD3 Xe-135m Ci
- 0E0
- 0E0
- 0E0 1.?2E-04 TOTAL FOR PERIOD Ci 2.24E+01 1".'5 0 E+ 01 3.78E-02 6725d+00 I
2.
(
1-131 C1 1.65E-05 3.40E-07
- 0E0
- 0EL I-133 Ci 5.23E-06
- 0E0
- 0E0
- 0E6 ~((
^~
TOTAL FOR PERIOD Ci 2.17E-05 3.40E-07
- 0E0
- 0E0
- Zeroes in this table indicate that no radioactivity was present above detectable levels.
See Table 2-8 for typical 3 aver limits of detection for gaseous sample analyses.
48
r 4
TABLE 2-3a (Page 2 of 2)
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADl0 ACTIVE LFFLUENT REPORT GASEOUS EFFLUENTS - MIXED MODE January 1, 1989 Through June 30, 1989 UNIT 1 Continut,us Mode Batch Mode Nuclides Unit Quarter Quarter
_ _ _ _ _ _, Quarter Quarter Released 1
2 1
'2
- 3. Particulate **
Co-58 Ci 2.80E-06
- 0E0 8.30E-05 9.00E-05
~
^
Co-60 Ci 7.96E-07
- 0E0 2.74E-06 4.59E-06 H-3, Ci 7.15E+02; 3,20E401 2.58fT00 9.56E+00
~
G-Alpha
~
Ci 5.76E-07 2.71E-07
- 0E0
- 0E0 I
Mn-54 Ci 5.84E li7
- 020'
'1.04E-05 3.78E-06 Tc-99m C1 2.6TA-06
- 0E0~
- 0E0
- 0E0
~
Nb-95 Ci ~ ~ ' _
80E0
$0 Q "
3.90E-06
- 0E0 1_;
7.15E+0 I 3.20E+01 2.58E+00 9.56E+00 TOTAL FOR PERIOD Ci
- Zeroes in this table indicate that no radioactivity was present above detectable icvels.
See Table 2-8 for typical lower ifnits of detection for gaseous sacple analyses
- Half lives greater than 8 days.
l
\\
49
' bA '
TABLE 2-3b (Page 1 of ~0 2
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - M1XED MODE February 5, 1989'Through June 30, 1989 UNIT 2 Continuous, Mode Batch Mode Nuclides Unit Quarter Quarter Quarter Quarter Released 1
2 1
2 1.
Fission Gases Kr-85 Ci
- 0E0
- 0E0
- 0E0 2.22E-01
~~
Xe-133 C1
- 0E0 1.19E+01 1.S9E-03 2.60E+02 Xe-135 Ci
- 0E0 8.99E-02
- 0E0
- 0E0 Ar Ci
- 0E0 1.17E+00 8' 0 E0 8.50E-01 Xe-131m Ci
- 0E0
- 0E0
- 0E0 2.12E+01 TOTAL FOR FERIOD Ci
- 0E0 1.32E+01 1.39E-03 2.82E+02
- 2. Iodines T][ 31 ci 1.37E-06 80E0 80E0 "0E0 TOTAL FOR PERIOD C1 1.37E-08
- 0E0
- 0E0
- 0E0
- Zeroes in this table indicate that no radioactivity was present above detectable levels.
See Table 2-8 for typical lower limits of detection l
for gaseous sample analyses.
l 50 1
L__---_
e.
TABLE 2-3b (Page 2 of 2)
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIO 1.ETIVE EFFLUENT REPORT CASEOUS EFFLUENTS - MIXED' MODE February 5, 1989 Through June 30, 1989 UNIT 2 Continuous Mode'
. Batch Mode Nuclides Unit Quarter Quarter Quarter Quarter Released 1
2 1
2 3.
Articulated **
Co-58 C1 80E0
- 0E0
- 0E0 _
9.66E-04 H-3 Ci 8.20E-01
- 0E0
- 0E0 2.38E ~
G-Alpha Ci t'0E0 9.04E-09
- 0E0
- 0E0 g
TOTAL FOR PERIOD Ci 8.20E-01 9.04E-09
- 0E0 2.38E+00
- Zeroes in this table indicate that no ra61oactivity was present above detectable levels.
See Table 2-6 for typical lower limits of detection for gaseous. sample analyses.
- Half lives greater than 8 days.
51
z,.
o q
m no TABLE 2-3c (Page 1 of 2)
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - MIXED MODE January 1, 1989 through June 30, 1989 Site Continuous' Mode Batch Mode Nuclides Unit Quarter Quarter Quarter Quarter Released 1
2 1
2 1.
Fission Gases Ci
^4s-135m Ci
- 0E0
- 0E0
- 0E0 1.72E-04 Kr-85 Ci
- 0E0
- 0E0
- 0E0 2.24E+01 Kr-88 Ci
- 0E0
- 0E0
- 0E0
- 0E0 Xe-133 Ci 2.24E+01 2.63E+01 3.07E-01 2.66E+02 Xe-135 C1 1.13E-02 2.16E-01 6.08E-04 7.82E-03 Ar-41 Ci
- 0E0 1.64E+00 7.04E-02 1.15E+00 Xe-131m Ci
- 0E0 80E0
- 0E0 2.13E+01 Xe-133m Ci
- 0E0
- 0E0 1.09E-03 5.24E-03 TOTAL FOR PERIOD C1 2.24E+01 2.82E+01 3.79E-01 3.11E+02 2.
