ELV-01369, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989
| ML20012B383 | |
| Person / Time | |
|---|---|
| Site: | Vogtle |
| Issue date: | 12/31/1989 |
| From: | Hairston W GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ELV-01369, ELV-1369, NUDOCS 9003140300 | |
| Download: ML20012B383 (158) | |
Text
.
Georo e Power Company
- 33) he:)mont Aense Atlanta Geava 30338 letphore 404 526 3195 flang feess 40 inwmet.s Conan Pwtway Post Oftce Dus 1295 Dirm.t9has Atabrr.b 35201 Telop+m* 2D5 06B 55B1 twma*.em eu !x nsem W. G. Hairston, til Sene Vice Prepount noce t, peat,o"$
ELV 01369 February 28, 1990 Docket Nos. 50 424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 Gentlemen:
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADI0 ACTIVE EFFLVENT RELEASE REPORT in accordance with requirements of the Vogtle Electric Generating Plant Unit I and Unit 2 Technical Specifications, Section 6.8.1.4, please find enclosed the Semiannual Radioactive Effluent Release Report for July 1,1989 through December 31, 1989.
Six copies are provided for your use. Two copies of this report are being provided to the NRC Region 11 office.
Sincerel,
fGt W. G. Hairston, 111 WGH/DMH:db Enclosure 799 9003140300 991231 gDR ADOCK 05000424 PNU:
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l' U. S. Nuclear Regulatory Commission ELV-01369 Page 2 cc:
Georaia Power Company Mr. '. K. McCoy r
Mr. G. Bockhold, Jr.
Mr. R. M. Odom Mr. W. R. Woodall, Jr.
Mr. P. D. Rushton i
Norms l
U. S. Nuclear Reaulatory Commission Mr. S. D. Ebneter, Regional Administrator Mr. D. B. Matthews, Director, Project Directorate !!-3 Mr. R. F. Aiello, Senior Resident Inspector, Vogtle State of Georaia Mr. J. Setser, DNR American Nuclear Insurerg Mr. L. Cross 799 I
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F V0GTLE ELECTRIC GENERATING PLANT 4
SEMIANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES
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SECTION TITLE PAGE 1.0 Liquid Effluents 6
1.1 Regulatory Limits / Technical Specifications 6
1.1.1 Effluent Radiation Monitoring System 6
1.1.2 Concentration Limits 6
1.'1. 3 Dase Limits 6
1.1.4 Liquid Processing 7
l 1.1.5 Outside Temporary Tanks 7
1.1.6 Reporting of Semiannual, Releases (Unplanned) 7.
- 1.2 Maximum Permissible Concentrations 11' i
. 1.3 Measurements and Approximations of Total 11 i
Radioactivity l
1.4 Liquid Effluent Release Data 13 1.4.1 Methodology 13
- 1. 4. 2 -
Batch Release Data 15 1.5 Radiological Impact on Man Due to Liquid 15
/
Release
- 1,6 Abnormal Releases 15 1.7' River Flow-16 2.0 Gaseous' Effluents 29 2.1 Regulatory Limits / Technical Specifications 29 i
'2.1.1 Process Effluent Monitoring System 29 2'.l.2 Dose Rate Limit 29 2.1.3 Air Dose Due to Noble Gas 29 2.1.4 Dose to Any Organ 30
- 2.1.5 Ventilation Exhaust Treatment System and 30 Gaseous Waste Processing System i
s 1
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.SECTION TITLE PAGE f
it.1.6 Explosive Gas Mixture 31 y
2.1.7 Activity In Gas: Decay Tanks 31 2.1. 8.
Total Fuel Cycle Dose Commitment.
31 I
'2.1.9 Reporting of Semiannual Releases (Unplanned) 32
[
2.2 Release Points of Gaseous Effluents 37 2.3 Sample Collection and Analysis 37 2.4 Determination of Total Quantities of 38 Radioactivity, Dose kates and Cumulative Doses I
2.4.1 F1.asion and Activation Gas 39 2.4.2' Radioiodine,' Tritium and Particulate 39 Released 2.4.3 Gross Alpha Release 40 2.5 Gaseous Effluent Release Data 40 2.S.1 Methodology 41 s-2.5.2 Gaseous Batch Data 42 2.6 Radiological Impact Due to Gaseous Roleases 43 l
3.0 Solid Waste 65' i
3.1 Regulatory Limits / Technical Specifications 65 i
- 3.1. 3 '
Use of Solid Radioactive Waste System 65 3.1.2 Reporting Requirements 65 j
13.1.3 Process Control Program (PCP) 65 e
- 3. 2.
Solid Waste Data 66-
'4.0 Changes to the Vogtle Electric 69 Generating Plant ODCM E
4.1 Changia in the Radiological Environmental 71 Monitoring Program i
5.0 Doses to Members of the Public Inside 71 EE The Site Boundary E
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SECTION TITLE EME I
6.0.
Major Chan9es to the Liquid, Gaseous and Solid Radwaste Treatment Systems 74 7.0' Meteorology 75 8.0 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 76 i
9.0 Tanks Exceeding Curie Content Limits 77-10.0 Changes to the Previous Semiannual Effluent 78 Reports 11.0 40 CFR Part 190 Assessment 78 Attachment A Meteorological Data 79-140 Attachment B Correction to 1987 Liquid Effluent Data 141-146 Table 1-2a 1987 - 1st Period Table 1-3a 1987 - 1st Period Table 1-4a 1987.- 1st Period Table 1-la 1987 - 2nd Period Table 1-3a 1987 -- 2nd Period Table 1-4a 1987 - 2nd Period Attachment C Correction to 1988 Liquid Effluent Data 147-152.
Table 1-2a 1988 - 1st Period Table 1-3a 1988 - 1st Period Table 1-4a 1988 - 1st Period Table 1-2a 1988 2nd Period.
Table 1-3a 1988 - 2nd Period Table 1-4a 1988 - 2nd Period 1412A' r
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1 7 V0GTLE ELECTRIC ~ GENERATING PLANT-g, D
f SEMIANNUAL' REPORT pq r
s RADI0 ACTIVE ~ EFFLUENT" RELEASE REPORT p
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' LIST OF' TABLES hJ TABLE' LISTLOF TABLES-PAGE' 4
1-1/
Technical Specification Table 3.3 I;
. Radioactive Liquid Effluent Monitoring Instrumentation 8.
J1-2a Liquid Effluents - Summation of;All Releases Unit 1 17
- 2b.
Liquid Effluents - Summation'of All-Releases
= Unit 2 18
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- 1-2c1 Liquid Effluents - Summation of All Releases L
Site 19 1-3a Liquid. Effluents - Unit 1-20 1-3b
' Liquid Effluents - Unit 2 21 1-3c
. Liquid Effluents - Site ~
22 1
h L1-4a Individuals' Doses-Due to Liquid Releases' L
' Unit,1 23:
'.1-4b Individuals Doses-Due to Liquid Releases Unit 2-24-g 1 Lower. Limits of Detection ~ = Liquid Sample
' Analysis-
- 25'
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1-6a Batch Release Summary of All-Releases -
Unit'l 27 e
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. -- 6b Batch Release Summary of All Releases -
Unit 2
- 28
'2-1 Technical Specification Table 3.3.10 N.
Radioactive Gaseous Effluent' Monitoring Instrumentation 33 2-2a.
Gaseous Effluents - Summation of All Releases Unit 1 44 m
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- TABLE LIST;0F-TABLES
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= Gaseous Effluents --Summation.of All Releases' l
2 -
Unit 2 45:
<2-2c Gaseous Effluents - Summation of All Releases L
Site:
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L 2-3a Gaseous Ef fluents - Mixed Mode: Releases
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Unit 1
'47
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"2-3b' Gaseous Effluents - Mixed Mode Releases i)
- Unit 2'
- 49 t-
- d 3c Gaseous 1 Effluents - Mixed Mode Releases Site.
51 4a Gaseous-Effluents - Ground Level Release - Unit 1 53-2-4b.
' Gaseous Effluents - Ground Levei Release-- Unit 2 55-2-4cn Gaseous Effluents - Ground Level Releases-Site'57 2-5 Gaseous Effluents - Dose Rates Site
'59J i
2-6a Air' Doses:Due to Noble Gases Unit 1 60 2-6b-
. Air. Doses Due to Noble Gases Unit 2 611 2-7a Individual Doses Duc-to Radioiodine,
-Tritium,'and1Particulates in Gaseous Releases - Unit l' 62 2-7b' Individual ~ Doses Due to Radioiodine,
- Tritium, and: Particulates in ' Gaseous Releases -: Unit 2
'63 2-8 Lower Limits of' Detection
-Gaseous Sample-
. Analyses
.64 3 -l '
Solid Waste and Irradiated Fuel Shipments 67 g
15-l' Basic Data. Assumed in Dose Assessments to Members of-the Public 73
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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 I
i 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 limits of Specification 3.11.1.1 are not exceeded.
The ALARM / TRIP Setpoints of these' channels shall be_ determined and i
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 s
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 mrems to any organ, and b.
During any calendar year to less than or equal to'3 mrems to the whole body and to less than or equal to 10 mrems to any organ.
6 i
1.1 '. 4 Liquid Processing 3.11.1.3 The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases-of radioactivity when the projected doses due_to the liquid effluent, from each unit, 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.
1.1.5 Outside Temporary Tanks 3.11.1.4-The quantity 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.
1.1.6 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 gaseous and liquid effluents made'during the reporting period.
7
7 TABLE 1-1 (FROM TECHNICAL SPECIFICATIONS)
(TABLE 3.3-9) s RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION
- 1. -
Radioactivity Monitors Providing Alarm and Automatic Termination of Release a.
Liquid Radwaste Effluent Line 1
37 (RE-0018) b.
Steam Generator Blowdown Effluent 1
38 (RE-0021)
Line c.
Turbine Bldg.-(Floor Drains) Sumps 1
38 Effluent Line (RE-0848) 2.
~ Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release a.
Nuclear Service Cooling Water 1
39 System Effluent Line (RE-0020A & B) q 3.
Flow Rate' Measurement Devices a.
LiquidfRadwaste Effluent Line 1
40 (PT-0018) b.
Steam Generator Blowdown 1
'40 Effluent Line (FT-0021) c.
Flow to Blowdown Sump 1
40 (AFQI-7620, FR-7620, pen-1)
(common) 6 8
x TABLE 1-1 (CONTINUED)
ACTION' STATEMENTS s
- ACTION 37 With the number of channels OPERABLE less than required by the: Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:
a.
At least two 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 via this pathway.
-ACTION 38 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 analyzed for radioactivity-i 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 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
l L
ACTION 39 With the number of channels OPERABLE less than p
required by the Minimum Channels OPERABLE requirement, 1
effluent releases via this pathway may continue j
p r,ovided 'tha t, 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 L
samplea are collected and analyzed for-radioactivity I
at a lower limit of detection of no more than 1E-07 microcurie /ml.
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I LACTIONJ40 With the number of channels OPERABLE lessthan required lby 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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- 1. 2 '
Maximum Permissible' Concentration MPC values used in determining allowable liquid radwaste f
release' rates and: concentrations for principal gamma emitters, I-131, tritium, Sr-89, Sr-90, and Fe-55 are taken from 10 CFR Part ~20 Appendix B.
Table II, Column 2.
For dissolved or entrained-noble gases in liquid radwaste, the MPC is obtained from Technical Specifications 3.11.1.1 as 2E-04 uCi/m1,' total activity b
For gross alpha in liquid radwaste, the MPC is obtained from-10 CFR Part-20, Appendix B, Note 2.d as 3.0E-08 uCi/ml.
Further, for all the above radionuclides or categories of-
-radioactivity, the overall MPC fraction is determined in accordance with 10 CFR Part 20, Appendix B,-Note 1.
?
The method whereby the MPC fraction is used to determine release rates and liquid radwaste effluent radiation monitor setpoints is-described in Subsection 1.4 of this report.
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 dissolved and entrained noble gases by gamma spectrometry.
Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample taken from tanks'which are released.
Liquid radwaste sample analyses are performed as
-follows:
y MEASUREMENT FREQUENCY METHOD L
.1.
-Gamma Isotopic Each Batch Gamma Spectroscopy H
with. computerized data reduction t-2.
Dissolved or entrained Each batch Gamma Spectroscopy L
noble gases with computerized p-data reduction 1;,
L 3.
Tritium Monthly Distillation and l
Composite liquid scintillation counting l
14.
Gross Alpha Monthly Gas flow proportional Composite counting l
11 i
e
' MEASUREMENT FREQUENCY METHOD w'
^
5.
.Sr-89 and Sr-90 Quarterly Chemical separation Composite and gas flow proportional or scintillation counting 6.
Fe-55 Quarterly Chemical separation Composite and liquid scintillation counting Gamma isotopic measurements are performed in-house in the radiochemistry lab using germanium spectrometry.
This consists of
-four high purity germanium detectors with resolution of 1.80 kev or lower._
The'_ detectors are shielded by four inches of lead.
A liquid radwaste sample'is poured into a. graduated cylinder to measure out one liter oftsample which is then poured into a bottle or into a 1 liter marinelli in preparation for a 2000-4000 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 p
' performed.
The procedure ensures that the LLD's are met for the nuclides specified in Table Notation 3 of Technical Specification
. Table 4.11-1: Mn-54, Fe-59, Co-58, co-60, Zn-65, Mo-99, Cs-134,
'Cs-137, Cc-141 and Ce-144.
The quantitative calculations, corrections for counting time, decay' time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio, and MDA p
calculations, are made based on the counts at the location on the.
spectrum where the peak for that radionuclide-would be located, if
.present.
Tritium, Gross Alpha, Sr-89, Sr-90 and Fe-55 are, in some cases, iperformed off-site rather than in-house to more efficiently use plant technicians.
The;radionuclide concentrations determined by-8amma spectroscopic analysis of a sample taken from a tank planned for release and the most current sample analysis results available for tritium, gross alpha, Sr-89, Sr-90 and Fe-55 are used along with'the corresponding MPCl values _to determine a MPC fraction for the tank planned for release.
This MPC fraction is then used, with appropriate safety o
factors, along with the-minimum assured dilution stream flow to calculate: maximum permissible release rate and a liquid effluent
! monitor setpoint.
The monitor setpoint is calculated to assure that the limits of Technical Specification 3.11.1.1 are not exceeded.
A monitor reading in excess of the calculated setpoint results in an automaticLtermination of the liquid radwaste discharge.
Liquid effluent discharge is also automatically terminated if the dilution l
stream flow rate falls below the minimum assured dilution flow rate used in the setpoint calculations and established as a setpoint on the
. dilution stream. flow monitor.
12
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Radionuclide concentrations, safety factors,' dilution stream flow rate, and liquid effluent radiation monitor calibrations are entered' k
into the-computer-and a pre-release printout is generated.
If the g
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 at.d 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-ge ne ra te d.-
The post-release printout contains actual release rates, 1 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,
Tables 1-2b and 1-3b for Unit 2.
1.4.1 Methodology t
.The values for the four categories 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-
-radionuclide activities.
This sum is'for each batch released to the river for the respective quarter.-
i
'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 entrained gases Concentrations of dissolved and entrained gases in liquid effluents are measured by germanium spectroscopy on each one 7
liter sample for each liquid radwaste batch.
Radioisotopes of-iodine in any form are also-determined during the isotopic analysis for each batch; therefore, a separate analysis for possible forms is not performed because it would not
.provideagaseous ditional information 13 i
7-,
bp i,
k
~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 effluent measurement will. include the cumulative errors resulting from the total. operation of sampling and measurement.
Because it.may be_very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of. error 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,
-l sample'and tank flow rates.
j 1.4.1.5.1 Fission and activation total release was calculated from
~
sample analysis results and release point flow rates.
]
j Sampling and statistical error-10%
Counting Equipment Calibration 10%-
Tank Volumes and System Flow Rates 20%
TOTAL ERROR TOT l'.4.1.5.2 Total tritium release was calculated from sample analysis results and release. point' volumes.
Tank volumes and system flow rate 20%
i Sampling and. statistical errors 10%
i Counting equipment calibration 10%
TOTAL ERROR IDY 1.4.1.5.3 Dissolved and entrained gases were calculated from sample analysis results and release point volumes.
L Tank Volumes and system flow rate 20%
. Sampling and statistical error 20%
j Counting equipment calibration 10%
j L
TOTAL ERROR 50%
j a
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1.4.1.'5.4 Gross alpha radioactivity was calculated from sample-analysis results and release point volumes.
Tank volumes and system flowrates 20%
Sampling and statistical error 10%
Counting Equipment calibration 10%
Compositing sample error 5%
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 batch releases of radioactive liquid effluent are listed in Table 1-6a for Unit 1, and-Table 1-6b for Unit 2.
1.5 Radiological Impact on Man Due to Liquid Releases l
Doses to an individual due.to radioactivity in liquid l
effluent were calculated in accordance with Technical Specification 3/4.11.1.2 using the methodology presented in i
the Plant Vogtle Offsite Dose Calculation Manual.
Results are presented in Table 1-4a for Unit 1 and 1-4b for Unit 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 1.6.1.1 There was no unplanned release for this report period.
15
- :e p_ p y;;-
p~. '.,
?.
q L:
N
[- '
(
l 1=. 7/
Riyar? Flow.
~
I e z -.
- - 1. - 7_.11 The average. flow' rate of
- the: Savannah River for this Semiannual" Effluent Report pariod-was obtainedlfros;the-g
- Clark Hill 1Das Corp of Engineers Office.
The average
- flow' rate is 7617 cubic feet /sec.
t t
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lt
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F-'
i Tablo 1-20 i
Georgia Power Company Vogtle Electric Generating Plant U-1 SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER e
ALL LIQUID EFFLUENTS UNIT: 1 Starting :
1-Jul-1989 Ending.: 31-Dec-1989
. TYPE 0F EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ~
ERROR %
?
A. FISSION & ACTIVATION PRODUCTS
'1.-TOTAL RELEASE (NOT INCLUDING
~ TRITIUM, GASES, ALPHA)
CURIES 5.812E-02 9.558E-02 40
- 12. AVERAGE DILUTED CONCENTRATION
'DURING PERIOD uCi/ML 1.919E-07
.1.891E-07 3 '. : PERCENT _OF-APPLICABLE LIMIT N/A N/A RB, TRITIUM 11 TOTAL RELEASE CURIES 6.941E+01 1.927E+02 40 s________________________________________________________________________________
- 2, AVERAGE' DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.287E-04 3.803E-04
- 13. PERCENT OF APPLICABLE-N/A N/A
._________________________ LIMIT
- C.-DISSOLVED AND ENTRAINED GASES 1; TOTAL RELEASE'
-CURIES 2.309E-02 2.275E-02 50 L2' AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.610E-08 4.489E-08
- 3.. PERCENT - OF APPLICABLE LIMIT N/A N/A
'D.
GROSS ALPHA RADIOACTIVITY L1.. TOTAL RELEASE CURIES
- 0E0
- 0E0 45 lE. WASTE VOL RELEASED (PRE-DILUTION)
LIT 8.724E+05 2.028E+06 20 F..? VOLUME OF DILUTION WATER USED LIT 3.019E+08 5.034E+08 20
- Z3ross in'this table indicate that no radioactivity was present above detectable ~ levels.'See table 1-5 for typical LLD values for liquid sample analyses.
17
(/
Tablo 1-2b Georgia Power Company Vogtle-Electric Generating Plant U-2 SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL LIQUID EFFLUENTS i
UNIT: 2 Starting :
1-Jul-1989 Ending : 31-Dec-1989 TYPE OF EFFLUENT-UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR'%.
A.
FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM,; GASES, ALPHA)
CURIES 1.007E-02 4.901E-02 40
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.387E-08 6.953E --_----.....-_-___.__--.._ -----_-____ ---._.....-____--_-_-__.---____-_-_...-_.
3.
PERCENT OF APPLICABLE LIMIT N/A N/A
' B.' TRITIUM
- 1. TOTAL RELEASE CURIES 1.152E+02 2.016E+02
- 40
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.730E-04 2.860E-04
- 3.. PERCENT OF. APPLICABLE LIMIT N/A N/A C.
DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 4.615E-03 2.698E 50
'2.m AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.094E-08 3.827E-08 13. PERCENT OF, APPLICABLE LIMIT N/A N/A D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL ~ RELEASE CURIES
- 0EO -
- 0E0 45
>E.
WASTE _VOL' RELEASED (PRE-DILUTION)
LIT 6.188E+05 1.232E+06 20 F. VOLUME OF DILUTION WATER USED.
LIT 4.213E+08 7.036E+08 20
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See table'1-5 for typical LLD for liquid sample analyses.
18 t
O Tablo 1-2C Georgia Power Company Vogtle Electric Generating Plant =
SEMIANNUAL SUMMATION OF ALL. RELEASES BY QUARTER ALL LIQUID EFFLUENTS-SITE Starting :
1-Jul-1989 Ending : 31-Dec-1989 iTYPE.0F EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %
b A.: FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)
CURIES 6.819E-02 1.446E-01 40 2.: AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 9.409E-08 1.195E-07
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A B.. TRITIUM
- 1. TOTAL RELEASE CURIES 1.846E+02 3.943E+02 40
'2.-AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.547E-04 3.258E-04
- 3. PERCENT N/A N/A
-__________'OF APPLICABLE LIMIT
'C.
DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 2.771E-02 4.973E-02 50
- 2. AVERAGE DILUTED CONCENTRATION DURINGl PERIOD uCi/ML 3.823E-08 4.109E-08 3.sPERCENT OF APPLICABLE LIMIT N/A N/A D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL-RELEASE CURIES
- 0E0
- 0E0 45
--___ -_..._-_-_______-. _________-________________-______~__________.. __
,E.LWASTE.VOL RELEASED (PRE-DILUTION)
LIT 1.491E+06 3.260E+06 20 F..
VOLUME OF DILUTION WATER USED LIT 7.232E+08 1.207E+09 20 e:Zoroes in this table indicate that no radioactivity was present above
'dntectable levels. See Table 1-5 for typical LLD for liquid sample analyses 19 w
m e
l Tcblo 1-33 REPORT CA'TEGORY-
- SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES
- TOTALS-FOR EACH NUCLIDE RELEASED, UNIT 1 TYPE OF ACTIVITY
- ALL RADIONUCLIDES
- REPORTING PERIOD
- QUARTER # 3 AND QUARTER # 4 YEAR 1989
-i l* CONTINUOUS RELEASES l
- BATCH RELEASES l
UNIT
- QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l NUCLIDE'
. l l
l l
l r________________________________________________________________________________l ALL NUCLIDES 4_
AG-110M l
CURIES l 0.00E+00 l 0.00E+00 l 3.70E-05 l 0.00E+00 l vBE-7 l
CURIES l 0.00E+00 1 0.00E+00 l 0.00E+00 l 2.74E-04.l CE-144 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.67E-05 l CO-57.
l CURIES l 0.00E+00 l 0.00E+00 l 1.01E-04 l 1.62E-04 l CO l CURIES l 0.00E+00 [ 0.00E+00 l 1.47E-02-l 6.07E-02 l CO-60; l
CURIES l 0.00E+00 l 0.00E+00 l 7.34E-03 l 1.08E-02 l_
CR-51 l
CURIES l 0.00E+00 l 0.00E+00 l 1.24E-03 l 2.52E-03 l-CS-134.
l CURIES l 0.00E+00 l 0.00E+00 l 3.39E-05 l 2.35E-04-l-
<CS-137 l
CURIES l 0.00E+00 l 0.00E+00 l 4.08E-05 l 2.69E-04 l
- FE-55 l
CURIES l 0.00E+00 l 0.00E+00 l 2.57E-02 l 1.10E-02 l~
FE-59 l
CURIES l 0.00E+00 l 0.00E+00 l'1.89E-04 l 4.49E-04 l H-3 l
CURIES' l 0.00E+00 1 0.00E+00 l 6.94E+01 l 1.92E+02.l HF-181 l
CURIES l 0.00E+00 l 0.00E+00 l 1.65E-05 l:5.56E-05 l
>I-131' l
CURIES l 0.00E+00 l 0.00E+00 [ 3.86E-05 1 5.10E-04-l I-133
-l CURIES l 0.00E+00 l 0.00E+00 l 3.46E-06 l.1.17E-04 l.
LA_140 l
CURIES l 0.00E+00 l 0.00E+00 l 6.34E-06 l 0.00E+00 l, MN-34 l
CURIES
[ 0.00E+00 [ 0.00E+00 [ 3.84E-03'l 4.69E-03 l
--NA-24 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.72E-05 -l NB-95 l
CURIES l 0.00E+00 l 0.00E+00'l 1.15E-03 l 2.09E-03.l-NB-97 l
CURIES l 0.00E+00-l 0.00E+00 l 5.89E-05 l 0.00E+00-l.
SB-1251 l
CURIES l 0.00E+00 l1 0.00E+00 l 1.06E-04 j.2.27E-04 l-TC-99M
-l CURIES
-l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.13E-05 l TE-125M l
CURIES
.l 0.00E+00 l 0.00E+00 l-4.59E-04 l 0.00E+00-l TE-132 l
CURIES l 0.00E+00 l 0.00E+00 l 2.78E-08 l 0.00E+00 l XE-133 l
CURIES l 0.00E+00 l 0.00E+00 l 2.27E-02 l
- 2. 25E-02 :l XE-133M l
CURIES l 0.00E+00 1 0.00E+00 l 4.55E-05 l'6.00E-05 l-XE-135' l
CURIES l 0.00E+00 l 0.00E+00.l 3.09E-04 l.1.41E-04 l j,ZN-65 l
CURIES l 0.00E+00 l 0.00E+00 l 9.13E-05 l 2.15E-05_l LZR l CURIES l 0.00E+00 l 0.00E+00 l 6.51E-04 l 1.33E-03-l_
LZR-97 l
CURIES-l 0.00E+00 l 0.00E+00 l 0.00E+00_l 1.33E-06 l G-ALPHA l
CURIES l 0.00E+00 l 0.00E+00 l
- 0E0 l *0EO.
l
' SR-89 l
CURIES l 0.00E+00 l 0.00E+00 l
- 0E0 l *0E0 l
SR-90' l
CURIES l 0.00E+00 l 0.00E+00 l
- 0E0 l *0E0 l
' TOTAL-FOR PERIOD l
CURIES l 0.00E+00 l 0.00E+00 l 6.95E+01 l 1.92E+02 l l 6 Zaroes in this table indicate that no radioactivity was present above d tcctable levels. See Table 1-5 for typical LLD for liquid sample analyses.
20 l.
l Table 1-3b REPORT CATEGORY
- SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES
- TOTALS FOR EACH NUCLIDE RELEASED, UNIT 2 TYPE OF ACTIVITY
- ALL RADIONUCLIDES
. REPORTING PERIOD
- QUARTER # 3 AND QUARTER # 4 YEAR 1989
[* CONTINUOUS RELEASES l
-* BATCH RELEASES l
UNIT
- QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l-NUCLIDE l
l l
l l
l ALL NUCLIDES
~BA-140 l-CURIES l 0.00E+00 l 0.00E+00 l 5.47E-08-l 0.00E+00 l BE-7' l
CURIES l 0.00E+00 l 0.00E+00 l 1.07E-05 l 8.10E-05 l CE-144 i
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.80E-05 l
.CO-57.
l CURIES l 0.00E+00 l 0.00E+00 j 2.45E-06 l 1.11E-04 l CO-58 l
CURIES l 0.00E+00 l 0.00E+00 l 2.45E-03 l 2.38E-02 l CO-60 l
CURIES l 0.00E+00 l 0.00E+00 l 3.03E-04 l 5.80E-03 l CR-51 l
CURIES l 0.00E+00 l 0.00E+00 l 1.40E-03 l 7.70E-03 l
.CS-137 l
CURIES l 0.00E+00 l 0.00E+00 l 2.75E-06 l 0.00E+00 l
.FE-55 l
CURIES l 0.00E+00'l 0.00E+00 l 3.47E-03 l 2.73E-03.l FE-59:
l CURIES l 0.00E+00 l 0.00E+00 l 1.04E-04 l 8.45E-04 l
=H-3 l
CURIES l 0.00E+00 l 0.00E+00 l 1.15E+02 l 2.01E+02 l HF-181 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 4.15E-05 l
>I-131 l
CURIES
-l 0.00E+00 l 0.00E+00 l 9.47E-05 l 1.21E-04 l I-133-
-l CURIES l 0.00E+00 l 0.00E+00 l 8.23E-05 l 3.37E-05 l LA-140 l
CURIES l 0.00E+00 l 0.00E+00 l 1.77E-05 l 6.82E-05-l.
MN-54 l
CURIES
-l 0.00E+00 l 0.00E+00 l 1.60E-04.l 2.07E-03 1 NB-95:
l CURIES l 0.00E+00 l 0.00E+00 l 1.27E-04 l 2.91E-03 l NB-97 l
CURIES l 0.00E+00 l 0.00E+00 l 5.68E-06 l 1.65E-05 l SB-125' l
CURIES l 0.00E+00 l 0.00E+00 l.1.07E-04 l 3.78E-04 l TC-99M1 l
CURIES l 0.00E+00 l.0.00E+00 l 4.40E-06 l 8.80E-06 l TE-125M' l
CURIES l 0.00E+00 l 0.00E+00 l 2.62E-04 l 0.00E+00 l W-187 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 4.36E-05'l XE-1331 _
l CURIES l 0.00E+00 l 0.00E+00 l 3.99E-03 l 2.57E-02 l XE-133M l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 8.10E-05 l XE-135 l-CURIES l 0.00E+00 l 0.00E+00 l'6.24E-04 l 1.18E-03 l
.ZN-65 l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00-l 4.73E-05 l ZR-95 l
CURIES-l 0.00E+00 l 0.00E+00 l 1.12E-04 l 2.01E-03 l
'ZR l CURIES l 0.00E+00-l 0.00E+00 l 0.00E+00 l 2.14E-05 l
'G-ALPHA l
CURIES l 0.00E+00 l 0.00E+00 l
- 0E0 l *0E0 l
SR-89 l
CURIES l 0.00E+00 1 0.00E+00 l
- 0E0 l *0E0 l
l,SR-90 l
CURIES l 0.00E+00-l 0.00E+00 l
- 0E0 l *0E0 l
.TOTALPFOR PERIOD' l
CURIES l 0.00E+00 l 0.00E+00 l 1.15E+02 l 2.01E+02
---__--_---_-_--------------_------_--_--l 6 Z3 roes in this table indicate that no radioactivity was present above
'dttactable' levels. See-Table 1-5 for typical LLD for liquid sample analyses.
1:
21 1.
L l
Tablo 1-3C REPORT CATEGORY
- ' SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES
- TOTALS FOR EACH NUCLIDE RELEASED, UNIT 1 & UNIT 2 TYPE OF ACTIVITY
- ALL RADIONUCLIDES l REPORTING' PERIOD
- ' QUARTER # 3 AND QUARTER # 4 YEAR 1989 l* CONTINUOUS RELEASES l
- BATCH RELEASES l
UNIT
- QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l NUCLIDE l
l l
l l
l
.ALL-NUCLIDES AG-110M l
CURIES l 0.00E+00 l 0.00E+00 l 3.70E-05 l 0.00E+003l AU-198 l
CURIES l 0.00E+00 l 0.00E+00 1 0.00E+00 l 1.30E-05-l
-BA-140 l
CURIES l 0.00E+00 l 0.00E+00 l 5.47E-08 l 0.00E+00 l
'BE-7 l
CURIES l 0.00E+00 l 0.00E+00 l.1.07E-05 l 3.55E-04 l.
..CE-144 l ' CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00.l 3.47E-05 l CO-57 l
CURIES l 0.00E+00 l 0.00E+00 l 1.04E-04 l 2.73E-04 l
'CO-58 l
CURIES l 0.00E+00 l 0.00E+00-l 1.72E-02 l 8.45E-02 l CO-60 l
CURIES l 0.00E+00 l 0.00E+00 l 7.64E-03 l 1.67E-02 l
- CR-51L l
CURIES l 0.00E+00 l 0.00E&OO l 2.64E-03 l 1.02E-02 l CS-134 l
CURIES l 0.00E+00 l 0.00E+00 1 3.39E-05 l 2.35E-04 l-CS-137-l CURIES l 0.00E+00 l 0.00E+00 l 4.36E-05 l 2.69E-04 l FE-55 l
CURIES l 0.00E+00 1 0.00E+00 l 2.92E-02 l 1.37E-02 l FE-59 l
CURIES
.l 0.00E+00 l 0.00E+00 l 2.93E-04 l 1.29E-03 l
'H-3.
l CURIES l 0.00E+00 l 0.00E+00 l 1.84E+02 1 3.93E+02 l LHF-181-
.l CURIES l 0.00E+00 l 0.00E+00 l 1.65E-05 l 9.71E-05 l
-I-131 l
CURIES l 0.00E+00 l 0.00E+00 l 1.33E-04 l 6.31E-04 l,
.I-133 l
CURIES l 0.00E+00 l 0.00E+00 l 8.58E-05 l 1.51E-04 l LA_140:
l CURIES l 0.00E+00 l 0.00E+00 l 2.40E-05 l 6.82E-05 l
.MN-54 l
CURIES l 0.00E+00 l 0.00E+00 l 4.00E-03 l 6.76E-03 l
=NA-24' l
CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.72E-05 l NB-95 l
CURIES l 0.00E+00 1 0.00E+00 l 1.28E-03 l 5.00E-03 l NB-97 l
CURIES l 0.00E+00 l 0.00E+00 l 6.46E-05 l 1.65E-05 l
- SB-125' l
CURIES l 0.00E+00 l 0.00E+00 l 2.13E-04 l 6.05E-04 l SR-92 l
. CURIES l 0.00E+00 l 0.00E+00 l 4.95E-06 l 1.67E-05 j
.TC-99M l
CURIES l 0.00E+00 1 0.00E+00 l 4.40E-06 l 2.01E-05 l
'TE-125M l
CUR 1ES l 0.00E+00 l 0.00E+00 l 7.21E-04 l 0.00E+00 l FTE-132 l
CURIES l 0.00E+00 l 0.00E+00 l.2.78E-08 l 0.00E+00 l XE-133 l
CURIES l 0.00E+00 l 0.00E+00 l 2.67E-02 l 4.82E-02 l XE-133M l
CURIES l 0.00E+00 l 0.00E+00 l 4.55E-05 l 1.41E-04 l XE-135 l
CURIES l 0.00E+00-l 0.00E+00 l 9.33E-04 l 6.88E-03 l ZN-65 l
CURIES l 0.00E+00 l 0.00E+00 l 9.13E-05 l 2.15E-05 l ZR-95' l
CURIES l 0.00E+00 [ 0.00E+00 l 7.63E-04 [ 3.34E-03 l.
JZR-97
.l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 2.27E-05'l W-187 l
CURIES l 0.00E+00 1 0.00E+00 l 0.00E+00 l 4.36E-05 l
.G-ALPHA l
CURIES l 0.00E+00 l 0.00E+00 l
- 0E0 l
- 0E0 l
7SR-89; l
CURIES l 0.00E+00 1 0.00E+00 l
- 0E0 l
- 0EO-l SR-90 l
CURIES l 0.00E+00 1 0.00E+00 l
- 0E0 l
- 0E0 l
3 TOTAL FOR PERIOD l
CURIES l 0.00E+00 l 0.00E+00 l 1.85E+02 l 3.93E+02 l
- ' Zeroes'in this table indicate that no radioactivity was present above Edetectable levels. See Table 1-5 for typical LLD for liquid sample analyses.
22 l
1.________....
TiBLE 1-4A V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT F
INDIVIDUAL DOSES DUE TO LIQUID RELEASES i
. July 1, 1989 Through December 31, 1989 UNIT 1 I
Cumulative Dose Per Quarter Organ-Tech Units Quarter
% of Quarter
% of-Spec Tech Tech Limit 3
Limit 4
Limit Bone 5.0 mrem 9.05E-04 1.81E-02 4.67E-03 9.34E-02 Liver 5.0 mrem 3.89E-03 7.78E-02 1.42E-02 2.84E-0_1_'
T.
Body
- 1. 5 -
mrem 3.12E-03 2.08E-01 1.06E,02 7.08E-01' Thyroid-5.0 mrem 2.32E-03 4.64E-02 3.46E-03 6.92E-02 Kidney-5.0 mrem 2.79E-03 5.58E-02 6.92E-03
- 1. 3 8 E- 01 :-
Lung 5.0 mrem-
-2.58E-03 5.16E-02 5.29E-03 1.06E-01 lGI-LLI 5.0 mrem 6.14E-03 1.23E-01 1.llE-02 2.21E-01
. Cumulative Dose'Per' Year
. Organ.
Tech Units Year to Date
% of Tech Spec Limit Spec Limit Bone 10.0 mrem 1.61E-02 1.61E-01 Liver 10.0' mrem 3.81E-02 3.81E-01 T.
Body 3.0 mrem 2.93E-02 9.77E-01
. Thyroid 10.0 mrem 1.15E 1.15E-01 Kidney 10.0 mrem 1.99E-02
-1.99E-01 Lung 10.0 mrem 1.65E-02 1.65E-01 GI-LLI'
-10.0 mrem -
3.07E-02 3.07E-01 23
_J
_____.___-____----__-_-__--_.___.__-_______-__-________A__---._____---______---
(
~
"1 p
l'
' TABLE 1-4b (1
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE' REPORT-INDIVIDUAL DOSES DUE TO-LIQUID RELEASES July 1, 1989 Through December: 31, 1989 UNIT 2 Cumulative Doce Per Quarter Organ Tech Units Quarter
% of Quarter
%-of.
Spec Tech Tech Limit 3
Limit 4
Limit
' Bone 5.0 mrem 1.13E-04 2.26E-03 1.09E-04 2.17E-03
~~
^
--5.0 mrem 4.02E-03 8.04E-02 6.79E-03 1.36E-01
.1 Liver
~
- T.
Body 1.5 mrem 3.95E-03 2.63E-01 6.62E-03 4.41E Thyroid 5.0 mrem 4 U'JE-03 6.15E-02 6.50E-03 1.30E-01~
Kidney 5.0 mrem 3.97E-03 7.94E-02 6.43E-03 1.29E-01 1
Lung 5.0 mrem 4.04E-03 8.08E-02 6.88E-03 1.38E-01 GI-LLI 5.0 mrem 4.32E-03 8.64E-02 1.12E-02 2.24E-01
-Cumulative-Dose Per Year Organ Tech Units Year to Date 1 of Tech Spec Limit.
Spec Limit Bone 10.0 mrem-1.14E-03 1.14E-02
' Liver 10.0 mrem 1.42E-02 1.42E-01
. T.
Body 3.0 mrem 1.36E-02 4.53E-01 Thyrold 10.0 mrem 1.Z65-02 1.ZbE-01 Kidney 10.0 mrem 1.2SE-02 1.28E-01 Lung 10.0 mrem 1.30E-02 1.30E-01 1r II-LLI 10.0 mrem 1.80E-02 1.80E-01 J
f 24
g, "
~~
~
~
<jf.
y-W r
L<
u TABLE 1-5 (Page 1 of 2)
{,:j LOWER LIMITS OF DETECTION LIQUID SAMPLE ANALYSES ~
V0GTLE ELECTRIC GENERATING PLANT p
k (JULYLic-1989-Through December. 31 -1989)'
g
-- ?Y 4
. The'valuesTin thisLt'able represent 1apriori lower limits of detection-(LLD) which-are typically achieved.in laboratory.analysesHof 1-iquid radwaste samples.
^).'.'
M;.
. RADIONUCLIDE LLD UNITS Mn-54 9.87E-09
-uci/ml
-Fe-59 7.91E uC1/ml.
100 1.12E-08 uCi/ml
.co-60; 1.~03E-08 uCi/ml Zn-65:
2.35E-08 uCi/mi
.1No-99 6.94E-08 uCi/ml:
Cs-134 1.35E-08 uCi/mi-
.Cs-137 1.18E-08 uCi/ml Ce-141-1.73E-08 uC1/ml-
'Ce-144; 7.37E-08
- uCi/mi pf I-131-1.21E-08'
-uci/mi EXe-133 2.93E-08 uci/ml Xe-135 1.05E-08'
.uci/ml
- Fe-551 1.00E-06.
uCi /ml-'
.5.00E-08 uC1/ml1 "Sr-90 7.00E-09 uCi/mi H-3:-
2.00E uCi/ml a.,;
1 Gross Alpha' 7.00E-08 u Ci /ml-5 d
i r s
t
- i s'? -
's l '
f i
25 l
.l m
l 0
Wl 1
An'L '
_0.
TABLE 1-5 (Page 2 of 2)
LOWER LIMITS OF DETECTION - LIQUID SAMPLE ANALYSES V0GTLE ELECTRIC GENERATING PLANT July 1, 1989 Through December 31, 1989 The values in this table represent apriori lower limits of detection (LLD).which are typically achieved in laboratory analyses of liquid radwante samples.
RADIONUCLIDE LLD UNITS Au-198 9.77E-09 uCi/ml Ba-140 4.86E-08 uCi/mi i
- Be-7 8.27E-08 uCi/ml Co 7.46E uCi/mi Cr-51 9.18E-08 uCi/ml Cs-138 5.37E-08 uCi/ml I-133 1.32E-03 uCi/mi I-135 4.59E-08 uCi/ml La-140 8.97E-09 uCi/ml Mn-56 7.32E-08 uCi/mi Na-24 1.35E-08 uCi/ml Nb-95 1.15E-08 uCi/ml Nb-97 1.23E-08.
uCi/mi Np-239; 2.62E-08 uCi/mi Ru-106 5.24E-08 uCi/m1' Sb-122 1.79E-08 uC1/mi Tc-99m 8'93E-09 uCi/mi Te-132-1.01E-08 uCi/mi'
'W-187-4.39E uCi/mi l
Xe-131m 3.57E-07 uCi/mi Xe-133m 7.39E-08 uCi/ml Zr-95 2.37E-08 uC1/mi Zr-97 9.73E-09 uci/mi Sb-124 1.79E-08 uCi/ml
-j 26
']
F l
t i
Table 1-6a Georgia Power Company Vogtle Electric Generating Plant UNIT 1 BATCH RELEASE
SUMMARY
OF ALL RELEASES Starting :
1-Jul-1989 Ending : 31-Dec-1989 4
LIQUID RELEASES NUMBER OF RELEASES 133
-. TOTAL TIME FOR ALL RELEASES :
10592.00 MINUTES MAXIMUM TIME FOR A RELEASE 373.00 MINUTES AVERAGE' TIME FOR A RELEASE 79.64 MINUTES MINIMUM TIME FOR A~ RELEASE 0.00 MINUTES
, AVERAGE STREAM FTOW 71.95 GPM GASEOUS RELEASES NUMBER OF RELEASES' 184 TOTAL TIME FOR ALL~ RELEASES :
26471.00 MINUTES
. MAXIMUM TIME FOR A' RELEASE 5918.00 MINUTES AVERAGE TIME FOR A RELEASE 143.86 MINUTES MINIMUM TIME FOR A RELEASE- :
2.00 MINUTES
\\
.m_____
.m_
__.e____________
M..__..______mm__...___________
- l I
4 l
2 27
m t
a Table 1-6b Georgia Power Company Vogtle Electric Generating Plant UNIT 2 BATCH RELEASE
SUMMARY
OF ALL RELEASES I
Starting 1.Jul.1989 Ending : 31-Dec-1989 l-LIQUID RELEASES
. NUMBER OF RELEASES 108 TOTAL TIME TOR ALL RELEASES :
14662.00 MINUTES.
MAXIMUM TIME FOR A RELEASE 598.00 MINUTES
.AVERh2E TIME FOR A RELEASE 135.76 MINUTES 4%INIMUM TIME FOR A RELEASE 0.00 MINUTES
'AVERACE. STREAM FLOW 31.99 GPM GASEOUS RELEASES NUMBER OF RELEASES 28 TOTAL TIME FOR ALL RELEASES :
22658.00 MINUTES MAXIMUM TIME FOR A RELEASE 8992.00 MINUTES AVERAGE TIME.FOR A RELEASE- :
809.21 MINUTES MINIMUM TIME FOR A RELEASE 10.00 MINUTES 28 ti-
t, i
2.0 Gaseous Effluents REGULATORY LIMITS / TECHNICAL SpF.CIFICATIONS 2.1 I'l The Technical Specifications presented in this section are E
for Unit l'and Unit 2.
The instrumentation required may
~
be found in Table 2-1 of this report.
L L_
2.1.1 Process Effluent Monitoring System i
hu I
I 3.3.3.10 I
L The-radioactive. gaseous effluent monitoring
[
f instrumentation channels shown in Table 3.3-10 shall he OPERABLE with their Alarm / Trip Setpoints set to ensure i
g that the limits of Specifications 3.11.2.la and 3.11.2.5 t
are not. exceeded.
The Alarm / Trip Setpoints of these i
U channels meeting Specification 3.11.2.la shall be y
determined and. adjusted in accordance with the methodology l
and parameters in the ODCM.
i r
l 2.1.2 Dose Rate Limit j
v i
3.11.2.1
]
y The' dose rate due to radioactive materials-released in' gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1 and 5.1-2) shall be
[
limited to the following a.
For noble-gases:
Less than-or equal to 500 mrems/yr h
to the whole body and less than or4 equal to-3000 arems/yr to the skin,_and f
p i
b.
'For Iodine-131, for' Iodine-133, for tritium, and for e-all radionuclides in particulate' form with half-lives i
greater than 8 dayst Less than or equal to 1500 mrems/yr to any organ.
l 2.1.3.
Air Dose Due to Noble Gas j
3.11.2.2 The air dose due to noble gases released in gaseous l
1 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.followingt
.j 1
1 29 b
~y
ca v-I pd J
i i
i a.
During any cala.ndar quarter:
Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and b.
During any calendar years Less than or equal to 10 t
prada for gamma radiation and less than or equal to 20 mrade for beta radiation.
i 2.1.4 Dose to Any Organ 3.11.2.3 r
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 I
effluents released, from each unit, to creas at and beyond the SITE BOUNDARY (sce Figure 5.1-1 and 5.1-2) shall be limited to the following:
a.
During any calendar quarter less than or equal to 7.5 mrems to any organ and, i
b.
During any calendar years Less than or equal to 15 mreme to any organ.
2.1.5 Ventilation Exhaust Treatment System and Gaseous Waste Processing System 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the CASEOUS 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 exceeds a.
0.2 mrad to air from 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.
T 30
{7'S
~
~}
h
!2,1.6 Ebplosivo GOD Mixtura r
3.'11.2.5 The' concentration of oxygen-in the GASEOUS WASTE PROCESSING SYSTEM shall be limited to less than or equal h
to 2%'by volume.whenever_the hydrogen concentration exceeds 4% by volume.
'2.1.7 Activity in Gas Decay Tanks L
3.11.2.6 The quantity of radioactivity contained in~each gas decay l
tank shall be limited to less than or equal to 2.0E5; 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 or dose commitment to any 3
MEMBER OF THE PUBLIC due to releases of radioactivity and l
to radiation from uranium fuel cycle sources shall be i
limited to less than or equal to 25 mrems to the-whole a
body or any-organ, except the_ thyroid, which shall be
(
limited to less than or equal'to 75 mrems.
L APPLICABILITY ACTION:
At all times l
a.
With the calculated' doses'from the release of i
radioactive materials in'11guid 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,
)
or 3.11.2.3b calculations shall be made' including L
direct radiation contributions from the units i
(including outside storage tanks etc.) to determine L
whether the above limits of specification 3.11.4 have j
been exceeded.
6.8.1.4 States in parts' L+
The Semiannual Radioactive Effluent Release Report to be submitted within 60 days ufter January 1 of each year j
shall also include an assessment-of radiation doses to'the.
likely.most exposed MEMBER OF THE PUBLIC from reactor i
releases and other uranium fuel cycle resources within 8 km, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation."
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory
+
Guide 1.109, Rev.
1, October 1977.
31 s
7-
- 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 asterials in.
gaseous and liquid effluents made during the reporting period.
?
VEGP. unplanned releases are described in section 1.6 of this report.
l -
I 2
9 32 L..
7 i
L i
i-TABLE 2-1 (Sheet 1 of 4) f 1
(From Technical Specifications)
(TABLE 3.3-10)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CRANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION
- 1. GASEOUS WASTE PROCESSING
-l
- a. Noble Gas Activity i
Monitor-Providing Alarm and Automatic Termination of Release (ARE-0014) 1 45
- b. Effluent System Flow Rate Measuring Device 1
46 (AFT-0014)
- 2. GASEOUS WASTE PROCESSING SYSTEM - Explosive Gas Monitoring System
- a. Hydrogen Monitor 1/recombiner 50 l
f
- b. Oxygen Monitor 2/recombiner' 49
- 3. CONDENSER AIR EJECTOR AND STEAM PACKING EXKAUSTER SYSTEM
- a. Noble Gas Activity Monitor (RE-12839C) 1 47 j
- b. Iodine Sampler (RE-12839E) 1 5L
- c. Particulate Sampler (RE-12839A) 1 51
- d. Flow Rate Monitor 1
46 (FT-12839) (FIS-12 862) #
- e. Sampler F' low Rate 1
46 Monitor (FI-13211) 33
p-q v
TABLE 2-1 (Sheet 2 of 4)
)
(From Technical Specifications)
(TABLE 3.3-10)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS t
INSTRUMENTS OPERABLE APPLICABILITY ACTION
- 4. PLANT VENT A. Noble Gas Activity Monitor (RE-12442C or RE-12444C) 1 47, 48 b.
Icdine Sampler / Monitor (RE-12442B or RE-124448) 1 51
- c. Particulate Sampler /
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 i
During Emergency Filtration l
o 34 i
r..
..y s.-
(
TABLE 2-1 (Sheet 3 of 4)
(FROM TECHNICAL SPECIFICATONS)
TABLE 3.3-10 ACTION STATEMENTS ACTION 45 With the number of channels OPERABLE 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 releaset i
n.
At least two independent samples of the tank's 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 1
via this pathway.
t ACTION 46 With the numbor 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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.0PERABLE requirement, immediately suspend containment PURGING of radioactive effluents via this pathway, i
6 ACTION'49 a.
With the outlet oxygen 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 the inlet hydrogen monitor is OPERABLE.