Iodines 1-131 Ci 1.65E-05 3.40E-07 80E0
- 0E0 1-133 Ci 5.23E-06
- 0E0
- 0E0
- 0E0 TOTAL FOR PERIOD Ci 2.17E-05 3.40E-07
- 0E0
- 0E0 d 7.e r oe s in this table indicate that no radioactivity was present above detectable levels.
See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
52
o TABLE 2-3c (Page 2 of 2)
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - MIXED MODE January 1, 1989 through June 30, 1989 Site Continuous Mode Batch Mode Nuclides
. Unit Quarter Quarter Quarter Quarter Released 1
2~
1 2
3.
Particulate **
Co-58 C1 2.80E-06
- 0E0 8.30E-05 1.06E-03 Co-60 Ci 7.96E-07
- 0E0 2.74E-06 4.51E-06 H-3 Ci 7.16E+02 3.20E+01 2.58E+00 1.19E+01 G-Alpha Ci 5.76E-07 2.80E-07
- 0E0
- 0.E0 Mn-54 Ci 5.84E-07
- 0E0 1.04E-05 3.78E-06 Tc-99m Ci 2.02E-06
- 0E0
- 0E0
- 0E0 Nb-95 Ci
- 0E0
- 0E0 3.90E-06
- 0E0 TOTAL FOR PERIOD Ci 7.16E+02 3.20E+01 2.58E+00 1.19E+01
- Zeroes in this table indicate that no radioactivity was present above detectable levels.
See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
53
j e
i TABLE 2-4a (Page 1 of 2)
]
3 k/
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT j
GASEGUS EFFLUENTS - GROUND RELEASES January 1, 1989 Through June 30, 1989
)
Unit 1
)
Continuous Mode Baten Mode Nuclides Unit Quarter
- Quarter
- Quartet" Quarter
- Released 1
2 1
2 1.
Fission Gases Ci
)
Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci Xe-135m Ci Xe-138 Ci
/~T Xe-133m Ci V
TOTAL FOR PERIOD Ci 2.
)
I-133 Ci TOTAL FOR PERIOD Ci
- No releases during this period,
)
)
1
)
54
1 TABLE 2-4s (Page 2 of 2)
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - GROUND LEVEL January, 1989 Through June 30, 1989 UNIT 1 l
l l
Continuous Mode Batch Mode Nuclides Unit Quarter
- Quarter
- Quarter
- Quarter
- Released l'
2 1
2 3.
Articulates Mn-54' Ci
~~
H-3 C1 Co-58 C1 Co-60 Ci G-Alpha Ci Tc-99m Ci Nb-95 Ci TOTAL FOR PERIOD Ci
- No releases during this period 55
L h
a F-TABLE 2-4b (Page 1 of 2)
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - GROUND RELEASES February 5, 1989 Through June 30, 1989 UNIT 2 Continuous Mode Batch Mode Nuclides Unit Quarter
- Quarter
- Quarter
- Quarter
- Released 1
2 1
2 1.
Fission Gases Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci
.Xe-135m Ci Xe-138 Ci Xe-133m Ci
~
TOTAL FOR PERIOD Ci 2.
Iodines I-131 Ci 1-133 Ci TOTAL FOR PERIOD Ci
- No releases during this period.
56
f-TABLE 2-4b (Page-2 of 2)
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - GROUND LEVEL February 5, 1989 Through June 30, 1989 UNIT 2
. Continuous Mode Batch Mode l
Nuclides Unit Quarter
- Quarter
- Quarter
- Quarter
- Released 1
2 1
-2 3.
Particulate Mn-54 Ci H-3 C1 Co-58 Ci
-Co-60 Ci G-Alpha
_ Ci Tc-99m Ci Nb-95 Ci TOTAL FOR PERIOD Ci
- No releases during this period 57
o
-TABLE 2-4c (Page 1 of 2)
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT-GASEOUS EFFLUENTS - GROUND RELEASES January 1, 1989 through June 30, 1989 Site Continuous Mode Batch Mode Nuclides Unit Quarter
- Quarter
- Quarter
- Quarter
- Released' 1
2 1
2 1.
Fission Gases Ci Kr-85 Ci Kr-88 Ci Xe-133 Ci Xe-135 Ci Ar-41 Ci Xe-131m Ci Xe-133m Ci TOTAL FOR PERIOD Ci 2.
Iodines 1-131 Ci 1-133 Ci 1-135 Ci TOTAL FOR PERIOD 'Ci
- No releases during this period.
58
L
{
TABLE 2-4c (Page 2 of 2)
V0GTLE ELECTRIC GENERATING PLANT h
SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - GROUND RELEASE 1
January 1,-1989 through June 30, 1989 l
Site
' Continuous Mode' Batch Mode Nuclides Unit Quarter
- Quarter
- Quarter
- Quarter
- Released 1
2 1
2 3.
Particulate Co-58 Ci Co-60 Ci H-3 Ci G-Alpha '
Ci Mn-54 Ci Tc-99m Ci Nb-95 Ci TOTAL FOR PERIO,D Cl
- No releases during this period.
59
l' tl
!~
l TABLE 2-5
.V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS-EFFLUENT - DOSE RATES January 1, 1989 Through June 30, 1989 SITE Dose Rates Due to Noble Gases Organ Tech Un!ts Quarter
% of Quarter
% of Spec 1
Tech 2
Tech Limit.