35 1
~
L TABLE 2-1 (Sheet 4 of 4)
FROM TECHNICAL SPECIFICATIONS TABLE 3.3-10 TABLE NOTATIONS (Continued) c.
With both oxygen channelsuor 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 and the oxygen concentration remains less than 1 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 taken and analyzed at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during desassing 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 L
continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 1
4.11-2.
L 1l' i
36
n-
,1--
F p.
'2.2 Release Points of Gaseous Effluents P
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 p
gas decay tanks are released through the Unit 1 plant L
vent. Containment purges are released through their respective plant vents.
F 2.3 Sample Collection and Analysis A11'of.the paths can be continuously monitored for gaseous radioactivity.
Each is equipped with an integrated-type sample collection device for collecting particulates and iodines.
Sample collection is in accordance with Technical Specification Table 4.11-2.
During this release period, there were no radioactive releases through the condenser air ejector and steam packing exhauster system vents.
Unless required-more frequently under certain circumstances specified in Table Notations to the,above mentioned tables, samples are collected as follows:
1..
Noble gas samples are collected by grab sampling monthly.
2.
Tritium samples are collected by grab sampling monthly.
3.
Radioiodine samples are collected from the sample stream through a charcoal cartridge over a 7-day period.
4.
Particulates are collected from the sample stream through a particulate filter over a 7-day period.
5.
The 7-day particulate filters above are analyzed for gross alpha activity.
6.
Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the quarterly com is analyzed for Sr-89 and Sr-90,posite sample 37
Batch Waste Gas Decay Tank releases are analyzed for iodines, particulates and noble gases before each release.
In addition, the containment atmosphere is analyzed for tritium on at least a monthly basis.
Sample analyses resulto and release flow rates from the release points form the basis for calculating released quantities of radionuclide specific radioactivity, dose rates associated with gaseous releases and cumulative doses for the current quarter and. year.
This task is normally performed with computer assistance.
The noble gas grab sample and analysis (for principal r
gamma emitters) results are used along with maximum expected release flow rates from each of the vents to calculate monitor setpoints, for the gaseous effluent monitors serving the two release points, to assure-that the limits of Technical Specifications 3.11.2.la are not exceeded.
Calculation of monitor setpoints is described in the Vogtle Electric Generating Plant ODCM.
With each release period and batch release, radioactivity, dose rates and cumulative doses are calculated.
Cumulative dose results are tabulated, along with percent of Technical Specification limits (3.11.2.2 and 3.11.2.3), for each release for the current quarter and 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.
l 2.4 Determination Of Total Quantities of Radioactivity, Dose Rates and Cumulative Doses l
The methods for determining release quantities of L
radioactivity, dose rates and cumulative doses are as L
follows:
l I
38 l
9
~
c
-2.4.1 Fission and Activation Gas The'radionuclide-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 particulates 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 particulates.
Dose rate calculation methodology is presented in the ODCM.
Beta and gamma air doses due to noble gases are calculated for the location in the unrestricted area with.the potential for the highest exposure due to gaseous releases.
Air doses are calculated for each release period and cumulative totals are kept for each unit for the calendar quarter and year.
Cumulative air' doses are compared to the dose limits specified in Technical Specification 3.11.2.2. Current percent of the technical specification limits are shown on the printout for each release period.
Air dose calculation methodology is presented in the ODCM.
2.4.2 Radioiodine, Tritium and Particulate Releases Released quantities of radioiodines are determined from the weekly samples and release flow rates for the two release points.
Radioiodine concentrations are determined by gamma spectroscopy.
Release quantities of.particulates are determined from the weekly (filter) samples and release flow rates for l
the two release points.
Gamma spectroscopy is used to i
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 calculated.
Strontium concentrations are input to the composite file of the computer to be used for release dose race and individual dose calculations.
39
-i
l b
t Tritium samples are obtained monthly from each vent by i
bubbling the sample stream through a water trap.
The tritium concentration in water is converted to tritium L
concentration in air and this value is input into the composite file of the computer to be used in release, dose rate, and individual dose calculations.
Dose rates due to radioiodine, tritium, and l
particulates are calculated for a hypothetical child, exposed to the inhalation pathway, at the location in the unrestricted area where the potential dose rate is expected to be the highest.
Dose rates are calculated for each release point, for each release period, and the total dose rate from both release points are compared to the dose rate limits specified in Technical Specificatioa 3.11.2.lb.
Individual doses due to radioiodine, tritium and particulates are calculated for the critical receptor, which for Vogtle Electric Generating Plant is a child exposed to the inhalation and ground plane pathways.
Individual doses are calculated for each release i
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 printout 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 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
40
i 2.5.1 Methodology Regulatory Guide 1.21 Tables 1A, 1B, and 1C are found l
in this report as Tables 2-2a, 2-2b, 2-3a 2-3b, 2-4a l
and 2-4b.. Data is presented on a quarterly basis as i
required by Regulatory Guide 1.21.
l To complete Table 2-2a and 2-2b, total release for each of the four categories (fission and activation t
gases,-
iodines, particulates, and tritium) was divided by the number of seconds in the quarter to
~
obtain a release rate in uCi/second for each category for each quarter.
However, the percent of the applicable Technical Specification limits are not applicable because we have no curie limits for gaseous releases.
Noble gases are limited as specified in i
3.11.2.la.
The other three categories (tritium, radioiodines, and particulates) 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 1
particulates are presented in Table 2-5 along with percent of technical specification limits.
Gross alpha radioactivity His 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.
Cumulative 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 particulates, are specified in Technical Specification 3.11.2.3.
Cumulative individual doses are presented in Table 2-7a and 2-7b along with percent of technical specification limits.
The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total operation of sampling and measurement.
Because it-may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of er.ror are not suggested.
The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste.
41
p, p
I L
Estimated errors are based on errors in counting o
equipment calibration, counting statistics, vent-flow I,' e '
rates, vent sample flow rates, non-steady release rates, chemical yield factors and sample losses for such items as charcoal cartridges.
9 L
2.5.1.1 Fission and activation total release was calculated from sample analysis results and release point flow rates.
Sampling and statistical error in counting 10%
L Counting equipment calibration 10%
Vent flow rates 10%
t Non-steady release rates 20%
TOTAL ERROR 50%
L
'2.5.1.2 I-131 releases were calculated from each weekly samplet i
Statistical error in counting 10%
Counting equipment calibration 10%
Vent flow rates 10%
Vent sample flow rates 50%
Non-steady release rates 10%
Losses from charcoal cartridges 10%
i TOTAL ERROR 100%
2.5.1.3 Particulates with half lives greater than 8 day releases were calculated from sample analysis results and release point flow rates.
Statistical error at LLD concentration 10%-
Counting equipment calibration 10%
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%
4 V.ent flow rates 10%
Counting calibration and statistics 10%
Non-steady release rates 10%
TOTAL ERROR 40%
2.5.2 Gaseous Batch Data Other data pertinent to batch releases of radioactive gaseous effluent from Unit 1 and Unit 2 are listed in Table 1-6a and 1-6b.
42.
r
'l 50 2.6 Radiological Impact Due to Gaseous Releases Dose rates due to noble gas releases were calculated for the site in accordance with Technical Specification 3/4.11.2.la.
Results are presented in Table 2-5.
Dose rates due to radioiodine, tritium, i
and particulates in gaseous releases were calculated in accordance with Technical Specification 3/4.11.2.lb.
These results are also in Table 2-3.
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 particulates were calculated in accordance with Technical Specification 3/4.11.2.3.
l These results are presented in Tables 2-7a and 2-7b, i
Dose rates and doses were calculated using the methodology presented in the Vogtle Electric Generating Plant Offsite Dose Calculation Manual.
t l
t c
i.
h 43
3,
~m I
Table 2-2a l
1 Georgia Power Company i
Vogtle Electric Generating Plant t
i SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER i
ALL AIRBORNE EFFLUENTS UNIT: 1 Starting :
1-Jul-1989 Ending : 31-Dec-1989 i
TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT l
i ERROR %
3
'A.
FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 3.908E+01 4.761E+01 50 t
- 2. AVERAGE RELEASE RATE FOR PERIOD uC1/Sec 4.916E+00 5.989E+00 3.
PERCENT OF APPLICABLE LIMIT N/A N/A
......_e.................
I B. RADIOIODINES i
- 1. TOTAL IODINE-131 CURIES 2.525E-05 2.843E-05 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.833E-06 3.577E-06
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A C.
PARTICULATES
- 1. PARTICULATES (HALF-LIVES >8 DAYS)
CURIES 0.000E+00 0.000E+00 90 1..__.....................................__.....................................
- 2. AVERAGE RELEASE RATE FOR PERIOD uC1/Sec 0.000E+00 0.000E+00
- 13. PERCENT OF APPLICABLE LIMIT N/A N/A
- 4. CROSS ALPHA RADIOACTIVITY CURIES 4.469E-07 5.942E-07 D. TRITIUM l-.................................__....___...........__.........................
- 1. TOTAL RELEASE CURIES 5.510E+01 5.914E+01 40 1...........................__.................___........__.......____..........
2.' AVERAGE RELEASE RATE FOR PERIOD uC1/Sec 6.932E+00 7.440E+00
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A 1
o ZCrCOs in this table indicate that no radioactivity was present above dOtcetable levels. See Table 2-8 for typical LLD for gaseous sample analyses.
l t.
l 44 l
l
i 1
i Table 2-2b Georgia Power Company Vogtle Electric Generating Plant SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL AIRBORNE EFFLUENTS
- UNIT 2
i Starting i 1-Jul-1989 Ending 31-Dec-1989 TYPE CF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %
i A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 6.289E+01 3.454E+01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uC1/Sec 7.912E+00 4 345E+00 i
3.
PERCENT OF APPLICABLE LIMIT N/A N
c..................................
__........./A B. RADIOIODINES
- 1. TOTAL IODINE-131 CURIES 1.080E-05 7.558E-07 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.358E-06 9.508E-08
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A F
C.
PARTICULATES
- 1. PARTICULATES(HALF-LIVES >8 DAYS)
CURIES 0.000E+00 0.000E+00 90
~
~
~
~
~
~~
~~~~~
~~~
~~~~~~~~~~~
EVEkEbE EELE55E EETE Ebk PEEIbb uci/5ec 35606E+35 6I633E+30 2
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A
- 4. GROSS ALPHA RADIOACTIVITY CURIES 1.701E-08 4.481E-08 I
V D. TRITIUM
- 1. TOTAL RELEASE CURIES 2.150E+01 1.229E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.705E+00 1.547E+00
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A
. 0 Z rces in this table indicate that no radioactivity was present above d;tcctable levels. See Table 2-8 for typical LLD for gaseous sample analyses.
45 b
I Table 2-2c i.
Georgia Power Company Vogtle Electric Generating Plant SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL AIRBORNE EFFLUENTS
- SITE Starting 1-Jul-1989 Ending 31-Dec-1989 LTYPE CF EFFLUENT' UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %
-A.
FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 1.020E+02 8.216E+01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.283E+01 1.034E+01
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A B. RADIOIODINES
- 1. TOTAL IODINE-131 CURIES 3.605E-05 2.919E-05 100
-2,1 AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.535E-06 3.672E-06
'3.
PERCENT OF APPLICABLE LIMIT N/A N/A C.
PARTICULATES
- 1. PARTICULATES(HALF-LIVES >B. DAYS)
CURIES 0.000E+00 0.000E+00 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uci/Sec 0.000E+00 0.000E+00
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A
- 4. GROSS ALPHA RADIOACTIVITY CURIES 4.639E-07 6.390E-07 D. TRITIUM cl. TOTAL RELEASE-CURIES 7.654E+01 7.144E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 9.629E+00 8.987E+00 J.
PERCENT OF APPLICABLE LIMIT N/A N/A 0 ZOro0s in this table indicate that no radioactivity was present above d;tOctable levels. See Table 2-8 for typical LLD for gaseous sample analyses.
L 46 r
n-TABLE 2-3a (Page 1 of 2)
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT REPORT n
GASEOUS EFFLUENTS - MIXED MODE July 1, 1989 Through December 31, 1989 UNIT 1 1
I I
i I
t, Continuous Mode Batch Mode L
Nuclides Unit.
Quarter Quarter Quarter Quarter
{
Released 3
4 3
4 1.
Fission Gases l
Xe-137 Ci
- GEO
- 0E0 5.16E-03
- 0E0 i
Kr-85 Ci
- 0E0
- 0E0 1.52E-01
- 0E0 Xe-133 Ci 2.68E+01 4.22E+01 1.15E+01 4.16E+00 b
Xe-135 Ci
- 0E0 5.68E-01 7.24E-02 1.36E-02 Ar-41 Ci
- 0E0
- 0E0 2.26E-01 5.48E-01 Xe-131m C1 80E0 80E0 1.49E-01 3.14E-02 Xe-133m Ci
- 0E0
- 0E0 8.74E-02 5.68E-02 Kr-85m Ci n0E0 80E0 2.38E-03
- 0E0 TOTAL FOR PERIOD C1 2.68E+01 4.28E+01 1.22E+01 4.81E+00 2.
Iodines 1-131 C1 2.52E-05 2.84E-05
- 0E0
- 0E0 1-133 C1 2.48E-05 4.12E-05 80E0 a0E0 TOTAL FOR PERIOD Ci 5.00E-05 6.96E-05
- 0E0 80E0
- 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.
47 i
f.
-E
'? ; i.
TABLE 2-33 (Pogo 2 of 2)
['
V0GTLE-ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - MIXED MODE
- July 1,.1989 Through December 31, 1989 UNIT 1 r
I Continuous Mode
' Batch Mode-Nuclides-Unit-Quarter Quarter Quarter Quarter Released 3
4 3
4 3.
Particulates**
p-
~
00-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00- 0.00E+00 0.00E+00 H-3 C1 5.50E+01 5.88E+01 4.54E-02 3.44E-01 G-Alpha Ci 4.46E-07 5.94E-07
- 0EO-8
- 0E0 9
' TOTAL FOR PERIOD-Ci 5.50E+01 5.88E+01 4.54E-02 3.44E-01
- Zeroes intthis table indicate'that no-radioactivity was present above
. detectable levels.;
See' Table 2-8-for typical lower-limits of detection Efor gaseous sample analyses.
- LHalf lives-greater than 8 days.
i L
Y 1
1 U
48 L
E __
,o--
(e N
x TABLE 2-3b (Page 1 of 2)
'V0GTLE ELECTRIC GENERATING PLANT
-SEMIANNUAL RADI0 ACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - MIXED MODE
, July'1, 1989 Through December 31, 1989 R
UNIT 2 l
1
?..
L -'
'l F
Continuous Mode
~ Batch Mode.
l
'Nuclides
' Unit Quarter Quarter Quarter Quarter l Released i
3 4
3 4
l'-
l.-Fission Gases-
.]
i t-f Xe-133 Ci 6.14E+01 3.30E+01 6.37E-02 1.27E s b.
' Xe-135
-Ci 9.59E-01 7.04E-01 5.38E-03 1.57E-02 i
p Ar-41 Ci 80E0 n0E0 4.22E-01 7.00E,i p
YUYIL FOR PERIOD Gi 6.24E+01 3.37E+01 4.92E-01 5.43E ;
3 V
l F
i p
2.
lodines p,
p, I-131-Ci 1.08E-05 7.56E-07
- 0EO-
- 0E0-
[N O
I-133 Ci 5.26E *0E0
- 0E0 80E0 i
h TOTAL FOR PERIOD Ci 6.34E-05 7.56E-07
- 0E0
- 0E0 j
i t'
.
- Zeroes in this table indicate that no radioactivity was present' abo've det'ectable' levels.
See Table 2-8 for; typical lower limits of detection a
-for gaseous sample analyses.
=l 1
I i
V
+
49 1
i I
P fu.t
- i
TABLE 2-3b (Page 2 of 2) i V0GTLE ELECTRIC GENERATING PLANT L
SEMIANNUAL RADIOACTIVE EFFLUENT RE{0RT GASEOUS EFFLUENTS - MIXED MODE L
July 1, 1989 Through December 31, 1989 UNIT 2 i
Continuous Mode Batch Mode L
Nuclides Unit Quarter Quarter Quarter Quarter Released 3
4 3
4 3.
Particulates**
-Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Gi 0.00E+00 0.00E+00 0.00E+00 0.00E+00 11 - 3 Ci 2.12E+01 1.19E+01 3.00E-01 3.96E-01 G-Alpha Ci 1.70E-05 4.45E-05 50E0 "0E0 t0TAL FOR PERIOD C1 2.12E+01 1.19E+01 3.00E-01 3.96E-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.
- Italf lives greater than 8 days.
50
c 4
I TABLE 2-3c (Page 1 of 2) c V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT GASEOUS EFFLUENTS - MIXED MODE July 1, 1989 Through December 31, 1989 Site
)
l Continuous Mode Batch Mode Nuclides Unit-Quarter Quarter Quarter Quarter Released 3
4 3
4 1.
Fission Gases Ci Xee137 Ci
- 0E0
- 0E0 5.16E-03
- 0E0
~
Kr-85m Ci
- 0E0 80E0 2.38E-03
- 0E0 Kr-85 Ci
- GEO 80E0 1.52E-01
- 0E0 Xe-133 Ci 8.82E+01 7.52E+01 1.16E+01 4.29E+00
'Xe-135 Ci 9.59E-01 1.27E+00 7.78E-02 2.93E-02 i
Ar-41 Ci
- 0E0
- 0E0 6.48E-01 1.25E+00 Xc-131m Ci
- 0E0
- 0E0 1.49E-01 3.14E-02 l
Xe-133m Ci
- 0E0
- 0E0 8.74E-02 5.68E-02 TOTAL FOR PERIOD-Ci 8.92E+01 7.65E+01 1.27E+01 5.66E+00 2.
Iodines 1-131 C1 3.60E-05 2.92E-05
- 0E0
- 0E0 1-133 Ci 7.66E-05 4.12E-05
- 0E0
- 0E0 TOTAL FOR PERIOD Ci 1.13E-04 7.04E-05
- 0E0
- 0E0 i
- Zeroes in this table indicate that no radioactivity was present above detectable levels.
See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
4 51
h TAB'E 2-3c (P;go.2 of 2)'
f'
.V0GTLE ELECTRIC GENERATING PLANT r!
+
SEMIANNUAL RADIOACTIVE EFFLUENT REPORT-
[
, GASEOUS. EFFLUENTS - MIXED MODE
- July-1, 1989 Through December 31, 1989 l
'h)
Site n.
c
)
Continuous' Mode Batch' Mode Nuclides
- Vnit Quarter Quarter Quarter Quarter' Released-3:
4 3
'4' l
3.,Particulates**
j i
^
~
I'o-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00-Co-60 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
-Mn-54 C1 0.00E+00 0.00E+00-0.00E+00 0.00E+00.
H-3 Ci 7.62E+01 7.07E+01 3.4SE-01 7.40E-01 G-Alpha C1 4.63E 6.39E-07 WQgQ WGEQ l
TOTAL FOR PERIOD Ci 7.62E+01 7.07E+01 3.45E-01 7.40E-01 f'
- Zeroes in.this. table indicate that no radioactivity was present above
~
detectable levels.
See1 Table'2-8 for typical. lower-limits of detection for-gaseoss sample analyses.
!I
- Half lives-greater _than 8 days.
l-t I,.'.*-
o e
LL 52
('
W-y 1
i L-
$Y,;,
l TABLE 2-4a-(Page 1 of 2)
V0GTLE ELECTRIC GENERATING PLANT E
SENIANNUAL RADIOACTIVE EFFLUENT REPORT i
GASEOUS EFFLUENTS - GROUND RELEASES l
j l, July 1 -1989 Through December 31, 1989-l L
UNIT 1 t
I
}
Continuous Mode Batch' Mode.
c, R,
=-Nuclides Unit.
Quarter
- Quarter
- Quarter
- Quarter *-
ie Released-3 4
3
'4
(-
Q.
1; Fission Cases iCi j
r:.
F Kr Ci-D; Kr-85m Ci Kr-87 Ci
[-
Kr Ci-l Xe-133 Ci F
Xe-135 C1
-[
I'
=.Ye-135m C1 Xe-138 Ci.
b Xe-133m C1-n L
o g,
. TOTAL FOR PERIOD Ci b
2.- Iodinea '
g-
[
I-131-Ci hi 1-133 Ci b.
E[
TOTAL'FOR. PERIOD-Ci
[i t
i,
- No'rel' eases during this period.
~
4 e
53
?:
.l x
- h.,. v TABLE 2-4a (Page 2 of'2) p.
g-.;-
L' V0GTLE ELECTRIC GENERATING PLANT
' SEMIANNUAL RADICACTIVE EFFLUENT REPORT GASEOUS: EFFLUENTS --GROUND LEVEL s ")
July 1, 1989 Through December 31, 1989 UNIT 1 w
Continuous Mode'
' Batch Mode
.Nuclides Unit Quarter
- Quarter
- Quarter
- Quarter *
-Released
'3 4
3=
4
,3. Particulates no-
~
(2 Mn~54-Ci Fe Ci
^
L,,
Co-58 ~
Ci h
- Co-60 Ci h
12n-65 Ci
'Sr-89 Ci Sr-90 Ci g
Mo-99 C1 i
l
'Nb-95:
Ci b
Cs-134 Ci 4~
Cs-137-
-Ci-Ba-140-Ci 1:
La-140:
01
- Ce-144-,
C1
-Co-141 Ci 5.,
h TOTAL'FOR' PERIOD Ci' i-Il lNo releases during'this; period
- ~
Y
[s
[**
. Half;1ives greater ~than 8 days l'
[$ i
?!
V
[-- y 6
4 54
- c..
!N y
1,
pp
.]
o f,
pll.
y 7.,. -<.
6
'}
TABLE 2-4b (Page 1 of 2)
V0GTLE ELECTRIC GENERATING' PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT REPORT CASEOUS EFFLUENTS - GROUND RELEASES
~
July-.1:, 1989 Through-December 31, 1989 UNIT 2 t
I
'[
r.
Continuous Mode Batch'Hode'
~ Nuclides Unit 7>
Released'
" Quarter * ~
Quarter
- Quarter *
' Quarter
- 3'
~
4' 3
4-11.-Fission Gases Ci-
.).
Kr-85 Ci Kr-85m Ci Kr Ci Kr-55 Ci Xe-133 Cl-
" Ke-133 ci Xe-l35m Ci Xe-138 Ci
= Xe-133m Ci
, TOT L FOR-PERIOD-Ci 2..lodines
[
1
[
I-131 Ci I-133 Ci I-135 Ci c.
[-
TOTAL.FOR PERIOD Ci l
. *No releases during this period.
l.. :i
,4
't l.
.}
b e
j L
55
'l r.
i
)+
_ j.
b
.i
- D00i[f'+
'D
=
6/
f g ?hl,!K 31 LI a.
1 V+
t 4,
t v-i:
P
[-.
TABLE'2-4b1(Page 2' of 2):
(
I 4
w-f*.
..V0GTLE ELECTRIC GENEPATING PLANT.
[I j
SEMIANNUAL-RADI0 ACTIVE EFFLUENT REPORT
[
GASEOUS' EFFLUENTS -1 GROUND LEVEL f
July--1, 1989.-Through December; 31,11989 UNIT-2 b
V V
c U
i' Continuous: Mode Batch-Mode Nuclides-Unit Quarter *-
Quarter
- Quarter
- b Released-3:
4-3'
~ Quarter
- 4' f
M n
-3.
Particulatea'**
,.w Mn-54 01
[
+
Fe-59 01 --
-Co-58 C1
~^
-Ci-Yn"!El C1 Sr-89 C1 Sr-90 Ci-
~
' !!o-9 9 Ci
'Nb-95 Ci 1Cs-134-Ci Cs-137 Ci
~ Ba-140 Ci L a -14 0 --
Ci Ce-144-
'ICi Ce-141 Ci
. TOTAL FOR i'ERIOD Ci No releases during-this period
'O E**-
Lilalf. lives greater than 8 days k
I t
1 4
56 s
r-p n
k ' N,
~
,s f.
gi W,
't e
yv4
- TABLE :-- 2-4e' - ( Page 1 o f. 2 )
l[
V0GTLE ELECTRIC GENERATING PLANT-
-SEMIANNUAL RADIOACTIVE EFFLUENT REPORT ~
. GASEOUS' EFFLUENTS -LGROUND-RELEASES-(
b July 1, 1989'Through. December 31,_1989 Site'
-l I
E' i.
k L
~
Batch Mode-9 Continuous Mode Quarter
- Quarter.*-
Nuclides.
Unit-Quarter
- Quarter *-
'3
~4
~-
Released 3'
4
.+
.~ 1. ; Fi s sion - Ca se s'
. Ci-l; F
'CiJ f
Kr-85m-Ci Kr-87 Ci Kr Ci U
Xe-133 Ci Xe-135 Ci tXe-135m-Ci
,l
[
1Xe-138' Ci D
Xe-133m Ci.
w..
TOTAL FOR-PERIOD Ci 2
.2P Iodines..
'I-131-Ci U
LI-133 Ci
- TOTAL ~FOR' PERIOD C1 9
Y
.*No releases-during this period.
- .7,
..I 57 s
-.k~
'i
)
t TABLE 2-4c (Page 2 of 2)
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT REPORT CASEOUS EFFLUENTS - GROUND LEVEL July 1, 1989 Through December 31, 1989 a.
Site Continuous Mode Batch Mode Nuclides Unit Quarter
- Quarter
- Quarter
- Quarter
- Released 3
4 3
4 3.
Particulatee **
Mn-54 Ci Fe-59 C1 Co-58 Ci Co-60 Ci Zn-65 Ci Sr-89 Ci Sr-90 Ci Mo-99 Ci Nb-95 C1 Cs-134 Ci Cs-137 Ci Ba-140 Ci La-140 C1 Ce-144 Ci Co-141 Ci
. TOTAL FOR PERIOD Ci No releases during this period.
Half lives greater than 8 days 58
r{
u
_c b
.i
[
y;-
i TABLE 2-5 V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT b
GASEOUS EFFLUENT - DOSE RATES July 1, 1989 Through December 31, 1989 SITE Dose Rates Due to Noble Cases Organ Tech.
Unita Quarter
% of Quarter
% of Spec 3
Tech 4
Tech Limit Limit Limit T.
Body 500 mrem /yr 5.64E-04 1.13E-04 5.55E-04 1.11E-04:
Skin 3000 mrem /yr 1.26E-03 4.20E-05 1.16E-03 3.57E-05 Dose Rates Due to Radiciodines, Tritium and Particulates Organ Tech Unita Quarter
% of Quarter
% of Spec 3
Tech 4
. Tech l
Limit Limit Limit Bone 1500 mrem /yr 1.84E-07 1.22E-08 1.26E-07 8.41E Liver 1500-mrem /yr 4.81E-03 3.20E-04 4.69E-03 3.13E-04' T. Body 1500 mrem /yr 4.81E-03 3.20E-04 4.69E-03 3.13E-04' Thyroid 1500 mrem /yr 5.91E-03 3.94E-04 4.73E-03 3.16E-04 Kidney 1500-mrem /yr 4.81E-03 3.20E-04 4.69E-03 3.13E-04 Lung 1500 mres/yr 4.81E-03 3.20E-04 4.69E-03 3.13E-04
' GI-LLI-1500 mrem /yr 4.81E 3.20E-04 4.69E-03 3.13E-04 l
I i
-i 59 l
i
g.y:p *,' ' <
t
,4
.I i
b
,yw.
- i j.% -
0 ps 5
S r-
. TABLE 2-6A E
V0GTLE ELECTRIC GENERATING PLANT i
?
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
' AIR DOSES DUE TO NOBLE ~ GAS' RELEASES-i July-1,1 1989 Through-December 31,'1989 UNIT 1
.?
H 51 o
L i
.Typ'e of Tech.
Units.
Quarter
%_of Quarter.
% of-J
'y
' Radiation.
Spec' Tech Tech.
Limit--
3 Limit 4-Limit.
b
' Gamma 5.0 mrad 2.43E-04 4.86E-03 3.31E-04 6.62E Beta =
10.0-arad 6.44E-04 6.44E-03 7.62E-04 7.62E-03 J
f
- a I
\\r j
s 5
% Tech Limit Cumulative' Doses-~PerfYear (Year-'to Date)
' Gamma 10.0 mrad 1.35E 1.35E-02
' Beta-20.0 mrad-2.12E-03 1.06E-02
.i
- 1
.k
- (
l 's 60 i:
i i
i L
)
f 0
E.
I t
?:
I TABLE 2-6b V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT-AIR DOSES DUE TO NOBLE GAS RELEASES July 1, 1989 Through December 31, 1989 UNIT 2 t
Type of Tech Units Quarter
% of Quarter
% of.
Radiation Spec Tech Tech Limit 3
Limit 4
Limit Gamma 5.0 arad 4.17E-04 8.34E-03 3.04E-04 6.08E-03 Beta 10 0 mrad 1.03E-03 1.03E-02 6.04E-04 6.04E-03 Cumulative Doses-Per Year (Year to Date
% of Tech Spec Limit)
' Gamma 10.0 mrad 2.47E-03 2.47E-02 Beta 20.0 mrad 6.92E-03 3.46E !
l 61
m-C' 1In TABLE 2-7A V0GTLE ELECTRIC GENERATING PLANT
. SEMIANNUAL RADI0 ACTIVE EFFLUENT' RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOI0 DINE, TRITIUH-AND-PARTICULATES IN GASEOUS RELEASES July 1, 1989 Through December'31, 1989 UNIT 1 L
Cumulative Dose Per Quarter Organ Tech Units Quarter
% of Quarter
% of Spec Tech Tech
[
~ Limit-3 Limit 4
Limit Bone-7.5 mrem 1.99E-06 2.65E-05 2.38E-06 3.17E-05 Liver
- 7. 5 -
mrem 2.24E-06 2.99E-03 2.70E-04 3.60E-03 T.
Body 7.5-mrem 2.23E-06 2.97E-05 2.70E-04 3.60E-03 Thyroid 7.5 mrem 4.27E-06 5.69E-05 2.73E-04 3.60E-03 Kidney 7.5 mrem 2.25E-06 3.00E-05 2.70E-04 3.60E-03 _
Lung 7.5 mrem 2.23E-06 2.97E-05 2.70E-04 3.60E GI-LLI 7.5 mrem 2.23E-06 2.97E-05 2.70E-04 3.60E-03 Cumulative Dose-Per Year Organ Tech Units Year to Date
%_of Tech Spec, Limit Spec Limit Bone 15.0 mrem 1.30E-05 9.07E-05 Liver 15.0 mrem 3.71E-03 2.48E-02
-T.-Body 15.0 mrem 3.71E-03 2.48E-02 Thyroid -15.0 mrem-3.72E-03 2.48E-02 Kidney 15.0 mrem 3.71E-03 2.48E-02
. Lung 15.0 mrem-3.72E-03 2.48E-02 GI-LLI-15.0 mrem 3.71E-03 2.48E-02 i
L l
62 i
I'
'^
E!y
- M
-r r
{.
i
' TABLE 2-7b o
V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE'T0-RADI0 IODINE, TRITIUM i
AND PARTICULATES IN GASEOUS RELEASES July 1, 1989 Through December 31, 1989
.=
UNIT 2 I,
Cumulative Dose Per Quarter
. Organ Tech Units Quarter
% of Quarter
% of Spec Tech
-Tech' Limit 3
Limit 4
Limit j-Bone 7.5 mrem 1.27E-06 1.69E 0.00E+00 0.00E+00 Liver 7.5 mrem 9.85E-05 1.31E-03 5.55E-05 7.40E-04
'T.
Body
= 7. 5 mrem 9.85E-05 1.31E-03 5.55E-05 7.40E-04 Thyroid 7.5 mrem 9.99E-05 1.33E-03 5.55E 7.40E ' Kidney 7.5 mrem 9.85E-05 1.31E-03 5.55E-05 7.40E-04 Lung 7.5 mrem 9.85E-05 1.31E-03 5.55E-05 7.40E-04 GI-LLI 7.5 mrem 9.85E-05 1.31E-03 5.55E 7.40E-04 t
Cumulative Dose Per Year i
organ Tech Units Year to Date
% of-Tech-Spec Limit
. Spec Limit Bone.
15.0 mrem 1.29E-05 1.72E-04 Liver 15.0 mrem 1.80E-04 1.20E-03
'T.
Body-15.0 mrem 1.81E-04 1.20E-03 Thyroid 15.0
' mrem 1.81E 1.21E +
Kidney 15.0 mrem 1.80E-04 1.20E-03
. Luna 15.0 mrem 1.84E-04 1.23E-03 GI-LLI 15.0 mrem 1.80E-04 1.20E-03 1
I 63 l
N 'T:,T "h% r;j <
~
+
,; s s
'+
i R
R.
it '
.h If I
0 10 TABLE'2-8 y,
LOWER LIMITS OF DETECTION - GASEOUS SAMPLE ANALYSES V0GTLE ELECTRIC GENERATING PLANT i
,.y' July 1, 1989 - December 31,_1989 l
X
,5
- J The1 values in this table ~representEapriori~1ower limits of detection' j
E
- (LLD) which are _ typically achieved in laboratory analyses of gaseous
.q p,
.radwaste samples.-
}
Ul:
,t LLD-UNTIS l
RADIONUCLIDE Kr-87 1.03E-07 uci/mi 4
>Kr-88 4.77E-08 uCi/ml
~
3
- Xe-133-
- 2. 4 7 E-08 uCi/mi' Xe-133m 7.63E-08 uC1/ml 3
'Xe-135~
1.28E uC1/mi
-I Xe-138
-7. 3 6 E-0 51 uci/mi 11-131?
4.54E-15*
-uCi/mi LHn-54 7.12E-15*
uCi/mi Fe 1.60E-14*
uCi/ml:
- Co 1.23E-14*
uCi/ml i
uCi/ml
.Zn 1.34E-14*
uCi/m1~
t Mo' 6.37E-14*
uCi/ml Cs-1341 5.52E-15*:
uCi/m1'
'Os-137 1.19E-14*
uCi/ml r
'Ce-141
'6.69E-15*
uCi/m1' Ce-144 3.40E-14*
uCi/ml np
_Sr-89 1.00E-13*'
uCi/ml Sr-90-.
1.'00E-13*
~ uC1/ml-l 11 - 3 9.00E-08 uC1/m1' Gross Alpha 1.00E-13 uCi/mi
- iBased'on an_ estimated sample volume of 5.7E+08 cc's.
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~ Solid Westa 3.1)
Regulatory Limits /Te'chnicc1 Specification i
The Technical Specifications presented in this-section are for Unit 1 and Unit 2 and are stated in part.
-f f
311 Use of Solid Radioactive Waste System j
t i
3.11.3 Radioactive wastes shall be solidified or dewatered in accordance with the PROCESS CONTROL. PROGRAM to meet-shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.
_3.1.2 Reporting Requirements 6.8.1.4 The Semiannual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous; Effluents p
from Light-Water-Cooled Nuclear Power-Plants",
i Revision 1,. June 1974, with data summarized ~on a quarterly basis following the format of' Appendix B thereof.-For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories class of solid wastes (as defined by 10 3
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 prior to implementation.
6.12.2 Licensee - initiated changes to the PCP.
a.
Shall be submitted to the Commission in the L
Semiannual Radioactive Effluent Release Report i
for the period in which the change (s) was made.
q This submittal shall contain:
1.
Sufficiently detailed information to totally support the rationale for the change without 1
benefit of additional or supplemental information; 65
n.
- ~
. y, V
E i
t 2.
A determination that the change did not k
reduce the overall conformance of the solidified waste product to existing criteria for solid wastes, and 6
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 General Manager Nuclear Plant.
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.
9 I
i 66
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I,)
TABLE 3-1 (Page 1 of 2)
V0GTLE ELECTRIC CENERATING PLANT JULY l',
1989 THROUGH DECEMBER 31, 1989 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID AND IRRADIATED FUEL SHIPMENTS Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel) b 1.
Type of Waste Unit 6 month Est. Total Period Error %
3 1.322E+01 1.00E+01 a.
Spent resins, filter sludges m
evaporator bottoms, etc.
Ci 6.348E+00 3
b.
Dry compressible waste, m
2.516E+01 4.00E+01 contaminated equipment, etc.
C1 1.209E-01 i
l 3
c.
Irradiated components, control m
rod, etc.
Ci 3
d.
Other (describe) oily trash, m
speedi-dry mix. equipment, etc.
C1 i
Estimate of major nuclide composition (by type of waste) j j
2.
Isotope-Percent Curies a.
Co-58 3.29E+01 2.09E+00 Fe-55 2.38E+01 1.51E+00 All others 4.32E+01 2.74E+00 L
b.
Co-58 4.15E+01 5.02E-02 Fe-55 2.59E+01 3.13E-02 All others 3.26E+01 3.95E-02 I
L No solid waste during this_ report period.
1.
67 L
p,
/
TABLE 3-l'(Page.2 of 2)
((
V0GTLE ELECTRIC. GENERATING PLANT JULY 1,:1989 THROUGH DECEMBER 31, 1989 l
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT E
-SOLID AND IRRADIATED FUEL SHIPMENTS Isotope-Percent Curies c.
None shipped this period
-d.
Co-60 Zn-65 Nb-95 I
Zr-95 All others 3.
Solid Waste Disposition
- No solid waste shipped during this report period.
Number-of Shipments Mode of Transportation Destination-3 Tractor and Shielded cask Chem Nuclear Barnwell,!S.C.
4-Tractor -Trailer Scientific Ecology,.
Oakridge, TN.
4.
Irradiated. Fuel Shipments (Disposition)-
Number of Shipments Mode of Transportation Destination 0
N/A N/A i
' Additional Information Required by Tech Specs:
- Shipment Waste Type Shipping Solidification Agent
[
-No.
' Class Container' Class RWS-89-004 A stable High Integrity LSA N/A LRWS-89-005-A stable LSA N/A-RWS-89-006 A stabic LSA' N/A l
i RWS-89-004
'A unstable Strong-Tight LSA N/A.
.RWS-89-005 A unstable Strong-Tight LSA N/A RWS-89-006 A unstable LSA N/A' RWS-89-007" A unstable LSA N/A NOTES:
~Vogtle Elect'ric Generating Plant performed three (3) shipments to Chem Nucicar, Barnwell, SC and four (4) shipments to Scientific Ecology Group, Inc.
In Oak Ridge, TN.
During this - reporting period, the waste volume and activity on this report reflects only that volume of waste and activity which was processed and
.i disposed of-as radioactive waste at Chem-Nuclear Systems, Inc.,
Barnwell Waste Management Facility, or by Scientific Ecology Group, Inc. during this reporting period.
t 68
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_4.0-
'Chongos'to the Vogtle Electric-Gsnercting Plant ODCM E
- 6. 8. l. 4 '
Technical Specification 6.8.1.4 requires,
~
in part,
-that changes to the Offsite-Dose Calculati'on Manual l
(ODCM) be reported to the Commission in the next
._ Semiannual Effluent Release Report.
There were-no_ changes to the Vogtle Electric Generating Plant ODCH for,the period of July 1, i
through December 31, 1989.
6.13.2 Licensee-initiated changes to the ODCM J
a.
Shall be submitted-to the Commission in the
-Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made t
effective.
The submittal shall contain:
1.
Sufficiently detailed information to totally support the rationale for-the change without-benefit of supplemental information.
Information submitted should consist of a package of those pages of1the ODCM to be s
changed, with each page numbered, dated and containing the revision number together with appropriate analyses or evaluation justifying 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 3
General Manager _- Nuclear Plant.
1' 3.12.1 The Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.12-1.
Ta'ble Notation (1): states in part:
It is recognized that, at times, it may not be possible or practicable to continue to obtain samples i
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.
69 4
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i Pursuant to specification 6.13, submit in the next
~
r Semiannual Radioactive Effluent Release Report documentation for a change in the OD"M including a j
.c revised figure (s) and Table for the OLCM' reflecting the new location (s), if any, with supporting l
information' identifying the cause of.the unavailability of samples for the pathway and
' justifying the selection of the.new location (s) for obtaining samples, or the-unavailability of suitable new locations.
3.12.2' states in part A Land Use Census shall be conducted.
The Action Statement for this requirement states in parts a.
With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the value currently being calculated-in-specification 4.11.2.3, pursuant-to-specification 6.8.1.4, identify the new location (s) in the next Semiannual Radioactive Effluent ~ Release Report.
t s
j 70 l
1 vs
O
~
t 4.1' Changes in the Radiological Environmental.lonitoring Program b
For this semiannual period, there has been no change 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:
This same' report shall also include assessment of the radiation doses from radioactive _ liquid and gaseous-effluents to MEMBERS OF THE PUBLIC due to their activities-inside the Site Boundary (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 the 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.
informational purposes. The activity at Plant Wilson consists of regular employment.
There will be no radiation: 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 thel Unit 2 reactors; the dispersion and deposition factors for any releases from the' plant vent (mixed mode) and from the turbine building'(ground level);-and-the-estimated maximum occupancy factor for an individual and the assumed: age group of this individual.
i Not listed in Table 5-1 is the source-term.. Liste'd in Tables 12-4a and 2-4b for the ground level releases and in Tables 2-3a and 2-3b for the mixed mode' releases-l
~
are the noble 1 gases, radiciodines, and particulates-with half lives-greater than eight days; these are l
tabulated by radionuclide and by-quarter.
The tritium releases in units of curies were as follows:
l Quarter 1
2 1
Mixed Mode 7.65E+01 7.14E+01 i
1 71
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The maximum doses in units of arem 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 L
Total Body 7.25E-07 8.49E-05 (direc t radiation _ f rom plume)
. Maximum Organ 3.57E-06 2.11E-04 (Thyroid) - Inhalation and ground plane L
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l-II Table 5-1 JULY 1,1989 THROUGH DECEMBER 31,1989 a
["
Basic Data Assumed in Dose Assessments TO MEMBERS OF THE PUBLIC h
-Item Visitors center-Plant Wilson.
i.
Distance (meters) 447 1420 S ctor
' ' ~
SE ESE 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) i Age group Child Adult (1) Ground level release
.(2) Mixed mode release VISITORS CENTER PLANT WILSON
' Quarter-1
_ uarter 2 Total Quarter 1 Quarter 2 Total Q
mrem mrem mrem mrem mrem mrem Tot'al Body 3.64E-07 3.61E-07 7.25E-07 4.26E-05 4.23E-05 8.49E-05:
ORGAN DOSE Bone 6.11E-11 4.39E-11 1.05E-10 2.26E-06 1.03E-08 2.27E-06 Liver P.46E-07 7.91E-07 1.64E-06 1.11E-04 9.68E-05 2.08E-04'
'TBody.
8.46E-07 7.91E-07 1.64E-06 1.11E-04 9.68E-05 2.08E-04 Thyroid 8.55E-07 7.97E-07 1.65E-06 1.14E-04 9.73E-05 2.11E-04:
Kidney 8.46E-07 7.91E-07 1.64E-06 1.11E-04 9.68E-05 2.08E-04 Lung 8.46E-07 7.91E-07 1.64E-06 1.11E-04 9.68E-05 2.08E-04 GI-LLI 8.46E-07 7.91E-07 1.64E-06 1.11E-04 9.68E-05 2.08E-04 73
4.
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.6'0 Ma'jor Changes to Liquid, Gaseous or Solid Radwaste Treatment: Systems l
6.8'.1.4 states in parts'
{
The 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 Radwaste Treatment Systems (liquid, gaseous, and solid):
(
a.
Shall be reported to the Commission in the Semiannual Radiactive Effluent Release Report for the period in which the evaluation was reviewed by the PRB.
The discussion of each change shall 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 cotally support the reason for the change without benefit of additional or supplemental information; 3.
A detailed description.of equipment, components, and-processes involved and the 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 that differ from those previously predicted in the License Application and amendments thereto; 5.
An. evaluation 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 previously estimated in the License application and amendments thereto; 6.
A comparison of the predicted releases of radioactive materials, in liquid and gaseous l
effluents and in solid waste, to the actual releases for the period prior to when the change is to be made; 74 l
m 7.
An estimate of the exposure to plant operating personnel as a result of-the change; and" 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 pe riod.
t 7.0 Meteorological Data 6.8.1.4 states in part:
The. Semiannual Radioactive Effluent Release Report to be submitted within 60 days'after January 1 of each year-shall include an annual summary of hourly meteorological. data collected over the previces year.
This annual summary may be either in the form
'f an-hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and i
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.
I t
h 1
9 75
p 8.0 Inoperable Liquid or Oaseous Effluent Monitoring Instrumentation 6.8.1.4_ states in part that:
The Semiannual Radioactive' Effluent Release Reports shall.also include the following:
an explanation'as to why_the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time-specified in Specifications 3.3.3.9 or 3.3.3.10 respectively.
3.3.3.9 states in part:
The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE 4
Action b.
states:
With'less than the minimum number of radioactive 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 less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, 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 in' operability was not corrected in a timely manner.
76
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IInoperable Tech Spec monitors are tracked on Limiting E
Condition of Operation (LCO) Forms.
The operators declare equipment. operable and inoperable and monitors are consideredLinoperable if there are open LCO's for that monitor.
18.1.1 The LCO's initiated do-not have to be reported for this report period since the LCO's initiated were closed'before 30 day period.
t
- 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 s!'
the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of specification 3.11.1.4 or 3.11.2.6, respectively ".
-3.11.1.4.
The quantity 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 states:
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 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 events leading.to this condition in the next; Semiannual Radioactive Effluent Release Report, pursuant to specification 6.8.1.4.
3.11.2.6 g-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).
Ac' tion 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 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.
77
l
)
y There were no outside temporary liquid tanks-for e
s.
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 (considered as Xe-133 equivalent).
10.0 Changes to the previous. Semiannual Effluent Reports Attachment B and Attachment C provide revised Liquid Effluent tables for the 1987 and 1988 Semiannual Effluent Reports. The changes resulted from an 8%
adjustment.to more accurately reflect actual waste
- monitor tank volumes.
11.0 A review of cumulative doses resulting from liquid effluents (Table 1-4) and gaseous effluents (Tables 2-6 and 2-7) shows total annual doses to be a.small fraction of'one millirem.
These evaluations and those discussed s
. in Section 5.0 of-this report (Doses to Members of the Public Inside-the Site Boundary) indicate the total dose to any Member of the Public is well below the criteria L_
of 40 CFR 190.
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PICKARD, LOWE AND GARRICK, INC.
1615 M STREET, N.W., SUITE 730 3 WASHINGTON, D.C. 20036 J
- N(WPOlti stACH, cAlifostNIA WASHINGTON, D.C.
ftLEPHONE 1146508000 tilfPHONE 202 659 1122 la
- itLECOPitt 714 646 902)
TELECOritt 202 296-0774
.TILIK 3789951 PLCIRV-TELEX 2519JI PLC UR -
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January 25, 1990 li l
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- Mr. Shan Sundaran Georgia Power Company
. Plant.Vogtle Route 2, Box 299A Waynesboro, GA 30830
Dear Shan:
s r
As you requested,~ enclosed are several attachments related to the meteorologica1' data 'f rom Plant Vogtle _ for the third and fourth 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 periods of missing data.
,The data quality and. recovery rate for the second half of.1989 were good i
but'not without some problems.
The only significant period of downtime occurred af ter Hurricane Hugo struck on September 22 with the instrumentation on the tower. being down for various time periods from 1 5 days.
The. delta temperature was'down for a longer period into early early October.
There were also delta temperature problems in'early July.
The attachments are as follows:
e.
Data Recovery Percentage for Each Parameter and Composites of Pertinent Parameters.
July 1 - December 31, 1989-s a
. Attachment'2. Wind Roses-A-1 :
10m Wind Speed and Direction July 1,.1989 through December 31, 1989.
A-2:
10m Wind Speed and Direction July 1, 1989 through September 30, 1989.
A-3.
10m Wind Speed and Direction October 1,1989 through December 31, 1989.
.. 1 :
60m Wind Speed and Direction July 1, 1989 through December 31, 1989.
2 t
(NOINEERS. APPUED SCIENTISTS
- MANAGEMENT CONSULTANTS 79
. ATTACHMENT A
?
Page 2 i
Mr. Shan Sundaran January 25, 1990 Georgia Power Company' Page 2 B-2.
60m Wind Speed and Direction July 1, 1989 through September 30, 1989.
8-3. _ 60m Wind Speed and Direction October 1,1989 through December 31, 1989.
e.
Joint Frequency Tables of Wind Speed and Direction 10m vs Delta Temperature 60-10m.
l A:
July 1, 1989 through December 31, 1989.
8:
July 1,l1989 through September 30, 1989.
C:
October 1,1989 through December 31, 1989, e.
Joint Frequency Tables of Wind Speed and Direction 60m vs Delta Temperature 60-10m.
A:
July 1, 1989-through December 31, 1989.
8:
July 1,1989 through September 30, 1989.
- C:
October 1,1989 through December 31, 1989.
e.. Daily and Monthly Rainf all Totals for July 1,1989 through December 31, 1989.
r e-.
Average of the Daily Maximum and Minimum Temperatures for July 1,1989 through December 31, 1989.
A:
Ambient Temperature
- 8:
Dew Point Temperature e.
Summary of Meteorological Data-for 1989.
i If you have any questions or need additional information, please call.
Very truly yours, V
)?t0 L
Mark J. Abrams Attachments 80 l
31 ATTACHMENT A Page 3 ATTACHMENT 1.
PERCENT DATA' REC 0VERY BY PARAMETER JULY 1,1989. THROUGH DECEMBER 31, 1989 I
s Parameter Percent -
Wind. Speed 10m 96.9
. Wind Speed 60m 98.6 Wind Direction 10m
.97.1 Wind Direction-60m 97.5 Delta Temperature 60-10m 92.0 Temperature 10m 96.9 Dew Point Temperature 10m 94.8 Precipitation 95.8 g
1-Composites 4
- Wind Speed:and Direction 10m, Delta Temperature 60-10m 91.2 Wind Speed and Direction 60m, Delta Temperature 60-10m.
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?r-l ATTACHMENT 2A-1. -10m WIND' ROSE JULY 1, 1989 THROUGH DECEMBER 31, 1989' l
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+ WEB SPEED LESS THAN7.5 tPM -
xWns SPEED LESS THAH12.5 iPH
+ WIND SPEED GREATER THAN 12.5 FFH.