Limit Limit
. 34E-03 T.' Body 500 mrem /yr 4.36E-04 8.72E-05 6.68E-03 Skin 3000 mrem /yr 1.00E-03 3.33E-05 1.67E-02 5.57E-65 Dose Rates Due to Radioiodines, Tritium and Particulate Organ Tech Units Quarter
% of Quarter
% of Spec 1
Tech 2
Tech Limit Limit Limit Bone 1500 mrem /yr 1.72E-05 1.15E-06 6.00E-05 4.40E-06
~~
Liver 1500 mrem /yr 1/30E-02 8.67E-04 7.72E-04 5.15E-05 T. Body 1500 mrem /yr 1.30E-02*"*"
8.67E-04 7.72E-04 5.15E-05 Thyroid 1500 mrem /yr 1.30E-02 8.67E-04 7.72E-04 5.15E-05 Kidney 1500 mrem /yr 1.30E-02 8.67E-04 7.72E-04 5.15E-05 Lung 1500 mrem /yr 1.30E-02 8.67E-04 7.88E-04 5.25E-05 G1-LLI 1500 mrem /yr 1.30E-02 8.67E-04 7.76E-04 5.17E-05 60
it'C,
- j.,y s
c l-(
.i TABLE 2-6A
^
V0GTLE ELECTRIC GENERATING-PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l
AIR DOSES DUE TO NOBLE GAS' RELEASES T
UNIT 1.
I
^
Type of Tech-Units Quarter
% cf Quart.or
% of Radiation.
Spec Tech Tech Limit 1-Liuit 2
Limit 1
Gamma 5.0
~~ died 1.28E-d4 2.56E-03 2.14E-04 4127E-03
^
I Beto
~~ 'f0. 0 mrad 3.50E-04' 3.50E D3~
3.59E-04 3.59E-03
% Tech Limit I
Cumulative Doses Per Year (Year to Date)
Gamma 10.0 mrad
~3.42E-04 3.42E-03 Beta 20.0 mrad 3.13E-04 3.57E-D3 1
61
r,.,,
g.
.a YN
.t l t '..
i p.
- 1. >:
).
TABLE 2-6b
'~
V0GtLE ELECTRIC GENERATING PLANT SEMIANNUAL RADI0 ACTIVE EFFI,UENT RELEASE REP.0RT.
AIR DOSES DUE TO NOBLE GAS RELEASES February 5, 1989 Through June 30, 1989 UNIT 2 l
l
. Type of Tech Units Quarter
% of Quarter
% of Radiation Spec Tech Tech Limit 1
Limit 2
Limit Gamma 5.0 mrad OE-0 0.E0 1.75E-03 3.50E-02
'~
Beta 10.0 mrad OE-0 0.E0 5.29E-03 5.29E-02 I
' Cumulative Doses Per. Year (Year to Date)
Gamma 10a0 mrad 1.75E-03 le75E-02 Beta 20.0 mrad 5.29E-03 2.65E-02 i
l l
l I
ca
)I ;,.1, i,
t TABLE 2-7A V0GTLE ELECTRIC GENERATING PLANT SEM2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RAD 1010 DINE, TRITIUM L
AND PARTICULATE IN GASEOUS RELEASES January 1, 1989 Through June-30, 1989 UNIT =1 l~
. Cumulative Dose Per Quart </
l Organ Tech Unite Quarter
% of Quarter
% of L
Spec Tech Tech l
Limit 1
Limit 2
Limit Bone 7.5 mrem 4.30E-06 5773E-05 4.89E-06 6.52E-05 Liver 7.5 mrem 3.25E-03 4.33E-02 1.93E-04 2.57E-03 T.
Body 7.5 mrem 3.25E-03 4.33E-02 1.93E-04 2.57E-03 Thyroid
- 7. 5 mrem 3.2SE-03 4.33E-02 1.93E-04 2.57E-03 Kidney 7.5 mrem 3.25E-03 4.33E 1.93E-04 2.57E-03 Lung 7.5 mrem 3.25E-03 4.33E-02 1.97E-04 2.62E-03 GI-LLI 7.5 mrem 3.25E<03 4.33E-02 1.9fE-04 2.57E-03 Cumulative Dose Per Year Organ Tech Units Year to Date
% of Tech Spec Limit Spec Limit Bone 15.0 mrem 9.19E-06 6.13E-d5 Liver 15.0 mrem 4.35L-02 2.89E-01 T.
Body 15.0 mrem 4.35E-02 2.89E-01 Thy roid 15.0 mrem 4.35E-02 2.89E-01 Kidney 15.0 mrem 4.35E-02 2.89E-01 Lung 15.0 mrem 4.35E-02 2.89E-01
~
GI-LLI 15.0 mrem 4.35E-02 2.89E-01 63 4
_ n _.
i:
,,, !i )
TABLE 2-7b V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIOUAL DOSES DUE TO RADI0 IODINE, TRITIUM AND PARTICULA 1'ES IN GASEOUS REJEASES February 5, 1989 Through June 30, 1989 UNIT 2 Cumniative Dose Per' Quarter Organ Tech Units Quarter
% of Quarter
% of Spec Tech Tech Lim i t. -
1 Limit 2
Limit Bune 7.5 mrem 1.01E-11 1.35E-10 1.16E-05 1.55E-04 Liver 7.5 mrem 3.71E-06 4.95E-05 2.23E-05 2.97E-04 T.