0.3 PERCEffT CAlttS
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ATTACHMENT A Page8 i
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i 84
ATTACif9ENT 28-1. 60m WIND ROSE JULY 1,1989 THROUGH DECEPBER 31, 1989
^*
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I Wire ROSE (WINBS FR0rO N
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. WIND SPEED LESS THAN3.5 FFM
+ Wits SPEED LESS THAH7.5 NPM xWIND SPEED LESS THAH12.5 tFM O
. WIND SPEED GREATER THAN 12.5 FFN 9.1 PERCEffT CENS z
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SITE: PLAffT (J0GTLE 01/25/39 99:18'
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i AfrACHZENT A Page8 I
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ATTACHMENT 28-3. '60m WIND ROSE l_.~
OCTOBER 1, 1989 THROUGH DECEMBER 31, 1989
/
o 2 2 1
l 1
1 '
I I
UD9 POSE (WIFSS FR0ff)
- 1 t
H g
1r >
- WDS SPEED LESS THm3.5 WM 4$
+WIIe SPEED LESS THAN7.5 WM
.~
xWDB SPEED LESS THAN12.5 NH
- O
, WIND SPEED GREATER THAN 12.5 FFN 9.9 PERCErfT CAlttS 3
E SITE: PLAttT UOGTLE 01/25/99 99:34
=
4>
9
., +.-
a __
u ATTACIMENT 3As JOINT' FREQUENCY TABLE OF WIND SPEED 1.of 8 AND DIRECTION 10m VS DELTA TEMPERATURE 60-10m JULY-1, 1989 THROUGH DECEMBER 31, 1989 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89070181-89123124 STABILITY CLASS:
A DT/DZ ELEVATION:
-SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND SPEED (tPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
O 2
0 0
0 6-2 NNE 1
2 2
0 0
0 5
NE 2
7 20 4
0 0
33 ENE 1
4 9
2 0
0 16 E
1 2
3 0
0 0
6 ESE O
3 0
0 0
0 3
SE 2
7 0
0 0
0 9
SSE 2
2 0
0 0
0 4
E S
1 2
0 0
0 0
3 SSU 0
4 0
0 0
0 4
SU 0
11 7
0 0
0 18 USU 0
22 21 0
0 0
43 U
.1 26 22 4
0 0
53 UNU 1
6 8
1 0
0 16 NU 0
2 5
1 0
0 8
5>
$h NNU 1
1 1
0 0
0 3
gn
[
TOTAL 13 103 98 12 0
0 226 PERIODS OF CALM (HOURS):
-13 4
VARIABLE DIRECTION 36 HOURS 0F MISSING DATA:
388
ATTACIMENT 3A (continued) 2 of 8 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89070101-89123124 STABILIT/ CLASS:
B DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND SPEED (tFH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
1 3
2 0
0 0
6 NNE 1
3 6
1 0
0 11 NE 2
5 18
.4 0
0 29 ENE 1
13 10 0
0 0
24 E
O 8
3 0
0 0
11 ESE 2
6 1
0 0
0 9
SE 1
2 0
0 0
0 3
SSE 2
5 0
0 0
0 7
S 4
3 4
0 0
0 11 SSU 1
10 4
0 0
0 15 SU 3
12 6
0 0
0 21 USU 2
20 6
0 0
0 28 U
0 16 7
0 0
0 23 UNU 2
9 4
1 0
0 16 NU 0
3 2
1 0
0 6
[h NNU 1
8 5
0 0
0 14 e,
OQ TOTAL 23 126 78' 7
0 0
234 g
PERIODS OF CALM (HOURS):
13 g
VARIABLE DIRECTION 61 4
HOURS OF MISSING DATA:
388
ATTACIMENT 3A (continued) 3 of 8 HOURS AT EAC4 UIND SPEED AND DIRECTION-PERIOD OF RECORD =
89070101-89123124 STABILITY CLASS:
C DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND SPEED (tPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
3 5
1 0
0 0
9 NNE 3
6 4
0 0
0 13 NE 3
10 13 3
0 0
29 ENE 2
15 9
0 0
0 26 E
O 5
4
'O O
O 9
ESE 2
9 2
0 0
0 13 SE 1
5 4
0 0
0 10 E
SSE 1
9 1
0 0
0 11 S
1 9
0 0
0 0
10 SSU 4
9-6 2
0 0-21 SU 4
16 6
0 0
0 26 USU 4
20 6
0 0
0 30 U
1 23 3
0 0
0 27 UNU 0
15 1
1 0
0 17 NU 0
10 2
0 0
0 12 g,y NNU 0
9 6
0 0
0 15 U>@
TOTAL 29 175 68 6
0 0
278 g
PERIODS OF CALM (HOURS):
13 E
4 VARIABLE DIRECTION-75 HOURS OF MISSING DATA:
388
ATTACittENT 3A' (dontiriued)
_4 of 8
-HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89070181-89123124 STABILITY CLASS:
D DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND - SPEED (PPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
19 58 23 3
0 0
103 NNE 9
45 34 9
0 0
97 NE 9
72 67 18 0
0 166 ENE 17 45 21 3
0 0
86 E
9 51 14 0
0 0
74 ESE 9
30 13 0
0 0
52 SE 6
36 11 0
0 0
53 3
SSE 9
29
'3 0
0 0
41 S
15 28 8
0 0
0 51 SSU 11 37 9
1 0
0 58 SU 12 48 7
2 0
0 69 USU 15 42 6
0 0
0 63 U
8 34 19 0
0 0
61 LtiU 13 21 S
1 0
0 44 NU 11 30 8
3 8-0 52 4>$
NNU 11 50 27 13 0
0 101 U$
TOTAL 183 656 279 53 0
0 1171 g
PERIODS OF CALM (HOURS):
13 E4~
VARIABLE DIRECTION 271 HOURS OF MISSING DATA:
388
ATTACIMENT' 3A T(continued)
. 5 of 8 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89870181-89123124-
. STABILITY CLASS:
E DT/DZ -
ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M' LAPSE:DT60M UIND SPEED (tFH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
14 37 8
.0 0
0 59 NNE 16 25 31 1
1 0
74 NE 31 79 37 4
0 0
151 ENE 35 42 3
0 0
0 80 E
28 34 3
0 0
0~
65 ESE 26 31 1
0 0
0 58 SE 30 44 2
0 0
0 76 SSE 45 42 2
0 0
0 89 S
51 3G' 3
0 0
0 90 SSU 30 45 14 6
0 0
95 SU 34 61 9
'2 0
0 106 USU 33 45 7
1 1
0 87 U
27 30 12 1
0 0
70 UNU 21 29 2
2 0
0 54 NU 7
11 4
0 0
0 22 NNU 21 29 8
0 0
0 58
- 4. dg TOTAL 449 620 146 17 2
0 1234 EG.
g PERIODS OF CALM (HOURS):
13 54 UARIABLE-DIRECTION' 282 HOURS OF MISSING DATA:
388 4
m
. ~
........, < - - -. -,. ~. -
. ed
' ATTACIMENT 3A (continued) 6 of 8 HOURS AT EACH UIND SPEED AND DIRECTION
-PERIOD-OF RECORD =
89070101-89123124 STABILITY CLASS:
F DT/DZ ELEVATION:
SPEED:SPD10M' DIRECTION:DIR10M LAPSE:DT60M WIND SPEEDGPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
6 17 10 0
0 0
33 NNE 4
14 4
0 0
0 22 NE 9
1S S
0 0
0 29 ENE
-17 11 0
0 0
0 28 E
16 10 0
0 0
0 26 ESE 19 9
0-0 0
0 28 SE 22
'9 8
0 0
0 31 3
SSE 21 11 0
0 0
0 32 S
26 7
0 0
0 0
33 SSU 19 9
1 0
0 0
29 SU 33 30 1
0 0
0 64 USU 41 32 0
0 0
0 73 U
23 17 0
0 0
0 40 UNU 21 9
0 8
0 0
30 NU 14 4
0 0
0 0
18 i
$' >4 NNU 8
16 0
0 0
0 24 I
TOTAL 299 220 21 0
0 0
S40 O >o z
z PERIODS OF CALMCHOURS):
13 mx UARIABLE DIRECTION 121 g
HOURS OF MISSING DATA:
388 l
b.
=.
ATTACHMENT 3A'(continued) 7 of 8 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89870101.89123124 STABILITY CLASS:
G DT/DZ.
ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UITID SPEED (MPH)
WIIID DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL
__m_
==m_
N 10 1
1 0
0 0
12 NNE 7
2 0
0 0
0 9
tie 14 S
0 0
0 0
19 i
ENE 15 6
0 0
0 0
21 E
22 3
0 0
0 0
25 ESE 16 2
0 0
0 0
18 SE 11 3
0 0
0 0
14 SSE 7
8 0
0 0
0 15 2
S 8
0 0
0 0
0 8
SSU 10 8
0 0
0 0
18 SU 22 28 0
0-0 0
50 USU 31 21 0
0 0
0 52 U
23 13 0
0 0
0 36 UNU 16 4
0 0
0 0
20 NU 11 1
0 0
0 0
12 NNU 12 4
0 0
0 0
16
[.4 eg TOTAL 235 109 1
0 0
0 345 EO g
PERIODS OF CALM (HOURS):.
13 g
VARIABLE DIRECTION 69 s
HOURS OF MISSING DATA:
388
g 2
[-
ATTACHMENT 3A'(continued) 8 of 8 HOURS AT-EACH UIND SPEED AND DIRECTION' PERIOD OF. RECORD =
89070181-89123124 STABILITY CLASS:
ALL DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M
. WIND SPEED (ifH)
-UIND DIRECTION 1-3 4 --7 8-12 13-18 19-24
>24 TOTAL N
53 123 45 3
0 0
224 Nile 41 97 81 11 1
0 231 NE 70 193 160 33 0
0 456 ENE 88 136 52 5
0 0
281 E
76 113 27 0
0 0
216 ESE 74 90 17 0
0 0
181 SE 73 106 17 0
0 0
196 e
SSE 87 106 6
0 0
0 199 S
106 85 15 0
0 0
206 SSU 75 122 34 9
0 0
240 SU 108 206 36 4
0 0
354 USU 126 202 46 1
1 0
376 U
83 159 63 5
0 0
310 UNU 74 93 24 6
0 0
197 NU 43 61 21 5
0 0
130 j>>
NNU 54 117 47 13 8
0 231 U@
TOTAL 1231 2009 691 95 2
0 4028 z
E l
PERIODS OF CALM (HOURS h 13 i
VARIABLE DIRECTION 915
[
l HOURS OF MISSING DATA:
388 l
i l
ATTACHMENT 3B. ' JOINT FREQUENCY TABLE OF lilND SPEED 1 of 8-AND DIRECTION 10m VS DELTA TEMPERATURE 60-10m JULY:1,-1989 THROUGH SEPTEMBER 30, 1989 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
'89070181-89093024 STABILITY CLASS:
A
' DT/DZ ELEVATION:.
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND SPEED (ifH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
O 2
0 0
0 0
2 NNE 1
0 0
0 0
0 1
NE 1
3 9
2 0
0 15 ENE 1
3 7
1 0
0 12 E
1 2
1 0
0 0
4 ESE O
3 0
0 0
0 3
SE 2
6 0
0 0
0 8
e SSE 2
1 0
0 0
0 3
S 0
2 0
0 0
0 2
SSU 0
3 0
0 0
0 3
SU 0
8 1
0 0
0 9
USU 0
11 5
0 0
0 16 U
1 18 10 0
0~
0 29 LNU 0
5 1
0 0
0 6
NU 0
0 0
0 0
0 0
5>
'=$
TOTAL 9
68 34' 3
0 0
114 g
PERIODS OF CALM (HOURS):
4 z
UARIABLE DIRECTION 28 j
HOURS OF MISSING DATA:
205
..~....
0 ATTACINENT 3B (continued) 2 Gf 8 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89070181-89093024 STABILITY CLASS:
.B
-DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND SPEED (ifH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
1 1
1 0
0 0
3 NNE 1
2 0
0 0
0 3
NE 2
2 8
3 0
0 15 ENE O
10 7
0 0
0 17 E
O 3
2 0
0 0
5 ESE 2
3 1
0 0
0 6
SE O
1 0
0 0
0 1
3 SSE 1
3 0
0 0
0 4
S 4
2 2
0 0
0 8
SSU 1
6 3
0 0
0 10 SU 3
10 3
0 0
0 16 USU 1
14 1
0 0
0 16 U
0 13 2
0 0
0 15 UNU 2
2 0
0 0
0 4
N NU 0
1 1
0 0
0 2
f tiNU 1
4 0
0 0
0 5
- g 2
TOTAL 19 77 31 3
0 0
130 E,
PERIODS OF CALM (HOURS):
4 j
UARIABLE DIRECTION 48 HOURS OF MISSING DATA:
205 I
v
=-
r e-r
-m.
=-=e-
- w
<e, w
a4-e=
.-.-e
.. - + -.
n--
w-e.--
w -~
,..-w wm~-
m,#+
.-----v==r,
- e.e-
- ATTACFMENTL 3B (continued)
. 3 of 8 m
HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89070101-89093024 STABILITY CLASS:
C DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND SPEED (ffH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
1 4
0 0
0 0
5 f1NE 3
1 0
0 0
5 NE 2
7 8
1 0
0 18 ENE 1
10 5
0 0
0 16 E
O 3
3 0
0 0
6 ESE 1
6 1
0 0
0 8
SE 1
2 0
0 0
0 3
=
SSE O
5
~ 1-0 0
0 6
S 0
4 0
0 0
0 4
SSU 3
9 2
0 0
0 14 SU 3
10 2
0 0
0 15 USU 4
10 1
0 0
0 15 U
1 12 0
0 0
0 13 UNU 0
9 0
0-0 0
9 NU 0
4 0
0 0
0 4
NNU 0
4 0
0 0
0 4
43
- 3;
- O TOTAL 18 102 24 1
0 0-145 z
m PERIODS OF CALM (HOURS):
4 x+
VARIABLE DIRECTION 46 HOURS OF-MISSING DATA:
205
ATTACHMENT 38.(continued)
- 4 Cf 8 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89070181-89093024 STABILITY. CLASS:
D DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
10 36 9
0 0
0 55 NNE 7
2F 11 1
0 0
47 NE 6
36 42 7
0 0
91 ENE 7
25 11 1
0 0
44 E
4 34 11 0
0 0
49 ESE 5
19 10 0
0 0
34 SE 3
16 6
0 0
0 25 SSE 2
14 2
0 0
0 18 3
S 9
9 4
0 0
0 22 SSU 6
20 5
1 0
0 32 SU 7
25 0
0 0
0 32 USU 9
22 0
0 0
0 31 U
2 18 0
0 0
0 20 1
UNU 6
9 0
0 0
0 15 NU 4
4 2
1 0
0 11 j>$
s NNU 3
20 11 7
0 0
41 O
TOTAL 90 335 124 18 0
0 567 z
E PERIODS OF CALM (HOURS):
4 VARIABLE DIRECTION 150-
[
HOURS OF MISSING DATA:
- 205,
~
2'-c ATTACl#fENT.3B-(continued)
' 5 of 8 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89070181-89093024 STABILITY CLASS:
E DT/DZ ELEVATION:.
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND SPEED (MPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
7 20 3
0 0
0 30 NNE 13 19 11 0
1 0
44 NE 22 62 21 2
0 0
107 ENE 29 25 2
0 0
0 56 E
20 22 1
0 0
0 43 ESE 22 26 1
0 0
0 49 SE 20 31 1
0 0
0 52 SSE 28 24 1
0 0
0 53 e
S 40 18 1
0 0
0 59 SSU 21 33 4
1
-0 0
59 SU 24 27 4
2-0 0
57 i
USU 26 16 0
1 1
0 44 U
15 4
1 1
0 0
21 l
UNU 9
4 0
2 0
0 15 NU 6
1 0
0 0
0 7
,3 NNU 15 17 1
0 0
0 33 gj TOTAL 317 349 52 9
2
-0 729 g
l PERIODS OF CALM (HOURS):
4 E.
4 VARIABLE DIRECTION 200 HOURS OF MISSING DATA:
205 l
l
W ATTACIMENT 3B (continued) 6 of 8 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89070181-89093024 STABILITY CLASS:
F DT/DZ~
ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M
' UIND SPEEDOPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
2 3
2 0
0 0
7 NNE 2
1 0
0 0
0 3
NE 3
1 0
0 0
0 4
ENE 8
3 0
0 0
0 11 c
E 7
3 0
0 0
0 10 ESE 10 5
0 0
0 0
15 SE 12 5
0 0
0 0
17 5
SSE 12 1
0 0
0 0
13 S
11 4
0 0
0 0
15 SSU 14 4
1 0
0 0
19-SU 24 13 0
0 0
0 37 USU 21 9
0 0
0 0
30 U
13 6
0 0
0 0
19 UNU 14 3
0 0
0 0
17 NU 7
3 0
0 0
0 10 4 >y 4
NNU 6
5 0
0 0
0 11 a
O$
TOTAL 166 69
. 3 0
0 0
238 g
PERIODS OF CALM (HOURS):
4 E4 VARIABLE DIRECTION 67 HOURS OF MISSING-DATA:
205 w-9 g
.,-e
,y w.-
., y w a-,w..
.g-y-,
.ws,4e.,
g y, # w 4,,s
,_.3-,.gy--
-g
.+w.-
m
,,.p.
w e.
y,,
..q,.,,
,_w,
,..nw-,,,,,...-..w--ec..
,es
a n
rg.
J.
ATTACiffENT 38 (continued) 7 of 8 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89070181-89093024 STABILITY CLASS:
G DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND SPEED (tPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL-N 1
0 0
0 0
0 1
NNE O
O O
O O
O O
NE 1
0 0
0 0
0 1
ENE 3
1 0
0 0
0 4
E 2
2 0
0 0
0 4
ESE 5
2 0
0 0
0 7
SE 5
1 0
0 0
0 6
5 SSE 1
2 0
0 0
0 3
S 1
0 0
0 0
0 1
SSU 6
2 0
0 0
0 8
SU 9
6 0
0 0
8 15 USU 8
6 0
0 0
0 14 U
7 2
0 0
0 0
9 UNU 3
1 0
0 0
0 4
NU 3
0 0
0 0
0 3
4$
NNU 0
0 0
0 0
0 0
- Q E
TOTAL 55 25 0
0 0
0 80 g
4 PERIODS OF CALM (HOURS):
4 UARIABLE DIRECTION 15 HOURS OF MISSING DATA:
205 i
S
.-- as ---
m -
w
_m-,
ws -
_,--e,.-
,--.y.
g
.-.--4-w.
,.%.,.~.,,,, + -..
t
ATTACMENT.3B (continued) 8.of 8 HOURS AT EACH UIND SPEED AND DIRECTIDN PERIOD OF RECORD =
89070181-89093024 STABILITY CLASS:
ALL' DT/DZ ELEVATION:
SPEED:SPD10M DIRECTIDN:DIR10M LAPSE:DT6eM UIND SPEED (PPH)
UIND DIRECTION 1 -3 4-7 8-12 13-18 19-24
>24 TOTAL N
22 66 15 0
0 0
103 tine 25 53 23 1
1 0
103 NE 37 111 88 15 0
0 251 ENE 49 77 32 2
0 0
160 E
34 69 18 0
0 0
121 ESE 45 64 13 0
0 0
122 SE 43 62 7
0 0
0 112 SSE 46 50 4
0 0
0 100 8
S 65 39 7
0 0
0 111 SSU 51 77 15 2
0 0
145 SU 70 99 10 2
0 0
181 USU 69 88 7
1 1
0 166 U
39 73 13 1
0 0
126 UNU 34 33 1
2 0
0 70 NU 20 13 3
1 0
0 37 NNU 25 51 12 7
0 0
95 gg E>Q TOTAL 674 1025 268 34 2.
0 2003 E
PERIODS OF CALM (HOURS):
4 E4 VARIABLE DIRECTION 554 HOURS OF MISSING' DATA:
205 u..
?
?
ATTACHMENT 3C. JOINT FREQUENCY TABLES OF WIND SPEED 1 of 8 c
AND DIRECTION OF 10m VS DELTA TEMPERATURE 60-10m OCTOBER 1, 1989 THROUGH DECEMBER 31, 1989 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89100181-89123124
)
STABILITY CLASS:
A DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND ' SPEED GPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
O O
O O
O O
O NNE O
2 2
0 0
0 4
NE 1
4 11 2
0 0
18 ENE O
1 2
1 0
0 4
E O
O 2
0 0
0 2
ESE O
O O
O O
8 0
SE O
1 0
0 0
0 1
3 SSE O
1 0
0 0
0 1
S' 1
0 0
0 0
0 1
SSU 0
1 0
0 0
0 1
SU 0
3 6
0 0
0 9
USU 0
11 16 0
0 0
27 U
0 8
12 4
0 0
24 UNU 1
1 7
1 0
0 10 NU 0
2 5
1 0
0 8
,4, NNU 1
0 1
0 0
0 2
e4 E>Q l
TOTAL 4
35 64 9
0 0
112 g
PERIODS OF CALM (HOURS):
9 E
-8 VARIABLE DIRECTION 8
HOURS OF MISSING DATA:
183 1
l l-(
ATTACHMENT 3C (continued) 2 of 8 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89100181-89123124 STABILITY CLASS:
B DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND SPEED (IPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
O 2
1 0
0 0
3 NNE O
1 6
1 0
0 8
NE O
3 10 1
0 0
14 ENE 1
3 3
0 0
0 7
E O
5 1
0 0
0 6
ESE O
3 0
0 0
0 3
SE 1
1 0
0 0
0 2
g SSE 1
2 0
0 0
0 3
S 0
1 2
0 0
0 3
SSU 0
4 1
0 0
0 5
SU 0
2 3
0 0
0 5
USU 1
6 5
0 0
0 12 U
0 3
5 0
0 0
8 UNU 0
7 4
1 0
0 12 NU 0
2 1
1 0
0 4
g4 NNU 0
4 5
0 0
0 9
- >o N
TOTAL 4
49 47 4
0 8
104 g
PERIODS OF CALM (HOURS):
9 4>
UARIABLE DIRECTION 13 HOURS OF MIS 91NG DATA:
183.
i
-c.
4 g
+
-r
-e e
,.%--..m.e-
.,,-..,.---,w,,=,~.-.~,..,w, ep-,,
s.w%,,w-ww,.w,+-e-*=
,.,_w- ~ - -.,
-.e.-..--..r..s._,..
%-w..
-.,,w e
ATTACHMENT 3C (continued)
- 3 of 8 v
HOURS.AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89100181-89123124 STABILITY CLASS:
C-DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND SPEED (IPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
2 1
1 0
0 0
4 NNE 2
3 3
0 0
0 8
NE 1
3 5
2 0
0 11 ENE 1
5 4
0 0
0 10 E
O 2
1 0
0 0
3 ESE 1
3 1
0 0
0 5
SE O
3 4
0 0
0 7
5 SSE 1
4 0
0 0
0 5
S 1
5 0
0 0
0 6
SSU 1
0 4
2 0
0 7
SU 1
6 4
0 0
0 11 USU 0
10 5
0 0
0 15 U
0 11 3
0 0
0 14 UNU e
6 1
1 0
0 8
5 NU 0
6 2
0 0
0 8
4 ifNU 0
5 6
0 0
0 11 gg l
=
TOTAL 11 73 44 5
0 0
133 E
i M
PERIODS OF CALM (HOURS):
9 5
l VARIABLE DIRECTION 29 HOURS OF MISSING DATA:
183
{a
+
ATTACIMENT 3C (continued) 4.of 8 -
9 HOURS AT EACH UIt!D SPEED AND DIRECTION PERIOD OF RECORD =
89100181-89123124 STABILITY CLASS:
D DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND SPEED (tPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
9 22 14 3
0 0
48 NNE 2
17 23 8
0 0
50 NE 3
36 25 11 0
0 75 ENE 10 20 10 2
0 0
42 E
5 17 3
0 0
0 25 ESE 4
11 3
0 0
0 18 SE 3
20 5
0 0
0 28 SSE 7
15 1
0 0
0 23 S
6 19
'4 0
0 0
29 SSU S
17 4
0 0
0 26 SU 5
23 7
2 0
0 37 USU 6
20 6
0 0
0 32 U
6 16 19 0
0 0
41 UNU 7
12 9
1 0
0 29 NU 7
26 6
2 0
0 41 kh NNU 8
30 16 6
0 0
60 ga
[
TOTAL 93
-321 155 35 0
0 604 g
PERIODS OF CALM (HOURS):
9 4
UARIABLE DIRECTION 121 HOURS OF MISSING DATA:
183 4
1
..w
.y
..e,...
_,,,w-y,,,.r.w-c,
-.r.,,,%,..,.,...,--,,._,mw.,
..~,,.c,
.,,w,
-,3,
c,
-w
,m..,
-,w%.,
..-, e
_ _ ~
ATTActMENT 3C (continued) 5 of 8 m
HOURS AT EACH UIND SPEED AND DIRECTIDN PERIOD OF RECORD =
89100181-89123124 STABILITY CLASS:
E DT/DZ ELEUATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M WIND SPEEDUPH)
UIND DIRECTION' 1-3 4-7 8-12 13-18 19-24
>24-TOTAL N
7 17 5
'O O
O 29 NNE 3
6 20 1
0 0
30 NE 9
17 16 2
0 0
44 ENE 6-17 1
0 0
0 24 E
8 12 2
0 0
0 22 ESE 4
5 0
0 0
0 9
SE 10 13 1
0 0
0 24
_g SSE 17 18 1
0 0
0 36 S
11 18 2
0 0
0 31 SSU 9
12 10 5
0 0
36 SU
.10 34 5
0 0
0 49 USU 7
29 7
0 0
0 43 U
12 26 11 0
0 0
49 UNU 12 25-2 0
0 0
39 NW 1
10 4
0 0
0 15 NNU
'6 12 7
0 0
0 25 A$
E>O TOTAL 132 271 94 8
0 0
505 z
PERIODS OF CALM (HOURS):
9 UARIABLE DIRECTION 82 HOURS OF MISSING DATA:
183
~.... -. -.
ATTACIMENT 3C (continued) 6 of 8 ~
HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89100181-89123124 STABILIT/ CLASS:
F DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND SPEEDUPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
4 14 8
0 0
0 26 NNE 2
13 4
0 0
0 19 NE 6
14 5
0 0
0 25 ENE 9
8 0
0 0
0 17 E
9 7
0 0
0 0
16 ESE 9
4 0
0 0
0 13 SE 10 4
0 0
0 0
14 5
SSE 9
10 0
0 0
0 19 S
15 3
0 0
0 0
18 SSU 5'
5 0
0 0
0 10 SU 9
17 1
0 0
0 27 USU 20 23 0
0 0
0 43 U
10 11 0
0 0
0 21 UNU 7
6 0
0 0
0 13 j
NU 7
1 0
0 0
0 8
eh NNU 2
11 0
0 0
0 13 gn j
TOTAL 133 151 18 0
0 0
302 e
m PERIODS OF CALM (HOURS):
9 5
UARIABLE DIRECTION 54 HOURS OF MISSING DATA:-
183
..e
.:,4s
,we-c.
...w.p.
,.,s e
e,
,m.,,
.,,,.y,o-
.,s.+,v.-.
..v%.
+v.
4,w..
em..,
w m-
_..,..w,,,.w.y
- m...
me.
w,,_,
,w.
ATTACIMENT 3C (continued) 7 cf 8
=,
HOURS AT EACH UIND SPEED AND DIRECTION-PERIOD OF RECORD =
89100181-89123124 STABILITY CLASS:
G DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M WIND SPEED (ffH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
9 1
1 0
0 0
11 NNE 7
2 0
0 0
0 9
NE 13 5
0 0
0 0
18 ENE 12 5
0 0
0 0
17 E
20 1
0 0
0 0
21 ESE 11 0
0 0
0 0
11 SE 6
2 0
0 0
0 8
SSE 6
6 0
0 0
0 12 S
7 0
0 0
0 0
7 SSU 4
6 0
0 0
0 10 SU 13 22 0
0 0
0 35 USU 23 15 8
0 0
0 38 U
16 11 0
0 0
0 27-UNU 13 3
0 0
0 0
16 NU 8
1 0
0 0
0 9
NNU 12 4
0 0
0 0
16 d4 oy 09 l
TOTAL 180 84 1
0 0
8.
265 2
g l
PERIODS OF CALM (HOURS):
9 it 4
VARIABLE DIRECTION 54 l
HOURS OF MISSING DATA:
183 l
L.
s.-
c
~
- 7...
p e
i ATTACHMENT 3C frontinued) 8 of 8-HOURS AT EACH UIND SPEED;AND' DIRECTION
- PERIOD OF: RECORD
-e -
89100181-89123124
-STABILITY CLASS:
ALL :DT/DZ ELEVATION:
SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60M UIND SPEED (PPH)
UIND DIRECTION
'1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
31 57
-30 3
0 0
- 121 NNE 16 44 58 10 0
0 128 NE 33 82 72 18 0
0 205 ENE 39 59 20 3
0 0
121 E
42 44 9-0 0
0 95 ESE 29 26
.4 0
0 0-59 SE 30
-44 10 0
0 0
84 SSE 41
.56 2
0 0
0 99 S
41 46 8
0 0
0 95
~
SSU 24 45-19
.7 0
0 95 SU 38 107 26 2-0 0
173 USU 57 114 39
-0 0
0' 210 U
44 86-50 4
^8 0
184 UNU 40 60 23 4
0-0 127 5>
NU 23 48 18 4
0 8.
93
$4 NNU 29 66 35 6
0 0
136 gg
________________________________________________________5
{
TOTAL 557 984 423 61 0
0.202 g
Y PERIODS OF CALM (HOURS):
.9 VARIABLE DIRECTION 361 HOURS OF MISSING DATA:
183
-r.
~...,
n
^ ^ ~ ~ ~ ^ '
r1
~
Jf.i
- ATTACIMENT 4A.-. JOINT-FREQ'KNCY: TABLES OF WIND SPEED ~
1.of 8; j,,
AND DIRECTION'60m VS DELTA TEMPERATURE 60-10m 4 ;t;p JULY ~1, 1989 THROUGH DECEMBER 31, 1989
_ 1q
.s4 5
HOURS AT'EACH UIND. SPEED AND DIRECTION PERIOD OF RECORD =
89070181-89123124 STABILITY CLASS:
A DT/DZ-ELEVATION:
SPEED:SPD60M DIRECTION:DIR60M LAPSE:DT60M UIND SPEED (PPH)
UIND DIRECTION 1-3
'4-7 8-12 13-18 19-24
'.>24 TOTAL N
1 2-0 0
0 0
3 NNE 1
2 4
1 0
0 8
NE 1
5 9
12 1
0 28 ENE O
4 6
6 0
0 16 E
2 3
4
'1 0
0 10 ESE 1
3 0
0 0
0 4
SE 1
3 0
0 0
0 4
SSE 1
'1 1
0 0
0 3
S 0
2
.0 0
0 0
2 SSU 0
4 2
0 0
0 6
SU 0
4 5
4 0
0 13 USU 0
9 26 15 1
0 51 i
U 0
9 26 13 5
0 53 l
UNU 0
1-5 5
5 0
16 NU 0
0 1
2' 1
0 4
k- }>
NNU 1
2-1 1
0 0
5 1o-TOTAL 9
.54 90 60 13-0 226 2:
E PERIODS OF. CALM (HOURS):-
4
=
UARIABLE DIRECTION 23 i_
HOURS OF MISSING. DATA:
391 l
,.2_
~. a. ~
~
~.
.,_.a.
99
~
ATTACIMENT 4AL(continued)'
2 Gf ;8 '-
HOURS AT EACH UIND SPEED AMO DIRECTION PERIOD.0F RECORD =.
89070101.-89123124 STABILITY CLASS:
B DT/DZ-ELEVATION:
SPEED:SPD60M DIRECTION:DIR60M L' APSE:DT60M WIND SPEEDGPH)
UIND DIRECTION 3 4-7 8-12 13-18 19 >24 TOTAL N
1 3
1 0
0 0
5 NNE 2
4 3
4 0
0 13 NE O
9 12 10 2
0 33 ENE O
7 11 2.
0 0
20 E
2 7
7 0
0 0
16 ESE O
2 3
0 0
0 5
SE 1
2 0
'O 0-0 3-SSE O
5 0
0 0
0 5
S 1
6 3
0 0
0 10 SSU 0
4 4
2 0-0 10 SU 0
9 10 1
0 0
20 USU 2
10 17 4
0 0
33 U
1 5
12 7
0 0
25 UNU 0
7 7
1 1
0 16 NU 0
1 4
2 1
0 8
.,3 f:
E@
TOTAL 13 84 98 35 4
0 234 s
PERIODS OF CALM (HOURS):.
4 E'
'4 -
VARIABLE DIRECTION 43 HOURS OF MIBSING DATA:
391
..,.a..
.._.m.,
. _ _ _ _ _.... _ -..,.,... =
=
n,
=--. :.
7 p..
a-
' ATTACittENT 4A (continued)'
- 3 cf 8
. HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =
89070101-89123124-STABILITY. CLASS:
.C DT/DZ LAPSE:DT60M
_______________~ SPEED:SPD60M DIRECTION:DIR60M ELEVATION:
UIND SPEEDOFHT WIND DIRECTION 1-3 4-7.8-12 13-18 19-24.
>24 TOTAL N
2 5
4 0 0 11 NNE O
6 2
1 0
0 9
NE 2
9 7
11 1
0 30 ENE 1
6 20 0
1 0
28 E
O 4
6 0
0 0
10 ESE 3
6 3
0 0
0 12 SE 1
3 7
0 0
0 11
[
SSE 1
8 0
0 0
0 9
S 1
8 0
0 0
0 9
SSU 2
5 2
3 1-0 13 SU
~1 12 13 3
0 0
29 USU 2
8 20 4
8 0
34 U
.1 15 16 1
0 0
33 UNU 0
7 6
1 1
0 15
$>4 5
NU 0
7 6
0 0
0 13 NNU 2
2 5
3' O
O 12 f-3
-2 TOTAL 19 111 117-27 4
.0 278 l
E
~~isissS s~~CE-~nssaS s-~~~~~~~~ ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
i
~
VARIABLE DIRECTION 44-l HOURS OF MISSING DATA:
391
~ >~
j 6..
2
+..
-e
- w'k
- + -
+s e
v--
e.
w
- a..,7 I 4 Gf 8 -
"ATTACIMENT sA (continued)-
e HOURS AT EA'CH WIND SPEED AND DIRECTION
~ PERIOD ~OF RECORD ='
.89070181-89123124 STABILITY CLASS:
D
.DT/DZ
- ELEVATION:
- SPEED:SPD60M DIRECTION:DIR60M LAPSE:DT60M UIND SPEEDCIPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19 ~ >24 TOTAL N
9 39 28 22 1
0 99 NNE 7.
43 31 30 1
0 112 NE 10 37 62 56 10 0
175-ENE 10 36 44 6
1 0
97 E
6 28
' 23 2
0 0
59 ESE 8
17 29 2
0 0
56 SE 3
17 28 2
0 0
50 SSE 8
18 13 2
0 0
41 S
3 26 14 2
0 0
45 SSU 4
19 24 4
0 0
51 SU 2
17 36 6
2 0
63 USU 4
20 31 18 1
0 74 U
5 14 21 19 3
0 62 UNU 8
13 14 7
3 1
46 NU 2
13 26.
7 1
2 51 5>
NNU 10 35.
31 17 5
1 99 j [
TOTAL 99 455 202 28 4-1180
=
________________________392______________________________________'
. E'
- t:*'
PERIODS OF CALM (HOURS):
~4 HOURS 0F MISSING DATA:
391 VARIABLE DIRECTION 141.
- en g-w-
r e-=
4&y-
-#,gw-
.,w.,
ee.asi
,.gcgy,-g9y
,y,y.,
y-
.ay%,
,r 3
c%
y
-,q,
+
.,ywwr-s,e mm-
,gs gy,we%,%,g_,
,,y, e,e
y.
.~
a7
,w vn
= - -
g:n
~
m
g ATTACHMENT 14AL(continued).
- 5 Gf 8 ~ _ ~
HOURS AT EACH UIND SPEED ANDl: DIRECTION
~ PERIOD'0F RECORD =
89070181-89123124.
STABILITY.' CLASS:.
E.
DT/DZ
- ELEVATION:
SPEED:SPD60M DIRECTION:DIR60M LAPSE:DT60M UIND SPEED (PPH)
UIND DIRECTION
'1-3 4-7' 8-12 13-18 19-24
>24 TOTAL N
7
'19
- 17 3
0 1
47 NNE 11 25 36 22 0-1 95 NE 7
17' 52-54 7
0 137 ENE 4
23 48 8
0 0
83 E
3 32 33 4
0 0
72 ESE 5
'25
-34
~3 0
0 --
67
~ '
SE 3
23
~42 6
0 0
74 SSE 5
41 42 2
0 0
90 S
5 44 34 5
1 0
89 SSU
'3 19 36
.18 6-
'1 83 SU 0
19 54 26-0 0
99 USU 5-
'11 34 32 2
0 84 U
3 10 24 31 5
1 74 UNU 4
4' 23 15 4
0 50 3,j '
NU 6
9
' 20 '
4 0
0' 39 NNU' 3
10 10 12 0
0 *>
lg o.
TOTAL 74 331 539 245 25 4
1218 E'
______________________________________ _______________________' g PERIODS OF: CALM (HOURS):
'4-
-t VARIABLE DIRECTION-
'61 HOURS OF MISSING DATA:
- 391 1
+
,_.~
2 _
.~
, y..
~
j P.
1 ATTACHMENT!4A-(continued)I-6 cf:8:
' HOURS AT EACH UIND SPEED AND DIRECTION PERIOD:0F RECORD =
89070181-89123124 STABILIT/ CLASS:
F.
DT/DZ ELEVATION:
SPEED:SPD60M DIRECTION:DIR60M LAPSE:DT60M UIND'SPEEDGPH)
UIND DIRECTION 1 -3 ' 4-7 12 13-18 19-24
>24' TOTAL N
5 8
.7 1
0 0
21 NNE 1
12 11 14 0
0 38 NE 1
9 8
18 2
0 38 ENE O
11 17 4
0 0
32 E
1 9
'16 6
0 0-32 ESE 1-3 LEO 0
0 0
24 SE 1
6 7
3 0
0 17 SSE 4
4' 14 6
0 0
28 G
S 4
23 7
2 0
0 36 SSU 2
7 25 3
0 0
37 SU 4
9 36-20 0
0 69 USU 4
8 21 34 0~
0 67 U
0 6
-20 16 0
0 42 UNU 3
7 8
8-0 0
26 NU 1
6
'11
-1 0
0 19
}>{
m NNU 1
-4 10 2
0 0
17 o
TOTAL 33 132 238 138 2
0 543.
- O'_
E m
PERIODS OF CALM (HOURS):--
4-2 UARIABLE DIRECTION- [
HOURS OF-MISSING DATA:
391
+ *
,~
x c
~
~ATTACIMENT 4A-(continued)-
7 Gf. 8 ;
HOURS AT-EACH UIND2 SPEED AND. DIRECTION PERIOD OF RECORD =--
89070101-89123124 STABILITY CLASS:
G DT/DZ -
ELEVATION:
SPEED:SPD60M DIRE'CTION:DIR60M LAPSE:DT60M WIND SPEED (PPHY UIND DIRECTION 1 4-7 8-12 13-18 19-24
>24. TOTAL-N 1
2 0
0:
0 0
3 NNE 2
4 0
1 0
0 7
NE 2
8 1
0 0
~0 11 ENE 1
9-9 6
0 0-25 E
2 2
14-0 0
0
- 18 ESE 5
7-4 0
0 0
- 16 SE 2
12 6
0 0
0 20 3
SSE 3
.11 14 2-0 0
30 S
2 8
5 2
0 0
17 SSU 0
6 13 5
0 0
24-SU 3
3 16 13 1
0 36 USU 1
6 15 22 1
0 45 U
1 8
16 20 0
0 45 UNU 2
9 8-3 0
0 22 NW 2
5 7
0 0
0 14 h
TOTAL 30 103
~137 74 2
0 346-g PERIODS OF CALM (HOURS):
4 E,
A VARIABLE DIRECTION 7
k HOURS OF MISSING DATA:
~391
.e g-
_-r,
-~
w r*-
4 e
"s
-t w
t-v#n -
==-e+.1~w-NN+-
r Fw-
-T--
-s #v*
-t v +
+
~s-
.y
. ~ -e
s;
-v n, :7 =
Q '~.~ ~
~.; L,
~ f. __,,'~
..z - q 3
,<- *- e ;
~
-ATTACHMENT 4A (continued) 8 cf 8:
HOURS;AT EACH UIND SPEED AND DIRECTION PERIOD:OF RECORD =
89070181-89123124 STABILITY CLASS:
ALL DT/DZ ELEVATION:
SPEED:SPD60M DIRECTION:DIR60M LAPSE:DT60M UIND SPEED (PPH) ~
UIND
~
DIRECTION 1-3 4--7 ~ 8-12 13-18.19-24
>24 TOTAL.
N 26-78 57 26
'1 1
189 NNE 24 96'
'87 73-
.1 1
282 NE 23 94 151 161 23 0
452-l ENE 16 96 155 32 2
0 301 l
E 16 85 103 13 0
0 217 ESE 23 63
-93 5
0 8
184 SE 12-66 90 11 0
0 179 SSE 22 88 84 12~
0 0
206 G
S 16 117 63
- 11 1
0 208 SSU 11
'64 106
'35 7
1 224 SU 10 73 170
'73 3
0 329 USU 18
.72 164 129 5
0 388 U
11 67
'135 107
-13 1
334 UNU 17 48 71 40 14 1
191 NU 11 41 75-16~
3 2
148 5>
-$ h-NNU 21 59 70
~37 5
1 193 gg.
TOTAL 277 1207 1674 781.
78 8
4025
=-
E:
PERIODS OF CALM (HOURS):
4
{
UARIABLE. DIRECTION
'343 HOURS OF MISSING' DATA:
-391 l
l.
s.
~
=,,,,
~."' ~
- ; N ~-
~
' i}
~_
,y
~
~ ATTACHMENT'4B. " JOINT FREQUENCY ~TABLEST0F WIND SPEED:
- 1. cf 8 ';
F; AND' DIRECTION 60m VS' DELTA TEMPERATURE 60210m
? JULY -1,1989 THROUGH SEPTEMBER 30, 1989:
h0URS AT:EACH. WIND. SPEED.ANDTDIRECTION PERIOD ~OF' RECORD =
-89870181-89093024-STABILITY CLASS:
A' DT/DZ ELEVATION:
SPEED:SPD60M DIRECTION:DIR60M ' LAPSE:DT60M UIND SPEEDGPH).-
UIND DIRECTION 1-3
- 4'-7. 8-12 13 18 19-24
>24 TOTAL N
1 2
8.
-0 8.
0 3
NNE O
1 0-0 0
0-1 NE 1
3
- S 7
0 0
16 ENE O
2.
5 2
0 0
9 E
2-3 3-0 0
0 8
ESE 1
2 8.
0 0
0 3
SE 1
3 0
0 0
0 4
G SSE O
L1 1
0 0
0 2
'S 0
2-0
-0 0
0 2
SSU 0
3 1
0 0
0 4
SU 0
4-1 1
0 0
6 USU 0
7 12 3
0 0
22 U
0 8
16 5
0 0
29 UNU O'
1 1
1 0
0 3
NU O'
O O
O O
O O
5>
$ f:
NNU 0
1 0
1 0
0 2
g;g 2
TOTAL 64
-43:
-45 20 0
0 114 E,
PERIODS OF CALM (HOURS):
3 l4 VARIABLE-DIRECTION, 16-.
HOURS OF MISSING DATA:'
213~
..u.
~
~ _ -,,
,. ~. _.
~
~
~
w
~-
~
' ?'l l {_ _'
ATTAC}MENTf48 (continued)-
^2 cf 8 h
HOURS AT EACH UIND SPEED AND; DIRECTION PERIOD OF RECORD,=~
89070101-89093024.
STABILITY CLASS:
B DT/DZ ELEVATION:-
SPEED:SPD60M DIRECTION:DIR60M-LAPSE:DT60M UIND SPEED (PPH)
UIND.
DIRECTION 1 -3
'4' -7 8-12 13-18 19-24
>24 TOTAL N
1 2
0:
0 0
0 3
NNE 1
2 0
0-0 0
3 NE O
7 4
6 2
0 19 ENE O
5 9
0 0
0 14 E
2 4
5
'O O
O' 11 ESE 0-1 1
'O 0-0 2
SE 1
0 0'
'O 0-0 1
G SSE O
4 0
0 0
0 4
S 1
2 2
0 0
0 5
~
SSU 0
'4 2
L1, 0
0 7
SU 0
9 5
0
- 0 0
14 USU 1
9 10 0
0 0
.20 U
1 4
9 1
- 0 0
15 UNU O'
2 2
0 0-O' 4
NNU 3
1 0'
O.
0 0
4
- $g>
N NU 0
1 2
'O O
O 3
4' i
l
=.
l TOTAL 11 57 51 8
2 0
129 E
t re l
PERIODS.0F CALM (HOURS):'
3 j!
VARIABLE-DIRECTION 36
.y HOURS-OF MISSING DATA:
213 l
s
.. ~
y J
- ATTACIMENT'4BL(continued)
- 3 of 8 HOURS.AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
89070181-89093024 STABILITY' CLASS:
C DT/DZ -
ELEVATION:'
SPEED:SPD60M DIRECTION:DIR60M LAPSE:DT60M WIND SPEED (MPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
2 5
'2 0
0 0
9 NNE O
3 1
0 0
0 4
'NE-0 7
3 7
0 0
17 ENE O
4 13 0
1 0
18 E
O 3
4 0
0 0
7 ESE 2
3 2
0 0
0 7
SE-0 2
1 0
0 0
3 SSE O
5 0
0 0
0 5
0 S
1 4
0 0
0 0
5 SSU 1
4 1
0 0
0 6
SU
.1 9
7 0
0 0
17 USU-1 5
8 1
0 0
15 U
1 11 7
0-0 0
19 UNU 0
4 2
0 0
0 6
NU 0
4 0
0 0
0 4
y>'
m NNU 2
- 1 0
0 0
0 3
I>O TOTAL 11 74 51 -.
8
-1 8
145 g
l PERIODS-OF CALM (HOURS):
3 x-VARIABLE DIRECTION.
27
[
j HOURS OF MISSING DATA:
213 i-1 l
.=
.s
s.
.=
hTTACHMENT~4B (continued)-
' 4 of 8
+
HOURS:AT'EACH. WIND SPEED AND DIRECTION PERIOD OF RECORD?=-
89070181-89093024-STABIL.ITY CLASS:
D.
.DT/DZ ELEVATION:
SPEED:SPD60M DIRECTION:DIR60M LAPSE:DT60M UIND'SPEEDGPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
.>24' TOTAL N
3 27 14 11 1
0 56 NNE 4
27 16 5-
.0 0
52 NE 5
20 33 33 4
0 95 ENE 6
20-25 3
1 0
55 E
3 18 20-2 0
0 43
'ESE 5
9 22'
'1 0
0 37 SE' 1
10~
11 0
0 0
22
_g SSE 4
10 4
0-0 0
-18 S
2 11 4
0 0
0 17 SSU 2
9 13 1
0 0
25 SU 1
7 21 0
0 0
29 USU 1
13 16 3
0 0
33 U
5
'7 10 2
0-
-0 24 UNU
.4 7
4 0
0 0
15 NU
'O 6
2 0
0-2 10
- A>
~
2 1
44 d
l NNU 4
~19 14
'4-eg b
ca 9 r
. TOTAL 50 220 229' 65 8
3 575 e
s PERIODS OF CALM (HOURS):
3.
E.'
-3 '
UARIABLE DIRECTION 75 HOURS OF MISSING DATA:-
213 l..
~
,.. ~
.. ~.;
~
^
~
.g a:
. ATTACHMENT 48'(continued).
5 ef2 8 -
7
- 7;
"=
' HOURS AT EACH.UIND SPEED AND DIRECTION PERIOD OF RECORD =
89070101-89093024 STABILITY CLASS:
E:
~DT/DZ-ELEVATION:
SPEED:SPD60M~ DIRECTION:DIR60M. LAPSE:DT60M
.- d -
4 WIND. SPEED (ifH)
UIND 3
DIRECTION 3 4-7.
8-12 13-18 19-24
>24 TOTAL' N
6 15-10 1
0
-1 33 NNE 8
~20 26 7
0 1
62-NE 2
12
'42 27 3
0 86 ENE 4
14 26 3
0:
0 47 l
E 2
29 27 2
0 0
60 ESE 3
22-30 2
0 0
57 SE 2
19 32 3
0 0
56 SSE 4
33.
18 2
0 0
57 l
S 4-27 21 1
1
.0 54 SSU 3
~14 21 7-0 0
45 SU 0
11 39
.7 0
0-57 USU 3
8 17 5
0 0-33 U
3-7 13 4-0 1
28 UNU 2
3 3
2 0
0 10 NU 5-7
~5 1
0 0
18 N>
.k}
NNU 3
2-1 3
0
-0 9
g TOTAL 54 243 331 77-4 3
712
+
2 E-
_ r= :
PERIODS OF'CALMCHOURS):
- 3.;
z
[
VARIABLE DIRECTION.
.46 HOURS OF MISSING DATA:
213
.~
.m...
c,
.- u
. =.
~, _
.,a LATTACHMENT4B(continued)'
~6 of'8-HOURS AT:EACH UIND SPEED-AND' DIRECTION PERIOff0F.REdORD =
89070101-89093024 STABILITY CLASS:
F DT/DZ-ELEVATION:
7 SPEED:SPD60M DIRECTION:DIR60M LAPSE:DT60M UIND SPEED (l'PH).
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
3 4
3 1
0 0
11 NNE 1
7 3
2' O
O 13 flE O
4 1
0 0
0 5'
ENE O
5 2
0 0
0 7
E 1
5 6
0.