Body 7.5 miem 3.71E-06 4.95E-U3
^2.23E-05 2.97E-u4 TEyroid
- 7. 5 mrem 3.71E-06 4.95E-05 2.23E-05 2.97E-04 Kidney 7.5 mrem 3.71E-06 4.95E-05 2.23E-05 2.97I-04 Edug 7 S urem 3.71E-06 4.95E'-05 2.66E-05~
3.55E-04 GI-LLI 7.5 mrem 3.71E-06 4.95E-05 2.Z4E-03 Z.9/E-U4 Cumulative Dose'Per Year Organ Tech Units Year to Date
% of Tech Spec Limit Spec Limit hone 15.0 erem 1.16E-05 7.73E-05 Liver-15.0 mrem 2.60E-05 I.73E-04 T.
Body 15.0 mrem 2.60E-05 1.73E-04 Thytold 15.0 mrem 2.60E-05 1.73E-04 Kidney
'15.3 mrem 2.60E-05 1.73E-04 lung 15.0 mrem 3.03E-05 2.02E-04
~~
GI-LLI 15.0 mrem 2.01E-05 1.74E-0%~~
l h
)
64
,--n--
)
L on Ag TABLE 2-8 LOWER' LIMITS'0F DETECTION - GASECUS SAMPLE ANALYSES I
v0GTLE ELECTRIC GENERATING PLANT January 1, 1989 - June 30, 1989 The values in this table represent apriori lower limits of detection (LLD) which are typically achieved in laboratory' analyses of gaseous radwaste samples.
i RADIONUCL1DE LLD UN 21_S l
Kr-87 1.03E-07 uCi/mi Kr-88 4.77E-08 uCi/mi Xe-133 2.47E-08 uCi/mi Xe-133m 7.63E-08 uCi/ml 1
Xe-135-1.28E-08 u Ci /m1' Xe-138 7.36E-05 uC1/ml I-131 4.54E-15*
uCi/ml-Mn-54 7.12E-15*
uCi/mi Fu-59 1.664-14*
uCi/ml Co-58 1.23E-14*
uCi/mi Co-60 1.41E-14*
uCi/ml Zn-55 1434E-14*
uCi/ml l
.Mo-99 6.37E-14*
uCi/ml Cs-134 5.52E-15*
uCi/ml Cs-137 1.19E-14*-
uCi/ml Ce-141 6.69E-15*
uC1/ml-Ce-144 3.402-14*
uC1/ml Sr-89 1.00E-13*
aci/mi Sr-90 1.00E-13*
uCi/mi H-3 9.00E-08*
uCi/mi l
Gross Alpha 1.00E-13*
uCi/ml l
- Based on an est:imated sample volume of 5. 7E+08 cc's i
l l
l L
l l
I I
1 1
(
65 l
l J
$.0 Solid Waste f t, 3.1; Regulatory Limit.8/ Technical Specification The Technical Specifications presented in this section are for Unit 1 and' Unit 2 and are stated in part.
3.1.1 Use of Solid Radioactive Waete System iJ" 3,77,3 s'all be solidified or devatered in Radioactive visteG n
accordance with the PROCESS CONTROL PROGRAM to meet shipping sud transportation requirements during transi+, and disposal site requirements when received at the disposal site.
- 3. ?,2 Reporting Requirements 6.8.1.4 The Semi annual Radioactive Effluent Release Reports shall include a
summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit an outlined in Regulatory Guide 1.21,
" Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releabes of Radioactive Materials in Liquid and Gaseous Efflueats from Light-Water-Cooled Nuclear Power Plants",
Revision 1,
June
- 1974, with data summarized on a
quarterly basis following the format of Appendix B thereof. For solid vastes, the format for Table 3 in Appendix B shS11 be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of container ( e. g.., LSA, Type A,
Type B,
Large Quantity) and SOLIDIFICATION agent or absorbent (e.g.,
cement, urea formaldehyde).
3.1.3 Process Control Program (PCP) 6.12.1 The PCP shall be approved by the Commission pr$9r to implementation.
6.12.2 Liceasee - initiated changes to the PCP.
a.
Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made.
1his submittal shall contain:
1.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; 66
+
t P.,
A determination that. the change did not reduce the overall conformance of the solidified waste product to existing criteria for solfd wastes, and 3.
Doci. mentation of the fact that the cha ng e has been reviewed and found acceptable by the PRB.
b.
Shall become effettive upon apprcval by the General Man &ger Nuclear Plant.
i~
For this reporting period there was no revision to the PCP, 3.2 Solid Waste Data Regulatory Guide 1.21, Table 3 is found in this report as Table 3-1, 1
l l'
l 1
67 w_-______
r-
.1 N
1 TABLE 3-1 (Page 1 of 2) l V0GTLE ELECTRIC GENERATING PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID AND IRRADIATED FUEL SHIPMENTS Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel) 1.
Type of Waste Unit 6 month Est. Total Period Error %
a.
Spent resins, 111ter Gludges m3
- 1. bye +01 1.UUE+01 evaporator bottom, etc.
C1 8.56E+00 3
b.
Dry compressible waste, m
4.489E+01 contaminated equipment, etc.
Ci 8.614E-02 4.00E+01 3
c Irradiated components, m
control rod, etc.
Ci 3
^
d.
Other (describe) oily trash m
speedi-dry mix equipment, Ci etc., Solidified oil, CRD filters 2.