0 0
12 ESE 1
1 16 10 0
0 18 SE 1
3 2
0 0
0 6
G SSE 3
.4 7
0 0
0 14 S
1' 7-3 2'
O O
13 SSU
.1 3
17 3
0 0
24 SU 4
8
.28 ~
6 0
0 46 USU 3
6 12 10 0
0 31 U
0 4
-12 2
0 0
.18 UNU
'1 3
2 3
0 0
9 NU O'
S 3.
0 0-0 8
NNU 0
2:
2 1
- 0 0
5 j#;
a 30' TOTAL 20 71.
119
~30 0
~240
_----____--_-__--___-----_-__---____-_______'0
- z.,
,m' PERIODS OF CALM (HOURS):
3
'N UARIABLE DIRECTION-14 HOURS OF' MISSING. DATA:
-213
.n
-. ~.
=-
Iq f
' ATTACHMENT:4B (ctntinued).
L7 of.8--
1
~ HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
'89070101-89093024 STABILITY CLASS:
G
.DTdDZ
' ELEVATION :~.
SPEED:SPD60M DIRECTION:DIR60M LAPSE:DT60M
~UIND SPEED (PFH7 UIND-DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
'1 0
0 0
0 0
1 NNE 1
0 0-0 0
0 1'
NE O
1 0
0 0
0 1
ENE O
1 1
0 0
0 2
E O
1 5
0 0
0 6
ESE 1
2 3
0 0
0 6
SE O
3 3
0 0
0 6
l G
SSE 2
2 2
0 0
'O 6
S 1
3 0
0 0
0 4
SSU 0
2 5
0 8.
8.
7 SU 1
0 8
5 0
0 14 LEU 1
3 1
1 0
0 6
i U
1~
6
~4 2
0 0
13 UNU 0
1 2
.0 0
0 3
NU 0
0.
.2 0
0-0 2
.,>l+
NNU 0
.1 1
0 0
0 2
4
,O_
TOTAL 9
26 37 8
0 0
80 g-te PERIODS OF CALM (HOURS):
3
.. x VARIABLE DIRECTION 3
VE HOURS OF MISSING DATA:
213 l
l
~
J;;
e ATTACIMENTL4B (continued).
8Tcf 8.-
' HOURS AT~EACH UIND SPEED'AND DIRECTION PERIOD'0F RECORD-=
- 89070181-89093024 STABILITY. CLASS:
ALL DT/DZ ELEVATION:
SPEED:SPD60M DIRECTION:DIR60M-LAPSE:DT60M UIND SPEEDGPH)
UIND-
. DIRECTION-1-3 4 8-12 13-18 19-24
>24 TOTAL N
17 55 29:
13 1
1 116 NNE 15 60 46 14 0
1 136 NE 8
54 88
'80 9
0 239 ENE 10 51 81 8
2 0
152 E
10 63 70 4
0 0
147 ESE 13 40 74 3
0 8
130 SE 6
40' 49 3
0 0
98 SSE 13 59' 32 2
0 0
106 S
10 56 30 3
1 0
100 SSU 7
39
-60 12 0
0 118 SU 7
48 109 19 0
0 183 USU 10 51
~76 23 0
'O 160 U
11 47 71 16 0
1 146 UNU 7
21 16 6
0 0
50
$g>
N NU S
23 14 1
0 2
45 d
NNU 12 27
-18 9
2 1
69 TOTAL 161
-734
~863 216-15 6
1995 2
2 E
PERIODS-0F CALM (HOURS):
.3
.j UARIABLE DIRECTION.
217 p
HOURS OF MISSING DATA:
213 l
s
.n-'
',7
- 1 ~of 8
' ATTACHMENT 4C.-
JOINT' FREQUENCY TABLES OF WIND SPEED
~AND DIRECTION 60m VS DELTA-TEMPERATURE 60-10m OCTOBER 1, 1989 THROUGH DECEMBER 31, 1989 HOURS AT'EACH UIND SPEED AND. DIRECTION' PERIOD OF RECORD =
89100101-89123124 STABILITY CLASS:
A
~DT/DZ ELEVATION:~
SPEED:SPD60M DIRECTION:DIR60M LAPSE:DT60M UIND SPEED (PPH)
UIND DIRECTION 1-3 4-7 8-12'13-18 19-24
>24 TOTAL-r N
0.
0 0
0 0'
O O
NNE 1
1 4
1 0
0 7
NE O
2 4
5 1
0 12 ENE O
2 1
4 0'
O 7
E O
O 1
1 0
0 2
ESE O
1 0
0 0
0 1
SE O
O O
O O
O O'
2 SSE 1
0 8.
0 0
t' 1
S 0
0 0
0 0
E O
SSU 8
1 1
0 0
9 2
SU 0
0 4
3 0
0 7
USU 0
2 14 12 1
0 29 U
0 1'
10 8
5 0
24 UNU 0
0 4
4 5
0 13 NU 0
0 1
2 1
0 4
j '
NNU 1
1 1
0 0
0 3
E>g!
TOTAL 3
11 45 40 13 8.
112
- 3g, PERIODS OF CALM (HOURS):
1 4
VARIABLE DIRECTION 7
HOURS OF MISSING DATA:
178
^
-"^ '.
W "F
er
'f"5' f
M 1
1' W('
'*T'>
"'F**
'*'%F1'-W+*-
=
vN P v* m
..n,.-
.,n_;
~
f ATTNC19 TENT 4C (continued)-
- 2 cf.8, HOURS AT EACil UIND SPEED AND DIRECTION PERIOD OF RECORD --
89100181-89123124 STABILITY CLASS:
.B
. DT/DZ' ELEVATION:
SPEED:SPD60M DIRECTION:DIR60M : LAPSE:DT60M WIND SPEEDGPH)
UIND DIRECTION 1-3 4-7 8-1'2 13-18 19-24
>24 TOTAL N
~0 1
1 0
0 0
2 NNE 1
2 3
4 0
0 10 NE O
2 8
4 0
0 14 --
ENE O
2 2
2 0
0 6
E O
3.
2 0
-O O
5 ESE O
1' 2
0 0
0 3
SE O
2
~0 0
0 0
2 SSE O
1 0
0-0 0
1 E
S 0
4 1
0 0
0 5
SSU O'
O 2
1 0
0 3
SU 0
0 5
1 0
0 6
USU 1
1
-7 4
0 0
13 U
0 1
3 6
0 0
10 UNU 0
5
'5-1 1.
0 12 NU 0
0 2
2~
1 0
5 j k NNU 0
2 4
2 0
0 8
a g:
Sg TOTAL 2-27
~47 '
27 2
- 8 105 g
j i
PERIGDS OF CALM (HOURS):
1 Q;
VARIABLE DIRECTION 7
-a -
HOURS OF MISSING DATA:
178
.~
_e.r,
.w.
._-,...u
_2_,_,.
_,______.m
.._..m_______~_m___..m._._,.__z_._._..mm
.m _ b, m.
~
~
gj r e:
c
'J
_.g
~
' ATTACHMENT lL4C -(continued)'.
~3 Gfi :
8 HOURS AT'EACH UIND SPEED AND DIRECTION-PERIOD OF' RECORD'=
89100181-89123124 STABILITY' CLASS:
C DT/DZ..
ELEVATION:
SPEED:SPD60M DIRECTION:DIR60M-LAPSE:DT60M
~
WIND SPEEDGPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19.>24 TOTAL N
O O
2 0
0 0
2 NNE O
3 1
'1 0
0 5
NE 2-2-
4 4
1 8.
13 ENE 1
2 7
0 0
0 10 E
O
-1 2
0 0
0 3
ESE 1
3 11 0
0' 8
5 SE 1
1 6
0 0
0 8
SSE 1
3 0
0 0
0 4
S 0
4
O
.0 0
0 4
SSU 1
1 1
~3 1
0 7
SU 0
3 6
3 0
0 12 USU 1
3 12 3
0 0
19 U
0 4
9 1
- 0 0
14 UNU O'
3
~4 1
1 0
9 i
,y.
l NU 0
3 6
0 0
0
'9 4.$
~
NNU 0
1 5
3 0
0 9
EO TOTAL 8
37 66 19
- 31 0
133 2
g PERIODS OF CALM (HOURS):
1 4
VARIABLE DIRECTION 17 HOURS OF MISSING DATA:
178 I
t u
.,r
- y.
.-,..L._,.
...y,
-s...r 4
..__,_.___,___m_m,,m___,____
...m..
m i
- (,
cgn
~
ATTACHMENT 4C (continued)~
4 sf 8 2 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD'= '
'89100181-89123124
^ STABILITY CLASS:
D DT/DZ '
ELEVATION:
SPEED:SPD60M DIRECTION:DIR60M LAPSE:DT60M WIND SPEED (IPH)
P UIND DIRECTION 1-3 4-7 8-12'13-18 19-24
>24 TOTAL N
6 12 14 11 0
0 43 NNE 3
16 15 25 1
0 60 NE 5'
17 29 23 6
0 89 ENE
-4 16 19 3
0 0
42 E
3 10 3
0 0
0 16 ESE 3
8 7
1 0
0 19 SE 2
7 17 2
0 0
28 C
SSE 4
8 9
2 0
0 23 S
1 15 10 2
0 0
28
~
SSU 2
10 11' 3
e 0
26 SW 1
10 15 6
2' 0
34 USU 3
7 15 15-1 0
41 U
0 7
11 17 3
0 38 UNU 4
6
.10 7
3 1
31 5>'
NU 2-7' 24
--7 1
0 41
$f' NNU 6
.16' 13 3
0 55
_______________________________'17 l
. gn L
TOTAL 49 172 226 137 20 1
605
.E PERIODS OF CALM (HOURS):
1 5.'
UARIABLE DIRECTION 66 HOURS OF MISSING' DATA:
178 w--
~
g y-r,
,p.
y uns m
.g--
e+
w r
- e. 4
_, +--,
w..-
.Nr sws--
~~u_w,-
U-v - w -,-
.7 z.
-d Y
-ATTACHMENT:4C (continued)'"'
,S of 8;-
r
~ HOURS AT EACH UIND SPEED.AND-DIRECTION PERIOD OF RECORD =
89100181-89123124 STABILITY-CLASS:-
E
- DT/DZ '-
ELEVATION:
' SPEED:SPD60M DIRECTION:DIR60M' LAPSE:DT60M UIND SPEEDG'PH)
. WIND DIRECTION 1 4-7 8-12 13-18 19-24
>24 TDTAL N
1 4
- 7 2
0 0
14 NNE 3
5 10 15' 8
0 33 NE 5
5 10
- 27 4
0 51 ENE 0
9 22 5
0 0
36 E
1' 3
6 2
0 0
12 ESE 2
3 4-1 0
0 10 SE 1
4 10 3
0 0
18 SSE 1
8 24 0
0 0
33 S
1 17 13 4
0 0
35 SSU 0
5 15 11 6
1 38 SU 0
8 15 19 0
8 42 USU 2
3 17
- 27 2
0 51 U
-0 3
11 27 5
0-46 UNU 2
1 20 13 4
0 40 NU 1
2 15 3
0 0
21 l
NNU 0
8 9
9.
0 0
26 Aa eg E@
TOTAL 20 88.
208
~168-21 1
506 E-PERIODS OF CALM (HOURS):
1
^Q VARIABLE DIRECTION 15 4>
HOURS OF' MISSING DATA:
178 a
r
'M
^
' ~<
- ___i,
,er.
m
,, _ _m
m
..t v'
- ATTACHMENT'4C (continued)
- 6 c f 8 ~.
HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =
-89100181-89123124 STABILITY CLASS:.
F.
.DT/DZ
. ELEVATION:
SPEED:SPD60M DIRECTICH:DIR60M LAPSE:DT60M WIND SPEED (ifH)-
UIND DIRECTION 1-3 4-7.8-12 13-18 19-24
>24 TOTAL N
2 4
4-
'O O
O 10 NNE O
5 8
12 0
0 25 NE 1
5
-7 18 2
0 33 ENE O
6 15 4
0 0
25 E
O 4
10 6
0 0
20 ESE 0-2
'4 0
0 0
6 SE O
3 5
3 0
0 11 U
SSE 1
0 7
6 0
0 14 S
3 16 4
0 0
0 23 SSU 1
-4 8
0 0
0 13 SU 0
1 8
14 0
0 23 USU 1
2-9 24 0
0 36 i
U 0
2 8
14 0
0 24 UNU 2
4 6
5 0
0 17 NU 1
1 8
1 0
0 11 v>~
NNU 1
2 8
1 0
0 12 44 ag
~ E O ;-
TOTAL 13 61 119 108 2
0 303 g
- e PERIODS OF CALM (HOURS):
1 z4 UARIABLE DIRECTION 10 HOURS OF MISSING DATA:
178 F
- s
' ATTACHMENT 4C (continued) 7 of.
HOURS AT EACH UIND SPEED-AND DIRECTION PERIOD OF' RECORD =
~89100181-89123124 STABILIT/ CLASS:
G DT/DZ ELEVATION:
SPEED:SPD60M DIRECTION:DIR60M LAPSE:DT60M UIND SPEED (IPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
O 2
0 0
0 0
2 NNE 1
4 0
1 0
0 6
NE 2
7 1
0 0
0 10 ENE 1
8 8
6 0
0 23 E
2 1
9 0
0 0
12 ESE
.4 5
1 0
0 0
10 SE 2
9 3
0 8.
0 14 5
SSE 1
9 12-2 0
0 24 S
1
-5 5
2 0
0 13 SSU 0
4 8
5 0
0 17 SU 2
3 8
~8 1
0 22 USU 0
3.
14 21 1
0 39 W
0 2
12 18 0
0 32 UNU 2
8 6
3 0
0 19 NU 2
5 5
'O O
O 12 k' > '
NNU 1
2 8
0 0
0 11 3; }o l
TOTAL 21 77
--100.
66
.2 0
266 m.
l E
l PERIODS OF CALM (HOURS):
1 m.
VARIABLE' DIRECTION 4
5 HOURS OF MISSING DATA:
178 l
_ _ _ - - _ _ =. _ _
,M t%'T r
ATTACHMENT'4C (continued)
' 8 cf 8
~
^
~
HOURS AT EACH UIND SPEED AND DIRECTION
' PERIOD OF RECORD =
89100181-89123124 STABILITY CLASS:
'ALL DT/DZ.
ELEVATION:
- SPEED:SPD60M DIRECTION:DIR60M LAPSE:DT60M UIND' SPEED (PPH)
UIND DIRECTION 3 4-7 8-12 13-18 19 >24 TOTAL.
N 9
23 28 13 0
0 73 NNE 9
36 41 59 1
0 146.
NE 15 40 63 81 14 0
213 ENE 6
45 74 24
-0 0
149 E
6 22 33 9
0 0
70 ESE 10 23 19
'2' O
O 54 SE 6
26 41 8
0 0
81
-g SSE 9
29
~52 10 0
0 100 S
6 61 33 8
0 0
108 SSU 4
25 46 23 7-1 106 SU 3
25 61 54 3
0 146 USU 8
21 88 106 5-0 228 U
0 20 64 91 13 0
188 UNU 10 27 55 34 14 1
141 NU 6'
18-61 15
-3 0
103
. m>-
"O TOTAL 116 473 811 565 63 2
2030 x-
- e PERIODS OF CALM (HOURS):
1.
z-4 VARIABLE DIRECTION 126 HOURS OF MISSING DATA:
178 l
s e,
.hw v..
y m.
wewa-p y
n
,-ra*
g
- =
---nr-p ir, g9g.
y y
p, y,34
.ewi=.y.-
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h ATTACHMENT A Page 58
-ATTACHMENT 5.
DAILY AND MONTHLY PLANT-V0GTLE PRECIPITATION JULY 1989 THROUGH DECEMBER 1989 I.
Precipitation Precipitation Date-(inches)
Date (inches) 7/3' O.63 10/1 2.43 17/4.
0.34 10/8 0.17 7/5 0.05 10/15 0.60
-7/9 0.03 10/17 0.41 7/12-1.67 10/18 0.41
-7/13 0.11 4.02 7/14" 0.09 7/15 0.70 7/16 0.14 7/19 0.78 7/20-0.59
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7/21 0.06 7/23 0.09
-7/24 0.11 7/27-0.08 7/28 0.83
'7/30 0.43 7/31 0.02 6.75 t
8/1 0.22 11/2 0.15 8/14 0.02 11/7 0.02 8/15 0.60 11/9 0.20 8/19 0.89 11/15 0.64 8/20 0.38 11/16 0.23
-8/24 0.20
'11/22 0.05 8/26 0.08-11/23
~0.65 8/27 0.02 11/26 0.05 8/28 0 ~.19 11/28 0.14 2.60 2.13
'i 9/5-0.38 12/7 0.45
-9/14 0.49 12/8 1.38 9/15 0.02 12/9 0.60
.9/21 3.66 12/12 0.64 9/22 0.72 12/13 0.06 9/24 0.06 12/18 0.13 9/25 0.13 12/19 0.56 9/26 0.24 12/31 0.45 9/28 0.11 4.27 9/29 0.08 5.89 Total = 25.66 inches
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f A*f7ACH' ENT A Z Page 61 ATTACHMENT 7. PLANT V0GTLE 1989 DATA
SUMMARY
The data collection on the Plant Vogtle meteorological tower varied somewhat during 1989, although the overall data collection remained [ I good. During the first half of the year there was only one minor problem with the 60m wind speed being out of service for about 4 days. However, during the second half of the year problems with the delta temperature (60-10m) caused the data collection percentages for pertinent parameters df (wind speed, wind direction and delta temperature) to be reduced to about 90%. Significant problems occurred af ter the passage of Hurricane Hugo with most parameters being bad f or a period of several days. The table below summarizes the data collection over the last 3 years. 1987 1988 1989 ~ 99.6 98.4 98.2 l Wind Speed 10m Wind Speed 60m 95.4 95.8 98.1 Wind Direction 10m 99.4 99.0 98.2 i Wind Direction 60m 99.1 99.0 98.5 Delta Temperature 60-10m 85.4 96.7 95.3 Temperature 10m 85.5 98.1 98.1 Dew Point Temperature 10m 82.5 78.8 95.2 Rainfall 99.8 99.5 97.7 i Composite WS, WD10m DT60-10m 84,9 95.8 94.9 WS, WD60m DT6G '10m 81.6 93.2 93.8 The wind roses f rom 10 and 60m continued to show good agreement between levels on the tower and with previous years. The peak direction sectors are the southwest, west-southwest and northeast with just about the same number of hours in each. During the first half of 1989, the winds from the southwest were more oormant. Duries the second half of the year, the northeast was the dormant sector. 139 5983A012690
ATTACTZ^ENT A Page62 e lhe table below sumarizes the joint f requency data of wind speed and direction 10m versus delta temperature 60-10m. Stability Category 1988 1989 A 6.6 9.8 8 5.8 4.7 C 6.8 5.7 0 28.0 30.6 E 28.5 28.0 i 13.9 12.4' G 10.4 8.8 The 1989 data showed a slightly higher percentage of unstable hours and correspondingly 1c4s hours of stable conditions. The temperature data in 1989 started out warmer than in recent years but ended up colder than recent years during most of the second half of 1989. This was particularly true of November and December which averaged - several degrees below normal. The rainfall total for 1989 equaled 45.28 inches which was considerably higher than recent years but just above average for a normal year. t $983A012690 140
+--,mn,,, 3 ATTACHMENT B H 3[ -r o .i 4 9k hh
- .y '
c t e t-1. -*s ~*=w%-m,s,s u~.r%%wn ~ ~#~ _ ~-,-es -cre.mr 4-me r, m m w anew -eve,r=r-e m Hi
r ATTACHZENT H Page1 TCblo 1-20 Georgia Power Company Vogtle Electric Generating Plant SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL LIQUID EFFLUENTS UNIT: 1 l Starting : 1-Jan-1987 Ending : 30-Jun-1987 TYPE CF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR % A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASEA, ALPHA)
CURIES 2.392E-03 1.124E-01 40 } 2.' AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.513E-09 1.047E-08 l
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A f
i B. TRIT 7UM
- 1. TOTAL RELEASE CURIES 1.934E-01 4.556E+01 40
- 2. AVERAGE DILUTED CONCENTRATION
) DURING PERIOD uCi/ML 2.032E-07 4.244E-06
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A C.