Estimate of major nuclide composition (by type of waste)
Isotope Percent Curies a.
Co-58 3.02E+01 2.58E+00 Fe-55 2.44S+01 2.09E+00 All others 4.54t+01 3.89E+00 b.
Co-60 3.75E+01 3.23E-02 Fe-55 2.65E+01 2.28E-02 All others 3.60E+01 3.10E-02
- No solid waste during this report period.
68
7-u 10
. TABLE 3-1 (Page 2 of.2)
+y V0GTLE ELECTRIC' GENERATING PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS ISOTOPE PERCENT CURlES c.
l' d.
All others
- No solid waste during this report period.
3.
Solid Waste Disposition Number of. Shipments Mode of Transportation Destination 3
Tractor Trailer Scientific Ecology Group Oak Ridge, TN 3
Tractor / Shielded Barnwell, SC Cask 4.
Number of Shipments Mode of Transportation Destination 0
N/A N/A i
1 Additional Information Required by Tech Specs j
Shipment Waste Type Shipping Solidification Number Class Container Class Agent RWRS-89--001 A Unstable Strong Tight LSA N/A l
RWRS-89-002 A Unstable Strong Tight LSA N/A J
RWRS-89-003 A Unstable Strong Tight LSA N/A RWS-89-001 A Unstable Steel Limer LSA N/A RWS-89-002 A Unstable Steel Liner LSA N/A RWS-89-003 A Unstable Steel Liner LSA N/A I
NOTE: Vogtle Electric Cenerating Plant performed three shipments j
to Scientific Ecology Group, Inc. in Oak Ridge, Tennessee, during this reporting period.
The waste volume and activity on this report reflect only that volume of waste and activity which was processed and disposed of as radioactive waste at Chem Nuclear System, Inc.,
"arnwell, j
S.C.
facility by Scientific Ecology Group, Inc.
during
]
this reporting period.
69 l
r.
j 4.0 Chnngoo to the Vogtlo Electric Conorating Plant ODCM i-6.8.1.4 Technical Specification 6.8.1.4
- requires, in
- part, that changes to the Offsite Dosa Calculation Manual (ODCM) be reported to the Commission in the next Semiannual Effluent Release Report.
There were no changes to the Vogtle Electric Genercting Plant 0DCM for the period of January 1
through June 30, 1989.
6.13.2 f
l Licensee-initisted changes to the ODCM a.
Shall be submitted to the Commission in the Semianne61 Radioactive Effluent Release Report for the period in which the change (s) was made effective.
The submittsi shall contain:
1.
S uf ficie ntly detailed information to totally support the rationale for the change without benefit of supplemental information.
Informat. ion submitted should consist of a package of those pages of the ODCM to be changed, with each page
- numbered, dated and containing the revision number together with app rop ri s te analyses or evaluation justifyirE the change (s);
2.
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and 3.
Documentation of the fact that the change has been reviewed and found acceptable by the PRB.
b.
Shall become effective upon approval by the I
l Geaeral Manager - Nuclear Plant.
l 3.12.1 The Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.12-1.
Table Notation (1) states in part:
l It is recognized
- that, at
- times, it may not be possible or practicable to continue to obtain sampins of the media of choice at the most desired location or time.
In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions, if available, will be made within 30 days in the Radiological Environmental Monitoring Program given in the ODCM.
l y
70 1
1
l.,
j.
t-l Pursuant to specification 6.13, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and Table for the ODCM reflecting the new location (s),
if
- any, with supporting information identifying the cause of the unavailability of samples for the pathway and justifying the selection of the new location (s) for l
obtaining samples, cr the unavailability. of suitable new locations.
i;',
3.12.2 states in part A Land Use Census shall be conducted.
l The Action Statement for this requirement. states in part:
a.
With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the value currently being calculated in specification 4.11.2.3, pursuant to specification 6.8.1.4, identify the new location (s) in the next Semiarnual Radioactive Effluent Release Report.
}
71
lc 'j,
- A D.
J w:
U :-
' n o the Radiological Environmental Monitoring 4.1_
Changes-i Program For ~ this semiannual. period, there has been no. change s
to the Radiological Environmental' Monitoring Program.
5.0 Doses'to Members of.the Public inside the Site Boundary 6.8.1.4 states in part:
l!
This same report shall also include assessment - of the.
radiation doses'. f rom radioactive liquid "and. gaseous effluents
.to MEMBERS OF THE-PUBLIC due
.to thei'r activities inside-the Site ' Boundary (Figure >5.1-1) during the report period.
All assumptions used in.
making these. assessments, i.e.,
specific
- activity, exposure' time,'and location'shall be included in these reports.'
The locations of concern within th'e site boundary are the Visitors Center and Plant' Wilson.
The activities at the Visitor-Center consists-of the occasional attendance at-meetings.and/or short visits for inf ormat ional purposes. The activity at Plant Wilson consists 'of regular employment.
There will be no radiacion dose at these - locations due to radioactive-liquid effluents.
Delineated"in Table-5-1 for'each of these locations are' the values of the basic. data assumed in' the dose. assessment due to' radioactive gaseous effluents.
Listed in this table are:
The distances and directions from a point midway between the. center of Unit 1 and the Unit 2 reactors; the dispersion and deposition factors for.any releases from tue plant vent (mixed mode) and from the turbine building (ground level);
and the estimated maximum occupancy factor for an individual and the assumed' age l
group of this individual.
i Not listed in Table 5-1 is the source term.
Listed in Tables'2-4a and 2-4b for the ground level releases and
~
in Tables 2-3a and 2-3b for the mixed mode releases are the noble gases, radioiodines, and particulate with half lives greater than eight days; these are tabulated by radionuclides and by quarter.
The tritium L
releases in units of curies were as follows:
I l
Quarter 1
2 Mixed Mode 7.176E+02 9.560E+00 72
6 o
The maximum doses in units of mrem accumulated by an individual MEMBER OF THE PUBLIC due to their activities inside the site boundary. during the second half of the-year'were assessed to be as follows:
VISITORS CENTER PLANT WILSON Total Body 1.45E-06 1.78E-04 (direct radiation from plume)
Maximum Org,an 8.22E-06 1.09E-03 (Thyroid) - Inhalation and ground plane l
l l
73 lu--_---___
t Table 5-1 JANUARY 1,1989 THROUGH JUNE 30,1989 Basic Data Assumed in Dose assessments TO MEMBERS OF THE PUBLIC Item Visitors center Plant Wilson Distance (meters) 447 1420 Sector SE ESE l
X/Q (sec/m3)
(1) 5.93e-06 9.45e-07 D:pleted X/Q (sec/m3) (1) 5.58e-06 8.34e-07 D/Q (m-2)
(1) 2.28e-08
- 4. 20e -09 X/Q (sec/m3)
(2) 7.12e-07 1.76e-07 D pleted X/Q (sec/m3) (2) 6.74e-07 1.59e-07 D/Q (m-2)
(2) 5.77e-09 2.07e-09 Occupancy factor 0.00046 (4hr/yr) 0.228 (2000 hr/yr)
Age group Child Adult (1) Ground level release (2) Mixed mode release VISITORS CENTER PLANT WILSON Quarter 1 Quarter 2 Total Quarter 1 Quarter 2 Total mrem mrem mrem mrem mrem mrem Total Body 7.60e-08 1.37e-06 1.45e-06 9.28e-06 1.68e-04 1.78e-04 ORGAN DOSE Bone 2.16e-08 7.11e-08 8.27e-08 2.08e-06 1.35e-05 1.56e-05 Liver 8.00e-06 1.72e-07 8.17e-06 1.06e-03 3.09e-05 1.09e-03 TBody 8.00e-06 2.03e-07 8.20e-06 1.06e-03 3.0De-05 1.09e-03 Thyroid 8.00e-06 2.03e-07 8.20e-06 1.06e-03 3.09e-05 1.09e-03 Kidney 8.00e-06 2.03e-07 8.20e-06 1.06e-03 3.09e-05 1.09e 93 Lung 8.00e-06 2.23e-07 8.22e-06 1.06e-03 3.30e-05 1.09e-03 GI 8.00e-06 1.72e-07 8.17e-06 1.06e-03 3.11e-05 1.09e-03 74 l
. g 6.0 Major Changes to Liquid, Gaseous or Solid Radwaste Treatment Systems 6.E.1.4 states in part:
Tne. Semiannual Radioactive Effluent Release Report shall include any major change to
- liquid, gaseous, or solid radwaste treatment systems pursuant to Specification 6.14, 6.14.1 Licensee-initiated major changes to the Radweste Treatment Systems (liquid, gaseous, and solid);
a.
Shall be reported to the Commission in the Semiannual Radiactive Effluent Rolease Report for the period 1a which the evaluation was reviewed by t he - PkB.
The discussion of each change shali contain:
1.
A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; 2.
Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; 3.
A detailed description of equipment, components, and processes involved and interfaces with other plant systems; 4
An evaluation of the
- change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste tnat differ from those previously predicted in the License Application and amendments thereto; 5.
An evaluction of the
- change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those l
previously estimated in the License application I
and amendments thereto; 6.
A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid
- waste, to the actual releases for *he period prior to when the change l
is to be made; 75 1.
C.
l.
l-l 7.
An estimate of. the exposure to plant operating l-personnel as a result of the change; and l
l 8.
Documentation of the fact that the change was reviewed and found acceptable by the PRB.
b.
Shall become effective upon approval by the General Manager Nuclear Plant.
There have been no major changes to the Liquid, Gaseous or Solid Radwaste Treatment Systems during this report period.
7.0 Meteorological Data 6.8.1.4 states in part:
The Semiannual Radioactive Effluent Relaase Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year.
This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of. wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.
The meteorological data is included in Attachment A.
l l
ll' l
l 76
m e
B.O Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 6.8.1.4 states in part that:
The Semiannua7. Radioactive Effluent Release Reports shall niso include the following:
an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected. within the timo rpecified in Specificaticas 3.3.3.9 or
- 3. 3. 3.10 re w;.ec tively.
3.3.3.9 states in part:
The
' radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-9 sha13 be OPERABLE Action b.
statest With less than the minimum number of radioac'tive liquid effluent monitoring instrumentation channels
- operable, take THE ACTION shown in Table 3.3-9.
Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.8.1.4 why this inoperability was not corrected in a timely manner.
3.3.3.10 states in part:
The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE Action b.
states:
With lese than the minimum number of radioactive gaseous effluent monitoring instrumentation channels j
- OPEEABLE, take the ACTION shown in Table 3.3-10.
Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to specification 6.8.1.4 why this inoperability was not corrected in a timely manner.
i 77 l
L
L e
Inoperable Tech Spec monitors are tracked on Limiting Condition of Operation (LCO)
Forms.
The operators declare equipment operable and inoperable and monitors l
are cone.idered inoperable if there are open LCO's for
[
that monitor.
L 8.1.1 LCO 1-89-181 l
l This LCO was written on 3-29-39 because 1RE-12444C reading was fluctuating.
MWO 18901526 addressed the problem by' replacing the detector;
- however, several additional problems were. discovered / caused by the maintenance.
A bed cable, power supply', preamp, and "D"
channel detector were also repaired / replaced.
The channel was returned to service on 4/30/89.
8.1.2 LCO 2-89-182 This LCO was written on 2/10/89 because ~ 2FT-12442 was reading zero.
The flow element ' and transmitter were replaced; bovever, the problem still existed.
After considerable troubleshooting, it was discovered that the-A/D board configuration needed changing.
The channel was returned to service on 3/22/89.
9.0 Tanks Exceeding Curie Content Limits 6.8.1.4 states in part:
The Semiannual Radioactive Effluent Release Reports shall also include the following, and description'of the events leading to liquid holdup tanks or gas storage t'anks exceeding the lirits of specification 3.11.1.* or 3.11.2.6, respectively ".
)
l 78 i
g s-3.11.1.4 The quantitity of radioactive material contained in each outside temporary tank shall be limited to lens than or equal to 10
- Curies, excluding tritium and dissolved or entrained noble gasen.
Action A states; With the quantity of radioactive material in any of the outside temporary tanks exceeding the above limit, immediately snspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank contents to within the limit, and describe the eve nt s:
leading to.
this condition in the next Semiannual Radioactive Effluent Release
- Report, pursuant t o-specification 6.8.1.4.
3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 2E5 curies of noble gases (considered-as Xe-133 equivalent).
Action A stat-es:
With the quantity of radioactive material in any gas decay tank exceeding the above
- limit, immediately suspend all additions of radioactive material to the
- tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contente to within the limit, and describe-the events leading to this condition in the next Semiannual Radioactive Effluent Release
- Report, pursuant to specification 6.8.1.4.
There were no outside temporary liquid tanks for radioactive liquids during this reporting period.
The radioactive material contained in each waste gas decay tank did not exceed 2E5 curies of noble gases (considered no Xe-133 equivalent).
79 J
w iM 7
The quant.itity of radioactive material contained in each outside temporary tank shall' be. limited to less
.than or _ equal to
- 10. Curies, excluding tritium and dissolved or entrained noble gases.
Action A ststes; With the quantity of radioactive material in' any of the outside. temporary. tanks exceeding the above limit, immediately suspend all additions of radioactive-material to the rank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />,. reduce.the tank contents to within the limit, and describe the events leading.to this condition in the. next Semiannual Radioactive Effluent Release
- Report, pursuant to specification 6.8.1.4.
3.11.2.6 The - quantity of radioactivity ' contained in ' each gas decay tank shall be limited to less than or equal to 2E5 curies' of noble gases (considered as - Xe-133 equivalent).
Action A. states:
With the quantity of radioactive material in any gas decay. tank exceeding the above
- limit, immediately suspend all additions of radioactive material to the tank,-
within-48 hours reduce the tank contents to within the limit, and describe' the events leading to this condition in the-next Semiannual Radioactive Effluent Release Report,. pursuant to specification 6.8.1.4.
There were no outside t e m p o ra ry.- liquid tanks for radioactive liquids during this reporting period.
The radioactive material contained in each waste gas decay l
tank did not exceed 2E5 curies of ' noble gases l
(conside. red as Xe-133 equivalent).
1 l
80 l
e
' {
8' e
f ATTACHMENT A.
l
____2_______-
___a
t 1
1 PICKARD, LOWE AND GARRICK, INC.
1615 M STREET. N.W., SUITE 730 WASHINGTON, D.C. 20036 f
(
NEWPORT BEACH, CAlff 0RNIA WASHINGTON, D.C.
TILE PHONI 714 650 8000 TEL1 PHONE 202 659-1122 Tf LECOPliR 714 646-9023 TEL ECOPilR 202 296-0774 l
TELtX 3718953 PLC tRV TEttX 251921 PLC UR July 21, 1989 Mr. Shan Sundaran Georgia Power Company Plant Vogtle Route 2, Box 299A Waynesboro, GA 30830
Dear Shan:
As you reo.uested, enclosed are several attachments related to the meteorological data from Plant Vogtle for the first and second quarters of 1989.
The data used in these tables and figures were generated primarily f rom the on-site micro-processor (DRT) supplemented by strip chart data for two short periods of missing data.
The data quality and recovery rate for the first half of 1989 were very good.
The only instrumentation to malfunction for a significant time period was the 60m wind speed that was out of service for about 4 days in June.
The attachments are as follows:
e.
Data Recovery Percentage for Each Parameter and Composites of Pertinent Parameters.
January 1 - June 30,1989 e.
Wind Roses
- A-1 :
10m Wind Speed and Direction January 1, 1989 throegh June 30, 1989.
- A-2:
10m Wind Speed and Direction January 1,1989 through March 31, 1989.
A-3.
10m Wind Speed and Direction April 1,1989 through June 30,1989.
- B-1:
60m Wind Speed and Direction January 1, 1989 through June 30,1989.