DISSOLVED AND ENTRAINED GASES l'. TOTAL RELEASE CURIES 1.103E-04 3.477E-03 50
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uC1/ML 1.159E-10 3.239E-10
.3. PERCENT OF APPLICABLE LIMIT N/A N/A c t t D. CROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 0.000E+00 0.000E+00 45 E. WASTE VOL RELEASED (PRE-DILUTION)
LIT 1.018E+06 3.559E+07 15 F. VOLUME OF DILUTION WATER USED LIT 9.508E+08 1.070E+10 15 ZCroes in this table indicate that no radioactivity was present above O d;tcetable levels. See Table 1-5 for typical LLD for liquid sample On31yses. 141
h ATTAC32ENT Q L Page2 I Tcblo 1-30 ' REPORT CATEGORY
- SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED, UNIT 1 TYPE' CF ACTIVITY
- ALL RADIONUCLIDES
) REPORTING PERIOD
- QUARTER # 1 AND QUARTER $ 2 YEAR 1987 l
l* CONTINUOUS RELEASES l
- BATCH RELEASES l
c....................__.............. UNIT
- QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l NUCLIDE l
l l l l l 1..............__......................__............____...................._____ BA-140 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.88E-05 l CO-58 l CURIES l 0.00E+00 l 4.30E-04 l 8.96E-05 l 5.64E-02 l CO-60 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.01E-03 l ,CR-51 l CURIES l 0.00E+00 l 2.51E-04 l 1.28E-05 l 2.49E-02 l CS-138 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.30E-05 l FE-55. l CURIES l 0.00E+00 l 0.00E+00 l 2.13E-03 l 8.20E-03 l FE-59 l CURIES l 0.00E+00 1 0.00E+00 l 0.00E+00 l 3.76E-03 l i
- H-3 l
CURIES l 0.00E+00 l 0.00E+00 l 1.93E-01 l 4.55E+01 l I-131 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 4.72E-04 l I-132 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 2.33E-06 l I-133 l CURIES l 0.00E+00 l 0.00E+00 l 5.39E-06 l 7.90E-04 l I-135 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 4.48E-05 l LA-140 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 8.44E-04 l MN-54 l CURIES l 0.00E+00 l 2.30E-06 l 0.00E+00 l 1.26E-03 l MN-56 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 3.88E-05 l LMO-99 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 5.91E-04 l NA-24 l CURIES l 0.00E+00 l 0.00E+00 l 2.21E-05 l 3.902-03 l NB-95 l CURIES l 0.00E+00 l 0.00E+00 l 7.71E-07 l 1.19E-03 l NP-239 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.12E-06 l RU-103. l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l RU-105 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+0C l 3.45E-06 l TC-99M l CURIES l 0.00E+00 l 0.00E+00 l 5.23E-06 l 7.07E-04 l TE-132 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.49E-06 l W-187 l CURIES l 0.00E+00 l 0.00E+00 l 1.99E-05 l 5.36E-03 l 'XE-131M l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 3.86E-06 l-XE-133 l CURIES l 0.00E+00 l 0.00E+00 l 4.18E-05 l 1.72E-03 l XE-133M l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 2.21E-06 l XE-135 l CURIES l 0.00E+00 l 0.00E+00 l 6.84E-05 l 1.75E-03 l ZN-65 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 2.72E-05 l ZR-95 l CURIES l 0.00E+00 l 0.00E+00 l 9.44E-06 l 2.03E-03 l ZR-97 l CURIES l 0.00E+00 l 0.00E+00 l 8.86E-05 l 1.13E-04 l SR-89 l CURIES l 0.00E+00 l 0.00E+00 l
- 0E0 l
- 0E0 l
SR-90 l CURIES l 0.00E+00 l 0.00E+00 l
- 0E0 l
- 0E0 l
G-ALPHA l CURIES l 0.00E+00 l 0.00E+00 l
- 0E0 l
- 0E0 l
TOTAL FOR PERIOD l CURIES l 0.00E+00 l 6.83E-04 l .96E-01 l 4.56E+01 l CIZ0 roes in this table indicate that no radioactivity was present above d;tectable levels. See Table 1-5 for typical LLD for liquid sample -Cn21yses. 142
p' " " 1 ATTACHE ENT D l-Pare 3 TABLE 1-4A V0GTLE E).ECTRIC GENERATING PLANT SEMIANNUAL RADI6 ACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES March 9, 1987 Through June 30, 1987 UNIT 1 l l-l~ Cumulative Dose Per' Quarter I Organ Tech Units Quarter % of Quarter % of i Spec Tech Tech f Limit. 1 Limit 2 Limit Bone 5.0 mrem 1.45E-05 2.90E-04 1.27E-04 2.54E-03 Liver 5.0 mrem 1.26E-05 2.52E-04 9.41E-04 1.88E-02 T. Body 1.5 mrem 5.05E-06 3.37E-04 8.58E-04 5.72E-02 Thyroid 5.0 mrem 2.88E-06 5.76E-05 1.09E-03 2.18E-02 Kidney 5.0 mrem 2.54E-06 5.08E-05 6.90E-04 1.38E-02 Lung 5.0 mrem 8.08E-06 1.62E-04 7.03E-04 1.41E-02 GI-LLI 5.0 mrem 2.96E-05 5.92E-04 2.30E-02 4.60E-01 Cumulative Dose Per Year Organ Tech Units Year to Date % of Tech Spec Limit Spec Limit Bone 10.0 mrem 1.41E-04 1.41E-03 Liver 10.0 mrem 9.54E-04 9.54E-03 T. Body 3.0 mrem 8.63E-04 2.88E-02 ( Thyroid 10.0 mrem 1.09E-03 1.09E-02 Kidney 10.0 mrom 6.93E-04 6.93E-03 Lung 10.0 mrem 7.11E-04 7.11E-03 GI-LLI 10.0 mrem 2.31E-02 2.31E-01 143' L: -
~ ATTACHZ.ENT H sL Page 4 Tcblo 1-23 [ G;;rgio Pow;r Corp ny Vogtle Electric Generating Plant SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER o ALL LIQUID EFFLUENTS
- UNIT: 1 i
Starting : 1-Jul-1987 Ending : 31-Dec-1987 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR % ...........___...__....__.._____.e_-_____.....,.. 1 A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)
CURIES 2.448E-02 2.912E-01 40 l J 2.' AVERAGE DILUTED CONCENTRATIGN L...DORING PERIOD uCi/ML 6.660E-09 2.444E-07 r
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A B. TRITIUM
- 1. TOTAL RELEASE CURIES 1.185E+02 1.305E+02 40
' 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.224E-05 1.095E-04 3........__.... '3. PERCENT OF APPLICABLE LIMIT N/A N/A i C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 3.122E-03 1.173E-02 50
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 8.494E-10 9.847E-09
- 13. PERCENT OF APPLICABLE LIMIT N/A N/A D. GROSS ALPHA RADIOACTIVITY
'1. TOTAL RELEASE CURIES 0.000S+00 0.000E+00 45 E.' WASTE VOL RELEASED (PRE-DILUTION) LIT 3.338E+06 5.795E+06 15 F.- VOLUME OF DILUTION WATER USED LIT 3.672E+09 1.186E+09 15 l Lo ZOroes in this table indicate that no radioactivity was present above d;tcctable levels. Seo Table 1-5 for typical LLD values for liquid sample on 1yses. 144
e ATTACCZENT H Tcblo 1-30 l REPORT CATEGORY
- SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES
- TOTALS FOR EACH NUCLIDE RELEASED, UNIT 1 i
TYPE CF ACTIVITY
- ALL RADIONUCLIDES i
REPORTING PERIOD
- QUARTER # 3 AND QUARTER $ 4 YEAR 1987 1* CONTINUOUS RELEASES l
- BATCH RELEASES l
l UNIT
- QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l
!$SEb!I5.___......-_____1__....___.1____...1...__.1__.--___.I_______.1 BAv140 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 6.33E-06 l l BE-7 l CURIES l 0.00E+00 l 0.00E+00 l 3.29E-03 l 2.48E-05 l CO-57 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E400 l 1.59E-04 l .CO-58 l CURIES l 0.00E+00 l 9.80E-05 l 1.51E-02 l 2.02E-01 l t CO-60 l CURIES l 0.00E+00 l 0.00E+00 l 3.88E-04 l 3.08E-03 l f lCR-51 l CURIES l 0.00E+00 l 0.00E+00 l 2.68E-03 l 5.67E-02 l fCS-134 l CURIES l 0.00E+00 l 0.00E400 l 0.00E+00 l 3.54E-06 l eFE-55 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.54E-02:l .FE-59 l CURIES l 0.00E+00 [ 0.00E+00 l 6.28E-04 l 5.03E-03 l 'H-3 l CURIES l 0.00E+00 l 0.00E+00 l 1.18E+02 l 1.30E+02 l l HF-181 l CURIES l 0.00E+00 l 0.00E+00 l 3.74E-06 l 3.80E-05 l I-131 l CURIES l 0.00E+00 l 0.00E+00 l 8.02E-05 1 7.78E-07 l I-133 l CURIES l 0.00E+00 l 0.00E+00 l 1.16E-04 l 0.00E+00 l. LA-140 l CURIES l 0.00E+00 l 0.00E+00 l 8.77E-05 l 1.37E-04 l MN-54 l CURIES l 0.00E+00 l 0.00E+00 l 5.76E-04 l 1.96E-03 l NA-24 l CURIES l 0.00E+00 l 0.00E+00 l 7.71E-05 l 2.45E-05 l NB-95. l CURIES l 0.00E+00 [ 0.00E+00 l 4.23E-04 l 2.41E-03 NB-97 l CURIES j 0.00E+00 l 0.00E+00 l 5.12E-07 l 0.00E+00 RU-103 l CURIES l 0.00E+00 l 0.00E+00 l 1.09E-06 1 0.00E+00 l -SB-122 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.80E-05 l - SB-124 l CURIES l 0.00E+00 l 0.00E+00 l 1.76E-04 l 1.14E-03 l TC-99M. l CURIES l 0.00E+00 l 0.00E+00 l 5.15E-05 l 5.92E-05 l l W-187 l CURIES l 0.00E+00 l 0.00E+00 l 3.54E-04 l 0.00E+00 l-1 ' XE-133 l CURIES l 0.00E+00 l 0.00E+00 l 1.41E-03 l 1.13E-02 l .XE-133M l CURIES l 0.00E+00 l 0.00E+00 l 7.94E-06 l 0.00E+00 l XE-135 l CURIES j 0.00E+00 l 0.00E+00 l 1.'iOE-03 l 4.17E-04 l ZN-65 l CURIES l 0.00E+00 l 0.00E+00 l 5.64E-06 l 3.83E-05 l ZR-95 l CURIES l 0.00E+00 l 0.00E+00 l 4.14E-04 l 1.97E-03 l ZR-97 l CURIES l 0.00E+00 l 0.00E+00 l 1.66E-06 l 0.00E+00 l SR-89 l CURIES l 0.00E+00 l 0.00E+00 l
- 0E0 l
- 0E0 l
SR-90 l CURIES l 0.00E+00 l 0.00E+00 l
- 0E0 l
- 0E0 l
G-ALPHA l CURIES l 0.00E+00 l 0.00E+00 l
- 0E0 l
- 0E0 l
t . TOTAL FOR PERIOD l CURIES l 0.00E+00 l 9.80E-05] 1.18E+02 l 1.30E+02 l U~ Zeroes in this table indicate that no radioactivity was present above d;t ctable levels. See Table 1-5 for typical LLD for liquid sample Cn21yses. 145 i
ATTACHMENT O i P4pe 8 TABLE 1-4A j V0GTLE ELECTRIC' GENERATING PLANT l SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DbE TO LIQUID RELEASES July 1, 1987 Through December 31, 1987 UNIT 1 P Cumulative Dose Per Quarter f. Organ Tech Units Quarter % of Quarter % of Spec Tech Tech Limit 3 Limit 4 Limit Bone 5.0 mrem 1.82E-07 3.64E-06 4.64E-04 9.28E-63 liver 5.0 mrem 6.5SE-06 1.31E-04 5.59E-03 1.12E-01 T. Body 1.5 arem 6.31E-06 4.21E-04 5.66E-03 3.78E-01 Thyroid 5.0 mrem 9.14E-06 1.83E-04 4.27E-03 8.54E-02 Kidney 5.0 mrem 5.86E-06 1.17E-04 4.40E-03 8.80E-02 Lung 5.0 mrea 5.81E-06 1.16E-04 4.46E-03 8.92E-02 G1-LLI 5.0 mrem 7.72E-05 1.54E-03 1.04E-01 2.09E+00' Cumulative Dose ~ Per Year Organ Tech Units Year to Date % of Tech Spec Limit Spec Limit Bone 10.0 m*3m 6.19E-04 6.19E-03 Liver -10.0 (Eam 9.13E-03 9.13E-02 .T. Body 3.0 mrem 9.03E-03 3.01E-01 Thyroid 10.0 mrem 7.98E-03 7.98E-02 Kidney 10.0 mrem 7.61E-03 7.61E-02 Lung 10.0 mrem 7.68E-03 7.6EE-02 -GI-LLI 10.0 mrem 1.38E-01 1.38E+00 146
r-- -,reme9 m:ry ~~myrr r. --- ) '3 4 I
- s.
j f f J t 1 1 4 i -( i i f ATTACHMENT C i 4 c .? b r 4 h { e [ r l A.' f h -- - - - ~ ~ ~ ~ ~ ' ' ~ ~ '
ATTACHMENT C Page1 I Tcblo 1-20 Georgia Power Company [ Vogtle Electric Generating Plant j 4 SEMIANNUAL SUMMATION OF ALL RELEApES BY QUARTER ALL LIQUID EFFLUENTS UNIT 1 Starting i 1-Jan-1988 Ending : 30-Jun-1988 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR % A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)
CURIES 7.304E-01 1.155E-01 40
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 9.673E-07 1.460E-07 3.
PERCENT OF APPLICABLE LIMIT N/A N/A l B. TRITIUM al. TOTAL RELEASE CURIES 1.373E+02 1.003E+02 40 2.-AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.818E-04 1.268E-04 '3. PERCENT OF APPLICABLE LIMIT N/A N/A C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 3.765E-03 1.105E-01 50 L2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.986E-09 1.397E-07 3.
PERCENT OF APPLICABLE LIMIT N/A N/A D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 0.000E+00 0.000E+00 45 E. WASTE VOL RELEASED (PRE-DILUTION)
LIT 1.826E+06 1.513E+06 15 F. VOLUME OF DILUTION WATER USED LIT 7.532E+08 7.896E+08 15 'o ZCroes in this table indicate that no radioactivity was present above d;tcetable levels. See-Table 1-5 for typical LLD for liquid sample ennlyses. 147
h' A*ITACHIENT C TABLE 1-30 i REPORT-CATEGORY t SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES
- TOTALS FOR EACH NUCLIDE RELEASED, UNIT 1
- TYPE CF ACTIVITY
- ALL RADIONUCLIDES i REPORTING PERl'OD QUARTER $ 1 AND QUARTER $ 2 YEAR 1988 l* CONTINUOUS RELEASES l
- BATCH RELEASES l
t UNIT tQUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l NUCLIDE l l l l l l
- BE-7 l
CURIES l 0.00E+00 l 0.00E+00 l 2.39E-04 l 2.76E-05 l ! CO-57 l CURIES l 0.00E+00 l 0.00E+00 l 1.06E-03 l 1.89E-04 l i CO-58 l CURIES l 0.00E+00 l 0.00E+00 l 4.69E-01 l 6.91E-02 l LCO-60 l CURIES l 0.00E+00 1 0.00E+00 l 1.84E-02 l 6.59E-03 l .CR-51_ l CURIES l 0.00E+00 l 0.00E+00 l 1.23F Q1 l 1.29E-02 l FE-55 l CURIES l 0.00E+00 1 0.00E+00 l 5.32L-02 l 8.26E-03 { FE-59 l CURIES l 0.00E+00 l 0.00E+00 l 1.03E-02 l 1.82E-03 l H-3 l CURIES l 0.00E+00 l 0.00E+00 l 1.37E+02 l 1.00E+02 l . HF-181' l CURIES l 0.00E+00 l 0.00E+00 l 6,12E-04 l 9.77E-05 l 'I-131 l CURIES l 0. 0 0E4-0 0 l 0.00E+00 l 1.17E-05 l 3.25E-04 l I-133 l CURIES l 0.00E+00 l 0.00E+00 l 6.04E-06 l 4.65E-04 l I-135 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 6.34E-05 l KR-85M l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 5.90E-06 l KR-88 l CURIES l 0.00E+00 l 0.00E+00 l 6.60E-05 l 0.00E+00 l .LA-140 l CURIES l 0.00E+00 l 0.00E+00 l 3.22E-04 l 3.32E-05 l ,MN-54 l CURIES l 0.00E+00 l 0.00E+00 l 1.42E-02 l 5.69E-03 l 'MO-99 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 6.15E-05 l ~NA-24 l CURIES l 0.00E+00 l 0.00E+00 l 6.28E-04 l 1.01E-04 l NB-95 l CURIES l 0.00E+00 l 0.00E+00 l 1.29E-02 l 4.18E-03 l NB-97 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.01E-05 l !NI-65 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l
- 1. 59E l
[RU-103 l CURIES l 0.00E+00 l 0.00E+00 l 1.86E-05 l 0.00E+00 l FRU-105 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 2.32E-05 l lSB-124 l CURIES l 0.00E+00 l 0.00E+00 l 1.18E-02 l 1.46E-03 l 'SB-125 l CURIES l 0.00E+00 1 0.00E+00 l 4.27E-03 l 8.65E-04 l TC-99M l CURIES l 0.00E+00 l 0.00E+00 l 5.9??-06 l 3.22E-04 l W-187 l CURIES l 0.00E+00 l 0.00E+00 [ 0.00B+00 l 2.00E-06 l XE-131M l CURIES l 0.00E+00 l 0.00E+00 l 2.90E-04 l 6.00E-05 l XE-133 l CURIES l 0.00E+00 l 0.00E+00 l 3.26E-03 l 1.07F-01 l .XE-133M l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 7.7#Ta04 ! gXE-135 l CURIES l 0.00E+00 l 0.00E+00 l 1.48E-04 l 2: 2-03 l "XE-135M l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 5.41E-07 l
- ZN-65 l
CURIES l 0.00E+00 l 0.00E+00 l 6.08E-04 l 1.80E-04 l ZR-95 l CURIES l 0.00E+00 l 0.00E+00 l 8.86E-03 l 2.52E-01 l
- ZR-97 l
CURIES l 0.00E+00 l 0.00E+00 l 3.07E-06 l 2.39E-06 l JSR-89 l CURIES l 0.00E+00 [ 0.00E+00 l
- 0E+00 l
- 0E+00 l
SR-90 l CURIES l 0.00E+00 l 0.00E+00 l
- 0E+00 l
- 0E+00 l
G-ALPHA-l CURIES l 0.00E+00 l 0.00E+00 l
- 0E+00 l
- 0E+00 l
-TOTAL'FOR PERIOD l CURIES l 0.00E+00 l 0.00E+00 l 1.38E+02 l 1.00E+02 ...________________________.-__...l o Zoroes in this table indicate that no radioactivity was present above dotOctable levels. See Table 1-5 fot typical LLD for liquid sample entlyses. 148 lL-
ATTACHMENT C [ Page 3 1 TABLE 1-4a V0GTLE ELECTRIC GENERATING PLANT i. SEMIANNUAL aADI0 ACTIVE EFFLUENT RELEASE REFORT [ INDIVIDUAL DOSES DUE TO LIQUID RELEASES January 1, 1988 Through June 30, 1988 UNIT 1 L Cumulative Dose Per Quarter Organ Tech Units Q ua 'c t e r % of Quarter 4 af Spec Tech Tech Limit 1 Limit 2 Limit Bone 5.0 mrem 8.55E-04 1.71E-02 2.18E-04 4.36E-03 Liver 5.0 mrem 2.45E-03 4.90E-02 3.37E-03 4.74E-02 T. Body 1.5 mrem 3.19E-03 2.13E-01 2.99E-03 1.99E-01 Thyroid-5.0 mrem 1.70E-03 3.40E-02 3.07.E-03 6.04E-02 Kidney 5.0 mrem 2.16E-03 4.32E-02 2.75E-03 5.50E-02 Lung 5.0 mrem 1.39E-03 2.78E-02 2.40E-03 4.80E-02 GI-LLI .5. 0 mrem 2.53E-01 5.06E+00 1.19E-01 2.38E+00 l I Cumulative Dose Per Year Organ Tech Units Year to Date % of Tech Lpec Limit Spec Limit-Bone 10.0 mrem 1.07E-03 1.07E-02 Liver 10.0~ mrem 5.82E-03 5.82E-02 T. Body 3.0 mrem 6.18E-03 2.06E-01 Thyroid 10.0 mrem 4.72E-03 4.72E-02 Kidney. 10.0 mrem 4.91E-03 4.91E-02 Lung 10.0 mrem 3.79E-03 3.79E-02 GI-LLI 10.0 mren 3.72E-01 3.72E+00 3. ) 149 ~
L ATTACHMENT C r Page 4 TCblo 1-20 Georgia Power Company Vogtle Electric Generating Plant SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL LIQUID EFFLUENTS
- UNIT: 1 Starting :
1-Jul-1988 Ending : 31-Dec-1988 r ' TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. ' ROT ERROR % A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)
CURIES 5.630E-02 6.138E-01 40
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 6.113E-08 9.264E-07
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A B. TRITIUM
? ,1. TOTAL RELEASE CURIES 7.311E+01 4.876E+01 40 l
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.938E-05 7.359E-05
,3. PERCENT OF APPLICABLE LIMIT N/A N/A 'C.. DISSOLVED AND ENTRAINED GASES .1. TOTAL RELEASE CURIES 2.201E-01 4.842E-01 50
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.390E-07 7.307E-07 l
e ........__m. 3. PERCENT OF APPLICABLE LIMIT N/A N/A ! D. GROSS ALPHA RADIOACTIVITY ~" 55 TObkL kbLbkbb "" ~" ~~' " "~~ ~ChkkbS bIbbbb+bb bIbbbb+bb 45 ~ ~ l /_.............____.________..._-__________...________....._______....._________. c LE.. WASTE VOL RELEASED (PRE-DILUTION) LIT 2.402E+06 2.096E+06 15 1 !, P. VCLUME OF DILUTION WATER USED LIT 9.186E+08 6.605E+08 15 [0 Z3 roes in this table indicate that no radioactivity was present above I l datGctable levels. See Table 1-5 for typical LLD for liquid sample -cnalyses. i 150
m ATTACHMENT C I TABLE 1-30 rREPORT CATEGORY
- SEMIANNUAL-LIQUID CONTINUOUS AND BATCH RELEASES
- TOTALS FOR - EACH NUCLIDE RELEASED, UNIT 1 F TYPE CF ACTIVITY
- ALL RADIONUCLIDES i
, REPORTING PERIOD
- CUARTER f 3 AND QUARTER # 4 YE*.R 1988 L
l* CONTINUOUS RELTASES l
- BATCH RELEASES l
NUCLIDE l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l BA-139 l CURIES l 0.00E+00 l 0.00E+00 l 7.04E-06 l 2.59E-05 l ,BE-7 l CURIES l 0.00E+00 l 0.00E+00 l 1.46E-05 l 5.05E-04 l CO-57 l CURIES l 0.00E+00 l 0.00E+00 l 5.46E-05 l 7.59E-04 l LCO-58 l CURIES l 0.00E+00 l 0.00E+00 l 2.36E-02 l 3.04E-01 l CO-60 l CURIES l 0.00E+00 l 0.00E+00 l 3.71E-03 l 1.86E-02 l ' CR-51 l CURIES l 0.00E+00 1 0.00E+00 l 5.87E-03 l 9.66E-02 l' 'CS-137 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.44E-04 l .FE-55 l CURIES l 0.00E+00 l 0.00E+00 l 6.61E-03 l 1.12E-01 l FE-59' l CURIES l 0.00E+00 l 0.00E+00 l 4.67E-04 l 1.66E-02 l t H-3 l CURIES l 0.00E+00 l 0.00E+00 l 7.31E+01 l 4.87E+01 l l HF-181 l CURIES l 0.00E+00 l 0.00E+00 l 2.01E-05 8.68E-04 l i I-131 l CURIES l 0.00E+00 l 0.00E+00 l 1.75E-03 4.44E-04 l .I-132 l CURIES l 0.00E+00 l 0.00E+00 l 1.74E-04 l 0.00E+00 l I-133 l CURIES l 0.00E+00 l 0.00E+00 l 3.60E-03 l 2.98E-04 l i I-135 l CURIES l 0.00E+00 l 0.00E+00 l 1.21E-03 l 0.00E+00 l KR-85M l CURIES l 0.00E+00 l 0.00E+00 l 1.55E-06 l 4.59E-06 l -KR l CURIE 3 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 2.69E-04 l t LA-140 l CURIES l 0.00E+00 ! 0.00E+00 l 4.52E-05 l 1.40E-04 l -MN-54 l CURIES l 0.00E+00 6 0.00E+00 l 2.75E-03 l 2.06E-02 l MO-99 l CURIES l 0.00E+00 1 0.00E+00 l 8.82E-04 l 0.00E+00 l NA-24 l CURIES l 0.00E+00 l 0.00E+00 l 4.82E-04 l 2.41E-03 l -NB-95 l CURIES l 0.00E+00 l 0.00E+00 l 1.12E-03 l 1.01E-02 l 'NB-97 l CURIES l 0.00E+00 l 0.00E+00 l 2.32E-09 l 0.00E+00 l PR-144 l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.53E-03 l RB-86 l CURIES l 0.00E+00 l 0.00E+00 l 2.11E-05 l 0.00E+00 l .RU-103 l CURIES l 0.00E+00 l'O.00E+00 l-0.00E+00 l 1.21E-05 l RU-105' l CURIES l 0.00E+00 l 0.00E+00 l 1.10E-05 l 0.00E+00 l t 'SB-122 l CURIES l 0.00E+00 1 0.00E+00 l 1.17E-09 l 1.09E-03 l SB-124-l CURIES l 0.00E+00,l 0.00E+00 l 5.75E-06 l 7.20E-03 l SB-125 l CURIES l 0.00E+00 l 0.00E+00 l 8.17E-05 l 8.83E-03 l TC-99M l CURIES l 0.00E+00 l 0.00E+00 l 7.27E-04 l 8.21E-05 l TE-129M l CURIES l 0.00E+00 l'O.00E+00 l 0.00E+00 l 2.70E-03 l .TE-133 l CURIES l 0.00E+00-l 0.00E+00 l 0.00E+00 l 4.23E-05 l w-187 l-CURIES l 0.00E+00 l 0.00E+00 l 2.38E-03 l 0.00E+00 l XE-131M l CURIES l 0.00E+00 l 0.00E+00 J 1.69E-03.l 5.90E-03 l XE-133 l CURIES l 0.00E+00 l 0.00E+00 l 2.06E-01 j.4.71E-01 l l XE-133M l CURIES l 0.00E+00 l 0.00E+00 l 1.27E-03 l 3.57E-03 ! i.XE-135 l CURIES l 0.00E+00 l 0.00E+00 l 9.84E-03 l 2.93E-03 l XE-135M l CURIES l 0.00E+00 l 0.00E+00 l 9.52E-04 l 0.00E+00 l ,ZN-65 l CURIES l' O.00E+00 l 0.00E+00 l 2.55E-05 l 4.60E-04 l ?ZR-95 l CURIES l 0.00E+00 l 0.00E+00 1 5.80E-04 l 6.18E-03 l lZR-97 l CURIES l 0.00E+00 l 0.00E+00 l 4.59E-06 l 4.16E-06 l lSR-89 l CURIES l 0.00E+00 l 0.00E+00 l
- 0E+00 l
- 0E+00 l
SR-90 l CURIES l 0.00E+00 l 0.00E+00 l
- 0E+00 l
- 0E+00 l
G-ALPHA l CURIES l 0.00E+00 l 0.00E+00 l
- 0E+00 l
- 0E+00 l
. TOTAL FOR PERIOD l CURIES l 0.00E+00 l 0.00E+00 l 7.33E+01 l 4.98E+01 l cZ ross in this table indicate that no radioactivity was present above i; ~d;tcctabla levels. See Table 1-5 for typical LLD for liquid sample analyses. l 151 1
ATTACHMENT C Page 6 4 i TABLE 1-4a .l t t V0GTLE ELECTRIC GENERATING PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT { INDIVIDUAL DOSES DUE TO LIQUID RELEASES July 1, 1988 Through December 31, 1988 UNIT 1 [.. Cumulative Dose Per Quarter Organ Tech Units Quarter % of Quarter % of. Spec Tech Tech Limit 3 Limit 4 Limit j h i Bone 5.0 arem 1.31E-04 2.62E-03 4.93E-03 9.86E-02 i Liver 5.0 arem 2.24E-03 4.48E-02 9.73E-03 1.95E-Od T. Body 1.5 mrea 2.49E-03 1.66E-01 6.19E-03 4.1 ?s*61 Thyroid 5.0 mrem 5.91E-03 1.18E-01 2.78E-03 5.56E-02 Kidney
- 5. 0 -
mrem 2.34E-03 4.68E-02 6.52E-03 1.30E-01 Lung 5.0-arem 2.22E-03 4.44E-02 1.16E-02 2.32E-01 G1-LLI 5.0 arem 5.11E-02 1.02E-01 5.84E-02 1.17E+00 [ L l l p l-P Cumulative Dose Per Year Organ Tech Units Year to.Date % of Tech Spec Limit I;. . Spec Limit Bone 10.0 mrem 5.06E-03 5.06E-02 Liver 10.0 mrem 1.78E-02 1.78E-01 l T. Body 3.0 arem 1.48E-02 4.93E Thyroid 10.0 mrem 1.34E-02 1.34E-01 Kidney 10.0 mrem 1.38E-02 1.38E-01 ~' . Lung 10.0 mrem 1.76E-02 1.76E-01 - GI-LLI 10.0 mrem 4.82E-01 4.82E+00 ( L L. I 152 L ~, -}}