ENGIN![R$. 1PPU[D $CIENTISTS. MANAGEMENT CONSULTANTS
a
..g Mr. Shan Sundaran
. July 21, 1989 Georgia Power Company Page 2 8-2.
60m Wind Speed and Direction January 1,1989 through March 31,1989.
B-3.
60m Wind Speed and Direction April 1,1989 through June 30, 1989, e..Joir.t Frequency Tables of Wind Speed and Direction-10m vs Delta Temperature 60-10m.
- A:
January 1,1989 through June 30, 1989.
- 8:
January 1,1989 through March 31, 1989.
C: ' April 1,1989 through June 30, 1989.
e.
Joint Frequency Tabics of Wind Speed and Direction 60a vs Delta Temperature 60-10m.
- A:
Januar;,1,1989 through June 30, 1989.
B:
January 1,1989 through March 31, 1989.
- C:
April 1,1989 through June 30, 1989, e.
Daily and Monthly Rainfall Totals for January 1,1989 through June 30, 1989.
e.
Average of the Daily Maximum and Minimum Temperatures for January 1,1989 through June 30, 1989.
- A:
Ambient Temperature B:
Dew Point Temperature If you have any questions or need additional information, please call.
Very.truly yours, Le PM Mark J. Abrams Attachments I
l l
,1 ATTACHMENT 1.
PERCENT-DATA RECOVERY BY PARAMETER-JANUARY 1, 1989 THROUGH JUNE 30, 1989 Parameter Percent Wind Speed 10m 99.5
' Wind Speed 60m 97.3 Wind Direction 10m 99.4.
Wind Direction 60m 99.5 Delta Temperature 60-10m 98.7 1
Temperature 10m 99.2 Dew Point Temperature 10m 95.6 Precipitation 99.6 Composites Wind. speed and Direction 10m, Delta -Temperature 60-10m 98.6 Wind Speed and Direction 60m, Delta Temperature 60-10m 96.5 I
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- PICKARD, l OWE AND GARRICK, INC.
1615 M STREET. N.W., SUITE 730 WASHINGTON, D.C. 20036 NEWPORT DEACH, CAltf00tNLA WASHINGTON, o.C.
TELEPHONE T14 650-4000
' TELEPHONI 202 659 1122 lf TitECOPit R 784 646 9023 TELECDPitt 202 2964nd l
TELEX 3718953 PLC tav TtttX 251921 PLC Ut 1
July 21, 1989-Mr. Shan Sundaran Georgia Power Company Plant Vogtle Route 2, Box 299A Waynesboro, GA 30830
Dear Shan:
As you requested, enclosed are several attachments related to the meteorological data from Plant Vogtle for the first and second quarters of 1989. The data used in these tables and figures were generated primarily f rom the on-site micro-processor (DRT) supplemented by strip chart data for two short periods of missing data.
The data quality and recovery rate for the first half of 1989 were very good. The only instrumentation to malfunction for a significant time period was the 60m wind speed that was out of service for about 4 days in June.
The attachments are as follows:
e.
Data Recovery Percentage for Each Parameter and Composites of Pertinent Parameters. January 1 - June 30,1989 e.
Wind Roses A-1:
10m Wind Speed and Direction January 1, 1989 through June 30,1989.
- A-2:
10m Wind Speed and Direction January 1, 1989 through March 31,1989.
- ' A-3.
10m Wind Speed and Direction April 1,1989 through June 30,1989.
B-1 :
60m Wind Speed and Direction January 1, 1989 through June 30,1989.
MANAGEMINT con 1ULTANT$
APPLi[D $CtfNTISTS INGIN!!R$
e
U I
Mr. Shan-Shndaran July 21, 1989 Georgia Power Company Page 2 o
l B-2, 60m Wind Speed and Direction January 1, 1989 through March 31,1989.
B-3, 60m Wind Speed and Direction' April 1, 1989 through June 30, 1989.
e-.
Joint Frequency Tables of Wind Speed and Direction 10m vs Delta Temperature 60-10m.
~ A:
January 1,1989 through June 30, 1989.
- B:
January 1,1989 through March 31,1989.
C:
April 1, 1989 through June 30, 1989.
e.
Joint Frequency Tables of Wind Speed and Direction 60m vs Delta. Temperature 60-10m.
A:
January 1,1989 through June 30, 1989.
B:
January 1,1989 through March 31, 1989.
C:
April 1, 1989 through June 30, 1983.
e.
Daily and Monthly Rainfall Totals for January 1, 1989 through June 30, 1989.-
e.
Average of the Daily Maximum and Minimum Temperatures for January 1, 1989 through June 30, 1989.
- A:
Ambient Temperature 8:
Dew Point Temperature If you have any questions or need additional information, please call.
Very truly yours, L.
L,
/7%)
Mark J. Abrams Attachments i
il.: *
' ATTACHMENT 1.
PERCENT DATA RECOVERY BY PARAMETER JANUARY 1, 1989'THROUGH JUNE 30, 1989-Parameter Percent Wind Speed 10m 99.5 Wind Speed 60m 97.3 Wind Direction 10m:
99.4 Wind Direction 60m 99.5 Delta Temperature 60-10m 98.7 Temperature 10m 99.2 Dew Point-Temperature'10m 95.6 Precipitation 99.6 Composites Wind Speed and Direction 10m, Delta Temperature 60-10m 98.6 Wind Speed and Direction 60m, Delta Temperature 60-10m 96.5 l
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